ML20066A999
| ML20066A999 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 12/18/1990 |
| From: | Barrett R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20066B002 | List: |
| References | |
| NUDOCS 9101040248 | |
| Download: ML20066A999 (12) | |
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COMMONWEALTH EDISON COMPANY DOCKET NO. 50-373.
LASALLE COUNTY STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 76 License No. NPF-11 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment filed by the Commonwealth Edison Company (the licensee), dated September 21, 1990, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's 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 regulations of the Comission; C.
There is reasonable assurance: (i)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 Chapter I; D.
The issuance of this amendment will not be inimical to the comon 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 enclosure to this license amendment and paragraph 2.C.(2) of the Facility Operating License No. NPF-11 is hereby amended to read as follows:
9101040248 901210 PDR ADDCK 05000373 P
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(2) Technical Specifications and Environmental Protection Plan The Technical-Specifications contained in Appendix A, as revised through Amendownt No. 76, and the Environmental. Protection Plan contained.-in A)pendix B, are hereby incorporated in the license.
The 1icensee s1all operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This amendment is effective upon date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Ric'er ar ett, Director Project Directorate III-2
-Division of Reactor Projects III/IV/V Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications-Date of Issuance:
December 18, 1990
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ATTACHMENT TO LICENSE AMENDMENT NO. 76 FACILITY OPERATING LICENSE NO. NPF-11
- DOCKET NO. 50-373 Replace the following pages of the Appendix "A" Technical-Specifications with the enclosed pages.- The revised pages are identified by amendment number and contain a vertical line indicating the area of change.
REMOVE INSERT 3/4 8-25 3/4 8-25 i
3/4 8-25a B 3/4 8-3 8 3/4 8-3
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TABLE 3.8.3.2-1 (Continued)
-DEVICE NUMBER AND LOCATION SYSTEH/ COMPONENT POWERED d) MCC 134X-1 (Compt. 84)
NB/MOV 1821-F002 e) MCC 136Y-1 (Compt. B-2) (Normal)
RH/MOV IE12-F009 f) MCC 136Y-2 (Compt. E4)
RI/MOV 1E51-F063 g) MCC-135Y-1 (Compt. A1)
RR/MOV 1833-F023A h) MCC 135Y-1 (Compt. A4)
RR/MOV 1833-F067A i) MCC 133-1 (Compt. C2)
RT/MOV 1G33-F102 j) MCC-133-1 (Compt. E1)
NB/MOV 1821-F005 k) MCC-136Y-2 (Compt. B1)
NB/MOV 1B21-F016
RH/MOV 1E12-F099A m) MCC 136Y-1 (Compt. E4)
RT/MOV 1G33-F001 n) MCC 136Y-2 (Compt. A5)
WR/MOV 1WR180 o) MCC 136Y-2 (Compt. 06)
RH/MOV IE12-F099B p) MCC 136Y-1 (Compt. H5)
VP/MOV IVP113B q) MCC 136Y-1 (Compt. H4)
VP/MOV IVP114A r) MCC 136Y-1 (Compt. H3)
VP/MOV IVP113A s) MCC 136Y-1 (Compt. H6)
VP/MOV IVP114B t) MCC 136Y-2 (Compt. A4)
WR/MOV 1WR179 u) MCC 135Y-1 (Compt. 03)
RT/MOV 1G33-F101 v) MCC 135Y-1 (Compt. D4)
RT/MOV 1G33-F100 w) MCC 133-1 (Compt. C3)
RT/MOV 1G33-F106 x) MCC 136Y-2 (Compt. 05)
RI/MOV 1E51-F076 y) MCC 135X-1 (Compt..C2/C3) (Emerg)
RH/MOV IE12-F009 z) MCC 133-2.(Compt. AC1)
VP/Orywell Cooler IVP15SA aa) MCC 133-2 (Compt. AB1)
VP/Orywell Cooler IVP15SE LASALLE-UNIT 1 3/4 8-25 Amendment No. 76
TABLE 3.8.3.2-1 (continued)
DEVICE NUMBER AND LOCATION SYSTEM / COMPONENT POWERED ab) MCC 133-2 (Compt. AB2)
VP/Drywell Cooler IVP15SD ac) MCC 134X-2 (Compt. H1)
VP/Drywell Cooler IVP15SB ad) MCC 134X-2 (Compt. H2)
VP/Drywell Cooler IVP15SC ae) MCC 134X-2 (Compt J1)
VP/Drywell Cooler IVP15SF 2.
Type K-M Cat # NZ M12V-630/ZM12AV a) MCC 135X-2 (Compt. E4)
VP/Pri Cont.
Vent Supply Fan 1A Backup b) MCC 136X-2 (Compt. G4)
VP/Pri. Cont.
