ML20210K802
| ML20210K802 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire  |
| Issue date: | 04/17/1986 |
| From: | Youngblood B Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20210K805 | List: |
| References | |
| NUDOCS 8604290071 | |
| Download: ML20210K802 (8) | |
Text
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UNITED STATES 6
8 NUCLEAR REGULATORY COMMISSION o
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CASHINGTEN D. C. 20555
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DUKE POWER COMPANY DOCKET NC. 50-369 McGUIRE NUCLEAR STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 55 License No. NPF-9 1.
The Nuclear Regulatory Comission (the Comission) has found that:
l 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-(the licensee) dated April 1,1985, and supplemented October 14, 1985, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comis-sion's regulations as set forth in 10 CFR Chapter I; i
B.
The facility will operate in conformity with the application, as amended, the provisions of the Act, and the regulations of the Comission; 1
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 I
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 comon 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 renuirements have been satisfied.
t 8604290071 860417 PDR ADOCK 05000369 i
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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 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.55, are hereby incorporated into the license.
The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
l 3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION bN
- L fq,B.J.Youngb?
irector PWR Project L
. ate #4 Division of Pw.
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Attachment:
Technical Specification l
Changes Date of Issuance: April 17, 1986 j
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UNITED STATES 8
NUCLEAR REGULATORY COMMISSION o
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DUKE POWER COMPANY DOCKET NO. 50-370 McGUIRE NUCLEAR STATION, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 36 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 (the licensee) dated April 1,1985, and supplemented October 14, 1985, complies with the standards and requirements of the. Atomic Energy Act of 1954, as amended (the Act) and the Comis-sion's regulations as set forth in 10 CFR Chapter I; B.
The facility will operate in confonnity 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 issuance of this amendment will not be inimical to the comon 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 Comission's regulations and all applicable requirements have been satisfied.
1 4
2.
Accordingly, the license is hereby amended by page cnanges 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 i
The Technical Specifications contained in Appendix A, as revised through Amendment No.36, are hereby incorporated into the 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 M??- k' W f
f,3 B. J. Youngblood, Director PWR Project Directorate #4 Division of PWR Licensing-A
Attachment:
Technical Specification Changes Date of Issuance: April 17, 1986 1
ATTACHMENT TO LICENSE AMENDMENT NO. 55 FACILITY OPERATING LICENSE NO. NPF-9 DOCKET NO. 50-369 AND TO LICENSE AMENDMENT N0. 36 FACILITY OPERATING LICENSE NO. NPF-17 DOCKET NO. 50-370 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. The corresponding over-j leaf pages are also provided to maintain document completeness.
Amended Overleaf Page Page 3/4 7-32 3/4 7-31 B 3/4 7-6 1
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a
PLANT SYSTEMS SURVEILLANCE RE00lREMENTS (Continued)-
b.
Stored sources not in use - Each sealed source and fission detector shall be t.ested prior to use or transfer to another licensee unless tested within the previous 6 months.
Sealed sources and fission detectors transferred without a certificate indicating the last test i
date shall be tested prior to being placed into use; and Startup socrces and fission detectors - Each sealed startup source c.
and fission detector shall be tested within 31 days prior to being subjected to core flux or installed in the core and following repair j
or maintenance to the source.
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4.7.9.3 Reports - A report shall be prepared and submitted to the Commission on an annual basis if sealed source or fission detector leakage tests reveal the presence of greater than or equal to 0.005 microcurie of removable contamination.
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McGUIRE - UNITS 1 and 2 3/4 7 31 l
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PLANT SYSTEMS 3/4.7.10 FIRE SUPPRESSION SYSTEMS FIRE SUPPRESSION WATER SYSTEM LIMITING CONDITION FOR OPERATION 3.7.10.1 The Fire Suppression Water System shall be OPERABLE with:
At least two fire suppression pumps (either A and C or 8 and C),
l a.
each with a capacity of 2500 gpm, with their discharge aligned to the fire suppression header; and b.
An OPERABLE flow path capable of taking suction from Lake Norman and transferring the water through distribution piping with OPERABLE sectionalizing control or isolation valves to the yard hydrant curb valves, the last valve ahead of the water flow alarm device on each sprinkler or hose standpipe, and the last valve ahead of the deluge valve on each Deluge or Spray System required to be OPERABLE per Specifications 3.7.10.2 and 3.7.10.4.
APPLICABILITY: At all times.
ACTION:
With one of the above required pump and/or one water supply inoperable, a.
restore the inoperable equipment to OPERABLE status within 7 days or provide an alternate backup pump or supply.
The provisions of Specifi-cations 3.0.3 and 3.0.4 are not applicable.
b.
With the Fire Suppression Water System otherwise inoperable establish a backup Fire Suppression Water System within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
I McGUIRE - UNITS 1 and 2 3/4 7-32 Amendment No.55 (Unit 1)
Amendment No.36 (Unit 2)
BASES 1
SNUBBERS (Continued)
The service life of a snubber is established via manufacturer input and information through consideration of the snubber service conditions and associated installation and maintenance records (newly installed snubber, seal replaced, spring replaced, in high radiation area, in high temperature area, etc...).
The requirement to monitor the snubber service life is included to ensure that the snubbers periodically undergo a performance evaluation in view of their age and operating conditions.
These records will provide statistical bases for future consideration of snubber service life.
The requirements for the maintenance of records and the snubber service life review not intended to affect plant operation.
3/4.7.9 SEALED SOURCE CONTAMINATION
,The limitations on removable contamination for sources requiring leak testing, including alpha emitters, is based on 10 CFR 70.39(c) limits for plutonium.
This limitation will ensure that leakage from Byproduct, Source, and Special Nuclear Material sources will not exceed allowable intake values.
Sealed sources are classified into three groups according to their use, with Surveiilance Requirements commensurate with the probability of damage to a source in that group.
Those sources which are frequently handled are required to be tested more often than those which are not.
Sealed sources which are continuously enclosed within a shielded mechanism (i.e., sealed sources within radiation monitoring or boron measuring devices) are considered to be stored and need not be tested unless they are removed from the shielded mechanism.
3/4.7.10 FIRE SUPPRESSION SYSTEMS The OPERABILITY of the Fire Suppression Systems ensures that adequate fire suppression capability is available to confine and extinguish fires occurring in any portion of the facility where safety related equipment is located. The Fire Suppression System consists of the water system, spray, and/or sprinklers, Halon, and fire hose stations. The collective capability of the Fire Suppression Systems is adequate to minimize potential damage to safety related equipment and is a major element in the facility fire protection program.
In the event that portions of the Fire Suppression Systems are inoperable, alternate backup fire-fighting equipment is required to be made available in the affected areas until the inoperable equipment is restored to service.
When the inoperable fire-fighting equipment is intended for use as a backup means of fire suppression, a longer period of time is allowed to provide an alternate means of fire fighting than if the inoperable equipment is the primary means of fire suppression.
For McGuire Nuclear Station pumps A and B serve as a backup for e,ach other.
Pump C is located separately with independ-ent dedicated power supply.
McGuire - UNITS 1 and 2 B 3/4 7-6 Amendment No.55(Unit 1)
Amendment No.36(Unit 2)
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