U, S. NUCLEAR REGULATORY COMMXSSXON
OFFICE OF INSPECTXON AND ENFORCEMENT
5t)-528/78-0550-529/78-04
Report No.
REGION V
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Licensee: Arizona Public Service Com any
Safeguards Group
P. 0. Box 21666
Phoenix, Arizona 85036
Faci1 ity Name Pal o Verde Uni ts 1 . 2 and 3
Xnspection at: Palo Verde Site Marico a Count Arizona
Xnspection conducted: J -2 1978
Inspectors;L. J. Garvi , Rea tor Inspector Date%igned
".",>proved By:
Summary:
. Vorder rueg en, Reactor Inspector~
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T. H. Bishop, React r Inspector
G. S. Spencer, hief, Reactor Construction andEngineering Support Branch
Date 'gned
Date Signed
Date Signed
Ins ection on Jul 14-21, 1978 Re ort No. 50-528/78-05, 50-529/78-0450-530/78-04
d: R f, d f p f factivities including: Follow-up items, tour, audits, nonconformingreports, containment welding, tendon sheath installation, drawingcontrol and pipe welding. The inspection involved 90 inspector-hoursonsite by three NRC inspectors.
Results: Four items of noncompliance were identified in the area oftendon sheath installation and inspection. Ho items of noncompliance ordeviations were identified in the other areas inspected.
~89.03g o 3(fRV Form 219 (2)
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DETAILS
Persons Contacted
*E*J*W*R.*B*W
D.G.
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E. Van Brunt, Jr., Vice President/Project DirectorA. Roedel, quality Assurance ManagerM. Petro, ANPP Construction ManagerL. Robb, Assistant Project DirectorS. Kaplan, guality Systems SupervisorE. Ide, guality Systems EngineerD. Webster, guality Assurance EngineerPankonin,,guality Assurance EngineerD. Forrester, guality Assurance Engineer
Bechtel Power Cor oration
W. G. Bingham, Project Engineering NanagerJ. A. Packard, Field Construction Manager
*S. N. Nickell, Project Superintendent*A. K. Priest, Project Field Engineer
S. R. Abraham, Resident Engineer*J. E. Braun, guality Assurance Engineer*C. F. Gaither, Field Project Engineer
J. R. Beers, Lead Civil EngineerN. McCormick, Assistant Project Field Engineer
~H. P, Smith, Project Field g.C. Engineer*L. Afek, Lead Mechanical EngineerG. Pattan, Auxiliary Building Area EngineerR. Rubick, Containment Area EngineerR. Maturani, Field Weld EngineerN. Yaldo, Group Leader Welding EngineerL. B. Mayville, Assistant Welding SuperintendentR. NcConkey, Lead Field Welding EngineerL. Blackburn, guality AssuranceL. Wikie, guality Assurance EngineerM. Creager, Civil Engineer (Containment)E. Kovacevich, Field Engineer - Codes and StandardsG. Beaugrand, Field Engineer - Codes and StandardsR. Randels, Construction Liaison EngineerG. Engels, Field Engineer - PipingG. Patton, Lead Field Engineer - MechanicalY. Ducket, Lead Field Engineer - Hechanical
Western Concrete
C. Spievak, gC Inspector
*Denotes those present at the exit interview.
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2. Licensee Action on Previous Ins ection Findin s
a ~ (Open) Noncompliance (50-528/78-03): A Marathon drawingchange notice was not distributed to or used at the locationwhere the work was being performed.
Although the licensee's written response to the Notice ofViolation had not been received as of the current inspection,preliminary constructor's action had been completed, and wasexamined. As corrective action, the constructor had revisedMPP/QCI 3.0, "field Control of Design Documents," to allowarea engineers(AEs) to determine where, and to whom, individualdocument changes are to be issued. This action creates someconcerns in that incomplete, and out-of-date, drawings are nowallowed to be in the field. A sampling of 25 drawings in usein the field revealed seven which did not include the latestchanges. It is also noted that the AE is not required todocument the issuance of individual changes so that it is notpossible to effectively audit the revised document controlprogram. The above concerns were acknowledged by licenseerepresentatives. This item will be further examined uponreceipt of the licensee's written response to the Notice ofViolation.
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(Closed) Open Item (50-528/78-03): Non-rotating equipment instorage did not have procedures defining storage requirements.The procedure has been developed and observed equipmentappeared to be stored acceptably.
(Closed) Open Item (50-528/78-03): An inspection manual hasbeen prepared to organize the pipe welding inspection procedures.
(Closed) Open Item (50-528/78-03): Pipe welding QC inspectorshave received training in the procedures contained in the pipewelding inspection manual.
(Open) Open Item (50-529/78-02): The Unit 2 reactor vesselwas dropped at the manufacturer's shop while being movedbetween work stations. Volumetric examination of welds willbe performed to assure that no hidden damage resulted.
(Closed) Open Item (50-528/78-03): A provision allowinginprocess inspection documentation has been incorporated intoQCI 2.4.
(Closed) Open Item (50-528, 529, 530/78-01): Rejection ofmajor component hold-down bolts.
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NRC CC713 was initiated to evaluate the subject of the improperinstallation of several of'he hold-down bolts. The bolts
.were accepted-as-is (due to sufficient strength). The NCR
will remain open to assure that proper attention is given thetensioning of the bolts.
(Open) Open Item (50-528/78-04): Existing procedures fortranslating engineering directions noted on SDDR's to con-struction or gC forces are inadequate. Procedures were beingrevised to incorporate provisions to assure that the constructionforces were informed.
(Open) Open Item (50-528/78-03): Seismic qualification ofUni-Strut electrical tray supports. This item was not inspected.
(Open) Open Item (50-528/78-04): Codes and standards used inthe construction of the containment lines.
Discussions were held with the licensee regarding the con-struction codes and standards used in containment lines erection.The licensee was still developing a list to be submitted tothe Region Y office.
k. (Closed) Open Item (50-528/78-04): Containment welder records.Records of containment liner welder identity were not sufficientin all cases to identify the exact areas welded by each welder."As-built Welding Control System" Procedure NPP/gCI 101.4 wasdeveloped to correct this problem.
1. (Closed) Open Item (50-528/78-04)': Radiographic examination.. of containment liner welds. The licensee stated that the PSAR
reference to regulatory guide would continue to be in force.
3. Construction Status
The licensee reported that Unit 1 was 26.8%%d, Unit 2 was 6.3!, andUnit 3 was 0.5/ complete as of July 1, 1978. The overall projectwas reported to be 12.3X complete.
4. ~Fili T
Equipment storage, housekeeping, concrete curing, reinforcing steelplacement, backfilling, pipe welds, equipment installation andcable tray installation were observed.
Several large nuts were noted laying in the dirt without threadprotection near primary coolant pump hold-down bolts in Unit l.Before the end of the inspection, the threads had been protectedand the nuts were attached to the pump hold-down bolts.
No other items of concern were noted.
5. Containment Liner i/eldin
ilelding on the first ring of Unit 2 containment liner was visuallyexamined. Also examined were horizontal and vertical seams onrings 9, 10 and 11, uni-strut welded to liner, crane rail supportattachments and welding on penetr ations in the containment ofUnit l.The welder identity mar kings on Unit 2 seemed to be sufficient totrace the welder qualification and testing records. On the upperrings of the Unit 1 containment, the welder identity markings hadimproved so that identity was easily traced (Ref. Report 50-528/78-04). For the most part, the welding that was visually examinedappeared to meet requirements. The areas that did not meet require-ments had not been inspected by the quality control inspectors.
Radiographs of approximately ten feet of liner plate welds wereexamined. No anomalies were noted during the examination.
6. Containment Prestressin S stem
a 0 Review of ualit Im lementin Procedures
Installation Specification No. 13-CH-37, Rev. 2, and blork PlanProcedure/guality Control Instruction Ho. 66, Rev.2, for thepost-tensioning trumplate assemblies and sheathing were ex-amined with the following items noted.
(1) The Construction Inspection Planning (CIP) sheets attachedto HPP/gCI 66 do not clearly reference each of designatedinspection hold points listed in the procedure. The .
CIP s are used to document 'required inspection activities.
(2) Inspection descriptions in the CIP are misleading, forexample, one description reads "Replace plastic plugswith thread protectors," whereas the referenced procedureparagraph (3.1.1 of Exhibit 660-5) deals with the posi-tioning of trumplates, deformations, installation ofmounting bolts, tightners to forms, and rust.
(3) Designated inspections are not listed on the CIP. Forexample, the inspection of vents and drains (Paragraph3.1.5 of Exhibit 66.0-5) is not listed on the CIP.
(4) The CIP calls for inspections which are not required andcannot be readily performed. For example Item 9.1 ofExhibit 66.0-6 calls for post concrete placement inspectionof sheathing positioning, alignment and installation,
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referencing Paragraph 3.1.4 of Exhibit 66.0-5. Para-graph 3.1.4 calls for pre-concrete placement inspectionof sheathing position and alignment, wire tie-offs, andtaping of sheathing couplers. These inspections cannotbe readily performed after concrete placement.
b. Observations of Work and Work Activities
Unit 1 trumplate, trumplate extension, and sheathing instal.=lation activities were observed. The installation was inpreparation of concrete placement No. 1C109. The activitiesinspected included sheathing positioning and alignment, wiretie-off, coupler taping, vent line installations, sheathingcondition, and inspection coverage. The observations wereconducted on July 18, 19, and 20, 1978. tetany items of in-complete work were observed on July 18 and 19. .The concretejump forms had only been positioned on a portion of thecontainment at that time. The inspector was advised byconstructor representatives that most of the incomplete itemswould be completed prior to final form positioning. However,on July 20, 1978,„after form positioning was completed, numerousitems of incomplete work were found to be still in existance.In addition, several items contrary to the requirements ofspecifications, procedures, and drawings were observed. Theseincluded:
(1) Vertical and horizontal sheaths in each of the buttresseswere tied at intervals greater that the maximum intervalof 3'6" specified in WPP/gCI 66.0. It was noted thataction had been taken to correctly tie the sheathingtoward the top of the forms, but sheathing at the bottomwas found to be untied for distances up to eight feet.Numerous other improperly tied vertical and horizontalsheaths were identified to licensee and constructorrepresentatives.
(2) Six trumplate extensions were found to be unwired attheir ends contrary to the requirements of WPP/gCI 66.0.
(3) Fittings, which appeared to be non-galvanized, wereinstalled in the vent lines Nos. H21-023, and H21-025.WPP/gCI 66.0 specifies the use of galvanized fittings.The fittings in question were subsequently removed andreplaced. with galvanized fittings.
(4) Two vertical sheathings (the 17th and 19th clockwise fromthe center of the equipment hatch) were found to befirmly wired in position, yet out of alignment by twoinches in ten feet,.whereas Drawing 13-C-ZCS-175, Rev. 2DCN 1 specifies a maximum misalignment of 3/4" within tenfeet.
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(5) A hole was found in the lowest visible horizontal sheathat a location approximately ten feet to the left ofbuttress No. 3. This hole was reportedly repaired, butupon observation by the inspector was found to be un-repaired. The hole was subsequently repaired.
(6) Horizontal sheaths above the equipment hatch were found tobe firmly wired in position, yet they were within l-l/2"of each other, whereas Drawing 13-C-ZCS-175, Rev. 2,DCN 1 specifies a minimum clearance of three inches inthis area.
(7) Yertical tendon sheath No. Y-79 was found to have anabrupt change in alignment of approximately three inches.This sheath was installed in conjunction with the previousconcrete lift (No. 1C108) on July 7, 1978. Tolerances ineffect at that time limited misalignment to + 3/4 inch.This tolerance was subsequently changed to + 3 inches,but with no abrupt changes.
Discussions with cognizant guality Control and FieldEngineers on July 19, 1978 revealed that mandatory in-spection hold points were not executed as required byWPP/gCI 66.0. Rev. 2. Specifically, the engineers statedthat the hold points for drilling of vent holes, instal-lation of vent piping, wiring of sheathing, and positioningof sheathing were inspected on a random basis only. Itwas also reported that no inprocess records of the randominspections were generated. Accordingly, it is notpossible to identify which items were inspected, even onthe random basis. It was noted also, that WPP/gCI 66.0specifies that inspections for position, alignment,vents, and tie wiring are to be conducted prior to placementof the concrete forms. Contrary to this requirement, theforms were positioned in place on July 20, 1978 prior tocompletion.
Review of ualit Records
As of noon, July 20, 1978, no quality records had been generatedfor the sheathing installation associated with Unit 1 containmentwall placement No. 1C109, despite the fact that the placementwas planned for the night of July 20, 1978. As noted inParagraph 6.b, guality Control Engineers had not documentedtheir inprocess inspections or hold point inspections performedon the sheathing installation. The lack of inprocess inspectionrecords, and documentation of those inspection hold pointsthat were inspected, is contrary to the requirements of 10 CFR
50, Appendix B, Criterion XYII and the PSAR Section 17 whichrequire inspection records.
The Construction Inspection Plan (CIP) addressing sheathinginstallation for the previous concrete placement (No. 1C108),was examined. It was noted that both Survey and Field Engineeringhad signed-off the CIP indicating correct sheathing (tie-wiring, taping, etc) was verified after concrete placement.It is not clear how such an inspection could have been performed.It was further noted that no Nonconformance Report had been .
issued for the abrupt change in alignment existing in verticalsheath V-79. The failure to properly document the nonconformingcondition to prevent its inadvertent use is contrary to therequirements of 10 CFR 50, Appendix B, Criterion XV and thePSAR Section 17.
7. Safet Related Pi in
During a tour of the auxiliary building, several installed pipingsections were seen to have shrinkage distortions that appeared tobe associated with welds joining individual shop-furnished spools.One of particular interest was associated with a 20-inch LPSIsystem spool No. 1-SI-194-S-105 at the 40-foot elevation in theauxiliary building. Two other spools in the outdoor storage yardwhich appeared to have similar weld strinkage conditions were alsoexamined. These were 24-inch, schedule 30, 0.562-inch wall thicknessspool No. 1-SI-307-S-005, and 20-inch schedule 20, 0.375-inch
wall'hicknessspool No. 1-CH-142-S-Oll. Upon further investigation, itwas learned that this weld shrinkage condition had been an item ofconcern to Bechtel and NCR No. PA-126 wa's issued on December 14,1977 to investigate the situation. Bechtel performed an engineeringanalysis of the distortion configuration to determine its effect onflow characteristics and joint stresses, and destructively analyzedtypical specimens for metallurgical attributes. In addition,personnel from Bechtel, Combustion Engineering and Nuclear EngineeringServices met with the supplier, Pullman Power Products, to discussthe matter and resolve any issues associated with surface preparationto properly provide for in-service inspection.
