ML20064M724
| ML20064M724 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 03/21/1994 |
| From: | Matthews D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20064M727 | List: |
| References | |
| NUDOCS 9403280353 | |
| Download: ML20064M724 (8) | |
Text
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UNITED STATES
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W ASHINoToN, D.C. 20f46 0001
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DUKE POWER COMPANY NORTH CAROLINA ELECTRIC MEMBERSHIP CORPORATI0ff SALUDA RIVER ELECTRIC C00PERATLVE. INC.
ROCKET NO. 50-4))
CATAW A NUCLEAR _ STATION. UNIT 1 J
AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.114 License No..'4PF-35 1.
The Nuclear Regulatory Commission (the Commission) 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 January 18, 1994, as supplemented March 8, 1994, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission'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.
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 compliante with the Commission's regulations set forth in 10 CFR Chapter I; D.
The issuance of this amendment will not be inimical to the common 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.
9403280353 940321 PDR ADOCK 05000413 P
. 2.
Accordingly, the license is hereby amended by page 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-35 is hereby amended to read as follows:
lechnical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.114, 7.nd the Environmental Protection Plan contained in Appendix B, bcih 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 v6 David B. Matthews, Director Project Directorate 11-3 Division of Reactor Projects - I/11 Office of Nuclear Reactor Regulation
Attachment:
Technical Specification Changes Date of Issuance:
March 21,1994
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UNITED STATES j
NUCLEAR REGULATORY COMMISSION C
WASHINGTON. D.C. 20666-0001
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DUKE POWER COMPANY NORTH CAROLINA MUNICIPAL POWER AGENCY NO. 1 PIEDMQ_NT MUNICIPAL POWER AGFNQ1 DOCKET NO. 50-414 CATAWBA NUCLEAR STATION. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 108 License No. NPF-52 1.
The Nuclear Regulatory Commission (the Commission) has'found that:
A.
The application for amendment to the Catawba Nuclear Station, i
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 January. 18, 1994, as supplemanted March 8, i
1994, complies with the standards and requirements of the Atomic Energy Act of 1954, as-amended (the Act), and the Commission's rules and regulations as set forth in 10 CFR Chapter.I; i
B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; 1
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 Commission's regulations set forth in 10 CFR Chapter I; D.
The issuance of this amendment will not be inimical to the common-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 c
have been satisfied.
L
. 2.
Accordingly, the license is hereby amended by page Gianges to the Technical Specifications as indicated in the attachment to this license amendment, and Paragraph 2.C.(2) of facility Operating License No.
NPF-52 is hereby amended to read as follows:
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.108, 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 David B. Matthews, Director Project Directorate 11-3 Divistor, of Reactor Projects - 1/II Office of Nuclear Reactor Regulation
Attachment:
Technical Specification Changes Date of issuance:
43rch 21, 1994
ATTACHMENT TO LICENSE AMENDMENT NO. 114 FACILITY OPERATING LICENSE NO. NPF-35 DOCKET N0. 50-413 AND TO LICENSE AMENDMENT N0. 108 FACILITY OPERATING LICENSE NO. NPF-51 DOCKET NO. 50-414 P
Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and contain vertical lines indicating the areas of change.
Remove Paaes Insert Paaes X
X 3/4 8-19 3/4 8-19 (Unit 1) 3/4 8-21 through 3/4 8-43 (Unit 2) 3/4 8-44 through 3/4 8-66 8 3/4 8-3 8 3/4 8-3 i
LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION EA.GE AG 3/4.7.11 (DELETED) 3/4.7.12 GROUNDWATER LEVEL,.................
3/4 7-38 3/4.7.13 STANDBY SHUTDOWN SYSTEM...............
3/4 7-40 3/4.8 ELECTRICAL POWER SYSTEMS 3/4.8.1 A.C. SOURCES Operating 3/4 8-1 TABLE 4.81 DIESEL GENERATOR TEST SCHEDULE 3/4 8-9 TABLE 4.82 LOAD SEQUENCING TIMES.................
3/4 8-10 Shutdown.........................
3/4 8-11 3/4.8.2 D.C. SOURCES Operating 3/4 8-12 TABLE 4.8-3 BATTERY SURVEILLANCE REQUIREMENTS...........
3/4 8-15 Shutdown.........................
3/4 8-16 3/4.8.3 ONSITE POWER DISTRIBUTION Operating 3/4 8-17 S h u td own.........................
