ML20239A646
| ML20239A646 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 09/08/1987 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Duquesne Light Co, Ohio Edison Co, Pennsylvania Power & Light Co |
| Shared Package | |
| ML20239A647 | List: |
| References | |
| DPR-66-A-115 NUDOCS 8709180049 | |
| Download: ML20239A646 (8) | |
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UNITED STATES C ~'
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- NUCLEAR REGULATORY COMMISSION-iJ WASHINGTON, D. C. 20555 -
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DUOVESNE LIGHT COMPANY OHIO EDISON COMPANY PENNSYLVANIA POWER COMPANY' DOCKET NO. 50-334 BEAVER VALLEY POWER STATION,' UNIT NO.__1_
AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.115 License No. DPR-66 1.
The Nuclear Regulatory Comission (the Commission) has found that:
l A.
The application for amendrnent by Duquesne Light Company, et al.
(the licensee) dated October 29, 1986 and supplemented by letter
. dated June 2,1987 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, f
the provisions of the Act, and the rules and regulations of the Comission; 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 Comission's regulations; D.
The issuance of this amendment will not be inimical to the comon l
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 Comission's regulations and all applicable requirements have been satisfied.
I 2.
Accordingly, the license is amended by changes to the Technical i
Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-66 is hereby amended to read as follows:
l 8709180049 e7090s PDR ADOCK 05000334 l
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(?) Technical Specifications The Technical Speci#ications contained in Appendix A, as revised through Amendment No.115, are hereby l
incorporated in the license. The licensee shall i
operate the facility in accordance with the Technical Specifications.
3.
This amendment is effective on issuance, to be implemented no later l
than 30 days after issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
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/ Jo t 1z, Director
[ Division of Reactor Projects I/II Pr ject Directorate (4
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Attachment:
Changes to the Technical 3
Specifications l
Date of Issuance: September 8,1987 l
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l ATTACHMENT TO LICENSE AMENDMENT NO.115 FACILITY OPERATING LICENSE NO. DPR-66 l
DOCKET NO. 50-334 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages.
The revised pages are identified by amendment number and contain~ vertical lines indicating the area of change.
Remove Insert
i 3/4 4-5 3/4 4-5 3/4 4-6 3/4 4-6 3/4 7-1 3/4 7-1 3/4 7-4 3/4 7-4 B 3/4 4-2 P 3/4 4-2 1
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REACTOR COOLANT SYSTEM SAFETY VALVES - SHUTDOWN LIMITING CONDITION FOR OPERATION l
3.4.2 A
minimum of one pressurizer code safety valve shall be I
OPERABLE with a lift setting
- of 2485 PSIG +1% -3%.**
APPLICABILITY:
MODES 4 AND 5.
ACTION:
a.
With no pressurizer code safety valve OPERABLE, immediately suspend all operations involving positive reactivity changes and place an OPERABLE RHR loop into operation in the shutdown cooling mode.
b.
With a
pressurizer code safety valve having discharged liquid water from a water solid pressurizer to mitigate an overpressure
- event, borate to a SHUTDOWN MARGIN equivalent to at least 1%
aK/K at 200*F within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
Inspect that valve for potential damage, initiate corrective action to return the valve to operable status prior to increasing RCS temperature and document the inspection results in the Annual Report pursuant to Specification 6.9.1.5.b.
i SURVEILLANCE REQUIREMENTS I
4.4.2 No additional requirements other than those required by Specification 4.0.5.
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The Lif*. Setting pressure shall correspond to ambient conditions of the valve et nominal operating temperature and pressure.
- Within 11% following pressurizer code safety valve testing.
l BEAVER VALLEY - UNIT 1 3/4 4-5 Amendment No.115 l
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REACTOR COOLANT SYSTEM SAFETY VALVES - OPERATING LIMITING CONDITION FOR OPERATION l
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.3.4.3 All pressurizer code safety valves shall be OPERABLE with a lift setting
- of 2485 PSIG +1%
-3%.**
-l APPLICABILITY:
MODES 1, 2 and 3.
ACTION:
1 a.
With one pressurizer code safety valve inoperable, either restore the inoperable valve to OPERABLE status within 15 minutes or be in HOT SHUTDOWN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
I b.
With a
pressurizer code safety valve having discharged liquid water from a water solid pressurizer to mitigate an overpressure
- event, be in at least HOT STANDBY within the next 6
- hours, and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
SURVEILLANCE REQUIREMENTS 4.4.3 No additional requirements other than those required by Specification 4.0.5.