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According to Bechtel personnel, the shrinkage distortion phenomenonis associated only with large diameter, thin wall stainless steelpipe and is caused by the application of weld overlay to the outsidesurface of the spool piece and, when necessary, the weld overlayprocess is the approved method for satisfying specification re-quirements pertaining to I.D. and wall thickness dimensions subsequent .
to the weld prep counterbore operation. Bechtel concluded fromtheir analyses that flow characteristic and stress level effectswere well within design margins, that the shrinkage distortion didnot impair the performance of ISI and radiographic examination, andthat the distortion was metallurgically acceptable. The inspectoragreed that ASNE code requirements were not compromised, and'nformedthe licensee that the subject was considered closed.
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8. Safet Related Structures
The inspector examined the foundations for the Train A safetyinjection pumps and the records associated with the insta1lation.Concrete placement 1A05 served the HPSI pump and placement 1A06 wasfor the LPSI pump. The records included the Construction InspectionPlans (CIP's) for concrete preplacement, placement, and post-placement, concrete delivery tickets, and cylinder break strengthtest reports. No anomalies were noted.
9. Exit Interview
At the conclusion of the inspection, a meeting was held with thelicensee and contractor representatives denoted in Paragraph l.The areas covered dur ing the inspection, and the observations andconclusions of the inspectors were reviewed. The inspectors ex-pressed strong concern in regard to quality systems that allowedthe tendon sheath installation to deteriorate to the level found bythe inspectors. The inspectors also expressed concern that theBechtel and APS guality Assurance site groups had not taken actionon July 19 or 20th when it was apparent that extreme correctiveaction was necessary.
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UNITED STATES
NUCLEAR REGULATORY COMMISSION
REGION V
SUITE 202, WALNUT CREEK PLAZA1990 N, CALIFORNIA BOULEVARD
WALNUT CREEK, CALIFORNIA 94996
Docket No. 50-530 Oy 7 19Q
Arizona Public Service CompanyP. 0. Box 21666Phoenix, Arizona 85036
Attention: Nr. E. E. Van Brunt, Jr.Vice President, Construction Projects and ANPP Director
Gentlemen:
Subject: Inspection of Palo Verde Unit 3
This refers to the inspection conducted by Hr. North of this office onOctober 11-12, 1977 of activities authorized by NRC Construction PermitNo. CPPR-143, and to the discussion of our findings held by Hr. Northwith you and other members of your s'taff at the conclusion of theinspection.
=Areas examined during this inspection are described in the enclosedinspection report. llithin these areas, the inspection consisted ofselective examinations of procedures and representative records, inter-views with personnel, and observations by the inspector.
No items of noncompliance with NRC requirements were identified withinthe scope of this inspection.
In accordance with Section 2.790 of the NRC's "Rules of Practice,"Part 2, Title 10, Code of Federal Regulations, a copy of this letter andthe enclosed inspection report will be placed in the NRC's PublicDocument Room. If this report contains any information that you believeto be proprietary, it is necessary- that you submit a written applicationto this office, within 20 days of the date of this letter, requestingthat, such information be withheld from public disclosure. The applica-tion must include a full statement of the reasons why it is claimed thatthe information is proprietary. The application should be prepared sothat any proprietary information identified is contained in an enclosureto the application, since the application without the enclosure will
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Arizona Public Service Company -2- goy 7 19'l7
also be placed in the Public Document Room. If we do not hear from youin this regard within the specified period, the report will be placed inthe Public Document Room.
Should you have any questions concerning this inspection, we will beglad to discuss them with you.
Sincerely,
. cf.
H. E. Book, ChiefFuel Facility and Materials
Safety Branch
Enclosure:IE Inspection Report
No. 50-530/77-05
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. iU. S. NUCLEAR REGULATORY COMMISSION
OFFICE OF INSPECTION AND ENFORCEMENT
REGION V
Report No. 50-530/77-05
Docket No. 50-530 License No. CPPR-143 Safeguards Group
Licensee: Arizona Public Service Com an
P. 0. Box 21666
Phoenix, Arizona 85036
Facility Name: Palo Verde Uni.t 3
Inspection at: Buckeye, Arizona
Inspection conducted; October 11-12, 1977/
Inspectors: 7>cVC"'rt
, a sation Specialistw7 7
Date ign d
Date Signed
Approved by:
Summary:
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oo , le , ue ac> sty an atersa sSafety
Branch'ateSigned
/o 9( 77Date Signed
Ins ection on October 11-12, 1977 Re ort No. 77-05Areas Ins ected: Environmental protection during construction includingstatus o complementation of each construction permit requirement;implementation of all applicable construction permit requirements andverification of existence of implementing procedures at the workinglevel. The inspection involved 13 inspector-hours on site (total forUnits 1, 2, and 3) by one NRC inspector.
Results: No items of noncompliance or deviations were identified.
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IE:V Form 219 (2)
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DETAILS
Persons Contacted
-Arizona Public Service Com an
2.
*E. E. Van Brunt, Jr., Vice President Construction Projectsand ANPP Director
*R. Robb, Manager, Nuclear Services*M. Pietro, Manger, Site Construction~J. Roedel, Manager, quality Assurance~J. Mann, Senior Health Physicist
D. Karner, Licensing Engineer Units 4 and 5R. Hand, Supervisor, Sste guality AssuranceC. Young, Environmental Scientist
'N. Millsey, Mechanical EngineerL. Icard, Instrument Control Technician
Bechtel Cor oration
J. Dyer, Site Advisor General Environment (SAGE)T. Cheville, Assistant Field EngineerC. Betzhold, Supervisor, guality Assurance
*Denotes those present at the exit interview.
Audits
The inspector questioned applicant and Bechtel personnel concerningaudits of environmental program related activi,ties performed sincethe last environmental program inspection (Inspection Report 50-528, 529, 530l76-02, September 8-10, 1976). A total of four audits
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been performed. The inspector examined all audit reports, Theaudits performed included one by the applicant's gA staff, two bythe Bechtel onsite gA staff and one of the applicant's samplecollection technique by Controls for Environmental Pollution (CEP),a contractor for the applicant. The audits identified two items of
~ an administrative nature for which corrective action was required.Appropriate cor rective action, verified by subsequent audits, hadbeen completed at the time of inspection. Audits and correctiveactions were appropriately documented.
No items of noncompliance were identified.
3. Im lementation of Construction Permit Re uirement E 1
The inspector discussed and examined documents describing the.implementation of sections 4. 5. 1 and 4.5.2 of the Final Environ-mental Statement (FES). The documents examined included Mon~thlSummar -Environmental Activit Re orts number 007, July 30 ~976to number 020, August 26, 1977 and weekly Environmental ControlPro ram-Environmental Archiolo ical Protection Re orts up to and
'including the report dated September 30, 1977. During an onsitetour . the inspector observed the applicant's actions with respectto the following FES requirements:
FES Section 4.5.1;
Item 2; No organic materials from the plant site were inevidence.
Item 5. No unnecessary grading was observed.
Item 7. Drainage has been provided to direct onsite runnoffto the south and east toward the East Wash drainageline. Onsite drainage is direct to a "J" hook im-poundment basin at the. south end of the East Washdiversion embankment. The East Wash diversion em-bankment has been completed and riprap placed alongits entire length. Rain at the site shortly beforethe inspection established that onsite drainage wasto the sout6 and east and was contained by the "J"hook basin.
Item 8.. Water trucks were in evidence and little dust wasnoted. Chemicals have not been used for dust control.
Item 10.
Item 12.
Item 13.
Item 14.
It was observed that spoil area slopes were gradedto meet existing contours.
An air curtain incinerator has been installed andis operating under a county permit. The residue isbeing buried. The inspector noted that the con-struction site was clean and orderly and free ofconstruction trash and blowing paper and debris.
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Batch plant and truck wash waste is being dischargedto a settling pond which will be buried.
Permanent sanitary facilities have been installedhowever, contractor serviced portable facilities arein use by the construction force.
Item 17. The inspector observed that energy dissipators wereinstalled at the bottoms of drop pipes.
Item 22.h Although construction of transmission corridorsand water pipe line routes has not commenced, theapplicant is currently conducting EnvironmentalAwareness Seminars for contractor and applicantpersonnel including the use of a video taped pre-sentation used for supervisory personnel. Environ-mental requirements are contained in all contracts.
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FES Section 4.5.2
Item 4. The applicant is sampling and Controls for Environ-mental Pollution,' contractor, is analyzing waterfrom onsite and neighborhood wells to identifypossible effects of station construction. No ad-verse effects have been noted to date.
Item 5. Silt loads from construction area runoff to the EastMash is contained by the "J" hook basin extention ofEast Wash diversion embankment.
Item 6., The applicant plans the construction of three stillingbasins on Winters Wash tributaries which originateon or traverse the west and northwest corner of thesite west of the railroad embankment. The applicant'sevaluation of the effects of the September 24, 1976,0. 66 inch rainstorm, was that no siltation attributableto construction was identifiable. In examiningaerial photographs of the site, the inspector observedthat a substantial area located in Winters Washsouth west of the site has been placed under cultivation.
Item 7. The applicant has informed all onsite personnel thatphysicians statements are required for any cases ofValley Fever (coccidioidomycosis) among onsitepersonnel. On October 12, 1977, the inspector wasinformed that the first case had been reported onOctober 11, 1977. The applicant was preparing toreport the occurrence to local health authorities.
- No items of noncompliance were identified.
4. Im lementation of Construction Permit Re uirement E 2
The applicant and Bechtel Corporation have established a controlprogram and written procedures and instructions as required by thissection of the construction permit. The inspector verified thatcurrent procedures were available to individuals responsible forimplementation of the environmental conditions. Provisions havebeen included for management audits of the implemention of environ-mental conditions, previously reported (Para. 2 Audits).
The applicant has maintained records, sufficient to furnish evidenceof compliance with the environmental conditions in the FES.
No items of noncompliance were identified.
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5. Im lemention of Construction Permit Re uirement E 3
The applicant in procedure NS-11, Environmental Evaluation Procedureand Bechtel in procedure No. 402.0 Environmental Control Pro<rram-Construction ~Activit Environmental Evaluation CAEE make provisionsfor the identification of the environmental impacts of constructionactivities not evaluated by the NRC.
The inspector examined CAEE reports 04-76 and 01-77 through 012-77;The only item referred to the NRC was the subject of CAEE report06-77 which concerned the use of the East Wash riprap haul road onthe north side of the site as an emergency evacuation route. Theapplicant discussed this item with the Palo Verde EnvironmentalProject Manager, NRC, and was informed that since the road was notpaved, it did not constitute an unevaluated item and no NRC actionwas required.
No items of noncompliance were identified.
6. . Im lementation of Construction Permit Re uirement E 4
The applicant has established a procedure, NS-11, previouslyidentified (Para. 5) which provides for response to identifiedunexpected harmful effects or evidence of serious damage detectedduring facility construction. The inspector's discussion withapplicant personnel, examination of records and tour of the sitedid not disclose any unexpected harmful effects or evidence ofserious damage.
No items of noncompliance were identified.
7. . Im lementation of Construction Permit Re uirement E 5
The applicant has taken the following steps in the implementationof Section 6 Environmental Monitorin Pro rams of the FES:
FES Section 6.1.1.1 Surface Water; the, applicant stated thatth b I f u ~pd i ff
the NPDES permit exempted the applicant from requirements formonitoring construction area runoff for total suspended solids.As previously noted (Para 3, Item 7) the East Wash riprapped,diversion embankment and "J" hook basin area have been constructed.
FES Section 6.1.1.2 Groundwater: the perched and regionalgroundwater levels are measured weekly and summarized andreported to the applicant semiannually by NUS. Samples arecollected and analyzed quarterly by CEP. The inspector ex-amined the CEP report dated March 31, 1977.
FES Section 6. l. 1.3 Treatment Plant Water; water samples arecollected and analyzed quarterly by CEP. The inspector
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examined the report dated June 1, 1977. The analyticalprogram has included a quarterly study of the concentration of
„ ...-.="-.-.-M-131 and gross alpha and beta and gamma spectrum measurements.In addition, the samples have been analyzed for heavy el ments,
:.:-..—:. -. hardness, B00, dissolved and suspended solids, chlorides,-. = - sulphates, total phosphorus, nitrogen and ni trates, pesticides,
,chlorinated hydrocarbons, chlorophenyoxy componds and coliform.and streptococci organisms.
FES Section 6.1.2 Onsite Meteorolo ; the inspector toured.— .the onsite meteorological station and verified that the equip-
ment conformed as to type and installation. In addition tothe onsite strip chart records, digital data is telemetered tothe applicant's Deer Valley facilities for transmission to NUS
for evaluation.
FES Section 6.1.3 ~EcoIo ; the app1icant through their con-tractor Bechtel is presenting environmental awareness seminarsto construction personnel. On a continuous basis SAGE andsemiannually NUS evaluate habitat alteration, revegetationpractices and the presence of rare or endangered species. Saltdrift monitoring plots (six) have been established, fenced andplacarded as protected environmental monitoring locations.
No items of noncompliance were identified.
8. Im lementation of Construction Permit Re uirement E 6
Final transmission line routing has not yet been established. Theroute of the water pipe line from the 91st Avenue Sewage TreatmentPlant has been established. The applicant has prepared an aerialphoto map of the route and has identified areas of possible arch-eologically interest on the map. The archeological walk over of theroute is complete. Prior to excavation for the line, archeologicaltrenching will be performed at several sites the line will traverse.The applicant is presently preparing the aerial photo maps, arch-eological data and pipe line plan and profile drawings for submissionto the NRC staff for review.
No items of noncompliance were identified.
9 . Exit- Interview
. The inspector met with the applicant representatives (denoted inPara. 1) at the conclusion of the inspection on October 12, 1977.The inspector identified the areas included in the inspection andinformed the applicant that no items of noncompliance had beenidentified.
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5.2. 3 REACTOR COOLANT PRESSURE BOUVDARV MATERIALS
5.2.3.1
See CESSAR Section 5.2.3.1
5.2.3.3 Fabrication and Processin of Ferritic Materials:
5.2.3.3.1 'racture Tou hness
See.CESSAR Section 5.2.3.3.1
In Addition:
Fracture toughness testing was performed in accordance with applicable ASME
Code and Addendas (See Section ").
Fracture toughness data for the Reactor Coolant Pressure Boundary componentsfor Palo Verde Unit 1 is presented in Tables 5.2.3-1 through 5.2.3-21.Full Charpy Transition Curves (including upper and lower shelf levels forenergy absorbed, Lateral Expansion, and percent Cleavage fracture) for thesix beltline plate materials, obtained from specimens tested in the weakdirection (transverse orientation), are shown in figures 5.2.3-1 through5. 2. 3-6.
Fracture toughness data for the Reactor Coolant Pressure Boundary Componentsfor Palo Verde Units 2 8 3 will be provided at a later date.
~Bechtel to provide this information.
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5.2.3 REACTOR COOLANT PRESSURE BOUNDARY MATERIALS
5.2.3.1 l 1ateri al S ec ificati ons
See CESSAR Section 5.2.3.1.
5.2. 3.3 Fabrication and Processina of Ferritic Yiaterials:
5. 2. 3. 3. 1 Fracture ~Tou hness
See CESSAR Section 5.2.3.3.1.
