ML20126D833
| ML20126D833 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 12/14/1992 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20126D824 | List: |
| References | |
| NUDOCS 9212280179 | |
| Download: ML20126D833 (3) | |
Text
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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGVLATION RELATED TO AMENDMENT NO.171 TO FACIllTY OPERATING LICENSE NO DPR-32 AND AMENDMENT N0.170 TO FACILITY OPERATING LICENSE NO. DPR-37 VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION, UNIT NOS, 1 AND 2 DOCKET NOS 50-280 AND 50-281
1.0 INTRODUCTION
By letter dated July 28, 1992, the Virginia Electric and Power Company (the licensee) proposed changes to the Technical Specifications (TS) for the Surry Power Station, Unit Nos. I and 2.
The changes would (1) delete the operability and surveillance requirements of the hydrogen monitor from the explosive gas monitoring instrumentation requirements for the waste gas holdup system, and (2) add a requirement to submit a special report to the NRC if the oxygen concentration in a waste gas decay tank exceeds the TS and is not returned to below that limit in a specified time. Moreover, the NRC staff and the licensee modified Action Item i on TS Table 3.7-5(a) for clarification purposes which did not change the proposed no significant hazards consideration determination.
In addition, administrative changes have been incorporated for consistency with NUREG-0452, Revision 4, " Standard Technical Specifications for Westinghouse Pressurized Water Reactors." The changes include the capitalization of TS " defined" words and the reformatting of tables.
2.0 Proposed Technical Soecification Chanaqs TS 3.ll-Al is being revised to require the oxygen concentration of the waste gas holdup tank be maintained at less than 2% by volume at all times whenever the hydrogen concentration could exceed 4% by volume.
TS 3.7.E, 4.1.B and Table 3.7-5(a) are being revised to capitalize the TS defined word " operable" for consistency with Standard TS.
TS 3.7.E is being revised to indicate only one explosive gas monitoring channel is required for operability.
The section is also being modified to refer to " alarm / trip" setpoint as " alarm" setpoint consistent with the actual function of the instrumentation.
TS Table 3.7-5(a) is being revised to delete the operability requirements for the hydrogen monitor and a " Total No. Of Channels" column is being added for consistency with the other tables in this section.
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. TS 3.ll.A.1 is being revised to replace the word " exceeds" with the phrase "could exceed" to consider the normal operation of the waste gas holdup system with the hydrogen concentration in excess of 4%.
TS 3.11.A.I.b is being revised to specifically reference TS 3.ll.A.I.a as the required action once TS 3.ll.A.I.b is met.
In addition, TS 3 ll.A.l.c is being added to require a special report to be submitted to the NRC within 30 days if the requirements of TS 3.ll.A.I.a are not met. The report will be required to include the following information:
(1) the cause of the waste gas holdup tank exceeding the 2% oxygen limit, and (2) the reason the oxygen concentration could not be returned to within limits, and (3) the actions taken and the time required to return the oxygen concentration to within the specified limits.
The Bases of TS 3.11 is also being changed to delete the reference to maintaining hydrogen concentration within specified limits.
TS 4.1. A is being revised to add " Table 4.1-It." to this section for completeness.
The hydrogen monitor surveillance requirements are being deleted from TS Table 4.1-1A.
TS 4.9.A is being revised to delete the references to hydrogen concentration and the hydrogen monitor.
3.0 EVALUATION The proposed changes, as specified above, ensure the concentration of potentially explosive gas mixtures contained in the waste gas holdup system will be maintained below the flammability limits of hydrogen and oxygen.
Maintaining oxygen below the concentration that will support combustion at any concentration of hydrogen provides assurance that the release of radioactive materials will be controlled in conformance with the requirements of General Design Criterion 60 of Appendix A, 10 CFR Part 50.
Therefore, the staff finds the proposed changes acceptable.
4.0 STATE CONSULTATION
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.
5.0 ENVIRONMENTAL CONSIDERATION
These amendments change a requirement with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20 and change the 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 effluents that may be released offsite, and that there is no significant increase in individual 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 1
.. -(57 FR 40223). Accordingly, these amendments meet the eligibility criteria for categorical exclusion set forth in 10 CFR. 51.22(c)(9). _ Pursuant to 10 CFR SI.22(b) no environmental impact statement or environmental assessment need be prepared.in connection with the issuance of these amendments.
6.0 (ONCLUSION 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 conducted 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 Contributors:
N. Stinson B. Buckley Date: December 14, 1992
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