ML20112F731

Application to Amend License NPF-3,revising Tech Specs by Adding Limiting Conditions for Operation & Surveillance Requirements for Bypass Timers,Tmi Action Plan Item II.K.3.18.GE Bypass Timer Actuation... Encl.Fee Paid

ML20112F731
Person / Time
Site:	Hatch
Issue date:	03/19/1985
From:	Beckham J GEORGIA POWER CO.
To:	Stolz J Office of Nuclear Reactor Regulation
Shared Package
ML20112F735	List: ML20112F731 ML20112F743 ML20112F747
References
TASK-2.K.3.18, TASK-TM 1471-N, 1471N, NED-85-125, TAC-57308, TAC-57309, NUDOCS 8503270527
Download: ML20112F731 (3)

Text

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• . 1 iC _' Georgia Power Company .

p' J . . 333 Piedmont Avenue-2- AtlaAta, Georgia 30308 . .

. Telephone 404 526-7020 b Mailing Address:

Post Office Box 4545 Atlanta, Georgia 30302 '

[- ' J. T. Beckham, Jr.

Georgia Power the southem electre system Vice President and General Manager

, Nuclear Operations .

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ED-85 125

1471N March 19, 1985 l-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 W.C DOCKET 50-366 OPERATING LICENSE WF-5 EDWIN I. HATCH NUCLEAR PLANT UNIT 2 REQUEST TO AMEPO TECHNICAL SPECIFICATIONS Gentlemen:

l In accordance with the provisions of 10 CFR 50.90 as required by 10 CFR 50.59(c)(1), Georgia Power Company (GPC) proposes to ameno the Hatch Unit 2 Technical Specifications (Appendix A to Operating License WF-5). The proposed change revises the Emergency Core Cooling System Actuation Instrumentation section to reflect a planned modification to the Automatic Depressurization System; (AOS) logic. The modification is intended to satisfy the requirements of TNI Action Plan Item II.K.3.18 for extending ADS operation to transient events or loss of coolant accidents which do not result in a release of steam to the drywell but which could require depressurization of the reactor pressure. vessel to maintain adequate core cooling. Specifically, the ADS logic will be modified such that the high drywell pressure permissive in the current' logic is bypassed after a sustained low - reactor water level. The' proposed Technical Specification change involves the addition of limiting conditions for operation and surveillance requirements for the " bypass" timers.

I The setting of the bypass timers is based on avoidance of excessive fuel cladding heatup using approved Appendix K models. Details of the setpoint j

analysis are contained in the General Electric Co. report AE-52-0484,

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)GeorgidPbwerb. _

Director of Maclear Reactor Regulation Attention: __ Mr. John. F. 'Stolz, Chief -

<  : Operating Reactors Branch No.' 4

- - , March :19, -1985 Page;Two

-"Bypass Timer Calculation; for the ADS Modification for Hatch trits l' and 2",

which is included as Enclosure 1. Instructions for incorporation of ~ the-

" Technical- Specification change and copies of the affected pages are included as Enclosure 2.~

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It should -be .noted~ that GPC - committed in earlier correspondence a (ED-83-398, dated July 28, 1983) to the installation of- a manual ~ ADS -

" inhibit" switch in addition to the timed bypass of- the' high drywell

' pressure permissive. The installation of this switch, whichtransient was intended to

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prevent : automatic depressurization during an anticipated without scram (ATWS), is being reconsidered in light of the following: (1)

-  ; Mitigation? of ATWS was not a requirement of Item II.K.3.18; . and (2)

Procedures and modifications to address ATWS will not'- be finalized and simplemented for a significant time. -GPC considers the criteria of Item II.K.3.18 to be satisfied by the timed bypass alone. The need for a manual ADS inhibit switch ~will be reconsidered as part - of the resolution of the ATWS issue.

The proposed change has been reviewed and approved by the Plant Review Board and the Safety Review Board and has been determined not to involve an and the

.unreviewed safety question. The probability of occurrence consequences of an accident or malfunction of equipment 'important to safety would . not be- increased above those analyzed in the FSAR. The ADS will FSAR in the .same

.manner respond as to accidents before ~' and malfunctions analyzed in theIn some cases manua the change.

. longer be necessary. The possibility of. an accident or malfunction of a different type than any analyzed in the FSAR is not created because reliability analyses have shown no significant increase in the probability of a spurious automatic depressurization. The margin of safety as defined in the basis for any Technical Specification is not reduced by the change.

_ because -the bypass - timer setting assures that all design margins are

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maintained. The proposed change has been evaluated and determined not to involve significant hazards considerations, as discussed in Enclosure 3.

Pursuant to 10 CFR 50.91, J. L. Ledbetter of the Georgia Department of Natural Resources w'M be provided with a copy of this submittal.

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m GeorgiaPower A Director of Nuclear Reactor Regulation Attention: Mr. John F. Stolz, Chief Operating Reactors Branch No. 4

~ MaIch 19,- 1985 Page Three Payment of the appropriate licensing fee is enclosed.

J. T. Beckham, Jr. states that he is Vice PIesident 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: be gJ. T. Beckham, Jr. f Swo'In to subscribed before this 19th day of MaIch,1985.

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1 g No a -Public Notary Pub!;c, Georgia, sf, *t large

1. 1. '*" EXP res i July 26,1983 JH M Enclosures xc: H. C. Nix, Jr.

Senic r Resident Inspector J. N. Grace, (MIC-Region II)

J. L.- Ledbetter Q mm