ML20070K216
| ML20070K216 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 03/11/1991 |
| From: | Butler W Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20070K219 | List: |
| References | |
| NUDOCS 9103180349 | |
| Download: ML20070K216 (12) | |
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UNITED STATES y.3e g
NUCLEAR REGULATORY COMMISSION E
W ASHING T ON. D. C. 20555 e
l PUBLIC. SERVICE ELECTR-IC 1, GAS--COMPANY.
I PHILADELPHIA-ELECTRIC-COMPANY l
DELMARVA-POWER AND-LIGHT..CONPANY ATL AN_ TIC CITY-ELECTRIC-COMPANY
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DOCKET -NO,.50-2 2 SALEM-GENERATING-STATION,. UNIT.NO,-1 AMENDNENT-TO.FACillTY 0PERATING-LICENSE l
i Amendment No. 120 License No. DPR-70 i
1.
The Nuclear Regulatory Comission (the Comission or the NRC) has found that:
A.
The application for amendment filed by the Public Service Electric &
Gas Company, Philadelphia Electric Company, Delmarva Power and Light Company and Atlantic City Electric Company (the licensees) dated December 21, 1990 complies with the stan1ards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's l
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 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-(11) that such activities will be conducted in compliance with the Comission's regulations set forth in 10 CFR Chapter I; 1
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 j
the Comission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by charges to the Technical Specifica-tions as indicated in the attachment to this license amendment, and I
paragraph 2.C.(2) of Facility Operating License No. DPR-70 is hereby j
amended to read as follows:
l 9103180349 910311 PDR ADOCK 05000272 P
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(2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendices A and B, as revised through Amendment No.120, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specificatit.ns.
3.
This license amendment is effective as of its date of issuance and shall be implemented within 60 days.
FOR THE IlVCLEAR REGULATORY COMMISSION
/S/
Walter R. Butler, Director Project Directorate I-2 Division of Reactor Projects - I/II
Attachment:
Changes to the Technical Specifications Date of Issuance: tiarch 11, 1991
- See previous concurrence
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(2) Technical Specifications and Environmental Protection Plan i
The Technical Specifications contained in Appendices A ant 2, as revised through Amendment flo.120, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
l 3.
This license amendment is effective as of its date of issuance and shall be implemented within 60 days.
1 FOR THE NUCLEAR REGULATORY COMMISSION fl gif O
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Walter R. Butler, Director Project Directorate I-2 Division of Reactor Projects - 1/11
Attachment:
Changes to the Technical Specifications Date of Iss. 'o: March 11, 1991 l
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.1:A' ATTACHMENT TO LICENSE AMENDMENT NO.120 FACILITY OPERATING LICENSE NO. DPR-70 DOCKET NO. 50-272 Revise Appendix A as follows:
Remove Pages Insert Pages 3/4 3-70 3/4 3-70 B 3/4 3-4 8 3/4 3-4
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INSTRUMENTATION i
3/4.3.4 TURBINE OVERSPEED PROTECTION j
LIMITING CONDITION FOR OPERATION 3.3.4 At least one turbine overspeed protection system shall be OPERABLE.
APPLICABILITY:
MODES 1, 2 and 3.
ACTION:
With one stop valve or one control valve per high pressure a.
turbine steam lead inoperable and/or with one reheat stop valve or one reheat intercept valve per low pressure turbine steam lead inoperable, restore the inoperable valve (s) to the OPERABLE status.
within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or close at least one valve in the affected steam lead; otherwise, isolate the turbine from the steam supply within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, b.
With the above required turbine overspeed. protection system otherwise inoperable, within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> either restore the system to OPERABLE status or isolate the turbine from the steam supply.
SURVEILLANCE REQUIREMENTS 4.3.4.1 The provisions _of Specification 4.0.4 are not applicable.
E 4.3.4.2 The above required turbine overspeed protection system shall be demonstrated OPERABLE; (1) prior to admitting steam to the turbine during each startup unless performed within the past 7 days (2) following startup, within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of attaining manufacturer's recommended power level for performing turbine valve testing, and (3) at a frequency not to exceed one year
- by direct observation of the movement of each of the followin6 valves through at least one complete cycle from the running position, Four high pressure turbine stop valves, a.
b.
Four high pressure turbine control valves.
