ML18149A332
| ML18149A332 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 10/07/1986 |
| From: | Stewart W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | Harold Denton, Rubenstein L Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML18149A333 | List: |
| References | |
| 86-376, NUDOCS 8610140390 | |
| Download: ML18149A332 (3) | |
Text
e VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 W. L. STEWART VICE PRESIDENT NUCLEAR OPERATIONS October 7, 1986 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation Attn:
Mr. Lester S. Rubenstein, Director PWR Project Directorate No. 2 Division of PWR Licensing-A U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Gentlemen:
VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNIT NOS. l AND 2 PROPOSED TECHNICAL SPECIFICATION CHANGE CONTROL ROD INSERTION LIMITS Serial No.
NO/PML/acm Docket Nos.
License Nos.86-376 50-280 50-281 DPR-32 DPR-37 Pursuant to 10 CFR 50.90, Virginia Electric and Power Company requests an amendment, in the form of changes to the Technical Specifications, to Operating License Nos. DPR-32 and DPR-37 for Surry Power Station Unit Nos.
1 and 2.
The proposed change to Section 3.12 of the Surry Technical Specifications pertains to operating with an inoperable, misaligned or dropped control rod.
The current Technical Specifications require implementation of an alternate set of control bank insertion limits if operation is continued with an inoperable or bottomed rod.
The alternate insertion limits are designed to offset the effects of the inoperable rod on such parameters as core peaking factors and shutdown reactivity margin.
As discussed in the Safety Evaluation the current approach has some inherent disadvantages which can penalize operational flexibility.
These disadvantages are addressed in more recent versions of Technical Specifications (such as the Westinghouse Standardized Technical Specifications) by eliminating the alternate insertion limits and imposing more detailed requirements for the timely evaluation of peaking factors, shutdown margin and the potential impact of operation with the dropped or misaligned rod on the various accident analyses presented in the Updated Final Safety Analysis Report.
The proposed change will increase operational flexibility while ensuring that operation with a dropped or misaligned rod will not invalidate the UFSAR accident analysis basis.
The proposed change has been reviewed and approved by the Station Nuclear Safety and Operating Committee and by the Safety Evaluation and Control Aool I I I
Staff.
As indicated in the attached Safety Evaluation, it has been determined that. this 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.
We have evaluated this request in accordance with the criteria in 10 CFR 170.12.
A check in the amount of $150 is enclosed as an application fee.
Very truly yours, W. L. Stewart Attachments: 1.
- 2.
- 3.
Proposed Technical Specification Change Safety Evaluation -
Voucher Check cc:
Dr. J. Nelson Grace Regional Administrator NRC Region II 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
COMMONWEALTH OF VIRGINIA)
)
CITY OF RICHMOND
)
The foregoing document was acknowledged before me, in and for the City and Commonweal th 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
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