ML20212J369
| ML20212J369 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 01/21/1987 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20212J366 | List: |
| References | |
| NUDOCS 8701280170 | |
| Download: ML20212J369 (2) | |
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UNITED STATES 8
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NUCLEAR REGULATORY COMMISSION f,
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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION SUPPORTING AMENDMENT NO.103 TO FACILITY OPERATING LICENSE N0. DPR-71 AND AMENDMENT N0.133 TO FACILITY OPERATING LICENSE N0. DPR-62 4
CAROLINA POWER & LIGHT COMPANY BRUNSWICK STEAM ELECTRIC PLANT, UNITS 1 AND 2 DOCKETS NOS. 50-325 AND 50-324
1.0 INTRODUCTION
The Reactor Coolant Pressure Boundary (RCPB) leakage detection system for each unit includes a safety-related portion for monitoring the containment sump flow rate using safety related instrumentation to record the integrated flow rate over time, and a nonsafety-related portion to provide an instantaneous flow rate indication in the control room. The licensee requested in their submittal date'd March 17, 1986, deletion of two square-root converters associated with the nonsafety-related portion of the RCPB leakage detection system from the Technical Specifications. Additional information was provided in a subsequent submittal dated October 13, 1986. This evaluation deals with the acceptability of the proposed deletions from the plant Technical Specifications.
2.0 EVALUATION 7
The licensee proposed, in a March 17, 1986 submittal, some revisions to the Brunswick Unit I and 2 Technical Specifications.
In the submittal, the licensee proposed to delete the two'nonsafety-related square-root converters identified by Tag Numbers G16-FY-K600 and G16-FY-K602. These square-root converters provide inputs to a ficw recorder in the control room for each unit. The inputs indicate the instantaneous flow rate from the primary containment sump and the drywell and equipment drain sump.
Since this recorder indicates flow out of the sumps, there is an indication only when the pumps are running. The recorder is nonsafety-related and does not provide the RCPB leakage detection system monitoring information required by the plant Technical Specifications that are used to implement the guidelines of Regulatory Guide 1.45, " Reactor Coolant Pressure Boundary Leakage Detection Systems". The flow recorder is not identified in the Technical Specifications.
As stated in the October 13, 1986 submittal, the operator relies on the digital counter, which indicates the total integrated flow, to determine the average flow rate and thereby assess the leakage from the RCPB. The digital counters do not get a signal from or rely on 8701280170 870121
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o the square-root converters. Since the square-root converters are not associated with the safety-related portion of the RCPB leakage detection system and are associated with a nonsafety-related recorder, the licensee has requested deletion of these square-root converters 3
from Technical Specifications 4.4.3.1.b and 4.4.3.2.a.
These two specifications deal with the primary containment sump flow integrating system and the drywell and equipment sump flow system, respectively.
3.0 ENVIRONMENTAL CONSIDERATION
S The amendments change a requirement with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20. 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 should be no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously published a proposed finding that the 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 651.22(c)(9).
Pursuant to 10 CFR 551.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendments.
4.0 CONCLUSION
We have concluded, based on the considerations discussed above, that:
L (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 Com-mission's regulations, and the issuance of the amendments will not be inimical to the common defense and security or to the health and safety of the public.
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Principal Contributor:
J. Ridgely 1
i Dated:
January 21, 1987 i
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