ML20210D327
| ML20210D327 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 09/16/1986 |
| From: | Jabbour K Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20210D332 | List: |
| References | |
| NUDOCS 8609190148 | |
| Download: ML20210D327 (7) | |
Text
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'o,'n UNITED STATES NUCLEAR REGULATORY COMMISSION g
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DUKE POWER COMPANY NORTH CAROLINA ELECTRIC MEMBERSHIP CORPORATION SALUDA RIVER ELECTRIC COOPERATIVE, INC.
DOCKET NO. 50-413 CATAWBA NUCLEAR STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.
11 License No. NPF-35 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment to the Catawba Nuclear Station,' Unit 1 (the facility) Facility Operating License No. NPF-35 filed by the Duke Power Company acting for itself, North Carolina Electric Membership Corporation and Saluda River Electric Cooperative, Inc., (licensees) dated June 6, 1986, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and-the Comission's regulations as set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, as amended, the provisions of the Act, and the regulations of the Comission;-
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 Comission's regulations set forth in 10 CFR Chapter I; D.
The issuance of this license amendment will not be inimical to the common defense and security or to the health and safety of the public; l
i-l E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all ~ applicable requirements have 4
been satisfied.
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' 2.. Accordingly, the license is hereby amended by page changes to the Technical Specifications as indicated in the attachments to this license amendment and Paragraph 2.C.(2) of Facility Operating License No. NPF-35 is hereby amended to read as follows:
(2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised
- through. Amendment No.ll, and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are-hereby incorporated into this license.. Dtke Power Company 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
\\9 Kahtan Jabbour, Project Manager PWR Project Directorate No. 4 Division of PWR Licensing-A
Attachment:
Technical Specification Changes Date of Issuance: September 16, 1986
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NUCLEAR REGULATORY COMMISSION 7,
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DUKE POWER COMPANY NORTH CAROLINA MUNICIPAL POWER AGENCY N0. 1 PIEDMONT MUNICIPAL POWER AGENCY DOCKET NO. 50-414 CATAWBA NUCLEAR STATION, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 4 License No. NPF-52 1.
The Nuclear 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-52 filed by the Duke Power Company acting for itself, North Carolina Municipal Power Agency No. I and Piedmont Municipal Power Agency (licensees) dated June 6, 1986, complies with the standards and re Energy Act of 1954, as. amended (the Act)quirements of the Atomic and the Comission's regulations as set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, as amended, the provisions of the Act, and the regulations of the Comission; 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 Comission's regulations set forth in 10 CFR Chapter I; D.
The issuance of this license amendment will not be inimical to the comon defense and security or to the health and safety of the public; E.
The issuance of this amendment is in accordance with 10 CFR Part Si of the Comission's regulations and all applicable requirements have been satisfied.
..2.
Accordingly, the license is hereby amended by page changes to the Technical Specifications as indicated in the attachments to this license amendment and Paragraph 2.C.(2) of Facility Operating License.No. NPF-52 is hereby amended to~ read as follows:
(2) Technical Specifications and Environmental Protection Plan The Tecnnical Specifications contained in Appendix A, as revised through Amendment No. 4, and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated into this license. Duke Power Company 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
\\5\\
Kahtan Jabbour, Project Manager PWR Project Directorate No. 4 Division of PWR Licensing-A
Attachment:
Technical Specification Changes Date of Issuance:
September 16, 1986 y' t
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ATTACHMENT TO LICENSE AMENDMENT NO.11 FACILITY OPERATING LICENSE NO. NPF-35 DOCKET N0. 50-413 AND TO l
LICENSE AMENDMENT N0. 4 FACILITY OPERATING LICENSE NO. NPF-52 DOCKET NO. 50-414 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised page is identified by Amendment number and contains vertical lines indicating the areas of change. The corresponding overleaf page is also provided to maintain document completeness.
Amended Overleaf Page Page 3/4 4-11 3/4 4-12 9
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REACTOR COOLANT SYSTEM SURVEILLANCE REQtlIREMENTS 4.4.4.1 In addition to the requirements of Specification 4.0.5, each PORV shall be demonstrated OPERABLE at least once per 18 months by:
a.
Performance of a CHANNEL CALIBRATION, and b.
Operating the valve through one complete cycle of full travel.
4.4.4.2 Each block valve shall_be demonstrated OPERABLE at least once per 92 days by operating the valve through one complete cycle of full travel unless the block valve is closed with power removed in order to meet the requirements of ACTION b. or c. in Specification 3.4.4.
4.4.4.3 The emergency power supply for the PORVs and block valves shall be demonstrated OPERABLE at least once per 18 months by:
a.
Manually transferring motive power from the normal (air) supply to the emergency (nitrogen) supply, b.
Isolating and venting the normal (air) supply, and c.
Operating the valves through a complete cycle of full travel.
l CATAWBA - UNITS I & 2 3/4 4-11 Amendment No. Il(Unit 1)
Amendment No. 4 (Unit 2)
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REACTOR COOLANT SYSTEM 3/4.4.5 STEAM GENERATORS l'
LIMITING CONDITION FOR OPE'ATION R
3.4.5 Each steam generator shall be OPERABLE.
APPLICABILITY: MODES 1, 2, 3 and 4.
ACTION:
With one or more steam generators inoperable, restore the inoperable generator (s to OPERABLE status prior to increasing T,yg above 200'F.
SURVEILLANCE REQUIREMENTS i
4.4.5.0 Each steam generator shall be demonstrated OPERABLE by performance of the following augmented inservice inspection program and the requirements of 1
Specification 4.0.5.
4.4.5.1 Steam Generator Sample Selection and Inspection - Each steam generator shall be determined OPERABLE during shutdown by selecting and inspecting at.
least the minimum number of steam generators specified in Table 4.4-1.
4.4.5.2 Steam Generator Tube Sample Selection and Inspection - The steam
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generator tube minimum sample size, inspection result classification, and the corresponding action required.shall be as specified in Table 4.4-2.
The inservice inspection of steam generator tubes shall be performed at the fre-quencies specified in Specification 4.4.5.3 and the inspected tubes shall be verified acceptable per the acceptance criteria of Specification 4.4.5.4.
The tubes selected for each inservice inspection shall include at least 3% of the total number of tubes in all steam generators;.the tubes selected for these inspections shall be selected on a random basis except:
1 a.
Where experience in similar plants with similar water chemistry indicates critical areas to be inspected, then at least 50% of the l
tubes inspected shall be from these critical areas; b.
The first sample of tubes selected for each inservice inspection (subsequent to the preservice inspection) of each steam. generator shall include:
4 CATAWBA - UNITS 1 & 2 3/4 4-12
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