i. introduction ii. radiation safety department

c

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PALISADES NUCLEAR PLANT HEALTH PHYSICS ISSUES

STEAM GENERATOR REPLACEMENT PROJECT AGENDA

MAY 2, 1990

I. INTRODUCTION

II. RADIATION SAFETY DEPARTMENT ORGANIZATION

III • RADIATION PROTECTION PROGRAM

.. A. Program Parameters

B. Operational Health Physics

c. A LARA

D. Traininq

E. Radioactive Waste

F. Decontamination

IV. CONTAINMENT OPENING - HVAC

V. OLD S.G. REMOVAL, HANDLING, AND TRANSPORT

VI. OLD S.G. STORAGE

VII. SELF ASSESSMENT

VII~ DRY FOEL STORAGE

A.,--. 2-

..

• SGRPOUTAGE

RADIOLOGICAL SERVICES ORGANIZATIONAL CHART ·

04390

...._ _ ____.~ - - - - - ~R~~ - - - - - 4.__ __ .....i RADIOLOGICAL SERVICES PROJECT RADIATION

MANAGER PROTECTION MANAGER

•

PL.~NT TRAINING PROJECT

I ~---i---CJ ALARA ALARA

COORDINATOR ALARA COORDINATOR I

ENGINEERING

PLANT PROJECT

0-RAnloLoGrc'AL "MATERIAi.ScONiiOi. 0 AD:MINIS1RA TOR

- - - -

AUX CL I SIG~ CTMTCL . CAFCL

• ' PALISADES STEAM GENERATOR REPLACEMENT PROJECT

ASST PROJ MGR JO~IS•

ORGANIZATION

PROJECT MANAGER D W JOOS

..------------..------------+------------,·····························································

ROJECT ADNIN/CONTROL M C SNIEGOWSIU

COST C LARNER••

SCHEDULE M DAVIS•

SCHEDULE TECH F DeBOURBON •

RECORDSIADlllH P LUNDELL•

SECRETARY J VANDENBERG •

OFFICE CLERK J WESNER•

'11lAINING D MORGAN•

'l1lAININO P RIG<rZZI

• CONTRACT PERSONNEL .. PERSONNEL ON LOAN

RAD PROTECTION M L LESINSKI •

Al.ARA ENGINEER K BARR•

RADWASTE ENGINEER M CERNY•

'IBAINING ENGINEER D ELDRIDGE•

RP OPERATIONS D DINGER•

SIU: COORDINATOR JS RIDLEY

Sl'lll COORDINATOR K SCHNEIDER

~

UCENSING ENGR AND CONSTR QUAUTY ASSURANCE J L KUENIN •• W CIARK •• K E MARBAUGH ••

UCENSING ENGINEER QA ENGINEER S SCHOWENWEISNER • P PAPAIOANNOU RC HIRZEL •

MECH ENGR QA ENGINEER T NcELROY • II L HIRZEL •

CIVIL ENGR QA ENGINEER K CHAO•• II R SMITH•

ENGINEER QA ENGINEER G DAVIS•• JD HESS•

ENGINEER QA ENGINEER C JOHNSON•• J E WERNER••

ENGINEER SENIOR OFFICE CLERK H MORGAN• DJ HOFFMAN

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'Yl/90

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BECl-ITEL ALARA LIAISONS

•SHIFTLY COMMUNICATION AND INFORMATION FOR CONSTRUCTION AND RSD

•PERFORM ALARA COORDINATION MEETINGS FOR UNIQUE WORK EVOLUTIONS

•BPCo CRAFT ALARA ORIENTATION

•INITIAL VvORK PACKAGE INPUT AND REVIEW

•ENSURE SEQUENCE OF EVENTS INCLUDED IN WORK PACKAGES

,.

•PROVIDE INPUT FOR MAN-REM ESTIMATES AND RWP GENERATION

.,

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e===::;=~=:":::::::::==:a;::::iENGikEERING J:OR SPRING OUTAGE •

! . I • IENGINE~RING FOlf FALL OUJAGE • I

• I

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1 : IREPLAC~MENT S/li MODIFICATION HO~K : •

--------------,OLD SIG INTERIM STORAGE BLDG CO'NSTRUCTIQN . . r-___. ____ ...,S(CURITY Bl.DG MODincATION~

.__ __ __.!RETAINING :HALL CONSTRUCTION

--------lCONTAINMENT ACCESS FACILIJY CONSTQCTION •

.___ __ _.ISPRlNG OUTAGE (S/G REPLACEMENT PREP HPRK)

::===::=====:::====~AUL ROAD. CONSTRUCTION

..

tSTART F~LL (S/G hEPLACEMtNT) OUT~GE

tF.UEL OFFLbAO COMPl.ETE

tPCS SYST£M RELEA~EO TD CONTRACTOR:

t~UTTING CONTAINM(NT OPENI~G COMPL~TE

• CJRIG:OLD S/G:s OUT oF:coNTAIN~ENT 0

RIG NEM SIG'S IN10 CONTAiNMENT Cl . . • RIG. FITUP. HELO f! NOE PCS. ELBOWS -' ---

INSTALL LINER ~L. PLACE.CONCRET( & INSTAJ_L TENDON I , I

PCS WORK COMPLETE t RELEASED t

• CORE R£LOAD COfl!PLETE O

PERFORk ILRT/C~TMT SIT .c:J

REACTOR CRif ICAL o • PLANT ON LINE t . .

PALIS DES STEAM GENERATOR REPLACEMENT.PROJECT .._ ___________ ..__ _________ __._ _ __... ________ ...:...., ___ '"'"3.11t i ef I

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REPLACEMENT STEAM GENERATOR IMPROVEMENTS

•BETTER SLOWDOWN (minimize future sludge lancing)

•BETTER TUBE SUPPORTS (minimize denting) -Horizontal Grid - Egg Crate -Vertical Grid -Batwing Strips

•HANDHOLES

-4, 6 n on lower and intermediate shells for inspecti'ons

•INSPECTION PORTS

· -2, 2" above tubesheet secondary face

•RECIRCULATION AND CHEMICAL CLEANING NOZZLE ~

-For recirculation of secondary water -For circulation of chemical cleaning fluid

•BIGGER MANWAYS

-All 18" inside diameter

•SURFACE PRETREATMENT

STEAM GENERATOR

REPLACEMENT

PROJECT

RADIATION PROTECTION

PROGRAM ,•

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STANDARDS

•:MEET REQUIREl\fENTS OF 10CFR20

•FOLLOW GUIDELINES IN NRC REGULATORY GUIDES 8.8 AND 8.10

•FOLLOW GUIDANCE PROVIDED IN:

-CPCo Radiation .Safety Plan

o Palisades Plant Health Physics procedures

-Project Plan

o Project Radiation Safety Plan o Project specific procedures and plans

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MANAGEMENT GUIDELINES FOR PROGRAM DEVELOPMENT

•MINIMIZE 11\.fPACT ON PLANT MANPOWER AND FACILITIES

•MINIMIZE CHANGES TO THE EXISTING PROGRAMS

•MAXIMIZE COMMUNICATION AND INTEGRATION OF PROJECT, PLANT AND REPAIR CONTRACTOR

•UTILIZE LESSONS LEARNED FROM PLANT OPERATIONS, PAST SGR PROJECTS, AND PAST NRC CONCERNS

-· ~

•PROVIDE AS A MINIMUM, STANDARD PALISADES RADIOLOGICAL PROTECTION SERVICES

•

GOALS

•l\1INIMIZE RADIATION EXPOSURE TO WORKERS AND THE PUBLIC

•MINIMIZE PERSONNEL CONTAMINATIONS

•MINIMIZE SPREAD OF CONTAMINATION

•MINIMIZE GENERATION OF RADIOACTIVE WASTE

•MINIMIZE SCHEDULE IMPACT DUE TO RADIOLOGICAL CONCERNS

•MAXl1\1IZE POSITIVE LONG TERM EFFECTS ON PLANT AND PROGRAMS ,

• MEEllNGS/INTERFACE

•RSD PLANT AND PROJECT

-Weekly RSD Staff -Daily Shift Turnover -Monthly/Weekly Project ALARA Committee -Monthly/Bimonthly SGRP Planning -Weekly Pre-Outage Readiness -Monthly Plant ALARA Committee

