ML20215G796

Advises That Info Requested in NRC Re Best Estimate Schedule for Resolution of Problems Encountered W/Firewater Cooldown Analysis Will Be Submitted as Part of Util Graduated rise-to-power Program

ML20215G796
Person / Time
Site:	Fort Saint Vrain
Issue date:	10/10/1986
From:	Warembourg D PUBLIC SERVICE CO. OF COLORADO
To:	Berkow H Office of Nuclear Reactor Regulation
References
P-86580, TAC-63576, NUDOCS 8610210130
Download: ML20215G796 (3)

Text

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2420 W. 26th Avenue, Suite 1000, Denver, Colorado 80211 October 10, 1986 Fort St. Vrain Unit No. 1 P-86580 Director of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D.C. 20555 Attention: Mr. H. N. Berkow, Director Standardization and Special Projects Directorate Docket No. 50-267

SUBJECT:

Reanalysis of Firewater Cooldown

REFERENCE:

NRC Letter K.L. Heitner to R.O. Williams, Reanalysis of Firewater Cooldown, dated 9/25/86 (G-86516)

Dear Mr. Berkow In the referenced NRC letter, it was requested that Public Service Company of Colorado (PSC), provide the staff with PSC's "best estimate" schedule for resolution of the problems encountered with the firewater cooldown analysis for the Fort St. Vrain Nuclear Generating Station (FSV), including the following information:

Completion of an analysis that supports an acceptable cooldown of the plant for the relevant accident scenarios, Revision of plant operating procedures an'd operator training to be consistent with the above analysis results, and Submission of the revised cooldown analysis for NRC review and approval prior to plant startup.

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P-86580 Page 2 Octob3r 10, 1986 In the October 6,7 1986 meeting between PSC and the NRC staff, PSC discussed a proposed graduated rise-to-power program with the staff.

PSC considers that this graduated rise-to-power program is the '

optimum course for the FSV plant to assure both public health and safety and the economic future of the plant. Much of the analytical work which must be conducted to demonstrate the adequacy of the steam-generator economizer-evaporator-superheater and reheater sections for

, safe shutdown cooling must be prioritized and performed on a schedule that will support the graduated rise-to-power proposal.

PSC executive management will be meeting with the NRC Commissioners on October 17, 1986 to discuss PSC's proposed graduated rise-to-power program. Following this meeting PSC expects -that the schedule information requested by the staff .can more realistically be integrated into the schedule for the graduated rise-to-power program.

Therefore, the staff's requested information will be submitted to the staff with or as part of PSC's graduated rise-to-power program.

If you have any questions concerning the schedule for the requested information, please contact Mr. M. H. Holmes at (303) 480-6960.

Very truly yours, A0 W WwJ D. W. Warembourg, ger Nuclear Engineering Division DWW/AW:jmt cc: K.L. Heitner

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P-86580 Page 2 Octobsr 10, 1986 In the October 6,7 1986 meeting between PSC and the NRC staff, PSC discussed a proposed graduated rise-to-power program with the staff.

PSC considers that this graduated rise-to-power program is the optimum course for the FSV plant to assure both public health and safety and the economic future of the plant. Much of the analytical work which must be conducted to demonstrate the adequacy of the steam generator economizer-evaporator-superheater and reheater sections for safe shutdown ecoling must be prioritized and performed on a schedule that will support the graduated rise-to-power proposal.

PSC executive management will be meeting with the NRC Commissioners on October 17, 1986 to discuss PSC's proposed graduated rise-to-power program. Following this meeting PSC expects that the schedule information requested by the staff can more realistically be integrated into the schedule for the graduated rise-to-power program.

Therefore, the staff's requested informatinn will be submitted to the staff with or as part of PSC's graduated rise-to-power program.

If you have any questions concerning the schedule for the requested information, please contact Mr. M._H. Holmes at (303) 480-6960.

Very truly yours,

.0 V )L-e+~4 D. W. Warembourg, er Nuclear Engineering Division DWW/AW:jmt

, cc: k.L. Heitner Reviewed By:

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