ML20062F433
| ML20062F433 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 11/13/1990 |
| From: | Butler W Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20062F437 | List: |
| References | |
| NUDOCS 9011270268 | |
| Download: ML20062F433 (17) | |
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NUCLEAR REGULATORY COMMISSION a
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PUBLIC $ERVICE ELECTRIC & GAS COMPANY PHILADELPHIA ELECTRIC COMPANY DELMARVA POWER AND LIGHT COMPANY ATLANTIC CITY ELECTRIC COMPANY DOCKET NO. 50-272 SALEM GENERATING STATION. UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Anendment No.115 License No. DPR-70 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 24, 1987, and supplemented by letters dated February 26, 1990, June 20, 1990, June 28, 1990 and September 19, 1990 complies with the standards 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 j
Comission; j
C.
There is reasonable assurance: (1)thattheactivitiesauthorizedby 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 set forth in 10 CFR l
Chapter I; D.
The issuance of this amendment will not be inimical to the comon i
defense and security or to the health and safety of the public; and j
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, 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-70 is hereby amended to read as follows:
9011270268 901113 PDR ADOCM 05000272 P
. (2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendices A and B as revised through Amendment No.115 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 to be impleniented within 60 days of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
/S/
W61ter R. Butler. Director Project Directorate 1-2 Division of Reactor Projects - 1/11
Attachment:
4 Changes to the Technical Specifications Date of Issuance:
November 13, 1990 j
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,, 1 (2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendices A and B as i
revised through Amendrent No.115,areherebyincorporatedInthe license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendmant it effective as of its date of issuance to be implemented within 60 days of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
($
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W61ter R. Butler, Director Project Directorate 1-2 Division of Reactor Projects - 1/11
Attachment:
Changes to the Technical Specifications Date of issuance: Neven.t er 13, 1990 4
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ATTACHMENT TO LICENSE AMENDMENT NO._115 FACILITY OPERATING LICENSE N0. OPR-70 DOCKET NO. 50-272 Revise Appendix A as follows:
Remove Pages
_ Insert Pages IV IV XII XII 3/4 3-70 3/4 3-71 B 3/4 3-4
lHDEE LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS IAGIlDE lAGE 3/4.2 poimt DISTRIBUTION I.IMITS
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3/4.2.1 AXIAL FLUX DIFFERENCE 3/4 2 1 3/4.2.2 HEAT FLUX HOT CHANNEL FACTOR 3/4 2 5 3/4.2.3 NUCLEAR ENTHALPY HOT CHANNEL FACTOR 3/4 2 9 3/4.2.4 QUADRANT POWER TILT RATIO 3/4 2 11 3/4.2.5 DNB PARAMETERS 3/4 2 13 3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR TRIP SYSTEM INSTRUMENTATION 3/4 3 1 3/4.3.2 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION 3/4 3 14 3/4.3.3 MONITORING INSTRUMENTATION Radiation M6'.itoring Instrumentation 3/4 3 35 Movable Incori Detectors 3/4 3 39 Seismic Instrtmentation 3/4 3 40 Meteorological instrumentation 3/4 3 43 Remote Shutdown Instrumentation 3/4 3 46 Fire Detection Instrumentation 3/4 3 49 Accident Monitoring Instrumentation 3/4 3 53 Radioactive Liquid Effluent Monitoring Instrumentation 3/4 3 58 Radioactive Caseous Effluent Monitoring Instrumentation 3/4 3 64 3/4.3.4 TURBINE OVERSPEED PROTECTION 3/4 3 70 SALEM. UNIT 1 IV Amendment No.115
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BASES SECTION Egil 3/4.3 INSTRUMENTATION 3/4.3.1 PROTECTIVE INSTRUMENTATION B 3/4 3 1 3/4.3.2 ENGINEERED SAFETY FEATURES (EST)
INSTRUMENTATION B 3/4 3 1 3/4.3.3 MONITORING INSTRUMENTATION B 3/4 3 1 3/4.3.4 TURBINE OVERSPEED PROTECTION B 3/4 3 4 3/4.4 REACTOR COO 1 ANT SYSTEM 3/4.4.1 REACTOR COO! ANT IDOPS AND COOLANT CIRCULATION B 3/4 4 1 3/4.4.2 SAFETY VALVES B 3/4 4.la 1
3/4.4.3 RELIEF VALVES B 3/4 4.la 3/4.4.4 PRESSURIZER B 3/4 4 2 3/4.4.5 STEAM CENERATORS B 3/4 4 2 3/4.4.6 REACTOR COOLANT SYSTEM LEAKAGE B 3/4 4 3 3/4.4.7 CHEMISTRY B 3/4 4 4 3/4.4.8
. SPECIFIC ACTIVITY B 3/4 4 5 I
3/4.4.9 PRESSURE / TEMPERATURE LIMITS B 3/4 4 6
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3/4.4.10 STRUCTURAL INTECRITY B 3/4 4 17 3/4.4.11 BLANK B 3/4 4 17 3/4.4.12 REACTOR VESSEL HEAD VENTS B 3/4 4 17 SALEM UNIT 1 XII Amendment No.llE i
. n~. a 3 /4. 3 '. 4 TURAINE OVEsePtED PitoTECTION LIMITINO CONDITION FOR OPERATION 3.3.4 At least one turbine overspeed protection system shall be OPERABLE.
