ML20216J473

Forwards Application for Amend to License DPR-34,changing Tech Spec Limiting Condition for Operation 4.1.9 to Reduce Potential for Flow Stagnation & Prevent Excessive Fuel Temps in Core & Spec 5.1.8 to Incorporate Requirements.Fee Paid

ML20216J473
Person / Time
Site:	Fort Saint Vrain
Issue date:	06/25/1987
From:	Robert Williams PUBLIC SERVICE CO. OF COLORADO
To:	Calvo J NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM), Office of Nuclear Reactor Regulation
Shared Package
ML20216H727	List: ML20216H722 ML20216H730 ML20216J473
References
P-87124, TAC-52634, NUDOCS 8707060015
Download: ML20216J473 (4)

Text

,a -

.s h Public Service ~

==/h...

P,0. Box 840 Denver, CO 80201- 0840 June 25, 1987 R.O. WILLIAMS, JR.

VICE PRESIDENT Fort St. Vrain NUCLEAR OPERATIONS Unit No. I P-87124 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:

Resubmittal of Proposed Technical Specification l

Change, LCO 4.1.9, Core Inlet Orifice Valves / Minimum Helium Flow and Maximum Core Region Temperature Rise.

REFERENCES:

(1) PSC Letter, 0. R. Lee to J. T. Collins, dated 12/15/83 (P-83403)

(2) PSC Letter, R. O. Williams to H. N. Berkow, dated 7/9/86 (P-86451)

(3) NRC Letter, K. L. Heitner to R. O. Williams,

-dated 12/5/86 (G-86631)

Dear Mr. Calvo:

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

Technical Specification LCO 4.1.9, Core Inlet Orifice Valves / Minimum Helium Flow and Maximum Core Region Temperature Rise, to reduce the potential for flow stagnation and thereby prevent -excessive fuel temperatures in the FSV core.

• Also included is proposed new Technical Specification SR 5.1.8 which incorporates the associated,

surveillance requirements.

Public Service Company of Colorado (PSC) requests NRC approval of these Technical Specifications and issuance of a license' amendment.

n7o28aBu* ooh 7' y

e 3

e t

m

a

.a P-87124 ~ June 25, 1987 This resubmittal supersedes PSC's previous proposed changes for LCO 4.1.9 (References I and 2). The Technical Specifications have been revised to address NRC concerns regarding the use of the 760 degrees F Calculated Bulk Core Temperature concept for interrupting forced circulation, as discussed in Reference 3.

The curves that PSC uses for determining allowable time periods for j

interruption of forced circulation have been added to the Technical i

Specifications in Section 4.0, along with a specific maximum time limit beyond which forced circulation must be restored.

In response to other NRC concerns identified in Reference 3 regarding FSV assurances of decay heat removal capability, PSC commits to the following:

1.

To maintain at least one PCRV liner cooling system loop in operation under the provisions of LCO 4.2.13 and LCO 4.2.15, and j

2.

To ensure that at least a firewater pump, a water supply, and a firewater flow path to the PCRV liner cooling system are operable during planned interruption of the primary coolant flow, when the PCRV liner cooling system is relied upon for decay heat removal.

< provides a Summary of Proposed Changes to the existing Technical Specifications and Attachment 2 includes the Proposed Changes.

The format for additions to the existing license reflects the format being incorporated into the Technical Specification Upgrade Program. Attachments-3 and 4 contain the Safety Analysis and the Significant Hazards Consideration for the proposed change, in accordance with 10CFR50.92.

This change does not involve a significant hazards consideration.

Consistent with PSC's position provided in Reference 2, PSC is currently operating and commits to continue operating FSV in accordance with requirements contained in the attached proposed Technical Specifications. These requirements are significantly more restrictive than the limits of the existing Technical Specifications, as discussed in the Safety Analysis provided in Attachment 3.

i 9

=

.i

. 4 P-87124 June 25, 1987 In accordance with the provisions of 10 CFR 170, an application fee of $150.00 was provided with the Reference 2 submittal of LC0 4.1.9.

An additional fee is not provided at this time, as PSC considers this resubmittal a continuation of the previous application.

If you have any questions or comments concerning the enclosed 1

information, please call Mr. M. H. Holmes at (303) 480-6960.

Very truly yours,

((

M/hp i

i R. O. Williams, Jr.

Vice President Nuclear Operations Attachments cc:

Regional Administrator, Region IV ATTN: Mr. J. E. Gagliardo, ".i'ief Reactor Projects Branch Mr. Robert Farrell Senior Resident Inspector Fort St. Vrain l

Mr. Albert J. Hazle Colorado Department of Health b,

l 8

e 1

UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION In the Matter

)

j

)

l Public Service Company of Colorado

)

Docket No. 50-267 Fort St. Vrain Unit No. 1

)

I 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.

$0?

R' 0; Williams, Jf.

Vice President Nucleer Operations STATE OF

( W arftv

)

)

COUNTY OF 2,rnno/

_)

Subscrige and sworn to Aefore me, a Notary Public on this

//M ' day of V/znz/

, 1987.

0 hidWO h Y'br//fr/tff/nd NytaryPublic

/'/

My commission expires hoaza/ 72

,198f.

O