ML20214M774

Application to Amend License DPR-34,changing Tech Specs to Include Phase II of Util Inservice Insp Program.Summary of Proposed Changes Also Encl

ML20214M774
Person / Time
Site:	Fort Saint Vrain
Issue date:	09/04/1986
From:	Walker R PUBLIC SERVICE CO. OF COLORADO
To:	Berkow H Office of Nuclear Reactor Regulation
Shared Package
ML20214M777	List: ML20214M774 ML20214M784
References
P-86498, TAC-53417, NUDOCS 8609110276
Download: ML20214M774 (10)

Text

l lO?;A O Public Service ~ PO. Box 840 (30 5'7 333 2420 W. 26th Avenue, Suite 1000, Denver, Colorado 80211 R.F. WALKER CHAIRMAN AND CHIEF EXECUTIVE OFFICER September 4, 1986 Fort St. Vrain Unit No. 1 P-86498 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:

Proposed Technical Specification Changes - Inservice Inspection and Testing Requirements

REFERENCES:

1) PSC letter, Lee to Berkow, dated 11/27/85 (P-85444)

2) NRC letter, Berkow to Walker, dated 5/30/86 (G-86286)

Dear Mr. Berkow:

This letter is to propose changes to the Fort St. Vrain Technical Specifications to include Phase II of PSC's Inservice Inspection Program (ISI). These changes are based on an earlier license amendment application (Reference 1) and reflect NRC comments that were addressed to PSC in Reference 2 as well as agreements reached with the NRC during telephone conversations on July 18, 1986. A summary of the proposed changes is provided in Attachment 1, and the proposed changes themselves are provided in Attachment 2. Please note that attachment 2 includes only those pages that have been revised.

Attachment 3 contains the Significant Hazards Consideration for the proposed changes. This report concludes that since the proposed changes do not result from modifications to plant equipment nor involve reductions in the margins of safety, no unreviewed safety question is raised. Therefore, the proposed changes involve no J q

significant hazards consideration. h0 8609110276 e60904 PDR ADOCK 05000267 PDR P

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P-86498' Page 2 September 4, 1986 Many of the proposed changes involve testing of pumps and valves. As such, the detailed surveillance procedures which implement these inspections will follow the guidance of the ASME Code,Section XI, Division 1 or 2, as appropriate. These procedures will be developed and implemented in accordance with the implementation schedules delineated for the individual surveillance requirements.

In accordance with the provisions of 10CFR170, an application fee of

$150.00 is enclosed.

If you have any questions or comments concerning the enclosed information, please call Mr. M. H. Holmes at (303) 480-6960.

Very truly yours, R.T.udaul.1,s-R. F. Walker Chairman and Chief Executive Officer RFW/MRS/ paw Attachments i

UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION ,,

In the Matter )

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Public Service Company of Colorado ) Docket No. 50-267 Fort St. Vrain Unit No. 1 )

AFFIDAVIT R. F. Walker, being first duly sworn, deposes and says: That he is Chairman and Chief Executive Officer, of Public Service Company of Colorado, the Licensee herein, that he has read the foregoing Application of Amendment to Appendix A of Facility Operating License and knows the contents thereof, and that the statements and matters set forth therein are true and correct to the best of his knowledge, information and belief.

. .N R. F. Walker Chairman and Chief Executive Officer STATE OF /h/pM/[# )

COUNTY OF I/114M2/ )

Subscripeandswornto).eforeme,aNotaryPubliconthis AU day of 61s,n/)>>t/v1) , 1986.

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NorXr'y Pub c //

't/598 afitmaf/W dii//o My commission expires h/4//d8 22 ,198f.

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BEFORE THE UNITED STATES NUCLEAR REGULATORY COMMISSION In the Matter of the Facility Operating License)

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of )

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PUBLIC SERVICE COMPANY OF COLORADO )

Application for Amendment to Appendix A of Facility Operating License License No. DPR-34 0F THE PUBLIC SERVICE COMPANY OF COLORADO FOR THE FORT ST. VRAIN NUCLEAR GENERATING STATION This application for Amendment to Appendix A of Facility Operating License, License No. OPR-34, is submitted for NRC review and approval.

Respectfully submitted, PUBLIC SERVICE COMPANY OF COLORADO By R. F. Walker Chairman and Chief Executive Officer KELLY, STANSFIELD & 0'DONNELL Bryant O'Donnell Robert E. Thompson Public Service Company Building Denver, Colorado 80202 Attorneys for Applicant

4 ATTACHMENT 1

SUMMARY

OF PROPOSED CHANGES

Section 5.0 - Surveillance Requirements Ayed the inservice inspection (ISI) surveillance requirements implementation criteria E, F, and G.

