ML20118B170
| ML20118B170 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 09/22/1992 |
| From: | Barrett R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20118B171 | List: |
| References | |
| NUDOCS 9209300279 | |
| Download: ML20118B170 (18) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION i
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[DMMONWEALTH EDISON COMPANY QQCKET NO. 50-373 LASALLE COUNTY _SIAll0N. UNIT 1 MENDMENT TO FAClllTY OPERATING LICENSE Amendment No. 87 License No. NPF-ll 1.
The Nucicar Regulatory Commission (the Commission) has found that:
A.
The application for amendment filed by the Commonwealth Edison Company (the licensee), dated June 17, 1992, 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; fl.
The facility will operate in conformity with the application, the provisions of the Act, and 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 issusace of thh amandment will not be inimical to the common defense and security or to the health and safety of the public; l
and C.
The issuance of this amendment is in accordance with 10 CFR Part bl of the Commission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the licente :s amende: by changes to the Technical Specifications as indicated in the enclosure to this license amendment i
and paragraph 2.C.(2) of the Facility Operating License No. NPF-ll is hereby amended to read as follows:
1 l
l 920Y3OO279 920922 PDR ADOCK 05000373 P
2 (2)
Technical Snecificattans and. Environmental _ Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 87, and the Environmentil 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 uoon startup from LIR05 refuel outage.
FOR THE NUCLEAR REGULATORY COMMISSION 4
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Richar Barrett, Director Pr ject Directorata !!!-2 Division of Reactor Projects - Ill/IV/V 4
i Office of Nuclear Reactor Regulation At t ac hinent :
l Changes to the Technical l
Specifications l
Date of issuance:
September 22. 1992 I
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ATTACHMENT TO LitENSE AMENDMEN1 NO 87 i
2 FACILITY OPERATING LICENSE NO. NPF-ll l.
.;l DOCKET NO. 50-373 i
l Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages.
The reviJwl pages are identified by amendment number and l
contain a vertical line indicating the area of change.
I BEMOVE INSERT i
j XXill XX111 i
l 3/4 8-22 3/4 8
.'2 3/4 8-24 3/4 8 24 3/4 8-25 1/4 8-25 4
j 3/4 8-25a j
B 3/4 8-3 B 2/4 8-3 l
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_ _ _.... ~ _ _ _ _ _ _
1 INDEX LIST OF TABLES (Continued)
TABLE PAGE i
4.6.1.5-2 TENDON LIFT-OFF FORCE.............................
3/4 6-12 3.6.3-1 PRIMARY CONTAINMENT ISOLATION VALVES..............
3/4 6-24 4
3.6.5.2-1 SECONDARY CON 1AINMENT VENTILATION SYSTEM AUTOMATIC ISOLATION DAMPERS......................
3/4 6-39 I
j 3.7.5.2-1 DELUGE AND SPRINKLER SYSTEMS......................
3/4 7-16 3.7.5.4-1 FIRE HOSE STATIONS................................
3/4 7-19 i
3.7.7-1 AREA TEMPERATURE MONITORING......................
3/4 7-25 4.8.1.1.2-1 DIESEL CENERATOR TEST SCHEDULE....................
3/4 8-7b i
4.8.2.3.2-1 BATTERY SURVEILLANCE REQUIREMENTS.................
3/4 8-18 3.8.3.3-1 MOTOR 0PERATED VALVES THERMAL OVERLOAD i
PROTECTION.......................................
3/4 8-27 i
B3/4.4.6-1 RE ACTOR VE SSE L TOUGHNE SS..........................
B 3/4 4-6 j
5.7.1-1 COMPONENT CYCLIC OR TRANSIENT LIMITS..............
5-6 i
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LA SALLE - UNIT 1 XXIII Amendment No, M, 87
ELECTRICAL POWER SYSTEMS PRIMARY CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICES LIMITING CONDITION FOR OPERATION 3.8.3.2 Primary and backup primary containment penetration conductor i
overcurrent protective devices associated with each primary containment medium and high voltage (6.9 kV, 4.16 kV and 480 volt) electrical penetration circuit shall be OPERABLE.
The scope of these protective devices excludes those circuits for which credible fault currents would not exceed the electrical penetration design rating.
APPLICABILITY:
OPERATIONAL CONDITIONS 1, 2, and 3.
ACTION:
a.
