ML18153C671

Application for Amends to Licenses DPR-32 & DPR-37,revising Safety Analysis Limit to Value of 1.62 & Provide Changes for Implementation of Statistical DNBR Evaluation Methodology

ML18153C671
Person / Time
Site:	Surry
Issue date:	07/08/1991
From:	Stewart W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML18151A638	List: ML18151A637 ML18153C671
References
91-374, NUDOCS 9107160232
Download: ML18153C671 (3)

Text

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ee VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 July 8, 1991 United States Nuclear Regulatory Commission Serial No.91-374 Attention: Document Control Desk NA&F/GLD R1 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 CHANGES F8h INCREASE/STATISTICAL DNBR METHODOLOGY Pursuant to 10 CFR 50.90, 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. The proposed Technical Specification changes support an increase in the safety analysis F8h limit to a value of 1.62 and provide changes for implementation of the Statistical DNBR Evaluation Methodology.

An increased F8h is needed to accommodate the increased radial power factors which will result from the planned installation of flux suppression inserts (FSls). The FSls decrease the relative power in key peripheral fuel assemblies and, thereby, reduce the fast neutron flux at reactor vessel locations experiencing neutron irradiation embrittlement.

Application of the Statistical DNBR Evaluation Methodology provides increased thermal-hydraulic margin at Surry by treating key DNBR analysis uncertainties in a less restrictive, but appropriately conservative statistical manner. The Statistical DNBR Evaluation Methodology, which is described in Topical Report VEP-NE-2-A, has been previously applied to the North Anna units.

Although FSls are not planned to be installed in Surry Unit 1 until Cycle 13, it is our intention to utilize the Statistical DNBR Evaluation Methodology in UFSAR transient reanalyses, reload core design, and safety analysis evaluations upon approval of the proposed Technical Specification changes.

ee ee The Technical Specification pages affected

• by this revision are included in . Attachment 2 provides a discussion and safety evaluation of the proposed changes.

This proposed revision has been reviewed and approved by the Station Nuclear Safety and Operating Committee and by the Management Safety Review Committee.

It has been determined that the proposed changes do not involve an unreviewed safety question as defined in 10 CFR 50.59 and, as shown in Attachment 3, involves no significant hazards consideration as defined in 10 CFR 50.92.

Very truly yours,

~\_~

W. L. Stewart Senior Vice President - Nuclear Attachments cc: U. S. Nuclear Regulatory Commission Region II 101 Marietta Street, N. W.

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

ee --

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 87JI day of ___::9=-#-=~~1---* 191/.

My Commission Expires: ( JJ1atg 31 , 19-'1.'L..

_t%le,~ilu.RL-Notary Public (SEAL) .-