ML20012E557
| ML20012E557 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 03/27/1990 |
| From: | Matthews D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20012E558 | List: |
| References | |
| NUDOCS 9004050401 | |
| Download: ML20012E557 (7) | |
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UNITED STATES e
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5 WASHINGTON, D. C 20656
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1 tUKE POWER COMPANY NORTH CAROLIf,A ELECTRIC MEMBERSHIP CORPORATION SALUDA RIVER ELECTRIC COOPERATIVE, INC.
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000XET NO. 50-413
.l QATAWBA NUCLEAR STATION. UNIT.
i AMENONENT TO FACILITY OPERATING 1.! CENSE
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s Amenenent flo. 72 License No. NPF-35 1.
The Nuclear Regulatory Commission (the Connission) has found that:
A.
The application for amendwent to the Catawba Nuclear Station, Unit 1 (the facility) Facility Operating License No. NPF-35 filed by the
' Duke Power Company actit-for itself, North Carolina Electric Membership) Corporation aniSaluda River Electric Cooperative, Inc.,
i (licensees dated Decenber 21, 1989, complies with t1e standares and requirenwnts of the Atomic Energy Act of 1954, as anended (the Act),
and the Consission's' rules and regulations.as set forth in 10 CFR Chapter I; t
1 B.
The facility will operate in conformity with the application, the L
provisions of the Act, and the rules and regulations of the Comission; t
C.
There is reasonable assurance (1) that the activities authorized by this anendsent ran be conductea without endangering the health and i
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; 1
i D.
The issuance of this amenckent will not be inimical to the conmon L
defense and security or to the health and safety of the public; and l
E.
The issuance of this anenerent is in accordance with 10 CFR Part 51 l
l of the Commission's regulations and all applicable requirements have L
been satisfied.
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2.
Accordingly, the license is hereby anended by page changes to the Technical Specifications as inoicated in the attachment to this license amendnent, and Paragraph 2.C.(2) of facility Operating License No. hPF-35 is hereby i
anended to read as follows:
Technical $recifications The Technical Specifications contained in Appendix A, as revised through Asenonent No. 72, are hereby incorporated into the license, i
The licensee shall operate the facility in accordance with the Technical Specifications and the Environnental Protection Plan.
3.
This license apenment is effective as of its date of issuance.
r TOR THE NUCLEAR REGULATORY COMMISSION r
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% -L Cavid B. Matthews, Director Project Directorate II-3 Division of Reactor Projects-I/II Office of Nuclear Reactor Regulation Attachnent:
i Technical Specification Changes Date of 1ssuance: March 27,1990 i
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UNITED STATES t
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_ DUKE POWER COMPANY NORTH CAROLINA MUNICIPAL POWER AGENCY NO.1 l
PIEDMONT MUNICIPAL POWER AGENCY DOCKET NO. 50-414 CnTAWBA NUCLEAR STATION, Oh!T 2 AMEhDMENT TO FACILITY CPERATlhG LICENSE 5
Amendnent No. 66 Liconse No. NPF-52 i
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The Nuc1 car Regulatory Comission (the Comission) has found that:
A.
The application for amendment to the Catawba Nuclear Station, Unit 2 (the facility) Facility Operating License No. NPF-5E filed by the Duke Power Company actip ' for itself, North Carolin6 Hunicipal Power -
Ageny No, I and Piedmont Municipal Power Ageny, (licensees) dated i
December 21, 1989, complies with the standards and requirenants of the Atomic Energy Act of 19E4, as amended (the Act), and the Conunission'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 Comission; C.
There is reasonable assurance (1) that the activities authorized by this anunonent 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; l
D.
The issuance of this amendnent will not be inimical to the coninon F
defense and security or to the health and safety of the public; and E.
The issuance of this amen $ent is in accordance with 10 CFR Part 51 t
of the Conunission's regulations and all applicable requirements have been satisfied.
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2.
