ML20247L113
| ML20247L113 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 07/19/1989 |
| From: | Shemanski P Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20247L117 | List: |
| References | |
| NUDOCS 8908010147 | |
| Download: ML20247L113 (10) | |
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UNITED STATES p
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NUCLEAR REGULATORY COMMISSION.
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' WASHINGTON, D, C. 20555 3
a CO?*MONWEALTH. EDISON.CORPANY DOCKET NO. 50 373 LASALLE. COUNTY. STATION.. UNIT.1
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AMENDMENT.TO. FACILITY.0PERATIWG LICENSE Amendment No. 68 License No. NPF-11 1.
The Nuclear Regulatory Comission (the Corzission or the NRC) has found that:
A.
The application for amendment filed by the Commonwealth Edison Company.
(the licensee), cated December 4, 1987 supplemented March 10, 1989, complies with the standards unc requirements of the Atomic Energy Act of 1954, as an. ended (the Act), and the Comission's regulations set forth in-.10 CFR Chapter I; B.
The f6cility will operate in conformity with the application, the provisions of. the Act, e.nd the regulations of the Comission; C.
There is reasonable assurance: (1) that the activities authorized by this ar.endment 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 1; D.
The issuance of this amendment will not be inimical to the common defense und security or to the health ano safety of the public; and
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E.
The issuance of this amendment is in accordance with 10 CFR Part S1 of the Comission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifics-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 anended to read as follows:
8900010147 890719 r5 DR ADOCK 0500 3.
. (2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No.68, 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
(.[
Paul C. Shemanski, Acting Director Project Directorate III-2 Division of Reactor Projects - III, IV, V and Special Projects
Enclosure:
Changes to the Technical Specifications Date of Issuance:
July 19,1989 i
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ENCLOSURE TO LICENSE. AMENDMENT.NO. 68 FACILITY.0PERATING 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 0-2 3/4 0-2 B 3/4 0 B 3/4 0-3 O
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APPLICABILITY SURVEILLANCE REQUIREMENTS 4.0.1 Surveillance Requirements shall be met during the OPERATIONAL CONDITIONS or other conditions specified for individual Limiting Conditions for Operation unless otherwise stated in an individual Surveillance Requirements.
4.0.2 Each Surveillance Requirement shall be performed within the specified surveillance interval with a maximum allowable extension not to exceed 25 percent of the specified surveillance.
4.0.3 Failure to perform a Surveillance Requirement within tha specified time interval shall constitute a failure to meet the OPERABILITY requirements for a Limiting Condition for Operation.
Exceptions to these requirements are stated in the individual Specifications.
Surveillance' requirements do not have to be performed on inoperable equipment.
4.0.4 Entry into an OPERATIONAL CONDITION or u her specified condition shall not be made unless the Surveillance Requirement (s) associated with the Limiting Condition for Operation have been performed within the stated surveillance interval or as otherwise specified.
4.0.5 Surveillance Requirements for inservice inspection-and testing of ASME C. ode Class 1. 2,-& 3 components shall be applicable as follows:-
a.
Inservice inspection of ASME Code Class 1, 2, and 3 components and inservice testing of ASME Code Class 1, 2, and 3 pumps and valves shall be performed in accordance with Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda as required by 10 CFR 50, Section 50.55a(g), except where specific written relief has been granted by the Commission pursuant to 10 CFR 50, Section 50.55a(g) (6) (i).
b.
Surveillance intervals specified in Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda for the inservice inspection and testing activities required by the ASME Boiler and Pres:;ure Vessel Code and aoplicable Addenda shall be applicable as follows in these Technical Specifications:
ASME Boiler and Pressure Vessel Required frequencies Code and applicable Addenda for performing inservice terminology for inservice inspection and testing inspection and testing activities activities Weekly At least once per 7 days Monthly At least once per 31 days Quarterly or every 3 months At least once per 92 days Semiannually or every 6 months At least once per 184 days l
Every 9 months At least once per 276 days 4
Yearly or annually At least once per 366 days LA SALLE - UNIT 1 3/4 C-2 AMENDMENT NO.
68
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APPLICABILITY l
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k BASES 3.0.5 (Continued)
(as must be the components supplied by the emergency power source) and all i
redundant systems, subsystems, trains, components and devices in the other division must be OPERABLE, or likewise satisfy Specification 3.0.5 (i.e., be j
capable of performing their design functions and have an emergency power source OPERABLE).
