ML20091C816
| ML20091C816 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 03/31/1992 |
| From: | Hoffman S Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20091C819 | List: |
| References | |
| NUDOCS 9204060228 | |
| Download: ML20091C816 (10) | |
Text
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'1 SOUTHERN NUCLEAR OPERATIllG COMPANY, thC.
DOCKET NO. 50-348 JOSEPH P. FARLEY llUCLEAR PLANT, UNIT 1 A11ENDMENT TO FACILITY OFERATING LICENSE Amendment No. 93 License No. NPF-2
-1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amencment by the licensee, dated December 11, 1991, complies with the standards and requirements of the Atomic Erergy Act of 1954, as amended (the Act), and the Comission's rules ano regulations set forth in 10 CFR Chapter I; B.
The f acility 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 amencment can be conducted without endangering the health and safety of the public, ar.d (ii) that such activities will be conducted in compliance with the Comission's regulations; D.
The issuance of thi license amendment will not be inimical to the m mon defense and security or to the health and safety of the public; and E.
The issuance of this amencment 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 amendea by changes to the Technical Specifications, as indicated in the attachment to this license amendment; and paragraph 2.C.(2) of facility Operating License No. NPF-2 is hereby amended to read as follows:
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9204060228 920331 PDR ADOCK 05000348 p
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'; (2) Technical Specifications The Technical Specifications contained in Appendices A and 8, as i
revised through Amendment No. 93, are hereby incorporated in the j
license.
Southern Nuclear shall operate the f acility in accordance with the Technical Specifications.
3.-
This license arnendinent is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMNISSION f,6c. ~
linor G. Adensam, Director Project Directorate 11-1 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation Attachtrent:
Changes to the Technical Specifications Date of Issuance: Maren 31, 1992 y
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l ATTACHMENT T0 tlCENSE AMENDMENT NO. 93 TO FACILITY OPERATlHG LICENSE h0. hPF-2 DOCKET h0. 50-348 Peplace the following pages of the Appendix A Technical Specifications with the enclosed pages.
The revised creas are indicated by marginal lir.es.
i Remove Pages Insert Pages 3/4 0-2 3/4 0-2 B 3/4 0-3 B 3/4 0-3 i..
APPilCABILITY SURVEILLANCE RE0VIREMENTS l.
At least 110T STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, 2.
At least H0T SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, and 3.
At least COLD SliUTDOWN within the subsequent 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
This specification is not applicable in MODES 5 or 6.
4.0.1 Surveillance Requirements shall be applicable during the OPERATIONAL MODES or other conditions specified for individual Limiting Conditions for Operation unless otherwise stated in an individual Surveillance Requirement.
4.0.2 Each Surveillance Requirement shall be performed within the specified time interval with a maximum allowable extension not to exceed 25% of the surveillance intervtl.
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 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 MODE or other 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 spccified.
4.0.5 Surveillance Requirements for inservice inspection and testing of ASME Code Class ), 2 and 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 10CFR50, Section 50.55a(g), except where specific written relief has been granted by the Commission pursuant to 10CFR50, 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 Pressure Vessel Code and applicable Addenda shall be applicable as follows in these Technical Specifications:
- Upon determination that the surveillance had been inadvertently omitted, the Surveillance Requirement sha'l be successfully performed within the Limiting Condition of Operation (LCO) period which would begin upon discovery.
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FARLEY-UNIT 1 3/4 0-2 AMENDHENT NO.% 93
APPLICASILITY BASES tean that for one division the emergency power source must be OPERABLE (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.,
be capable of performing their design functions and have an emergency power source OPERABLE).
In other words, both emergency power sources 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 M00LS 5 or 6 Specification 3.0.5 is not applicable, and thus the individual ACTION statements for each applicable Limiting Condition for Operation in these MODES must be adhered to.
4.0.1 This specification provides that surveillance activities necessary to insure the Limiting Conditions for Operation are met and will be performed during the OPERATIONAL MODES 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 MODES or other conditions are provided in the individual Surveillance Requirements.
Surveillance Requirements for Special Test Exception
- need only be performed when the Special Test Exception is being utilized as an exception to an individual specification.
4.0.2 This specification establis:1es the limit for which the specified time interval for Surveillance Requirements may be extended.
it permits an allowable extension of the normal surveillance interval to facilitate surveillance scheduling and consioeration of plant operating conditions that may not be suitable for conducting the surveillance; e.g., transient conditions or other ongoing surveillance or maintenance activities.
The allowable tolerance also provides flexibility to accommodate the length of a feel cycle for surveillances that are performed at each refueling outage and are specified with an 18 month surveillance interval.
It is not intended that this provision be used repeatedly as a convenience to extend surveillance intervals beyond that specified; instead, this 'covision should be used to realize a benefit to safety.
The limitation of Specification 4,0.2 is based on engineering judgment and the recognition that the most probable result of any particular surveillance being performed is the verification of conformance with the Surveillance Requirements.
This provision is sufficient to ensure that the reliability ensured through surveillance activities is not signifi-cantly degraded beyond that obtained from the specified surveillance interval.
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 C e associated surveillance activities have been satisfactorily perP ad within the specified time interval. Nothing in this provision is
- 4 construed as defining equipment, systems or components OPERABLE, when su ' items are known to be inoperable although still meeting the Surveillance Requirements.
FARLEY-UNIT 1 B 3/4 0-3 AMENDMENT NO. % 93
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UNITED STATES 3r, E
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,8 50biHERN NUCLEAR OPERATING COMPANY, INC.
