ML18153C014

Application for Amends to Licenses DPR-32 & DPR-37,deleting Tech Spec 5.3.A.7 Re Enriched Fissionable Matl Used in Core or Available on Site,In Form of Fabricated Neutron Flux Detectors for Purposes of Monitoring Core Neutron Flux

ML18153C014
Person / Time
Site:	Surry
Issue date:	12/11/1989
From:	Stewart W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML18153C015	List: ML18153C014 ML18153C016
References
89-805, NUDOCS 8912200046
Download: ML18153C014 (5)

Text

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. e e VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 December 11, 1989 United States Nuclear Regulatory Commission Serial No.89-805 Attention: Document Control Desk NO/JZL:

Washington, D.C. 20555 Docket Nos. 50-280 50-281 License Nos. DPR-32 DPR-37 Gentlemen:

VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNITS 1 AND 2 PROPOSED TECHNICAL SPECIFICATION SPECIAL NUCLEAR MATERIAL Pursuant to 10 CFR 50.90, the Virginia Electric and Power Company requests amendments, in the form of changes to the Technical Specifications, to Operating License Nos. DPR-32 and DPR-37 for the Surry Power Station Units 1 and 2, respectively. This change deletes Technical Specification 5.3.A.7 which states that up to ten grams of enriched fissionable material may be used either in the core or available on site, in the form of fabricated neutron flux detectors for the purposes of monitoring core neutron flux.

This request has been reviewed and approved by the Station Nuclear Safety and Operating Committee and the Safety Evaluation and Control Staff. It has been determined that the proposed changes do not involve an unreviewed safety question as defined in 10 CFR 50.59 or a significant hazards consideration as defined in 10 CFR 50.92. The basis for our determination of no significant hazard is included in Attachment 2.

Very t~ours,

&t~~

W. L Stewart Senior Vice President - Nuclear Attachments

1. Proposed Technical Specification Change

2. Significant Hazards Consideration Determination 8912200046" 891211 PDR ADOCK 05000280 P PNU

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• cc: U.S. Nuclear Regulatory Commission Region II 101 Marietta Street, N.W.

Suite 2900 Atlanta, Georgia 30323 Mr. W. E. Holland NRC Senior Resident Inspector Surry Power Station Commissioner Department of Health Room 400 109 Governor Street Richmond, Virginia 23219

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• COMMONWEALTH OF VIRGINIA )

)

COUNTY OF HENRICO )

The foregoing document was acknowledged before me, in and for the County and Commonwealth aforesaid, today by W. L. Stewart who is Senior Vice President - Nuclear, of Virginia Electric and Power Company. He is duly authorized to execute and file the foregoing document in behalf of that Company, and the statements in the document are true to the best of his knowledge and belief.

Acknowledged before me this // day of ./a.e~ , 19..&.2._.

My Commission Expires: ~~ 2:£ , 19 9ei .

__§~_~_//fdL_

Notary Public

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(SEAL/: -;

e ATTACHMENT 1 Proposed Technical Specification Change

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• DISCUSSION The Surry Power Station Facility Operating Licenses (Nos. DPR-32 and DPR-37) allow the receipt, possession, and use of special nuclear material as fission detectors, as well as other uses, in amounts as required. Technical Specification 5.3.A.7, in describing the design features of the station, states that up to ten grams of enriched fissionable material may be used either in the core or available on site, in the form of fabricated neutron flux detectors, for the purposes of monitoring core neutron flux.

Greater than ten grams of enriched fissionable material is presently in use at each Surry Power Station Unit in the form of core neutron flux detectors.

An investigation was conducted to determine the source of Technical Specification 5.3.A.7. It was noted that Technical Specification 5.3.A.7 was an original specification and that no correspondence could be located that referenced the ten gram figure.

Standard Technical Specifications do not include a corresponding limitation or discussion of the quantity of special nuclear material used on site. It is our conclusion that Technical Specification 5.3.A.7 was incorporated into the original Technical Specifications for information purposes only and was not intended to limit the quantity of special nuclear material used in neutron flux detectors. This conclusion is supported by the use of the phrase, " ... in amounts as required;" in the Operating Licenses, as amended, and the absence of a corresponding limiting condition for operation. To prevent this original design information from being interpreted as a limit, we propose to delete Technical Specification 5.3.A.7. Deletion of this specification is consistent with Standard Technical Specificatio.ns.