ML20082K104
| ML20082K104 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 08/19/1991 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20082K099 | List: |
| References | |
| NUDOCS 9108290187 | |
| Download: ML20082K104 (2) | |
Text
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UN11 ED STATES 8'
NUCLEAR REGULATORY COMMISSION
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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO.161 TO FACILITY OPERATING LICENSE N0. DPR-32 AND AMENDMENT N0.160 10 FACILITY OPERATING LICENSE NO. OPR-37 VIRGINTA ELECTRIC AND POWER COMPANY SURRY POWER STATION, UNIT NOS. 1 AND 2 DOCKET N05. 50-280 AND 50-231
1.0 INTRODUCTION
By letter dated October 12, 1994, the Virginia Electricland Power Company (the licensee) proposed a changs to the Technical Specifications (TS) for the Surry Power Station, Units 1 and 2.
Specifically, the proposed change would revise TS Table 4.1-2A by replacing the control rod drop time test frequency requirement associated with "the breach of the Reactor Coolant System integrity" with conditions similar to those in the Westinghouse Standard Technical Specifi-cations (STS), which the NRC staff has approved.
2.0 DISCUSSION j
Currently, control rod drop time tests are required "each refueling shutdown or af ter disassembly or maintenance requiring the breach of the Reactor Coolant System integrity." Literal interpretation of this requiren.ent would result in unnecessary testing following any " breach of Reactor Coolant System integrity" which does not affect the drop time of any control rod, such as maintenance of a loop valve or opening of a power operated relief valve in the Reactor Coolant System.
The proposed change would clarify the required test frequency by incorporating terminology from the Westinghouse STS.
The revised control rod drop time test frequency requirement would include testing of all rods after each refueling shutdown and each removal of the reactor vessel head, and of
" specially affected individual rods following any maintenance on or modification to the control rod drive system which could affect the drop time of those specific rods." This change retains all test frequency requirements intended in the original TS, while removing ambiguous wording which could result in unnecessay testing. Therefore, the staff finds the proposed change acceptable.
3.0 STATE CONSULTATION
i In accordance with the Commission's regulations, the Virginia State official was notified of the proposed issuance of the amendments. The State official had no comment, i
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4.0 ENVIRONMENTAL CONSIDERATION
These amendments change a requirement with respect to installation or use of a facility component located within the restrit,ted area as defined in 10 CFR Part 20 and changes surveillance requirements.
The NRC staff has determined that the amendments involve no significant increase in the amounts, and no significant change in the types, of any effiuents that may be released offsite, and_that there is no significant increase to individual or cumulative occupatio-nal radiation exposure. The Commission has previously issued a proposed finding that these amendments involve no significant hazards consideration and there has been no public comment on such finding (55 FR 10547). Accordingly, these amendments meet the eligibility criteria for categorical erclusion set forth in 10 CFR 51.22(c)(9).
Pursuant to 10 CFR 51.22(b) no env.conmental impact statement or environmental assessment need be prepared in connection with the issuance of these amendments.
5.0 CONCLUSION
The Commission has concluded, based on the considerations discussed above, that:
(1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be condu ted in compliance with the Commission's regulations, and (3) the issuance of these amendments will _not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributor:
D. Dorman Date: August 19, 1991 0
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