ML19324B874

Transmits Proposed Program for Completing Individual Plant Exam Process,Per Generic Ltr 88-20 & NUREG-1335.Program Should Identify Method & Approach Selected for Performing Exam

ML19324B874
Person / Time
Site:	Hatch
Issue date:	10/27/1989
From:	Hairston W GEORGIA POWER CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
RTR-NUREG-1335 GL-88-20, HL-785, NUDOCS 8911080510
Download: ML19324B874 (3)

Text

' Geoig a Power Cortpany

,

• 333 Piedmont Avenue

, AUata. Georg;a 30308 Totephone 404 526-3t95

- Mailing Ackfress.

40 invofnest Center Parkway

, Post Ofhce Box 1295 -

ne bS B 8 5 81 I!c scut!cn t+ttnc wrom W. G. Hairston, lit Senior Vee President t' Nuclear Operations HL-785 0341V october 27, 1989 U.S. Nuclear Regulatory Commission ATTN: . Document Control Desk

! Hashington, D.C. 20555 PLANT HATCH - UNITS 1, 2 NRC DOCKETS 50-321, 50-366 OPERATING LICENSES DPR-57, NPF-5 RESPONSE TO GENERIC LETTER NO. 88-20 Gentlemen

L On' September 1, 1989, the Nuclear Regulatory Commission (NRC)

L published in the Federal Register a notice announcing the availability of

!- NUREG-1335, " Individual Plant Examination: Submittal Guidance," and

- initiation of the Individual Plant Examination (IPE) process. In L accordance: with Generic Letter No. 88-20, licensees are required to l . submit within 60 days of this Federal Register notice, their proposed

programs for completing their IPEs. The purpose of this letter is to transmit the proposed program for completing an IPE for the Edwin I.

l Hatch Nuclear Plant (HNP).

1 According to the Federal Register notice, the proposed program should:

l' (1) Identify the method and approach selected for performing the IPE; (2) Describe the method to be used, if it has not been submitted for staff review (description may be referenced); and (3) Identify the milestones and schedules for performing the IPE and submitting the results to the NRC.

The following information is provided concerning the proposed program for completing the HNP IPE in response to Generic Letter No. 88-20.

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• EDR ADOCK 05000321 PNU f j

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Georgia Power A U.S. Nuclear Regulatory Commission october 27, 1989 Page Two Method Acoroach - Georgia Power Company proposes to perform a Level I Probabilistic Risk Assessment (PRA) to satisfy the Front-End (core damage portion) IPE requirements for HNP. The HNP Level I PRA will use information available from previously completed Level I PRAs and other pertinent sources such as selected NRC and EPRI publications.

The Back-End (containment performance portion) IPE for HNP will be based on the general concept of a Level II PRA. During the performance of the Back-End analysis, information available from previously performed Level II PRAs, and guidance provided in Generic Letter No. 88-20 and NUREG-1335 will be utilized. Other sources of information such as selected NRC and EPRI publications will also be considered for use.

Descriotion of Method - The Level I PRA methodology will be based on the concept of utilizing multiple systemic event trees such as frontlino system event trees and support system event trees in order to define and quantify core damage accident sequences. An important element of the methodology will be the development of a detailed dependency matrix to illustrate the relationships, as well as the dependencies, between frontline and support systems, and between support systems. The core damage accident sequences will be reported in terms of initiating event groups and/or failures of frontline systems, support systems, and components.

The Back-End IPE methodology will consist of the development and quantification of a containment event tree (CET). Other aspects of the methodology will include means for estimating the source term for important  :: ore damage accident sequences, containment failure probability, and the effects of uncertainty in key phenomena considered important in determining the containment performance capability during a severe accident.

It is anticipated that the IPE methodology will consist of using the MAAP computer code and other available computer codes for supporting, as deemed necessary, tasks such as determination of minimum success criteria, timing of accident sequence events, and source term estimates.

Bilestones and Schedule The following table provides a list of milestones and a completion schedule for HNP IPE:

s

. y edigia Powel

,- 4 U.S. Nuclear Regulatory Commission ,

october 27, 1989 e Page Three HNP IPE Milestones and Completion Schedule 1

Task Completion No. Task Descriotion Dates Task 1 Plant Familiarization, Initiating Events I Analysis Event Tree Analysis, Systems j Analysis and Internal Flooding Analysis 5/1991  :

Task 2 Accident Sequence Quantification 9/1991 )

Task 3 Containment Performance Analysis 2/1992 1 Task 4 Evaluation and Plan for Resolution of IPE l Findings 4/1992 Task 5 Report NRC 9/1992 l

l It should be. noted that the milestones and methodologies noted '

herein are proposed at this time. Changes to methodologies will be ,

reported to the NRC for informational purposes. Schedular changes will not be reported unless they would impact the September 1992 final reporting schedule.

The information provided herein is true to the best of my knowledge and belief. If you have questions, please advise.

Respectfully submitted, ul >/. N H. G. Hairston, I I Sworn to and subscribed before me this M day of /IB b 1989.

Y 1AAM km 8 $b Y i JifComsbkhEds[S.$,ib2 GKH/eb c: Georaia Power Comoany Mr. H. C. Nix, General Manager - Nuclear Plant Mr. J. D. Heidt, Manager Engineering and Licensing - Hatch GO-NORMS i U.S. Nuclear Reaulatory Commission. Washinoton. D.C.

Mr. L. P. Crocker, Licensing Project Manager - Hatch U.S. Nuclear Reaulatory Commission. ReaiorLII  ;

Mr. S. D. Ebneter, Regional Administrator Mr. J. E. Menning, Senior Resident Inspector - Hatch 0341V .