ML19347E257
| ML19347E257 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 04/16/1981 |
| From: | Widner W GEORGIA POWER CO. |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-2.K.3.03, TASK-2.K.3.16, TASK-2.K.3.18, TASK-2.K.3.57, TASK-TM TAC-45595, TAC-45596, NUDOCS 8104240402 | |
| Download: ML19347E257 (2) | |
Text
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G orgo Pont Corepany 333 Pecmoat Avenue At'anta Georg>a 30308 Teiet.none 404 526 6526 f/gng Address Pest Ofs e Bas 4545 c
Aranta George 30302 GeorgiaPower ff4! $(Wert'.'ItCfrC Sy0ft*/n keP SPIII Ib 1901
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dcnt and General Manager Nuctear Generation
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- kf Director of Nuclear Reactor Regulation App"oOIS8 4 6
U. S. tbclear Regulatory Commission g k @ roer Washington, D. C.
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EDWIN I. HATCH NUCLEAR PLANT UNITS 1, 2 NWEG-0737 ITEMS II.k.3.16 AND II.k.3.18 SUPPLEMENTAL COMMENTS Gentlemen:
Our letter of April 1,1981, deferred endorsement and any comitment of future actions pending completion of our review of the BWR Owners' Group generic reports on NUREG-0737 Items II.k.3.16 and II.k.3.18.
With the conclusion of that review, we hereby endorse the content and conclusions of those reports, ncting that the recommendations of the II.k.3.18 report are still under consideration as discussed below.
Further, pursuant to the requirements of Item II.k.3.16, we hereby submit our plans for reduction of Safety Relief Valve (SRV) failures.
We propose a program consisting of three actions which will result in an improvement factor of approximately ten over the reliability of the EWR-4 three-stage Target Rock SRVs described as the base case in the BWR Owners' Group report.
This assumed base case is similar to the original design of SRV equipment of the Hatch facility.
Those actions are (1) replacement of three-stage pilot assemblies on the SRVs with two-stage assemblies, (2) resetting of the Main Steam Isolation Valve (MSIV) low-level trip setpoint to a lower level, and (3) adoption of a procedure to manually open appropriate SRVs following an automatic prersure-relief action.
The use of two-stage pilot asemolies on the Plant Hatch SRVs was previously reviewed by the NRC staff and implemented.
Item 2 above, reset of the MSIV setpoints, is currently undergoing engineering analysis to determine the optimum method of implementation.
The modification will be submitted for NRC pre-implementation review as part of the normal technical specification revision process.
Implementation of this item will be scheduled for completion during the refueling outage following approval of the technical specification revision.
Procedural requirements for the manual opening of a E81V, item 3 above, as described in the generic report will be implemented as part of the procedural revisions associated with the emergency procedure guidelines developed as part of the program for compliance with NUREG-0737.
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GeorgiaPower A Director of Nuclear Reactor Reguation U. S. Nuclear Regulatory Commission Page Two April 16, 1981 The recommendations of the generic report on Itsn II.K.3.18 are under evaluation and proposed modifications - to the automatic depressurization system (ADS) actuation
- logic, if
- any, will be submitted for pre-implementation review by April 1, 1982.
Should you have any questions regarding this letter, please contact my office.
W. A. Widner states that he is Vice President of Georgia Power Company and is authorized to execute this oath on behalf of Georgia Power Company, and that to the best of his knowledge and belief the facts set forth in this letter are true.
GEORGIA POWER COMPANY By:
W. A. Widner Sworn to and subscribed before me this 16th day of April,1981.
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Noury Public, Georgia. State at Large
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H. Manry R. F. Rogers, III o
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