ML20080J068

Application for Amend to License DPR-57,changing Tech Spec Requirements for HPCI & RCIC Sys,To Require Sys Operability When Reactor Vessel Pressure Greater than 150 Psig

ML20080J068
Person / Time
Site:	Hatch
Issue date:	02/06/1984
From:	Beckham J GEORGIA POWER CO.
To:	Stolz J Office of Nuclear Reactor Regulation
Shared Package
ML20080J070	List: ML20080J068 ML20080J118 ML20080J142
References
NED-83-648, TAC-48294, TAC-54495, TAC-98294, NUDOCS 8402140436
Download: ML20080J068 (5)

Text

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[ -i O,orgta Powr Cornpany 333 Paedmont Avenue A!!anta. Gecta a 30308 Teicphorut 404 526-7020 Ma.bng Addren Post Ottce Box 4545 Attanta. Georgia 30102 Georgia Power J. T. Beckham. ,;r.

' Vice Piesdent and Gcnera! Manager g434g fluclear Generabon I- February 6, 1984 Director of Nuclear Reactor Regulation

-Attention: Mr. John F. Stolz, Chief Operatirig Reactors Branch No. 4 Division of Licensing U. S. Nuclear Regulatory Commission Washington, D. C. 20555 NRC DOCKET 50-321 OPERATING LICENSE DPR-57 EIMIN I. HATCH NUCLEAR PLANT UNIT 1 SUBMITTAL OF HPCI AND RCIC CHANGE PROPOSAL Gentlemen:

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 (GPC) hereby proposes an amendment to the Edwin I. Hatch Unit 1 Technical Specifications (Appendix A to the Operating License). This amendment would change the equirements for the High Pressure Coolant Injection (HPCI) system and the Reactor Core Isolation Cooling (RCIC) system to require the systems to be operable when the reactor vessel pressure is greater than 150 psig.

GPC has had a review performed by our NSSS and fuel supplier, General Electric Co.', which shows that this change would have no effect on the Plant Hatch Unit 1 FSAR analyses of peak fuel cladding temperature changes during analyzed accidents and transients using NRC approved methodology.

The PRB . and the SRB have reviewed and detemined that application of these proposed Technical Specification changes would not constitute an unreviewed safety question. 'Ihe probability of occurance or the consequences of an accident or malfunction cf safety-related equipment would not be ' increased above those analyzed in the FSAR, because the Hatch Unit 1 PSAR- accident / transient analyses and performance specifications for HPCI and RCIC do not take credit for operation of HPCI or RCIC below a reactor

. pressure of 150- psig. The possibility of an accident or malfunction different from those analyzed in the FSAR would not result from these changes, since these systems would not be operated in a manner new or different from that described in the FSAR. The margin of safety as analyzed in Technical Specifications would not be reduced because the Plant Hatch t

8402140436 940206 PDR ADOCK 05000A21 M A P PDR 7 4 g q d d l17

GeorgiaPower A Director of Nuclear Reactor Regulation Attention: .. Mr. John F. Stolz Operating Reactors Branch No. 4 February 6,1984 Page Two Unit 1 Technical Specifications do not require surveillance testing of HPCI or RCIC below a reactor pressure of 150 psig. Furthemore, the Low Pressure Coolant Injection System, Automatic Depressurization System, and Core Spray

- System, are all still required to be operational in the range of reactor

. pressure between 113 and 150 psig, as is consistent with the FSAR analyses.

Instructions for incorporation of these changes (Attachment 1) along with copies of affected Technical Specification pages are enclosed.

Included with this proposal is a determination of amendment class (Attac! ment 2). We have determined this to be one Class III amendment, and have enclosed the appropriate payment.

In accordance with the requirements of 10 CFR 50.92, a Significant Hazards Review for each change to the Technical Specifications is enclosed (Attacluent 3).

Included with this submittal is a safety evaluation, performed by General Electric Company, of the the proposed changes entitled, 'HPCI/RCIC Operability Limit, Edwin I. Hatch Nuclear Power Plant - Unit 1."

Pursuant to the requirements of 10 CFR 50.92, J. L. Ledbetter of the Georgia Department of Natural Resources will be sent a copy of this letter and all applicable attaciments.

J. T. Beckham, Jr. 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.

GBORGIA POWER COMPANY By: -

g J. T. Beckham, Jf.

Sworn to and subscribed before me this 6th day of February,1984.

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xc: H. C. Nix, Jr. "* %

Senior Resident Inspector J. P. O'Reilly, (NRC-Region II)

J. L. Ledbetter uns i... .

i ATTACINENT 1 NRC DOCKET 50-321 OPERATING LICBLSE DPR-57 EININ I. HATCH NUCLEAR PLANT INIT 1 SUBMITTAL OF HPCI AND RCIC CHANGE PROPOSAL The - - proposed changes to Technical Specifications (Appendix A to Opereting License DPR-57) would be incorporated as follows:-

Remove page Insert Page, 3.5-6 3.5-6 3.5-7 '

3.5-7 3.5-8 3.5-8 l

3,5-16 3.5-16 3.5-17 3.5-17 3

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ATTACINENT 3 NRC DOCKET 50-321

[i- OPERATING LICENSE DPR-57 L EININ I. HATCH NUCLEAR PLANT UNIT 1 SUBMITTAL OF HPCI AND RCIC CHANGE PROPOSAL

1. Change "113 psig" to "150 psig" in Sections 3.5.D.I.a.(2), 3. 5.D. 3, 3.5.E.1.a.(2), and 3.5.E.3:

BASIS:

These changes would make the Technical Specification requirements consistent with the modes of HPCI and RCIC operation described in the FSAR,* and would remove the present Technical Specification inconsistency between Plant Hatch Units 1 and 2 with regard to the HPCI/RCIC minimum reactor pressure operability limit. Reviews performed in accordance with NRC approved methodology show that these changes would have no effect on the FSAR analyses of peak fuel cladding temperature changes during , analyzed accidents and transients. Therefore, these changes would not result in any increase in the probability or consequences of a postulated accident, or a. decrease in the margin of safety. No unanalyzed type of accident or transient would result from these changes. Furthermore, these changes are clearly within all acceptable criteria. Therefore, these changes are consistent with Item (vi) of the

" Examples of Amendments that are Considered Not Likely to Involve Significant Hazards- Considerations" listed on page 14,870 of the April

. 6,1983,' issue of the Federal Register.

2. Change the Bases to reflect the above changes:

BASIS:

These changes would make the Technical Specification requirements consistent with the modes of HPCI and RCIC operation described in the FSAR, and would remove the present Technical Specification inconsistency between Plant Hatch Units 1 and 2 with regard to the HPCI/RCIC minimum reactor pressure operability limit. Reviews performed in accordance with NRC approved methodology show that these changes would have no effect on the FSAR analyses of peak fuel cladding temperature changes during analyzed accidents and transients. Therefore, these changes would not result in any increase'in the probability or consequences of a postulated accident, or a decrease in the margin of safety. No unanalyzed type of accident or transient would result from these changes. furthermore, these changes are clearly within all acce criteria. Therefore, these changes are consistent with Item (vi) ptable of the

" Examples of Amendments that are Considered Not Likely to Involve Significant Hazards Considerations" listed on page 14,870 of the April 6,1983, issue of the Federal Register.

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