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REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS) DISTRIBUTION FOR INCOMING MATERIAL 5QC51270/287 REC: CASE E G ORG: PARKER W O DOCDATE: 06/09/78 NRC DUKE PWR DATE RCVD: 06/15/78 DOCTYPE: LETTER NOTARIZED: NO COPIES RECEIVED SUBJECT: LTR 1 ENCL 1 FORWARDING RESPONSE TO NRC REQUEST FOR INFO AND SUPPLEMENT TO APPLICANT"S LTR OF 04/27/78, CONSISTING OF ADDL INFO CONCERNING THE WASTE WATER/CHEMICAL TREATMENT PONDS AT SUBJECT FACILITY. PLANT NAME:OCONEE - UNIT 1 REVIEWER INITIAL: XJM OCONEE -- UNIT 2 DISTRIBUTER INITIAL:Pto OCONEE - UNIT 3 DISTRIBUTION OF THIS MATERIAL IS AS FOLLOWS ****************** NOTES: 1. M. CUNNINGHAM - ALL AMENDMENTS TO FSAR AND CHANCES TO TECH SPECS GENERAL DISTRIBUTION FORsAFTER ISSUANCE OF OPERATING LICENSE. (DISTRIBUTION CODE A001) FOR ACTION: BR CHIEF ORB#4 BC**W/7 ENCL INTERNAL: RE FILE*+W/ENCL NRC PDR**W/ENCL C L OELD**LTR ONLY HAN AU ER**W/ENCL. CORE PERFORMANCE BR**W/ENCL AD FOR OPER TECH**W/ENOL ENGINEERING BR**W/ENCL REACTOR SAFETY BR**W/ENCL PLANT SYSTEMS BR**W/ENCL EEB**W/ENCL EFFLUENT TREAT SYS+*W/ENCL J. MCGOUGH**W/ENCL EXTERNAL: LPDR'S WALHALLA. SC**W/ENCL TIC**W/ENCL NSIC**W/ENCL ACRS CAT B**W/16 ENCL DISTRIBUTION: LTR 40 ENCL 39 C:CINOL BR: 781670028 SIZE: 1P+5P **************************** THE END *****,***********~

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REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS) DISTRIBUTION FOR INCOMING MATERIAL 5QC51270/287

REC: CASE E G ORG: PARKER W O DOCDATE: 06/09/78 NRC DUKE PWR DATE RCVD: 06/15/78

DOCTYPE: LETTER NOTARIZED: NO COPIES RECEIVED SUBJECT: LTR 1 ENCL 1 FORWARDING RESPONSE TO NRC REQUEST FOR INFO AND SUPPLEMENT TO APPLICANT"S LTR OF 04/27/78, CONSISTING OF ADDL INFO CONCERNING THE WASTE WATER/CHEMICAL TREATMENT PONDS AT SUBJECT FACILITY.

PLANT NAME:OCONEE - UNIT 1 REVIEWER INITIAL: XJM OCONEE -- UNIT 2 DISTRIBUTER INITIAL:Pto OCONEE - UNIT 3

DISTRIBUTION OF THIS MATERIAL IS AS FOLLOWS ******************

NOTES: 1. M. CUNNINGHAM - ALL AMENDMENTS TO FSAR AND CHANCES TO TECH SPECS

GENERAL DISTRIBUTION FORsAFTER ISSUANCE OF OPERATING LICENSE. (DISTRIBUTION CODE A001)

FOR ACTION: BR CHIEF ORB#4 BC**W/7 ENCL

INTERNAL: RE FILE*+W/ENCL NRC PDR**W/ENCL C L OELD**LTR ONLY

HANA UER**W/ENCL. CORE PERFORMANCE BR**W/ENCL AD FOR OPER TECH**W/ENOL ENGINEERING BR**W/ENCL REACTOR SAFETY BR**W/ENCL PLANT SYSTEMS BR**W/ENCL EEB**W/ENCL EFFLUENT TREAT SYS+*W/ENCL J. MCGOUGH**W/ENCL

EXTERNAL: LPDR'S WALHALLA. SC**W/ENCL

TIC**W/ENCL NSIC**W/ENCL ACRS CAT B**W/16 ENCL

DISTRIBUTION: LTR 40 ENCL 39 C:CINOL BR: 781670028 SIZE: 1P+5P

**************************** THE END *****,***********~

DDC MONTHLY ACCESSION LIST

FILE LEVELS DOC* DATE

STN-50-520 TENNESSEE VALLEY AUTHORITY HARTSVILLE #3 50 04/04/78 ACCESSION NBR: 78101-0185 TASK NBR:

DuOtMENT-T-O:-0THEP -i-tHE - BC DOCUMENT SIZE: 3P NOTARIZED:.