•BECHTEL/SGRP

· -Plan of the Day - prior to each shift -Weekly Schedule - 4 week look ahead -Weekly Action Item -Monthly Project Status

•PLANT/SGRP

-Plant Status - each morning or shift -Daily Schedule ... each afternoon

" -Outage Management - weekly

SGRP LESSONS LEARNED

•MOCK-UP TRAINING

-Mock-up on more job evolutions -More aggressive mock-up needed

•CLEANLINESS

-Must be stringently maintained -Internal piping, cavity, work areas, etc. -Cleanliness training required

•RADIOGRAPHY

-Radiography plan drafted for control -Communication between RSD and radiographer

•COMMUNICATIONS

-Wireless headsets -Closed circuit television . ,,

-Portable radios

•DEDICATED TECHNICIAN COVERAGE

" -Workers report to Crewleader prior to entry -Coverage technicians know when workers entering area -Dedicated technician familiar with area work -Maximizes coverage efficiency and consistency

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COOK VS PALISADES

•DUAL UNIT SITE

•PROCEDURE REWRITE

•ONSITE NVLAP ACCREDITATION JN-PROCESS

•RADWASTE FACILITIES NEEDED

•RECENT SWITCH TO OFFSITE LAUNDRY

•SINGLE UNIT SITE

•NO PROCEDURE REWRITE

•ONSITE NVLAP DOSIMETRY AVAILABLE ·

•RADWASTE HANDLING FACILITIES ADEQUATE

•OFFSITE LAUNDRY ALREADY IN USE

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0. AH . f

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• • SGRP COMPARISON OF

~

PEAK RADIATION SAFETY STAFFING Point HB DC Palisades* Beach Robinson Cook Contractor House

Health Foreman & Leads 6 3 10 [f_ Physics ·Seniors 32 70 53 99 Juniors & Access 32 33 41 24 Control

Totals 70' 106 . 104 138** (103)

Dosimetry Technicians 15 4 3 Clerks 36 2 8

Totals 36 17 15** (11)

Dec on Foremen 4 2 Technicians 52 35 60

Totals 56 37 60**

' (45)

*Projected Numbers-**At peak staffing, 75% will be dedicated to SGRP (#)

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- --- ------ ------------------

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• • SGRP COMPARISONS

' HP PORTABLE SURVEY INSTRUMENTS

Point DC Beach Cook Palisades*

Dose Rate Instruments

R0-2 0 23 25

R0-2A 10 15 12

Teletector 6 10 20

Gamma Survey Instruments 8 10 (15)

Total 24 58 57 (15)

Air Samplers

High-Vol Grab Samplers 7 15 15

Lo-Vol Continuous Monitors 12 17 12

Total ... 19 32 27 '·

*Will be used for SGRP and balance of Plant (emergency use instruments only)

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SGRP c·oMPARISONS HEAL TH PHYSICS INSTRUMENTATION

I '· Point DC

I Beach Cook Pa 1i sades ""

Contamination Monitors

PCM-18 0 5 4

Portable Friskers 20 30 49*

Count Room Instruments

Gros~ B-G Counter 3 3 2

Gross 12 Counter 0 0 2

Alpha Scintillator 3 1 2*

Gamma Spectrograph 1 1 2*

Area Radiation Monitors

Remote Monitors 1 4· 4 ..

*Will be used for SG"RP and Balance of Plant <.

• SGRP COMMUNICATIONS

•WIRELESS HEADSETS

-Radiation Safety Technician use

-Reliable communication within containment

oCrewleader to job cov~rage technicians o Between dedicated technicians

-Inside to outside containment communication

o Access control to Crewleader oCount room to job coverage technicians

•CLOSED CffiCUIT TELEVISION (CCTV)

-ALARA tool

-Aids in continuous coverage of high dose jobs· ,·

-Aids in monitoring long term jobs

o Automatic cutting o Automatic welding

•HAND HELD RADIOS

-Communication between BPCo and RSD

, -Necessary for multi:msource radiography

••

ELECTRONIC DOSI ETRY / WITH COMPUTER INT RFACE

•WHAT IS IT?

" -Secondary dosimeter . -LED displays accumulated dose and dose rate -Accumulated dose and dose rate alarms

•WHAT DOES IT DO?

-Automatically rezeroes -Sets dose alarm from computer margins or def a ult setting

-Sets dose rate alarm from RWP or default setting -Instantly updates MIS computer for personnel dose on entry

-Stores total accumulated dose and highest dose -rate seen

•HOW DOES IT WORK?

-Worker inserts dosimeter into reader . ,.

-Enters SS no. and RWP no. "

•WHY USE ELECTRONIC DOSIMETRY?

"-Alarming capabilities -More easily read than pocket ion chambers -Instant ~omputer updating aids dose tracking and personnel dose reporting ·

-Minimizes dosimeter discrepancies

AIRBORNE CONTR.OL

• •DECONTAMINATION

-Initial Containment -On-going -Tool(Equipment

•CONTAINMENTS

-Pipe Cutting -Pipe End Decon -Fi ltr ati o n/Venti I ati on

•RESPIRATOR

-Fit Test -MPC Tracking

•AIR SAMPLING

-CAM -Grab

• MAN-REM ESTIMATE METHOD

•CONSTRUCTION MAN-HOURS

•CONSTRUCTION. WORK LOCATIONS

•RADIATION SURVEY DATA FOR LOCATIONS

•WEIGHTING FOR OCCUPANCY IN

-Low Dose -General Area Dose -High Dose

For Each Task

• •WEIGHTING FOR RCA EFFICIENCY

-Dress· In/Out -Respirator -Special Dosimetry . -Tool Checkout

•PLANT HISTORIC DATA

•OTHER SGRPs

•ESTIMATE

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SGRP

MAN-REM ESTIMATE

CONSTRUCTION SCOPE: 573.7

CPCo SCOPE: 125.5

TOTAL PROJECT: 699.2

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SGRP MAN-REM ESTIMATE REVISION 1 (4/19/90)

ill.k.

1. Health Physics/Decon

2. Plant Support

3. Construction Opening

4. Rigging and Supports

5. S/G Modifications ..

6. PCS Piping

7. Insulation

8. New Pipe Systems (BD/Recirc)

9. Secondary Piping

• 10. Old S/G Storag~ Facility

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11. Instrument Sample System

12. HVAC

13. Scaffold and Tents

14. Temporary Services

15. Project Support (Tours, Inspections, etc.)

16. Testing & Inspection (NOE)

11: Prep Outage 1989

Man-Rem

109

16

5

86

12

171

48

41

10

1

1

8

81

17

58

29

13

STEAM GENERATOR REPLACEMENT DOSE SUMMARY

PLANT .s.G TOT AL DOSE CBEM)

SURBY-2 3 2141

SURRY-1 3 1758

TURKEY POINT-3 3 2151

TURKEY POINT~4 · 3 1305

~·J-. rQINT BEACH-1 2 576 , 8~

'H 8 ROBINSON-2 3 1206

(:f NDIAN POINT-3 4 541

4 561 DC COOK-2 . ~

PALISADES 2 699 (ESTIMATED)

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TECHNIQUES TO SAVE DOSE

•REDUCE FROM 6 CUT TO 5 CUT METHOD

•PERFORM LOOP CUTS ~VITHOUT REMOVING MANWAYS

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•REMOVE ALL PRIMARY COOLANT SEAL FLUSH FILTERS

•PERFORM CUT PIPE END INTERNAL DECON

•CCTV

•SURROGATE TOUR

•MOCK-UP TRAINING

•RSD HEAD SET COMMUNICATIONS SYSTEM

• ALARA REVIEW PROCESS .;..JI;<, ...

)~ ,# •WP&IR

-Bechtel ALARA review -SGRP ALARA review

•FACILITY CHANGE PACKAGE

-CPCo design review -ALARA checklist -CPCo ALARA approval

•RWP

-CPCo RWP ALARA review -CPCo ALARA approval

•PRE-JOB BRIEFING -...

-Lead technician or crewleader -Duty HP, RWP technician or ALARA ..

