ML17054A448
| ML17054A448 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 02/02/1984 |
| From: | Vassallo D Office of Nuclear Reactor Regulation |
| To: | Niagara Mohawk Power Corp |
| Shared Package | |
| ML17054A449 | List: |
| References | |
| DPR-63-A-055-01 NUDOCS 8402150529 | |
| Download: ML17054A448 (10) | |
Text
~
~g8 Rfgy
~ ~
~'
I
~o C) ky
~O
++*++
t UNITED STATES t
NUCLEAR REGULATORY COMMISSION WASHINGTON, O. C. 20555 NIAGARA MOHAWK POWER CORPORATION DOCKET NO. 50-220 NINE MILE POINT NUCLEAR STATION, UNIT NO. I AMENDMENT TO FACILITY OPERATING LICENSE Amendment Ho.
55 License No.
DPR-63 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Niagara Mohawk Power Corporation (the licensee) dated May 20,
- 1980, 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; 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:
.8402150529 840202
DR. ADQCK'05000220 P
" 'a'=. PDR
~g
~ ~
I j
I t
I
(2) Technical S ecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 55, 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 COMMISSION
Attachment:
Changes'to the Technical Specifications Date of Issuance:
February 2, 1984 Domenic B. Yassallo, Chief Operating Reactors Branch ¹2 Division of Licensing
~ ~
ATTACHMENT TO LICENSE AMENDMENT NO.
55 FACILITY OPERATING LICENSE NO.
DPR-63 DOCKET NO. 50-220 Revise the Appendix A Technical Specifications bv removinq pages 2 and 25 and inserting revised pages 2 and 25.
The revised areas are indicated by Marginal lines.
~ '
l.2 ~O>erable A system, subsystem,
- train, component or device shall be operable when it is capable of performing its specified'u>>etio<<(s).
Implicit in this definition shall be the assumption that all necessary attendant instrumentation,.
- controls, normal and emergency electrical power sources, except as noted in 3.Q, cooling or seal water, l<<brication or other auxiliary equipment that are required for the system, subsystem,
- train, component or device to perform its function(s) are also capable of performing their related support function(s).
l.3 ~Oera ala Operating means that a system or component is performing its required functions in its required manner.
le4 Protective Instrumentation Lo ic Definitions Instrument Channel An instrument channel means an arrangement of a sensor and auxiliary equipment required to generate and transmit to a trip system a single trip signal related to the plant parameter monitored by that instrument channel.
A trip system means an arrangement of instrument channel trip signals and auxiliary equipment required to initiate action to accomplish a protective trip function.
A trip system may require one or more instrument channel trip signals related to one or more plant parameters in order to initiate trip system action.
Initiation of protective action may require the tripping of a single trip system or the coincident tripping of two trip systems.
1.5 Sensor Check A se>>sor check is a q<<alitative determination of acceptable operability by observation of sensor behavior during operation.
This determinatin shall include, where possible, comparison of the sensor with other independent sensors measuring the same variable.
le6 Instr<<ment Channel Test Instrument channel test means injection of a simulated signal into the channel to verify its proper response i ncl<<ding, where applicable, alarm and/or trip initiating action.
3.0 LINITIHG CONDITIONS FOR OPERATION AND SURVEII,LANCE RFgUIREHEHTS OPERAB I LITY RENDU IREtlENTS
<!hen a system, subsystem,
- train, component or device is determined to be inoperable solely because its emergency power source is inoperable, or solely because its normal power source is inoperable, it may be considered operable for the purpose of satisfying the requirements of its applicable Limiting Condition for Operation, provided:
(I) its corresponding normal or emergency power source is operable; and (2) all of its redundant system(s),
subsystem(s),
train(s),
component(s) and device(s) are operable, or likewise satisfy the requirements of this specification.
Unless both conditions (I) and (2) are satisfied, the unit shall be placed in a condition stated in the individual specification.
In the event a Limiting Condition for Operation and/or associated surveillance requirements cannot be satisfi g
because of circumstances in excess of those addressed in the specification, the unit shall be placed in a condition consiste>>t with the individual specification unless corrective measures are completed that permit op< ration. under the permissible surveillance requirements for the specified time interval as measured from initial discovery or until the reactor is placed in an operational condition in which the specification is not applicable.
3.1.0 FUEL CLADDING A)
GENERAL APPLICABILITY Applies to the power level regulation, control rod system, liquid poison system, emergency cooling
- system, and core spray system.
LCO's for the minimum allowable circuits corresponding to the LS3 settings are included in the Reactor Protection System LCO (3.6.2).
B)
GEHERAL OBJECTIVE LIHITING CONDITIONS FOR OPERATION To define the lowest functional capability or performance level of the systems and associated components which will assure tl>e integrity of the fuel clad 'ing as a barrier against the release of radioactivity.
SURVEILLANCE REQUIREHENTS To define the tests or inspections "equired to assure the functional capability or performance level of the requi red systems or components.
25
IM