ML20138M184

Clarifies Commitment Dates in Util Re Proposed Mods Per 10CFR50,App R Fire Protection Evaluation.Remaining Mods Expected to Be Completed During Refueling Outage

ML20138M184
Person / Time
Site:	Fort Saint Vrain
Issue date:	10/14/1985
From:	Warembourg D PUBLIC SERVICE CO. OF COLORADO
To:	Hunter D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
References
P-85362, TAC-54373, NUDOCS 8510310566
Download: ML20138M184 (3)

Text

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OCT l 81985 i!

O Pubh. Service

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Company of Colorado P.O. Box 840 October 14, 1985 cenver. co 80201 -0840 Fort St. Vrain N'

• 1 Unit No. 1 P-85362 Regional Administrator Region IV U. S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 1000 Arlington, Texas 76011 Attn: Mr. Dorwin Hunter Docket No. 50-267

SUBJECT:

Modifications Associated With 10CFR50 Appendix R Fire Protection Evaluation

REFERENCE:

PSC Letter Lee to Johnson, dated 04/01/85 (P-85113) Report No. 4

Dear Mr. Hunter:

This letter is sent to clarify commitment dates made in the referenced letter which are associated with proposed modifications resulting from PSC's 10CFR50, Appendix R Fire Protection Evaluation.

Table 4.1 in the report enclosed with that letter lists several modifications which require a plant outage of 14 days for installation. As indicated by the note at the end of Table 4.1 (See Attachment 1), it was not PSC's commitment to install those modifications during the first 14 day outage after the change notice and materials are on site.

PSC is making every effort to install these modifications as soon as possible and, in f.ct, have installed a high percentage of the ones available at this date. However, we wish to point out that even though an outage may occur of sufficient length (14 days), it is possible that plant conditions or schedules may not permit installation of a desired modification.

PSC has indicated to the staff that there will be some plant outage time in the near future associated with the Environmental Qualification Program. We are factoring the Appendix R modifications into our outage scheduling, but we must necessarily place the highest priority on modifications and work associated with the environmental programs.

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We will continue to aggressively pursue our Appendix R modificatio$s and ask that NRC expedite their review of our Appendix R Fire Protection Evaluation.

At this time, we expect to complete all remaining modifications during our next refueling outage.

If you have any questions, please contact Mr.

M.

H.

Holmes at (303) 571-8409.

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Very truly yours, 0 W- }% wd D. W. Warembourg, er Nuclear Engineering Division DWW/FWT:pa Attachment

O TABLE 4-1 (continued)

Length of Required Change Notice and Plant Shutdown Completion ite m Description Material On Site (Doys)

Date 4.12 S.W. Return Pump Jon. I, I986 14 4.13 ACM Diesel Tech. Specs April 1,1985 (draft to NRC) 4.14 Shutdown Procedures Oct. I, 1985 Special Repair Procedures July 1,1985 (including fire watch) or by startup if offer that date.

GN Table 4-1 identifies numerous modifications requiring at least a 14-day scheduled plant shutdown for installation. PSC will make N every effort to install as many as possible during each scheduled shutdown, but it should not be inferred that all modifications for gg N r+

which material is on-site will be installed during the first scheduled shutdown.

5 DC-85-04