ML20073T300
| ML20073T300 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 05/05/1983 |
| From: | Clark R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20073T301 | List: |
| References | |
| TAC-51419, NUDOCS 8305110224 | |
| Download: ML20073T300 (5) | |
Text
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UNITED STATES 0
[hs.q[/'#'[.,p, NUCLEAR FiEGULA1 ORY COMMISSION
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WASHINGTorJ. D. C. 205S5
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t,gv NORTHEAST NUCLEAR ENERGY COMPANY THE CONNECTICUT LIGHT AND POWER COMPANY.
THE HARTFORD ELECTRIC LIGHT COMPANY THE WESTERN MASSACHUSETTS ELECTRIC COMPANY DOCKET NO. 50-336 MILLSTONE NUCLEAR POWER STATION, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 85 License No. DPR-65 1.
The Nuclear Regulatory Commission (the Commission)-has found that:
A.
The application for amendment b Company, et al. (the licensee) y Northeast Nuclear Energy dated April 25,.1983, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regula*tions set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized
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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 l
defense and security or to the health and safety of the public; and l
E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements -
have been satisfied.
I t'305110224 830505 PDR ADOCK 05000336 P
5 2-2.
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. OPR-65 is hereby amended to read as follows:
(2)
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 85 are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective on the date of issuance.
FORTHENUCLEARREGULATbRYCOMMISSION l'
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y-Robert A. Clark, Chief Operating Reactors Branch #3 Division of Licensing
Attachment:
Changes to the' Technical Specifications Date of Issuance:
May 5, 1983 e
ATTACHMENT TO LICENSE AMENDMENT NO.85 FACILITY OPERATING LICENSE NO. DPR-65 DOCKET NO. 50-336 Remove and replace the following page of the Appendix A Technical Specifications with the enclosed page.
The revised page is identi-fied by' amendment number and qontains vertical lines indicating the area of change.
The corresponding overleaf page is provided to main-tain document completeness.
Remove Insert 3/4 9 4 3/4 g-4 h
t 4
j e
4 4-e'
REFUELING OPERATIONS DECAY TIME LIMITING CONDITION FOR OPERATION 3.9.3 The reactor shall be suber.itical for a minimum of 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> prior to movement of irradiated fuel in the reactor pressure vessel.
APPLICABILITY:
MODE 6.
ACTION:
With the reactor subcritical for less than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, suspend all opera-tions involving movement of irradiated fuel in the reactor pressure vessel.
SURVEILLANCE REQUIREMENTS 4.9.3 The reactor shall be determined to have been subcritical for at least 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> by verification of the date and time of subcriticality prior to movement of irradiated fuel in the reactor pressure vessel.
l MILLSTONE - UNIT 2 3/4 9-3
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9
REFUE'.IflG OPERATIO!!S C0!;TAlfiMENT PENETRATIONS LItilTING C0fiDITI0ti FOR OPERATI0fi 3.9.4 The containment penetrations shall be in the following status:
a.
The equipment door closed and held in place by a minimum of four bolts,*
I b.
A minimum of one door in each airlock is closed, and c.
Each penetration providing direct access from the containment atmosphere to the outside atmosphere shall be either:
1.
Closed by an isolation valve, blind flange, manual valve, or special device, or i
Be capable of being closed by an OPERABLE automatic 2.
containment purge valve.
APPLICABILITY:
During CORE ALTERATIONS or movemeht of irradiated fuel withia the containment.
ACTI0ti:
With the requirements of the above specification not satisfied, immediately suspend all operations involving CORE ALTERATIONS or movement of irradiated fuel in the containment.
SUR','EILLANCE REQUIREMEf1TS 4.9.4 Each of the above required contaimnent penetrations shall be determined to be either in its isolated condition or capable of being closed by an OPERA 3LE automatic containment purge valve within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> prior to the start of and at least once per 31 days during CORE ALTERATIONS or movement of irradiated fuel in the containment by:
a.
Verifying the penetrations are in their isolated condition, or b.
Testing the containment purge valves per the applicable portions of Specification 4.6.3.1.2.
- For the Cycle 6 refueling only, during fuel movement or core alterations, a temporary equipment door may be substituted for the equipment hatch. door to facilitate steam generator maintenance activities.
l filLLST0fiE - UNIT 2 3/4 9-4 Amendment No. 60, 85 s