5. 2. 3. 3. 2 Control of 'ideldin
5.2.3.3,2.1 Avoidance of Cold Cracl:in
See CESSAR Section 5.2.3.3.2. l.
5. 2. 3. 3. 2. 2c 2 U—'4See CESSAR Section 5.2.3.3.2.2.
5.2.3.'3.2.3 Re ulator Guide 1.71
See CESSAR Section 5.2.3.3.2.3.
5.3 REACTOR VESSEL
5.3.1.1 Reactor Vessel t1aterials
See CESSAR Section 5.3.1.
0 S ecial Controls for Ferritic and Austenitic Stainless Steels
See CESSAR Section 5.3.1.4.
I„
5.2.3.3.2 Control of Melding
5.2.3.3.2.1 Avoidance of Cold Crackin
See CESSAR Section 5.2.3.3.2. 1
5. 2. 3. 3. 2. 2 Re ulatory Guide 1.34
See CESSAR Section 5.2.3.3.2.2
5.2.3.3.2 ~ 3 Rec ulatory Guide 1.71
See CESSAR Section 5.2.3.3,2.3~~ ~~ ~~ ~~ ~
TABLE 5.2.3" 1
PALO VERDE-UNIT 1
FRACTURE TOUGHNESS DATA
REACTOR VESSEL (PLATES)
PieceNu.".,ber
ReferenceDrawin No.:
Haterial. Code No:
HaterialLocation
142-102 E-78173-161-003-02 H-4311-1
142-102 E-78173-161-003-02 H-4311-2
SA533-GRB"CL1
SA533-GRB-CL1
Lower Shell PlateLower Shell Plate
142-102-124-102
E-781?3-161-003-02 H-4311-3 SA533-GRB-CLl Lower Shel 1 Plate
E-78173-161-003-02 H-6701-1 SA533-GRB-CLl Intermediate Shell Plate
124-102 E-78173-161 "003-02 H-6701-2
124-102 E-78173-161 "003-02 H-6701-3
122-102 E-78173-161-003-02
122-102 E-78173-161-003-02
P-6701-4
H-6701 "5
.122-102 E-78173-161 "003-02 H-6701-6
102-102A E-78173-161-003-02 H-6709"1
SA533-GRB-CL1
SA533-GRB-CL1
SA533-GRB"CLl
SA533-GRB-CL1
SA533-GRB-CL1
SA533-GRB-CL1
Intermediate Shell PlateIntermediate Shell Plate
Upper Shell Plate
Upper Shell Plate
Upper Shell PlateClosure Head Dome
150-102 E-78173-161-003-02 H-6715-1 SA533-GRB-CLl 'ottom Head Dome
150-102 E-78173-161-003-02 H-6715-2 SA533-GRB-CL1 Bottom Head
Dome'02-102B
E-78173-161-003-02 H-6709-2 SA533-GRB-CLl Closure Head Dome
Drop Meight .
NDT~F-10
-40
-20
-40
-50
-30
"30
"30
-30
-20
-70
-30
"40
~)T10(a)
~ 40(a)
20(a)
+30(a)
+40(a)
+40(a)
+60(')+40(a)
40(a)
+10(a)
20(a)
30(a)
-10(a)
HinimumUpper Shelf
Ener ft-lbs
134
127
142
83
96
100
N/A
N/A
N/A
N/A
N/A
N/A
N/A
(a) Determined per Applicable ASHE-BPV-Code Sect III, Subsection NB, Article NB-2331"(a-1,2,3)
N/A Not applicable (No minimum upper shelf requirement).
189A/js A-
= TABLE 5.2.3"2
PALO VERDE UNIT-1
FRACTURE TOUGHNESS DATA
REACTOR VESSEL (FORGIiHGS)
PieceH rber
Reference~orawin Ho:
MaterialCode Ho:
MaterialS ecification
128-301
128-301
E-78173-161-003-02
E-78173-161-003" 02
131-102, E"78173-161-003" 02
131-102 E- 78173-161 "003"02
128-101 E-?8173-161 "003-02
128-101 E-78173-161 "003-02
128-101
128-101
126-101
E-78173-161-003-02
E-?8173-161-003-02
E-78173"161"003-02
M-4304"1
M-4304"2
M-4307-1
M-4307-2
M-6703-1
M-6703-2
M-6703-3
Yi-6703"4
M-6705-1
SA508-CL2
SA508-CL2
SA508-CL2
SA508"CL2
SA508-CL2
SA508-CL2
SA508-CL2
SA508-CL2
.SA508-CL2
106-101 E-78173-161-003" 02 M-6706-1
E-781I3-161-003-02128-501
128-501 E-17873-161-003-02
128-501 E-78173-161-003-02
128-501 E"78173-161-003-02
M-6708-1
Yi-6708-2
M-6708-3
lj-6708-4
SA508-CL2
SA508-CL2
SA508-CL2
SA508-CL2
SA508-CL2
131-101
131-101
. E-78173-161-003-02 . M-6712-1
E"781 I 3-161-003-02 M"6712-2
SA508-CLl
SA508"CL1
131-101 E-78173-161-003-02 M-6712-3 SA508" CL1
131-101 E-78173-161-003-02 - M-6712-4 SA508-CL1
Location
Outlet NozzleOut'let Nozzle
Outlet Nozzle Safe End
Outlet Nozzle Safe End
Inlet Nozzl e
Inlet Nozzle
Inlet Nozzle
Inlet Nozzle
Vessel Flange
Closure Head Flange
Inlet Nozzle Extension
Inlet Nozzle Extension~ .
In'let Nozzle 'Extension
Inlet Nozzle Extension
Inlet Nozzle Safe End
Inlet Hozzle Safe End
Inlet Nozzle Safe End
Inlet Nozzle Safe End
Drop VeightNOT F0 180
-10 -10
-10 -'l0
"10 -10
-10 "10
-20 "20
+10 +10
-10 -10
0 0
-70 -70
-70 -70
+20 +20
+20 +20
+20 +20
+20 +20
-10 -10
-10 "10
-10 -10
"10 -10
0
10(a)
lp(a)+10(a)
+10(')p(a)
+10(a)
10(a)p(a)
-70(')-70(')+2p(a)
+20(')+20(a)
+20(')lp(a)10(a)
10(a)
10(a)
180
1p(a)
10(a)
+10(a)
+lp(a)0(a)
+1 0 (a)
10(a)p(a)
70(a)
70(a)
+20')+20(a)
,20(a)+20(a)
lp(a)-lp(a)-10(a-lp(')
RTHDT ( F)
(a) Detersiined per applicable ASME-BPV Code and addenda, Sect III, Subsection NB, Article NB-2331-(a"1,2,3)
TABLE 5.2.3-3
PALO VERDE UNIT-1
FRACTURE TOUGHNESS DATA FRO<1 MELD vETAL CERTIFICATION TESTS
REACTOR VESSEL
(DATA TO BE PROVIDED AT A LATER DATE)
Seaa 8 Seam Nomenclature Meld Filler Lot 8 RNDT ( F)
189A!js F" ""
Sea "lNu.",.ber
TABLE 5.2.3-4
PALO VERDE UNIT-1
FRACTURE TOUGHNESS DATA FROM WELD PROCEDURE (UALIFICATIONTESTS
REACTOR VESSEL
(DATA TO BE PROVIDED AT A LATER DATE)
~t<DT FDetailed Weld Meld Procedure Meld Filler materials Joined HAZ HAZ
IL""'R'NOTl~'el d~OF
TABLE 5.2.3"5
PALO VERDE .UNIT-1
FRACTURE TOUGHNESS DATA
REACTOR COOLANT PIPING (PLATES)
PieceNu".ber .
722-102
722-102
722" 102
722" 102
722-104
722-'104
722-1C4
722-104
722-104
722-104
722" 104
722-104
722-106
722-106
722" 106
722-106
ReferenceDrawin No.:
E"78473"761-001-00
E-78473-761-001"00
E-78473-761-001-00
E-78473-761-001-00
E-78473-761-002-02
E-78473-761-002-02
E-78473"761-002-02
E-78473-761-002-02
E-78473-761-002-02
E-78473-761-002-02
E-78473-761-002-02
E-78473-76'l-002-02
E-78473-761-002-02
E-78473" 76'l -002"02
E-78473-761-002-02
E-78473-761-.002-02
llaterialCode No:
H-7601" 1
H-7601-2
H"7601-3
H-7601-4
Yi-7602-1
H-7602-2
H-7602-3
H-7602-4
H-7602-5
H-7602-6
Yi-7602-7
H-7602-8
H-7603-1
Yi-7603-2
H-7603-3
H-7603-4
HaterialS ecification
Sl61 6-GR70
SA516-GR70
SA516-GR70
SA516-GR70
SA516-GR70
SA516-GR70
SA516-GR70
SA516-GR70
SA516-GR70
SA516-GR70
SA516-GR70
SA516-GR70
SA516-GR70
SA516-GR70
SA516-GR70
SA516-GR70
Location
Segment
Segment
Segment
Segment
Segment
Segment
Segment
Segment
Segment
Segment
Segment
Segment
Segment
Segment
Segment
Segment
StraightStraightStraightStraightStraight
- StraightStraightStraightStraightStraightStraightStraightStraightStraightStraightStraight
Drop Meight~NDT 'F
-'l0
-10
-10
-10
-10"'l0
-10
0
-10
-10
-10
-10
-'lD
-10
-10
~lT.10(a)
+10(a)
.10(a+10(a)
+10(a)
+10(a)
+20(a)
+20(')
+10".10')+20(a)
+10(a)
0(a)
0(a)
0(a)
0(')
189A/js H-~~ (TABLE 5.2.3-5 (Continued)
PALO YERDE UNIT"1
FRACTURE TOUGHNESS DATA
REACTOR COOLANT PIPING {PLATES)
PieceNumber
722-106
722-106
722-106
722-106
722-102
722-204
722-204
722-204
722-204
722-208
722-208
722-104
722-104
722-104
ReferenceDrawino No.:
E-78473-761-002"02
E-78473-761-002-02
E-78473-761-002-02
E-78473-761-002-02
E-78473-761-002-02
E-78473-761-002-02
E-78473-761-002-02.
E-78473-761-001-00 .
E-78473-761-001-OD
E-78473-761-001-00
E"78473-761-001-00
E-78473-761.-002-02
E-78473-761-002-02
E-78473-761-002-02
HaterialCode No:
H-7603-5
H-7603-6
M-7603-7
H-7603-8
H-7604-1
H"7605-1
H-7605"2
H-7605-3
H-7605-4
M-7606-1
H-7606-2
M-7606-6
H-7606"7
H-7606-8
MaterialS ecification
SA516-GR70
SA516-GR70
SA516-GR70
SA516"GR70
SA516-GR70
SA516"GR70
SA516-GR70
SA516-GR70
SA516-GR70
SA516-GR70
SA516-GR70
SA516-GR70
SA516-GR70
SA516"GR70
Location
Straight Segment
Straight Segment
Straight Segment
Straight Segment
Elbow Segment
Elbow Segment
Elbow Segment
Elbow Segment
Elbow Segment
Elbow Segment
Elbow Segment
Straight Segment
Straight Segment
Straight Segment
Drop Weight~NOT F
-10
-10
"10
-10
-10
-10
-10
"10
-10
-10
"10
"10
-10
-10
~o)DTRT
0(a)0(a)0(a)0(')
lp(a)
+1 p(a)
lp(a)lp(a)
+1 p(a)
+10(a)
lp(a)+10(a)
+20(a)
+10(a)
(a) Determined per applicable ASHE BPV Code Sect III, Subsection NB. Article NB-2331(a-l,2,3)
TABLE 5.2.3-6
PSLO VERDE UNIT-1
FRACTURE TOUGHNESS DATA
REACTOR COOLANT PIPING (FORGINGS)
PieceNumber
Reference~Drawin No:
728-101 E-78473" 761-001-00
728-201
728-201
728-202
E"78473-761-001-00
E-78473-761 "001-00
E-78473-761-002-02
728-202 E-78473-761-002-02
728-102 E-78473-761-002-02
728-102 E-78473-761"002-02
728-102 E-78473-761"002-02
728-102 E-78473-761-002-02
728-103 E-78473-761-002-02
728-103 E-78473-761-002-02
728-103 E-78473-751-002-02
728"103 E-78473-761-002-02
728-203 E-78473"761-002-02
MaterialCode No:
M-7607-1
H-7608-1
H-7608-2
H-7609-1
H-7609-2
H-7610-1
M-7610-2
H-7610-3
Material
SA541-CL1
SA541-CLl
SA541-CLl
SA541"CL1
SA541-CLl
SA541-CLl
SA541-CL1
SA541-CL1
M"7610-4 SA541-CLl
H-7612" 1 SA182-GRF1
M-7612-3
H-7612-4
M-7613-1
SA182-GRF1
SA182-GRF1
SA182-GRFl
H-7612-2 SA182-GRF1
Location
Surge Nozzle
Shutdown Cooling Outlet Noz.
Shutdown Cooling Outlet Noz.