•IN-PROGRESS AND POST-JOB REVIEWS

-ALARA (SGRP, CPCo)

•LESSONS LEARNED

-ALARA

•

-PROJECT SOURCE TERM REDUCTION

DECEMBER '89 SOURCE IDENTIFICATION/ PRIORITIZATION (34)

JANUARY '90 ACTION PLAN TO IMPLEMENT BEST OPTIONS

FEBRUARY '90 SGRP COST/BENEFIT ANALYSIS ON SHARED CHEMICAL DECON OF LETDOWN, REGEN Hx, LETDOWN Hx LOOP

MARCH '90

APRIL '90

. MAY '90

SGRP COST/BENEFIT ON CUT/REMOVE OF FIVE SOURCES, THREE QUALIFIED

WALKDOWNS TO EVALUAT·E UPGRADED SHIELDING FOR SOURCES NOT QUALIFIED FOR REMOVAL

BECHTEL COST/BENEFIT ~OF THE . THREE LINES IDENTIFIED 'f3Y SGRP

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PIPE END DECONTAMINATION •:MECHANICAL DECONTAMINATION

I '

-Grit blast at a 45° angle ' '

-Glass bead for smoothing : -Vacuum and pressure equilization -Closed circuit TV -No damage to base material

•USED SUCCESSFULLY AT:

-IP-3 SGRP -Muhleberg -Obrigheim

•WHEN COMBINED WITH SHIELDING, AVERAGE DOSE REDUCTION FACTOR OF - 20

•ESTIMATED WASTE (if 6 cut method)

-6.6 cf coborundum (grit) -3.6 cf glass beads ,.

-6 small dust cans -3 RBU filters (1 cl)

•NO l\flXED WASTE " .

•DOSES FROM 5000 mRem/hr TO 250 mRem/hr

•PIPE END MACHINING PERFORMED WITHOUT RESPIRATORS

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PCS PIPE END DECONTAMINATION EQUIPMENT

PRESSURE GAGE I

. POSITION OF SPECIMENS DURING TEST

PRESSURE PIPE .

SUCTION PIPE

DECON MANIPULATOR

CLAMPING DEVICE

SEAL DISC

• ALUMINUM OXIDE GRIT BLASTING

PROCESS EQUIPMENT

•RECIRCULATING BLAST UNIT

•MANIPULATOR

•FRONT BOX

•SEAL DISC

•ALUMINUM OXIDE/GLASS BEADS

•CCTV -· .,

PRIMARY SYSTEM CHEMICAL DECON

•J'NDEPENDENT STUDY

•ESTIMATED COST: $1,650,000.00

•ESTIMATED MAN-REM COST: 30 MAN-REM

•ESTIMATED MAN-REM SAVINGS: 25 MAN-REM

•SCHEDULE REQUIREMENT: 3-5 CRITICAL PATH DAYS

•ADDITIONAL CONSIDERATIONS

-PCS Dam Installation -Core Support Barrel Removal -Disruption of Missie Shield Logistics -Loss of Lay Down Areas -Manways Will Remain On (No Jumps) -Low External Dose Contribution

•RESULTS

-Negative Cost/Benefit " -Negative Schedule Impact

-Negative Logisti.cs

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MINIMIZING CHANNEL· HEAD RADIATION FIELDS

•INDEPENDENT INDUSTRY SURVEY

•AVERAGE. PLANT DOSE RATES:

13 R/hr TUBESHEET 10 R/hr GENERAL AREA

•PALISADES OLD STEAM GENERATORS

5 R/hr TUBESHEET 3.5-5 R/hr GENERAL AREA

•FACTORS FOUND TO MITIGATE RAD FIELDS:

MATERIAL -LOW COBALT CONTENT -TUBES BRIGHT ANNEALE

SURFACE -REDUCED ROUGHNESS -REDUCED PLATEOUT -REDUCED RAD LEVELS

CHEMISTRY -pH 7.1 --LITHIUM 2.2 ppm (MAX) -DISSOLVED 0 2 <5ppb

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-HYDROGEN PEROXIDE INJECTION

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SIG SURFACE ENHAN.CEMENT

OBJECTIVE: PROVIDE A UNIFORM MICROSMOOTH SURFACE

•MECHANICALLY CLEAN AND SMOOTH SURFACE

-Brush to remove scale and debris

-Flapper wheel and buff to a smoothness of 40 RMS

•ELECTROCHEMICALLY POLISH TO REMOVE MICRO ROUGHNESS

-Conf arming cathode

-Standard electrolyte and technique

-Rinsing with demin water

-Final smoothness featureless at 1 OOX scanning electron microscope

• SGRP TRAINING

•GENERAL EMPLOYEE TRAINING (GET)

-INPO 87-008 "Guidelines for GET"

-GET updated as necessary for SGRP

•PROJECT ORIENTATION (GET UPDATE)

-SG RP workers currently on-site

-Update on Project specifics

of acilities

oplans and procedures

•CONTRACT TECHNICIANS ... .. -INPO 87-008, "Guidelines for RPT Training"

-Entrance exam for incoming knowledge and skills

-Procedure training and exam

-OJT

-Continuing Training

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SGRP TRAINING (CONTINUED)

•SUPERVISOR ALARA SEMINAR

-BPCo supervision

-Motivational ALARA techniques

-Points out ALARA responsibilities

-Shows causes of unnecessary exposure

-Familiarization with RP paperwork

•MOCK-UP TRAINING

-Required prior to RWP sign-in

-Pipe-end decon

-Machining

-Welding

-Channel head jumps as necessary "

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DECONTAMINATION

•INITIAL CONTAINMENT DECON

-Allows access -Reduces respiratory requirements -Reduces personnel contaminations

•GENERAL AREA DECON

-Maximizes co-nta.mination control -Maximizes productivity -Minimizes protective clothing requirements -Minimizes use of respirators

. -Minimizes personnel contaminations

•SPECJAL DECON REQUIREMENTS

··. ·· -~·- · -Thermal shield

-Liner plate -Steam generators

•CONTRACTOR DECON SERVICES

-Tools and equipment " -Respirators

-Protective clothing

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RADIOACTIVE MATERIALS PROGRAM

•MINIMIZATION OF VOLUME GENERATED

-Prevention of material and equipment from becoming. contaminated

-Pre-job planning, material lists

-Decontamination of materials and equipment

-Re-use of equipment which has been contaminated

•MINIMIZATION OF VOLUME BURIED

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-Segregation of reusable material which inadvertently ends up in the trash

-State of the art supercompactor

-Vendors available for special requirements

• 0 ....

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CUBIC FEET THOUSAND

llJ 0

-.J 0

00 0

78.000

.......

....... 0

105,000

•

en -I m

:D )> )> ~ oQ

)> :E m < )> z m :0 en m )>

-u -t ~ G) m mm -t 0 m :n < 0 z c 0 :D (/)

:;l z E :o ~ -~m 0 -t -u 0- mr ....... en l> ::tw

G)O mm z~ mm :D z )> -t -t -u m :n DO

c.... m 0 -I

•

t-w w l..J._

u -OJ :J u

•

STEAM GENERATOR REPAIR PROJECTS POINT BEACH, COOK AND PALISADES (ESTIMATE)

SGRPs

35,000 ,...----------------------.

30,000

25,000

20,000

15,000

10,000

10,000

5,000

POINT BEACH COOK PALISADES (ESTIMATE)

RADWASTE VOLUME BURIED

·~"' . •,;:-. __ ,.. ...... --

• CONSTRUCTION OPENING

•ORIGINAL CONTAINMENT CONTRUCTION UTILIZED AN OPENING

•OTHER OPERATING FACILITIES EQUIP:MENT HATCHES OPEN TO THE ATMOSPHERE

•SIZE AND LOCATION OF OPENING I I

2.~ • Z"it;

•STEEL AND CONCRETE ..

-Survey and disposition

-Temporary enclosure -HVAC -Local containments and ventilation

I \

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•ENGINEERING CONTROLS

-Grab samples -CAMs

,-HEPA outlet ...