Accordingly, the license is hereby anended by page changes to the Technical Specifications as indicated in the attoctawnt to this license antnoment, and Paragraph 2.C.(2) of facility Operating License No. NPF-52 is hereby anended to read as follas:
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Anandnent No. 66, 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 amendrent is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION f /c -
p David B. Matthews, Director Project Directorate 11 1 Division of Reactor Projects-1/11 Office of Nuclear Reactor Regulation Attachnent:
Technical Specification Changes Date of Issuance: March 27, 1990 1
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l ATTACHMENT TO LICENSE AMENDMENT NO. 72 FACILITY OPERATING LICENSE NO. NPF-35 j
DOCKET NO. 50-413 ANp y
TO LICEN_SE AMENDMENT NO. 66 FACILITY OPEP,ATING LICENSE NO. NPF-52 l
00CKET NO. 50-414 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages.
The revised pages are identified by Amendment nunber and contain vertica.1 lines indicating the areas of change.
i Amended Page 3/4 0-2 i
B 3/4 0-4 0
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7 APPLICABILITY SURVEILLANCE REQUIREMENTS 4.0.1 Surveillance Requirements shall be met during the OPERATIONAL MODES or other conditions specified for individual Limiting Cenditions 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-veillance interval, defined by Specification 4.0.2, 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 a130wable outage time limits 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 Requirements do not have to be performed on innperable 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 specified..This provision shall not prevent passage through or to OPERATIONAL MODES as rejuired to comply with ACTION requirements.
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 accordance with Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda as required by l
10 CFR Part 50, Section 50.55a(g), except where specific written relief has been granted by the Commission pursuant to 10 CFR Part 50, Section 50.55a(g)(6)(i);
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l CATAWBA - UNITS 1 & 2 3/4 0-2 Amendment No. 72 (Unit 1)
Amendment No. 66 (Unit 2)
e APPLICABILITY BASES Specification 4.0.1 establishes the requirement that surveillances must be perfornied during the OPERATIONAL MODES or other conditions for which the requirements of the Limiting Conditions for Operation apply unless otherwise stated in an individual Surveillance Requirement.
The purpose of this specifi-cation is to ensure that surveillances are performed to verify the operational status of systems 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 do not have to be performed when the fa-cility is in an OPERATIONAL MODE for which the requirements of the associated Limiting Condition for Or.eration do not apply unless otherwise specified.
The Surveillance Requirements associated with a Special Test Exception are only appli-cable 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 Te'quirements may be extended.
It permits an allowable extension of the normal surveillance interval to facilitate surveillance scheduling and consideration of plant cperating 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 fuel cycle for surveillances that are performed at each refueling outage and are specified with an 18-month surveillt 7 interval.
It is not intended that this provision be used repeatedly as a convenience to extend surveillance intervals beyond that specified for surveillances that are not performed during refueling outages.
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 Require-ments.
This provision is sufficient to ensure that the reliability ensured througl i
surveillance activities is not significantly degraded beyond that obtained from the l
t specified surveillance interval.
l Specification 4.0.3 establishes the failure to perform a Surveillance Requirement l
within the allowed surveillance interval, defined by the provisions of Specifi-cation 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 thfr.
l specification, systems and components are assumed to be OPERABLE when Surveillance Requirements have been satisfactorily performed within the specified time interval.
I However, nothing in this provision is to be construed as implying that systems or H
components are OPERABLE when they are found or known to be inoperable although still meeting the Surveillance Requirements.
This specification also clarifies that the ACTION requirements are applicable when Surveillance Requirements have not been completed within the allowed surveillance interval and that the time limits of the l
ACTION requirements apply from the point in time it is identified that a surveillance has not been performeo and not at the time that the allowed surveillance interval was exceeded.
Completion of the Surveillance Requirement within the allowable outage time limits of the ACTION requirements restores compliance with the requirements of Specification 4.0.3.
However, this does not negate the fact that the failure to have performed the surveillanca within the allowed surveillance interval, defined by the provisions of Specification 4.0.2, was a violation of the OPERABILITY 1
CATAWBA - UNITS 1 & 2 B 3/4 0-4 Amendment No.72 (Unit 1)
Amendment No.66 (Unit 2)
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