ML20151R680
| ML20151R680 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 01/29/1986 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20151R663 | List: |
| References | |
| NUDOCS 8602060180 | |
| Download: ML20151R680 (3) | |
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UNITED STATES 8
NUCLEAR REGULATORY COMMISSION o
I vvAsHWGTON, D. C. 20655 k.....)
JAN 2 91986 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 43TO FACILITY OPERATING LICENSE DPR-77 i
AND AMENDMENT NO.35 TO FACILITY OPERATING LICENSE DPR-79 i
TENNESSEE VALLEY AUTHORITY i
i INTRODUCTION By letter dated May 6, 1985, the Tennessee Valley Authority (the licensee) re-quested an amendment to the operating license to change the Technical Specifications of Sequoyah Nuclear Plant, Units 1 and 2.
Specifically, the change for each unit requires the acoustic monitors to be one of the two re-quired channels of pressurizer power operated relief valve (PORV) and safety valve (SV) position indicators in accident monitoring tables and bases.
EVALUATION i
i The licensee proposes to add a footnote to Table 3.3-10 stating that one channel l
of the required number of channels for the PORV and SV position indicators shall be the acoustic monitors. The licensee has further proposed to add to the Bases of Section 3/4.3.3.7 a discussion of the separate methods of determining PORV and SV position.
i These separate methods include the acoustic flow monitors mounted on each safety
'l valve line (one per valve). Failure of a valve to reclose would be detected by a flow indicating module in the main control room. When any valve is not fully closed an alarm in the main control room will actuate. The second method con-l sists of temperature sensors downstream of each safety valve (one per valve) with temperature indication and alarm provided in the main control room. The third
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method of detecting PORY and SV position is provided through main control room alams for pressure relief tank temperature, pressure and level. The last method is through pressurizer pressure indication and alam in the main control Foom.
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These changes are proposed to address the staff concern identified in Inspection l
Report 50-327/83-26 and 50-328/83-26 for Sequoyah, Units 1 and 2, regarding the acoustic monitors as PORV and SV position indicators. The proposed changes ensure that the acoustic flow monitors will be one of the two required position indication channels for the PORVs and SVs. The proposed change results in a more restrictive limiting condition for operation in that the acoustic flow monitors are required to be one of the means of position indication. The staff also concludes that proposed changes resolve the enncerns in the inspection re-ports and finds the revisions acceptable for incorporation into the Sequoyah, Units 1 and 2, Technical Specifications.
8602060180 860129 DR ADOCK 0500 7
ENVIRONMENTAL CONSIDERATION These amendments involve a change in the use of a facility component located l
within the restricted area as defined in 10 CFR Part 20. The staff has deter-mined that the amendments involve no significant increase in the amounts, and no significant change in the types, of any effluents that may be released off-i site and that there is no significant increase in individual or cumulative occupational radiation exposure. The Comission has previously issued a pro-posed finding that these amendments involve no significant hazards consideration, and there has been no public coment on such finding. Accord-1 ingly, the amendments meet the eligibility criteria for categorical exclusion l
set forth in 10 CFR 51.22(c)(9). Pursuant to 10 CFR 50.22(b), no environmental impact statement or environmental assessment need be prepared 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 July 31, 1985 (50 FR 31072) and consulted with the state of Tennessee. No public comments were received, and the state of Tennessee did not have any coments.
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 i
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:
F. Burrows, Electrical. Instrumentation and Control Systems Branch, PWR-A M. Miller, PWR#4, PWR-A C. Stahle, PWRf4, PWR.-A Dated: January 29, 1986 l
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.,, ~ - 3 January 29, 1986
. 3 AMENDMENT N0.43 TO FACILITY 0PERATING LICENSE N0.
DPR Sequoyah Nuclear Plant AMENDMENT N0.35 TO FACILITY OPERATING LICENSE NO.
DPR Sequoyah Nuclear Plant
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