In other words, both emergency power sources 0 and 1A must be OPERABLE and all redundant systems, subsystems, trains, components and devices in both divisions must also be OPERABLE.
If these conditions are not satisfied, action is required in accordance with this specification.
In OPERATIONAL CONDITION 4 or 5, Specification 3.0.5 is not applicable, and thus the individual ACTION statement for each applicable Limiting Condition for Operation in these OPERATIONAL CONDITIONS must be adhered to.
4.0.1 This specification provides that surveillance activities necessary to ensure the Limiting Conditions for Operation are met and will be performed during the OPERATIONAL CONDITIONS or other conditions for which the Limiting Conditions for Operation are applicable.
Provisions for additional surveillance activities to be performed without regard to the applicable OPERATIONAL CONDI-TIONS or other conditions are provided in the individual Surveillance Require-ments.
Surveillance Requirements for Special Test Exceptions need only be performed when the Special Test Exception is being utilized as an exception to an individual specification.
4.0.2 The provisions of this specification provide allowable tolerances fur performing surveillance activities beyond those specified in the nominal surveillance interval.
These tolerances are necessary to provide operational flexibility because of scheduling and performance considerations.
The phrase "at least" associated with a surveillance frequency does not negate this allowable tolerance; instead, it permits the more frequent performance of surveillance activities.
The allowable tolerance for performing surveillance activities is sufficiently restrictive to ensure that the reliability associated with the surveillance activity is not significantly degraded beyond that obtained from the nominal surveillance interval.
It is not intended that the allowable tolerance be used as a convenience to repeatedly schedule the performance of surveillance at the allowable tolerance limit.
4.0.3 The provisions of this specification set forth the criteria for determination of compliance with the OPERABILITY requirements of the Limiting Conditions for Operation.
Under this criteria, equipment, systems or components are assumed to be OPERABLE if the associated surveillance activities have been satisfactorily performed within the specified time interval.
Nothing in this provision is to be construed as defining equipment, systems or components OPERABLE, when such items are found or known to be inoperable although still neting the Surveillance Requirements.
LA SALLE - UNIT 1 B 3/4 0-3 AMENDMENT NO.
68
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UNITED STATES
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i COMMONWEALTH. EDISON.CONPANY DOCKETNO.50-}74, LASALLE. COUNTY. STATION,. UNIT.2 ANENDMENT.TO FACILITY OPERATING LICENSE Amendment No. 50 License No. NPF-18 1.
The Nuclear Regulatory Commission (the Comission or the NRC) has found that:
A.
The application for amendment filed by the Commonwealth Edison Company (the licensee), dated December 4, 1987 supplemented March 10, 1989 complies with the standards and reqrtirenents 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 Comm,ission; C.
There is reasonable assurance: (1) that the activities authorized by this amendinent can be conducted without endangering the health and s,afety of the public, and (ii) that such activities will be conducted in costpliance with the Comrrission'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 ano 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 chartges to the Technical Specifica-tions as indicated in tne enclosure to this license ainendment and paragraph t
2.C.{2) of the Facility Operating License No. NPF-18 is hyreby amended to read as follows:
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4 (2) Yechnical Specifications and. Environmental. Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 50, 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 Spec 1fications eno the Environmental Protection Plan.
3.
This. amendment is effective upon date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION (S
Paul C. Shemanski, Acting Director Project Directorate III-2 Division of Reactor Projects - III, j
IV, V and Special Projects j
Enclosure:
Changes to the Technical l
Specifications
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Date of Issuance:
July 19,1989 1
4 ENCLOSURE T0. LICENSE. AMENDMENT.NO. 50 FACILITY.0PERATING. LICENSE.NO. NPF-18 DOCKET.NO. 50-374 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 0-2 3/4 0-2 B 3/4 0-3 8 3/4 0-3 l
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APPLICABILITY SURVEILLANCE REQUIREMENTS 4.0.1 Surveillance Requirements shall be met during the OPERATIONAL CONDITIONS or other conditions specified for individual Limiting Conditions for Operation unless otherwise stated in an individual Surveillance Requirements.
4.0.2 Each Surveillance Requirement shall be performed within the specified surveillance interval with a maximum allowable extension not to exceed 25 percent of the specified surveillance.
