ML17054C010
| ML17054C010 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point |
| Issue date: | 11/08/1985 |
| From: | Vassallo D Office of Nuclear Reactor Regulation |
| To: | Niagara Mohawk Power Corp |
| Shared Package | |
| ML17054C011 | List: |
| References | |
| DPR-63-A-075 NUDOCS 8511200088 | |
| Download: ML17054C010 (10) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION, WASHINGTON, D. C. 20555 NJAGARA MOHAWK POWER CORPORATJON DOCKET NO. 50-220 NJNE MJLE POJNT NUCLEAR STATJON UNJT NO.
1 AMENDMENT TO FACJLJTY OPERATJNG LJCENSE Amendment No. 75 License No.
DPR-63 l.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Niagara Mohawk Power Corporation (the licensee) dated November 3, 1985, as supplemented and clarified by letter dated November 5, 1985, 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 J; 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 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 Commission's regulations and all applicable requirements have been satisfied.
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.
DPR-63 is hereby amended to read as follows:
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(2) Technical S ecifications The Technical Specifications contained in Appendix A, as.
revised through Amendment No.
75, are hereby incorporated in the license.
The licensee 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 COMMJSSJON Domenic B. Vassallo, Chief Operating Reactors Branch ¹2 Division of Licensing
Attachment:
Changes to the technical Specifications Date of Jssuance:
November 8,
1985
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ATTACHMENT TO LJCENSE AMENDMENT NO. 75 FACJLJTY OPERATJNG LJCENS'E NO.
DPR-63 DOCKET NO. 50-220 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages.
The revised areas are indicated by marginal lines.
Existin Pa e
48 Revised Pa e
47
I
LNITING CONDITION FOR OPERATION 3.1.3 EMERGENCY COOLING SYSTEH
~tt Applies to the operating status of the emergency cooling system.
Objective:
To assure the capability of the emergency cooling system to cool the reactor coolant in the event the noraal reactor heat sink is not ava i 1 able.
~Si it t
a.
During pmer operating conditions and whenever the reactor coolant temperature is greater than 212 F, both emergency cooling system shaTT be operabTe except as specified in 3.1.3.b and c.
b.
During the remainder of Cycle 8 with one emergency cooling system inoperable, Specification 3.1.3a shall be considered fulfilled, provided the additional surveillance required in 4.1.3.f is performed.
During Cycle 9 and subsequent cycles. if one emergency cooling system becomes inoperable, Specification 3.1.3.a shall be considered fulfilled, provided that the inoperable system is returned to an operable condition within 7 days and the additional surveillance required in 4.1.3.f is performed.
SVRYEIl.LANCE REqUIREHENT 4.1. 3 EMERGENCY COOLING SYSTBf tt ttt Applies to periodic testing requirements for the emergency cooling system.
Objective:
To assure the capability of the emergency cooling system for cooling of the reactor coolant.
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The emergency cooling systea surveillance shall be performed as indicated below:
a.
At least once ever five ears The systea heat removal capability shall be determined.
b.
At least once dail The shell side water level and makeup tank water 'level shall be checked.
c.
At least once r month-The makeup tank level control valve shall be nenually opened and closed.
'mendment Ho.
75 47
LIMITINGCONDITION FOR OPERATIQH Mater tanks.
e.
During P~r Operating Conditions, each emergency cooling system high point vent to torus shall be operable.
1.
Mith a vent path for one emergency cool ing system
)noperable, restore the vent path to an operable condition vfthin 30 days.
2.
Mith vent paths for both emergency cool ing systeas inoperable, restore one vent path to an operable condition vith 14 days and both vent paths within 30 days f.
If Specification 3.1.3.a, b, c, d
or e are not met, a normal orderly shut@ca shall be initiated within one hour, and the reactor shall be in the cold shutdown conditions v)thin ten hours.
f d.
)eke up mter shall be available from the tm gravity feed aakeup d.
e.
SURYEILLANCE REgUIREHENT At least once each shift-The area temperature shall be checked.
Durin each major refuel in outa Autoaatic actuation and functional system testing shall be performed during each amor refueling outage and Aenever major repairs are completed on the system.
Each emergency cooling vent path shall be deaonstrated operable by cycling each peer-operated valve (05-01R, 05-11, 05-12,05-04R, 05-05 and 05-07) in the vent path through one ccnplete cycle of full travel and verifying that all manual valves are in the oper position.
Survei11ance vith an Ino rable S stem During Cycle 8 with one of the emergency cooling systems inoperable, the level control valve and motor operated isolat)on valve in the operable system shall be demonstrated to be operable mekly.
Amendment No.
75 During Cycle 9 and subsequent cycles,.
Ken one of the emergency cooling systems is inoperable, the level control valve and the motor-oper'ated isolation valve in the operable system shall be demonstrated to be operable iaaediately and daily thereafter.
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