ML20033F485
| ML20033F485 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire  |
| Issue date: | 03/13/1990 |
| From: | Matthews D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20033F486 | List: |
| References | |
| GL-89-14, NUDOCS 9003210204 | |
| Download: ML20033F485 (7) | |
Text
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UNITED STATES g}#
NUCLEAR REGULATORY COMMISSION
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DOCKET WO. 50-369 McGUIRE NUCLEAR STATION. UNIT 1 AME!0 MENT TO FACILITY OPERATING LICENSE Amendment No.104 License No. NPF-9 1.
The Nuclear Regulatory Comission (the Comission) has found that:
The :pp(lication for amendnent to the McGuire Nuclear Station, A.
Unit 1 the facility) Facility Operating License No. hPF-9 filed by the Duke Power Company (the licensee) dated Decenter 21, 1989, complies with the standards and requirenents of the Atomic Energy Act of 1954, as anended (the Act), and the Comission's rules and regulations as 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 Co unission;
-C.
There.is reasonable assurance (1) that the activities authorized by this anendment can be conoucted without endangering the health and safety of the public, and. (ii) that such activities will be conducteo in compliance with the Commission's regulations set forth in 10 CFR Chapter I; D.
The. issuance of this amendment will rot be inimical to the common defense and security or to the' health and safety of the public; and E.
The issuance of this an=ndnent is in accordance with 10 CFR Part 51 of the Commission's regulations ar.d all applicable requirements have been satisfied, j$$32ggggf $$$,
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Accordingly, the license is hereby amended by page change:; to the Technical Specifications as indicated in the attachment to this license amendment, andParagraph2.C.(2)ofFacilityOperatingLicenseNo.NPF-9ishereby
. amended to read as follows:
Technical Specifications The Technical Specifications contained-in Appendix A, as revised through Amendment No.104, are hereby incorporated into the license.
The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
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'cet David B. Matthews, Director Project Directorate 11-3 Division of Reactor Projects-I/II Office of Nuclear Reactor Regulation
Attachment:
L Technical Specification Changes Date of' Issuance: March 13, 1990 l
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NUCLEAR REGULATORY COMMISSION
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DUKE POWER COMPANY l
i DOCKET NO. 50-370
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AMENDMENT TO FACILITY OPERATING LICENSE I
Amendment No. 86 License No. NPF-17 q
1.
The Nuclear Regulatory Comission (the Commission) has found that:
The app (lication for amendment to the McGuire Nuclear Station,the fa'.ility A.
Unit 2 by the Duke Power Company (the' licensee) dated December 21, 1989, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations as' 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 Commission; C.
Thereisreasonableassurance(1)thattheactivitiesauthorizedby L
this amendment can be conducted without endangering the realth and l
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; L
H 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 i-the Comission's regulations and all applicable requirements have been L
satisfied.
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2.
Accordingly, the license is hereby amended by page changes to the Technical Specificatiens as indicated in the attachment to this license amendment, and Paragraph 2.C.(2) of Facility Operating License No. NPF-17 is hereby amended to read as fM tows:
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 86, are hereby incorporated into the license.
The licensee shall operate the facility in accordance with the Technical Specifications and the. Environmental Protection Plan.
3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
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M David B. Matthews, Director Project Directorate II-3 Division of Reactor Projects-I/II Office of Nuclear Reactor Regulation
Attachment:
Technical Specification Changes Date of Issuance:
March 13, 1990 l.
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ATTACHMENT TO LICENSE AMENDMENT NO.104 FACILITY OPERATING LICENSE NO. NPF-9 DOCKET NO. 50-369 AND TO LICENSE AMEND 1ENT NO. 86 F/CILITY OPERATING LICENSE NO. NPF-17 DOCKET N0. 50-370 P.eplace the-following pages of the Appendix "A" Technical Specifications with the enclosed pages.
The revised pagos are identified by Amendnent nunber and contain vertical lines indicating the areas of change.
