ML20024D525
| ML20024D525 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 08/01/1983 |
| From: | Gucwa L GEORGIA POWER CO. |
| To: | Stolz J Office of Nuclear Reactor Regulation |
| References | |
| NED-83-411, TAC-51851, TAC-518511, NUDOCS 8308050185 | |
| Download: ML20024D525 (1) | |
Text
Georgia Power Company 333 P+dmont Avense Atlanta. Georg a 30308 Telephone 404 526 6526 Matog Address:
Post office Box 4545 A:fanta Georg:a 30302 Georgia Power L. T. Gucwa
' > smtruvn e(ctrc s1. stem Ch ef thc! ear Eng;ncer Power Generation Departmer NED-83-411 August 1, 1983 Director of Nuclear Reactor Regulation Attention:
Mr. John F. Stolz, Chief Operating Reactors Branch No. 4 Division of Licensing U. S. Nuclear Regulatory Commission Washington, D. C.
20555 NRC DOCKEIS 50-321, 50-366 OPERATING LICENSES DPR-57, NPF-5 EIMIN I. HA'ICH NUCLEAR PIANT UNITS 1, 2 RETRANSMI' ITAL OF JUNE 21, 1983 LEITER Gentlemen:
Our letter of June 21, 1983, giving additional information for the expedited relief necessary to perform the feedwater sparger repair, was telecopied to you on that date.
Due to an administrative error, the letter was never formally transmitted. Attached is a copy of the subject letter.
If you should have any further questions in this regard, please contact this office.
Very Truly Yours,
[N OM L. T. Gucwa MJB Attachttents xc: J. P. O'Reilly H. C. Nix, Jr.
Senior Resident Inspector
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June 21, 1953 5
Director of Nuclede Reactor Regulation
' Attention:
Mr. John F. Stolz, Chief
. Operating Reactors Branch No. 4 Division of Licensing
'U. S. Nuclear Regulatory Commission WashinE on, D. C.
20555 t
WRC DOCKET 50-366 OpstATING LICENER HPF-5 EDWIN 1. HATCH NUCtlAR PLANT UNIT 2 EXPEDITED RELIEF - ADDITICHAL INFORMATION Gentlemens As discussed in Georgia Power Company's (CPC) lettee dated June' 20,
- 1983, we request expedited attention to our roguest for Technical specification' relief from the requirement to have a CROUP 11 isolation to low sl nal (LL1). The following additional occur on a reactor water level 5
Information is submit.teri in support of that request.
Revision The Plant Review board has reviewed plant procedure BNP-2-10967 0,
" Water Level Control During Feedwater Sparger Bracket Replacement and Reactor vessel Inspection". This procedure, which is to be implemented upon approval of our proposed change to the Technical speelfications, provides for manual actuation of the automatic function which is being temporarily are in defeated ~while the bracket replacoinent and vessel,inspec tico progress.
The procedure requires, in the Prercquisites section, that no work is to be done which has the potential for draining the reactor vessel this procedure is in progress.
The procedure further while work under a minimum, one loop of RHR and one loop of Core Spray be requires that, as This available for injection into the reactor vessel should the need arise.
leaves one loop of RHR available for shutdown cooling which will not interfere with the capability of the other RHR loop to inject into the vessel.
A data sheet which is part of_the procedure requires recording of reactoe water level every 1$ minutos with appropriate action requirements If a 10 inch should the level change.
Two levels of action are provided.
drop in lovel occues over a 15 minute period as recorded on the data sheet, to be restored by increased flow from the Control Rod Drive level is If level continues to drop to the ~100 inch level, one loop of Core system.
Spray is to be initiated.
The procedure further es11s for actions to be taken to protect personnel workin5 in the reactor vessel in the event of any sudden increase in water level.
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e Director of Nuclear Reactor Regulation U. S. Nuclear Regulatory Cossalssion Washington, D. C.
20555 June 21, 1983 Page 2 In addition to the normal implementing procedure requirements Geor51a Power Company will provide the following additional control measures durin5 that period of time that the Croup 11 leolation is not required for shutdown coolin5 on reactor water level low signal (LL1):
l Maintenance Roguests (MR's) that are currently belD5 worked on Unit 2 will be placed on hold and released after review by the i
shift supervisor to ensure that the work does not have the Potential for draining the vessel.
Quality Assurance (QA) personnel will independently observe that'the requirements of the procedure are bein5 met.
In our safety ovaluation of the requested action under the requiremente of 10 crR 50.59 and 10 CFR 50.92, attention has been focused on the fact that the actions pecposed will not lnerease the probability of a pipe break or malfunction of equipment that could cause a loss in reactor water level above that residual level which exists for any plant in the Cold Shutdoern condition. On that basis we are able to state that the amendment would not involve a significant increase in the probability or consequences of an accident previously evaluated.
Inasmuch as the FSAR covers a spectrum of postulated breaks which cause water level to fall below the level at which we will take action, as stated above, the possibility of a new or different kind of accident has not been created. The availability of multiple sources of makeup water to the vessel In conjunction with the compensatory measures addressed in the procedure discussed above assures that mar 51ns of safety
- are belp5 maintained and that this request does not involve a si5nificant reduction in margins of safety.
I Very Truly Yours j
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J. T. Beckham, Jer -
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RDB/rb xc: H.C. Nix,Jr.
Senior Resident Inspector J. P. O'Reilly, (NRC R*E 0h II)
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