With one or more of the primary containment penetration conductor overcurrent protective devices inoperable, restore the protective device (s) to OPERABLE status or de-energize the circuit (s) by tripping the associated circuit breaker or racking out or removing the inoperable ciNuit breaker within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, declare the affected system or component inoperable, and verify the circuit breaker to be tripped or the inoperable circuit breaker racked out, or removed, at least once per 7 days thereafter.
Otherwise, be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUT 00VN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, b.
The provisions of Specification 3.0.4 are not applicable to over-current devices in circuits which have their circuit breakers trippeo, racked out, or removed.
SURVEILLANCE REQUIRt1ENTS i
4.8.3.2 Each of the primary containment penetration conductor overcurrent protective devices shall be demonstrated OPERA 2LE:
a.
At least once per 28 months:
1.
By verifying that the 6.9 kV and 4.16 kV circuit breakers are OPERABLE by selecting, on a rotating basis, at least 10% of the circuit breakers and performing:
a)
A CHANNEL CALIBRATION of the associated protective relays, l
and b)
An integrated system functional test of the breakers a rcurrent protective trip circuit which includes simulated automatic actuation of the trip syshm to demonstrate that the overall penetration protection design remains within operable limits.
c)
For each circuit breaker found inoperable during these functional tests, an additional representative sample of at least.10% of all the circuit breakers of the inoperable type shall also be functionally tested until no more failures are found or all circuit breakers of that type have been functionally tested.
LASALLE-UNIT 1 3/4 8-22 Amendment No. 42, 87 I
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i LASALLE-UNIT 1 3/4 8-24 Amendment No. 87 8
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THIS PAGE 1HTENT10NALLY LEFT BLANK 4
LASALLE-UNIT 1 3/4 8-25 Amendment No. 87
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 than 0.040 below the manufacturer's full charge 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-l tained and are located in Chapter 8 " Electrical Power", section of the Updated Final Safety Analysis Report, UFSAR.
3/4.3.3 ELECTRICAL EQUIPMENT PROTECTIVE DEVICES g
Primary containment medium and high voltage (6.9 kV, 4.16 kV and 480 volt)
J electrical penetrations and penetration conductors are protected by either de-energizing circuits not required during reactor operation or demonstrating h
the OPERABILITY of primary and backup overcurrent protection circuit breakers by periodic surveillance.
A controlled list of the components applicable to Specification 3.8.3.2 is maintained as an Administrative Technical Requirement.
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 mol6ed 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 or. Motor Operated Valves", Revision 1, March 1977.
LA SALLE UNIT 1 B 3/4 8-3 Amendment No. 76, 87
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i NUCLEAR REGULATORY COMMISSION
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COMMONWEALTH EDISON COMPANY DOCKET NO. 50-374 LASALLE COUNTY STATION. UNIT 2 AMENDMENT ~
FACILITY OPERATING LICENSE 2't Amendment No. 71 l
1icense No. NPF-18 i
1.
The Nuclear Regulatory Commission (the Commission) has found that:
l A.
The application for amendment filed by the Comonwealth Edison Company (the licensee), dated June 17, 1992, complies with the standards and requirements of the Atomic Energy Act of 1954, cs amended (the Act), and the Commission's regulations set forth in 10 CFR Chapter I; B.
The facility will oper-ste in conformity with the application, the provisions of the Act, ano the rerJlations of the Commission; C.
There is reasonable assurance: (i) that the activities authorized 1
j by this amendment can he conducted without endangering the health and safety of the public, and (11) that such activities will be conducted in compliance with the Commission's regulations set forth in 10 'FR Chapter I; 4
D.
The issuance of this amendment will not be inimical to the common i
defense and security or ta 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 Specifications as indicated in the enclosure to this license amendment and paragraph 2.C.(2) of the Facility Operating License No. NPF-18 is hereby amended to read as follows:
l l
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(2)
Technical Specifications and Envirpnmental protection Plan i
i Tte Technical Specifications contained in Appendix A, as revised j
through Amendment Nc.
71, 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.
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3.
This amendment is effective upon startup from llR05 refuel outage.