Six low pressure hot reheat stop valves, c.
d.
Six low pressure hot reheat intercept valves.
The above valves are to be tested at a frequency consistent with the methodology presented in WCAP 11525, "Probabilistic Evaluation of Reduction in Turbine Valve Test Frequency", and in accordance with the establishedNRCacceptancecriseriafrtheprobabilityofamissile ejection incident of 1.0 x 10 per year, in no case shall the test interval for the above valves exceed one year.
SALEM UNIT 1 3/4 3 70 Amendment No.120,
l 1
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INSTRtMENTATION BASES 3/4.3.4 TURBINE OVERSPEED PROTECTION This specification is provided to ensure that the turbine overspeed protection instrumentation and the turbine speed control valves are OPERABl.E and will protect the turbine from excessive overspeed.
Protection from turbine excessive overspeed is ref. aired since excessive overspeed of the turbine coul':
generate potentially damaging missiles which could impact and damage safety related components, equipment or structures.
Salem Unit 1 turbine is operated at full time, partial arc admission.
To prevent double shocking the turbine, perform turbine valve testing in accordance with manufacturer's recommendations.
During normal operation, turbine valve testing is performed at a frequency consistent with the methodology presented in WCAP 11525, "Probabilistic Evaluation of Reduction in Turbine Valve Frequency " This report evaluates the contribution of failure or unavailability of the turbine valve safety function to the probability that the turbine will overspeed and eject a missile.
It concludes that extended intervals between turbine valve functional tests can be achieved without exceeding the NRC acceptance criteria for the probability of a turbine missile ejection incident.
Factors which affeet the selected valve test interval include low pressure turbine rotor type and inspection interval; turbine valve type, arrangement and overspeed controls; and secondary side water chemistry.
SALEM - UNIT 1 B 3/4 3 4 Amendment No. 120,
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.i NUCLEAR REGULATORY COMMISSION o
WASHINoTON, o.C 20666 s.,., f PUBLIC SERVICE ELECTRIC & GAS COMPANY PHILADELPHIA ELECTRIC COMPANY DEUiARVA POWER AND LIGHT COMPANY q
ATLANTIC CITY ELECTRIC COMPANY 00CKET H0. E0-311 SALEM GENERATING STATION, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.100 License No. DPR-75 1.
The Nuclear Regulatory Comission (the Comission or the NRO) has found that:
A.
The application for amendment filed by the Public Service Electric &
Gas Company, Philadelphia Electric Company, Delmarva Power and Light Company and Atlantic City Electric Company (the licensees) dated December 21, 1990 complies with the str.Jards and requirements of the Atomic Energy Act of-1954, as. amended (the-Act), and the Comission'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 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, ard (ii) that such activities will be conducted in compliance with the Commission's regulations set forth in 10 CFR Chapter I; 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.
2.
Accordingly, the license is amended by changes to the Technical Specifica-tions as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-75 is hereby amended to read as follows:
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2-(2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendices A and B,'as revised through Amendment No.100, are hereby-incorporated in the license The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of its date of issuance and shall be implemented within 60 days.
FOR THE NUCLEAR REGULATORY COPMISSION
/S/
Walter R. Butler, Director Project Directorate 1-2 Division of Reactor Projects - I/II Attachraent:
Changes to the Technical Specifications Date of Issuance: March 11, 1991
- See previous conpurrence (h)
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I
.- (2) Technical Specif! cations and Environmental Protection Plan The Technical Specifications contained in Appendices A and 3, as revised through Amesdment No.100, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of its date of issuance and shall be implemented within 60 days.
FOR THE HUCLEAR REGULATORY COMMISSION
- j. 5l Walter R. Butler, Director Project Directorate I-2 Division of Reactor Projects - I/Il
Attachment:
Changes to the Technical l
Specifications i
Date of Issuance: March 11, 1991 l
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ATTACHMENT TO LICENSE AMENDMENT NO.100 FACillTY OPERATING LICENSE NO. OPR-75 DOCKET NO. 50-311 Revi e Appendix A as follows:
s Remove Pages Insert P_tgee 3/4 3-65 3/4 3-65 8 3/4 3-3 8 3/4 3-3 m
.. _ _ _. ~. _ _ _ _. _ _ _ _ _ _ _ _ _ _ _ _.. _.. _. _, _. _ _ _
INSTRUMENTATION 3 /4. 3.4 TURBINE OVERSPEED PROTECTION LIMITING CONDITION FOR OPERATION 3.3.4 At least one turbine overspeed protection system shall be OPERABLE.