DOCKET NO. 50-364 JC$fPH H. FARLEY NUCLEAR PLANT, UNIT 2 AMENT #ENT TO FACILITY OPfrATING LICENSE Amendinent ho. 86 License No NPF-8 1.
The Nuclear Regulatory Corrnission (tne Consaission) has found that:
A.
The application for anendinent by the licensee, dated December 11, 1991, complies with the standark and requirerrents of the Atoruic Energy Act of 1954, as arrended n; \\ct), and the Connission's rules and regulation $ set forth in 10 CfR Chapter I; B.
The f acility will operate in conformity with the application, the provisions of the Act, and the rules ano regulations of the Comission; C.
There is reasonable assurance (i) that the activities authorized by this anendment can be conducted without endangering the health and cafety of the public, ano (ii) that such activities will te conducted in conpliance with the Consnission's regulations; D.
The issuance of this license amendment will not be inimical to the ccrvaon defense and security or to the health and safety of the public; and E.
The issuance of this anendir.ent is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable recuirernents have been satisfied.
2.
Accordingly, the license is ar, ended by changes to the Technical Specifications, as Indicated iri the attachment to this license amendment; and paragraph 2.C.(2) of facility C'perating License No. hPF-8 Is hereby amended to read as follows:
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2 (2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendrent No. 86, are hereby incorporated in the license. Southern Nuclear shall operate the facility in accordance with the Technical Specifications.
3.
This license anendment is effitctive as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMIS$10N i
Th hProjectDirectorate11-1Tiilor G. Adensan, Direct
/
Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation Attachnent:
Changes to the Technical Specifications Date of Issuance: March 31, 1992 e
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ATTACLFENT 10 LICEliSE AMENDl4ENT NO. P6 TO FACILITY OPERATiliG LICENSE fi0. NPF-8 l
DOCLET NO. 50-364 Replace the following pages of the Apper. dix A Technical Specifications with the enciesed pages.
T/ie revised areas are iridicated by nearginal lir.es.
Remove Pages Insert Pajig l
3/4 0-2 3/4 0 2 B 3/4 0-3 0 3/4 0-3 l
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APPLICA0lLill SURVEllLAt4CE REQQlRQiU(IS l.
At lesst HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, 2.
At least HOT SHUTDOWN within the fellowing 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, and 3.
At least COLD SHUTDOWN within the subsequent 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
This specification it not applicable in MODES 5 or 6.
4.0.1 Surveillance Requirements shcIl be applicable during the OPERATIONAL H0 DES or other conditions specified for individual Limiting Conditions for Operation unless otherwise stated in an individual Surveillance Requirement.
4.0.2 Each Surveillance Requirement shall be performed within the specified time interval with a maximum allowable extension not to exceed 25% of the surveillaace interval.
4.0.3 Failure to perform a Surveillance Requirement
- within the specified time interval shall constitute a failure to meet the OPERABill1Y-requirements for a limiting Condition for Operation.
Exceptions to these re wirements are stated in the individual specifications.
Surveillance Requirements do not have to be performed on inoperable equipment.
4.0.4 Entry into an OPERATIONAL MODE or other specified condition shall not be made unless the Seveillance 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 Code Class 1, 2 and 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 sccordance with Section XI of the ASME Boiler and Pres 5ure Vessu Code and applicable Addenda as required by 10CFR50, Section 50.55a(g), except wl.ere specific written relief has been granted by the Commission pursuant to 10CFR50, Section 50.55a(g)(6)(1).
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 Pressure Vessel Code and applicable Addenda shall be applicable as follows in these Technical Specifications:
- Upon determination that the surveillance had been inadvertently omitted, the Surveillance Requirement shall be successfully performed within the Limiting Condition of Operation (LCO) period which would begin upon discovery.
FARLEY-UNIT 2 3/4 0-2 AMENDMENT NO A.86
I APPLICABillTY BASES mean that for one division the emergency power source must be OPERABLE (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.,
be capable of perforn ng their design functions and have an emergency power o
source OPERABLE),
in other words, both emergency power soure.es 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 MODES 5 or 6 Specification 3.0.5 is not applicable, and thus the individual ACTION statements for each applicable Limiting Condition for Operation in these MODES must be adhered to.
4.0.1 This specification provides that surveillance activities necessary to insure the Limiting Conditions for Operation are met and will be performed during the OPERATIONAL MODES 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 MODES or other conditions are provided in the individual Surveillance Requirements.
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 This specification establishes the limit for which the specified i
time interval for Survol11ance Requirements may be extended.
it permits an allowable extension of the normal surveillance interval to facilitate surveillance scheduling and consideration of plant operatin may not be suitable for conducting the survelliance; e.g., g conditions that transient conditions or other ongoing surveillance or maintenance activities. The allowable tolerance also provides flexibility to accommodate the length of a fuel cycle for surveillances that are performed at each refueling outage and are specified with an 18 month surveillance interval.
It is not intended that this provision be used repeatedly as a convenience to extend surveillance intervals beyond that specified; instead, this provision should be used to realize a benefit to safety.
The limitation of Specification 4.0.2 is based on engineering judgment and the recognitien that the most probable result of any particular surveillance being performed is the verification of conformance with the Surveillance Requirements.
This provision is sufficient to ensure that the reliability ensured through surveillance activities is not signifi-cantly degraded beyond that obtained from the specified surveillance interval.
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 aerformed within the specified time.
interval. Nothing in this provision is to be construed as defining equipment, systems or components OPERABLE, when such items are known to be inoperable although still meeting the Surveillance Requirements.
FARLEY-UNIT 2 B 3/4 0-3 AMENDMENT NO. 86
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