Spray Nozzle
Spray Nozzle
Letdown Drain Nozzle
Letdown Drain Nozzle
Letdown Drain Nozzle
Letdown Drain Nozzle
Safety Injection Nozzle
Safety Injection Nozzle
Safety Injection Nozzle4
1'afetyInjection Nozzle
Charging Inlet Nozzle
~01 8G
-10
-10
-10
N/A
N/A
N/A
N/A
N/A
N/A
0
-10
Drop WeightNDT F)-
RT>DT ( F)/LST"( F)
0 180
+1O(')
~10(a)
+10(a)
/,40(d). /+40(d)
/+40(d)
/+40(d)/.4O(d)/+4O(d)
0(a)
10(a)
0(a)
O(')0(a)
(a) Determined per applicable ASME-BPV Code and addenda Sect III, Subsection NB, Article NB-2331-(a-l,2,3)
(d) 'LOW ST SERVICE TEMPERATURE' Determined per applicable ASML-BPV Code and Addenda Sect III, Subsection NB,
Article NB-2332-a
Lowest service temperature
N/A Not applicable
0TABLE 5. 2. 3-7
PALO VERDE UNIT-1
FRACTURE TOUGHNESS DATA FROiN WELD METAL CERTIFICATION TESTS
REACTOR COOLANT PIPING
(DATA TO BE PROVIDED AT A LATER DATE)
Seam ¹ Seam Nomenclature Meld Filler Lot ¹ RTNDT ( F)
TABLE 5.2.3"8
PALO VERDE UNIT-1
FRACTURE TOUGHNESS DATA FROM 'WELD PROCEDURE (UALIFICATIONTESTS
REACTOR COOLANT PIPING
(DATA TO BE PROVIDED AT A LATFR DATE)
Sean Detailed Weld'eld Procedure Weld Filler~NDT F NDT
Materials Joined HAZ HAZ WeldMaterial 1
- Material 2 1 2 ~F
189A/js H-
'iece
NumberReference
Drawin No.:MaterialCode No:
TABLE 5.2.3-9
~ 'ALO VERDE UNIT-1
FRACTURE TOUGHNFSS DATA
PRESSURIZER (PLATES)
HaterialS ecification Location
Drop Meight~DDT F
642-102
642-102
676" 102
622-102
622-102
642-652
E-78473-661-002-03
E-78373-661-002-03
E-78373"651"002-03
E-78373-661-002-03
E-78373-661-002-03
E-78373-661-002-03
H-5008-1
Yi-5008-2
t<-7030-1
H-7309-1
H-7309-2
M-7313-1
SA533-GRB-CL1
SA533".GRB-CL1
SA533-GRB-CL1
SA533-GRB-CL1
SA533-GRB-CL1
SA533-GRB-CL1
Lower Shell Plate
Lower Shell Plate
Top Head Dome
Upper Shell Plate
Upper Shell PlateBottom Head Dome
-10
"10
-10
-10
-10
"10
10(a)
+20(a)
-10(')10(a)
-10(')10(a)
(a) Determined per applicable ASYiE BPV Code Sect III, Subsection NB, Article NB"2331 (a-l,2,3)
I l
189A/js A-2~r 5
1
TABLE 5.2.3-10
PALO VERDE UNIT-.1
FRACTURE TOUGHNESS DATA
PRESSURIZER (FORGINGS)
PieceNu.;ber
Reference~0@awi n Na:
608-303 E-78373"661-002-03
608-304 E-78373-661-002-03
656-652 E-78373-661-002-03
656-101 E-78373-661-002" 03
658-201 E-78373-661-002-03
608-303 E-78373-661-002-03
608-303 E"78373-661-002-03
608 303 E 78373 661 002 03
MaterialCode No:
H-7301-1
H-7302-1
H-7303"1
H-7303-2
H-7303-3
M-7303"4
~ H-7304-1
M-7313-1
MaterialS ecification
k
SA508-CL2
SA541-CL2
SA541-CL2
SA541-CL2
SA541-CL2
SA541-CL2
SA541-CL2
SA508-CL2
Location
Support SkirtSurge Nozzle
Safety Valve Nozzle
Safety Valve Nozzle
Safety Valve Nozzle
Safety Valve Nozzle
Spray Nozzle
Support Skirt
Drop WeightNDT F
0 180
-10
-10
-10
-10
-10
-10
+10
-10
RTNDT ( F)
0 180
-lo(')10(a)
+40(a)
.4o')+4O(a)
40(a)
.lo(')10(a)
(a) Determined per applicable ASHE-BPY Code and addenda Sect III, Subsection NB, Article NB-2331-(a-l,2,3)
~ ~
189A/js B-
'eam
8
TABLE 5.2.3-11
PALO VERDE UNIT-1
FRACTURE TOUGHNESS DATA FROST WELD NETAL CERTIFICATION TESTS
PRESSURIZER
{DATA TO BE PROVIDED AT A LATER DATE)
Seam Nomenclature Weld Filler Lot 0'TNDT { F)
'189A/js F-( .~
SeamNumber
TABLE 5.2. 3-12
PALO VERDE UNIT-1
FRACTURE TOUGHNESS DATA FROH MELD PROCEDURE QUALIFICATION TESTS
PRESSURIZER
(DATA TO BE PROVIDED AT A LATER DATE)
~RTgpy,p) RTgpy
Detailed Meld Weld Procedure Meld Filler Yiater ials Joined HAZ HAZ WWeeidI"
189A/js H- "':"
PieceNu-.ber
248-302
254-102
254-102
255-104
244-102A
ReferenceDrawin No.:
c 78373 261 003-04
E-78373-261-003-04
E-78273-261"003-04
E-78273-261-003-04
E-78273-261-003-04
244-1028 E-78273-261"003-04
244-102C E-78273-261-003-04
276-3101A
276-3101B
E-78372-261-003-04
E-78273-261-003-04
244-)020 -
E-78273"261-003-04'aterial
Code No:
TABLE 5.2.3-13
PALO VERDE UNIT"1
FRACTURE TOUGHNESS DATA
STEAM GENERATOR UNIT 1 (PLATES)
MaterialSoecification Locat'.on
M-2105-1 SA516-GR70 Stay Cap
H-7021-1 SA533-GRB-CLl Primary Head
H-7021-2 SA533-GRB-CL1 Primary Head
H-7202-1 SA533-GRB-CLl Support SkirtH-8104-1 SA533-GRB-CLl Primary Extension Ring
H"8104-1 SA533-GRB-CL1 Primary Extension RingH-8104-1 SA533-GRB-CLl Primary Extension RingH-8104-1 SA533-GRB-CL1 Primary Extension Ring
H-7243-1 SA533-GRB-CL1 Primary Hanway Cover
H-7243-1 SA533-GRB-CLl Primary Hanway Cover
Drop Meight~HDT F
-40
-10
-10
-35
-20
-20
-20
-20
+10
+10
~o)P
~-0(a)
10(a)
10(a)
35(a)
20(a)
-20(')0(a)
p0(a)
~10(a)
+10(a)
(a) Determined per applicable ASME-BPV-Code Sect III Subsection NB, Article NB-2331-(a-1,2,3)
189A/js A-
TABLE 5.2.3-14
PA 0 VERDE UNIT-1
FRACTURE TOUGHNESS DATA
STEAM GENERATOR UNIT 01 (FORGINGS)
PieceNu~ber
246-101
248-101
Reference~Drawin No:
E-78273" 261-003-04
E-78273-261-003-04
252-201
258-101
258-301
258-301
258-202
258-402
258-402
E-78273"261-003-04
E-78273-261-003-04
E-78273-261"003-04
E-78273-261-003-04
E-78273-261-003-04
E-78273-261-003-04
E-78273-261-003"04
248-201 E-78273-261-003-04
252-101 E-78273-261 "003"04
MaterialCode No:
M-4701-1
M-4706-2
M"4710"2
M-7022-1
M-7023-1
M-7024-1
M-7025-1
M-7025-2
M-7026-1
M-7027-2
M-7027-3
Material
SA508-CL2
SA508-CL2
SA508-CL2
SA508-CL3
SA508-CL3
SA508-CL2
SA508-CL2
SA508-CL2
SA508-CL1
SA508-CL1
. SA508-CL1
Location
Tube Sheet
Stay Stub
Stay Cap
Stay Cyl inderStay Ring
Inlet Nozzle
Outlet Nozzle
Outlet Nozzle
Inlet NOzzle Safe End
Outlet Nozzle Safe End
Outlet Nozzle Safe End
Drop WeightNDT F)0 180
+40 +40
+40 +40
-30 "30
+10 +10-+10 +10
-5 "5-5 -5+11 +11
-23 "23
-32 "32
"32 -32
0
+so<'>
.40(')-30(a).40(')30(a)5(a)
5(a)
-23(')-12(')
12(a)
180
40(a)
40(a)
30(a)
~40(a)
~30(a)5(a)5(a)
-23(')12(a)
12(a)
RTNDT ( F)
(a) Determined per applicable ASME-BPV Code 8 addenda, Sect III, Subsection NB, Article NB-2331-(a-l,2,3)
1
189A/js B (™'1
1
TABLE 5.2.3-15
PALO VERDE UNIT-1
FRACTURE TOUGHNESS DATA FROM MELD METAL CERTIFICATION TESTS
STEAM GENERATOR 81
(DATA TO BE PROVIDED AT A LATER DATE)
Seam 8 Seam Nomenclature Meld Filler Lot 8. RTNDT ( F )
189A/js F
TABLE 5.2.3-1S
PALO VERDE UNIT-1
FRACTURE TOUGHNESS DATA FROM WELD PROCEDURE QUALIFICATION TESTS
STEAM GENERATOR Ol
(DATA TO BE PROVIDED AT A LATER DATE)
Seam Detailed MeldNumber Seam Nomenclature Procedure 0
Meld Procedureualification 8
~NDT F NDT
Meld Filler Materials Joined HAZ HAZ MeldMaterial Lot 8 Haterial 1 Haterial 2 1 2 ~F
189A/js H-AXF
PieceNumber
ReferenceDrawin Ho.:
MaterialCode Ho:
TABLE 5.2. 3"17
PALO VERDE UNIT-1
FRACTURE TOUGHNESS DATA
STEAM GEHERATOR UNIT 82 (PLATES)
MaterialS ecification Location
Drop Meight~NDT 'F
248-302
256-'104
276-3101 A
276-3101 B
254-102
254-102
244-102A
244-1028
244-102C
244-102D
E-78273-351-003-02
E-78273-361-003"02
E-78273-361-003-02
E-78273"361-003"02
E-78273"351-003-02
E-78273-361-003-02
E-78273-361-003-02
E-78273-361"003-02
E-78273-361-003-02
E-78273-361-003-02
M-2105-1
l l-4919-1
M-7243-1
M-7243-1
M-7021-3
M-7021-4
M-8104-1
M-8104-1
M-8104-1
M-8104-1
SA516-GR70
SA533-GRB-CLl
SA533-GRB-CL1
SA533-GRB-CL1
SA533-GRB-CL1
SA533-GRB-CL1
SA533-GRB-CL1
SA533-GRB-CLl
SA533-GRB-CLl
SA533-GRB"CL1
Stay Cap
Support SkirtPrimary Manway Cover
Primary Manway Cover
Primary. Head
Primary Head
Primary Extension Ring
Primary Extension Ring
Primary Extension Ring
Primary Extension Ring
-40
+10
+10
+10
-10
-10
-20
-20
-20
-20
+3p(a)
+10(a)
+10(')+10(a)
-10(')0(a)
2p(a)
20(a)
2p(a)
2p(a)
(a) Determined per applicable ASME-BPV-Code Sect III Subsection NB, Article HB-2331-(a-l,2,3)
189A/js A-@P
TABLE 5.2.3-18'ALO
VERDE UNIT"l.
FRACTURE TOUGHNESS DATA
STEAM GENERATOR UNIT 82 (FORGINGS)
PieceNu4Dber
Reference~Drawia Na:
HaterialCode No:
246-101 E-78273-361-003-02 Yi-4701-2
248-201
252-101.
252-201
258" 101
258-301
258-301
258-202
258-402
258-402
E-78273-361-003-02
E-78273" 361-003-02
E-78273-361-003-02
E"78273"361-003-02:-'-78273-361-003-02-".
E-78273-361-003-02
E-78273-361-003-02
E-78273-36't-003-.02
E-78273-361-003-02
H-4710-2
M-7022-2
H-7023-2
M-7024-2
M-7025-3
Yi-7025-4
M-7026-2
M-7027-1
H-7027-4
248-101 E-78273-361-003-02 H-4706" 1
Yiaterial ~ ~
S ecification
SA508-CL2
SA508-CL2.
SA508"CL2
SA508-CL3
SA508-CL3
SA508-CL2
SA508-CL2
SA508-CL2
SA508-CL1
SA508-CLl
SA508-CLl
Location
Tube Sheet
Stay Stub
Stay Cap
Stay CylinderStay Ring
Inlet Nozzle
Out'1et Nozzle
Outlet Nozzle
Inlet Nozzle Safe End
Outlet Nozzle Safe End
Outlet Nozzle Safe End
Drop WeightNDT ( F
8 18D
-20 -20
+40 +40
-30 -30
+10 +10
-10 +10
-15 -15
-16 -16
"16 -16
"23 "23
-32 -32
"32 "32
0
„,(a)~40(a)
30(a)~ .+40(a)
+10(')-15(')-16(a)'16(a)
-23(')
-12(')
180
~40(a)
+40(a)
30(a)
40(a)
~1 0(a)
15(a)
-16(')16(a)
-23(')12(a)
12(a)
RTNDT ( F)
(a) Deterained per applicable ADHE-BPV Code 8 addenda, Sect III, Subsection NB, Article NB-2331-(a-l,2,3)
l
TABLE 5.2.3" 19
PALO VERDE UNIT"1
FRACTURE TOUGHNESS DATA FROM MELD HETAL CERTIFICATION TESTSe
STEAN GENERATOR 82
(DATA TO BE PROVIDED AT A LATER DATE)
Seaa ¹ Seam Nomenclature Meld Filler Lot 8 . RTNPT ( F)
189A/js F
TABLE 5.2.3-20
PALO YERDE UNIT-1
FRACTURE TOUGHNESS DATA FROM WELD PROCEDURE QUALIFICATION TESTS
STEAM GENERATOR P2
(DATA TO BE PROVIDED AT A LATER DATE)
Seculi Detailed MeldNuaber Seam Nomenclature Procedure ¹
Meld Procedure Meld FillerMaterial Lot 0
~NOT F NOTMaterials Joined HAZ HAZ Meld
Material 1 Material 2 1 2 ~F .
189A/js A-5&'ABLE5.2.3-21
PALO VERDE UNIT-I
FRACTURE TOUGHNESS DATA
REACTOR COOLANT PUHPS (FORGINGS)
(DATA TO BE SUBHITTED AT A LATER DATE)
PieceNumber
Reference~Drawia No:
Hateria'lCode No:
HaterialS ecification Location
Drop Height~NDT F
0 180
RTNDT ( F)
-0 180
~ ~
~ ~ ~ ~
f,' ": T i' f) CI
y L f~ ) L!PP1 1: /f~A!)~ 1 ('';C >. f. 3': 1"g fi.-'.
"00
180
CijC.PO.Cij0
160C0CL'
CLCiJ
ILJ
140 8
000
RC)
tOKCL0>CCij
120
10G
EOC)
g
6G0
0LU
W
1
1
CG
20
CC0
CL
80
~ X~X~
I
p< ~a
ic
~ X0 7C
+1
0
-80/
-40 0 40 80 120 160 . 200 240
T Eilf'EfiATURK F
Lower Shell Plateimmaterial 'Code Ho: N-4311-1
I'AI 0 'I',= Pic .WU"Li.,R 0'i f.;:"". l i"4 . TAT T
Qt'ffAP,:1
1 -'n;-:Suf.VS
f l fiJ0:":, 5 . 2, 3- 1
"OG
i80R
A
i60
(L
Cf.4J
CJiCQ
C)
KCCoOCUJ
120
i QA
SG
X ~+o
o
0"
00
lACO
IQG
U
0[Uz 40IJj
20
0
-80 -40 0 40 80 120 '60 200 240
TL';ii'"RA~JRi'. F
Lover Shell PlateIiaterial Code Ilo: 14-4311-2
PRLO V. Ri)EilLJCLFHI". G;":l'I'= R'r1T, i<G STAT I '")is
UNI '
CIIAP.i" r i i Sl fk:":SALTS
5~32
~ ~
~ ~
~ ~ ~Q I'.
