ML18153C204

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Suppl to 891103 Application for Amends to Licenses DPR-32 & DPR-37 Re Inoperable Control Rods.Proposed Change Provides Clarification to Required Actions for Two or More Inoperable Control Rods
ML18153C204
Person / Time
Site: Surry  Dominion icon.png
Issue date: 04/27/1990
From: Stewart W
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML18153C205 List:
References
89-644A, NUDOCS 9005030305
Download: ML18153C204 (3)


Text

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e e VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 April 27, 1990 United States Nuclear Regulatory Commission Serial No. 89-644A Attention: Document Control Desk NO/ETS 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 SUPPLEMENT TO PROPOSED TECHNICAL SPECIFICATION FOR INOPERABLE CONTROL RODS On November 3, 1989, pursuant to 10 CFR 50.90, the Virginia Electric and Power Company requested amendments to the Technical Specifications, for Operating License Nos. DPR-32 and DPR-37 for the Surry Power Station Units 1 and 2 respectively. This change would eliminate the confusion associated with the existing inoperable control rod specification, and at the same time bring it in line with the Standard Technical Specifications.

The proposed supplemental change provides clarification to the required actions for two or more inoperable control rods by specifying that a shutdown margin determination is required within one hour after determining more than one control rod inoperable. Previously, this requirement had been specified by procedure but not formally by Technical Specifications. The supplemental change is included in Attachment 1.

This supplemental change has been reviewed and approved by the Station Nuclear Safety and Operating Committee. It has been determined that the proposed change does 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 no significant hazards consideration determination has not changed from our original submittal. This basis was provided in our November 3, 1989 submittal (Letter no.89-644).

Very truly yours,

~N:fCLJ W. L. Stewart Senior Vice President - Power Attachment

1. Proposed Supplemental Technical Specification Change

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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

e COMMONWEALTH OF VIRGINIA )

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COUNlY 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 Z__2 day of ~ , 19~.

My Commission Expires:

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Notary Public I' I~

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