ML19339B575
| ML19339B575 | |
| Person / Time | |
|---|---|
| Site: | Hatch |
| Issue date: | 10/29/1980 |
| From: | Widner W GEORGIA POWER CO. |
| To: | Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML19339B576 | List: |
| References | |
| NUDOCS 8011070277 | |
| Download: ML19339B575 (3) | |
Text
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E731 C%C'? 308 J645 NYM's!fEso GeorgiaPower W. A. Widne, a a;er Octcber 29, 1980
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Director of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C.
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9' NRC DOCKET 50-321 OPERATING LICENSE DPR-57 EDWIN I. HATCH NUCLEAR PLANT UNIT 1 PROPOSED TECHNICAL SPECIFICATION CHANGE J
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5 In accordance with the provisions of 10 CFR 50.90, as required by the provisions of 10 CFR 50.59(c)(1), Georgia Power Company hereby proposes an amendment to the Technical Specifications (Appendix A to the Operating License).
The proposed amendment would change the overly restrictive provisions of Section 3.5.J.2a to be consistent with the provisions of Section 3.7.1.2 action item a.4 of the Plant Hatch Unit 2 Technical Specifications which have been previously reviewed and approved by the NRC staff. This change would allow the plant to operate for up to seven days with both the diesel generator and the standby service water pump inoperable.
As noted in the bases for 3.5.J/4.5.J, diesel IB has a manual backup water supply available from the Unit 1 Division 1 or Division 2 plant service water subsystems, so that, during a loss of the standby service water pump due to breakdown or maintenance, either division of the PSW system can manually be aligned to supply cooling water to the 18 diesel.
Only one of the Division 1 PSW pumps and one of the Division 2 PSW pumps are required for cooling diesel generators lA and 1C, respectively, while the standby service water pump provides adequate cooling water to diesel generator 18.
In the event that the standby service water pump is inoperable, the HNP-1 Division 1 - Division 2 intertie supply piping can be aligned to cool the IB diesel as noted above.
In this condition, one PSW pump is capable of supplying the cooling requirements for the reactor i
building cooling system, the control room air conditioners, and the l A, i
18, and 1C diesel generators. The PSW system can supply all power generation systems at full load and the diesel geraom with redundancy if. one PSW pumo and/or the standby service water pump are inoperable.
A single active failure of a component is required in this condition to cause loss of I diesel generator. This condition is within the envelope of accidents analyzed in the Final Safety Analysis Report. Hence, when the ap (
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Director of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission October 29, 1980 Page Two standy service water pump is operable along with a single diesel generator, only the limiting condition for operation due to the loss of the diesel generator need be considered. It is therefore proposed that the wording of 3.5.J.2a be revised to allow credit for the alternate service water cooling source to the IB diesel generator. This change would make the Unit 1 and 2 Technical Specifications consistent with respect to loss of the standby service water pump.
The Plant Review Board and the Safety Review Board have reviewed and approved the proposed amendment and have concluded that the proposed amendment does not constitute an unreviewed safety question. The possibility of a new accident or malfunction not previously considered has not been created; nor have the consequences of previously analyzed accidents or malfunctions been changed. Margins of safety have not been reduced nor operating limits changed in a nonconservative direction.
The proposed amendment is a Class III amendment. Accordingly, a check for $4,000.00 is enciesed.
Very truly yours, j
W. A. Widner WEB /mb Enclosures Sworn o and subscribed before e this 29th of October,19gr.
Notary PubHc. Georipa, state at ae
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My Commisson Expres Sept. 20.1963 Notary Public xc: Max Manry R. F. Rogers, III
ATTACHMENT 1 NRC DOCKET 50-321 OPERATING LICENSE OPR-57 EDWIN I. HATCH NUCLEAR PLANT UNIT 1 4
i FEE ASSESSMENT i
Pursuant to 10 CFR 170.12 (c), Georgia Power Canoany has evaluated the attached proposed amendment to Operating License DPR-57 and has determined that:
a)
The proposed amendment does not require the evaluation of a new Safety Analysis Report or rewrite of the facility license; b)
The oroposed amendment does not contain several complex issues, does not involve ACRS reviev, or does not require an environmental impact statement; c)
The proposed amendment does not involve a complex issue, an environ-j mental issue or more than one safety issue; d)
The proposed amendment does involve one single issue; namely, j
correction of an overly restrictive Specification 3.5.J.2a on the j
standby service water pump; and e)
The proposed amendment is therefore a Class III amendment.
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