+
f' /I EIS-l fllf.IDEAL;:/l'fla",5I Ci~lCI. I: fI /fi('E
229
200
100
us )e
CC)LU
EJ)CO
00
0
lO
1 20ZO
KCC0
lOG
JCCCC
CE
X y, ~
W ~ y ~
0
0'.lsJi-'al CO
20
oI ~
-80 -40 0 40 '. So 120 200 24C
TI,"i'if'f,"llATUR:"; F
Lower. Shell Plate?material Code No: H-4311-3
PRLCi 'iERGEf3UCL AR DL":i'i'"i"'1' NG 5TnT I QN
U4! TCIIAfif'( 1":.ST RESULTS
5 I 2 3 3
4
~ v ~
~ II
~ ~
0 -- f: l /I PSw - L A 7 f' fiL;":Xf'P f ~i f 0 l f+ C I.. f'0 /l'f
f.'-f'+0
200
IRLIJC.>
W0
UJED0:C:LIj
LJ
1BO
160
1CO
Cl
VP
CC
120
100 KIL
0
lAC7
IGO
Wz 40la)
20
o
0 IL ~o ~
C ~,~
X
0
l~ '
-80 -40 0 40 80.
T:NPFRATURE F
120 160 200 2~1
Pi~I 0 Vt=RP.""llUCLERR C","'"..Pg) I >C STR
'fI1 7 Iimmaterial Code No; N-6701-1 „.. CflORf'( 'EST l',;5JL7
F .'1)1/h;.
~ .~
1
~~
++0
200
IRII/LJCt.4J0
4JCDCI:
CKILI
C>
180
160
1CO
tO
120' n
07
CC„0
10G
CCCrIIICC
OG
IC~ IC
COCC)
II" 60II.0 00 0
~ ~
~.' M
4JCO
UJ
20
0
-40 0
0
0
~W
40 80
~ ~
120
. K
200 24C
1F'1P; P,ATUR."" F
PP.LO V(,Pi!~t..Intez11>ediate Shell Plate I]!1pLEp~> p= 1;=p>g,"'T ~)II'. S ~
A!' Q~gHateria3.'ode No: i4-6701-2. - .'. c. f!!qI,py
I
F'lC(11'l" ~ ~ 2
."or,
'Oo
WtJWC
Ioo
CL
C4W
l EJ1CO
Rc5
V7KCC0
bi
l20
$ 00
WI
oo
I60
0
WCot LU
)C )C p:
0
0 0
0
D
~M
~t ~
gH
'0
I
l~
~
'
'80 -40 0 40 80 120 160 200 24t
TEt'IPERATURF. F
PRi g VER(.iL=.Intermediat:e Sh'ell I'3ate ',fU( LI=Rf> Q- J;= Rp f l f')j 5TH, T I Dl'f~,„, -, UNllMQeerLQ1 Code No: bl-6701-3' ' 'C~(Ar'PYJT~ti'1 Rl::"-Ut.T5
F I Cv'R".". 5, 2, 3-6
5.3 REACTOR VFSSEI
5.3.1 REACTOR VESSEL MATERIALS
5. 3.1.1 Material S ecifications
See CESSAR Section 5 ~ 3.1.1
5. 3. 1.4 S ecial Controls for Ferritic and Austenitic Stainless Steels
See CESSAR Secti on 5. 3. 1. 4
5.3.1.5 Fracture Tou hness
See CESSAR Section 5.3. 1.5
In Addition:
Data from fracture thoughness tests of base metal, weld metal and heat-affected-zone (lkAZ) material for Palo Verde Unit 1*are presented in tables5. 2. 3-1 through 5. 2. 3-4 of Section 5. 2. 3. 3. l.
Chemistry analyses for the Beltline plates and weld metal for Palo VerdeUnit 1 are presented in tables 5.3. 1-1 8 2 respectively.
~S'imilar data for Palo Verde Units 2 8 3 will be presented at a later date.
6
5.3.1.6 Reactor Vessel Material Surveillance Pro ram
Palo Verde Unit 1*
The surveillance program monitors the radiation induced
changes in the strength and toughness properties of thereactor vessel beltline materials. These changes are
determined by comparison'of pre- and post-irradiation testresults using uniaxial tension specimens, standard and
precracked Charpy impact specim'ens> and compact tensionpecimens.
This surveillance program was stablished using the
criteria presented in ASTM E185-79, "Standard Practice forConducting Surveillance Tests for Light-Hater Cooled
5:uclear Power Reactor Vessel". It also conforms to the
)equirements of 10 CFR Part 50< Appendix H (October 26>
1979) entitled "Reactor Vessel Material SurveillanceI'rogram Requirements"- The material toughness
requirements are determined in accordance with 10 CFR Part50, Appendix G and ASME Boiler and Pressure Vessel Code@
':ection III, Article NB2300.
5.3.1.6.1 Test Material Selection
'Jhree metallurgically different materials, representativeof the reactor vessel< are inv stigated. These are, base
metall'eld metall'nd heat:-affected-zone material. Base
metal specimens are fabricated from sections of two platesin the beltline region of the vessel which become the
limiting plates with respect to the operation during itslife time.
/'I
*(For Palo Verde Units 2 & 3 see CESSAR Section 5.3.1.6 ~ )
I 0
Bose metal test material is manufactured from two platesaelected from the reactor pressure vessel belt1ine.Selection was based on an evaluation of initial toughness
(characterized by the reference temperature, RT ), and
the pred'icted effect of chemical composition (residualcopper and phosphorus) and neutron fluence on thetoughness (RT shift) during reactor operation. A
NDTplate from the lower shell course had the highestpredicted RT shift. A plate from the intermediate
NDTshell (nozzle) course had the highest adjusted RTNDT
(initial RTNDT plus RTNDT shif').
Weld region test material is p':oduced by fielding togethersections of lower shell course plates from the beltline ofthe reactor vessel. The HAZ test material is manufactured
from a section of the same plate used for lower shellcourse base metal surveillance test material. The weld
metal test material is produced from the same heat of weld
wire or rod and lot of flux u ed in the beltline of the
reactor vessel. Welding parameters duplicate those used
for the beltline welds.
Representative stock (archive material) to provide two
additional sets of test specimens .for each material are
provided with full documentation and identification. Zn
addition, material is includec from a standard heat ofASTH A533-B Class l manganese-molybdenum-nickel steel made
available by the USNRC sponsored Heavy Section Steel
Technology (HSST) Program. This standard referencematerial (SRM) is used as a monitor for Charpy impact
tests, permitting comparisons among the irradiation data
, from operating power reactors and experimental reactors.Compilation of data generated from post-irradiation testsof these correlation monitors will be carried out by the
~ flSST program.
0
5 '.1.6.2 Test S ecimens
5.3.1.6.2.1 e and uantit
The total quantity of specimens furnished in this program
for baseline (unirradiated) and post-irradiation testingis presented in Table 5.3.1-3. The types of specimens are
drop weight, tension,'Charpy impact, and compact tensionfor baseline testing; and tension, Charpy impact, and
compact tension for post-irrad'tion testing.
5.3.1.6.2.2 The type and quantity of test specimens provided forestablishing the properties of the baseline (unirradiated)reactor vessel materials are presented in Table 5.3.1.4.~he data from tests of these specimens provide the basisfor detemining the radiation induced property changes ofthe reactor vessel materials.
Drop weight test specimens are provided to establish the
nil-ductility transition temperatures (T ) of theNDT
unirradiated lower shell course base metal (transverse,orientation), weld metal and EAZ material. Standard
Charpy impact test specimens f.'rom the lower and
intermediate shells are provided to establish the initialimpact energy transition curve and reference temperature
(RT ) of the base metals (longitudinal and transverseNDT
orientation), weld metal and HAZ material. Uniaxialtension test specimens are provided to define the initialstrength versus temperature relationship for the
~ surveillance materials. For intermediate shell course/
base metal, no drop weight or longitudinal tensionspecimens are provided. Reactor vessel materialqual ification test results will be used instead.Precracked Charpy impact and compact tension (lt and
0
1/2t) specimens
are provided tofrom the two base metals and weld metaldetermine the fracture toughness
properties over the range extending from linear elastic toelastic-plastic fracture.
5.3.1.6.2.3 Irradiated S ecimens
The type and quantity of test specimens for monitoring the
properties of the irradiated materials over the lifetimeof the reactor vessel are presented in Table 5.3.1-5.Charpy impact, precracked Charpy, 1/2t compact tension,and tension specimens are used to measure changes in thestrength and toughness of the surveillance materials.
Charpy impact test specimens are provided to establish the
impact energy transition curve after irradiation for the
two base metals {longitudinal and transverse orientation),weld metal and HAZ material. Tension test specimens areprovided to measure the strength and ductility of the two
base metals and weld metal following irradiation. The
precracked Charpy and compact tension specimens are
provided to measure the fracture toughness afterirradiation.
5.3.1.6.3 Surveillance Ca sules
The surveillance test specimens are placed in corrosionresistant capsule assemblies for protection from the
primary coolant during irradiation. The capsules alsoserve to physically locate the test specimens in selected
positions within the reactor vessel and to facilitate the
removal of a desired quantity of test specimens when a
specified radiation exposure has been attained. Sixsurveillance capsule assemblies are provided for the
4
reactor vessel. A summary of specimen type, origin, and
quantity contained 'in each capsule assembly is presented
in Table 5'3.'1-6 ~
A typical capsule assembly, il'ustrated in Figure 5.3-1,consists of a series of three specimen compartments<.
connected by wedge couplings, and a lock assembly. Each
compartment enclosure of the capsule assembly isinternally supported by the surveillance specimens and is
2externally pressure tested to 3125 lb/in during finalfabrication The wedge couplings also serve as end caps
for the specimen compartments which are housed within the
.capsule holders attached to th reactor cladding. The
lock assemblies fix the locations of the capsules withinthe holders by exerting axial forces on the wedge couplingassemblies which cause these assemblies to exerthorizontal forces against the sides of the holderspreventing relative motion. 'Ihe lock assemblies alsoserve as a point of attachment for the tooling used toremove the capsules from the
reactor'ach
capsule assembly consists of three compartments.
Each compartment consists of two sections attached by a
connecting spacer ~ Each capsule compartment section isassigned a unique identification so that a complete record .
of test specimen location within each compartment sectioncan be maintained.
Palo Verde Unit 1'ill have six surveillance capsules
including 2 precracked Charpy assemblies and one compact
tension assembly for lower shell specimens and 2
~ precracked Charpy assemblies and one compact tension
assembly for intermediate shell specimens. The types ofspecimens contained in each is given in Table 5.3.1-6. Inaddition, each of the six capsules contains one set ofnine flux monitorsi two sets of five flux monitorsi and
one set of temperature monitors.
,
'5.3.1.6.3.1 Precracked Char Ca sule Assembl
The four precracked Charpy capsule assemblies consist ofthree capsule compartments< two Charpy and Flux
Compartments and one Temperature, Flux, Tension and Charpy
Compartment. The contents of each compartment are
described below:
a ~ Charpy and Flux Compartment Assembly
This assembly (Figure 5.3-2) contains 15 base metal
(transverse) impact test specimens and a set of five
flux spectrum monitors in the top section. The
bottom section contains nine precracked Charpy testspecimens each of base metal (longitudinal and
transverse). The Charpy test specimens are arranged
vertically in 1 x 3 arrays and are oriented with the
notch toward the reactor core. The temperature
differential between the specimens and the reactor
coolant is minimized by using spacers between the
specimens and the compartment and by sealing both
sections of the assembly in an atmosphere of helium.
b. Temperature, Flux, Tension & Charpy Compartment
Assembly
This assembly (Figure 5.3-3) c'ontains three base
metal (transverse) tension te'st specimens and 12 HAZ
(heat-affected-zone) impact test specimens in the top
section. The tension specimens are placed in a
housing machined to fit the compartment. Splitspacers are placed around the gage length of the
specimens to minimize the temperature differentialbetween the specimen gage length and the coolant.
The impact specimens are arranged vertically in 1 x 3
arrays and are oriented with the notch toward the
reactor core. Spacers a> e utilized between the test
specimens and the compartment. The bottom section
contains a set of nine flux spectrum monitors> a set
of temperature monitors, 9 SRM (Standard Reference
Material) impact test specimens and 3 weld metal
tension test specimens- Both compartment sections
are sealed within an atmosphere of helium.
c» Charpy and Flux Compartment Assembly
This assembly (Figure 5 '-2) contains 15, weld metal
impact test specimens and a set of five flux spectrum
monitors in the top section. The bottom section
contains nine precracked weld metal and 9 base metal
(longitudinal) impact test specimens. The testspecimens are arranged vertically in 1 x 3 arrays and
are oriented with the notch toward the reactor core.
The temperature differential between the specimens
and the reactor coolant is minimized by using spacers
between the specimens and the compartment and by
sealing both sections of the assembly in an
atmosphere of helium.
5.3.1.6.3.2 Com act Tension Ca sule Assemblies
The two CT capsule assemblies consist of 3 capsule
compartmentsr two Charpy< Flux and Compact Tension
Compartments> and one Temperature, Flux, Tension, and
Charpy Compartment. The contents of each compartment are
described below:
a ~ Charpy, Flux & Compact Tension Compartment Assembly
This assembly (Figure 5.3-4) contains 15 base metal
(transverse) impact test specimens and a set of fiveflux spectrum monitors in the top section. The
bottom section contains 10 base metal (transverse)
1/2t compact tension tes': specimens. The 1/2t
compact tension specimen. are oriented so that
opening of the crack starter notch is facing the top
of the
compartment. This orientation will result in a
neutron flux gradient parallel to *the crack front.The temperature .differential between the specimens
and the reactor coolant is minimized by using spacers
between the specimens and the compartment and by
sealing both sections of the assembly in an
atmosphere of helium.
b. Temperature, Flux, Tension & Charpy Compartment
Assembly
This assembly (Figure 5.3-3) is the same as that inthe precracked Charpy capsule
c ~ Charpy, Flux 6 Compact Tension Compartment Assembly
This assembly (Figure 5.3-4) contains 15 weld metal
impact test specimens and a set of five flux monitors
in the top section. The bottom section contains 10
weld metal 1/2t compact tension test specimens. The
Charpy and compact tension specimens are arranged inthe same manner as in (a) and are surrounded by
spacers to minimize temperature differentials between
the specimens and ~ the reactor coolant.
5.3.1.6.4 Neutron Irradiation and Tem erature Ex osure
Predicted changes in the properties of the reactor vessel
materials are based on data from specimens irradiated to
various fluence levels and in different neutron energy
spectra. In order to permit accurate evaluations of the
radiation induced changes in the surveillance materials,
complete information on the neutron flux, neutron energy
spectra< and the irradiation temperature of the
encapsulated specimens must be available.
5.3.1.6.4.1 Flux Measurements
Past neutron flux measurements are obtained by insertionof thresholds d'etectors into each of the six irradiationcapsules. Such detectors are particularly suited for theproposed application, because their effective threshold
energies lie in the range of interest (0.5 to 15 MeV).
These neutron threshold detectors and the thermal neutron
detectorsI presented in Table 5 '.1-7, can be used tomonitor the thermal and fast neutron spectra incident on
the test specimens. These detectors possess reasonably
long half-lives and activation cross-sections covering thedesired neutron energy range- These neutron thresholddetectors exceed the number required in ASTM E482.
