ML17056A738
| ML17056A738 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 04/05/1990 |
| From: | Capra R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17056A739 | List: |
| References | |
| NUDOCS 9004130024 | |
| Download: ML17056A738 (10) | |
Text
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UNITED STATES NUCLEAR REGULATORY COMMlSSION WASHINGTON. D. C. 20555 NIAGARA MOHAHK POWER CORPORATION DOCKET NO. 50-220 NINE MILE POINT NUCLEAR STATION UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.
114 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 June 1, 1989, as amended August 8, 1989 and February 20, 1990, 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:
(2)
Technical S ecifications The Technical Specifications contained in Appendices A and 8, as revised through Amendment No. 114, 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 G~~Robert A. Capra, Director Project Directorate I-1 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation Date of Issuance:
April 5, 1990
ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO. 114 TO FACILITY OPERATING LICENSE NO.
DPR-63 DOCKET NO. 50-220 Revise Appendix A as fo11ows:
Remove Pa es 220 223 Insert Pa es 220 223
Table 4.6.2g INSTRUMENTATION THAT INITIATES CONTROL ROD WITHDRAWAL BLOCK Surveillance Re uirement Parameter (1)
- a. Detector Not in Startup Position
- b. Inoperative
- c. Upscale Sensor Check N/A N/A N/A Instrument Channel Test (g)
(g)
(g)
Instrument Channel Calibration N/A N/A (g)
(2)
- a. Detector not in Startup Position
- b. Inoperative c.
Downscale
- d. Upscale N/A N/A N/A N/A (g)
(g)
(g)
(g)
N/A N/A (g)
(g) 7252G 220 Amendment No.
114
NOTES FOR TABLES 3.6.2 and 4.6.2 (a)
No more than one of the four SRH inputs to the single trip system shall be bypassed.
(b)
No more than one of the four IRH inputs to each instrument channel shall be bypassed.
These signals may be bypassed when the APRH's are onscale.
(c)
No more than one of the four APRH inputs to each instrument channel shall be bypassed provided that the APRH in the other instrument channel in the same core quadrant is not bypassed.
No more than two C or D level LpRH inputs to an APRM shall be bypassed and only four LPRH inputs to only one APRM shall be bypassed in order for the APRH to be considered operable.
In the Run mode of operation, bypass of two chambers from one radial core location in any one APRH shall cause that APRH to be considered inoperative.
A Travelling In-Core Probe (TIP) chamber may be used as a substitute APRH input if the TIP is positioned in close proximity to the failed LPRH it is replacing.
If one APRH in a quadrant is bypassed and meets all requirements for operability with the exception of the requirement of at least one operable chamber at each radial location, it may be returned to service and the other APRH in that quadrant may be removed from service for test and/or calibration only if no control rod is withdrawn during the calibration and/or test.
(d)
May be bypassed in the startup and refuel positions of the reactor mode switch when the IRH's are onscale.
(e)
This function may be bypassed when the count rate is 100 cps.
(f)
One sensor provides input to each of two instrument channels.
Each instrument channel is in a separate trip system.
(g)
Calibrate and/or test prior to startup and normal shutdown.
Thereafter test once per week until no longer required'h)
The actuation of either or both trip systems will result in a rod block.
Amendment No.
114 223