ML18153D030

Application for Amends to Licenses DPR-32 & DPR-37,modifying Definition of Containment Integrity & Establishing LCOs & Operation & Action Statements for Containment Isolation Sys, Per Generic Ltr 91-08 & NUREG-0452

ML18153D030
Person / Time
Site:	Surry
Issue date:	06/01/1992
From:	Stewart W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML18152A176	List: ML18152A175 ML18153D030
References
RTR-NUREG-0452, RTR-NUREG-452 92-302, GL-91-08, GL-91-8, NUDOCS 9206120197
Download: ML18153D030 (3)

Text

e e VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA. 23261 June 1, 1992 United States Nuclear Regulatory Commission Serial No.92-302 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 PROPOSED TECHNICAL SPECIFICATION CONTAINMENT ISOLATION

_ Pursuant to 10 CFR 50.90, the Virginia Electric and Power Company requests

""- amEfndments,sin '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. - The proposed change 1) modifies the definition of containment integrity and establishes Limiting Conditions for Operation and Action Statements for containment isolation systems consistent with the Standard Technical Specifications (NUREG-0452), 2) eliminates the requirement for containment integrity during positive reactivity additions by rod drive motion or boron dilution, 3) eliminates the requirement for containment integrity with the head unbolted and less than 5% shutdown margin, 4) removes the containment isolation valve tables from the Technical Specifications in accordance with Generic Letter 91-08, "Removal of Component Lists From Technical Specifications," and 5) includes administrative changes to achieve consistency. The proposed change is included in Attachment 1. Also, consistent with the guidance of Generic Letter 91-08, a revision to the Containment chapter of the UFSAR is being completed and will be included in the next UFSAR submittal.

This request has been reviewed and approved by the Station Nuclear Safety and Operating Committee and the Management Safety Review 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. A discussion of the change and the basis for our no significant hazards consideration determination is included in Attachment 2.

Very truly yours, QY~~

Av' W. L. Stewart

\- Senior Vice President - Nuclear Attachments

1. Proposed Technical Specification Change

2. Discussion and Significant Hazards Consideration Determination oo{

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p.  : --

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

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

COMMONWEALTH OF VIRGINIA )

)

COUNTY OF HENRICO )

The foregoing document was acknowledged before me, in and for the County and Commonwealth aforesaid, today by J. P. O'Hanlon who is Vice President - Nuclear Operations, for 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 ___,,9"4-'-'U<loL/21...u.:.e_.._..-",--* 19!1..l...

My Commission Expires: cdt1-:J 3/ , 19~

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