ML19324B370

Responds to Generic Ltr 88-20, Individual Plant Exam: Submittal Guidance. Util Proposes to Perform Level I PRA Available from Previously Completed Level I PRAs & Other Pertinent Sources Such as Selected NRC & EPRI Publications

ML19324B370
Person / Time
Site:	Farley
Issue date:	10/26/1989
From:	Hairston W ALABAMA POWER CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
RTR-NUREG-1335 GL-88-20, NUDOCS 8911060161
Download: ML19324B370 (3)

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1. ' ' Alabama Power Company 40 inverness Center Parkway Post Offee Box 1?95

• Birmingham, Atabama 35201 lolephone 20$ 8(.8M81 -

W, G. Hairston, lit Senior Vice Presloent Nuclear Operabons Alabam3IDWCf October 26. 1989 Pe span scrre mwn I

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Dockist Hos. 50-348  ;

50-364 r

U. S. Nuclear Regulatory Commission \:

ATIN: Document Control Desk l Washington, D.'C. 20555 j Gentlemen:

Joseph M. Farley Nuclear Plant ';

i Response to Generic Letter No. 88-20 i

l On September 1,1989, the Nuclear Regulatory Commission (NRC) published in the Federal Register a notice announcing th0 availability of NUREG-l?35,

" Individual Plant Examination: Submittai Guidance," and initiation of'the  !

Individual Plant Examination (IPE) process. In accordance with Generic l l

l- Letter No. 88-20, licensees are required to sutnit within 60 days of this  !

rederal Register notice their proposed programs for completing their IPEs.

We purpose of this letter is to transmit the proposed program for i conpleting an IPE for the Joseph >!. Tarley Nuclear Plant (PVP). l According to the rederal Register notico, 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 sutnitted 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.

Be following information is provided concerning the proposed program for conpleting the FNP IPE in response to Generic Letter No. 88-20 i

t Method and Approach Alabama Power Company proposes to perform a Level I PRA for meeting tha Front-End (core damage portion) IPE requirements for FNP. The FNP Level I PRA will use information available from previously completed Level .

I PRAs and other pertinent sources such as selected NRC and EPRI publications. .

8911060161 891026 PDR i P

ADDCK 05000348[I oNU 3 I

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U. 5. Nuclear Regulatory Commission

"" October 26, 1989  ;

We Back-End (containment performance portion) IPE for FNP will be based on j 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 Ceneric Letter No. 88-20 and NUREG-1335 will be utilized.

other sources of information such as selected NRC and EPRI publications will l also be considered for use.

Description of Method  !

We Level 1 PRA methcdology will be based on the concept of utilizing multiple i i

systemic event trees such as frontline system event trees and support system event trees to define and quantify core damage accident sequences. An inportant element of the methodology will be the developnent of a detailed dependency matrix to illustrate the relationships as well as the dependencies between frontline and support systems, and between support systems. We core i damage accident sequences will be reported in terms of initiating event groups i and/or failures of frontline systems, support systems and components.

l We Back-End IPE methodology will consist of the development and quantification i of a containment event tree, other aspects of the methodology 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 will be considered in determining the containment performance t capability during a severe accident.

It is anticipated that the IPE methodology will consist of using available  :

computer codes such as MAAP for supporting, as deemed necessary, tasks such as determination of minimum success criteria, timing of accident sequence events, l and source term estimates.  ;

Milestones and Schedule  ;

h e following table provides a list of milestones and a completion schedule '

for the FNP IPE:

TNP IPE Milestones and Completion Schedule Task 1 Develop Plant and System Models 7/1991 Task 2 Accident Sequence Ouantification 11/1991 Task 3 containment Performance Analysis 3/1992 i Task 4 Evaluation & Resolution of IPE Findings 6/1992 i

Task 5 Report to NRC 9/1992 i

It should be noted that the milestones and methodologies noted herein ate j-

. proposed at this time. Changes to methodologies will be reported to the IRC -

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

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U. S. thelear Regulatory Commission Page 3 October 26, 1989 4f

'Ihe information provided herein is true to the best of m/ knowledge and j

belief. If you have any cpestions, please advise.

Respectfully sutaitted, AtABN% POWER COMPANY

' . ~W W. G. Hairston, III WGH/JA5timd-10.49 i

cc Mr. 5. D. Ebneter Mr. E. A. Reeves Mr. G. F. Maxwell SWORN

'DIIS JI/fd'IOMY AND OF SUBSCRIBE V , , 1989 [D BEIT)R 191 m bv,,'N' Lfh Nopy'Public M

' CON EXP! Pts etc, fg,g i

My Commission Expires:

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