One set of nine flux spectrum monitors and two sets offive flux spectrum monitors are included in each
surveillance capsule- Each detector is placed inside a
sheath which identifies the material and facilitateshandling. Cadmium covers are used for those materials(e.g.< uranium, nickel, copper, and cobalt) which have
ompeting neutron capture activities. The neutron
threshold detectors are placed in holes drilled instainless steel housings (Figure 5.3-3) ~
Xn addition to these detectors, the program also includescorrelation monitors (Charpy impact tests specimens made
from a reference heat of ASTM A533 Bg Class 1> manganese-
molybdenum-nickel steel) which are irradiated along withthe specimens made from reactor vessel materials. The
changes in impact properties of the reference materialprovide a cross-check on the dosimetry in any given
surveillance program. These changes also provide data forcorrelating the results from this surveillance program
with the results from experimental irradiations and other
l
reactor surveillance programs using specimens of the same
reference material..
5.3.1.6.4.2 Tem erature Estimates
Because the changes in mechanical and impact properties ofirradiated specimens are highly dependent on the
irradiation temperature, it is necessary to have knowledge
of the specimen temperature as well as that of the
pressure vessel. During irradiation, instrumented
capsules are not practical for a surveillance program
. extending over the design lifetime of a power reactor.Thus, maximum temperature of the irradiated specimens can
be estimated with reasonable accuracy by including in thecapsule assemblies small pieces of low melting pointalloys or pure metals. The compositions of candidate
. materials with melting points in the operating range ofpower reactors are listed in Table 5.3.1-8. The monitors
are selected to bracket the operating temperature of the
reactor vessel.
The temperature monitors consist of a helix of low melting
alloy wire inside a sealed quartz tube. A stainless steelweight is provided to destroy the integrity of the wirewhen the melting point of the alloy is reached. The
compositions and therefore the melting temperatures of the
temperature monitors are differentiated by the physicallengths of the quartz tubes which contain the alloy wires.
A set of temperature monitors is included in each
surveillance capsule. The temperature monitors are placed
in holes drilled in stainless steel housings as shown inFigure 5.3-3.
-10-
5. 3. 1. 6. 5 Irradiation Locations
The test specimens are enclosed within six capsuleassemblies, the axial positions of which are bisected by
the midplane of the active core. The capsules are
positioned near the inside wall of the reactor vessel so
that the irradiation conditions (fluence, flux spectrum,
temperature), of the test specimens resemble as closely as
possible the irradiation conditions of the reactorvessel. The neutron fluence of the test specimens isexpected to be within 50% of that seen by the adjacentvessel wall, so the measured changes in properties of the
- surveillance materials will closely approximate the
radiation induced changes in the reactor vessel beltlinematerials.
".he capsule assemblies are placed in capsule holderspositioned circumferentially about the core at locationswhich include the regions of maximum flux. Figure 5.3-5presents the exposure locations for the capsule
,assemblies. All capsule assemblies are inserted intotheir respective capsule holders during the final reactorassembly operation.
5.3.1.6.6 Withdrawal Schedule
The capsule assemblies remain within their capsule holdersuntil the test specimens contained therein have been
exposed to predetermined levels of fast neutron fluence.At that time, the capsule assembly is removed and the
surveillance materials are evaluated. Detailedinstructions for the removal of capsule assemblies are
provided for each plant. The;capsule assembly removal
schedule is presented in Tabl» 5.3.1-9. Removal time isin terms of Effective Full Power Years {EFPY). The
I I
capsule withdrawal schedule has been designed toperiodically monitor the effects of neutron irradiation on
the reactor vessel based on the magnitude of the predicted
RT shift and the decrease in upper shelf energy.NDT
Sufficient standby capsules have been provided to enable
monitoring the effects of any major core change< measure
changes resulting from reactor vessel annealing or
evalu'ating a flaw in the beltline materials. Capsules 3<
5g and 6 are scheduled to meet 10CFR50, Appendix H,
monitoring requirements for weld and HAZ material; capsule
3 is scheduled for removal near 254 of design life or
approximately 50F shift (whichever comes first), capsule 6
near 75'5 of design life< and capsule 5 at an intermediate
time. = Capsules 3 and 5 will provide intermediate shellcourse plate data at 25% and 75% of design fluence for the
intermediate shell course. Capsules 1 and 6 will provide
lower shell course plate data at 30% and 75% of design
fluence for the lower shell course. The two remaining
capsules are designated as standby capsules.
Withdrawal schedules may be modified to coincide with
those refueling outages or plant shutdowns most closely
approaching the withdrawal schedule.
Xrradiation Effects on Prediction Basis
The design curve used to predict the radiation induced
increase in transition temperature is shown in Figure
5.3-6. Predicted changes in the transition temperature
are used to select the surveillance materials (Section'.3.1.6') and to formulate the initial heat-up and
cool-down limit curves for plant operation. Once actual
post-irradiation surveillance data becomes available, ~
these data will be used to adjust plant operating limitcurves.
-12-
Figure 5.3-6 was conservatively drawn using the data givenin Table 5.3.1-10 including SA 533-B Class 1 plate and
weld zone material typical of that used in the fabricationof the Palo Ver'de reactor vessel beltline materials. The
curve is applicable for materials with copper contents of0.10 w/o or less, consistent with Palo Verde beltlinematerial specifications, irradiated at 550F + 25F.
-13-
,109A/js C-1I
TABLE 5. 3. 1-1
PALO VEROE UNIT-1
REACTOR VESSEL BELTLIHE PLATES CHEMICAL ANALYSIS
HaterialCode
Element
Intermediate Shell Plates Louver Shel 1 Plates
M-6701-1 N-6701"2 t5-6701-3 H-4311-1 t1-4311-2 tl-4311-3
Si
Hi
Cr
*Ho
V
Cb
TiCo
Cu
Al
B
M
Sb
As
Sn
ZrPb
H2
0. 23 ~
1. 38
0. 005
0,018'.
24
0. 66
0 ~ 06
0. 52
0. 003
<. 01
<. 01
0. 015
0. 07
0. 032
<. 001
<. 01
0.0024
<.001
0.003
<. 001
<. 001
0. 009
0. 23
l. 34
0. 004
0. 017
0. 28
0. 61
0. 05
0. 53
0. 003
(. 01
<. 01
0. 013
0. 06
0. 035
<. 001
<. 01
0. 0016
<. 001
0. 003
<. 001
<. 001
0. 009
0. 23
l. 35
0. 004
0. 016
0. 28
0. 61
0. 05
0. 53
0. 003
<. Ol
(. 01
0. 013
0. 06
0. 037
<. 001
<. 01
0. 0015
<. 001
0. 003
<. 001
(. 001
0. 009
0. 24
l. 48
0. 004
0. 003
0. 22
0. 65
0. 07
0. 51
0. 003
<. 01
<. 01
0. 012
0. 04
0. 026
<. 001
<. 01
0. 014
0. 001
<.001
<.001
0. 014
0. 20
l. 45
0. 005
0. 007
0. 19
0. 62
0. 04
0,530. 001
<. 01
<. 01
0. 011
0. 03
0. 022
<. 001
<. Ol
0. 012
0.001
<.001
<.001
0. 013
0. 22
l. 46
0. 004
0. 005
0. 19
0. 64
0. 05
0. 53
0. 001
<. 01
(. 01
0. 011
0. 03
0. 022
<. 01
<. 01
0. 017
0. 002
<. 001
<. 001
0. 012
- 189A/js 0-
TABLE 5.3.1-
PALO VERDE UNIT-1
REACTOR VESSEL BELTLIHE MELO NETAI (AS OEPOSITEO) CHENICAI AHALYSIS
Seam
Element 141-142C 101-1428 101-142A
Lower Shell Lon . Seams
101-124C 101-1248 101-124A
Intermediate Shell Lon . Seams Girth Seam
Hn
Si
Hi
Cr
Vio'
Cb* ~*
Ti
Co
Cv
Al
As
Sn
ZrPb
Sb
H2
0. 15
l. 29
0. 005
0.006
0. 21
0. 05
0. 03
0. 53
0. 005
<. 01
<. 01
0. 015
0. 03
0. 005
<.001
0. 01
0. 004
0. 001
0. 001
<. 001
<. 001
0. 005
0. 15
l. 32
0. 005
0.006
0. 20
0. 05
0. 03
0. 52
. 0.005'.01
<. 01
0. 015
0. 03
0. 005
<. 001
0. 01
0. 004
0. 001
0. 001
<. 001
<.001
0.005
0. 15
1.36
0. 006
0.006
0. 21
0. 05
0. 03
0. 54
0. 006
<. 01
<.01
0. 016
0. 03
0. 007
<. 001
0. 02
0. 005
0. 00')
0. 001
<. 001
<. 001
0. 006
0. 13
l. 21
0.009
0.007
0. 12
0. 03
0. 02
0. 49
0. 004
<. 01
<. 01
0. 005
0. 02
0. 004
<.001'.
01
0. 007
0. 003
<. 001
0. 01
0. 14
1. 20
0. 01
0.008
0. 14
0. 03
0. 02
0.49
0. 005
<. 01
<. 01
0. 005
0. 02
0. 004
<.001
<. 01
0. 006
0. 002
<. 001
.006
0. 12
l. 24
0. 012
0. 009
0. 13
0. 03
0. 02
0.52
0. 006
<. 01
<. 01
0. 00o
0. 02
0. 004
<. 001
<. 01
0. 006
0. 003
<.001
0.008
0. 11
1. 51
0. 013
0. 009
0. 54
0. 11
0. 16
0. 52
0. 005
<. 01
<. 01
0. 008
0. 02
0. 01
0. 001
0. 01
0. 001
0. 003
<. 001
<. 001
0. 009
0. 013
TABLE 5.3.1-3
PALO VERDE UNIT 1TOTAL QUANTITY OF TEST SPECIM
Base Metal
Type ofS ecimen Orientation
Lower,Shell
Inter-mediateShell
WeldMetal HAZ SRM* Total
Drop Weight
Standard Charpy
Transverse
Lon yitudinalTransverse
12
4269
3663
12
'14
12
6996
36
'147342
Precracked Charpy LongitudinalTransverse
3030
3030 48
60108
ct Tension lt Transverse1/2t Transverse
8„14
814
824
2452
Tension LongitudinalTransverse
1221 18 30
1269
TOTAL 238 199 236 108 69 850,
*Standard Reference Material
L
'ABLE 5.3.1-4
PALO'VERDE UNIT 1TYPE 'AND 'QUANTITY OF 'SPECIMENS FOR 'BASELINE 'TESTS
Base Metal uantity
Type ofS ecimen
LowerOrientation 'hell
Inter-mediateShell
MeldMetal HM SRM" 'otal
Drop Weight
Standard Charpy
Transverse
LongitudinalTransverse
12
2424
18.18
12
1524 '4 57
90
12 36
Precracked Charpy
sion
LongitudinalTransverse
LongitudinalTransverse
1212
1212 12
12
2436
1233
Compact Tension lt Transverse1/2t Transverse
TOTALS
84
120 36 15
2412
324
*Standard Reference Material characterized by HSST Program; provided for correlationwith HSST characterization tests.
TABLE 5.3.1-5
PALO VERDE UNIT 1TYPE AND QUANTITY OF SPECIMENS FOR
IRRADIATION'EXPOSURE 'AND IRRADIATED TESTS
Base Metal uant ity
Type ofS ecimen Orientation
LowerShell
Inter-mediat»Shell
WeldMetal ER,Z SRE1* Total
Standard Charpy LongitudinalTransverse
1845
1845 90 72
54 90252
"..':Precracked Charpy LongitudinalTransverse
1818
1818 36
3672
Tension Transverse 18 36
t Compact Tension Transverse
TOTALS
10
118
10
118
20
72 54 526
*Standard Reference Material
l
.
TABLE 5.3.1-6
PALO VERDE UNIT 1 SURVEILLANCE PROGRAM
CAPSULEASSY. NO.
6TYPE
AZIMUTHALLOCATION
WITHDRAWALSCHEDULE
EFPY *LEAD
FACTOR
SURVEILLANCEMATERIAL
ORIGINS NO.
SPECIMENS
TYPE ORIENTATION
1Pcv
38 8-10 <l.15 1. Base MetalLower Shell PlateM-4311-1 «)
2. Weld Metal(M-4311-2/M-4311-3(c)Weld Wire:B-4 Heat/Lot 90071Flux Linde 0091/1054
3. HAZ MetalLower Shell PlateM-4311-1
4. SRM HSST Plate ul <-)fAK-
159939
315
12
9
Cv'Cv
PCvTension.C
Tension,Cv
PCv
Cv
Trans.Trans.Long'.Trans.Long.
Trans.Trans.
Trans.
Trans.
Lon
43 Standby <1.15 1. Base MetalInter. She)1 PlateM-6701-2(e
2. Weld Metal(b)M-4311-2/M-4311-3Weld Wire;B-4 Heat/Lot 90071Flux Linde 0091/1054
3. HAZ MetalLower Shell Plate M-4311-1(
4. SRM HSST Plate Ol (d)
1510
3
3
15
10
12
Cv4t CTTension.
Tension.Cv
4t CT
Cv
Cv
Trans.Trans.Trans.
Trans.Trans.
Trans.
Trans.
Lon .
*Effective Full Power Years
l
TABLE 5. 3.1-6 (Cont'd)
PALO VERDE UNIT 1 SURVEILLANCE PROGRAM
CAPSULEASSY. NO.
5TYPE
3
PCv
AZIMUTHALLOCATION
137'ITHDRAWALSCHEDULEEFPY
4-5
LEADFACTOR
<1'. 15
SURVEILLANCEMATERIAL
ORIGINS
1. Base MetalInter. Shell PlateM-6701-2 «)
NO.
15993
9
SPECIMENS
CvPCvPcvTensionCv
Trans.Trans.Long.Trans.Long.
TYPE ORIENTATION
4CT
142 Standby <1.15
2. Weld Metal (b)M-4311-2/M-4311-3(
~ - Weld Wire:B-4 Heat/Lot 90071Flux Linde 0091/1054
3. HAZ MetalLower Shell Plate M-4311-1 t
4. SRM HSST Plate Ol(
1. Base MetalLower Shell Plate
2. Weld Metal(M-4311-2/M-4311-3(c)Weld Wire:B-4 Heat/Lot 90071Flux Linde 0091/1054
3. 'AZ MetalLower Shell Plate M-4311-1(a)
4. SRM HSST Plate Ol(
3
15
12
1510
3'
15
10
12
TensionCv
Pcv
.Cv
Cv
Cv4t CTTension
TensionCv
St CT
Cv
Trans.Trans.
Trans.
Trans.
Lon
Trans.Trans.Trans.
Trans.Trans.
Trans.
Trans.
Lon
TABLE 5.3.1-6 (Cont'd)
PALO VERDE UNIT 1 SURVEILLANCE PROGRAM
CAPSULEASSY. NO.
