ML20083K074
| ML20083K074 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 12/22/1978 |
| From: | Whitmer C GEORGIA POWER CO. |
| To: | Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20083K077 | List: |
| References | |
| TAC-08194, TAC-08195, TAC-8194, TAC-8195, NUDOCS 7901030213 | |
| Download: ML20083K074 (2) | |
Text
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-Q Ge:rgis Powir Comoany
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P:t 0 hee Box 4515 i
M eta Georga 30333 s
Te ecyone 404 522 6050 L
cnar r. wNtmer Georoia Power O
.a wes.mnt E; v m December 22, 1978 Director of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C.
20555 NRC DOCKET 50-366 OPERATING LICENSE NPF-5 EDWIN I. HATCR NUCLEAR PLANT UNIT 2 j
MULTIPLE SUBSEQUENT SAFETY / RELIEF VALVE ACTUATION EVALUATION-Gentlemen:
The Nuclear Regulatory Commission's letter of March 22, 1978, requested I
Georgia Power Company to provide a plant unique assessment of the effects 1
of multiple subsequent actuations of safety / relief valves (SRVs) following an isolction event ~for Plant Hatch Unit 2.
A report entitled " Multiple Subsequent SRV Actuation Evaluation for E. I. Hatch Nuclear Plant Unit 2",
transmitted to'the NRC by our letter of July 27, 1978, contains a structural
. evaluation of the Plant Hatch Unit 2 Torus Support System (TSS).
[
As indicated in our July 27, 1978, letter, the structural evaluation'-
l contained in the (original) report was based on the results of an SRV i
discharge test performed at the Peach Bottom Nuclear Plant Unit 2.
In October, 1978, several tests to determine a plant unique TSS response to SRV discharges were conducted at Plant Hatch Unit 2.
Subsequently, the i
original report has been updated incorporating the preliminary data obtained
- during the SRV discharge tests. A report entitled " Multiple Subsequent Safety / Relief Valve Action Evaluation for E. 'I.
Hatch Nuclear Plant Unit 2, i
Revisirn 1" included as an enclosure to this transmittal contains a structural evaluation of the Plant Hatch Unit 2 TSS, using the preliminary data (column loads and torus shell stresses for a single SRV " cold pop") from the Plant Hatch Unit 2 SRV discharge tests. The bases and conservatisms such as attenuation factors, number of valves undergoing " hot pop" simultaneously,
" hot pop" factor, etc. used in this reevaluation are essentially the same j
as those that were used in the original report.
The results of our reevaluation, using the preliminary data from the tests, confirm the conclusions arrived at in the original report with regard dbLATURY DOCif FLE COPE y
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GeorgiaPower A Director of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission December 22, 1978 Page 2 to satisfying the acceptance criteria stated in your letter of March 22, 1978. Accordingly -it is the conclusion of Georgia Power Company that the Edwin I. Hatch Nuclear Plant Unit 2 can operate with an adequate safety margin without undue risk to the health and safety of the public.
Yours very truly, C
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as. F. Whitmer WEB /KRI/mb a,
Enclosure 1
S rn to and subscribed befo me this 22nd day of December, 1978.
v, / Notary Puchc. Georgra,dState atiggggry Public My Commission Empires Sept. 29,1981 xc: Ruble A. Thomas 4
George F. Trowbridge, Esquire Y
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