ML17054A704
| ML17054A704 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 05/08/1984 |
| From: | Vassallo D Office of Nuclear Reactor Regulation |
| To: | Niagara Mohawk Power Corp |
| Shared Package | |
| ML17054A705 | List: |
| References | |
| DPR-63-A-061 NUDOCS 8405210483 | |
| Download: ML17054A704 (10) | |
Text
e UNITED STATES t
NUCLEAR REGULATORY COMMISSION WASHINGTOiV,D. C. 20555 NIAGARA MOHAWK POWER CORPORATION DOCKET NO. 50-220 NINE MILE POINT NUCLEAR STATION, UNIT NO.
1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.
61 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 January 30, 1984, 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:
84052l0483 840508 PDR ADOCK 05000220 P
0 I
(4 P 1
(2) Technical S ecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 61, are hereby incorporated in the licens'e.
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:
May 8, 1984 Domenic B. Vassallo, Chief Operating Reactors Branch 5'2 Division of Licensing
ATTACHMENT TO LICENSE AMENDMENT NO.
61 FACILITY OPERATING LICENSE NO.
DPR-63 DOCKET NO. 50-220 Revise the Appendix A Technical Specifications by removing and inserting the following pages:
Existing
~Pa e
194 195 Revised
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194 195 The revised areas are indicated by marginal lines.
TABLE 4.6.2a INSTRUHENTATION THAT INITIATES SCRAH Surveillance Re uirement Parameter (1)
Hanual Scram (2)
High Reactor Pressure
( 3)
High Drywell Pressure (4)
Low Reactor Mater Level (5)
Illgh Mater Level Scram Oischarge Volume (6)
Hain-Steam-Line Isolation Valve Position Sensor Check None None None Once/day None None Instrument Channel Test Once per 3
months Once per month(1)
Once per month(1)
Once per month(1)
Once per month Once per 3
months Instrument Channel Ca 1 ibrat ion None Once ptt 3
months Once pqr 3 months<1)
Once pIl 3
months Once per 3
months Once per operating cycle (7)
High, Radiation Hain-Steam Line Once/shift Once per week Once per 3 months 194 Amendment No.
61
TABLE 4.6. 2a (Cont 'd)
INSTRUMENTATION THAT INITIATES SCRAM 1
Survei 1 1 ance. Re uirement Parameter (8)
Shutdown Position of Reactor Mode Switch (9)
Neutron Flux (a)
IRH (i)
Upscale (ii)
Inoperative (b)
APRM (i)
Upscale (ii)
Inoperative (iii )
Downscale (10) Turbine Stop Val ve Closure Sensor Check Hone (f)
(f)
None Hone I
None None Instrument Channel Test Once during each major refueling outage Once/week Once/week Once/week Once per 3 months Instrument Channel Calibration Hone Once/week Once/week Once/week.
Once per operating cycle (11) Generator Load Rejection None Once per month Once per 3
months
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~,
4 195 Amendment No.
61