ML17059B155
| ML17059B155 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 06/10/1996 |
| From: | Jeffrey Mitchell NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML17059B156 | List: |
| References | |
| NUDOCS 9606180560 | |
| Download: ML17059B155 (12) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 NIAGARA MOHAWK POWER CORPORATION DOCKET NO. 50-410 NINE MILE POINT NUCLEAR STATION UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.
72 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 January 25,
- 1996, 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:
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(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.
72 are hereby incorporated into this license.
Niagara Hohawk 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 COHHISSION p~c.~ ~
Jocelyn A. Hitchell, Acting Director Project Directorate I-1 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
June 10, 1996
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ATTACHMENT TO LICENSE AMENOMENT AMENDMENT NO.
72 TO FACILITY OPERATING LICENSE NO. NPF-69 DOCKET NO. 50-410 Revise Appendix A as follows:
Remove Pa es 3/4 3-33 3/4 3-43 3/4 3-44 Insert Pa es 3/4 3-33 3/4'-43*
3/4 3-44
- Overleaf page
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EIVIER EN Y RE LIN Y TEIVI A T ATI N IN TR IVIENTATI N TABLE N TATION When the system is required to be OPERABLE per Specification 3.5.2 or 3.5.3.
(a)
Required when the associated diesel generator is required to be OPERABLE.
When a channel is placed in an inoperable status solely for performance of required surveillances, entry into associated Conditions and required ACTIONS may be delayed for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> provided the associated function or the redundant function maintains ECCS initiation capability.
(b)
Also actuates the associated division diesel generator.
(c)
Not required to be OPERABLE when reactor steam dome pressure is less than or equal to 100 psig.
(d)
The injection function of Drywell Pressure High and Manual Initiation is not required to be OPERABLE with indicated reactor vessel water level on the wide range instrument greater than level 8 setpoint coincident with the vessel pressure less than 600 psig because of hot calibration/cold operation level error.
(e)
Provides signal to close HPCS pump injection valve only.
(f)
Provides signal to HPCS pump suction valves only.
~A~I)N ACTION 30 - With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip Function requirement:
a.
With one channel inoperable, place the inoperable channel in the tripped condition within 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />s* or declare the associated system
'noperable.
b.
With more than one channel inoperable, declare the associated system inoperable.
ACTION 31 - With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip Function requirement, place the inoperable channel in the tripped condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />; restore the inoperable channel to OPERABLE status within 7 days or declare the associated system inoperable.
The provisions of Specification 3.0.4 are not applicable.
NINE MILE POINT - UNIT 2 3/4 3-33 AMENDMENTNO. Eb 72
I I
TABLE 4.3.3.1-1 (Continued)
EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION SURVEILLANCE RE UIREMENTS TRIP FUNCTION D.
Loss of Power (Divisions I 8 II)
CHANNEL CHANNEL FUNCTIONAL CHANNEL CHECK TEST CALIBRATION OPERATIONAL CONDITIONS FOR WHICH SURVEILLANCE IS RE UIRED 1.
- 4. 16-kV Emergency Bus Undervoltage
S Loss of Voltage 2.
- 4. 16-kV Emergency Bus Undervoltage
S Degraded Voltage E.
Loss of Power (Division III) l.
- 4. 16-kV Emergency Bus Undervoltage
S Loss of Voltage 2.
- 4. 16-kV Emergency Bus Undervoltage
S Degraded Voltage 1, 2, 3, 4t, 5t 1,2,3,4$,5$
1, 2, 3, 4$, 5f 1, 2, 3, 4t,.:5t
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EMER EN Y-RE 0
LIN Y TEM T ATI N IN TRUMENTATI N RVEILLANCERE UI EMENT TABLE NOTATI N When the system is required to be OPERABLE per Specification 3.5.2.
Not required to be OPERABLE when reactor steam dome pressure is less than or equal to 100 psig.
t Required when the associated diesel generator is required to be OPERABLE.
(a)
Manual initiation switches shall be tested at least once per 18 months during shutdown.
All other circuitry associated with manual initiation shall receive a CHANNEL FUNCTIONAL TEST at least once per 92 days as part of the circuitry required to be tested for automatic system actuation.
(b)
The injection function of Drywall Pressure
- High and Manual Initiation is not required to be OPERABLE with indicated reactor vessel water level on the wide range instrument greater than Level 8 setpoint coincident with the vessel pressure less than 600 psig due to the hot calibration/cold operation level error.
(c)
Perform the calibration procedure for the Trip Setpoint at least once per 92 days.
NINE MILE POINT - UNIT 2 3/4 3-44 AMENDMENT NO. k( 72
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