DOCKET DATE: 04/06/78 LPDR: Y R'EPO'RT NBR: RECP: RECP AFFILIA ORG: WOLF J F ORG AFFILIAT

SUBJECT: MEMO. & ORDER RE AMEND OF THE SCHEDL SUBMISSION OF BRIEFS & TESTIMONY CON

50 04/10/78 ACCESSION NBR': 78111-0295 TASK NBR: 520 DOCUMENT TYPE: OTHERS FICHE NBR :

DOC.UMEN.T- SI-ZE. 114F.' NOTARIZED. . DOCKET DATE: 04/13/78 LPDR: YE REPORT NBR:

-RE CP-.. . RECP-AFFI L-I-A ORG: SANGER H S ORG AFFILIAT

POWELL 0 G GaUTTERM~A-N-AH

SUBJECT: APPLICANTS REPLY TO INTERVENORS PETI TEN.ESE VA.LLE AUTHoRTY WCERT OF

50 04/20/78 ACCESSION NBR: 78115-0301 TASK NBR: u vuOCuMEN*TIT TYPE-:-LE.TT. FICHE BR .

C DOCUMENT SIZE: 1P+3P NOTARIZED: N DOCKET DATE: LPDR: YE REPORT-.BR': RECP: HUGHES N B RECP AFFILIA ORG: OREILLY J P ORG AFFILIAT

SUBJECT: IE CIRCULAR NO. 78-02 RE PROPER LUBR FOR TERRY TURBINES, W/ATT IE CIRCUL ISSUED-IN.1978.

DuKE POWER COMPANY POWER BUILDING

422 SOUTH CHURCH STREET, CHARLOTTE, N. C. 28242

WILLIAM 0. PARKER,JR. June 9, 1978 VICE PRESIDENT TELEPHONE: AREA 704

STEAM PRODUCTION 373-4083

Mr. Edson G. Case, Acting Director Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C. 20555

Attention: Mr. R. Reid, Chief Operating Reactor Branch #4

U4

Reference: Oconee Nuclear Station Docket Nos. 50-269, -270, -287

Dear Sir:

In response to a request from the staff for information and as a supplement to my letter of April 27, 1978, please find attached additional data concerning the waste water/chemical treatment ponds at Oconee Nuclear Station.

Very truly yours,

William 0. Parker, Jr.

RLG:scs Attachment

ygib70028

Oconee Nuclear Station Chemical Treatment Ponds

The waste water/chemical treatment ponds (CTP) have been utilized at Oconee Nuclear Station for the retention of low level radioactive waste since August 1975. The tables attached provide monthly summaries of all inputs to and releases from the CTP.

In August 1975, the first long-lived isotopes in used Powdex resin were identified. Table 1 (attached) lists the spent powdex resin inputs from that time. The activity measured during this early time period was considered to include both that on the resin and that activity in the backwash water. The activity in the water was however, significantly less in magnitude.. In August 1976, the first identifiable tube leak at Oconee occurred in Unit 3. Small amounts of radioactivity were measured in the Powdex resin and backwash water. Activity associated with water inputs to the CTP beginning in November 1976 listed in Table 2 (attached). From this period of time until January 1977, the activity level of the CTP remained very low, permitting the use of limits based on unrestricted releases. In January 1977, an.incident occurred which required large amounts of contaminated liquid to be placed in the CTP. No releases were made from the CTP until March 1977. At this time, the releases were controlled and the activity associated with each release added to the station releases from the normal radioactive effluent release point. This data is included in Table 3 (attached). From September 1977 through January 1978, Oconee Unit 2 operated with a small magnitude primary to secondary leak. After two unsuccessful outages to locate the leaking tube, the leak was finally found and repaired in January 1978. Operation with this leak contributed to the quantities of radionuclides currently present in the CTP. The current inventory of the CTP, through April 1978, is listed in Table 4 (attached). Also included in this table is a comparison of activity with limits derived from the accident criteria contained in our August 24, 1977 and our April 27, 1978 letters. As can be seen by the data contained in Tables 1 and 2, the activity associated with the January 1977 incident was far greater than any other source.

