ML19317H158
| ML19317H158 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse, Arkansas Nuclear  |
| Issue date: | 03/31/1978 |
| From: | David Williams ARKANSAS POWER & LIGHT CO. |
| To: | Reid R Office of Nuclear Reactor Regulation |
| References | |
| 1-038-17, 1-38-17, NUDOCS 8004210624 | |
| Download: ML19317H158 (4) | |
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REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
DISTRIBUTION FOR INCOMING MATERIAL 50-313 REC: REID R W ORG: WILLIAMS D H DOCDATE: 03/31/78 NRC AR PWR & LIGHT DATE RCVD: 04/10/7@
ECCTYPE: LETTER NOTARIZED: NO COPIES RECEIVED
SUBJECT:
LTR 1 ENCL 40 FORWARDING REPT PROVIDING JUSTIFICATION FOR CONTINUED OPERATION OF SUBJECT FACILITY, SINCE UNIT 1 DID NOT ACHIEVE 100% PWR OPERATION BY 01/01/78.
PLANT NAME: ARKANSAS - UNIT 1 REVIEWER INITI AL:
XJM DISTRIBUTOR INITIAL: A[
+**************** DISTRIDUTION OF THIS MATERIAL IS AS FOLLOWS ******************
l REACTOR VESSEL MATERIAL SURVEILLANCE (DISTRIBUTION CODE A021)
FOR ACTION:
BR CHIEP-REID**W/3 ENCL ZHETZIG**W/ ENCL INTERNAL:
T G FILE *4 NRC PDR**W/ ENCL I i'EwW2-ENCL._ -_.
OELD**LTR ONLY MIPC**W/ ENCL HANAUER**W/ ENCL PAWLICKI**W/ ENCL EISENHUT**W/ ENCL SHAO**W/ ENCL BAER**W/ ENCL BUTLER **W/ ENCL GRIMES **W/ ENCL HAZEL TON n *W/ ENCL HOGE**W/ ENCL R GAMBLE **W/ ENCL RANDALL**W/ ENCL EXTERNAL:
LPDR'S RUSSELLVILLE, AR**W/ ENCL TIC **W/ ENCL NSIC**W/ ENCL ACRS CAT B**W/16 ENCL DISTRIBUTION:
LTR 40 ENCL 39 CONTROL NBR: t-74UlW '
4-f SIZE: ;1P+2P oco********************************
THE END
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ARKANSAS POWER & LIGHT IU? "
- UTTLE ROCK, ARKANSAS 72203 (50 NE@Og",' /.
POST OFFICE BOX 551 ifhh[y March 31, 1978 A01 i II OECE?vt0 1-038-17 IO DI8 4
dud *AANat Director of Nuclear Reactor Regulation F,\\
8"'I N ATTN:
Mr. R. W. Reid, Chief Operating Reactor Branch #4 O
y U. S. Nuclear Regulatory Commission Washington, D. C.
20555
Subject:
Arkansas Power 6 Light Company Arkansas Nuclear One-Unit 1 Docket No. 50-313 License No. DPR-51 Reactor Vessel Material Surveillance Program (File:
M-1, 0520.2)
Gentlemen:
In accordance with Arkansas Nuclear One-Unit 1 (ANO-1) Technical Specification 4.2.8, please find attached a report to provide justification for continued operation of ANO-1.
This report is provided as Davis-Besse Unit 1 did not achieve 100% power operation by January 1,1978.
Very truly yours,
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Daniel H. Williams Manager, Licensing DHW:DGM:nf U
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MEMSEA MlOOLE" SOUTH UTsuTIES SYSTEM
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ARKANSAS POWER 6 LIQlT COMPANY'S REPORT FOR JUSTIFICATION OF CONTINUED OPERATION OF ARKANSAS NUCLEAR ONE - UNIT 1 By letter dated August 17, 1976, and supplemented by letters dated December 20 and 22, 1976, and January 13, 1977, we requested that the exemption to Appendix 11 of 10CFR Part 50 granted for ANO-1 by letter dated June 11, 1976, be modified to allow indefinite operation of ANO-1 with the remainder of the reactor vessel surveillance capsules to be irradiated at Toledo Edison Company's Davis-Besse Unit 1, and the ANO-1 Technical Specifications to be revised to allow the remainder of the ANO-1 reactor vessel surveillance capsules to be irradiated at Davis-Besse Unit 1.
By Amendment No. 22 to the ANO-1 Operating License No. DPR-51 dated April 1, 1977, the above requested exemption to Appendix G, 10CFR Part 50 and revision to the ANO-1 Technical Specifications were found to be acceptable and, therefore were approved conditioned on satisfactory and timely operating time accumulation at Davis-Besse Unit No. 1.
That satisfaction is ultimately based on the availa-bility of data to establish longer term pressure-temperature limits prior to the expiration of the applicability of the existing limits.
At the end of 345 EFPD's of operation of Arkansas Nuclear One - Unit 1 (ANO-1),
capsule ANI-E was withdrawn and the contents were tested.
Based on the results of these tests the ANO-1 pressure-temperature limits of the reactor coolant pressure boundary were modified and these new limits are applicable through 5 effective full power years (EFPY) of operation. As of February 2, 1978, ANO-1 completed the second cycle of speration.
The accumulated days of service as of this date were 772 EFPD.
The Toledo Edison Company's Davis-Besse Unit 1, serving as the host reactor for the remaining ANO-1 surveillance capsules, is expected to be at 1004 power by early Bby.
The length of the first Davis-Besse 1 cycle will be approximately 450 EFPD, and at the conclusion of this cycle another ANO-1 capsule will be withdrawn and evaluated. Conservatively allowing one year for testing the irradiated specimens, analy ing the results, and modifying the pressure-temperature limits, ANO-1 will have accumulated 4.5 EFPY of operation. The current pressure-temperature limits will be valid through this period of opera-tion.
The ANO-1 capsule to be withdrawn at the conclusion of the first Davis-Besse 1 cycle will receive an accumulated fluence of approximately 6.5 x 1018 2
n/cm (E> 1 MeV) which corresponds to 12.4 EFPY with respect to the reactor vessel 1/4 T location. Therefore, before the expiration of the current pressure-temperature limits which are applicable through 5 EFPY surveillance data will be available and the limits will be modified to extend their applicability to 12 EFPY. Before 12 EFPY have been accumulated by ANO-1, additional surveillance data will be available which will permit a further extension of the operating limitations.
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1herefore we 'believe the continued operation of ANO-1 with the reactor vessel surveillance program conducted at Davis-Besse Unit No. 1 is
' justified and, further, does not compromise the viability of uninterrupted pow 3r operation of ANO-1 after 5 EFPY.
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