3 / 4 8-18 3/4.8.4 ELECTRICAL EQUIPMENT PROTECTIVE DEVICES Containment Penetration Conductor Overcurrent Protective Devices...................
3/4 8-19 1/4.9 REFUELING OPERATIONS 3/4.9.1 BORON CONCENTRATION (Unit 1)...............
3/4 A9-1 3/4.9.1 BORON CONCENTRATION (Unit 2)...............
3/4 B9-1 3/4.9.2 INSTRUMENTATION 3/4 9-2 3/4.9.3 DECAY TIME.........................
3/4 9-3 3/4.9.4 CONTAINMENT BUILDING PENETRATIONE 3/4 9-4 3/4.9.5 COMMUNICATIONS.......................
3/4 9-7 3/4.9.6 MANIPULATOR CRANE 3/4 9-8 3/4.9.7 CRANE TRAVEL - SPENT FUEL STORAGE POOL BUILDING 3/4 9-9 CATAWBA - UNITS 1 & 2 X
Amendment No.114 (Unit 1)
Amendment No.108 (Unit 2)
e EL.F4TRICAL POWER SYSTEMS L
3/4.8.4 ELECTRICAL EQUIPMENT PROTECTIVE DEVICES CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICES LIMITING CONDITION FOR OPERATION 3.8.4 Primary and backup containment penetration conductor overcurrent protective devices associated with each containment electrical penetration circuit shall be operable. The scope of these protective devices excludes those circuits for which credible fault currents would not exceed the electrical penetration design rating.
APPLICABILITY:
MODES 1, 2, 3, and 4.
ACTION:
With one or more of the above noted primary or backup containment penetration conductor overcurrent protective device (s) inoperable:
a.
Restore the protective device (s) to OPERABLE status or de-energize the circuit (s) by tripping the associated backup circuit breaker or racking out or removing the inoperable circuit breaker within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, declare the affected system or component inoperable, and verify the backup circuit breaker to be tripped or the inoperable circuit breaker racked out or removed at least once per 7 days thereafter; the provisions of Specification 3.0.4 are not applicable to overcurrent devices in circuits which have their backup circuit breakers tripped, their inoperable circuit breakers racked out, or removed, or b.
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 SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
SURVEILLANCE REQUIREMENTS 4.8.4 The above noted primary and t,ackup containment penetration conductor overcurrent protective devices shall be demonstrated OPERABLE:
a.
At least once per 18 months:
1)
By verifying that the medium voltage (4-15 kV) circuit breakers are OPERABLE by selecting, on a rotating basis, at least 10'/. of the circuit breakers of each voltage level, and performing the following:
a)
A CHANNEL CALIBRATION of the associated protective relays, b)
An integrated protective system functional test which includes simulated automatic actuation of the system and verifying that each relay and assr,ciated circuit breakers function as desiged, and CATAWBA - UNITS 1 & 2 3/4 8-19 Amendment No.114 (Unit 1)
Amendment No.108 (Unit 2)
ELECTRICAL POWER SYSTEMS j
BASES 3/4.8.4 ELECTRICAL EQUIPMENT PROTECTIVE DEVICES Containment electrical penetrations and penetration conductors are pro-tected by either deenergizing circuits not required during reactor operation or by demonstrating the OPERABILITY of primary and backup overcurrent protec-tion circuit breakers during periodic surveillance.
The Surveillance Requirements applicable to lower voltage circuit breakers and fuses provide assurance of breaker and fuse reliability by testing at least one representative sample of each manufacturer's brand of circuit breaker and/or fuse.
Each manufacturer's molded case circuit breakers and/or fuses are grouped into representative samples which are then tested on a rotating basis to ensure that all breakers and/or fuses are tested.
If a wide variety exists within any manufacturer's brand of circuit breakers and/or fuses, it is necessary to divide that manufacturer's breakers and/or fuses into groups and treat each group as a separate type of breaker or fuse for surveillance purposes.
The lists of components for which Technical Specification 3/4.8.4 is applicable are found in Catawba Selected Licensee Commitment (SLC) Section 16.8-1 in Chapter 16 of the Catawba Final Safety Analysis Report (FSAR).
CATAWBA - UNITS 1 s 2 B 3/4 8-3 Amendment No.11 Unit 1)
Amendment No.10 Unit 2)