Vent Supply Fan 1B Backup LASALLE-UNIT 1 3/4 8-25a Amendment No. 76
ELECTRICAL POWER SYSTEMS BASES A.C. SOURCES AND ONSITE POWER DISTRIBUTION SYSTEMS (Continued) specific gravity, ensures that the decrease in rating will be less than the safety margin provided in sizing; (3) the allowable value for an individual cell's speci-fic gravity ensures that an individual cell's specific gravity will not be more then 0.040 below the manufacturer's full cliarge specific gravity and that the overall capability of the battery will be maintained within an acceptable limit; and (4) the allowable value for an individual cell's float voltage, greater than 2.07 volts, ensures the battery's capability to perform its design function.
The battery load profile and battery charger specifications will be main-tained and are located in Chapter 8, " Electrical Power", section of the Updated Final Safety Analysis Report, UFSAR.
3/4.8.3 ELECTRICAL EQUIPMENT PROTECTIVE DEVICES Primary containment medium and high voltage (6.9 kV, 4.16 kV and 480 vold electrical penetrations and penetration conductors are protected by either de-energizing circuits not required during reactor operation or demonstrating the OPERABILITY of primary and backup overcurrent protection circuit breakers by periodic surveillance.
The surveillan'ce requirements applicable to lower voltage circuit breakers and fuses provides assurance of breaker and fuse reliability by testing at least one representative sample of each manufacturers brand of circuit breaker and/or fuse.
Each manufacturer's molded case and metal case circuit breakers and/or fuses are grouped into representative samples which are then tested on a rotat ~
ing basis to ensure that all breakers and/or fuses are tested.
If a wide variety exists within any manufacturer's brand of molded case circuit breakers and/or fuses, it is necessary to divide that manufacturer's breakers and/or fuses'into groups and treat each group as a separate type of breaker or fuses for surveil-lance purposes, The bypassing of the motor operated valves thermal overload protection continuously or during accident conditions by integral bypass devices ensures that the thermal overload protection will not prevent safety related valves from per-forming their function.
The Surveillance Requirements for demonstrating the bypassing of the-thermal _cVerload protection continuously"and during accident conditions are in accordance with Regulatory Guide 1.106 Thermal Overload Pro-tection for Electric Motors on Motor Operated Valves", Revision 1, March 1977.
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COMMONWEALTH EDISON COMPANY DOCKET NO. 50-374 LASALLE COUNTY STATION, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 60 License No. NPF-18 1.
TheNuclearRegulatoryCommission(theCommission)hasfoundthat:
A.
The application for amendment filed by the Comonwealth Edison Company (the licensee), dated September 21, 1990, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's regulations set forth in 10 CFR Chapter _I; B.
The facility will operate in conformity with the application, the provisions of the Act, ard the 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 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.-
Accordir. gly, the license is amended by changes to-the Technical.Specifica-tions as indicated in the enclosure to this license amendment and paragraph 2.C.(2)oftheFacilityOperatingLicenseNo.NPF-18isherebyamendedto read as follows:
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-2 (2).-Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revP,ed through Amendment No. 60, and the Environmental Protection Plan contained in. Appendix B, are hereby incorporated in the license.
The licensee shall operate the facility _in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This amendment is effective upon date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Rich rd arrett, Director Project Directorate-111-2 Division of Reactor Projects III/IV/V Office of Nuclear Reactor Regulation
Attachment:
i Changes to the Technical
-Specifications.