•WALL REINSTALLATION

•TESTING

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REQUIREMENTS FOR OPENING CONTAINMENT DOOR

•HEALTH PHYSICS NOTIFICATION

-Crew leader stops or limits area jobs with airborne potential

-CAMs operability and source checked

-Grab sample taken prior to opening (not mandatory)

-Grab sampler loaded

-Inner vicinity floor smeared to ensure < lOK dpm/100cm2

•FUEL HANDLING SUSPENDED

•FUEL HANDLING BUILDING VENTILATION EXHAUST IN OPERATION

•CONTAINMENT PURGE SUPPLY FANS TAGGED OFF

•IODINE REMOVAL UNITS OPERABLE

•PERSONNEL AIR LOCK OPERABLE/DOOR NORMALLY CLOSED

•WEATHER CONDITIONS FACTORED INTO DECISION TO PROCEED

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MITIGATION OF RELEASE FROM CONSTRUCTION OPENING

•WHEN REQUIRED

-CAM alarm

-649' G/A air sample result > 25% MPC

•ACTIONS REQUIRED

-Commence air sampling immediately

-Contain source if known

-Activate 12

removal units if 12 present

- -Verify HVAC operability

-Verify in-flow

-Close temporary door if possible (ctuantify release if not possible)

•PRIOR TO NEXT OPENING

-Investigate cause

-Determine future preventive measures

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STEAM GENERATOR DESCRIPTION

•TWO UNITS

•462 TONS EACH

•60 FEET LONG

•20 FEET IN DIAMETER

• •1718 CURIE CONTENT EACH

•40 mRem/Hr MAXIMUM SURFACE DOSE RATE ESTIMATE (DRY)

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RIGGING AND TRANSPORT

•RIGGING INSIDE CONTAINMENT

•RETAINING WALL OUTSIDE CONTAINMENT

•RIGGING OUTSIDE CONTAINMENT

•HAUL ROUTES

•EVENT ANALYSIS

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·------::BLuE STAR MEMORIAL HIGHWAY

- 6

OUTAGE BUILDING

LEGEND

+ GROUM>Wt:ll

• AIR SN1PLING STATIONS

,A TLD STATIONS

• ...

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EVENT ANALYSIS

•SCENARIO*

-SIG drop outside of containment

-Seal welded nozzle caps come off

•ASSUMPTIONS

-Curie content 1718

-Bre~thing rate from Section C.2.(C) of Regulatory Guide 1~4

-Dose conversion factors from Tables E. 7 to E.10 of Regulatory Guide 1.145

-10% of activity in steam generator is released and 1 % of that r~leased goes airborne

* Present design analysis drop scenario shows that n.a breach of SIG can occur and nn release of radioactivity will occur in case of an accidental drop

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• • , ·EVENT ANALYSIS (CONTINUED)

•CALCULATED DOSE COMPARISON TO IP-3

STEAM GENERATOR WHOLE BODY DOSE DROP LOCATION PALISADES IP-3

(_i....JrJ~ ~ CRITICAL ORGAN DOSE PALISADES IP-3

CONTAINMENT 0. 10 mRem 0.3 mRem 30 mRem 118 mRem

STORAGE FACILITY 0.58 mRem 2.3 mRem 153 mRem 1030 mRem

•10CFR100 GUIDELINE ·

-300 REM TO THYROID OR CRITICAL ORGAN - 25 REM TO WHOLE BODY

NOTE: THE PRESENT DESIGN ANALYSIS DROP SCENARIO SHOWS THAT llil BREACH OF THE STEA~ GENERATOR CAN OCCUR AND llil RELEASE OF ACTIVITY WILL OCCUR IN THE CASE OF AN ACCIDENTAL DROP.

•SITE EMERGENCY PLAN WOULD COVER THE INCIDENT

• T~SFER FOR RECYCLING

•ADV ANT AG·ES

-S/Gs would be immediately and ultimately disposed of

-Burial space would be minimized

•DISADVANTAGES

-High exposl ire rate if not deconned

-Additional time, expense and man-rem if deconned

-Cost, time and man-rem required for shipment

-Many ship:rnents required

-M_any potential accident scenarios would need to be addressed ~ .·

-Potential objections or additional requirements by states traversed ·

-Application of technology to this situation untested

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BARGE AND BURY

•ADVANTAGES

-S/Gs would be immediately and ultimately disposed of

-Future uncertain cost increases would be avoided

DISADVANTAGES

-SIG surface exposure rates would be higher than if delayed

-There would be additional man-rem and expense over interim storage

-Potential problems associated with shielding and loading intact S/Gs -·

-Many potential accident scenarios would need to be addressed · . " "

-Site preparations and rigging/loading could negatively impact schedule

-Project schedule delays could· result in storage until • spring

-Uncertainty in ability to bury outside of Michigan could. drastically alter this approach ·

•

•

ON-SITE STORAGE

•ADV ANT AGES

-No credible accident scenario

-Handling is simplified and time required for disposition is reduced ·

-At the end of plant life, the radiological hazard will be greatly reduced (1/10 original in 24 mo. then Tl/2 is 5 .2 yrs)

-Future improvements in technology could be applied

~DISADVANTAGES

;I

-This is an interim solution, final disposition will occur during decommissioning

-Uncertainty in future disposal costs

• STEAM GENERATOR DISPOSAL OPTION COMPARISON .

r •

'

• FATE OF OTHER REMOVED STEAM GENERATORS

•SURRY (1 & 2)

•H B ROBINSON 2

•POINT BEACH 1

•TURKEY POINT 3 & 4

•INDIAN POINT 3

•DC COOK2

1 SHIPPED FOR STUDY 5 ON-SITE STORAGE

3 ON-SITE STORAGE

2 ON-SITE STORAGE

6 ON-SITE STORAGE

4 ON-SITE STORAGE ..

4 ON-SITE STORAGE

..

COMPARISON OF STEAM GENERATOR STORAGE FACILITIES

WALL ROOF EXTERNAL PLANT THICKNESS THICKNESS DOSE RATE

PALISADES 2'-6" 1 I -6" (MIN) <0.5 MR/HR

INDIAN PT 3 3'-0" 1'-6" (MIN) <0.5 MR/HR

DC COOK 2 2 I -6 H 2' -6" < 1.0MR/HR

TURKEY PT 3 & 4 2'-0" 1 I -0" <2.5 MR/HR

PT BEACH 1 2'-0" 2'-0" <2.5 MR/HR

SURRY 1 & 2 3'-0" NOT <0.5 MR/HR AVAILABLE

•

ROBINSON 2 2'-0" 2'-0" < 1.0MR/HR

DESIGN PARAMETERS OF PALISADES OLD STEAM GENERATORS

INTERIM STORAGE FACILITY

•LOCATION

-Approximately 2200ft northeast of the containment

•DIMENSION

-Length 129' 4" -Width 29' 0" -Height 28' 9 1/4" (maximum)

•NUMBER OF STEAM GENERATORS

-2

•WALL TIIlCKNESS

-2' 6"

•ROOF TIIlCKNESS

-1' 9" to 2' 1"

" •SURFACE RADIATION LEVEL

-0.S mR/hr on exterior

.,,

• I

• INTERIM STORAGE FACILITY (CONT)

•

•OFFSITE BOUNDARY

-Van Buren State Park is the closest offsite boundary at 1200 ft north of the facility

•NEAREST ON-SITE STRUCTURE:

-Outage Building at 275 ft away

•LOCKED AND POSTED ACCESS DOOR

•SURVEILLANCE PROGRAM RADIATION, CONTAMINATION

•MAXIMUM ALLOW ABLE BUILDING WALL SURF ACE DOSE RA TE 0.5 mR/Hr

•S/Gs COATED TO SEAL SURFACE.