APPLICABILITY:
MODES 1, 2 and 3.
i ACTJON:
1 a.
With one stop valve or one controt valve per high pressute turbine steam lead inoperable and/or with one reheat stop valve or i
one reheat intercept valve per low pressure turbine steam lead j
inoperable, restore the inoperable valve (s) to the OPERABLE etatus 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 i
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 carbine from the steam supply.
SURVE7L1ANCE REQUIREMENTS 4.3.n.1 The provisions of Specification 4.0.4 are not applicable.
4.3.I,.2 The above required turbine overspeed protection systes shc11 be demonstrated OPERABLEi (1) prior to admitting steam to the turbine dtring eanh i
startup unless performed within the past 7 days, (2) within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of attaining greater than or equal to 85% of RATED THERMAL POWER, at,d (3) et 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.
b.
Four high pressure turbine control valves, i
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 establishedNRCacceptanceerigeriafortheprobabilityofamissile ej ection incident of 1.0 x 10' per year, in no case shall the test interval for the above valves exceed one year.
9 SALEM UNIT 1 3/4 3 70 Amendment No. 115 1
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SURVEILIANCE REQUIREMENTS (Continued) 4.3.4.3 The above required turbine overspeed protection system shall be demonstrated OPERABLE:
x At least once per 18 months by performance of a CHANNEL s.
CALIBRATION on the turbine overspeed protection systems, b.
At least one per 40 months by disassembling at least'one of each of the above valves and performing a visual and surface inspection of valve seats, disks and stems and verifying no unacceptable flaws or corrosion.
If unacceptable flaws or excessive corrosion are found, all other valves of that type shall be inspected.
'4'.3,4,4 Verify the test frequency maintains the probability of a missile i
ejection incident within NRC guidelines by reviewing the methodology presented in WCAP 11525:
a'.
At least once every two refueling outages, b.
After modificacions to the main turbine or turbine overspeed protection valves, a
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SALEM UNIT 1 3/4 3 71 Amendment No.115 i
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3/4.3.4 Ttmaint Ov m ptrn PROTECTION This specification is provided to ensure.that the turbine overspeed protection instrumentation and the turbine speed control valves are OPERABLE and will protect the turbine from excessive overspeed. Protection from turbine excessive overspeed is required since excessive overspeed of tho' turbine could generate potentially damaging missiles which could impact and damage 1
safety related components, equipment or structures.
To prevent double shocking the turbine, valve testing is not required when j
steam is being admitted to the turbine and THERMAL POWER is less than 85% of RATED THERMAL POWER, provided the valves are tested prior to startup and within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of attaining 85% of RATED THERMAL POWER.
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 affect the selected valve test interval include low pressure turbine rotor d
type and. inspection interval; turbine valve type, arrangement and overspeed controls; and secondary side water chemistry, i
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SALEM UNIT 1 B34 34 Amendment No.115
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NUCLEAR REGULATORY COMMISSION l
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WASHINGTON, D. C. 20665 l'
PUBLIC SERVICE ELECTRIC & GAS COMPANY PHILADELPHIA ELECTRIC COMPANY DELMARVA POWER AND LIGHT COMPANY lTLANTIC CITY ELECTRIC COMPANY DOCKET-NO. 50-311 1
SALEP GENERATING STATION. UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 97 License No. DPR-75 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 Ligh Company and Atlantic City Electric Company thelicensees) dated December 24, 1987, and supplemented by -letters dated February 26, 1990, June 20, 1990, June 28, 1990 and September 19, 1990 complies with the standards 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)thattheactivitiesauthorized-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. set forth in 10 CFR C
Chapter I; l'
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 Comission'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.
l-paragraph 2.C.(2) of Facility Operating License No. DPR-75 is
..ay amended to read as follows:
i
n., (2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendices A and B, as revised through Amendr.ient No. 97, 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 to be impler.1ented within 60 days of the date of issuance.
FOR THE NUCLEAR REGUL ATORY COMMISSION
/S/
k' alter R.. Butler, Director Project Directorate I-?
