ML20081J231

Application for Amend to Licenses DPR-57 & NPF-5,changing Tech Specs to Incorporate Revised Specs for Snubber Inservice Surveillance Requirements

ML20081J231
Person / Time
Site:	Hatch
Issue date:	10/27/1983
From:	Head G GEORGIA POWER CO.
To:	Stolz J Office of Nuclear Reactor Regulation
Shared Package
ML20081J235	List: ML20081J231 ML20081J240
References
NED-83-511, TAC-08298, TAC-08310, TAC-48362, TAC-48363, TAC-8298, TAC-8310, NUDOCS 8311080377
Download: ML20081J231 (3)

Text

--

cmga Pew comany 333 Pedmcnt A.enue Ama Georpa 303c8 Ick(hone 4015?6 7tM3 M.Mnq Add',050 Por orc Eb 4545 A!.aMA Gea a 303r2 G.F. Head ew a-a ; , "

Sere V,m P- 1 ao NED-83-511 October 27, 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 DOCKETS 50-321, 50-366 OPERATING LICENSES DPR-57, NPF-5 EDWIN I. HATCH NUCLEAR PLANT UNITS 1, 2 REQUEST 10 AMEND TECINICAL SPECIFICATIONS Gentlemen:

In accordance with the provisions of 10 CFR 50.90, as required by 10 CFR 50.59(c)(1), Georgia Power Company hereby proposes to amand the Technical Specifications (Appendix A to the Operating License) for each Hatch unit to incorporate revised specifications for snubber inservice surveillance requirements. Pursuant to 10 CFR 50.92, J. L. Ledbetter of the Georgia Department of Natural Resources will be sent a copy of this submittal. The proposed changes to the Technical Specifications are submitted to implement revised snubber inservice surveillance requested by the D. G. Eisenhut (NRC) letter dated November 20, 1980. Specific instructions for incorporation of the changes and the changes are included as Enclosures 1 and 2 for Ihtch

Units 1 and 2, respectively.

The proposed changes to the Technical Specifications replace those submitted previously by our letters dated April 14, 1981 and April 30, 1982. He aforementioned previous submittals were withdrawn by our letter dated May 31, 1983. Revision of our earlier submittals was necessary due to the inadvertent deletion of a statement concerning inaccessible snubber inspection frequency, the need to provide the Hatch Unit 1 safety-related rhechanical snubber listing which was unavailable at the time of the original submittal due to snubber modifications / replacement, and to reflect current industry standards concerning snubber operability.

The proposed changes to the Hatch Units 1 and 2 Technical Specifications provide for total revision of the existing snubber inservice surveillance requirements. The key items addressed in the proposed Technical Specification changes are the addition of new requirements for visual inspection acceptance criteria, an engineering evaluation of piping due to failed snubbers, an increase in functional test sample size, the addition of surveillance requirements for mechanical snubbers, and service life monitoring.

I f 8311080377 831027 PDR ADOCK 05000321 P PDR hI

'Ig

y Georgia Power 1

-Director of Nuclear Reactor Regulation Attention: Mr. John F. Stolz, Chief Operating Reactors Branch No. 4 October 27, 1983 Page h o

%e proposed changes to the Hatch Unit 1 Technical Specifications have been written in Standard Technical Specification format. As a result of the format change and total revision of the snubber surveillance Technical Specifications, all pages pertaining to or referencing snubbers (shock suppressors) modified by huendments 37, 43, and 51 will be superseded.

Se proposed changes to the Technical Specifications for the two Hatch units have been reviewed and approved by the Plant Review Board and the Safety Review Board and have been determined not to constitute an unreviewed safety question. The probability of occurrence and the consquences of an accident or malfunction of equipnent important to safety would not be increased above those analyzed in the FSAR because the operation of safety-related quipnent is not affected by the proposed changes. The possibility of an accident or malfunction of a differt _ type than analyzed in the FSAR would not result fran these changes because no new modes of failure are introduced. %e margin of safety as defined in the basis for any Technical Specification would not be reduced by these changes because operation of the plant would renain within previously analyzed limits. The proposed changes have been evaluated and determined not to involve significant hazards considerations. his evaluation is docunented in Enclosure 3.

As discussed in Enclosure 4, the proposed change to the Hatch Unit 1 hchnical Specifications has been evaluated to be a single Class III anendment while that for Fatch Unit 2 has been evaluated to be a single Class I anendment. We anendment fee of $4,400.00 was subnitted previously by Georgia Power Canpany check no. 916412 in our letter dated April 14, 1981.

G. F. Head states that he is Vice President of Georgia Power Company and is authorized to execute this oath on behalf of Georgia Power Canpany, and that

, to the best of his knowledge and belief the facts set forth in this letter are true.

GBORGIA POWER O NPANY By: . F . /1 ,

G.'F. Head Sworn to and subscribed before me this 27th day of October,1983.

ff -

pt Public Enclosure Notary PMc, Geeps, Swe at tage My Cornmission Exp,res My 2% l985

, , _ - . - , _ . _ _ . _ . . . _ . - . . . -- -,, .- _ _. ._ , _ _ . ~ _ .--

GeorgiaPower A i

Director of Nuclear Reactor Regulation Attention: Mr. John F. Stolz, Olief Operating Reactors Branch No. 4 October 27, 1983 Page 'Ihree xc: J. T. Beckhan, Jr.

H. C. Nix, Jr.

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

J. L. Ledbetter

'f r

_