ML19325F033

Responds to Generic Ltr 88-20,Suppl 1, Initiation of Individual Plant Exam for Severe Accident Vulnerabilities. Level I PRA Will Be Performed to Satisfy Exam Requirements

ML19325F033
Person / Time
Site:	Comanche Peak
Issue date:	10/30/1989
From:	William Cahill TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC)
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
RTR-NUREG-CR-2300, RTR-NUREG-CR-2815, RTR-NUREG-CR-4550 GL-88-20, TXX-89782, NUDOCS 8911130249
Download: ML19325F033 (4)

Text

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Log # TXX 89782

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10035 Ref. # Generic letter 88 20 nlELECTRIC i

October 30, 1989 wuhenJ.CahalJr.

kn uone w I'rrudent U. S. Nuclear Regulatory Commission Attn Document Control Desk Washington, D. C. 20555

$UBJECT: COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)

DOCKET NOS. 50 445 AND 50 446 NRC GENERIC LETTER 88 20:

INDIVIDUAL PLANT EXAMillATION FOR SEVERE ACCIDENT VULNERABILITIES REF: 1) NRC Generic Letter 88 20, Supplement 1:

" Initiation of The Individual Plant Examination For Severe Accident Vulnerabilities,"

dated Augtst 29, 1989.

2) NUREG 1335: " Individual Plant Examination:

Submittal Guidance," dated August 1989.

Gentlemen:

The following CPSES information is provided in response to NRC Generic Letter (GL) 88 20. " Individual Plant Examination For Severe Accident Vulnerabilities." NRC GL 88 20 requests Licensees to submit their proposed programs for completing an Individual Plant Examination (IPE). The CPSES response to the GL 88 20 requested information is provided as follows.

(1) GL 88-20 Reauest Identify the method and approach selected for performing the IPE.

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CPSES Responset TU Electric intends to perform an IPE for CPSES Units 1 and 2 using method number one described in the GL 88 20. Specifically, a Level I probabilistic risk assessment (PRA) plus a containment performance analysis (i.e., back end portion) will be performed to satisfy the IPE requirements. Current PRA methods and procedures consistent with those described in NUREG/CR-2300, NUREG/CR 2815, or NUREG/CR-4550, are intended to be used for the level I portion of the IPE. The containment performance analysis of the study will be performed using the general

! approach described in Appendix A of refer 6nce (2), entitled " Approach To l Back-End Portion of IPE."

l 8911130249 891030 doot PDR ADOCK 0500044" A PDC , ' !

P. O. Boz 1002 Glen Rose, Texas 7604N002 1

i TXX 89782 i October 30, 1989  ;

Page 2 of 3  !

The CPSES IPE program methodology encompasses the following features:  !

o The development of plant specific initiating events: l o The development of plant specific system fault tree models and '

accident sequence (event tree) models:

o The use of fault tree linking methodology in the development of accident sequences:

o The development of a generic component reliability data base (appropriate plaht specific data is not expected to be available ,

prior to the CPSES IPE submittal): l o A human reliability analysis:

o The development of containment event trees and source term analysis; and o The use of current industry computer codes (e.g., CAFTA. ETA. MAAP, l etc.).

(2) GL 88 20 Reauest: ,

Describe the method to be used, if it has not been previously submitted for staff review (the description may be by reference).

CPSES Resoonse:

The CPSES IPE program methodology intended to be utilized to satisfy the  !'

requirements of GL 88 20 is consistent with the guidance provided by I reference (2).

( In accordance with the requirements of GL 88 20, TV Electric does not intend to include external events in the IPE submittels however, internal flooding will be addressed as part of the internal events. In addition, the Unresolved Safety Issue A 45, entitled " Shutdown Decay Heat Removal Requirements" will be evaluated by the CPSES IPE program.

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I TXX 89782 l October 30, 1989 Page 3 of 3 )

l (3) GL 88 20 Reauest:

Identify the milestones and schedules for performing the IPE and submitting the results to the NRC.

CPSES ResDonset i

The projected schedule for subiaittal of final results to the NRC is September 1, 1992.

The attachment provides the required affidavit in accordance with the reporting requirements of NRC GL 88 20 that responses be submitted under oath ,

or affirmation.

Sincerely,  ;

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William J. Cahill, Jr.  ;

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HAM /smp Attachment c - Mr. R. D. Martin, Region IV Resident Inspectors, CPSES (3) i a

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Attachment to TXX 89782 October 30, 1989 Page 1 of 1 UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION i

In the Matter of )

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Texas Utilities Electric Company ) Docket Nos. 50 445 I

) 50 446 (Comanche Peak Steam Electric ) i Station Units 1 & 2) )

AFFIDAVIT  !

t William J. Cahill. Jr. being duly sworn, hereby deposes and says that he is '

Executive Vice President. Nuclear of TV Electric, the lead Applicant herein:

that he is duly authorized to sign and file with the Nuclear Regulatory ,

Commission this response to NRC Generic Letter 88 20, that he is familiar with the content thereof; and that the matters set forth therein are true and correct to the best of his knowledge, information and belief.  !

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William J. Cahl % Jr.  !

Executive Vice President, Nuclear i

STATE OF TEXAS )

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COUNTY OF DALLAS )

Subscribed and sworn to before me, a Notary Public on this 2 Cr{ day of '

f}L*ffh, . 1989.

i 6nd. M 9(otary Public l

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