Division of Reactor Projects - I/II
Attachment:
Changes to the-Technical Specifications Date of Issuance:
November 13, 1999 3
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(2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendices A and B, as l
revised through Amendment No. 97, 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 to be implemented within 60 days of the date of issuance.
l FOR THE NUCLEAR REGULATORY COMMISSION 4
V Walter R. Butler, Director
-l Project Directorate I-2 Division of Reactor Projects - I/II l
Attachment:
Changes to the Technical Specifications Date of. Issuance:
November 13, 1990 i
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AT1 ACHMENT TO LICENSE ANENDMENT NO. 97 FACILITY OPERATING LICENSE NO. DPR-75 DOCKET NO. 50-311 Revise Appendix A as follows:
Remove Pages Insert Pages 3/4 3-65 3/4 3-65 3/4 3-66 3/4 3-66 B 3/4 3-3 B 3/4 3-3 B 3/4 3-4 1
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I' 1 i INSTR 1 MENTATION 3/4.3.4 TURRINEONteePernPROTECTION LIMITING CONDITION FOR OPERATION' 3.3.4 At least one turbine overspesd 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 ti.S inoperable valve (s) to the OPERABl2 status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or clos 6 at least one valve in the affected steam lead; otherwise, isolate che 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 turbins overspeed protection systen-otherwise inoperable', within 6 hs urs either restore the system to OPERABLE status or isolate the turbine from the steam supply.
SURVEILIANCE REQUIREFENTS 4.3.4.1 The provisions of Specification 4.0.4 a o not applicable.
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) within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of attaining greatet chan or equal to 85% of RATED THERMAL POWER,- and (3) at a-frequency r.sc 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, b.
Four hi h prassure turbine control valves, 5
c.
Six low pressure hot reheat stop valves, d.
-Six low pressure hot reheat intercept,alves.
i The above valves are es 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 crigeria for the probability of a missile ejection incident of 1.0 x 10' per year, in no case shall the test interval for the above valves exceed one year.
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SALEM - UNIT 2 3/4 3 65 Amendment No. 97 L
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11tSTRIBENTATION SURVEILIAllCE REQUIRDENTS (Continued)
-4.3.4.3 The above required turbine overspeed protection system shall be demonstrated OPERABLE:
At least once por 18 months by performance of a CHANNEL l
.a.
CALIBRATION on the turbine overspeed protection systems.
b.
At least one per 40 months by disassembling at least one of l
each of the above valves and performing a visual and surface inspection of valve seats, disks and stems and verifying no unacceptable flaws or corrosion.
If unacceptable flaws or excessive corrosion are found, all other valves o! that type shall be inspected.
4.3.4.4 Verify the test frequency maintains the probability of a at sile election incident within NRC guidelines by reviewing the sothodology 1 resented in WCAP 11525:
At least once every two refueling outages.
1 a.
b.
After modifications to the main turbine or turbine overspeed protection valvea i
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.e SALEM - UNIT 2 3/4 3 66 Amendment No. 97
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INSTRUMENTATION BASES 3/4.3.3.8' RADI0 ACTIVE LIOUID EFFLUENT MONITORINC INSTRUMENTATION The. radioactive liquid effluent instrumentation is provid.d to monitor and control, as applicable, the releases of radioactive materials in liquid affluents during actual or potential releases of liquid effluents. The alarm / trip setpoints for these instruments 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 OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63, and'64 of Appendix A to 10 CFR Part 50. The purpose of tank level indicating devices is to assure the detection and control of leaks that if not controlled could potentially result in the transport of radioactive materials to UNRESTRICTED AREAS.
3/4.3.3.9 RADIOACTIVE CASEOUS EFFLUENT MONITORING INSTRUMENTATION The radioactive gaseous effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in gaseous e
effluents during actual or potential releases of gaseous effluents. The alarm / trip setpoints for these instruments 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. This instrumentation also includes provisions-for monitoring (and controlling) the concentrations of potentially explosive gas mixtures in the waste gas holdup system.
The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63, and 64 of Appendix A to 10 CFR Part 50, 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 OPERABLE and will protect the turbine from excessive overspeed.
Protection from turbine excessive overspeed is required since excessive overspeed of the turbine could
-generato potentially damaging missiles which could impact and damage safety related components, equipment or structures.
To prevent double shocking the turbine, valve testing is not required when steam is being admitted.to the turbine and THERMAL POWER is less than.85% of RATED THERMAL POWER, provided the valves are tested prior to startup.and within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of attaining 85% of RATED THERMAL POWER..
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SALEM UNIT 2 B 3/4 3-3 Amendment No 97
INSTRUMENTATION
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BASES During normal power operation, turbine valve testing is perforced at a frequency consistent with the methodology presented in WCAP 11515,
'Probabilistic Evaluation of Reduction in Turbine Valve Test 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 affect the selected valve test interval include low pressure turbine rotor type and inspection interval; turbine valve type, arrangement and overspeed control; and secondary side water chemistry.
t I
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SALEM - UNIT 2 B 3/4 3 4 Amendment No. 97