ML20040F891
| ML20040F891 | |
| Person / Time | |
|---|---|
| Site: | Trojan File:Portland General Electric icon.png |
| Issue date: | 02/05/1982 |
| From: | Withers B PORTLAND GENERAL ELECTRIC CO. |
| To: | Eisenhut D Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-2.K.2.13, TASK-TM GL-81-19, TAC-46909, NUDOCS 8202100432 | |
| Download: ML20040F891 (2) | |
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Ba1 D V#rers Vce PreMy1 February 5, 1982 Trojan Nuclear Plant Docket 50-344 License NPF-1 O
Mr. Darrell G. Eisenhut, Director
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Division of Licensing f, s office of Nuclear Reactor Regulation j
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Dear Mr. Eisenhut:
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fp Reactor Vessel Thermal Shock e
i NRC Generic Letter 81-19 NRC Generic Letter 81-19, issued April 20, 1981, requested responses identifying the specific action we propose to take regarding the subject of thermal shock to Trojan's reactor pressure vessel.
As indicated in our letter dated May 21, 1981, PGE participated in the Westinghouse Owners Group (WOG) activities on this issue. Westinghouse's
" Summary 2eport on Reactor Vessel Integrity for Westinghouse Operating Plants", WCAP-10019, was the culmination of the WOG efforts toward resolving this issue. WCAP-10019 was transmitted to the NRC by owners group letter OG-66, dated December 30, 1981.
Based on the results of the generic 4-loop plant fracture mechanics analysis of Trojan under postulated limiting transients, it is concluded that there is no impairment of pressure vessel life due to thermal shock.
PGE recognizes the conservative nature of the generic analysis and agrees with the analysis techniques and conclusions of WCAP-10019. Accordingly, S
/6 F202100432 820205 PDR ADOCK 05000344 P
PDR Street Portand. Ceegon 972C4
o N Gerier-d MCoriyasri3r Mr. Darrell G. Eisenhut-February 5, 1982 Page two 1
this issue is considered to be closed with no further action by PGE necessary.
Sincerely,
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Bart D. Withers Vice President Nuclear c:
Mr. Lynn Frank, Director State of Oregon Department of Energy i
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