ML20214U381

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Advises That Scheduled Submittal Date for Fire Protection Program Plan Will Be 871215 to Ensure That Plan Accurately Reflects Recent Fire Protection Shutdown/Cooldown Model Changes & Commitments,Per D Kubicki & K Heitner Telcon
ML20214U381
Person / Time
Site: Fort Saint Vrain Xcel Energy icon.png
Issue date: 06/02/1987
From: Robert Williams
PUBLIC SERVICE CO. OF COLORADO
To: Calvo J
NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM), Office of Nuclear Reactor Regulation
References
P-87208, TAC-54373, NUDOCS 8706110168
Download: ML20214U381 (2)


Text

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P.O. Box 840 Denver, Co 80201-0640 R.O. WILUAMS, JR.

VICE PAESiOENT NMEAR OPERATIONS June 2, 1987 Fort St. Vrain Unit No. 1 P-87208 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555 Attention: Mr. Jose A. Calvo Director, Project Directorate IV Docket No. 50-267

SUBJECT:

Fire Protection Program Plan Submittal Date

REFERENCE:

1) PSC Letter, Warembourg to Calvo, dated 5/15/87 (P-87167)

Dear Mr. Calvo:

l Based on conversations with Mr. Dennis Kubicki and Mr. Kenneth Heitner of the NRC staff, PSC plans to revise its scheduled submittal date for the Fort St. Vrain (FSV) Fire Protection Program Plan (FPPP) to December 15, 1987.

! This rescheduling will ensure the FPPP accurately reflects recent l Fire Protection Shutdown /Cooldown model changes and commitments made i to the NRC.

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P-87208

~- "- Page 2 June 2, 1987 There are a number of reasons for this change:

Reason #1 PSC has subwitted substantial revisions to its Fire Protection Shutdown /Cooldown models as an R Evaluation Report revision in Reference. 1, Appendix which the NRC is currently reviewing. This will have to be included in the FPPP.

Reason #2 PSC is undertaking a study to ensure that commitments previously made to the NRC in the area of Fire Protection are adequately addressed in the FPPP and Station procedures.

Reason #3 PSC is currently verifying the Fire Protection design against the guidelines contained in the applicable NFPA codes.

Reason #4 PSC is currently updating its 1978 BTP9.5-1 Appendix A Evaluation to reflect plant changes that are ongoing as committed to in Section 9.12.5.2 of the Updated FSAR.

This updated Evaluation will be included in the FPPP.

Since PSC has never received a complete NRC Safety Evaluation on this Evaluation, it is anticipated that the NRC will review this as part of its overall review of the FPPP.

Reason #5 PSC has not yet received our NRC Fire Protection / Appendix R Safety Evaluation,- which would include formal NRC approval of the FSV Appendix R exenption requests. PSC can not submit this FPPP until NRC approval is received per the guidance of Generic Letter.86-10.

i If you have any questions, please contact Mr. M. H. Holmes at (303) 480-6960.

Very truly yo,urs, L

R. O. Williams, Jr.

Vice President

Nuclear Operations l

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