ML19325E790

Responds to Generic Ltr 88-20,transmitting Proposed Program for Completing Individual Plant Exam for Plant.Program Should Identify Method & Approach Selected for Performing Exam

ML19325E790
Person / Time
Site:	Vogtle
Issue date:	10/30/1989
From:	Hairston W GEORGIA POWER CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
RTR-NUREG-1335 ELV-00994, ELV-994, GL-88-20, NUDOCS 8911080463
Download: ML19325E790 (4)

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, e m . ,o m w,on. j Docket Nos. 50-424  !

50-425 U. S. Nuclear Regulatory Commission

,( Document Control Desk  ;

Washington, D.C 20555 i

, i Gentlemen: )

I V0GTLE ELECTRIC GENERATING PLANT Resoonse to Generic letter No. 88-20 j On September 1, 1989, the Nuclear Regulatory Commission (NRC) published in the Federal Register a notice announcing the availability of NVREG-1335, " Individual  !

Plant Examination: Submittal Guidance," and initiation of the Individual Plant  :

Examination (IPE) process. In accordance with Generic Letter No. 88-20,  !

licensees are required to submit, within 60 days of this Federal Register i notice, their proposed )rograms for completing the IPEs. The purpose of this I letter is to transmit tie proposed program for completing an IPE for the Vogtle '

Electric Generating Plant (VEGP).  ;

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

r Identify the method and approach selected for performing the IPE;  ;

(1) ,

(2) Describe the method to be used, if it has not been sutunitted for staff f review (description may be referenced); and j (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 VEGP IPE in response to Generic Letter Nc. 88-20.

Method and Approach j Genrgia Power Company proposes to perform a level I PRA for meeting the Front- t End (core damage portion) IPE requirements fnr VEGP. The VEGP Level I PRA will  !

use information available from previously completed Level I PRAs and other pertinent sources such as selected NRC and EPRI publications.

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Georgia Power h L

U. S. Nuclear Regulatory Commission ELV-00994 Pace Two c

I The Back-End (containment performance portion) IPE for VEGP 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 11 PRAs, and guidance provided in Generic Letter No. 88-20 and NUREG-1335 will be utilized. t Other sources of information such as selected NRC and EPRI publications will  !

l also be considered for use.  ;

I Description of Method  ;

The Level ! PRA methodology will be based on the concept of utilizing multiple i systemic event trees such as frontline system event trees and support system event trees to define and quantify core damage accident sequences. An important element of the methodology will be the development of a detailed de)endency i matrix to illustrate the relationships as well as the dependencies setween frontline and support systems, and between support systems. The core damage o accident sequences will be reported in terms of initiating event groups and/or i failures of frontline systems, support systems, and components.  ;

1 The Back-End IPE methodology will consist of the develo) ment and quantification  !

of a containment event tree. Other aspects of the metiodology will include

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

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I U. S. Nuclear Regulatory Commission ELV-00994

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Milestones and Schedule

' The following table provides a list of milestones and a completion schedule for the VEGP IPE:

VEGP IPE Milestones and Completion Schedule Task Task Description Com)1etion A lates Task 1 Develop Plant and System Models 06/1991 Task 2 Accident Sequence Quantification 10/1991 Task 3 Containment Performance Analysis 02/1992 Task 4 Evaluation and Resolution of IPE Findings 05/1992 Task 5 Report to NRC 09/1992 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.

If you have any questions, please contact this office.

Mr. W. G. Hairston, 111 states that he is a Senior 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.

GEORGIA POWER COMPANY By: 6d.I b d W. G. Hairston, 111 Sworn to and subscribed before me this 47 M day of 8 c:h., 1989.

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U. S. Nuclear Regulatory Commission j ELV-00994  ;

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Mr. C. K. McCoy  !

Mr. G. Bockhold  :

Mr. P. D. Rushton NORMS  :

NUMARC U.S. Nuclear Reaulatory Commission Mr. S. D. Ebneter, Regional Administrator  :

Mr. J. B. Hopkins, Licensing Project Manager, NRR Mr.,J. F. Rogger: Senior Resident Inspector, Vogtle I

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