1 FOR THE NUCLEAR REGULATORY COMMISSION l
/
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j 0-i Rich r J. Barrett, Director Project Directorate 111-2 Division f.f Reactor Projects - Ill/lV/V Office of Nuclear Reactor Regulation i
Attachment:
Changes to the Technical l
Specifications Date of Issuance: September 22, 1992 i
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ATTACllMEN1 TO LICD]1E;_ AMENDMENT NO. 71 fEJLITY OEE!'hTITG Lif.ENSE NO. NPF-18 DOCKET NO,,50-374 I
Replate the following pages of the Appendix 'A' Technical Specifications with
}
the enclosed pages.
The revised pages are identified by amendment number and i
contain a vertical line indicating the area of chrnge.
Pages indicated with j
un asterisk are provided for convenience, i
REMOVE INSERT l
XXIll XXIll
- 3/4 8-21
- 3/4 8-21 3/4 8-22 3/4 8-72
]
3/4 8-24 3/4 8-24 3/4 8-25 3/4 8 25 3/4 8-25a
)
- 3/4 8-26
- 3/4 8-26 B 3/4 8-3 P
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. -. - - -. _, _. _ -, _. - _,,,..,.,. -. -,,.. ~,..,. - -,, -,,, -. - - _.,.. - -. _..
LIST OF TABLES Montinued)
TABLE PAGE 3.6.5.2-1 SECONDARY CONTAINMENT VENTILATION SYSTEM AUTOMATIC ISOLATION DAMPERS.......................
3/4 6-42 l
3.7.5.2.1 DELUGE AND SPRINKLER SYSTEMS.........-.............
3/4 7-16 l
3.7.5.4-1 FIRE HOSE STATIONS...............................
3/4 7-19 1
3.7.7-1 AREA TEMPERATURE MONITORING.......................
3/4 7-26 4.8.1.1.2-1 DIESEL GENERATOR TEST SCHEDULE....................
3/4 8-76 i
4.8.2.3.2-1 BATTERY SURVEILLANCE REQUIREMENTS.................
3/4 8-18 4
3 3.8.3.3-1 MOTOR-OPERATED VALVES THERMAL IVERLOAD PROTECTION........................................
3/4 8-27 j
C3/4.4.6-1 REACTOR VESSEL TOU'3HNESS B 3/4 4-6 5.7.1-1 COMPONENT CYCLIC OR TR"NP LIMITS..............
5-6 i
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LA SALLE - UNIT 2 XXIII Amendment No. M, 71
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ELECTRICAL POWER SYSTEMS l
3/4.8.3 ELECTRICAL EQUIPMENT FROTECTIVE DEVICES A.C. CIRCUITS INSIDE PRIMARY CONTAINMENT LIMITING CONDITION FOR OPERATION i
3.8.3.1 At least the fol?owing A.C. circuits inside primary containment shall be deenergized*:
a.
Installed welding grid systems 2A and 28, and j
b.
All drywell lighting circuits, i
j c.
All drywell hoists and cranes circuits.
APPLICABILITY:
OPERATIONAL CONDITIONS 1, 2, and 3.
ACTION:
)
With any of the above required circuits energized, trip the associated circuit breaker (s) in the specified panel (s) within I hour.
L 4
SURVEILLANCE REQUIREMENTS j
i 4.8.3.1 Each of the above required A.C. circuits shall be determined to be de-energized at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> ** by verifying that the associated circuit breakers are in the tripped condition.
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- Except during entry into the drywell.
i
- Except at least once per 31 days if locked, sealed, or otherwise secured in-the tripped condition.
LA SALLE - UNIT 2 3/4 8-21
ELECTRICAL POWER SYSTEMS PRIMARYCONTAINMENTPENETRATIONCONDUCTOROVERCURRENTPROTECTIVEDEVIf']
4 LIMITING CONDITION FOR OPERATION 3.8.3.2 Primary and backup primary containment penetration conductor overcurrent protective devices associated with each primary containment medium and high voltage (6.9 kV, 4.16 kV and 480 volt) electrical penetration circuit 4
shall be OPERABLE.
The scope of these protective devices excludes thor circuits for which credible fault currents would not exceed the electric.al penetration design rating.
APPLICABILITY:
OPERATIONAL CONDITIONS 1, 2, and 3.
ACTION:
a.
With one or more of the primary containment penetration conductor overcurrent protective devices inoperable restore the protective 4
device (s) to OPERABLE status or de-energize the circuit (s) by tripping the associated circuit breaker or racking out or removing 4
the inoperable circuit breaker within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, declare the affected system or component inoperable, and verify the circuit breaker to be tripped or the inoperable circuit breaker racked out, or removed, at least once per 7 days thereafter.
