ML20245H827
| ML20245H827 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 04/27/1989 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20245H816 | List: |
| References | |
| NUDOCS 8905030542 | |
| Download: ML20245H827 (2) | |
Text
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- p" uqjo UNITED STATES g
8 NUCLEAR REGULATORY COMMISSION o
INASHINGTON, D. C. 20660 7,,
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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT N0.125 TO FACILITY OPERATING LICENSE NO. DPR-32 AND AMENDMENT N0.125 TO FACILITY OPERATING LICENSE N0. DPR-37 4
VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION, UNIT NOS. 1 AND 2 DOCKET NOS. 50-280 AND 50-281 INTRODUCTION The licensee, the Virginia Electric and Power Company, in its submittal dated July 29, 1988, proposed to amend the Technical Specifications (TS) to Facility Operating License Nos. DPR-32 and DPR-37. The proposed revision would modify TS 4.1.B.5.a to include two additional manual isolation valves located down-stream of the solenoid operated valves (S0Vs) in the reactor vessel head high point vent system. This revision will require the additional manual isolation valves to be locked open and placed under administrative control.
EVALUATION The NRC staff had previously approved the licensee's design of the Surry Units 1&2 reactor vessel high point vent system in a Safety Evaluation Report (SER) dated September 12, 1983 and concluded that it met the requirements of NUREG-0737, Item II.B.1 " Reactor Coolant System Vents." The approved system is comprised of a common manual isolation valve upstream of two parallel trains of remote operating S0Vs. Since issuance of the above cited SER, the licensee has installed a manual isolation valve in each train downstream of the 50Vs.
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downstream manual valves will allow testing and maintenance of the S0Vs when the reactor is shut down. These manual valves will also be used to determine which train of the 50V is leaking in the event of an S0V leakage problem.
Based on the staff's review of the licensee's July 29, 1988 submittal describing the licensee's modification and proposed TS changes, we conclude that modifica-tions conform with the requirements of NUREG-0737, Item II.B.1 " Reactor Coolant System Vents" and are, therefore, acceptable.
ENVIRONMENTAL CONSIDERATION These amendments involve a change in the installation or use of the facilities
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components located within the restricted areas as defined in 10 CFR Part 20.
l The staff has determined that these amendments involve no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite and that there is no significant increase in individual
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l or cumulative occupational 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.
Accordingly,
these amendments meet the eligibility criteria for categorical exclusion set forthin10CFR51.22(c)(9).
Pursuant to 10 CFR 51.22(b) no environmental impact statement or environmental assessment need be prepared in connection with the issuance of these amendments.
CONCLUSION We have concluded, based on the considerations discussed above, that:
(1) there is reasonable assurance that the health and saf aty of the public will not be endangered by operation in the proposed manner, and (2) such activities will be conducted in compliance with the Commission's regulations and the issuance of these amendments will not be inimical to the conmon defense and security or to the health and safety of the public.
Dated: April 27, 1989 Principal Contributor:
B. Buckley 1
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