Amended Pages 3/4 0-2 B3/4 0-4 t
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i SURVEILLANCE REQUIREMENTS
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4.0.1 Surveillance Requirements shall be met 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 interval.
4.0.3 Failure to perform a Surveillance Requirement within the allowed sur-
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veillanca interval, defined by Spccification A.O.2, shall constitute noncompli-ance with the OPERABILITY requirements for a Limiting Condition for Operation.
The time limits of the ACTION requirements are applicable at the time it is identified-that a Surveillance Requirement has not been performed.
The ACTION requirements may be delayed for up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to permit the completion of the surveillance when the allowable outage time l hits of the ACTION requirements are less than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
Surveillance Requirecents do not have to be performed on inoperable equipment.
4.0.4 Entry into an OPERATIONAL NODE 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 specifiej This provision shall not prevent passage through or to OPERATIONAL MODES as required to comply with ACTION requirements.
4.0.5 Surveillance Requirements for inservice inspection and testing of ASME Code Class 1, 2, and 3 r.cmponents shall be applicable as follows:
a.
Inservice inspectici 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 perforud 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)(1);
McGUIRE UNITS 1 and 2 3/4 0-2 Amendment No.104 (Unit 1)
Amendment No. 86 (Unit 2)
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-APPLiCA'BILITY BASES Specifications 4.0.1 through 4.0.5 establish the general requirements appli-
' cable to SurveiTTance Requirements.
These requirements are based on the Surveillance Requirements stated in the Code of Federal Regulations, 10 CFR 50.36(c)(3):
' Surveillance requirements are iequirements relating to test, calibration, or inspection to ensure that the necessary quality of systems and components is maintained, that facility operation will be within safety limits, and that the limiting conditions of operation will be met."
Spnification 4.0.1 establishes the requirement that surveillances must be performed daring tiie OPERATIONAL MODES or other conditions for which the requirements of the Limiting Conditions for Operation apply unless otherwise stated in an ir.riividual Surveillance Requirement.
The purpose of this specification is to ensure that surveillances are performed to verify the operationC status of 1,ystems and components and that parameters are within specified limits to ensure safe operation of the facility when the plant is in a MODE or other specified condition for which the associated Limiting Conditions for Operation are applicable.
Surveillance Requirements ao not have to be parformed when the facility is in an OPERATIOE MODE for which the requirements of the associated Limiting Condition for Operation do not apply unless otherwise specified.
The Surveillance Requirements associated with a Special Test Exception are only applicable when the Special Test Exception is used as an allowable exception to the requirements of a specification.
Specification 4.0.2 establishes 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' consideration of plant operating conditions that may not be suitable for conducting the surveillance; e.g., transient conditions or other ongoing surveillance or maintenance activities.
It also provides flexibility to accommodate the length of a tuel cycle for surveillances that are performed at each refueling outage and l
are specified with an 18-month surveillance interval.
It is not intended that L
this provision be used repeatedly as a convenience to extend rurveillance intervals beyond that specified for surveillances that are not performea during refueling L
caages.
The limitation of Specification 4.0.2 is based on engineering judgment erd the recognition that the most probable result of any particular surveillance being performed is the verification of conformance with the Surveillance Require-ments.
This provision is sufficient to ensure that the reliability ensured through surveillance activities is not significantly degraded beyond that obtained from the specified surveillance interval.
Specification 4.0.3 establishes the failure to perform a Surveillance Requirement withili the allowed surveillance interval, defined by the provisions of Specification 4.0.2, as a condition that constitutes a failure to meet the OPERABILITY requirements for a Limiting Condition for Operation.
'Under the provisions of this specification, systems and components are assumed to be OPERABLE when Surveillance Requirements have been satisfactorily performed within the specified time interval.
However, nothing in this McGUIRE - UNITS 1 and 2 B 3/4 0-4 Amendment No.104 (Unit 1)
Amendment No. 86 (Unit 2)
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