ML20204K098
| ML20204K098 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 03/16/1987 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20204K068 | List: |
| References | |
| NUDOCS 8703270363 | |
| Download: ML20204K098 (2) | |
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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 54 TO FACILITY OPERATING LICENSE DPR-77 AND AMENDMENT NO. 46 TO FACILITY OPERATING LICENSE DPR-79 TENNESSEE VALLEY AUTHORITY INTRODUCTION Generic Letter 85-09 specifies Technical Specification changes applicable to the Reactor Trio System Instrumentation and Surveillance. Generic Letter 85-09 concluded that Technical Specification changes should be proposed by licensees to explicitly require independent testing of the undervoltage and shunt trip attachments of the reactor trip breakers during power operation, testing of bypass breakers prior to use, and independent testing of the control room manual switch contacts and wiring during each refueling outage. These changes have now been incorporated in the Westinghouse Standard Technical Specifications.
EVALUATION The licensee submitted proposed Technical Specification changes for the Sequoyah Nuclear Plant, Units I and 2, by letter dated January 20, 1987.
The following proposed changes were submitted:
Table 3.3-1, Functional Unit 20 (Reactor Trip Breakers), Functional Unit 21 (Automatic Trip Logic).
Table 4.3-1, Functional Unit 1 (Manual Reactor Trip), Functional Unit 20 (Reactor Trip Breaker), Functional Unit 21 (Automatic Trip Logic) and Functional Unit 23 (Reactor Trip Bypass Breaker).
I We have compared the licensee's proposed Technical Specification changes with those of Generic Letter 85-09 and find that they are consistent with the require-ments of Generic Letter 85-09.
The Table 3.3-1 proposed changes pertain to limiting conditions for operation and associated action statements if the minimum operability conditions are not satisfied. The action statements would require going to hot standby within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and subsequent opening of the reactor trip breakers within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> if the inoperable condition persisted.
If only one of the diverse trip features of a reactor trip breaker became inoperable, the action statement would permit an additional 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> before going to hot standby.
The Table 4.3-1 proposed modifications would require verification of operability of the manual trip circuits of the reactor trip breakers (RTBs) and byoass breakers during refueling outages and prior to startup, including independent verification of the undervoltage and shunt trip circuitry. The Table 4.3-1 prooosed modifica-tions would also require on-line testing of the RTBs, including independent testing of the undervoltage and shunt trip functions, and on-line testing of the automatic trip logic channels for each train, at least every 67 days on a staggered test basis. They also orovide for testing of the operability of the reactor trip bypass breaker prior to placing the breaker in service.
3103270363 F/03id, PDR ADOCK 05000327 P
-L-4 We have reviewed the proposed Sequoyah Technical Specifications for the above
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functional units, including the action statements and table notations, and find they are consistent with those of Generic Letter 85-09. We find that the pro-posed changes enhance plant reliability and safety, and therefore find them to be acceptable.
ENVIRONMENTAL CONSIDERATION These amendments involve changes to the installation or use of the facilities' components located within the restricted area as defined in 10 CFR Part 20 and changes in surveillance requirements. The 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 signif-icant 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. Accordingly, the amendments meet the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). Pursuant to 10 CFR 51.22(b) no environmental impact statement or environmental assess-ment need be preparvd in connection with the issuance of the amendments.
CONCLUSION The Commission made a proposed determination that the amendments involve no significant hazards consideration which was published in the Federal Register on February 11,1987 (52 FR 4420) and consulted with the state of Tennessee.
No public comments were received, and the state of Tennessee did not have any comments.
We have 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, and (2) such activities will be conducted in compliance with the Comission's regulations and the issuance of these amendments will not be inimical to the comon defense and security or to the health and safety of the public.
Principal Contributors: Joe Holonich, PWRf4, DPWR-A
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Argil Toalston, PAEI, DPWR-A Dated: March 16, 1987
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AMENDMENT NO.54TO FACILITY OPERATING LICENSE N0. DPR Sequoyah Nuclear Plant Unit 1 AMENDMENT N0.46TO FACILITY OPERATING LICENSE NO. DPR Sequoyah Nuclear Plant Unit 2
. DISTRIBUTION w/ enclosures:
. Docket No.
50-327/328 NRC PDR Local PDR NSIC PRC System PD#4 Reading File J. Holonich M. Duncan OGC-Beth R. Diggs, ADM T. Barnhart (8)
E. L. Jordan, DE0A:I&E L. J. Harmon, 18E B. J. Youngblood J. Holonich N. Thompson E. Butcher W. Jones H. Thompson, Jr.
H. Denton L. Spessard J. Taylor G. Zech, RII B. Hayes T. Novak K. Barr, RII M. Reinhart, AR J. Lazevnick A. Toalston
,