ML19260D536
| ML19260D536 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 01/17/1980 |
| From: | Ziemann D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19260D534 | List: |
| References | |
| NUDOCS 8002110351 | |
| Download: ML19260D536 (5) | |
Text
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CONNECTICUT LIGHT AND POWER COMPANY THE HARTFORD ELECTRIC LIGHT COMPANY WESTERN MASSACHUSETTS ELECTRIC COMPANY NORTHEAST NUCLEAR ENERGY COMPANY DOCKET NO. 50-245 MILLSTONE NUCLEAR POWER STATION, UNIT N0.1 AMENDMENT TO PI'.0 VISIONAL OPERATING LICENSE Amendment No. 65 License No. DPR-21 1.
The Nuclear Regulatory Comission (the Comission) has fcund that:
A.
The application for amendment by Connecticut Light and Power Company, The Hartford Electric Light Company, Western Massachusetts Electric Company, and Northeast Nuclear Energy Company (the licensees) dated January 9,1980, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Cconission's rules and regulatiros set forth in 10 CFR Chapter I; B.
The facility will operate in confonnity with the application, the provisions of the Act, and the rules and regulations of the Comission; 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 Commission's regulations; 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 Comission's regulations and all applicable requirements have been satisfieu.
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r B002110) 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment and paragraph 3.8 of Provisional Operating License No.
DPR-21 is hereby amended to read as follows:
B.
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 65, are hereby incorporated in the license.
Northeast Nuclear Energy Company shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as' of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION iu m V
DennisL.Ziemann,hhief Operating Reactors Branch #2 Division of Operating Reactors
Attachment:
Changes to the Techr.ical Specifications Date of Issuance:
January 17, 1980 j
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ATTACHMENT TO LICENSE AMENDMENT NO. 65 PROVISIONAL OPERATING LICENSE NO. DPR-21 DOCKET NO. 50-245 Replace the following page of the Appendix "A" Technical Specifications with the enclosed page.
The revised page contains the captioned amendment number and a vertical line indicating the area of change.
PAGE 3/4 5-8 Overieaf page 3/4 5-7 is provided for convenience.
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LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENT 2.
From and after the dite that one of the 2.
When it is determined that one safety /
three relief / safety valves of the auto-relief valve of the automatic pressure natic pressure relief subsystem is made or relief subsystem is inoperable the found to be inoperable when the reactor is actuation logic of the retaining APR pressurized above PO psig with irradiated valves and FWC! subsystem shall be fuel in the reactor vessel, reactor opera-demonstrated to be operable inmediately tion is permissible only durino the and daily thereafter.
succeeding seven days unless repairs are made and provided that during such time E. Surveillance of the Isolation Condenser l
the remaining automatic pressure relief System shall be performed as follows:
valves, FWCl subsystem and gas turbine generator are operable.
1.
Isolation Condender System Testing:
3.
If the requirements of 3.5.D cannot be
- a. The shell side water level and met, an orderly reactor shutdown shall temperature shall be checked be initiated and the reactor shall be
- daily, in a cold shutdown condition within 24 hou rs.
E. Isolation Condenser System 1.
Whenever the reactor pressure is greater than 90 psig and irrediated fuel is in the reactor vessel, the isolation con-denser shall be operable except as specified in 3.5.E.2 and the shell '
side water level shall be greater than 66 inches.
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A encment No. 16, 61 3/4 5-7
LiftillHG LONDITION FOR OPERATION SURVEILLANCE REQlllREHEHI 2.
From and af ter the date that the Isola-b.
Stra?sted automatic actuation and tion Condenser is made or found to be inoperable, for any reason, power functional system testintj shall be operation shall be restricted to a perfonned during each refueling maximum of 40% of full power, i.e.,
outage or whenever major repairs (804 MWth) within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> until are cumpleted on the system.
such time the Isolation Condenser c.
The system heat removal capability is returned to service.
shall be determined once every five years, d,
Calibrate vent line radiation 3.
If the requirements of 3.5.E cannot be monitors qtorterly.
met, an orderly shutdnwn shall be initiated
.md the reactnr shall be in a cold 2.
When it is determined that the isolation shutdnwn condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
condenser system is inoperable the F.
Minimum Core _a_nd Containment Cooling System FWCI subsystem and gas turbine generator Availability, shall be demonstrated to be operable innediately and daily thereaf ter.
1.
Except as specified in 3.5.F.2, 3.5.F.3, F.
Surveillance of Core and Containment Cooling 3.5.I'.7 and 3.5.F.8 below, both emer-System gency pnwer sources shall be operable whenever irradiated fuel is in the 1.
The surveillance requirements for normal reactor.
operation are in Section 3.9.
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.'T 5-8 Amendment No. PI, %, 65