4.0.3 Failure to perform a Surveillance Requirement within the specified time interval shall constitute a failure to meet the OPERABILITY requirements for a Lieniting Condition for Operation.
Exceptions to these requirements are stated in the individual Specifications.
Surveillance requirements do not have to be performed on inoperable equipment.
4.0.4 Entry into an OPERATIONAL CONDITION or other specified condition shall not be made unless the Surveillance Requirement (s) associated with the Limiting Condition for Operation have been prformed within the stated surveillance interval or as otherwise specified.
4.0.5 Surveillance Requirements for inservice inspection and testing of ASME Code Class 1, 2, & 3 components shall be applicable as follows:
a.
Inservice inspection of ASME Code Class 1, 2, and 3 components and inservice testing of ASME Code Class 1, 2, and 3 pumps and valves shall be performed in accordance with Section XI of the ASME Boiler and Presture Vessel Code and applicable Addenda as required by 10 CFR 50, % : tion 50.55a(g), except where specific written relief has been granted by the Commission pursuant to 10 CFR 50, Section 50.55a(g) (6) (i).
b.
Surveillance intervals specified in Section XI of the ASME Boiler 1
and Pressure Vessel Code and applicable Addenda for the inservice inspection and testing activities required by the ASME Eoiler and Pressure Vessel Code and applicable Addenda shall be applicable as follows in these Technical Specifications:
ASME Boiler and Pressure Vessel Required frequencies 1
Code and applicable Addenda for performiqq inservice terminology for inservice inspection and testing i
inspection and testing activities activities
]
Weekly At least once per 7 days Monthly At least once per 31 days Quarterly or every 3 months At least once per 92 days Semiannually or every 6 months At least once per 184 days Every 9 months At least once per 276 days Yearly or annually At least once per 366 days
- Not applicable to 18 month surveillance required for Unit 2 Cycle 2 operation.
LA SALLE - UNIT 2 3/4 0-2 AMEND 51ENT NO. 50
APPLICABILITY BASES 3.0.5 (Continued)
(as must be the components supplied by the emergency power source) and all redundant systems, subsystems, trains, components and devices in the other division must be OPERABLE, or likewise satisfy Specification 3.0.5 (i.e., bc l
capable of performing their design functions and have an emergency power source OPERABLE).
In other words, both emergency power sources O and _A must be OPERABLE and all redundant systems, subsystems, trains, components and devices in both divisions must also be OPERABLE.
If these conditions are not satisfied, action is required in accordance with this specification.
In OPERATIONAL CONDITION 4 or 5, Specification 3.0.5 is not applicable, and thus the individual ACTION statement for each applicable Limiting Condition for Operation in these OPERATIONAL CONDITIONS must bi adhered to.
4.0.1 This specification provides that surveillance activities necessary to ensure the Limiting Conditions for Operation are met and will be performed during the OPERATIONAL CONDITIONS or other conditions for which the Limiting Conditions for Operation are applicable.
Provisions for additional surveillance activities to be performed without regard to the applicable OPERATIONAL CONDI-TIONS or other conditions are provided in the individual Surveillance Require-ments.
Surveillance Requirements for Special Test Exceptions need only be performed when the Special Test Exception is being utilized as an exception to an individual specification.
4.0.2 The provisions of this specification provide allowable tolerances for performing surveillance cctivities beyond those specified in the nominal surveillance interval.
These tolerances are necessary to provide operational flexibility because of scheduling and performance considerations.
The phrase "at least" associated with a surveillance frequency does not negate this allowable tolerance; instead, it permits the more frequent performance of surveillance activities.
The allowable tolerance for performing surveillance activities is sufficiently restrictive to ensure that the reliability associated with the surveillance activity is not significantly degraded beyond that obtained from the nominal surveillance interval.
It is not intended that the allowable tolerance be used as a convenience to repeatedly schedule the performance of surveillance at the allowable tolerance limit.
4.0.3 The provisions of this specification set forth the criteria for determination of compliance with the OPERABILITY requirements of the Limiting Conditions for Operation.
Under this criteria, equipment, systems or components are assumed to be OPERABLE if the associated surveillance activities have been satisfactorily performed within the specified time interval.
Nothing in this provision is to be construed as defining equipment, systems or components OPERABLE, when such items are found or known to be inoperable although still meeting the Surveillance Requirements.
LA SALLE - UNIT 2 8 3/4 0-3 A'iENDMENT N0. 50
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