ML20094R740
| ML20094R740 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 11/29/1995 |
| From: | Mckee P NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20094R744 | List: |
| References | |
| NUDOCS 9512050146 | |
| Download: ML20094R740 (4) | |
Text
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UNITED STATES p
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NUCLEAR REGULATORY COMMISSION o
WASHINGTON, D.C. 20066-4001
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NORTHEAST NUCLEAR ENERGY COMPANY. ET AL.
DOCKET NO. 50-423 tiU LSTONE NUCLEAR POWER STATION. UNIT NO. 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.121 License No. NPF-49 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Northeast Nuclear Energy Company, et al. (the licensee) dated June 8,1995, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I 1
B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and 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 Commission's regulations; 3
1 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.
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l 9512050146 951129 PDR ADOCK 05000423 p
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Accordingly, the license is amended by 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-49 is hereby amended to read as follows:
(2)
Technical Specifications i
l The Technical Specifications contained in Appendix A, as revised through Amendment No.121
, and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto are hereby incorporated in 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 the date of its issuance, to be implemented within 60 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Phillip F McKee, Director Project Directorate I-3 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
November 29, 1995 4
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ATTACHMENT TO LICENSE AMENDMENT NO.121 FACILITY OPERATING LICENSE NO. NPF-49 DOCKET NO. 50-423 Replace the following pages of the Appendix A, Technical Specifications, with 4
the attached pages. The revised pages are identified by amendment number and contain vertical lines indicating the areas of change.
j Remove Insert 4
Xi Xi 3/4 5-2 3/4 5-2 3/4 8-23 4
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BDil LIMITING Col 51TIONS FOR OPERATION AIS SURVEILLANCE REQUIREMENTS SECTION EAfiE 3/4.8 ELECTRICAL POWER SYSTEMS 3/4.8.1 A.C. SOURCES Operating 3/4 8-1 TABLE 4.8-1 DIESEL GENERATOR TEST SCHEDULE...........
3/4 8-9 Shutdown......................
3/4 8-10 3/4.8.2 D.C. SOURCES Operating 3/4 8-11 TABLE 4.8-2a BATTERY SURVEILLANCE REQUIRENENTS 3/4 8-13 TABLE 4.8-2b BATTERY CHARGER CAPACITY..............
3/4 8-14 Shutdown......................
3/4 8-15 3/4.8.3 ONSITE POWER DISTRIBUTION Operating 3/4 8-16 Shutdown......................
3/4 8-18 3/4.8.4 ELECTRICAL EQUIPMENT PROTECTIVE DEVICES Containment Penetration Conductor Overcurrent Protective Devices.................
3/4 8-19 t
Notor-Operated Valves Thermal Overload Protection 3/4 8-21 1
Notor-Operated Valves Thermal Overload Protection
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Not Bypassed....................
3/4 8-22 3/4.9 REFUELING OPERATIONS 3/4.9.1 BORON CONCENTRATION 3/4 9-1 3/4.9.2 INSTRUNENTATION 3/4 9-2 l
3/4.9.3 DECAY TIME,....................
3/4 9-3 l
3/4.9.4 CONTAlletENT BUILDING PENETRATIONS 3/4 9-4 i-3/4.9.5 C0ftt0NICATIONS...................
3/4 9-5
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ENERGENCY CORE C00LI M SYSTEMS SURVEILLANCE REQUIRENENTS (Continued) c.
At least once per 31 days when the RCS pressure is above 1000 psig by verifying that the associated circuit breakers are locked in a deenergized position or removed.
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