ML20076G867

Outlines Plan to Complete Review & Update Tech Spec Requirements for Inservice Insp & Testing Pertaining to Other Reactor Auxiliary & Support Sys That Perform Safety Function for Postulated Design Basis Events

ML20076G867
Person / Time
Site:	Fort Saint Vrain
Issue date:	06/01/1983
From:	Brey H PUBLIC SERVICE CO. OF COLORADO
To:	Jay Collins NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
References
P-83195, TAC-53417, NUDOCS 8306160286
Download: ML20076G867 (2)

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. l public Service Company &Odonde 2420 W. 26th Avenue, Suite 100D D,enver, Colorado 80211

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983 Fort St. Vrain k'

P-83195 Unit No. 1 y..

Mr. John T. Collins, Regional Administrator Region IV Nuclear Regulatory Commission 611 Ryan Plaza Drive Suite 1000 Arlington, Texas 76011

SUBJECT:

Fort St. Vrain Inservice Inspection and Testing - Status Update

REFERENCE:

1) PSC letter P-80218; J.K. Fuller to James Miller, dated 7/16/80

Dear Mr. Collins:

Recently, the Technical Specifications for Fort St.

Vrain were revised by License Amendment No. 33 to update various Surveillance Requirements pertaining to inservice inspection and testing for the Prestressed Concrete Reactor Vessel (PCRV), Reactor Internals, Primary Coolant System, Secondary Coolant System, and PCRV Auxiliary Systems.

This letter outlines PSC's plan to complete the review and update of Technical Specification Requirements for inservice inspection and testing as they pertain to other reactor auxiliary and support systems that perform a safety function for postulated design basis events.

Principal auxiliary and support systems to be reviewed are the helium

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circulator auxiliary system, the helium purification system, the reactor auxiliary cooling water systems, the reactor building HVAC system, and ACM equipment.

The review of the reactor auxiliary-cooling water systems is essentially complete and was submitted to the NRC in preliminary fann by Reference 1.

This review covered the 8306160286 830601 gDRADOCK 05000267

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P-83195 Page 2 circulating water system, the service water system, the fire water supply system, the reactor plant cooling water system and the purification cooling water system, and provided drafts of proposed changes to the applicable Technical Specification requirements.

Because of the nature of the remaining work, PSC does not plan to submit the results of further reviews in preliminary form.

Instead, changes to the Surveillcoce Requirements, resulting from these reviews, will be assembled in one package and submitted with an application to amend the Technical Specifications. The adequacy of the Surveillance Requirements applicable to these systems will be discussed in the safety evaluation accompanying the application.

This submittal will complete PSC's commitment to review and update the inservice inspection and testing requirements for Fort St. Vrain.

PSC anticipates that the remaining system re/iews and preparation of the license amendment will be completed by the end of 1983.

Should you have any questions concerning PSC's plan to complete this update, please contact Mr. Mike Holmes at (303) 571-8409.

Very truly yours, WL s

H. L. Brey, Manager i

Nuclear Engineering Division HLB /JRJ:pa

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