While the limits were originally derived only for powdex, the accident limiting criteria should apply to liquid activity as well. Comparison of original liquid inventory with that removed by demineralizers in early 1977 indicate that a large part of the activity originally associated with the water is now in the sediment. Comparison of an isotopic sample taken from the pond water the week of May 1, 1978, with the current calculated inventory of each isotope indicates that greater than 95% of the pond activity is in the sediment.

Currently, all inputs are monitored.and liquid samples from the CTP are analyzed at least once per week for isotopic content. The ponds are batch released to assure that release limits are not exceeded and that an accurate account of activity in the pond is maintained.

TABLE 1

SPENT POWDEX RESIN TO CTP, pCi

VOL. 131 132 133 135 139 134 136 137 58 60 54 51 99 11 0m 59 95 24 57 95 140 140 99m DATE CF I I I I Ba Cs Cs Cs Co Co Mn Cr Mo Ag Fe Nb Na Co Zr Ba La Tc Nb

8/75 84 1690 269 3 5 9 6 2

9/75 144 298 146 5 2 6 5 2

10/75 276 370 168 8

11/75 168 300 17 13 137 945 134 10

12/75 252 71 17 97 17 15 25 4

1/76 180 291 53 54 8 12

2-5/76 NO ACTIVITY DETECTED IN RESIN SAMPLES

6/76 180 2 5 1

7/76 84 453 26 80 1 2 34 1

8/76 264 307 11 3 3 4564 363 1179 1290 2 185 7 22 32

9/76 168 390 62 1 5 391 44 103 56 1 7 1

10/76 60 299 25 1 6 301 57 325 7

11/76 252 35352 810 1620 149 2958 11912 1358 1067 11471 1625 165 548 515 2335 2218

12/76 84 2304 147 22 190 373 70 296 10

1/77 84 4356 62 402 9 621 907 169 671 693 24 23 106 1

2/77 168 4330 441 11 689 1496 181 401 65 7 4 4 3 11 8 2

3/77 124 148 119 195 480 109 330 1 7

4/77 312 190 15 1803 3177 988 674 1120 18 4 9 22

5/77 84 309 37 261 403 68 7 115 1

6/77 180 1182 72 18 367 502 455 114 448 172 4 12 4 8 1 17

7/77 48 1019 488 286 479 1756 203 141 505 12 3250 13

8/77 216 88 28970 50326 1752 796 725 137 13. 13 13 2

9/77 264 1443 2535 226 146 153 10 2 1

10/77 192 217 538 1013 123 163 134

11/77 180 256 813 1477 181 259 203 4 8

12/77 312 1939 42 5110 9707 280 276 428

1/78 204 1499 2139 3946 123 154 254 - 74 6

2/78 204 6 594 1154 37 76 164

3/78 180 22 1825 3526 22 146 68

4/78 216 1045 61 257 123 34 12453 21920 3 67 45 57

TABLE 2

LIQUID INPUTS TO CTP, pCi

VOL. 131 132 133 135 139 134 136 137 58 60 54 51 99 l10m Fe59 Nb95 Na24 Co57 Zr95 Ba140 La140 Tc 9 9m Nb

