ML20212A039

Forwards Application to Amend License DPR-34,changing Tech Specs Re Steam Line Rupture Detection/Isolation Sys

ML20212A039
Person / Time
Site:	Fort Saint Vrain
Issue date:	12/19/1986
From:	Robert Williams PUBLIC SERVICE CO. OF COLORADO
To:	Berkow H Office of Nuclear Reactor Regulation
Shared Package
ML20212A044	List: ML20212A039 ML20212A056 ML20212A066
References
P-86672, TAC-60421, NUDOCS 8612220261
Download: ML20212A039 (3)

Text

-_

e o OPublic Service ~ .o,, .

Company of Colorado 2420 W. 26th Avenue, Suite 1000, Denver, Colorado 80211 December 19, 1986 Fort St. Vrain Unit No. 1 P-86672 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 Change - Steam Line Rupture Detection / Isolation System

REFERENCE:

PSC Letter, Walker to Berkow dated June 4, 1986 (P-86227)

Dear Mr. Berkow:

This letter submits proposed changes to the Fort St. Vrain (FSV)

Technical Specifications that incorporate the requirements for the Steam Line Rupture Detection / Isolation System (SLRDIS). The Technical Specifications have been revised to address NRC comments regarding Public Service Company of Colorado's (PSC) previous submittal in the referenced letter.

Attachment 2 is the Proposed Changes to the existing license. These Proposed Changes supersede the previous submittal and have been revised to clarify the Actions and to add a response time test surveillance. Also, the Basis discussions have been revised accordingly.

Attachment 1, the Summary of Proposed Changes to the existing license, and Attachment 3, the Significant Hazards Consideration, are included for completeness. The content of these attachments, as well as the Safety Analysis and Analysis Value Discussion also provided in the referenced letter, is not affected by the attached changes to the Technical Specifications.

\

8612220261 861219 7 DR ADOCK 0500 q0

P-86672 Page 2 December 19, 1986 As previously indicated, there-are certain small steam line breaks that would not actuate SLRDIS. To assist the operators in detecting these conditions, PSC intends to retain the functional capability of the temperature sensors and alarms associated with the current Steam Pipe Rupture Detection System (SPRDS). The requirements for this instrumentation have been deleted from the FSV Technical Specifications as SPRDS is no longer required by the Safety Analysis.

PSC commits to reasonably maintain and test this instrumentation to ensure its operability, consistent with similar equipment that is not covered by Technical Specifications. This will include calibration on a once per refueling cycle basis, not to exceed 18 months, and corrective maintenance in a reasonable time interval.

PSC requests that the NRC approve the Proposed Changes in Attachme,it 2 without subjecting them to additional notice for public comment.

PSC considers the attached specifications as not significantly different from the SLRDIS Technical Specifications in the original proposed finding of no significant hazards consideration. The changes from the previous submittal are comparable to those that have arisen in other Technical- Specification development efforts where licensees provided supplemental changes that were not subjected to additional notices, as discussed in Attachment 4.

PSC considers that the attached Proposed Changes to the FSV Technical Specifications for SLRDIS are fully responsive to the NRC concerns identified in recent telephone conversations, and requests their approval in support of FSV restart activities.

-If you have any questions regarding the proposed changes to the FSV^

Technical Specification described in this letter, please contact Mr.

M. H. Holmes at (303) 480-6960.

Veryf tru,1 urs, h ifp/

R. O. Williams, Jr.

Vice President Nuclear Operations R0W/SWC/ paw Attachments

UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION In the Matter )

)

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 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.

8155 kee~'/W R. O. Williams, Jr.'

Vice President Nuclear Operations STATE OF [h/'nnr/fd )

COUNTY OF $92#/v' Subscrp>i eday andofsworn to before me, a Notary , 1986.Public on this

/v /i/(an/uv A m u n ?N ( ! /it / / % ! w II/]

No'tary Public qjfy .ydatridf/t/ / 'Hf//-

l fltiftuu My commission expires O//<?n2/;16 , 198jA

/