•CLOSED SUMP -·

•SEALED BUILDING •

•REMOTE SAMPLING PORTS

• ISF OFF-SITE DOSE

•ASSUMPTIONS

-200 mRem/hr SIG dry surface dose rate*

-Right cylinder 930.62" long, 155.5" diameter

-ISF 130' long, 30' high, 30' wide

-1200' to nearest fence (worst case)

-Tourist at fence 100% of the time

-Sky shine included

-Nearest residence 3000 ft, 100% occupancy

•LIMITS •

-EPA 40CFR190.10(a) limit = 25 mRem/yr

-ISF dose to fence = 5.0 E-4 mRem/yr "

-ISF dose to nearest resi~ent = 1.0 E-5 mRem/yr

*Conservative compared to expected value of 40 mRem/hr •

·•

•

ENVIRONMENTAL SAMPLING PROGRAM

•ONGOING

-PRESENT ENVIRONMENTAL MONITORING PROGRAM

o Direct Radiation oAirborne oWaterborneolngestion

•IN ADDITION

"

-DURING S/G

oDirect Radiation olngestion

-AFTER STORAGE

oDirect Radiation oWaterborne

-·

•

•

Name

David W. Joos R.H. Beck Mark Rubin John A. Zwolinski Brian E. Holian Bob Pierson Keith Wichman Chen P. Tan Arnold Lee P •• K. Beckman Kelly V. Cedarquist Tom Newton Mark Caruso Jake Wechselberger Emmett Murphy Winston W. Liu Tom Tai Mark L. Lesinsuf Jim Kue:min W i 11 i am C 1 ark Cris Hillrr.an J.G. Lewis Herman M. Esch David P. Hoffman Ken Berry Bud Gerling

NRC/CPCo/BPC Meeting

May 3, 1990

Palisades Plant Site

Affiliation

Attachment 3

CPCo/VP Energy Supply Services/SGRP Mgr Bechtel NRR/NRC NRR/ADP/DRSP NRR/PM-Palisades NRR/PDIII-1/DRSP NRR/DET/EMCB NRR/DET/ESGB NRR/DET/EMEB Bechtel CPCo/iSI CPCo/ISI NRC/NRR/SRXB NRR NRR/DET/EMCB Reactor Inpsector NRC RIII Bechtel CPCo SGRP/RP CPCo SGRP/Licensing CPCo SGRP/Eng & Const CPCo Falisades/Prcj~cts CPCo/SGRP CPCo/Palisades/Planning CPCo/VP Nuclear Operation5 CPCo/Director Nuclear Licensing CPCo/Pal/A&TA Supervisor

NRC PRESENTATION and TOUR

DATE: MAY 3, 1990

LOCATION: MANAGERS CONFERENCE ROOM

SUBJECT: SGRP, SG IMPROVEMENTS and SECONDARY SYSTEM IMPROVEMENTS

AGENDA: 8:00 INTRODUCTION D V JOOS

8:15 VIDEO

8:30 PROJECT PLAN D V JOOS

9:00 SG & SECONDARY IMPROVEMENTS C T HILLMAN

10:00 SGRP OUTAGE SCHEDULE A K BECKMAN

11:30 LUNCH

12:00 SURROGATE TOUR ON LASER DISK J S RIDL!Y

1:00 PLANT TOUR OUTSIDE CONTAINMENT TURBINE BLDG SFP INSIDE CONTAINMENT SG HAUL ROUTE SG INTERIM STORAGE NEY SGs

4:30 CLOSEOUT

J G LEVIS

D V JOOS

" ,•

. t . •

~&l1D®&lID[g@ .. · @1f(g&UMfl @~OO~lru&LF@OO

OO~~l1&©~~[g001f ~OO@~~©if

PALISADES

s G R p·

PROJECT PLAN

'

1. INTRODUCTION

2. MISSION & GOALS

3. ORGANIZATION

4. SCOPE & RESPONSIBILITIES

5. PROJECT SCHEDULE

6. OUTAGE SCHEDULE -

7 . BUDGET ~

•

•

•

SGRP MISSION

"TO ACCOMPLISH THE STEAM GENERATOR REPLACEMENT WITHIN

BUDGET, ON OR AHEAD OF SCHEDULE, AND WITH HIGH QUALITY .

IN ADDITION, ALL PROJECT OBJECTIVES SHOULD BE

ACCOMPLISHED SAFELY AND WITH RADIATION EXPOSURE AS LOW

AS REASONABLY ACHIEVABLE." .·

SAFETY

SCHEDULE

• COST

-COMPLIANCE

QUALITY

SGRP PROJECT GOALS

• NO LOST-TIME ACCIDENTS • RADIATION EXPOSURE LESS THAN

679 MAN-REM e NO OVER-EXPOSURES • LESS THAN 215 CONTAMINATIONS • LESS THAN 10,000 CUBIC FEET

RADWASTE FOR BURIAL

e 21 DAYS SPRING OUTAGE CRITICAL PATH 75 DAYS REPLACEMENT OUTAGE CRITICAL PATH

• LESS THAN $103 MILLION

• NO NRC CIVIL PENALTIES .. • LESS THAN 45 NRC NON

COMP~IANCE POINTS . • NO ENVIRONMENTAL VIOLATIONS • NO WORKER SAFETY VIOLATIONS

e COMPLIANCE WITH REQUIREMENTS • MINIMIZE REWORK .

• PALIS}\DES STEAM GENERATOR REPLACEMENT PROJECT

ORGANIZATION

PROJECT MANAGER D 1' JOOS

ASST PROJ MGR JG LEWIS

.----------...---------+--------"'---•••oooooo•oOoHooo•oHooooooooooooooooooooooooooooooooooo•oo

ROJ ADMIN/CONTRO M C SNIEGOWSKI

RAD PROTECTION M LESINSKI

RADIATION PROTECTION PLANNING AND SCHEDULING FACILITIES AND SERVICES

CONTRACTS SOURCE-TERM REDUCTION

ADMINISTRATION DECONTAMINATION

RECORDS MANAGEMENT . RADlfASTE

' '·

UCENSING J KUEMIN

ENGIR AND CONSTR W Cl.ARK

STRATEGY DEVELOPMENT ENGR AND CONSTRUCTION

SUBM11TAL PREPARATION AND DEFENSE PROCUREMENT

NRC COMMUNICATIONS TESTING AND INSPECTIONS

QUALITY ASSURANCE K MARBAUGH

AUDIT AND SURVEIWNCE PROGRAM

QUALITY PROGRAM DEVELOPMENT AND LICENSING

l. l i ~ l ' ~ ! .j l

1 l

.j ·.:

PALISADES STEAM GENERATOR REPLACEMENT PROJECT BECHTEL ORGANIZATION

PROJECT ENGINEERING C BROWN

DESIGN ENGINEERING

UCENSING

FIELD SERVICES MANAGER H CHARNEY

FIELD ENGINEERING

FIELD PROCUREMENT

FIELD CONSTRUCTION

FIELD COST/SCHEDUUNC

FIELD Al.ARA

FIELD SAFETY

FIELD QUAUTY CONTROL

PROJECT MANAGER AK BECKMAN

ASST PROJECT MANAGER R L BECK

BECHTEL-KWU COORD C DIPPOLD

PCS WELDING

QUAUTY ASSURANCE ENC P DADLANI

COST/SCHEDULE SUPV H MUELLER

COST AND SCHEDUUNC

PROJ PROCUREMENT HGR H ZEIGER

PROCUREMENT

!Vl/90

SGRP SCOPE & RESPONSIBILITIES

• PROJECT MANAGEMENT

• COMPLETION & DELIVERY OF THE STEAM GENERATORS

• ENGINEERING AND CONSTRUCTION

• • TESTING & INSPECTION

• FACILITIES

• LICENSING

• RADIATION PROTECTION , . .,

• QUALITY ASSURACE/QUALllY CONTROL

e SECURITY

"'

•

Budget Rev: 2A

SGrRP TOTAL PROJECT BUDGET

ALL COSTS OOO's

CONTRACTOR $54516

RAO PRO $9740

OWNER MGMT $7701 CONTINGENCY $7352

' '

QA $1725 FACILITIES $2570

MAINT UPGRDS $2750 AFUDC $3959

. TESTING $4307 A & G $7337

•

Desk Reference 4.1.1

ih=========================-=-===-~--=-=--~=====================~~====--=-=·--==-======~

• NRC MEETING

STEAM GENERATOR STATUS UPDATE

TOPICAL AGENDA

MAY 3, 1990

EXISTING STEAM GENERATORS

* Steam Generator History

- operation and tube plugging history ..

