ML20214V381
| ML20214V381 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 12/02/1986 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20214V363 | List: |
| References | |
| NUDOCS 8612090661 | |
| Download: ML20214V381 (3) | |
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UNITED STATES 8
NUCLEAR REGULATORY COMMISSION o
g y
E WASHINGTON, D. C. 20555 l
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO.51TO FACILITY OPERATTNG LICENSE DPR-77 AND AMENDMENT NO.43TO FACILITY OPERATING LICENSE DPR-79 TENNESSEE VALLEY AUTHORITY INTRODUCTION By letter dated April 7, 1986, the Tennestee Valley Authority requested changes to the Technical Specifications of Sequoyah Nuclear Plant, Units I and 2.
The requested changes would delete the requirements for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of data acquisition
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a'fter restoring the Axial Flux Difference Monitor to OPERABLE status. The staff has reviewed this request and prepared the following evaluation.
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EVALUATION Specification 4.2.1.1.a.2 requires that during the first 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after restoring the Axial Flux Difference (AFD) Monitor Alarm to OPERABLE status the indicated AFD be monitored once per hour. The motivation for this requirement was the desire to assure that the alarm was operating properly and to provide information to assess " penalty time" when operating with the Constant Axial Offset Control strategy. However, the Sequoyah plants now operate with the Pelaxed Axial Offset Control strategy which does not require that " penalty time" be accumulated.
Further, Specification 4.2.1.1.a.1 requires periodic monitoring of the alarm to assure its continued operation. Specification 4.2.1.1.b provides the surveillance requirements for periods when the alarm is not OPERABLE.
We therefore conclude that Specification 4.2.1.1.a.2 is not required and that the proposed Technical Specification change is acceptable.
ENVIRONMENTAL CONSIDERATION These amendments involve changes in use of facility components located within I
the restricted area as defined in 10 CFR Part 20 and changes in surveillance requirements. The staff has determined that the amendments involve no signi-ficant 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 in-crease 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 51.22fc1(91. Pursuant to 10 CFR 51.22(b) no environmental impact statement or environmental assess-ment need be prepared in connection with the issuance of the amendments.
8612090661 861202 PDR ADOCK 05000327 P
f CONCLUSION The Commission made a proposed determination that the amendments involve no significant hazards consideration which was published in the Federal Register on August 27,1986 (51 FR 30581) 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 Commission's regulations and the issuance of these amendments will not be inimical to the common defense and security or to the health and safety of the public.
Principa.1 Contributors: Carl R. Stahle, PWR#4, DPWR-A Joe Holonich, PWR#4, DPWR-A W..Rrooks, PARS Dated: December 2, 1986 h
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t e
December 2, 1986 AMENDMENT NO.51T0 FACILITY OPERATING LICENSE NO. DPR Sequoyah Nuclear Plant Unit 1 AMENDMENT NO.43T0 FACILITY OPERATING LICENSE NO. DPR Sequoyah Nuclear Plant Unit 2
, DISTRIBUTION w/ enclosures:
' Docket No.-
50-327/328 4
NRC PDR Local PDR NSIC PRC System PD#4 Reading File C. Stahle M. Duncan OGC-Beth R. Diggs, ADM T. Barnhart (8)
E.L. Jordan, DEQA:I&E L.J. Harmon, IAE B.J. Youngblood J. Holonich N. Thompson E. Butcher W. Jones H. Denton J. Taylor G. Zech, RII B. Hayes K. Barr. RII E. Fields, EICSB H. Thompson, Jr.
M. Reinhart, AR