Section 5.2 - Applicability Editorial change to indicate that the surveillance requirements in Section 5.2 of the Technical Specifications also apply to the reactor auxiliary systems.

SR 5.2.8 - Circulator Bearing Water Pumps and Makeup Pump Surveillance Title modified to reflect new scope.

a) Editorial change b) Editorial change c) Unchanged d) New requirements to test the bearing water pumps and associated instruments and controls.

Basis - Expanded to address pump performance capability.

Editorial changes to reflect modified surveillance requirements.

SR 5.2.9 - Helium Circulator Bearing Water Accumulator Surveillance Functional test frequency modified from monthly to every 92 days.

Basis - Editorial changes to reflect modified surveillance requirements.

SR 5.2.10 - Fire Water System / Fire Suppression Water System Surveillance b.4b) Minimum firewater pump performance capability modified to allow for acceptable degradation in service.

b.4d) System pressure changed to read "119 psig" from "125 psig."

SR 5.2.16 - Closure Leakage Surveillance Requirements g) New surveillance requirements for testing and monitoring confinement capability associated with the helium purification system.

Basis - Expanded to address the new surveillance requirements.

SR 5.2.21 - ACM Transfer Switches, Valves and Instruments Surveillance Changed title to reflect modified scope of surveillance requirements.

Scope expanded to include partial stroking of the valves. Modified to provide operational flexibility until the next scheduled plant  ;

shutdown provided the surveillance interval does not exceed 18 months.

Basis - Changed to reflect the modified surveillance requirements.

SR 5.2.24 - Reactor Auxiliary Cooling Water Systems Surveillance Changed title to reflect modified scope of surveillance requirements, b) Changed the frequency of circulating water makeup pump functional test from weekly to monthly. New requirements for verification of pump performance capability and mechanical condition.

d) New requirements for examination of the circulating water makeup ponds.

e) New requirements for testing the service water pumps and associated instruments and controls.

f) New requirements for testing the reactor plant cooling water pumps and associated instruments and controls, g) New requirements for testing the purification cooling water pumps and associated instruments and controls, h) New requirements for testing the automatic isolation capability of cooling water system instruments and valves for confinement of reactor coolant.

Basis - Changed to reflect the modified surveillance requirements.

SR 5.3.4 - Safe Shutdown Cooling Valves Surveillance Editorial changes to clarify the surveillance requirements.

New requirements for testing valves (including normally power operated valves) that must be manually positioned for actuation of the safe shutdown cooling mode of operation.

I Basis - Editorial change to indicate that proper valve operation can be determined from observation of valve stem movement.

SR 5.3.9 - Safety Valve Surveillance Modified to include ASME Section XI Requirements for safety valve testing (five calendar year intervals).

Basis - Changed to reflect the modified scope of safety valve testing.

SR 5.4.5 - PCRV Cooling Water System Flow Instruments Surveillance Changed title for accuracy.

Modified to provide operational flexibility until the next scheduled plant shutdown, provided the surveillance interval does not exceed 18 months.

Basis - Editorial change only.

Page Substitutions In order to incorporate this submittal into the existing Technical Specifications, the following page substitutions will be necessary:

Remove Page Number Replace with Page Number 5.0-2 Amend. 36 10/13/83 5.0-2 5.2-1 Amend. 33 03/08/83 5.2-1 5.2-16 Amend. 33 03/08/83 5.2-16 5.2-17 Amend. 33 03/08/83 5.2-17 5.2-18 Amend. 33 03/08/83 5.2-18 5.2-19 Amend. 33 03/08/83 5.2-19 5.2-20 Amend. 33 03/08/83 5.2-20 5.2-26 Amend 33 03/08/83 5.2-26 5.2-27 Amend. 33 03/08/83 5.2-27, 5.2-27a 5.2-31 Amend. 33 03/08/83 5.2-31 5.2-32 Amend. 33 03/08/83 5.2-32, 5.2-32a 5.2-34 Amend. 33 03/08/83 5.2-34, 5.2-34a, 5.4-34b, 5.2-34c, 5.2-34d, 5.2-34e 5.2-35 Amend. 33 03/08/83 5.2-35 5.3-5 Amend. 33 03/08/83 5.3-5 5.3-6 Amend. 33 03/08/83 5.3-6, 5.3-6a 5.3-7 Amend. 33 03/08/83 5.3-7 5.3-18 Amend. 39 01/25/84 5.3-18, 5.3-18a 5.3-19 Amend. 39 01/25/84 5.3-19 5.4-13 Original 01/24/74 5.4-13 5.4-14 Original 01/24/74 5.4-14, 5.4-14a

ATTACHMENT 2 PROPOSED TECHNICAL SPECIFICATION CHANGES l

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