Date of Issuance:
December 18, 1990
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ATTACHMENT TO LICENSE AMENDMENT NO. 60 FACILITY OPERATING LICENSE NO. NPF-18 DOCKET NO. 50-374 Replace-the following > ages of the Appendix "A" Technical Specifications with the enclosed pages. T1e revised pages are-identified b contain a vertical line indicating the area of change. y amendment 5 umber and REMOVE INSERT 3/4 8-25 3/4 8-25 3/4 8-25a B 3/4 8-3 8 3/4 8-3 0
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TABLE 3.8.3.2-1 (Continued)-
DEVICE NUMBER AND LOCATION SYSTEH/ COMPONENT POWERED d) MCC 234X-1 (Compt. B4)
NB/MOV 2B21-F002 e) MCC 236Y-1 (Compt. B2 (Normal)
RH/MOV 2E12-F009 f) MCC 236Y-2 (Compt. E4)
RI/MOV 2E51-F063 g).MCC 235Y-1 (Compt. A1)
RR/MOV 2833-F023A h) MCC 235Y-1 (Compt. A4)
RR/MOV 2B33-F067A i) MCC 233-1 (Compt. C2)
RT/MOV 2G33-F102 j) MCC-233-1 (Compt. E1)
NB/MOV 2B21-F005 k) MCC-236Y-2 (Compt. B1)
NB/MOV 2821-F016
RH/MOV 2E12-F099A m) MCC 236Y-1 (Compt. E4)
RT/MOV 2G33-F001 n) MCC 236Y-2 (Compt. A5)
WR/MOV 2WR180 o) MCC 236Y-2 (Compt. 06)
RH/MOV 2E12-F099B p) MCC 2'36Y-1 (Compt. H5)
VP/MOV 2VP1138 q) MCC 236Y-1 (Compt. H4)
VP/MOV 2VP114A r) HCC 236Y-1 (Compt. H3)
VP/MOV 2VP113A s) MCC 236Y-1 (Compt. H6)
VP/MOV 2VP114B t) MCC 236Y-2 (Compt. A4)
WR/MOV 2WR179 u) MCC 235Y-1 (Compt. 03)
RT/MOV 2G33-F101 v) MCC 235Y-1 (Compt. 04)
RT/MOV 2G33-F100 w) MCC 233-1 (Compt. C3)
RT/MOV 2G33-F106 x) MCC 236Y-2 (Compt. 05)
RI/MOV 2E51-F076 y) MCC 235X-1 (Compt. C2/C3) (Emerg)
RH/MOV 2E12-F009 z).MCC 233-2 (Compt. AC1)
VP/Drywell Cooler 2VP15SA aa) MCC 233-2 (Compt. AB1)
VP/Drywell Cooler 1
2VP15SE LASALLE - UNIT 2 3/4 8-25 Amendment No. 60
4 TABLE 3.8.3.2-1 (continued)
DEVICE NUMBER AND LOCATION SYSTEM / COMPONENT POWEREO ab) MCC 233-2 (Compt. AB2)
VP/Drywell Cooler 2VP15SD ac) MCC 234X-2 (Compt. H1)
VP/Orywell Cooler 2VP15SB ad) MCC 234X-2 (Compt. H2)
VP/Drywell Cooler 2VP15SC ae) MCC 234X-2 (Compt. J1)
VP/Drywell Cooler 2VP15SF 2.
Backup breakers are located in the front of the respective MCC, a) MCC 235X-2 (Compt. AA4)
VP/Pri. Cont.
Vent Supply Fan 2A Backup b) MCC 236X-2 (Compt. AA4)
VP/Pri Cont.
Vent Supply Fan 2B Backup LASALLE - UNIT 2 3/4 8-25a Amendment No. 60
ELECTRICAL POWER SYSTEMS BASES A.C. SOURCES AND ONSITE POWER DISTRIBUTION SYSTEMS (Continued) specific gravity, ensures that the decrease in rating will be less than the safety margin-provided in sizing; (3) the allowable value for an individual cell's speci-than 0.040 below the manufacturer's full chlarge specific gravity and that overall capability of the battery will be maintained within an acceptable limit; and (4) the allowable value for an individual cell's float voltage, greater than 2.07 volts, ensures the battery's capability to perform its design function.
The battery load profile and battery charger specifications will be main-tained and are located in Chapter 8 " Electrical Power", section of the Updated Final Safety Analysis Report, UFSAR.
3/4.8.3 ELECTRICAL EQUIPMENT PROTECTIVE DEVICES Primary containment medium and high voltage (6.9 kV, 4.16 kV and 480 volt) electrical penetrations and penetration conductors are protected by either de-energizing circuits not required during reactor operation or demonstrating the OPERABILITY of primary and backup overcurrent protection circuit breakers by periodic surveillance.
The surveillance requirements applicable to lower voltage circuit breakers and fuses provides assurance of breaker and fuse reliability by testing at least one representative sample of each manufacturers brand of circuit breaker and/or fuse.
Each manufacturer's molded case and metal case circuit breakers and/or fuses are grouped into representative samples which are then tested on a rotat-ing basis to ensure that all breakers and/or fuses are tested.
If a wide variety exists within any manufacturer's brand of molded case circuit breakers and/or fuses, it is necessary to divide that manufacturer's breakers and/or fuses into groups and treat.each group as a separate type of breaker or fuses for surveil-
-lance purposes.
The bypassing of the motor operated valves thermal overload protection continuously or during accident conditions by integral bypass devices ensures that the thermal overload protection will not prevent safety related valves from per-forming their function.
The Surveillance Requirements for demonstrating the bypassing of the thermal overload protection continuously"and during accident conditions are in accordance with Regulatory Guide 1.106 Thermal Overload Pro-tection for Electric Motors on Motor Operated Valves", Revision 1, March 1977.
LA SALLE - UNIT 2 B 3/4 8-3 Amendment No. 60