ML17292A008
| ML17292A008 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 09/18/1995 |
| From: | Hebdon F Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17292A009 | List: |
| References | |
| NPF-12-A-129 NUDOCS 9509210334 | |
| Download: ML17292A008 (12) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555 SOUTH CAROLINA EL CTRIC 5 GAS COM ANY SOUTH CAROLINA PUBLIC SERVICE AUTHORITY DOCKET NO. 50-395 VIRGIL C.
SUMMER NUCLEAR STATION UNIT NO.
1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 129 License No. NPF-12 2.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by South Carolina Electric It. Gas Company (the licensee),
dated June 30,
- 1995, as supplemented on August 11,
- 1995, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without'endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
Accordingly, the license is amended by changes to the Technical Specifications, as indicated in the attachment to this license amendment; and paragraph 2.C.(2) of Facility Operating License No. NPF-12 is hereby amended to read as follows:
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(2) Technical S ecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 129 and the Environmental Protection Plan contained in Appendix 8, are hereby incorporated in the license.
South Carolina Electric 5 Gas Company shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This amendment is effective as of its date of issuance and shall be implemented within 30 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Frederick J.
Hebd n, Director Project Directorate II-3 Division of Reactor Projects I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
September 18, 1995
ATTACHMENT TO LICENSE AMENDMENT NO. 129 TO FACILITY OPERATING LICENSE NO.
NPF-12 DOCKET NO. 50-395 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages.
The revisions are indicated by marginal lines.
Remove Pa es 3/4 4-10 B3/4,4-2 Insert Pa es 3/4 4-10 3/4 4-10a 3/4 4-10b 83/4 4-2 B3/4 4-2a
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REACTOR COOLANT SYSTEM 3/4.4.4 RELIEF VALVES LIMITINGCONDITION FOR OPERATION 3.4,4 Allpower operated reliefvalves (PORVs) and their associated block valves shall be OPERABLE.
APPLICABILITY:MODES 1, 2, and 3, ACTION:
a.
With one or more PORV(s) inoperable and capable ofbeing manually cycled, within 1 hour:
1) restore the PORV(s) to OPERABLE status or 2) close the associated block valve(s) and maintain power to the block valve; otherwise, be in at least HOT STANDBYwithinthe next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOWNwithinthe following6 hours.
b.
With one PORV inoperable and not capable ofbeing manually cycled; within 1 hour:
1) restore the PORV to OPERABLE status or to a condition where itmay be manually cycled* or 2) close its associated block valve and remove power from the block valve; otherwise, be in at least HOT STANDBYwithinthe next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOWNwithin the following6 hours.
c, Withtwo PORVs inoperable and not capable ofbeing manually cycled, 1) within 1 hour:
a) restore the PORVs to OPERABLE status or to a condition where they are capable ofbeing manually cycled* or b) close the associated block valves and remove power from the block valves and 2) withinthe next 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />s:
a) restore a minimum oftwo PORVs to OPERABLE status or b) restore a minimum oftwo PORVs to a condition where they are capable ofbeing manually cycled*;
otherwise, be in at least HOT STANDBYwithinthe next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOWNwithinthe following6 hours.
Ifa PORV is inoperable but capable ofbeing manually cycled, the associated block valve must be closed with power maintained to the block valve.
SUMMER - UNIT1 3/4 4-10 Amendment No.
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REACTOR COOLANT SYSTEM LIMITINGCONDITION FOR OPERATION ACTION:
Continued d.
Withthree PORVs inoperable and not capable ofbeing manually cycled, 1) within 1 hour:
a) restore at least one PORV to OPERABLE status or to a condition where itis capable ofbeing manually cycled*, and b) close and remove power from the block valves for any PORVs
'remaining inoperable and not capable ofbeing manually cycled and 2) withinthe next 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />s:
a) restore a minimum oftwo PORVs to OPERABLE status or b) restore a minimum oftwo PORVs to a condition where they can be manually cycled*;
otherwise, be in at least HOT STANDBYwithinthe next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOWNwithin the following6 hours.
e.
With one block valve inoperable:
1) within 1 hour:
a) restore the block valve to OPERABLE status, or b) place the associated PORV in manual control and 2) withinthe next 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />s:
a) restore the block valve to OPERABLE status or b) close the block valve and remove power from the block valve; otherwise, be in at least HOT STANDBYwithinthe next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOWNwithinthe following6 hours.
Withtwo block valves inoperable:
1) within 1 hour:
a) restore the block valves to OPERABLE status, or b) place the associated PORVs in manual control and 2) within72 hours:
a) restore at least two ofthe three block valves to OPERABLE status and b) ensure that the remaining inoperable block valve is closed and the power is removed; otherwise, be in at least HOT STANDBYwithinthe next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOWNwithin the following6 hours.
Ifa PORV is inoperable but capable ofbeing manually cycled, the associated block valve must be closed with power maintained to the block valve.
SUMMER - UNIT1 3/44-10a Amendment No.129
REACTOR COOLANT SYSTEM LIMITINGCONDITION FOR OPERATION ACTION:
Continued g
Withthree block valves inoperable:
1) within 1 hour:
a) restore the block valves to OPERABLE status, or b) place the associated PORVs in manual control and 2) withinthe next 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> restore at least one ofthe three block valves to OPERABLE status and 3) withinthe next 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />s:
a) restore at least two ofthe three block valves to OPERABLE status and b) ensure that the remaining inoperable block valve is closed and the power is removed; otherwise, be in at least HOT STANDBYwithinthe next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOWNwithinthe following6 hours.
h.
