ML20065J526
| ML20065J526 | |
| Person / Time | |
|---|---|
| Site: | Catawba  (NPF-35-A-117, NPF-52-A-111) |
| Issue date: | 04/04/1994 |
| From: | Matthews D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20065J530 | List: |
| References | |
| NUDOCS 9404180266 | |
| Download: ML20065J526 (7) | |
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UNITED STATES y.
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.j NUCLEAR REGULATORY COMMISSION WASHINoToN, o.C. 206560001 o
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DUKE POWER COMPANY NORTH CAROLINA ELECTRIC MEMBERSHIP CORPORATION SALUDA RIVER ELECTRIC COOPERATIVE. INC.
DOCKET NO. 50-413 CATAW8A NUCLEAR STATION. UNIT 1 AMEN 0 MENT TO FACILITY OPERATING LICENSE Amendment No.117 License No. NPF-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 September 28, 1993, as supplemented February 17, 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 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; i
and i
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.
9404100266 940404 PDR ADOCK 05000413 P
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, 2.
Accordingly, the license is hereby amended by page changes to the Technical Specifications as indicated in the attachment to this licens$
amendment, and Paragraph 2.C.(2) of Facility Operating License No.
NPF-35 is hereby amended to read as follows:
Technical Soecifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 117, and the Environmental Protection Plan
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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
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David B. Matthews, Director Project Directorate 11-3 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Technical Specification Changes
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Date of Issuance: April 4, 1994
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UNITED STATES I
3 NUCLEAR REGULATORY COMMISSION U'
WASHINoToN, D.C. 20Ni6 0001 DUKE POWER COMPANY fl0RTH CAROLINA MUNICIPAL POWER AGENCY N0. 1 PIEDM0NT MUNICIPAL POWER AGENCY 00CKET N0. 50-4 H CATAWBA NUCLEAR STATION. UNIT 2 AMEN 0 MENT TO FACILITY OPERATING LICENSE
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Amendment No.111 License No. NPF-52 1.
The Nuclear Regulatory Commission (the Commission) 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 j
(licensees), dated September 28, 1993, as supplemented February 17, 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 (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 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.
a 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-52 is hereby amended to read as follows:
Technical Soecifications The Technical Specifications contained in Appendix A, as revised through Amendment No. III, 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 3
At f t
David B. Matthews, Director Project Directorate 11-3 J
Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Technical Specification Changes Date of Issuance: April 4, 1994
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ATTACHMENT TO LICENSE AMENDMENT NO.117 FACILITY OPERATING LICENSE NO. NPF-35 DOCKET NO, 50-413 6NQ TO LICENSE AMEN 0 MENT NO.111 FACILITY OPERATING LICENSE NO. NPF-52 DOCKET NO. 50-414 Replace the following pages of the Appendix "A" Technical Specifications with
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the enclosed pages.
The revised pages are identified by Amendment number and contain vertical lines indicating the areas of change.
Remove Paaet
.Lasert Paaes 3/4 5-6 3/4 5-6 3/4 5-7 3/4 5-7 l
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EMERGENCY CORE COOLING SYSTEMS SURVEILLANCE REQUIREMENTS 4.5.2 Each ECCS subsystem shall be demonstrated OPERABLE:
a.
At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> by verifying that the following valves are in the indicated positions with power to the valve operators removed:
Valve Number Valve Function
_Va]ve Position NI-162A Cold Leg Recirc.
Open NI-121A Hot leg Recirc.
Closed NI-1528 Hot Leg Recirc.
Closed NI-183B Hot Leg Recirc.
Closed NI-173A Residual Heat Open Removal Pump Disch.
NI-1788 Residual Heat Open Removal Pump Disch.
NI-100B Safety Injection Open Pump Suction from Refueling Water Storage Tank NI-1478 Safety Injection Open Pump Mini-flow b.
At least once per 31 days by:
1)
Verifying that the ECCS piping is full of water by venting the ECCS pump casings and accessible discharge piping high point.s, and 2)
Verifying that each valve (manual, power-operated, or automatic) in the flow path that is not locked, sealed, or otherwise secured in position, is in its correct position.
c.
By a visual inspection which verifies that no loose debris (rags, trash, clothing, etc.) is present in the. containment which could be transported to the containment sump and cause restriction of the pump suctions during LOCA conditions.
This visual inspection shall be performed:
1)
For all accessible areas of the containment prior to establish-ing CONTAINMENT INTEGRITY, and 2)
Of the areas affected within containment at the completion of each containment entry when CONTAINMENT INTEGRITY is established.
d.
At least once per 18 months by:
1)
Verifying automatic interlock action of the residual heat removal system from the Reactor Coolant System by ensuring that with a simulated or actual Reactor Coolant System pressure signal greater than or equal to 425 psig the interlocks prevent i
the valves from being opened.
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CATAWBA - UNITS 1 & 2 3/4 5-6 Amendment No. 117 (Unit 1)
Amendment No. 111_
(Unit 2)
EMERGENCY CORE COOLING SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) 2)
A visual inspection of the containment sump and verifying that the subsystem suction inlets are not restricted by debris and that the sump components (trash racks, screens, etc.) show no evidence of structural distress or abnormal corrosion.
e.
At least once per 18 months, during shutdown, by:
l 1)
Verifying that each automatic valve in the flow path actuates to its correct position on Safety Injection and Containment Sump Recirculation test signals, and 2)
Verifying that each of the following pumps start automatically upon receipt of a Safety injection test signal:
a)
Centrifugal charging pump, b)
Safety Injection pump, and c)
Residual heat removal pump.
f.
By verifying that each of the following pumps develops the indicated differential pressure when tested pursuant to Specification 4.0.5:
1)
Centrifugal charging pump 2 2349 psid, 2)
Safety Injection pump 2 1418 psid, and 3)
Residual heat removal pump 2 165 psid.
l g.
By verifying the correct position of each electrical and/or mechanical stop for the following ECCS throttle valves:
1)
Within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> following completion of each valve stroking operation or maintenance on the valve when the ECCS subsystems are required to be OPERABLE, and 2)
At least once per 18 months.
Centrifuaal Charaina Pumo Iniection Throttle Safety In.iection Throttle Valve Number Valve Number NI-14 NI-164 NI-16 NI-166 NI-18 NI-168 NI-20 NI-170 I
CATAWBA - UNITS 1 & 2 3/4 5-7 Amendment No. L17 (Unit 1)
Amendment No.111 (Unit 2)
.,