ML20108B976
| ML20108B976 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 02/12/1985 |
| From: | John Miller Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20108B979 | List: |
| References | |
| TAC-56458, NUDOCS 8503070536 | |
| Download: ML20108B976 (5) | |
Text
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8 NUCLEAR REGULATORY COMMISSION o
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l NORTHEAST NUCLEAR ENERGY COMPANY THE CONNECTICUT LIGHT AND POWER COMPANY THE WESTERN MASSACHUSETTS ELECTRIC COMPANY DOCKET NO. 50-336 MILLSTONE NUCLEAR POWER STATION, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 98 License No. DPR-65 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Northeast Nuclear Energy Company, etal.(thelicensee),datedDecember 10, 1984 complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comission's rules and regulations 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 Comission; i
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; 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 satisfied.
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8503070536 850212 PDR ADOCK 05000336 P
2.
Accordingly, the license is amended by changes to t and paragraph 2.C.(2) of Facility Operating License No. DPR-65 is h
- ent, amended to read as follows:
j-(2) Tech'nical Specifications The Technical Specifications contained in Appendices A and 8 revised through Amendment No. 98, are hereby incorporated in the l
, as Ifcense.
the Technical Specifications.The licensee shall operate the facility in accord l
l 3.
This license amendment is effective as of the date of issuance FOR THE NUCLEAR REGULATORY COMMISSION
^
mes R. Miller, Chief Operating Reactors Branch #3 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: February 12, 1985 3
ATTACHMENT TO LICENSE AMENDMENT N0.98 FACILITY OPERATING LICENSE NO. OPR-65 DOCKET NO. 50-336 Remove and replace the following page of the Appendix A Technical Specifica-tions with the enclosed page. The revised page is identified by amendment number and contains vertical lines indicating the area of change. The corre-sponding ove'rleaf. page is provided to maintain document completeness.
Remove-Insert 3/4 9-4 3/4 9-4 i
4 L
l REFUELING OPERATIONS QNTAINMENT PENETRATIONS LIMITING CONDITION FOR OPERATION The containment penetrations shall be in the following status:
3.9.4 The equipment door closed and held in place by a minimum of I
four bolts or the outage equipment door is installed, a.
A minimum of.one door in each airlock is closed, and-b.
Each penetration providing direct access from the containment c.
atmosphere to the outside atmosphere shall be either:-
4
. Closed by.an isolation valve, blind flange, manual 1.
valve, or special device, or Be capable of being closed by an OPERABLE automatic 2.
containment purge valve.
During CORE ALTERATIONS or movement of irradiated fuel APPLICABILITY:
within the containment.
ACTION:
With the requirements of the above specification not. satisfied, immediately-suspend all operations involving CORE ALTERATIONS or movement of irradiated-fuel in~ the containment.
SURVEILLANCE REQUIREMENTS Each of the above required containment penetrations shall be determined 4.9.4 to be either in its isolated condition or capable of being' closed by an 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 OPERABLE automatic containment of and'at least once per 31 days during CORE ALTERATIONS or: movement of irradiated fuel in the containment by:
i Verifying the penetrations are in'their isolated condition, or a.
l Testing the containment purge _ valves per the applicable portions -
'b.
[
of Specification 4.6.3.1.2.
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_,.7 MILLSTONE - UNITc2; 3/4 9-4
- AmendmentNo.pp,gg,98-p.
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i-REFUELING OPERATIONS DECAY TIME LIMITING CONDITION FOR OPERATION 3.9.3 The reactor shall be subcritical 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, i
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.
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m MILLSTONE - UNIT 2 3/4 9-3 I,l v
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