APPLICABILITY:
MODEG 1, 2 and 3.
60110t1:
l l
a.
With one stop valve or one control valve per high pressure turbine steam lead inoperable and/or with one reheat stop valve or one reheat intercept valve per-low pressure turbine steam lead inoperable, restore the inoperable valve (s) to the OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or close at least one valve in the affected steam lead; otherwise, isolate the turbine from the steam supply within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, b.
With the above required turbine overspeed protection system otherwise inoperable, within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> either restore the system to OPERABLE status or isolate the turbine from che steam supply.
SURVEILLANCE REQUIREMENTS 4,3,4.1 The provisions of Specification 4.0.4 are not applicable.
4.3.4.2 The above required turbine overspeed protection system shall be demonstrated _0PERABLI; (1) prior to admitting steam to the turbine during each startup unless performed within the past 7 days,_(2) following startup, within-24 hours of attaining manufacturer's recommended power level for performing turbine valve testing, and-(3) at a frequency not to exceed one-year
- by direct observation of the movement of each of the following valves through at least one complete cycle from the running position, a.
Four high pressure turbine stop valves.
l b.
Four nigh pressure turbine control valves.
c.
Six low pressure hot reheat stop valves, d.
Six low pressure hot reheat intercept valves.
The above valves are to be tested at a frequency consistent with the methodology presented in WCAP 11525, "Probabilistic Evaluation of Reduction in Turbine Valve Test Frequency", and in accordance with-the established NRC acceptance cri ejection incident of 1.0 x 10'5eria f r the probability of a missile per year, in no case shall the test interval for the above valves exceed.one year.
SALEM - UNIT 2 3/4 3 65 Amendment No.100, l
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,1NSTRl' MENTATION i
l BA$ES i
I 3/4.3.3.s RADIOACTIVE LIOUID EFFLUENT MONITORINC INSTRUMENTAtlQH The radioactive liquid affluent instrumentation is provided to monitor and control. as applicable, the releases of radioactive materials in liquid 1
effluents during actual or potential releases of liquid effluents.- The 1
alarm / trip setpoints for these instrierents shall be calculated and adjusted in accordance with the procedures in the ODCM to ensure that the alarm / trip will occur prior to exceeding the limits of 10 CFR Part 20. The OPERA 8!i,1TY and use
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of this instrumentation is consistent with the requirements of General Design j
Criteria 60, 63, and 64 of Appendix A to 10 CPR Part 50.: The purpose of tank 4
19 vel indicating devices is to-assure the detection and coitrol of leaks that J
if not controlled could potentially result in the transport of radioactive materials to UNRESTRICTED AREAS.
3/4.3.3.9 RADIOACTIVE CASEOUS EFFLUENT MONITORINC INSTRUMENTATIQH The radioactive gaseous effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in ganeous i
1 effluents during act 0 or potential releases of gaseous effluents. The j
alarm / trip setpoin'a e these instruments shall be calculated and adjusted in accordance with tht ocedures in the ODCM to ensure that the alarm / trip will occur prior to execs aing the limits of 10 CFR Part 20. This instrumentation also i:icludes provisions for monitoring (and controlling) the concentrations of potentially explosive gas mixtures in the waste gas holdup system.
The OPERAB11.ITY and use of this instrumentation is. consistent with the requirements of General Design Criteria 60, 63, and 64 of Appendix A to
?
3/4.3.4 TURBINE OVERSPEED PROTECTION-This specification is provided to ensure that the turbine overspeed protection instrumeritation and the turbine speed control valves are OPERABl.E and will protect the turbine from excessive overspeed.- Protection from turbine excessive overspeed is required since excessive overspeed of the turbine could I
generate potsntially damaging missiles which could impact and damage safety relrted components, equipment or structures.
Salem Unit 2 turbine is operated at full time,- full are admission.
To prevent excessive steam flow induced cyclic stresses of che control stage blading, perform turbine valve testing in accordancu with manufacturer's recommendctions.
SALEM UNIT 2 B 3/4 3 3 Amendment No. 100,
.