ML17056B691
| ML17056B691 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 02/27/1992 |
| From: | Capra R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17056B692 | List: |
| References | |
| NUDOCS 9203040230 | |
| Download: ML17056B691 (8) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 NIAGARA MOHAWK POWER CORPORATION DOCKET NO. 50-410 NINE MILE POINT NUCLEAR STATION UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 36 License No.
NPF-69 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Niagara Mohawk Power Corporation (the licensee) dated November 6,
- 1991, as supplemented December 5,
- 1991, 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 1;
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.
NPF-69 is hereby amended to read as follows:
5'203040230
- 920227, i
PDR ADOCK 050004iO P
PDR~
(2)
Technical S ecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, both of which are attached
- hereto, as revised through Amendment No. 36 are hereby incorporated into this license.
Niagara mohawk Power Corporation shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective.as of the date of its issuance to be implemented within 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION Rc~M C2 Robert A. Capra, Director Project Directorate I-I Division of Reactor Projects
. I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
February 27, 1992
ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO.
36 TO FACILITY OPERATING LICENSE NO. NPF-69 DOCKET NO. 50-410 Revise Appendix A as follows:
Remove Pa e
3/4 5-5 Insert Pa e
3/4 5-5
EMERGENCY CORE COOLING SYSTEMS SURVEILLANCE RE UIREMENTS 4.5.1 (Continued) e.
For the ADS by:
At least once per 31 days, performing a CHANNEL FUNCTIONAL TEST of the accumulator backup compressed gas system, low-pressure alarm system.
2.
At least once per 18 months:
a)
Performing a system functional test which includes simulated automatic actuation of the system throughout its emergency operating
- sequence, excluding actual valve actuation.
b)
Manually opening each ADS valve when the reactor steam dome pressure is greater than or equal to 950 psig* and observing that either:
1)
The SRV discharge acoustic monitoring system responds accordingly, or 2)
The control valve or bypass valve responds accordingly, or 3) 4)
There is a corresponding change in the measured steam flow, or The SRV discharge line temperature monitoring system responds accordingly.
c)
Performing a CHANNEL CALIBRATION of the accumulator backup compressed gas system, low-pressure alarm system, and verifying an alarm setpoint of 163.5 +3.2, -3.2 psig on decreasing pressure.
d)
Performing a leak rate test for ADS SRV pneumatic operators by pressurizing each ADS accumulator at 178 psig (supply header 'high pressure alarm) up to its supply header isolation check valve with the SRV in the open position.
Total leakage rate for each SRV shall not exceed 0.5 SCFH for the SRV actuated by either of the ADS solenoids.
The provisions of Specification 4.0.4 are not applicable provided the surveillance is performed within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after reactor steam pressure is adequate to perform the test.
NINE MILE POINT UNIT 2 3/4 5-5 Amendment No.
36