ML20151G939
| ML20151G939 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire  |
| Issue date: | 07/22/1988 |
| From: | Lainas G Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20151G943 | List: |
| References | |
| NUDOCS 8808010067 | |
| Download: ML20151G939 (6) | |
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DUKE POWER COMPANY DOCKET NO.60-369 McGUIRE NUCLEAR STATION. UNIT 1 A!F10 MENT TO FACILITY OPERATING LICENSE Amendment No. 90 License No. NPF-9 1.
The Nuclear Regulatory Comission (the Cornission) has found that:
The app (lication for amendment to the McGuire Nuclear Station,the facility) F A.
Unit 1 by tho Duke Power Company (the licensee) dated July 15 and 19,1988, and supplemented July 21, 1988, corplies 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; B.
The f acility will operate in conformity with the application, as i
amended, the provisions of the Act, and the rules and regulatioas t
of the Cocenission; 4
C.
There is reasonable asturance (1) that the activities authorized by this amendment can be conducted without endangering the beelth 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 common defense and security or to the health and safety of the public; and l
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The issuance of this amendment is in accordance with 10 CFR Part 51 t
of the Comission's regulatiors and all applicable requirements have been satisfied.
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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:
l (2) Technical Specifications i
The Technical Specifications contained in Appendix A, as revised through Amendment No. 90, are hereby incorporated into the license.
The licensee shall operate the facility in accordente with thc i
Technical Specifications and the Environmental Protection Plan.
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This license amendment was effective as of July 15, 1988.
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Original signed by:
Gus C. Lainas, Assistant Director i
for Region !! Reactors Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation 1
Attachrent:
Technical Specification Changes j
Date of Issuance: July 22, 1988 I
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DUKE POWER C0t'PANY DOCKET NO. 50-370 McGUIRE NUCLEAR STATION, UNIT 2 AMENDNENT TO FACILITY OPERATING LICENSE I
1 Amendment No. 71 1
License No. NPF-17
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1.
The Nuclear Regulatory Comission (tie 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 (the licensee) dated July 15 and 19,1988, and sucplemented July 21, 1988, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comission's roles and 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 rules and regulations of the Comission; C.
There is reasonabla assurance (1) that the activities authorized by this amendment can be conducted without ondan2ering the health and safety of the public, and (11) 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 wf11 not be inimical to the comon defense and security or to the hvalth and safety of the public; and 1
E.
The issuance of this amenda4nt is in accordance with 10 CFR Part 51 of the Comission's regulations and all applic.ble requirements have been l
satisfied, l
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2.
Accordingly, the license is hereby amended by page changes to the Technical Specifications as indicated in the attachments to this license amendrent, t
and Paragraph 2.0.(2) of Facility Operating License No. NPF-17 is hereby amended to read as follows-I
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(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 71, are hereby inc.orporated into the license, j
The licensee shall operate the facility in accordance with the Techr.ical Specifications and the Environmental Protection Plan.
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3.
This license an.entent was effective as of July 15, 1988.
I FOR THE NUCLEAR REGULATORY COMMISSION r
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Original signed by:
Gus C. Lainas, Assistant Director 4
for Region II Reactors Division of Reactor Projects - I/I!
l Office of Nuclear Reactor Regulation
Attachment:
Technical Specification l
Changes 1
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Date of Issuance:
July 22, 1988 l
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ATTACHMENT TO LICENSE AMENOMENT NO. 90 FACILITY OPERATING LICENSE NO. NPF-9 DOCKET NO. 50-369 AND TO LICENSE AHENDMENT NO. 71 FACILITY OPERATING LICENSE NO. NPF-17 DOCKET NO. 50-370 Replace the following page of the Appendix "A" Technical $pecifications with the enclosed page. The revised page is identified by Arnendment number and contains vertical lines indicating the areas of change.
Amended Page 3/4 8-5
ELECTRICAL POWER SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) 4 I
5)
Verifying that on an ESF actuation test signal, without lowof-offsite power, the diesel generator starts on the auto-start signal and operates on standby for greater than or equal to 5 minutes.
The generator voltage and frequency shall be at least 4160 volts and 57 Hz within 11 seconds after the aute-start signal; the steady-state generator voltage and frequency shall be maintained within 4160 1 420 volts and 60 1 1.2 Hz during this test; l
6)
Simulating a loss-of-offsite power in conjunction with an ESF actuation test signal, and I
a)
Verifying deenergization of the emergency busses and load
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shedding froa the emergency busses; l
b)
Verifying the diesel starts en the auto-start signal, energizes the emergency busses with permanently connected loads within 11 seconds, energizes the auto-connected l
emergency (accident) loads through the load sequencer and J
operates for greater than or equal to 5 minutes while its j
generator is loaded with the emergency loads.
After
)
energization, the steady-state voltage and frequency of i
the emergency busses shall be maintained at 4160 t i
420 volts and 60 1 1.2 Hz during this test; and c)
Verifying that all automatic diesel generator Orips, except engine overspeed, lube oil pressure, generator time over-current and generator differential are automatically bypassed upon loss of voltage on the emergency bus concur-rent with a Safety Injection Actuation signal.
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7)
Operating for one hour at 4000 kW to achieve temperature stabil-ity. Within 5 minutes, restart and p rform Surveillance Requirement 4.8.1.1.2e.6)b).
8)
Verifying the diesel generator operates for at least 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
During the first 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> of this test, the diesel generator shall be loaded to greater than or equal to 4400 kW and during 4
the remaining 22 hoers of this test, the diesel generator shall be loaded to greater than or equal to 4000 kW.
The generator voltage and frequency shall be at least 4160 volts and 57 Hz within 11 seconds after the start signal.
The steady-state generator voltage and frequency shall be maintained within j
4160 1 420 volts and 60 1 1.2 Hz during this test.
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McGUIRE - UNITS 1 and 2 3/4 8-5 Amendment No. 90 (Unit 1) i Amendment No. 71 (Unit 2)