ML20133K675

Notifies That Draft Proposed Rev to Tech Spec Limiting Condition for Operation 4.1.9 Re Core Region Temp Rise Will Be Submitted for Review by 851122

ML20133K675
Person / Time
Site:	Fort Saint Vrain
Issue date:	10/17/1985
From:	Brey H PUBLIC SERVICE CO. OF COLORADO
To:	Butcher E Office of Nuclear Reactor Regulation
References
P-85372, TAC-52634, NUDOCS 8510220237
Download: ML20133K675 (2)

Text

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h PublicService .u. s.,m.

Company of Colorado 2420 W. 26th Avenue, Suite 100D, Denver, Colorado 80211 October 17, 1985 Fort St. Vrain Unit No. 1 P-85372 Director of Nuclear Reactor Regulation U.S. Nuclear Regulatory Comission Washington, D.C. 20555 Attention: Mr. E.J. Butcher, Jr., Acting Chief Operating Reactors Branch No. 3 DOCKET NO: 50-267

SUBJECT:

Revised Draft of LC0 4.1.9, Core Region Temperature Rise

REFERENCE:

PSC Letter, Brey to Johnson dated August 1, 1985 (P-85271)

Dear Mr. Butcher:

This letter is to report the current status of PSC's efforts regarding the proposed revision of Fort St. Vrain Technical Specification LC0 4.1.9, Core Region Temperature Rise, and to advise the NRC that a draft of this Spacification will be submitted for review by November 22, 1985, As indicated in the referenced letter, PSC had intended to submit a Draft of LC0 4.1.9 by October 15, 1985, along with the final draf t of the upgraded Technical Specifications. However, recent FSV activities related to plant restart, Environmental Qualification (E0) of electrical equipment, the Inservice Inspection (ISI) program, and the upgraded Technical Specifications, have not permitted this.  ;

Notwithstanding these other activities, recent progress has been made in this effort, as follows:

i PSC has obtained the ORECA computer code, and has identified and been able to explain the origin of past differences between ORNL's results using the ORECA code and the codes used by GA Technologies (GA) to analyze LC0 4.1.9.

L QR10220237 e51017 0L0 p ADOCK 05000267 I

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A meeting was held between GA and PSC representatives to finalize the calculated flow requirements and define the operational flow capabilities.

FSV has been restarted, and this will permit PSC to verify capabilities for meeting the helium flow requirements of the proposed LC0 4.1.9.

Investigations are continuing in the areas of establishing an orifice positioning strategy, allowing for short term low flow transients, and optimizing orifice positions, during operation.

PSC is pursuing the remaining open items and will submit a draft LC0 4.1.9 for NRC review by November 22, 1985. Upon resolution of any NRC comments, PSC will submit a formal Technical Specification amendment request.

f If you have any questions, please contact Mr. M. H. Holmes at (303) 571-8409.

Very truly yours,

-w H. L. Brey, Manager Nuclear Licensing and Fuels Division HLB /SWC/ljb