ML20045H957
| ML20045H957 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 07/08/1993 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20045H952 | List: |
| References | |
| NUDOCS 9307220171 | |
| Download: ML20045H957 (4) | |
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WASHINGTCN, D.C. 20556-0001 gv f i
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION j
RELATED TO AMENDMENT NO.180 TO FAClllTY OPERATING LICENSE NO. DPR-32 AND AMENDMENT NO.180 TO FACILITY OPERATING LICENSE N0. 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
Pursuant to 10 CFR 50.90, by letter dated August 7, 1992, the Virginia Electric and Power Company (the licensee) proposed changes to the Technical Specifications (TS) for the Surry Power Station, Units 1 and 2, respectively.
The changes would (1) add explicit operability, action, and surveillance requirements for the Recirculation Mode Transfer (RMT) function, (2) delete the references to Refueling Water Storage Tank (RWST) maximum volume requirements and clarify RWST water temperature requirements, and (3) specify time limits to accomplish unit shutdowns under certain circumstances and to take corrective actions to address minor deviations from TS limits on RWST volume, temperature, or boron concentration.
In addition, administrative changes have been incorporated for consistency with NUPEG-0452, " Standard Technical Specifications for Westinghouse Pressurized Water Reactors,"
Revision 4.
The changes include the capitalization of TS " defined" words and the reformatting of tables.
2.0 PROPOSED TECHNICAL SPECIFICATION CHANGES TS 3.3.A.1 is being revised to specify a maximum RWST water temperature of 45" F.
TS 3.3.B is being revised to add time limits, consistent with TS 3.0.1, for placing a unit in hot shutdown and then in cold shutdown.
TS 3.3.B.10 is being added to provide a one-hour TS Action Statement to return RWST volume, temperature, or boron concentration to allowable values prior to entering a 6-hour TS Action Statement to shut down the unit.
i TS 3.4. A.3 is being revised to delete the maximum RWST volume and to specify a maximum RWST water temperature of 45* F.
TS 3.4.B.5 is being added to provide a one-hour TS Action Statement to return RWST volume, temperature, or boron concentration to allowable values prior to entering a 6-hour TS Action Statement to shut down the unit.
9307220171 930708 PDR ADOCK 05000200 p
2 TS 3.4.B is being revised to add t'ime limits, consistent with TS 3.0.1 and NUREG-0452, " Standard Technical Specifications for Westinghouse Pressurized Water Reactors," Revision 4, for placing a unit in cold shutdown within 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br /> if safety injection equipment cannot be returned to service within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after reaching hot shutdown.
TS 3.4.C is being deleted to be consistent with the previous deletions of the provision which permitted operation with RWST water temperature greater than 45" F.
TS Table 3.7-2 is being revised to add Item No. 7, Recirculation Mode Transfer (RMT).
Operability requirements for the RWST level channels and actuation logic channels are being specified. A corresponding TS Action Statement (Action 25) is being included which will require an inoperable RWST level channel to be placed in bypass within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> with the total number of operable channels one less than the total number of channels or be in HOT SHUTDOWN within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following iD hours.
In addition, the Action Statement allows one additional channel to be bypassed for up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for surveillance testing.
TS Table 3.7-4 is being revised to add Item No. 9, Limiting Instrument Settings for RMT actuation.
TS 3.7 Basis Section for Accident Monitoring Instrumentation is being revised to accurately reflect valve position indication devices for Pressurizer Power Operated Relief Valves (PORV). The PORV position indication operability requirements are being restated consistent with NUREG-0452, " Standard Technical Specifications for Westinghouse Pressurized Water Reactors,"
Revision 4.
TS Table 4.1-1 is being revised to clearly require RWST level instrumentation channel functional testing and actuation logic testing on a monthly basis.
TS Table 4.1-2A is being revised to add surveillance requirements for RWST water temperature and volume.
In addition, administrative changes are being completed to achieve consistency throughout the TS.
3.0 EVALUATION The proposed changes, as specified above, address two major safety considerations. They are (1) the effect on RMT reliability with a failed RWST level instrument in the bypass condition and (2) the effect on RWST integrity with the deletion of the maximum volume requirement. The remainder of the proposed changes are administrative in nature and do not significantly affect plant operations.
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3 Bypassing a failed RWST level instrument changes the RMT actuation logic from two-out-of-four channels to two-out-of-three channels sensing a low RWST level. With a level instrument in bypass, the capability to withstand a single active failure is still maintained. Continued plant operation with an RWST instrument in bypass is consistent with NUREG-0452, " Standard Technical Specifications for Westinghouse Pressurized Water Reactors," Revision 4.
The existing TS do not explicitly provide operability requirements for RMT or the RWST level instruments. Therefore, a failed RWST level instrument would require entering TS 3.0.1, shutting down the unit and placing the plant in an unnecessary transient.
Conversely, placing a failed instrument in trip would increase the probability of a spurious RMT actuation which could cause loss of charging pump suction during normal operation or loss of safety injection suction during a design basis accident. Allowing continued plant operation with an RW5T level instrument in bypass does not significantly change the level of protection afforded by the RMT function, while avoiding unnecessary plant transients.
A seismic evaluation was done for the RWST and its contents which established a maximum volume limit during a 1981 containment spray system modification. A subsequent analysis was performed to confirm the seismic adequacy of the tank for any maximum volume. Modifications were made to the RWST support system as a result of this analysis. The analysis concluded that the tank design was adequate throughout the range of RWST volume. With the implementation of these modifications, specifying a maximum RWST volume is no longer necessary.
4.0
SUMMARY
The staff has reviewed the licensee's proposed revisions to TS Sections 1, 3.3, 3.4, 3.7, and 4.1 and finds them to be acceptable.
5.0 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.
6.0 ENVIRONMENTAL CONSIDERATION
S Pursuant to 10 CFR 51.32 an environmental assessment has been published (58 FR 28423) in the Federal Reaister on May 13, 1993. Accordingly, the Commission has determined that the issuance of this amendment will not result in any environmental impact other than those evaluated in the Final Environmental Statement.
7.0 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 i
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4 activities will be conducted in co'mpliance 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:
T. Farnholtz Date: July 8, 1993 i
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