- corrosion mechanisms

* Current Problems and Remedies

- tube support plate growth

- denting and cracking

- IGA/SCC

* Chemistry Performance

- sludge lancing

- chemistry with the Reverse Osmosis unit

REPLACEMENT STEAM GENERATORS ,•

* Steam Generator Design Improvements

- stainless steel eggcrate supports

- recirculation ring

increased blowdown line size

* Secondary Side Improvements

copper removal

- blowdown system enhancements

• * Future Plans

- Steam Generator Reliability Program

·-- ·---~-- -.····-······.----- .... ~· .. -··-.- ... ·····--.----~,---·-··-,·-~·-··-·"' _____ Pasze ... ":. .. _l_. ____ .,, ... _·-..--····-··------------·-··--··-·- -·--- .

•

SG AND SECONDARY IMPROVEMENTS

• EXISTING STEAM GENERATORS

SG HISTORY

CURRENT PROBLEMS AND REMEDIES

CHEMISTRY PERFORMANCE

• REPLACEMENT STEAM GENERATORS

DESIGN IMPROVEMENTS

• SECONDARY SIDE IMPROVEMENTS

• FUTURE PLANS ,,

-·- ---------· .... ··. ··-··-·- -·· -·--- ~-----.--. ... ' -·- -·- ·---····· -.-• ···-----------:~· .... ···:··· ----- ............ ·-·· ,.. ... ···--·- .. .

.· "

•

••

PALISADES STEAM GENERATOR OPERATING HISTORY

- JAN 1973 FIRST TUBE FAILURE AFTER ONE YEAR OF OPERATION; WASTAGE ATIACK, PLUGGED FIRST 11 ROWS (1,400 TUBES; 8%)

- AUG 1973 EXCESSIVE LEAKAGE; PLUGGED ALL TUBES WITH GREATER THAN 60% WASTAGE DEFECTS

- MAY 1974

-1975 TO

1982

;. MAR 1982

• AU.G 1983

(340 TUBES)

PLANT WAS STILL OFF LINE FOR RX VESSEL REPAIRS. FAILURE MECHANISM WAS IGA; SYSTEM FLUSHED AND WATER TREATMENT CHANGED TO ALL-VOLATILE TREATMENT (APPROXIMATELY 920 PLUGGED; 16% PLUGGED TOTAL) .

WASTAGE ESSENTIALLY ARRESTED; 1085 PLUGGED OVER 8 YEARS (ADDITIONAL 6%) DENTING WAS OCCURRING AT A MINOR RATE; TUBE SUPPORT PLATES BEING LOCKED UP

2 LEAKING TUBES IN A-SG; DEVELOPMENT- BEGUN ON A ECT PROBE CAPABLE OF TRAVERSING THE FULL LENGTH OF THE TUBES FOR BETTER DETECTION OF CIRCUMFERENTIAL CRACKS AND IGA

BEGAN OUTAGE WHICH WAS EXTENDED 11 MONTHS BY REQUIRED QUALIFICATION OF THE RECENTLY DEVELOPED 4C4F ECT PROBE. TESTING REVEALED A SUBSTANTIAL NUM.BER OF POSSIBLE IGA INDICATIONS (PLUGGED APPROXIMATELY 280 TUBES)

:• .... ····.- .. ···. - .. ····:·-.:~·- .. ····

•

•

OPERATING HISTORY· CONTINUED

- NOV 1985 A ROUTINE REFUELING OUTAGE WITH NO ABNORMAL SG INSPECTION RESULTS; DENTING CONTINUING

- DEC 1987 FIRST OUTAGE DUE TO SG LEAKS IN OVER 5 YEARS. CIRCUMFERENTIAL CRACK AT 13TH SUPPORT PLATE OF B-SG; BORIC ACID ADDED TO SECONDARY !;;ICE TO HELP MITIGATE DENTING, PRECEDED BY SLUDGE LANCING

- AUG 1988 TUBE LEAK IN B-SG; CIRCUMFERENTIAL CRACKS AT 13TH SUPPORT PLATE; 34 TUBES PLUGGED

- DEC 1988 WELD DEFECT ON B-SG TUBE PLUG; PREVENTIVE PLUGGING OF 9 TUBES

- JAN 1989 CIRCUMFERENTIAL CRACK AT 3RD SUPPORT PLATE; PREVENTIVE PLUGGING OF 238 TUBES

- OCT 1989 ADDITIONAL 145 TUBES PLUGGED DUE TO CRACKING IN HIGH STRESS REGIONS

"' . ·TOTAL TUBES PER SG 8519; PRESENTLY A-SG HAS 2044 TUBES

PLUGGED (24%) AND B-SG HAS 2442 TUBES PLUGGED (29%)

·:··= ... ~ "'"·~·- ·...,. ·., ..... ·::-: ... --·.·::.:· .• :-~1"1·:-:·:1~4': ': .... -, ...... : .. ~· . .:...1,:'l'-.""';!"",..:.-.;.:·-i .• ,.<":'~'.\.~~~=.~:-~.··.:r~·-<T>tu_:nY.l~.:~~~.r.;~:-.~---:":r_-.~~~J;'!'.R'•-..~7 ""~·.::=..:-..-ry-~,,.,...1.)a.v ........ ~····.,.":"· .. ~::-·-·-. - ~·-.. :- -·· .. "·· -:-;· · .· ·: - .·• .• . """: ·· - .......... ·- ....... . . . . .

•

PLUGGED/YEAR

STEAM GENE.RATOR TUBE PLUGGING

73 74 75 76 77 78 79 80 81 82 83 84 85 86 87 88 89

YEAR

- SGA - SGB

SG FORCED OUTAGES: 73-1, 74-2, ~2-1, 87-1, 88-2, 89-1

CUMULATIVE. PERCENT 307.~·~~~~~~~~~~~~~~~~~~~----.

257.

20"

157.

10"

57.

o"

~ .

73 74 75 76 77 78 79 BO 81 62 83 84 65 86 87 88 89

YEAR

. . .-:.,. :.'..; ·-·--":">:~~·~'\:--,.•~·-'C:-. .... ':"'·"'-'·:c~~~-~~~"n.:·f..·:·...::.R'!'~r.;_.,rk-.\~~:lt'-'F~.·";C""~"°>\~~'l'.":~..:~1~?~";t~?"-:7~~·~·,::.o.~··,?-'l~}'h~u .. :-o~~ ... ~.": ... ~~-... - .•. ·.-·-·····-..:".:~ .• - ........ ~-~:"' ... "·:"'~ _:;::. ~; · •·. :·-·. · : .. -·. ··;. --· -··>· · .• :--·.:· _,. .--· -:·-: - .... -...~.·--· ~-·:··;:··.· --

• EXISTING STEAM GENERATORS

• CORROSION MECHANISMS

WASTAGE

DENTING

IGA/s·cc -

e CURRENT PROBLEMS AND REMEDIES

TUBE SUPPORT PLATE GROWTH

DENTING AND CRACKING

IGA/SCC

• CHEMISTRY PERFORMANCE

SLUDGE LANCING

CHEMISTRY WITH THE REVERSE OSMOSIS UNIT

•

..

•

IMPROVEMENTS

e STAINLESS STEEL EGGCRATE TUBE SUPPORTS

• MINIMIZE FLOW STAGNATION .•

• REDUCE POTENTIAL FOR DENTING • MINIMIZE STEAM BLANKETING

e LARGER MANWAYS"

e MODIFIED INSPECTION PORTS

e INTEGRAL MAIN STEAM FLOW RESTRICTOR

e IMPROVED SLOWDOWN CAPABILITY

e ELECTROPOLISH PCS HEADS

- - -~~~.r.;;-z-:!:.{~ ... -::-;.t;.:.-1'.'.":~~-~?;"~[...r.~.~f{\~·~·~:f!.'J.'o.~.';·:;:1,'.1.?~:·:7~.";~·:"';::;.:~·r-··.·~:.;;·.~·/--... ·._<,":": ... ~•-·1:.;.·7~';··.·:!" ~--. ;;, •..::·: :--..':···: ~:~-·'!".:· .. ···· ~-,:.:_:· ·;- :.:.: ,-.;·-~.~-: --~. _.-. ... ~: _,. ~~.::·"'::;·.··'.!!' .... ~:. ~;..,.,.·.--~· -::r:·- .,~. -~- : .. ·• -. : •• ·.-; ',&. .. _.- •• ~,.. ·:·,_: ... -;.·. -.- ·"":P'I<•:"'.·

•

;I

• . .

