ML20210C679
| ML20210C679 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 09/16/1986 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20210C661 | List: |
| References | |
| NUDOCS 8609180396 | |
| Download: ML20210C679 (2) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION g
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WASHINGTON, D. C. 20555
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SAFETY EVALUATION BY THE 0FFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT N0.46TO FACILITY OPERATING LICENSE DPR-77
-AND AMENDMENT N0.38T0 FACILITY OPERATING LICENSE DPR-79 TENNESSEE VALLEY AUTHORITY INTRODUCTION The Tennessee Valley Authority (TVA) in a submittal dated January 25, 1984 requested a license amendment which would include the reactor vessel level instrumentation system (RVLIS) in the Accident Monitoring Instrumentation Technical Specifications.
EVALUATION The staff has reviewed this request by comparing it to the requirements
' provided in Generic Letter 83-37. Based on the result of its review, the staff has concluded the following:
1.
The surveillance requirements for channel check and channel calibration as specified in Item 17 of Table 4.3-7, " Accident Monitoring Instrumen-tation Surveillance Requirements," meet the requirements of Generic Letter 83-37 and are acceptable.
2.
The required number of channels and minimum number of channels as
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specified in Item 17 of Table 3.3-10," Accident Monitoring Instrumen-i l
tation," are in accordance with the recomendation of Generic Letter 83-37 and also are acceptable.
In summary, the staff has found the proposed technical specification change to add RVLIS to Accident Monitoring Instrumentation acceptable. This proposed technical specification change should be implemented following the startup from the Cycle 3 refueling outage for each unit.
After upgrading of the SuLeooling Margin Monitors (SMM) is completed, the technical specification change for Sm on Item 11 of Tables 3.3-10 and 4.3-7 and its action statements should also be changed in accordance with the Generic Letter No. 83-37 requirements.
ENVIRONMENTAL CONSIDERATION These amendments involve changes in the use of facility components located within the restricted area as defined in 10 CFR Part 20. The staff has detennined 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 Comission has previously
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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 assessment need be prepared in connection with the issuance of the amendments.
IV. CONCLUSION The Commission made a proposed determination that the amendments involve no significant hazards consideration which was published in the Federal Register on September 28,1984 (49 FR 38410).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.
Principal Contributors: Carl R. Stahle, PWR#4, DPWR-A Joe Holonich, PWR#4, DPWR-A R. Karsch, RSB Dated: September 16, 1986 a
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