0 Qerwise, be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTOOWN within tne following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
b.
The provisions of Specification 3.0.4 are not applicable to over-current devices in circuits which have their circuit breakers tripped, racked out, or removed.
i SURVEILLANCE REQUIREMENTS 4.8.3.2 Each of the primary containment penetration conductor overcurrent protective devices shall be demonstrated OPERABLE:
l a.
At least once per 18 months:
j 1.
By verifying that the 6.9 kV and 4.16 kV circuit breakers are OPERABLE by selecting, on a rotating basis, at least 10% of i
the circuit breakers and performing:
i a)
A CHANNEL CALIBRATION of the associated protective relays, and b)
An integrated system functional tet,t of the breakers overcurrent protective trip circuit which includes simulated automatic actuation of the trip system to demonstrata that the overall penetration protection design remains within operable limits.
c)
For each circuit breaker found inoperable during these functional tests, an additional representative sample of at least 10% of all the circuit breakers of the inoperable type shall also be functionally tested until no more failures are found or all circuit breakers of that type have been functionally tested.
LASALLE - UNIT 2 3/4 8-22 Amendment No. 23, 71
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LASALLE - UNIT 2 3/4 8-25 Amendment No. 71 e-..e--
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4 ELECTRICAL POWER SYSTEMS j
MOTOR OPERATED VALVES THERMAL OVERLOAD PROTECTION LIMITING CONDITION FOR OPERATION i
a l
3.8.3.3 The thermal overload protection of each valve shown in Table 3.8.4.2-1 shall be bypassed continuously or under accident conditions, as applicable, by an OPERABLE bypass device integral with the motor starter.
j APPLICABILITY:
Whenever the motor operated valve is required to be OPERABLE.
I ACTION:
1 a.
With the tnermal overload protection for one or more of the above required valves not bypassed continuously or under accident conditions, i
as applicable, by an OPERABLE integral bypass device, take administra-i tive action to continuously bypass the thermal overload within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> j
or declare the affected valve (s) inoperable and apply the appropriate ACTION statement (s) for the affected system (s),
i The provisions of Specification 3,0.4 are not applicable.
b.
4 1
SURVEILLANCE REQUIREMENTS 4.8.3.3.1 The thermal overicad protection for the above required valves shall be verified to be bypassed continuously or under accident conditions, as applicable, by an OPERABLE integral bypass device by the performance of a CHANNEL FUNCTIONAL TEST of the hypass circuitry for those thermal overloads which are normally in force during r.lant operation and bypassed under accident conditions and by verifying that the thermal overload protection is bypassed for those thermal averloads which tre continuously bypassed and temporarily placed in force only when the valve motors are undergoing perioaic or maintenance testing; a.
At least once per 18 months, and i
b.
Following main'.enance on the motor starter.
4.8.3.3.2 The thermal overload protection for the above required valves which are continuously bypassed shall be verified to be bypassed following testing during which the thermal overload protection was temporarily placed in force.
i LA SALLE - UNIT 2 3/4 8-26 l
l
ELECTRICAL POWER SYSTEMS
{
BASES l
A.C. SOUP.CES 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 than 0.040 below the manufacturer's full charge specific gravity and that the overall capability of the battery will be maintained within an acceptable limit; and (4) the allowable value for an inaividual cell's float voltage, greater than 2.07 volts, ensures the battery's capability to perform its design function.
Tha 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.
i 3/4.8.3 ELECTRICAL EQUIPMENT PROTECTIVE DEVICES Primary containment medium and high voltage (6.9 kV, 4.16 kV and 480 volt) 4 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.
A controlled list of the components applicable to Specification 3.8.3.2 is maintained as an Administrative Technical Requirement.
The surveillance requirements applicable to lower voltage circuit breakers i
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 brePkers and/or fuses art grouped into representative samples which are then tested on a rotat-4 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 i
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 demon:trating the bypassing of the thermal overload protection continuously" Thermal Overload Pro-and during accident conditions are in accordance with Regulatory Guide 1.106 tection for Electric Motors on Motor Operated Valves", Revision 1, March 1977.
LA SALLE - UNIT 2 B 3/4 8-3 Amendment No. 71 h
1