ML20128B143
| ML20128B143 | |
| Person / Time | |
|---|---|
| Site: | Trojan File:Portland General Electric icon.png |
| Issue date: | 01/28/1993 |
| From: | Cross J, Robinson W PORTLAND GENERAL ELECTRIC CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9302020411 | |
| Download: ML20128B143 (4) | |
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- Portland General Electdc Company James E. Cross
. Vice President and Chief Nuclear Officer -
- January 28, 1993I Trojan' Nuclear Plant; Docket 50-344 License NPF-1
-U.S. Nuclear Regulatory Commission
.Attnt Document Control Desk Washington DC 20555
Dear Sir:
Eire Proterlion/ App.endix R ProgramJ111calonna_Ilp.date In response-to your letter of January 22 1992 and as a follow-up.to our October 30, 1992 letter transmitting ~the third quarter 1992 update of.the:
Fire Protection / Appendix R program milestones, attached is-the fourth-quarter 1992 update to~the milestone activities. Changes to milestones are annotated by revision bars.
Due.to Portland General Electric Company's (PCE's) recent announcement to?
discontinue operation of-the Trojan Plant, PGE is evaluating-commitments-associated with the Appendix'R reanalysis' effort.-- Changes to.the. Fire l
Protection / Appendix R Program resulting'from-this evaluation'will be provided-to the Nuclear Regulatory Commission (NRC) in-future--
correspondence.
-Sincerely,-
4 s_ Md W. R.' Robinson-for J. E. Cross I.ttachment I
c:- Mr. John B.' Martin Regional-Administrator,_ Region V U.S. Nuclear Regulatory Commission Mr. David-Stewart-Smith State of Oregon-
-Department of-Energy 010093-Mr. K.;E. Johnston i
NRC Senior Resident Inspector Trojan Nuclear Plant 9302020411 930128
.PDR ADOCK~0500 4
- 121 SW Salmon Street. Portland, OR 97204 fl
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'. Trojan' Nuclear Plant.
Document Control Desk:
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Dodket 50-344 January 28, 1993 License NPF Attachment?
Page,1.of 3; j
l FIRE PROTECTION / APPENDIXR PROGRAM l
MILEEIONES_UEDATE - FOURIILQUARIEIL1292
.)
Inak -
- Dennip. tion
._DatL i
1.
Establish Administrative Goals for Fire Protection.-
Complete-
.-Consolidate the Fire Protection Program.-
. Develop procedure for Fire Protection Program Interfaces and responsibilities.
L 2.
Revise Portland General Electric Company'(PCE)-1012, Complete L
Fire Protection Plan Program Description.
3.
Document Program Coals and Standards.
Complete-Use of Title'10, Code of Federal Regulation,.
Part 50.59 (10 CFR 50.59) evaluations and exemption requests under Generic Letter 86-10.
. Establish performance standards for the Fire Protection Program.-
4.
Issue Fire Protection Program Procedures.
Complete Procedures to include a review of Trojan's Appendix R design' basis and analysis assumptions when making changes of.the safe shutdown analysis or its implementing procedures.
5.
Complete Safety Sequence'Diagrem.
Complete
?.'
. Reevaluate present approach to Appendix R safe shutdown.
pj 6.
Complete Electrical' Circuit Analysis.
Complete
_. Emergency Fire. Procedure (EFP)' background documents will be updated to be consistent with EFPs and modified' spurious operationn analysis.
7.
Periodic update of PGE-1012, Fire Protection Complete-Plan Program Description.
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' Tro. inn Nuclear Plant Doctunent Cont rol Desk Docket 50-344 January 28 1993 License NPF-1 At taclunen t Page 2 of 3 Tash
_ Description __ _
__Da t tu 8.
Complete Cable Separation Analysis.
06/15/93
. Periotin walkdown of fire areas to identif y spurious operation components in support of spurious opernilon associated circuit reanalysis.
. Perform more detailed spurious operation evaluation considering circuit analysis, time constraints, operator actions, and available indications /
parameters.
. Validate Calculation TNP 89-17 for transit time to or through fire areas to perform manual actions.
Reassess shutdown methodology including statlon blackout.
. Address pressurizer power-operated relie f valve (PollV) circaltry ill/LO interf ace requirements of Generic Letter f4-10.
Incorporate circuit analysis of communications equipment into safe shutdown analysis.
Inform the NRC if station blackout is the preferred methodology for achieving safe shutdown.
The completion of this task and the associated subtasks remain on schedule. A revised spurious operations analysia was completed and documented as Calculation TF-006, " Spurious Operation Evaluation". Calculation TF-011. "lligh Priority Operator Actions and Transit in Affected Fire Area", was issued to supersede TNP 89-17 and identifies fire areas in which access is needed to perform time-critical actions or transit through the area.
p 9.
Complete Design Basis Doctunent System 13 07/01/93 Validation.
. Plent walkdowns au being performed and are on scheduled to meet the task completion date.
10.
Complete Fire Damper Modif1 cations.
12/31/93 Fire damper modifications are in progress and on schedule to meet the task completion date.
' Trojan Nuclear Plant Document Control Desk Docket 50-344 January 28, 1993 License NPF-i Attachment Page 3 of 3 Iank Description m
_4
_Date._
11.
Complete Foamed Fire Seal keplacement.
12/31/93
. Foamed seal replacements are in progress and on achedule to meet the task completion date.
12.
National Fire Protection Associatia,n (NFPA) Code 05/12/94 Resolutions.
. Verify system design and identify NF44/
Underwriters Laboratories, Inc. (UL) code deviations.
. Deve'op inst,ection/ maintenance criteria for itre protection features not presently covered by existing Plant procedures.
NFPA code deviation issues are being addressed.
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13.
Im,'ement Revised Methodology - Modifications.
06/15/94 Protect pressurizer PORVs from effects of multiple hot shorts Work associated with this task has not been initiated.
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