The Lift Setting pressure shall correspond to ambient conditions of the valve at nominal operating temperature and pressure.
- Within i 1% following pressurizer code safety valve testing.
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i BEAVER VALLEY - UNIT 1 3/4 4-6 Amendment No.14,115
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- 3/4.7 PLANT SYSTEMS e
3/4.7.1 TURBINE CYCLE I
IL 5AFETY VALVES LIMITING CONDITION FOR OPERATION i
l 3.7.1.1 A11' main steam line code safety valves associated with each-steam generator of an unisolated reactor coolant loop shall be OPERABLE with Lift Settings within +1% -3% of the value specified in l
Table 3.7-3.**
APPLICABILITY:
MODES 1, 2 and 3.
t ACTION:
a.
With 3
reactor coolant loops and associated steam generators in operation and with one or more main steam line code safety valves inoperable, operation in MODES 1,'
2 and 3 may proceed provided, that within 4
hours, either the inoperable. valve is restored to OPERABLE status or~ the Power Range Neutron Flux High Setpoint i
trip is reduced per Table 3.7-1; otherwise, be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in' COLD SHUTDOWN within the I
following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />, b.
With 2
reactor coolant loops and associated steam generators in operation and with-one or.more main steamline code safety valves
. associated with an operating loop inoperable, operation,in MODES
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1, 2
and.3 may proceed provided, that within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, either the inoperable valve. is restored to OPERABLE status or the Power
.l Range Neutron Flux High Setpoint trip is reduced per Table 3.7-2; otherwise, be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
c.
The provisions of Specification 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.7.1 No additional surveillance requirements other than those l
required by Specification 4.0.5.
Within + 1% of the value specified in Table 3.7-3 following main steamline code safety valve testing.
BEAVER VALLEY - UNIT 1 3/4 7-1 Miendment No.115 i
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TABLE 3.7-3 l
l STEAM LINE SAFETY VALVES PER LOOP LIFT ORIFICE l
VALVE NUMBER SETTING ***
DIAMETER l
a.
SV-MS101A, B&C 1075 psig 4.250 in, b.
SV-MS102A, B & C 1085 psig 4.515 in.
c.
SV-M5103A, B&C 1095 psig 4.515 in.
d.
SV-MS104A, B&C 1110 psig 4.515 in.
c.
SV-M5105A, B&C 1125 psig 4.515 in, l
The Lift Setting pressure shall correspond to ambient conditions of the valve at nominal operating temperature and pressure.
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Amendment No.115 BEAVER VALLEY - UNIT 1 3/4 7-4
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REACTOR COOLANT SYSTEM BASES relieve any overpressure condition which could occur during l
shutdown.
In the event that no safety valves are OPERABLE, an I
operating RRR
- loop, connected to the
I During operation, all pressurizer code safety valves must be OPERABLE to prevent the RCS from being pressurized above its safety limit of 2735 psig.
The combined relief capacity of all of these j
valves is greater than the maximum surge rate resulting from a complete loss of load assuing no reactor trip until the first Reactor 4
Protective System trip set point is reached (i.e., no credit is taken for a
direct reactor trip on the loss of load) and also assuming no operation of the power operated relief valves or steam dump valves.
Demonstration of the safety valves lift settings will occur only during shutdown and will be performed in accordance with the provisions of Section XI of the ASME Boiler and Pressure Code.
3/4.4.4 PRESSURIZER The requiremen.t that (150)kw of pressurizer heaters and their cssociated controls be capable of being supplied electrical power from an emergency bus provides assurance that these heaters can be energized during a
loss of offsite power condition to maintain natural circulation at HOT STANDBY.
I 3/4.4.5 STEAM GENERATORS i
One OPERABLE steam generator in a non-isolated reactor coolant loop provides sufficient heat removal capability to remove decay heat after a
reactor shutdown.
The requirement for two O&ERABLE steam generators, combined with other requirements of the Limiting conditions for Operation ensures adequate decay heat removal capabilities for RCS temperatures greater than 350*F if one steam generator becomes inoperable due to single failure considerations.
Below 350*F, decay heat is removed by the RHR system.
1 BEAVER VALLEY - UNIT 1 B 3/4 4-2 Amendment No.,)df,115 i
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