ML20235E427

Fourth Quarterly Rept on Status of Reactor Bldg Sump Monitoring Sys.Rept Will Be Submitted on or Before 871022 Describing Results of Testing & Plans for Future Reactor Bldg Sump Monitoring

ML20235E427
Person / Time
Site:	Fort Saint Vrain
Issue date:	09/22/1987
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-87333, TAC-61580, NUDOCS 8709280112
Download: ML20235E427 (2)

Text

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T, h Public Service

• Er,CL, P.O. Box 840 Denver, CO 80201- 0840 R.O. WILLIAMS, JR.

September 22, 1987 VICE PRESIDENT Fort St. Vrain NUCLEAR OPERATIONS Unit No. 1 P-87333 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:

Status of the Reactor Building Sump In-Line Beta Monitoring System

REFERENCE:

1. PSC Letter, Gahm to

1. Berkow dated 09/18/86 6' (P-86559)

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2. PSC Letter, Gahm to yy Berkow dated 12/22/86 (P-86655) hh c-

3. PSC Letter, Williams to Berkow dated 03/22/87 E (P-87113)

4. PSC Letter, Williams to Calvo dated 06/22/87 (P-87237)

Dear Mr. Calvo:

This is the fourth quarterly report on the status of the Reactor l Building Sump Monitoring System in accordance with Public Service '

Company of Colorado's agreement with you. This period covers the l last half of the six months extension in testing.

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8709280112 870922 A PDR ADOCK 05000267 R PDR /

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P-87333 September'22, 1987 In Reference 3, we conveyed our intent to address our problem with the quality of the effluent from the Reactor Building Sump filter banks. The primary concerns were particulate material greater than one (1) micron causing excessive wear in the pump and the reduction of scintillation cell sensitivity caused by the particulate material and the accumulation of an oil film. The Reactor Building Sump In-Line Beta Monitoring System is essentially unchanged, mechanically, since the last report.

Final approval of Change Notice 2313C was received in July. This modification will move the sampling point from the carbon steel discharge pipe to the stainless steel filter housing discharge flange-in order to forestall scale and corrosion products from entering the Reactor Building Sump Beta Monitor. The necessary modification work . ;.

on the sample line has not begun. The delay is resulting from higher priority work consuming available manpower. It is possible that additional priority work will continue to delay. work on this project.

Oil contamination of the Reactor Building Sump continues to be a problem based on visual evaluation of Reactor Building Sump water samples. Much of this contamination appears to coincide with work being done on Reactor Building equipment. The effort to mitigate this problem will be ongoing.

In accordance with our agreement in Reference 3, this concludes the l test period extension. On or before October 22, 1987, a report will be submitted describing the results of the testing and our plans for future Reactor Building Sump monitoring.

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

Sincerely,

/

R. O. Williams,'Jr.

Vice President, Nuclear Operations  !

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R0W:VHF/skd I cc: Regional Administrator, Region IV ATTN: Mr. J. E. Gagliardo, Chief Reactor Projects Branch Mr. Robert Farrell Senior Resident Inspector Fort St. Vrain