ML20004B049
| ML20004B049 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 05/22/1981 |
| From: | William Jones OMAHA PUBLIC POWER DISTRICT |
| To: | Eisenhut D Office of Nuclear Reactor Regulation |
| References | |
| GL-81-19, NUDOCS 8105270155 | |
| Download: ML20004B049 (2) | |
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1623 MARNEY 8 OMAMA. NESRASKA 64i02 a TELEPHONE S38 4000 AREA CODE 402 May 22, 1981 p \\ t% fpV'/
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Mr. Darrell G. Eisenhut, Director
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Office of Nuclear Reactor Regulation
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Division of Licensing Washington, D.C.
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References:
- 1) CEOG Letter from K. P. Bask 3a to Darrell Eisenhut dated May 15, 1981.
- 2) OPPD Letter from W. C. Jones to Director of Ni1R dated March 10, 1980.
Dear Mr. Eisenhut:
Subj ect: Reactor Vessel Pr ssurizer Thermal Shock This letter is in response to Generic Letter 81-19 of April 20, 1981, on thermal shock to reactor pressure vessels. Reference 1 transmitted to you the CE Owners Group's response to your request at a meeting on March 31, 1981, and responds to further reports and clarifications which you provided at a meeting on April 29, 1981. Omaha Public Power Dis-trict intends to fully participate in the CE Owners Group program on the issue of reactor vessel prersurized thermal shock. Reference 1 outlined the proposed program which will be acted on at the CE Owners Group meeting on June 4, 1981. Omaha Public Power District will participate in th> program defined at this meeting.
Omaha Public Power District has removed the first surveillance capsule
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from its Fort Calhoun Station. The reports on this capsule are con-l tained in References 2 and 3.
The measured fluence at 2.6 EFPY was 5.1 2
x 1018 n/cm. The original target, contained in the FSAR was 1.8 x 2
3 1018 n/cm. The calculations for the specimen are contained in Reference 3 and show a calculated fluence of 5.1 x 1018 n/cm. The calculations 2
show an 20L fluence of 4.2 x 1019 n/cm2 versus a design estimate of 2.9 i
x 1019 n/cm. Therefore, the measured fluence and calculations show the 2
fluence to be a factor of 2.1 higher than the design estimate. At E0C 6 the vessel will have received a fluence equivalent to approximately 5.3 EFPY exposure. Based upon the calculations contained in Reference 1, it fool 5
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Mr. Darrell G. Eisenhut May 22, 1981 Page Two is estimated that reactor vessel pressurized thermal shock will not become a problem at the Fort Calhoun Station for at least another four (4) EFF. Therefore, the District concludes there is sufficient time for i
an orderly resolution of this problem.
Sincerely, Aw yp/
W. C. Jones j
Division Manager Production Operations
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