ML19327B628

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Forwards Response to Generic Ltr 88-20, Initiation of Individual Plant Exam for Severe Accident Vulnerabilities
ML19327B628
Person / Time
Site: Trojan File:Portland General Electric icon.png
Issue date: 10/27/1989
From: Cockfield D
PORTLAND GENERAL ELECTRIC CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
GL-88-20, NUDOCS 8911030018
Download: ML19327B628 (3)


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PDrliand General Elodric Cortiseriy

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L David W. Cockfield Vice President, Nuclear l

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October-27, 1989 Trojan Nuclear Plant i

Docket 50-344 License NPF-1 l

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U.S. Nuclear Regulatory Commission ATTN!

Document Control Desk Washington DC '20555

Dear Sir:

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Response to Generic Letter 88-.20, Supplement No. 1, " Initiation of the Individual Plant Examination for Severe Accident Vulnerabilities" f

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Information is provided in the attachment to this letter pursuant to your request'under Title 10, Code of Federal Regulations, Part 50, Section S4(f) g (10 CFR 50.54(f)] describing Portland General Electric's (PGE's) proposed pro 5 ram for completin6 the Individual Plant Examination (IPE) for the i

Trojan Nuclear Plant.

Sincerely, 1

Attachment c:.Mr. John B. Martin Regional Administrator, Region V l:

1 U.S. Nuclear Re5ulatory Commission l

Mr. David Stewart-Smith State of Oregon Department of Energy Mr. R. C. Barr NRC Resident Inspector Tecian Nuclear Plant i-l:-

b 0911030018 891027 PDR ADOCK 05000344 I

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121 S.W Sa! mon Street, Port!and. Oregon 97204

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' Trojan Nuclear Plant Document Control Desk F

Docket 50-344 Attachment License NPF-1 October 27, 1989 Page 1 of 2 i

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PORTLAND GENERAL ELECTRIC COMPANY (PCE)

PROPOSED PROGRAM FOR COMPLETING THE INDIVIDUAL

- PLANT EKAMINATION (IPE) FOR THE TROJAN NUCLEAR PLA_NI

!l l-WRC REQUEST Wo. 12-e

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Identify the method and approach selected for perform-ing the IPE.

Response '

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4 PGE will utilize the probabilistic risk assessment (PRA) method for performing an IPE for Trojan. The effort will include an in-depth

. analysis of Plant design and operations to identify any instances of g

particular vulnerability to core melt or unusually poor containment i

performance given a core melt accident. This analysis will identify potential changes to Plant systems, components, and procedures that would reduce the likelihood of core melt or unusually poor Containment performance. These potential changes will be anelyzed against specific criteria to assess desirability of implementation and those changes selected will be scheduled and performed.

Experienced permanent utility staff personnel will be used to the maximum extent practical for the effort, however, assistance from an experienced PRA' firm with nuclear plant familiarity will also be required.

This will enhance confidence and familiarity with the results, facilitate integration of the knowledge gained from the l

examination into emergency operating procedures and training programs, and allow for ease in ongoing use of the IPE for future accident management programs.

NRC REQUEST NO. 2:

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Describe the method to be used, if it has not been previously submitted for staff review.

Response

The PRA method for performing an IPE has been previously submitted for NRC staff review and has been identified as an acceptable method in NRC Ceneric Letter 88-20.

NRC REQUEST NO. 3:

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

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Trojan Nuclear Plant Document Control Desk Docket 50-344 Attachment License NPF-1 October. 27, 1989 Page 2 of 2

Response

The milestones and schedules for performing the IPE are as follows:

a.

Select PRA firm to assist PCE in performing the Trojan IPE by December 31. 1989.

b.

Substantially complete IPE work and prepare preliminary IPE report for internal PCE review by January 31, 1992.

c.

Complete internal review and finalize IPE results by May 31, 1992.

d.

Submit final IPE report to NRC for review by September 1, 1992.

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