SECONDARY SYSTEM IMPROVEMENTS

• COPPER REMOVAL

MAIN CONDENSER RETUSING

FEEDWATER HEATER AND DRAIN COOLER REPLACEMENT

OXYGEN CONTROL

CONDENSER BOOT REPLACEMENT

CORROSION PRODUCT REMOVAL

ORGANIC REMOVAL

SECONDARY WATER QUALITY

WATER QUALITY INSTRUMENT UPGRADE,, ··

• PHASE II SLOWDOWN SYSTEM ENHANCEMENTS

INCREASE SLOWDOWN AND RECIRC PIPE SIZE

INCREASE CAPACITY OF SLOWDOWN HX

LARGER FLOW SLOWNDOWN PUMPS

.. _,""'':"'T·"-""~;"1:••·~··.-.~-• -~"T"';'f"' •-.·-·;·~·-··- .. - -·-··--.·,--•·· --~.-- ... ····•-· ·· • • • ,_. " --··· -,- . ··- ····- -;-· -·- -·- ... __ • .._... •. ··~- • ·- .• ··•·······. • •• •

---------------

•

•

FUTURE PLANS

• STEAM GENERATOR RELi.ABiLiTY PROGRAM

PROGRAMMATIC ASPECTS

OPERATION ENHANCEMENTS

MAINTENANCE ENHANCEMENTS

• •

I

•

• Pre-Outage SGR Activities

• SGR Activities During Plant Defueling

• 75 Day SGR Critical Path Activities

• SGR Activities During Plant Refueling

-·

•

.-.. ·-· --·- - ·- .... _.,,....~---.....--·--"- ...... -·.-·-· -----..---·-·· ·:· -· -..,....----··········-·· ··---··· .... ---- ·-··-.-.--- --·· ...... -- ----~·-·-·:--····

:I.All r Offll E

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Sl"RllCNllllL lMIUIUP JES£ 'ftT Pl.MT ON

r" '!'ilft GD!Dlfl!'Olt flf !IP. KLDlll'JG 11 lmtUO!

•

•

I~ -

• Mock-up Channel head & PCS Piping

•

•

•

•

•

•

•

PCS Cutting and Machining PCS Welding PCS Decontamination PCS Nozzle/Elbow Fit-up

Old Steam Generator Storage Building

Training

Detailed Planning

Reinforced Earth Wall

Assemble Platform and Rigging Equipment Outside of Containment Opening

. ·--.,····-· -- ·- ····-· - -·-...,-··- ... ---· --· ··--··-- _____ ,, ___ ------=--·--·· ----- "::•·'~-~ --~-·-·- ....... , - ... ····~ ·-

-.

• SIEMENS

SG-Mock Up Steam Generator Replacement Ringhals 2/Sweden Personnelt-, Equipment Training and OuaHficatioR .. ·-

·-.-·- ., .. - ... -- ..

89PWR124 UBKWU U444PT

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611.41 •

10

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122.53' !

FACE OF WALL

TO" O' C,1,1', COl'ING ITYlll

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14.76 •

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ELEVATION FRONT FACE

Top rowof lie strips, second course of full panels

SCALE • 1· • 10'

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610.84 08.38

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(LATER,.

REINFORCED EARTH VOLUME rSEE NOTE 4)

FRONT FACE ---....lh: REINFORCED EARTH VALL

.-.-.. ... -·-····--

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LAYER OF GEOGRID I CTENSAR SR-2 OR EQUIVALENT)

COMPACTED STRUCTURAL Fill

22·-o· 1 o·-o·

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' SECTION@

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•

•

..

•

•

•

. ti

Install Temporary Power

Install Scaffolding

Insulation Removal

Interference Removal

Tendon Detentioning and Removal

Cutting Containment Wall Opening

.,,

,,, ,.,.. . ..

··-~·1i

,•

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120·

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PARTIAL PLAN - CONTAINMENT· WALL AZ. 85° TO 145'

SCALE: 11 • = 1 '·0·

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• PRESENTATIONS

CONTAINMENT CONSTRUCTION OPENING •••••••••••••••••••••• APRIL 12

NARROW-GAP WELDING •••••••••••••••••••••••••••••••••••. APRIL 2 6

RA.DIATION PROTECTION ••••••••••••••••••••••.•.••••••••• MAY 2

SG and SECONDARY SIDE IMPROVEMENTS •••••••••••..•.•••.• MAY 3

PIPE and PIPE SUPPORTS. • • • • • • • • • • • • • • • • • • • • 8 • • • • • •

FSAR ANALYSES. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . RIGGING AND HAULING •••••••••••••••••••.••••••••.••••••

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•

FCP DESCRIPTION

Blowdown System Piping - Phase I Recirculation System Piping - Phase I Wide Range Instrumentation Tubing - Phase I Breathing Air Station Relocation - Phase I Rigging and Support Installation - Phase I Reinforced Earth Retaining Wall Aux Bldg Modification for CAF Overall SG Replacement Program Temporary Commodities Old Steam Generator Storage Facility Outside Rigging Inside Rigging CCW Surge Tank Room Tubing Relocation CCW Surge Tank Room Roof Slab Removal Containment Construction Opening PCS Piping Replacement Main Steam System Piping Modification Emergency FW System Piping Modification Blowdown System Piping - Phase II Recirc System Piping - Phase II Steam Generator Sample System Wide Range Level Instrumentation Foundation Structure for Rigging Platform CVCS Piping/Valve Relocation Steam Generator Replacement Main Feedwater System Modification

SCHEDULE

Completed Completed Completed Completed Completed April 13 June 15 June 15 June 15 May3 June 15 June 15 June 15 June 15 June 15 June 15 June 15 June 1 June 15 June 15 June 1 June 15 May21 June 15 June 15 ,. May15 "

..

INTERIM OLD SG STORAGE FACILITY

• 0 Structural l)esign of Storage Facility

0 Seismic Design Considerations

0 Other Natural Phenomena

0 Flooding

0 Fire Protection and Fire Hazards

0 Electrical Design Considerations

0 Radiological Impact (Onsite and Offsite Doses)

-· 0 Radiological Consequences of Abnormal Events

0 Surveillance Requirements ,. .,

0 Structural Adequacy of SG Supports

0 Security Access Controls

0 Construction Impact

0 Technical Specification Impact

• 0 FSAR Impact

CONTAINMENT ·coNSTRUCTION OPENING

0 Containment Design Parameters

0 Containment Structural Adequacy

0 Shutdown Cooling System Operation Coordin.ation

0 Impact on Safety-Related Equipment during Construction

0 Temporary HV AC Consideration

0 Missile/Tornado and Depressurization Considerations

0 Containment Access Control and Security Control

"' ~

0 Replacement Materials (concrete, rebar, sheathing, liner plate) and Construction Details

" 0 Radiation Protection

0 Temporary Enclosure Consideration

0 Fuel Building/Containment Interface

•

CONTAJNMENT CONSTRUCTION OPENING (cont)

0 Liner Plate Protection Considerations-

0 Protective Coating on Liner Plate

0 Procedural Controls

0 Waste Disposal

0 Removal and Reinstallation of Tendons

0 Mockup Training

• 0 Inspection Method/Criteria

0 Performance Tests

0 Technical Specification Impact _.

.. 0 FSAR Impact

' r

RIGGING INSIDE CONTAINMENT

0 Structural Evaluation of Rigging Loads on Existing Polar Crane Rail, Containment Shell and Reactor Cavity Shield Walls

0 Heavy Load Consideration

0 Load Test of all Lifting Systems and Components

0 Impact on Plant Security System

0 Fire Protection System Considerations

0 Electrical Design Considerations


,. -o Consequences of Dropping Old/New "SG, Rigging,

or Other Equipment

0 Radiation Protection ;I


0 FSAR Impact

I

HAUL ROUTES AND RIGGING OUTSIDE CONTAINMENT

o Structural Evaluation of Access Roads

o Evaluation of Underground Utilities

o Assessment of Nearby and Overhead Facilities for Interferences

0 Load Test of all Lifting Systems and Components

0 Structural Evaluation of Rigging Platform, Structural Supports, and Foundation

0 Flood Control

0 Procedural Controls ,,.

Impact on Fire Protection .,

0

0 Impact on Plant Security System

0 Impact on Electrical ·Systems

• HAUL ROUTES AND RIGGING OUTSIDE CONTAINMENT (cont)

