ML20071Q796
| ML20071Q796 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire  |
| Issue date: | 07/29/1994 |
| From: | Berkow H Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20071Q799 | List: |
| References | |
| NUDOCS 9408120019 | |
| Download: ML20071Q796 (7) | |
Text
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UNITED STATES 2Y E
NUCLEAR REGULATORY COMMISSION I
WASHINGTON, D.C. 20555 4001
,o DUKE POWER COMPANY DOCKET N0. 50-369 McGUIRE NUCLEAR STATION. UNIT 1 l
AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.
145 License No. NPF-9 1.
The Nuclear Regulatory Commission (the Commission) has found that:
[
A.
The application for amendment to the McGuire Nuclear Station, Unit 1 (the facility), facility Operating License No. NPF-9 filed by the Duke Power Company (licensee) dated November 11, 1993, as supplemented on June 13, 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 i
by this amendment can be conducted without endangering the health l
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 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.
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9408120019 940729 PDR ADOCK 05000369 P
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O 1 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-9 is hereby amended to read as follows:
Technical Soecifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 145, are hereby incorporated into this license. The licensee 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 4
C
- eFbert N. Berkow, Director Project Directorate 11-3 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Technical Specification Changes Date of Issuance: July 29, 1994
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4 UNITED STATES y-E NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-4001
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4 DUKE POWER COMPANY DOCKET NO. 50-370 McGUIRE NUCLEAR STATION. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 127 License No. NPF-17 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment to the McGuire Nuclear Station, Unit 2 (the facility), Facility Operating License No..NPF-17 filed by the Duke Power Company (licensee) dated November 11, 1993, as supplemented on June 13, 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 i
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.
i l
. 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-17 is hereby amended to read as follows:
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 127. are hereby incorporated into this license.
The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection P1an.
3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION hab~
-Herbert N. Berkow, Director Project Directorate II.',
Division of Reactor Prrjects - I/II s
Office of Nuclear Reactor Regulation
Attachment:
Technical Specification Changes Date of Issuance:
July 29, 1994
O ATTACHMENT T0' LICENSE AMENDMENT N0. 145 FACILITY OPERATING LICENSE N0. NPF-9 DOCKET NO. 50-369 AND TO LICENSE AMENDMENT NO.127 FACILITY OPERATING LICENSE N0. NPF-17 DOCKET NO. 50-370 Replace the following pages of the Appendix "A" Tecnnical 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 3/4 5-7 3/4 5-7 3/4 5-8 3/4 5-8
_7 i
SURVEILLANCE RE0VIREMENTS (Continued)
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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 shutdo'wn, by:
l 1)
Verifying that each automatic valve. in the flow path actuates to its correct position on Safety Injection actuation and automatic l
switchover to Containment Sump Recirculation test signals,. and i
2)
Verifying that each of the following pumps start automatically i
upon receipt of a Safety Injection actuation test signal:
a)
Centrifugal charging pump, l
b)
Safety Injection pump, and c)
RHR pump.
f.
By verifying that each of the following pumps develops the indicated differential pressure when tested pursuant to Specification 4.0.5:
i 1)
Centrifugal charging pump 2 2347 psid, l
2)
Safety Injection pump 1 1418 psid, and l
3)
RHR pump 1 166 psid.
l g.
By verifying the correct position of each electrical and/or mechanical position 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 i
i f
McGUIRE - UNIT 1 and 2 3/4 5-7 Amendment No. 145 (Unit 1) l Amendment No. 127 (Unit 2)
4 SURVEILLANCE RE0VIREMENTS (Continued) 2)
At least once per 18 months.
Boron Injection Safety Injection Throttle Valves Throttle Valves yalve Number Valve Number NI-480 NI-488 NI-481 NI-489 NI-482 NI-490 NI-483 NI-491 h.
By performing a flow balance test, during shutdown, following comple-i tion of modifications to the ECCS subsystems that alter the subsystem flow characteristics and verifying that:
1)
For centrifugal charging pump lines, with a single pump running:
a)
The sum of the injection line flow rates, excluding the highest flow rate, is greater than or equal to 325 gpm for Unit I and 320 gpm for Unit 2, and b)
The total pump flow rate is less than or equal to 560 gpm.
l 2)
For Safety Injection pump lines, with a single pump running:
a)
The sum of the injection line flow rates, excluding the highest flow rate, is greater than or equal to 423 gpm, and l
b)
The total pump flow rate is less than or equal to 675 gpm.
3)
For RHR pump lines, with a single pump running, the sum of the injection line flow rates is greater than or equal to 4025 gpm.
l McGUIRE - UNIT 1 and 2 3/4 5-8 Amendment No. 145 (Unit 1)
Amendment No. 127 (Unit 2)
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