&
TYPE
WITHDRAWALAZIMUTHAL SCHEDULELOCATION EFPY
LEADFACTOR
SURVEILLANCEMATERIAL.
ORIGINS NO.
SPECIMENS
TYPE ORIENTATION
5PCv
230 12-15 <1.15 1. Base MetalInter. Shell PlateM-6701-2 «)
159
3. 9
CvPcvPcvTension.Cv
Trans.Trans.Long.Trans~Lon .
2. Weld Metal(b"M-4311-2/M-4311-3(c)Weld Wire:B-4 Heat/Lot 90071Flux Linde 0091/1054
3
15
9 PCv
TensionCv
Trans.Trans.
Trans.
3. HAZ MetalLower Shell Plate M-4311-1
4. 'RM HSST 01( )
1212
9
CvCv
Trans'rans.
Long.
6Pcv'10 18-24 <l.15 1. Base Metal
Lower Shell PlateM-4311-1(
15993
9
CvPCvPcvTensionC
Trans.Trans.
, Long.Trans.Lon
2. Weld Metal(b)M„4311 2/M 4311 3(c}Weld Wire:B-4 Heat/Lot 90071Flux Linde 0091/1054
3. HAZ MetalLower Shell Plate M-4311-1( )
4. SRM HSST Plate 01( )
TensionCv
9 PCv
12 Cv
Cv
Trans.Trans.
Trans.
Trans.
Long.
0NOTES FOR TABLE 5.3.1-6
'(a) See Table 5.3.1-1 of this FSAR for chemistry of Plate Code
No. M-4311-1 flower shell plates);
~ (b) See Table 5.3.1-2 of this FSAR for chemistry of Plate Code
(c)
No. 101-142 A-C (lower shell long seams).
Surveillance weld metal between plates M-4311-2 6 M-4311-'3
(long seam) .
(d) See ORNL-4315 dated Feb. 1968, for chemistry of SRM
(HSST-Ol Plate).
(e) See Table 5.3.1-1 of this FSAR for chemistry of Plate Code
No. M-6701-2 (intermediate shell plate).
: TABLE 5. 3.1-7
PALO VERDE UNIT-1CANDIDATE*MATERIALS FOR >it:uiRO,~ THRESHOLD DETECTORS
Haterial
Uranium
Sul fur
Iron
t)ickel
'Copper
Titanium
Cobalt
Reaction
0 (n f) Cs1 37
S (n p) P
Fe (n,p) Hn54
Hi (n,P) Co
Cu (n,a) Co60
Ti (n,p) Sc
Co (n,y) Co
Threshold Energy (tleV)
0.7
2.9
4.0
5.0
7.0
8.0
Therm'al
Hal f-Life
30a2 years
14.3 days
314 days
71 days
5.3 years
84 days
5.3 years
1
TABLE 5.3.1-8
PALO VERDE lftfIT-1COHPOSIT) 0th RtfO t)EL fltfG POIt'fTS OF
CANDIDATE HRIEfllRLS FOR TEsii'EltATUf<E VOHXTORS
~ ~
Com osition (Mt%)
80 Au, 20 Sn
90.0 Pb, 5.0 Sn, 5.0 Ag
97.5 Pb, 2.5 Ag
97.5 Pb, 0.75 Sn, 1.75 Ag
Helting TemperatureoF
558
580
~ ~
I
TABLE 5.3.1-9
PALO VERDE UNIT 1CAPSULE ASSEMBLY REMOVAL SCHEDULE
CapsuleAzimuthalLocation
RemovalTime
Base MetalMaterial Included
38
43
137'42
230
310
8-10 EFPY
Standby4-5 EFPY
Standby
12-15 EFPY
18-24 EFPY
Looser Shell PCv
Lowe= Shell CT
Intermediate Shell PCv
Lour Shell PCv
In"ermediate Shell CT
Intermediate Shell PCv
Time in effective full power years (EFPY)
Note: Schedule may be modified to coincide with those refuelingoutages or scheduled shutdowns most closely approximatingthe withdrawal schedule.
TASLE 5.3.1".10~J'ALO
VERDE UNIT-1A5338"CU PLATE AND MELD MATERIAL MITH COPPER CONTENT LES& THAN OR E UAL TO 0.10 w/o
ReferenceData Point
7. 04
7. 05\ 801-8. 01
Material
SA5338-weld
SA5338-weld
SA5338-weld
SA5338-weld
2 ~ 3
2.7
2.0
2.3
Fl ~ence19(n/cm (10) )
.(a) 'b)dfs dfs
1.9
5.0
TransitionTemperature
Increase 'F
88
155
55'
Selectedp
. 020
. 020
.010
. 010
Chemistr
.004
.004
.008
. 008
w/oCv
.10
.05
.05
.05
9. 01
9. 02
9. 05
11. 06
11. 07
11.13
11.14'1.15
11.16- 1 l. 24
11. 25
11. 27
1 l. 28
23. 07
SA5338-plate
SA5338-plate .
SA5338-plate
SA5338-weld
SA5338-weld
SA533S-plate-
SA5338-plate
SA5338-plate
SA5338-plate
SA5338-plate
SA5338-plate
SA5338-plate
, SA5338-plate
SA5338-plate
2.8
2.8
3.1
.5
2.4
;2
2.0
2.0
.5
.5
.52.4.2.4
2.4
2.4
2.7
2.1
.17'2. 18
2. 18
.44
.44
2. 09
2. 09
3.8
40
65
70
80
80
90
35
30
95
35
.008
.008
.008
.005
. 005
.008
.008
.008
.008
. 008
. 008
.008
.008
. 009
.008
.008
.008
. 014
. 014
. 015
. 015
. 015
. 015
. 014
. 014
. 014
. 014
. 017
.03
.03-'. 03
.06
.06'. 09
.09
.09
.09
.09
.09
.09
.09
.09
a. fission spectrum .
b. calculated spectrum
I
TA8LE 5.3.1 "10 {CONT'D)
~ PALO VERDE UNIT"1A5338-CLl PLATE AND MELD MATERIAL WITH COPPER CDNI'ENT LESS'.THAN OR E UAL TO 0.10 w/o
.
Reference0=. a Point Material
Fl)encelg(n/cm (10) )(a) (b)
dfs 'fsTransitionTemperature
Increase 'FSelected
pChemistr w/o)
Cu
23. 08
23. 09
23. 10
23. 11
23. 19
23. 20
23. 21
23. 22
37. 01
37. 02.
49. 11
49.12
59. OI
60. 04
60. 06
60. 07
- SA5338-plate
SA5338-plate
SA5338-plate
SA5338-plate
SA5338-weld
SA5338-weld
SA5338-weld
SA5338-we 1 d
SA5338-weld
SA5338-plate
SA3028-weld
SA3028-weld
SA5338-plate
SA5338-plate
SA5338-plate
SA5338-weld
5.7
4.0
5.4
5.3
4.9
5.0'.9
5.0
2.5
2.5
2;3
6.1
5.0
3.5
4.7
4.6
4.2
4.3
4.2
4.3
.15
.'37
1.6
5.3
4.74.7
55
45
85
65
35
50
15
15
100
0
18
75
75
65
15
.009
.011.
. 011
. 009
'.010
. 010
.004
.004
.002 .
. 003
. 012
. 012
.008
. 010
.007
. 005
. 017
. 018
. 018
. 017
. 010
. 010
. 010
. 010
. 008
. 014
. 017
. 017
. 008
. 012
.011
. 010
.09
.09
.09
~ 02
.07
.07 .
-. G5
.05
.09
.G9
.01
'.Ol.03
.04
.05
.03
'REFERENCES FOR DATA POINTS IN TABLE 5.3.1-10
7. HSST Semi-Annual Progress Report Period Ending Feb. 29, 1972, ORNL-
4816.
8. Hawthorne, "Radiation Resistant Weld Metal for Fabricating A533-B
Nuclear Reactor Vessels", Welding Journal, July 1972, p. 360-S.
9. Hawthorne, "Demonstration of Improved Radiation EmbrittlementResistance of A533-B Steel Through Control of Selected Residual
Elements," NRL Report 7121, January 1970.
ll. Hawthorne, "Trends in Charpy-V Shelf Enc rgy Degradation and YieldStrength'ncrease of Neutron-Embrittled Pressure Vessel Steels", NRL
Report 7011, Dec. 22, 1969, and NRL Repcrt 6772.
23. Hawthorne, Koziol, "Evaluation of Commercial Production A533-B
Plates and Weld Deposits Tailored for Iriproved RadiationEmbrittlement Resistance," ASTM STP 570, 1975, pp. 83-102.
37. Steele, "Irradiation Effects on Reactor Structural Materials," NRL
Report 2027< August 1969.
49. Kass, "Radiation Effects in Boiling Water Reactor Pressure Vessel
Steels," NEDO-21708, October 1977.
59. Hawthorne, "Further Observations on A533-B Steel Plate Tailored forImproved Radiation Embrittlement Resistance," NRL Report 7917, Sept.
22'975.
60. Hawthorne, "NRC-CE-NRL Cooperative Program: Series 3 (Extra Lower
Copper) Materials Evaluations," NRL/NUREG MR 3512, May 1977.
~Lock Assembly
Charpy and FluxCompartment Assembly .
orCharpy, Flux, andCompact TensionCompa rtment Ass embly
M!edge Coupling Assembly
Cor necting Spacer
"Temperature, Flux,Tension and CharpyCompa rtment Ass embly
Charpy and FluxCompa rtment Ass embly
orCharpy, Flux, andCompact TensionCompa [%ment Ass embly
AR IZONAPUB L I C SE R V ICE CO.
Palo Verde StationUnit 1
SURVEILLANCE CAP S ULE ASSEMBLY
V/edge Coupling - End Cap
I
II
l
Charpy Impact.Specimens
Flux Monitor Housing
\
Precracked (:harpyandlor Charpy ImpactSpecimens
'
Connecting Spacer
Space rs
Rectangul ar Tubing
Wedge Coupling - End Cap
" ARIZONAPUBLlC SERVICE CO
Palo Verde StationUnit 1
CHAPiPY AND FLUX COMPARTMENT ASS EMBLYFigure
5. 3-2
" .'IIiedge Coupling = End Cep
Tension Specimens.and Tension SpecimenHousing
Cha rpy Impact Specimens
QonllectIng Spacer ——-
/Lid monitor i-lousIng ----
|
Stainless Steel---fubingTh reshold --.
Pe<ec<or
Ptqx Spectrum Monitor
Temperature Monitor ..
Temperature Monitor .
Hqgsing .
~ Flux Spectrum MonitorCadmium Shielded
Stainless Steel TubingCadmium ShieldThreshold Detector
Quartz Tubing
~Weight
Lomb Melting Alloy
Ch,argy Impact$ pqcimens
R;ton.g u I,'qr"Tu bi:ng--
o I
Tension Specimens andTens ion Speci.men
.H.ous.i.ng
Wedge Coupling-'EncL Cap
AR IZONAPUBLIC SERVICE QO.
Pj)q;Verde StjtjonLJnit 1
TEMPERATURE, Fl'UX'ENS'TON'AND CHA'RPY.CGMPARTM NT ASSEMBLY
'igure5 ~ 3 3
l
Vfedge Coupling — End Cap
I
I
I
III
I
Cha ryy ImpactSpec~ mens
I
Flux Monitor Housing~ -.I
1/2 t Compact TensionSpecimens
Connecting Spacer
'pacers
Rectangul ar Tubing
Wedge Coupling - End Cap
AR IZONAPUB LIC SERVICE CO.
Palo Verde Station,Unit 1
CHARPY FLUX AND COMPACT TENSIONCOMPA RTMENT AS S EMBLY
Figure
5.3-4
TJ
0(o>Cn o)>2.o. >~N~n Wp~R(Q~o>
. lTI
o Op
VESSEI137o
100
VESSEL' ~OUTI ET NOZZI E147o r
rVESSEL
Y ~ - . INLETr i NOZZLE
r
1 r COHL SI IPOUD
~ ——-CORE SUPPORT BARREL Ij
I
Z IC)
OZ
(/)VlmV3I
Vl
4l Q7Cn
~ nEACT<iR VESSEL
I1/
C
I I
/'I (I Il
0o
VESSEL„o
VESSEL
38'NLARGED
PLAN VIEW
VESSEL310o
CORE
REACTORVESSEL
ELEVATIONVIEW
VESSELCAPSULEASSEfilBLY
CORESUPPORTBARREL
J
200
0I- 150K
. K'D
h 100
z0I-cn '50
0
CD
o~0
QO
0
1018 10'gNEUTRON F LENCE, n/cni (E)1MeV)
1 020
D A533B-C1 1 PLATE
Q-tNELD METAL
NOTE: DATAPOINTS ARE DEFINED BY TABLE 5.3.1-10
AR IZONAPUBLIC SERVICE CO.
Palo Verde S:ationUnit 1
TRANSITION TEMPERATURE SHIFT FOR PLATE AND WELDMETALCONTAINING =.0.10 W/0 COPPER
Figure
5.3-6
l J
109A/gs"13
5.3.1.7 Reactor Vessel 8 Other RCPB Fastener
See CESSAR Section 5.3. 1.7
In addition:
Fracture toughness and Tensile test data for Reactor Vessel closure headbolting for Palo Verde Unit-1 is presented in table 5.3. 1.7-1.
Fracture toughness and Tensile test data for all other fasteners used inthe Reactor Coolant Pressure boundary for Palo Verde Unit-1 are presentedin tables 5.3.1.7-2 and 5.3.1.7-3.
Fracture toughness and Tensile Test data for RCPB 8 fasteners for PaloVerde Units 2 6 3 will be provided at a later date.
189A/js E-'
TABLE 5.3.1.7-1
PALO VERDE UNIT-1
FRACTiURE TOUGHNESS DATA
"REACTOR VESSEL FASTENERS
MaterialCode No:
M-6720-1
M-6720-1
Ye-6720-1
M-6720-1
Mi-6720-0
M-6720-1
M-6720-2
.Yi-6720-2
Yi-6720-2
M-6720-2
M-6720-2 .
e>i-6720-2
M-6720-2
M-6720-2
M-6720-2
M-6720-2
Yi-6720"3
M-6720-3
M-6720-3
MaterialS ecification
SA540-GRB-24-CL3
SA540-GRB-24-CL3
SA540-GRB-24-CL3
SA540"GRB-24-CL3
SA540-GRB-24-CL3
SA540-GRB-24-CL3
SA540-GRB-24-CL3.
SA540-GRB-24-CL3
'A540-GRB-24-CL3
SA540-GRB-24-CL3
SA540-GRB-24-CL3
SA540-GRB-24"CL3
SA540-GRB-24-CL3
SA540-GRB-24-CL3
SA540-GRB-24-CL3
SA540-GRB-24-CL3
SA540-GRB-24-CL3
SA540-GRB-24"CL3
SA540-GRB-24-CL3
Location .
