ML20100C232
| ML20100C232 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire  |
| Issue date: | 03/18/1985 |
| From: | Adensam E Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20100C235 | List: |
| References | |
| NUDOCS 8503280778 | |
| Download: ML20100C232 (7) | |
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UNITED STATES
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DUKE POWER COMPANY DOCKET NO. 50-369 j
McGUIRE NUCLEAR STATION, UNIT 1 1
AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.41 License No. NPF-9 1.
The Nuclear Regulatory Comission (the Comission) 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 September 28, 1984, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended 4
(the Act) and the Commission'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
. 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 Comission's regulations' set forth in 10 CFR Chapter I;
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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 51 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-9 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 41, are hereby incorporated into this license.
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2-The licensee shall operate the facility in accordance with the Tech-nical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COPMISSION Elinor G. Adensam Chief Licensing Branch No. 4 Division of Licensing
Attachment:
Technical Specification Changes Date of Issuance: March 18, 1985
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DUKE POWER COMPANY DOCKET NO. 50-370 McGUIRE NUCLEAR STATION, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendme'nt No. 22 License No. NPF-17 1.
The Nuclear Regulatory Comission (the Comission) 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 September 28, 1984, 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: (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)ssuanceofthislicenseamendmentwillnotbeinimicaltothe 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 51 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-17 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained'in Appendix A, as revised through Amendment No. 22, are hereby incorporated into this license.
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The licensee shall operate the facility in accordance with the Tech-nical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMISSION Elinor G. Adensam, Chief Licensing Branch No. 4 Division of Licensing
Attachment:
Technical Specification Changes Date of Issuance: March 18, 1985
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ATTACHMENT TO LICENSE AMENDMENT NO. 41 i
FACILITY OPERATING LICENSE NO. NPF-9 i
DOCKET NO. 50-369 AND TO LICENSE AMENDMENT NO. 22 FACILITY OPERATING LICENSE NO. NPF-17 DOCKET NO. 50-370 Replace the following page of the Appendix "A" Technical Specifications with the enclosed page. The revised page is identified by Amendment number and contains a vertical ifne indicating the area of change. The corresponding overleaf page is being provided to maintain document completeness.
Amended Overleaf Pg Page 3/4 6-24 3/4 6-23 e
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CONTAINMENT SYSTEMS 3
SJRVEILLANCE REQUIREMENTS (Continued) 4.6.3.2 Each isolation valve specified in Table 3.6-2 shall be demonstrated OPERABLE during the COLD SHUTDOWN or REFUELING MODE at least once per 18 monttis by:
a.
Verifying that on a Phase A Containment Isolation test signal, each Phase A isolation valve actuates to its isolation position ~,
b.
Verifying that on a Phase B Containment Isolation test signal, each Phase B isolation valve actuates to its isolation position, and c.
Verifying that on a Containment Radioactivity-High test signal, each purge and exhaust valve actuates to its isolation position.
4.6.3.3 The isolation time of each power operated or automatic valve of Table 3.6-2 shall be determined to be within its limit when tested pursuant to
. Specification 4.0.5.
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TABLE 3.6-2 h
CONTAINMENTISOLATIONVALV$S E
MAXIMUM ISOLATION y
-VALVE NUMBER FUNCTION TIME (SEC)
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. Phase "A" Isolation w
E BB-18#
Steam Generator A Blowdown Containment Outside Isolation
<10 BB-28#
Steam Generator B Blowdown Containment Outside Isolation 710 BB-3B#
Steam Generator C Blowdown Containment Outside Isolation 710 BB-4B#
Steam Generator D Blowdown Containment Outside Isolation 710 BB-5A#
Steam Generator A Blowdown Containment Inside Isolation 310 BB-6As Steam Generator B Blowdown Containment Inside Isolation
<10 BB-7A#
Steam Generator C Blowdown Containment Inside Isolation 710 BB-8A#
Steam Generator D Blowdown Containment Inside Isolation 310 t'
CF-26AB#
Steam Generator D Feedwater Containment Isolation
<5 CF-28AB#
Steam Generator C Feedwater Containment Isolation 75 i
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CF-30AB#
Steam Generator B Feedwater Containment Isolation 75 T
CF-35AB#
Steam Generator A Feedwater Containment Isolation 75 T
CF-126B Steam Generator A Main Feedwater to Auxiliary Feedwater S0 Nozzle Isolation CF-1278 Steam Generator B Main Feedwater to Auxiliary Feedwater
$10 Nozzle Isolation CF-1288 Steam Generator C Main Feedwater to Auxiliary Feedwater
$10 si Nozzle Isolation
@U CF-1298 Steam Generator D Main Feedwater to Auxiliary Feedwater
$10 R$-
Nozzle Isolation NE
'CF-134A Steam Generator A Feedwater Containment Isolation Bypass
<10 CF-135A Steam Generator B Feedwater Containment Isolation Bypass 710 i
@f CF-136A Steam Generator C Feedwater Containment Isolation Bypass 310 2
CF-137A Steam Generator D Feedwater Containment Isolation Bypass
<10 00 CF-151A Auxiliary Nozzle Temper SG A 310 l
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