ML20206P381

Application for Amend to License DPR-34,revising Interim Tech Spec 3/4.1.7, Reactivity Change W/Temp to Be Consistent W/Increased Values for Calculated Reactivity Worth of Reserved Shutdown Sys,Per Rev 4 to FSAR

ML20206P381
Person / Time
Site:	Fort Saint Vrain
Issue date:	04/08/1987
From:	Robert Williams PUBLIC SERVICE CO. OF COLORADO
To:	Berkow H NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation
Shared Package
ML20206P386	List: ML20206P381 ML20206P393
References
P-87056, TAC-65241, NUDOCS 8704210169
Download: ML20206P381 (5)

Text

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h Public Service ~ l% h 2420 W. 26th Avenue, Suite 100D, Denver, Colorado 80211 April 8, 1987 Fort St. Vrain Unit No. 1 P-87056 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555 ATTN: Mr. H. N. Berkow, Director Standardization and Special Projects Directorate Docket No. 50-267

SUBJECT:

Proposed Change to Interim Technical Specification 3/4.1.7, Reactivity Change with Temperature

REFERENCE:

1) PSC letter, Lee to Johnson, dated 7/10/85(P-85242) 2)NRCletter, Johnson to Lee, dated 7/23/85 (G-85294)

Dear Mr. Berkow:

This letter proposes a change to interim Technical Specification 3/4.1.7, Reactivity Change with Temperature. Public Service Company of Colorado (PSC) is currently operating Fort St. Vrain (FSV) in accordance with interim Technical Specifications for reactivity control. This commitment was provided in Reference 1 and approved in Reference 2.

The FSV design includes a negative temperature coefficient as an inherent safety feature. In order to ensure that the reactor can be shut down with the reserve shutdown system in the unlikely event that all control rod pairs cannot be inserted, Reference 1 specified a maximum reactivity change with temperature of 0.056 delta k. This was based on a reactivity worth for the reserve shutdown system of 0.120 delta k. In Revision 4 of the FSV FSAR, Section 3.5.3.3 was revised to reflect an updated reserve shutdown system worth of 0.130 ,0h delta k in the equilibrium core. This increased worth supports an [

increase in the maximum reactivity change to 0.065 delta k.

8704210169 87040s PDR ADOCK 05000267 P PDR

P-87056 Page 2 April 8,1987 Attachment 1 is a summary of the proposed change to FSV interim Technical Specification 3/4.1.7 that reflects this higher reactivity change limit. Attachment 2 is the proposed change, Attachment 3 is the Safety Analysis, and Attachment 4 is the Significant Hazards Consideration for the proposed change.

PSC would 'like to reiterate our previous commitment provided in Reference 1, to operate Fort St. Vrain in accordance with procedures based upon the interim Technical Specifications approved in Reference 2. Where the interim Specifications differ from those that are a part of the existing operating license, the operating procedures reflect the more conservative requirement. Upon approval of the proposed change in Attachment 2, PSC will revise the applicable procedures to reflect the higher reactivity change limit.

If you have any questions regarding this proposed change please contact Mr. M. H. Holmes at (303) 480-6960.

Very truly yours R. O. Williams, Jr.

Vice President Nuclear Operations ROW /SWC/ paw cc: Albert J. Hazie Colorado Department of Health Regional Administrator, Region IV ATTN: Mr. J. E. Gagliardo, Chief Reactor Projects Branch Mr. Robert Farrell Senior Resident Inspector Fort St. Vrain L

9 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. O. Williams, Jr., being first duly sworn, deposes and says:

. That he is Vice President, Nuclear Operations, of Public Service Company of Colorado, the Licensee herein, that he has read the foregoing proposed change to the interim control rod drive Technical Specifications 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.

ht R.' O. Williams , Jr.

Vice President Nuclear Operations STATE OF C,,fM_o COUNTY OF n/' e s#

Subscribed and sworn to befpre me, a Notary Public on this

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• day of apit , 1987.

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ATTACHMENT 1

SUMMARY

OF PROPOSED CHANGES s.--- -

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Attachment 1 Summary of Proposed Changes 3/4.1.7 REACTIVITY CHANGE WITH TEMPERATURE' Section Description of Change LC0 3/4.1.7 Changed the value for the maximum reactivity change with temperature to be consistent with the increased values for the calculated reactivity worth of~the Reserve Shutdown System, Revision 4 of the FSAR, Section 3.5.3.3.

Basis for'LCO 3/4.1.7 Revised the values given'in the Basis to support the new upper limit provided in the' Specification.