ML20147F662
| ML20147F662 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 02/29/1988 |
| From: | Hood D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20147F666 | List: |
| References | |
| NUDOCS 8803080010 | |
| Download: ML20147F662 (7) | |
Text
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NUCLEAR REGULATORY COMMISSION p,
UNITED STA1Es 3m c
WASHINGTON, D. C. 20066 o
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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 Anendment No. 41 License No. NPF-35 1.
The % clear Regulatory Comission (the Comission) has found that:
A.
The apolication for amendment to the Catawb Nuclear Station, Unit 1 (the facility) Facility Operating License R. NPF-35 filed by the Duke Power Company acting for itself, North Carolina Clectric Membership Corporation and Saluda River Electric Cooperative. Inc., (licensees) dated Deceder 3,1987, 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; j
8.
The facility will operate in confonnity with the application, as amended, the provisions of the Act, and the rules and regulations of the Comission; C.
There is reasonable tssurance (1) 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; 0.
The issuance of this tevndment 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 the Commission'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-35 is hereby amended to read as follows:
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(2) Technical Scecifications The Technical Specifications contained in Appendix A, as revised through Amendment No.
41, and the Environmental Protection Plan l
contained in Appendix B, both of which are attached hereto, are hereby incorporated into the license.
Duke Power Conpany shall operate the facility in accordance with the Technical Specifications l
and the Environtrental Protection Plan.
3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION i
Darl Hood
, Acting Director i
Project Directorate II-3 Division of Reactor Projects I/II
Attachment:
Technical Specification Changes Date of Issuance:
February 29, 1988 i
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DUKE POWER COMPANY NORTH CAROLINA MUNICIPAL POWER AGENCY NO. 1 PIEDMONT tt'NICIPAL POWER AGENCY DOCKET NO. 50-414 CATAWBA NUCLEAR STATION, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE knendment No. 34 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.1 and Piedmont Municipal Power Agency (licensees) dated December 3,1987, complies with the standards and requirements of the Atonic 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 confonnity with the application, as amended, 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 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 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 the Comission's regulations and all applicable requirements have been satisfied.
?.
Accordingly, the license is hereby amended by page changes to the Technical Specifications as indicated in the attachments to this license amendment.
and Paragra.ph 2.C.(2) of Facility Operating License No. NPF-52 is hereby l
amended to read as follows:
(2) Technical Specifications j
The Technical Specifications contained in Appendix A, as revised through Amendment No.
34, and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated into the 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 CCtNISSION i
Darl Hood Acting Director Project Directorate II-3 Division of Reactor Projects I/II
Attachment:
Technical Specification Changes j
Date of Issuance: February 29, 1988 i
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C Replace the followina page of the Appendix "A" Technical Specifications with a
the enclosed page. the revised page is identified by knendment nunter and i
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3/4.6 CONTAINMENT SYSTEMS 3/4.6.1 PRIMARY CONTAINMENT CONTAINMENT INTEGRITY LIMITING CONDITION FOR OPERATION 3.6.1.1 Primary CONTAINMENT INTEGRITY shall be maintained.
APPLICABILITY:
MODES 1, 2, 3, and 4.
ACTION:
Without primary CONTAINMENT INTEGRITY, restore CONTAINMENT INTEGRITY within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> or be in at least 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 /> and in COLD SHUT 00WN aithin the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
SURVEILLANCE REQUIREMENTS 4.6.1.1 Primary CONTAINMENT INTEGRITY shall be demonstrated:
a.
At least once per 31 days by verifying that all penetrations
- not capable of being closed by OPERABLE containment automatic isolation valves and required to be closed during accident conditions are closed by valves, blind flanges, or deactivated automatic valves secured in their positions, except as provided in Table 3.6-2 of Specification 3.6.3; b.
By verifying that each containment air lock is in compliance with the requirements of Specification 3.6.1.3; and c.
After each closing of each penetration subject to Type B testing, except the containment air locks, if opened following a Type A or B test, by leak rate testing the seal with gas at a pressure not less thanPls,ese.68psig,andverifyingthatwhenthemeasuredleakagerate 14 for th als is added to the leakage rates determined pursuant to Specification 4.6.1.2d. for all other Type B and C penetrations, the j
combined leakage rate is less than to 0.60 L,.
Except valves, blind flanges, and deactivated automatic valves which are located inside the annulus or the containment and are locked, sealed or otherwise secured in the closed position.
These penetrations shall be verified closed during each COLD SHUTDOWN except that such verification need not be performed more often than once per 92 days.
l 1
CATAWBA - UNITS 1 & 2 3/4 6-1
l CONTAINMENT SYSTEMS CONTAINMENT LEAKAGE LIMITING CONDITION FOR OPERATION l
- 3. 6.1. 2 Containment leakage rates shall be limited to:
a.
An overall integrated leakage rate of:
1)
Less than or equal to L,, 0.30% by weight of the containment l
air per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at P,, 14,68 psig, or 2)
(Unit 1) Less than or eoual to L, 0.122% by weight of the t
containment air per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at a reduced pressure of P '
t 7.34 psig, b.
A combined leakage rate of less than 0.60 L, for all penetrations and valves subject to Type B and C tests, when pressurized to P,,
and l
A combined bypass leakage rate of less than 0.07 L, for all c.
penetrations identified in Table 3.6-1 as secondary containment i
bypass leakage paths when pressurized to P,.
APPLICABILITY: MODES 1, 2, 3, and 4.
ACTION:
With:
(a) the measured overall integrated containment leakage rate exceeding 0.75 L, or 0.75 i, as applicable, or (b) the measured combined leakage rate for all g
penetrations and valves subject to Types B and C tests exceeding 0.60 L,, or (c) the combined bypass leakage rate exceeding 0.07 L,, restore the overall integrated leakage rate to less than 0.75 L, or less than 0.75 L, as applicable, t
I and the combined leakage rate for all penetrations and valves subject to Type B and C tests to less than 0.60 L,, and the combined bypass leakage rate to less than 0.07 L, prior to increasing the Reactor Coolant System temperature above 200*F.
4 SURVEILLANCE REQUIREMENTS 4.6.1.2 The containment leakage rates shall be demonstrated at the following test schedule and shall be determined in conformance with the criteria speci-fied in Appendix J of 10 CFR Part 50 using the methods and provisions of ANSI N45.4-1972 or the mass plot method:
CATAWBA - UNITS 1 & 2 3/4 6-2 Amendment No. 41 (Unit 1) i Amendment No. 34 (Unit 2)
, - - _