ML18150A157

Supplemental Application for Amends to Licenses DPR-32 & DPR-37,changing Tech Specs Re Operation W/Inoperable Control Rod,Imposing Detailed Set of Evaluation & Surveillance Requirements.Suppl Adds Addl Requirements,Per 870409 Telcon

ML18150A157
Person / Time
Site:	Surry
Issue date:	06/08/1987
From:	Stewart W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
Shared Package
ML18150A159	List: ML18150A157 ML18150A161
References
86-376A, NUDOCS 8706150213
Download: ML18150A157 (3)

Text

e e VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 June 8, 1987 W. L. STEWART V1cE PRESIDENT NUCLEAR OPERATIONS U. S. Nuclear Regulatory Commission Serial No. 86-376A Attn: Document Control Desk E&C/NAS:vlh Washington, D. C. 20555 Docket Nos. 50-280 50-281 License Nos. DPR-32 DPR-37 Gentlemen:

VIRGINIA ELECTRIC AND POWER COMPANY SORRY POWER STATION UNITS 1 AND 2 SUPPLEMENT TO PROPOSED TECHNICAL SPECIFICATION CHANGE CONTROL ROD INSERTION LIMITS Virginia Electric and Power Company letter, Serial 86-376, dated October 7, 1986, submitted a Technical Specification change request pertaining to operation with an inoperable, misaligned, or dropped control rod. The proposed changes impose a detailed set of evaluation and surveillance requirements for such operation. This submittal revises our change request, consistent with a telephone conversation with the NRC Staff on April 9, 1987, by including an additional surveillance requirement requiring evaluation of the axially dependent radial power peaking factor, Fxy(Z). Evaluation of Fxy(Z) provides added assurance that operation with a dropped or misaligned rod will not invalidate the UFSAR accident analysis basis.

This supplemental change augments the previously submitted change request and as such does not alter the conclusions, safety review, or significant hazards determination of the previous request. The supplemental change has been reviewed and approved by the Station Nuclear Safety and Operating Committee and by the Safety Evaluation and Control Staff. As indicated in the attached Safety Evaluation, it has been determined that this supplement to our initial request does not involve an unreviewed safety question as defined in 10 CFR 50.59 nor does it pose a significant hazards consideration as defined in 10 CFR 50.92.

8706150213 870608 PDR ADOCK 05000280 P PDR

e e The application fee for this change request.was previously submitted with our October 7, 1986 transmittal. If you have any questions, or need additional information to process this request, please contact us.

Very truly yours,

~l~

W. L. Stewart Attachments:

1. Proposed Technical Specification (Supplemental Change)

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

Suite 2900 Atlanta, GA 30323 Mr. W. E. Holland NRC Senior Resident Inspector Surry Power Station Mr. Charles Price Department of Health 109 Governor Street Richmond, Virginia 23219 Mr. Chandu P. Patel NRC Surry Project Manager PWR Project Directorate No. 2 Division of PWR Licensing-A

- e COMMONWEALTH OF VIRGINIA)

)

CITY OF RICHMOND )

The foregoing document was acknowledged before me, in and for the City and Commonwealth aforesaid,

• today by W. L. Stewart who is Vice President -

Nuclear Operations, 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 L day of * ~ , 19 [7 My Commission e x p i r e s : , ~ ~ ZS:, 19 """q"'""""~--

'\_

~

's (SEAL)

S/001