ML20210T398
| ML20210T398 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 10/01/1986 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20210T396 | List: |
| References | |
| NUDOCS 8610080489 | |
| Download: ML20210T398 (3) | |
Text
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l UNITED STATES 8
NUCLEAR REGULATORY COMMISSION o
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wasHWGTON, D. C. 70665
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SAFETYEVALUATIONBYTHEOFFICEOFNUCLEARREACTORREGU[ATION SUPPORTING AMENDMENT NO.100 TO FACILITY OPERATING LICENSE NO. DPR-71 AND AMENDMENT NO.129 TO FACILITY OPERATING LICENSE NO. DPR-62 CAROLINA POWER & LIGHT COMPANY I
BRUNSWICK STEAM ELECTRIC PLANT, UNITS 1 AND 2 DOCKET NOS. 50-325 AND 50-324
1.0 INTRODUCTION
By letter dated May 6,1985, as supplemented February 19, 1986, the Carolina Power and Light Company (the licensee) submitted proposed changes to the Technical Specifications (TS) appended to Facility Operating License Nos. DPR-71 and DPR-62 for the Brunswick Steam Electric Plant, Units 1 and 2.
The licensee proposed to modify the surveillance requirement in TS Table 4.3.1-1 for the Turbine Stop Valve-Closure and Turbine Control Valve Fast Closure, Control Oil Pressure-Low functions of the Reactor Protection System.
2.0 EVALUATION Currently, TS Table 4.3.1-1 (Items 9 and 10) requires the Turbine Stop valve-Closurc and Turbine Control Valve Fast Closure, Control 011 Pressure-Low functions to be tested monthly whenever the reactor is in Operational Condition 1.
Further, to meet the requirements of TS Section 4.0.4, these functions must also be tested prior to entering Operational Condition 1.
The proposed change to the TS would add a footnote to Items 9 and 10 of Table 4.3.1-1 to indicate that surveillance is not required when thermal power is below 30% of rated power. With the proposed change, the turbine stop and control valve surveillance would be performed every month while operating above 30%
power and, per TS Section 4.0.4, prior to exceeding 30% power.
As justification for the proposed change, the licensee noted that the proposed change would be consistent with existing TS Table 3.3.1-1 which permits the fast closure scram functions of the turbine stop and control valves to be bypassed while below 30% power. These functions may be bypassed because the capacity of the turbine bypass valves is sufficient, at these lower power levels, to maintain proper system pressure. The turbine stop valve closure scram, which initiates a scram earlier than either the neutron monitoring system or reactor coolant system high pressure, is required at higher power levels to provide a satisfactory margin below core thermal-hydraulic limits.
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The licensee has further indicated that the current TS requirements of TS Table 4.3.1-1 in conjunction with TS Section 4.0.4, result in unnecessary complications to the surveillance procedure. These TS sections require surveillance testing before entering Operational Condition 1, i.e., while in Operational Condition 2, 3 or 4.
- However, performance of these tests causes large power swings and significant thermal cycling of plant systems. Since the Intermediate Range Monitors (IRM) are not bypassed in Operational Condition 2, a high IRM scram is likely to occur due to a pressure transient if the tests are performed in Operational Condition 2.
In Operational Condition 3 or 4, the system configuration to perform the surveillance is complex and/or requires the.use of jumpers. Therefore, it is advantageous to perform the required surveillance in Operational Condition 1 when the IRMs are bypassed but prior to reaching 30% power.
We have reviewed the licensee's submittal and have determined that the surveillance need not be performed on the Turbine Stop Valve-Closure and. Turbine Control Valve Fast Closure, Control Oil Pressure-Low functions while operating below 30% power.
Since these functions are bypassed below 30% power, the proposed change to the TS is consistent with TS Section 4.0.3 which indicates that surveillance need not be performed on inoperable equipment.
In addition, the surveillance requirements reflected by the proposed change have been accepted in the past by the NRC staff for other boiling water reactor facilities.
Based on our review, we, therefore, conclude that the proposed change to TS Table 4.3.1-1 is acceptable.
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 and change 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 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 951.22(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:
(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 i
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inimical to the comon defense and security or to the health and safety p
of the public.
Principal Contributor:
K.W. Van Dyne Dated: October 1, 1986 m
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