The provisions ofSpecification 3.0.4 are not applicable.
SURVEILLANCE RE UIREMENTS 4.4.4.1 Iriaddition to the requirements ofSpecification 4.0.5, each PORV shall be demonstrated OPERABLE at least once per 18 months by.operating the valve through one complete cycle offulltravel during MODES 3 or 4, 4.4.4.2 Each block valve shall be demonstrated OPERABLE at least o'ce per 92 days by operating the valve through one complete cycle offulltravel unless the block valve is closed with the power removed in order to meet the requirements of3.4.4.b, 3.4,4.c, or 3.4.4,d.
SUMMER - UNIT1 3/4 4-10b Amendment No.
129
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REACTOR COOLANTSYSTEM BASES 3/4.4.2 SAFETY VALVES The pressurizer code safety valves operate to prevent the RCS from being pressurized above its Safety Limitof2735 psig. Each safety valve is designed to relieve 420,000 lbs per hour ofsaturated steam at the valve set point p us 3% accumulation, The reliefcapacity ofa single safety valve is adequate to relieve any overpressure condition which could occur during shutdown. In the event that no safety valves are OPERABLE, an operatinq RHR loop, connected to the RCS, provides overpressure reliefcapability and willprevent RCS over-pressurization. In addition, the Overpressure Protection System provides a diverse means ofprotection against RCS overpressurization at low temperatures.
During operation, all pressurizer code safety valves must be OPERABLE to prevent the RCS from being pressurized above its safety limitof2735 psig, The combined reliefcapacity ofall ofthese valves is greater than the maximum surge rate resulting from a complete loss ofload assuming no reactor trip until the firstReactor Protective System trip set point is reached (i.e., no credit is taken for a direct reactor trip on the loss ofload) and also assuming no operation ofthe power operating reliefvalves or steam dump valves, Demonstration ofthe safety valves'ift settings willbe performed in accordance with the provisions ofSection XIofthe ASME Boiler and Pressure Code.
3/4.4.3 PRESSURIZER The limiton the maximum water volume in the pressurizer assures that the parameter is maintained withinthe normal steady state envelope ofoperation assumed in the SAR. The limitis consistent with the initialSAR assumptions.
The 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> periodic surveillance is sufficient to ensure that the parameter is restored to withinits limitfollowingexpected transient operation. The maximum water volume also ensures that a steam bubble is formed and thus the RCS is not a hydraulically solid system. The requirement that a minimum number ofpressurizer heaters be OPERABLE enhances the capability ofthe plant to control Reactor Coolant System pressure and establish natural circulation, 3/4.4.4 RELIEF VALVES PORVs
'he pressurizer power operated reliefvalves (PORVs) and steam bubble function to relieve RCS pressure during all design transients up to and including the design step load decrease with steam dump. The PORVs and block valves may be used to depressurize the RCS when normal pressurizer spray is unavailable.
Operation ofthe air operated PORVs minimizes the undesirable opening ofthe spring loaded pressurizer code safety valves. Each PORV has a remotely controlled motor-operated block valve to provide a positive shutoff capability should a reliefvalve become inoperable. The series arrangement of the PORV and its associated block valve permit surveillance while at power.
SUMMER - UNIT1 B 3/4 4-2 Amendment No. 94, 1~9
REACTOR COOLANTSYSTEM BASES RELIEF VALVES PORVs (Continued)
The PORVs, their block valves, and their controls are powered from buses that normally receive oQsite power but are also capable ofbeing powered from emergency power sources. Two PORVs and their associated block valves are powered from two separate safety trains. Bymaintaining two PORVs and their associated block valves OPERABLE, redundant capability to perform their design function is maintained.
Plant operators employ the PORVs to depressurize the RCS in response to certain plant transients ifnormal pressurizer spray is not available. For the Steam Generator Tube Rupture (SGTR) event, the safety analysis assumes that manual operator actions are required to mitigate the event. Aloss ofoffsite power is assumed to accompany the event, and thus, normal pressurizer spray is unavailable to reduce RCS pressure.
The PORVs are assumed to be used for RCS depressurization, which is one ofthe steps performed to equalize the primary and secondary pressures in order to terminate the primary to secondary break Qow and the radioactive releases from the affected steam generator.
Credit is taken for the PORVs in safety analyses ofevents that result in increasing RCS pressure where departure from nucleate boilingratio (DNBR) criteria are critical. By assuming PORV manual actuation, the primary pressure remains below the high pressurizer pressure trip setpoint, thus tke DNBR calculation is more conservative.
Events that assume this condition include a turbine trip and the loss ofnormal feedwater.
One PORV that is capable ofmanual operation has sufficient capacity to perform its function to depressurize the RCS and mitigate the effects ofa postulated event. Two PORVs that are OPERABLE or capable ofmanual operation provide adequate redundancy.
Operating the PORV and block valve through one complete cycle verifies
'hat the valve and its associated supporting systems are capable ofmanual operation.
SUMMER - UNIT1 B 3/4 4-2a Amendment No, 129