•

o Transportation Incidents (loss of transporter control, transporter overturning, etc.)

o Consequences of Dropping Old/New SG, Rigging, or Other Equipment

o Technical Specification Impact

o FSAR Impact

• L

RETAINING WALL OUTSIDE CONTAINMENT

o Structural Adequacy of the Structure·

o Evaluation of Underground Utilities ..

o Assessment of Nearby and Overhead Facilities for Interferences

o Procedural Controls

o Construction Impact

o Separation from Containment

o Impact on Containment/Tendon System

o Impact on Fire Protection

o Impact on Plant Security System

o Impact on Electrical Systems

o Design Life of the Structure


o FSAR Impact

PIPING SYSTEMS INSIDE CONTAINMENT

o . Seismic Design Considerations

o Missile Design Considerations

o Pipe Support Design Considerations

o High-Low Pressure Interfaces

o Interfacing LOCA

o Pipe Penetrations (LLRT, Heatup, etc)

o Pipe Breaks (MSLB, HELB, etc.)

o Single Failure Criteria

o Environmental Qualification Impact ..

o Code Compliance and Reconciliation

o Containment Heat Load Considerations "

o Containment Heat Sink Considerations

o Thermal In~ulation Removal and Replacement

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. ••• .. •- -·. • -- ••• .. •·.:•·,.····· .···--,-·-r•··••• •·.;.•···-····---······

• PIPING SYSTEMS INSIDE CONTAINMENT (cont)

0 Heavy Load Considerations

0 Protective Coating

0 Hydrogen Generation

0 Pipe Severance an~ Reconnection Technique

0 Radiological Impact of Pipe Cutting

0 Waste Disposal

0 Return-to-Service Testing


0 FSAR Accident Analyses .I'

•

0 FSAR Impact

. ~

• -. .

o••· •• ...-··-,-- .-.•···.- .·--.-- 0 - ••• •"•'• '"-• ··-.-• n• -· O•••o ·-. •• --~ .•- •••• ,_ o •"": •"•"'." •• T• - • • • •• • •

•

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SG BLOWDOWN AND RECIRCULATION PIPING -SPRING OUTAGE INSTALLATION

0 Structural Evaluation of Pipe Support Loads (permanent and temporary) on .Containment Interior Structures


0 Missile Design Considerations

0 Protective Coating

0 Impact on Subcompartment Analysis

0 Containment Heat Sink Considerations


Heavy Load Considerations ,.

0 ~


0 FSAR Accident Analyses

0 FSAR Impact

. ··-··· - ··~--·· ·· .. ·~-. ·-·· ····-········-- ...... ~-··

WIDE RANGE LEVEL INSTRUMENTATION

0 Potential Changes to Setpoint

0 Review of FSAR Accident Analyses

0 Review of Set Point Index

0 Enyironmental Qualification Impact

0 Regulatory Guide 1.97 Compliance

0 Fire Protection Considerations

0 Single Failure Criteria

0 Electrical Power Supply Considerations

0 Structural Evaluation of Instrumentatjon Support Loads on Containment Interior Structures


0 Technical Specifi~ation Impact

0 FSAR Impact

• - .

··-.-·••-·--···· -·· •••• ·~.··••••·••·•••-r.···--·•·-· -······:-- •• .•.· • • ···-•• .. '

• WIDE RANGE LEVEL INSTRUMENTATION -SPRING OUTAGE INSTALLATION

0 Structural Evaluation of Instrumentation Support Loads on Containment Interior Structures


0 Impact on Subcompartment Analysis





FSAR Impact " 0 ,

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• INTERFERENCE REMOVAL AND REINSTALLATION

0 Consequences of Load Drop

0 Laydown Load Consideration

0 Impact on Safety Systems During Removal/Reinstallation

0 Impact on Fire Protection System

0 Impact on Security System

• 0 Loss of Offsite Power


0 Return -to-Service Testing ,.

Technical Specification Impact .,

0


"' 0 FSAR Impact

•

TEMPORARY RIGGING COMPONENTS INSIDE CONTAINMENT - SPRING OUTAGE INSTALLATION

o Structural Evaluation of Rigging Component Loads on Containment Dome Trusses and Liner Plate

o Seismic Design Considerations

o Impact on Subcompartment Analysis

o Containment Heat Sink Considerations

o Hydrogen Generation

o Protective Coating

o Heavy Load Considerations

,.

o Heavy Load Consideration Not Addressed in Existing Plant Procedures


o FSAR Accident Analyses

o FSAR Impa~t

• BREATHING AIR SYSTEM - SPRING OUTAGE INSTALLATION

0 Structural Evaluation of Support Loads on Containment Interior Structures

0 Pipe Support Design Consideratio_ns


0 System Interface

0 Performance Tests



0 FSAR Impact _,. .,

. , r

• STEAM GENERATOR REPLACEMENT FC -

0 Comparison with Existing SG Design

0 Code Compliance and Reconciliation

0 Structural Adequacy of Existing SG Support System

0 Thermal Insulation Removal and Replacement



0 Containment Heat Load Considerations


./'

0 Containment Net Free Volume Considerations


" 0 System Interface

0 Equipment Qualification Program Evaluation

- -- .. -·--- .. ,.,..-.~ ·- .. - ·-·-······· .. ···---·---···.-··--- .. --.---7--..--------·-·-·-·7.•-.··-· --···· ··---~-.--. ··.····

• STEAM GENERATOR REPLACEMENT FC (cont)

0 PCS Flow

0 Flow-Induced Vibration

0 Temperature Difference between Hot and Cold Legs

0 Pressure Drop Across the Core

0 ALARA Considerations



0 Evaluation of FSAR Accident Analyses

" ~

0 FSAR Impact

•

..

OVERALL SG REPLACEMENT PROJECT

0 Comparison with Existing SG Design

0 Code Compliance and Reconciliation

0 Structural Considerations



0 Procedural Control During Construction

0 Operational Procedure Review

0 System Interface

0 Equipment Qualification Program Re~iew ~

0 PCS Flow

0 Flow-Induced Vibration

0 Temperature Difference between Hot and Cold Legs

• OVERALL SG REPLACEMENT PROJECT (cont)

0 Pressure Drop Across the Core

0 ALARA Considerations



0 FSAR Accident Analyses Review

0 FSAR Impact

.. 0

•

•

-------

... -

FSAR CHAPTER 14 SAFETY ANALYSES

FOR THE REPLACEMENT STEAM GENERATORS

• DISPOSITION OF ALL CHAPTER 14 EVENTS CCPCo, ANF, CE>

• THE DISPOSITION IS BASED ON REPLACEMENT STEAH GENERATOR DESIGN DIFFERENCES AND RESULTING PLANT OPERATING CONDITIONS

• ONLY TWO EVENTS ARE DISPOSITIONED AS REQUIRING REANALYSIS:

1. FSAR 14.15, STEAH GENERATOR TUBE RUPTURE CSGTR), DUE TO -A LARGER TUBE INSIDE DIAMETER

2. FSAR 14.18.2, HAIN STEAH LINE BREAK CMSLB) CONTAINMENT RESPONSE (INCREASED SECONDARY INVENTORY)

• PRELIMINARY RESULTS TO THE SGTR AND THE MSLB CONTAINMENT EVENTS ARE ACCEPTABLE (ACCEPTANCE CRITERIA BEING HET> - ..

• THE ACCEPTABLE COHPLETION OF THE EVENTS REQUIRED WILL SUPPORT THE REPLACEMENT OF THE STEAH GENERATORS UNDER THE 10CFR50.59 P~OCESS

·,

i. introduction ii. radiation safety department

Documents