Closure Head Studs
Closure Head Studs
Closure Head Studs
Closure Head Studs
Closure Head Studs
Closure Head Studs
Closure Head Studs
Closure Head Studs
Closure Head Studs
Closure Head Studs
Closure Head Studs
Closure Head Studs
Closure Head Studs
Closure Head Studs
Closure Head Studs
Closure Head Studs
Closure Head Studs
Closure Head Studs
Closure Head Studs
Tube/BarNo:
479-00
479-01
482-00
482-01
485-00
485-01
462-00
462"ply463-00
463-01
470-00
470-01
472-00
472-01
475-00
475-01
623"00
623"OI
624"00
Pre-Load~Tem F
«lp(a)«10(a)
.lo(')+1O(a)
«1 p(a)
«lp(a)«Ip(a)+10(a)
10(a)
«10(a)
«10(a)
«10(a)
+lo(').lo(')«10(a)
+lo(')«10(a)
«10(a)
1p(a)
Yield~STR KSI
136. 2
'140. 0
140. 2
145. 0
144. 5
143. 0
133. 7
135. 5
142. 7
142. 2
145. 0
141. 2
141. 0
133. 2
141. 0
137.0
142.5
143. 5
135. 0
Ultimate~STRIKSI
- 154.0
157. 5
156. 5
160. 0
158. 5
158. 0
'I48. 0
151. 0
158. 5
157. 0
160. 0
156. 0
156. 0
149. 0
155. 0
152. 0
156. 0
157. 5
150. 0
7 C'
TABLE 5.3.1.7-1 (Cont'd.)
PALO VERDE UNIT-1
FRACTURE TOUGHNESS DATA
"REACTOR VESSEL FASTENERS (Cont'd.)
MaterialCode No:
MaterialS ecification Location
Tube/BarNo:
Pre-Load~Tee F
Yield~STR KSI
Ultia'ate~STR KSI
M-6720-3
M-6720-3
M-6720-3
!
M-6720-4
M-6720-4
M-6720-4
M-6720-4
M-6720-4
M-6720-4e
M-6720-4
M-6720-4
MI-6720-4
H-6720-4M-6720-4
M-6720-41
M-6720-5
Mi-6720-5
M-6720-5
M-6720-5
SA540-GRB-24-CL3
SA540-GRB-24-CL3
SA540-GRB-24-CL3
SA540-GRB-24-CL3
SA540-GRB-24"CL3
SA540-GRB-24-CL3
SA540-GRB-24-CL3
SA540-GRB-24-CL3
SA540-GRB-24-CL3
SA540-GRB-24-CL3
SA540-GRB-24"CL3
SA540-GRB-24-CL3
SA540-GRB-24-CL3
SA540-GRB-24-CL3
SA540-GRB-24-CL3
SA540-GRB-24-CL3
SA540-GRB-24-CL3
SA540-GRB-24-CL3
SA540-GRB-24-CL3
Closure
Closure
Closure
Closure
Head Studs.
Head Studs
Head Studs
Head Studs
Closure Head Studs
Closure Head Studs
Closur'e Head Studs
Closure Head Studs
Closure Head Studs
Closure Head Studs
Closure Head Studs
Closure Head Studs
Closure Head Studs
Closure Head Studs
Closure Head Studs
Closure Head Studs
Closure Head Studs
Closure Head Studs
Closure Head Studs
624-01
628-00
628-01
633-00
633-01
635-00
635-01
639-00
639-01
643-00
643-01
649-00
649-01
650-00
650-01
556-00
556-01
557-00
557-01
10(a)
+1 0(a)
10(a)
+lp(a)+10(a)
10(a)
+10(a)
+1 p(a)
10(a)
+10(a)
+lp(a)lp(a)
+10(a)
+) 0(a)
+10(')+10(a)
+10(a)
.10(')
.10(')
137. 5
135. 3
139. 5
130. 0
137. 5
132. 0
132. 5
131. 5
134. 8
131. 3
131. 0
131. 5
132. 0
134. 2
133. 5
138. 3
136. 0
139. 7
152. 0
150. 0
155. 0
147. 0
154. 0
149. 0
149. 0
148. 0
150. 0
'48.0149. 0
149. 0
149. 0
150. 0
150. 0
'1 54. 0
153. 0
155. 0
140.0 ~ 156.0
C f
t
t
t
f
189A/js E-
TABLE 5.3.1.7-1 (Cont'd.)
PALO VERDE UNIT"1
FRACTORE TOVGHNESS DATA
"REACTOR VESSEL FASTENERS (Cont'd.)
HaterialCode No:
H-6721-1
M-6721-1
l"-6721'"1
14-6721-1
H-6721-1
H-6721-1
M-6721-1
Ys-6721-1
N-6721-1
H-6721-1
MaterialS ecification
SA540-GRB-23-CL3
SAS40-GRB-23-CL3
SA540-GRB-23-CL3
SA540-GRB-23-CL3
SA540-GRB-23-CL3
SA540-GRB-23-CL3
SA54o-GRB-23" CL3 .
SA540-GRB"23-CL3
SA540-GRB-23-CL3
SA540-GRB-23-CL3
Location
Closure Head Nuts & Mashers
Closure Head Nuts & Mashers
Closure Head Nuts & Mashers
Closure Head Nuts & Mashers
Closure Head Nuts & Mashers
Closure Head Nuts & Mashers
Closure Head Nuts & Mashers
Closure Head Nuts & Mashers
Closure Head Nuts & Mashers
Closure Head Nuts & Mashers
Tube/BarNo:
156-00
156-01
157-00
157-01
161-00
161-01
163-00
163-01
165-00
165-01
Pre-Load~Tee 'F
+lo(')+lo(')
10(a)
+1 0( a)
10(a)
+1 0(a)+.0(a)
+10(a)
+10(a)
+lo(')
Yield~STR Kc1
143. 0
146. 0
148. 0
147. 0
148. 0
145. 7
144. 5
148. 5
155. 5
154. 7
Ultimate~STR KST
156. 0
158. 5
160. 0
159. 5
160. 0
158. 0
157. 0
160.0.
167. 0
165. 5
(a) Determined per applicable ASIDE-BPV Code 8 Addenda, Sect III, Subsection NB, Article NB-2333-A (dia. over 4.0")Piece Numbers Reference Drawing
Studs Nuts Mashers ~ Number
179-'301 179-3401 179-3402 E-78173-161-004-02
C t
l
'89A/js E-
MaterialCode Ro:
ltateri alS ecification
TABLE 5.3.1.7-2
PALO VERDE. UNIT"1
FRACTURE TOUGHNESS DATA
Location
t PRESSURIZER", STEAM GENERATORS 1"" & 2""" MAHMAY
Tube/BarHo:
FASTENERS
Pre-Load~Tee F
Yield~STR KST
Ultimate~STR KST
HS-306-1
MS-306-1
MS-306-1
MS-314-1
Yi5-314-1
HS-314" 1
HS-314" 1
HS-314-1
MS-314-1
MS-314-1
HS"314-.1
YiS-314-1
MS-314-1
HS-314-1
MS-314-1
MS-314-1
MS-314-1
HS-314-1
HS-314-1
SA193"GRB7
SA193-GRB7
SA193-GRB7
SA540-GRB-24-CL3
SA540-GRB-24-CL3
SA540-GRB-24-CL3
SA540-GRB-24-CL3
SA540" GRB-24"CL3
SA540-GRB-24-CL3
SA540-GRB-24-CL3
SA540-GRB-24-CL3
SA540-GRB-24-CL3
SA540-GRB-24-CL3
SA540-GRB-24-CL3
SA540-GRB"24-CL3
SA540-GRB-24-CL3
SA540-GRB-24-CL3
SA540-GRB-24"CL3
SA540-GRB-24-CL3
Nuts 8 Mashers
Huts 8 Mashers
Nuts 5 Mashers
Studs
Studs
Studs
Studs
Studs
Studs
Studs
Studs
Studs
Studs
Studs
Studs
Studs
Studs
Studs
Studs
1A
18
lc
71-00
71-01
217-00
217" 01
237-00
237"01
43-00
43-01
70-00
70-01
69-00
69-01
204-00
204-01
208-00
40(b),4,(b)-.40(b)
lp(b)10(a)
+1 p(b)
+lp(b)lp(b)
+10(b)
lp(b)
+1 p(b)
+10("+10(b)
10(b)
+10(b)
+1 p(b)
10(b)
lp(b)lp(b)
128. 5
135. 0
128. 5
150. 0
149. 0
150. 7
148. 2
147. 2
150. 0
N/R
N/R
H/R
H/R
N/R
N/R
N/R
H/R
H/R/
143. 5
151. 0
145. 0
162. 5
162. 0
161. 0
159. 0
159. 0
162. 0
H/R
N/R
N/R
N/R
N/R
N/R
H/R
H/R
N/R
1
C
MaterialCode No:
MS-314-1
MI5-314-1
Mate~ialSDecification
SA540-GRB-24-CL3
SA540-GRB-24"CL3
Studs
Studs
LocationTube/Bar
No:
208-01
240-00
TABLE 5.3. 1.7-2 (Cont'd.)
PALO VERDE UHIT-1
FRACTURE TOUGHNESS DATA
f PRESSURIZER~, STEAM GENERATORS l~~ 8I 2"+" MAWAY
H/R
H/R
FASTENERS (Cont'd.)
Pre-Load Yie'ldT~ee 'I — ~STR KSI
10(b)
+10{')
Ultimate~STR KSI
H/R
H/R
""Steam Generator Ol
"""Steam Generator 82
(b) Determined per applicable ASME-BPV Code 8 Addenda, Sect III, Subsection NB, Article NB-2333-A {dia 1"-4" incl)Note: Since the same material lot was used for Pressurizer K| Steam Generators (Units 1 8 2) Primary Manways listed below
are the respective Piece Numbers 8 Reference Drawing Numbers.
. Piece Number Reference Drawing
Huts 8'shers Studs Number
"Pressurizer „ 676-3101 676-3301 E-78373-661-002"03
276-3901 = 276-3501 E-78273-261-003-03
276"3901 276-3501 E-78273-361-003-02
H/R Not required
189A/js E- "
TABLE 5.3.1.7"3
PALO VERDE UNIT-1
FRACTURE TOUGHNESS DATA
REACTOR COOLANT PUMPS (FASTENERS)
(DATA TO BE SUBMITTED AT A LATER DATE)
MaterialCode No:
MaterialLocation
Tube/BarNo.
Pre-Load~Tee eF
Yield~STR KSI
Ultimate~STR KSI
I
5.4. 2.4 Steam Generator fiaterials
See CESSAR Section 5.4.2.4
In addition:
Fracture toughness data for the primary side of Steam Generators Units 1 8
2 for Pa'lo Verde Unit-1 are presented in Section 5.2.3.3. 1.
Fracture toughness data for the Secondary Side of Steam Generators Units 1
8 2 for Palo Verde Unit-1 are presented in Tables 5.4.2.4-'1 through 9. (Tobe provided at a later date).
Similar data for Palo Verde Units 2 5. 3 will be provided at a later date.
189A/js B-~~
Seam ¹
'ABLE 5.4.2.4-3
FRACTURE TOUGHNESS DATA FROM WELD YiETAL CERTIFICATION TESTS
PALO VERDE UNIT-1
STEN< GENERATOR SECONDARY SIDE ¹1
(DATA TO BE PROVIDED AT A LATER DATE)
Sean Ncmenclature Meld Filler Lot ¹ NDT < '>
189A/js A-
TABLE 5.4.2.4-2
FRAC1URE TOUGHNESS DATA
PALO VERDE UNIT-1
STEAM GENERATOR 8'1 SECONDARY SIDE (FORGINGS)
(DATA TO BE PROVIDED AT A LATER DATE)
PieceNumber
Reference~0vawin 00:
Mater ial Materi alLocation
Dropweight RTNDT ( F)NDT oF
0 180 0 180
189A/js A-
TABLE 5.4.2.4-1
FRACTURE TOUGHNESS DATA
PALO VERDE UNIT-1
STEAM GENERATOR 81 SECONDARY SiDE (PLATES)
(DATA TO BE PROVIDED AT A LATER DATE)
Piece .
Nu;..herReference
~Dvawin No:Material Material
Location
Drop~eight~NDT ( F
RTNDT { F)
I
189A/$ s F-Qr
TABLE 5.4.2.4-4
FRACTURE TOUGHNESS DATA FROM MELD PROCEDURE QUALIFICATIONTESTS
PALO VERDE UNIT"1
STEAM GENERATOR SECONDARY SIDE ¹1
(DATA TO BE PROVIDED AT A LATER DATE)
SeanNu ober
Detailed Meld Meld Procedure~HDT oF "
NDT
Meld Filler Materials Joined HAZ HAZ WeldHaterial Lot ¹ Material 1 Hateria1 2 1 2 QFF
C
18SA/js H-
TABLE 5 ~ 4.2.4-5
PALO VERDE UNIT-1
FRACTURE TOUGHNESS DATA
STEAM GENERATOR 82 SECONDARY SIDE (PLATES)
(DATA TO BE PROVIDED AT A LATER DATE)
PieceNua:her
ReferenceDrawin No.:
MaterialCode No:
MaterialS ecification Location
Drop Weight RT
~NDT F
189A/js H-
TABLE 5.402.4-6
FRACTURE TOUGHNESS DATA
PALO VERDE UNIT-1 =
STEAM GENERATOR 02 SECONDARY SIDE (FORGINGS)~t
(DATA TO BE PROVIDED AT A LATER DATE)
PieceDu-,.bee
ReferenceD"oM1htM Nu:
Matei ial.Code No: .
MaterialS ecification Location
Drop Weight: ~DDT F).' 180
RTNDT ( F)
0 100
L~
189A/js B- "'ABLE5.4:2.4-7
FRACTURE TOUGHNESS DATA FROM WELD METAI CERTIFICATION TESTS
PALO VERDE UNIT-1
STEAM GENERATOR SECONDARY SIDE 02
(DATA TO BE PROVIDED AT A LATER DATE)
Seam 8 Seam Nomenclature Meld Filler Lot 0'TNPT ( F)
189A/js F-M
TABLE 5.4.2.4-8
FRACTURE TOUGHNESS DATA FROM MELD PROCEDURE QUALIFICATION TESTS
PALO VERDE UNIT"l
STEAM GENERATOR SECONDARY SIDE ¹2
(DATA TO BE PROVIDED AT A LATER DATE)
~Ropy op RTgpySeam Detailed Meld Meld Procedure Weld Filler Materials Joined HAZ HAZ h'eld
iH-
fiK
H
I
i
t
1
189A/js E
TABLE 5.4.2.4-9
~ FRACTURE TOUGHNESS DATA
PALO VERDE UNIT-1
STEAN GENERATORS 1 Ec 2 SECONDARY SIDE FASTNERS
(DATA TO BE PROVIDED AT A LATER DATE)
0
materialCode No:
HaterialS ecification Location
Tube/BarRo:
Pre-Load Yield~Tem 'T ~STR KSI
Ultinate~STR KSI
t