DATE CF I I I I Ba Cs Cs Cs Co Co Mn Cr Mo Ag F b N o Z a L c N

11/76 2718 91 87 87

12/76 16472 4005 1448 2166 1335 99 42 1067 8

1/77 39186 8.54E+6 7.44E+5 5.69E+5 9.80E+5 1600 483 13124 1100 129 95 1.26E+5 7.27E+4 2.75E+5

2/77 3208 1343 374 725 166

3/77 9296 674 1137 2060 486 87 17

4/77 566 66 2334 4309 115 69 158

5/77 7764 12428 1932 3431 758 94 48 1716 36 154

6/77 11535 49 71 182 448 47 38

7/77 9959 219 151 254 602 32 51

8/77 7725 18 39 11

9/77 6685 177 323 212 172 78

10/77 27652 117 244 401 60 156

11/77 7923 105 35 68 28 15

12/77 11100 400 250 330

1/78 11690 148 545 954

2/78 11020 95 248

3/78 1432 NO ACTIVITY DETECTED

4/78 1294 NO ACTIVITY DETECTED

TABLE 3

CTP LIQUID RELEASES, VCi VOL. 131 132 133 135 139 134 136 137 58 60 54 51 99 110m 59 95 24 57 95 140 140 9 9M sp,

DATE CF I I I I Ba Cs Cs Cs Co Co Mn Cr Mo Ag Fe Nb Na Co Zr Ba La Tc. Nb

3/77 96 2355 12 4118 4 18

4/77 1236 1622 2778 5 307 3

5/77 1616 12163 9633 64 14 195 11

6/77 1042 3531 6840 10 16 46 12

7/77 85 4583 8742 3 9 11

8/77 13333 27200 84 209

9/77 10758 21199 202

10/77 1154 3859 4673 172 275

11/77 711 2392 4190

12/77 172 1016 2197

1/78 219 1184

2/78 937 1781

3/78 9388 17038

4/78 2015 4018

TABLE 4

Current (ci) Isotope Activity Fraction 1 Fraction 2

Cs37 8.01 x1013 Csl34 3.10 x104 Co60 6.40 x 10-30 .002 Mn54 8.74 x 10- .001 .001 1131 8.0 x 10- 001 Co58 6.42 x 10 10 <10 Co57 5.5 x 10-5 4 <10 As110m 1.3 x 10<10 4 Zr95 - 4 x 106<1 Fe59 1 x 106 1 <104

M099 1 x 10 ~-6 1 4< 0 4 Mo99 1x1 Cr51 -1 x 106 <10- <104

.15 .77

Current Activity as of April 30, 1978

Fraction 1 - fraction of current activity of limits contaned in my April 27, 1978 letter.

Fraction 2 - fraction of current activity of accident criteria based limits contained in my August 4, 1977 letter.

DISTRIBUTION: License Fee File LFMB Reactor File (2) Docket File*269, 270 &

287 Docket Nos. LFMB R/F.(2)

50-270 JUN 2 R. Reid, DOR 50-287 197 R. Ingram, DOR

R. Diggs, ADM Duke Power Copany PDR ATTN: Mr. Tiliam 0. Parker, Jr. LPDR

Vice-President, Steam Production 422 South Church Street Charlotte, North Carolina 28242

Gentlemen:

This office has received a copy of your May 16, 1978 request which you filed with the Division of Operating Reactors. The request relates to the installation of a limited number of sleeves in the steam generators .at Oconee Unit Nos. 1, 2 and 3 to verify acceptable sleeve performance under operating conditions. The application was not accompanied by an approval fee as prescribed by Section 170.22 of.10 CFR Part 170 (copy enclosed).. Requests for approvals such as that identified above should be classified in the same manner as applications for i1cense amendments in Section 170.22. Section 170.12(c) requires that your company provide a proposed determination of the amendment (approval) class, state the basis therefor, and subrait the fee with your application for an approval or amendment.

We have determined that the requested.action falls in Class III for Oconee I ($4,000) Class I for Oconee 2 and 3 ($400 each) because the proposed action involves review of a single safety issue. You should forward fees totalling $4,800 promptly to this office Fees are payable to the U.S. Nuclear Regulatory Commission by check, draft, or money order. If after the final evaluation of your application is completed it is determined that it was incorrectly classified, you will be-refunded any overpayment or billed for any additional amount due.

If we can be of assistance to you, call 301/492-7225.

Sincerely,

orginSed bt

Wa. 0. William 0. Miller, Chief License Fee Management Branch Office of Administration

Enclosure: 10 CFR 170

omF LFM -M ADM ,LFB:ADM LFM SURNAME'

DARTE 5 ... . .

NRC FORM 318 (9-76) NRCM 0240 u. S. GOVERNMENT PRINTING OPPICEs 1076 - 626.64