ML17058A854
| ML17058A854 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 07/15/1991 |
| From: | Capra R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17058A855 | List: |
| References | |
| NUDOCS 9107230392 | |
| Download: ML17058A854 (12) | |
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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 STATIONUNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 33 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 February 19, 1991, as supplemented on March 8,
- 1991, and May 20, 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 rot 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:
pDR ADOCK 050004i0
(2)
Technical Specifications 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. 33 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
Attachment:
Changes to the Technical Specifications Date of Issuance:
July 15, 1991 Robert A. Capra, Director Project Directorate I-1 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
ATTACHMENT TO LIGENSE AMENDMENT AMENDMENT NO. 33 TO FACILITY OPERATING LICENSE NO. NPF-69 DOCKET NO. 50-410 Revise Appendix A as follows:
Remove Pa es 2-3 3/4 3-17 Insert Pa es 2-3 3/4 3-17 3/4 3-19a (added page)
TABLE 2.2.1-1 REACTOR PROTECTION SYSTEM INSTRUMENTATION SETPOINTS Intermediate Range Monitor,-
Neutron Flux - High m
FUNCTIONAL UNIT m
C)M 2.
Average Power Range Monitor:
I TRIP SETPOINT ALLOWABLE VALUE
<120/125 divisions of full scale
<122/125 divisions of full scale a.
Neutron Flux Upscale, Setdown b.
- Flow-Biased Simulated Thermal Power - Upscale 1)
Flow-Biased 2)
High-Flow-Clamped c.
Fixed Neutron Flux-Upscale d.
Inoperative 3.
Reactor Vessel Steam Dome Pressure
- High 4.
Reactor Vessel Water Level-Low, Level 3
5.
Main Steam Line Isolation Valve - Closure
<15K of RATED THERMAL POWER 0.66 (W-~W)('). 5n,
.th maximum of <113.5X of RATED THERMAL POWER
<118'f RATED THERMAL POWER
<1037 psig
>159.3 in. above instrument zero"
<8X closed
<20X of RATED THERMAL POWER
<0.66 (W-dW)
+ 54K, with maximum of <115.5X of RATED THERMAL POWER
<120K of RATED THERMAL POWER
<1057 psig
>157.8 in. above instrument zero
<12K closed
<3.0 x full-power background
<1.88 psig e
6.
Main Steam Line Radiation (b)
<3.6 x full-power background g.
High 7.
Drywell Pressure - High
<1.68 psig
- See Bases Figure B3/4 3-1.
(a) The Average Power Range Monitor Scram Function varies as a function of recirculation loop drive flow (W).
bW is defined as the difference in indicated drive flow (in percent of drive flow which produces rated core flow) between two loop and single loop operation at the same core flow.
AM=0 for two loop operation.
BW=5X for single loop operation.
(b) See footnote ("") to Table 3.3.2-2 for trip setpoint during hydrogen addition test.
TABLE 3.3.2-2 ISOLATION ACTUATION INSTRUMENTATION SETPOINTS TRIP FUNCTION 1.
Primar Containment Isolation Si nals (Continued) a.
Reactor Vessel Water Level~
1)
Low, Low, Low, Level 1
2)
Low, Low, Level 2
3)
Low, Level 3
b.
Drywell Pressure - High c.
Radiation - High""
2)
Pressure Low 3)
Flow - High d.
Main Steam Line Tunnel 1)
Temperature - High 2) bTemperature High 3)
Temperature - High MSL Lead Enclosure e.
Condenser Vacuum Low f.
RHR Equipment Area Temperature - High (HXs/A88 Pump Rooms) g.
Reactor Vessel Pressure - High (RHR Cut-in Permissive) h.
SGTS Exhaust - High Radiation TRIP SETPOINT
>17.8 in.
>108.8 in.
>159.3 in.
<1.68 psig
<3x Full Power Background
>766 psig
<103 psid
<165.7 F
<ee.7'F
<146.7 F
>8.5 in Hg vacuum
<135 F
<128 psig
<5. 7xl0-3 pCi/cc ALLOWABLE VALUE
>10.8 in.
>101.8 in.
>157.8 in.
<1.88 psig
<3 ex Full Power Background
>746 psig
<109 ~ 5 psid
<169.9 F
<71.3 F
<150.9 F
>7.6 in.
Hg vacuum
<144 5 F
<148 psig
<1.0xl0-2 pCi/cc
Table 3.3.2-2 (Continued)
ISOLATION ACTUATION INSTRUMENTATION SETPOINTS Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to the planned start of the hydrogen injection test and with the reactor power at greater than 20K rated power, the normal full-power radiation background level and associated trip and alarm setpoints may be changed based on a calculated value of the radiation level expected during the test.
The background radiation level and associated trip and alarm setpoints may be adjusted during the test program based on either calculations or measurements of actual radiation levels resulting from hydrogen injection.
The background radiation level shall be determined and associated trip and alarm setpoints shall be reset within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after completion of the hydrogen injection test.
At reactor power levels below 20X rated power hydrogen injection shall be terminated, and control rod withdrawal is prohibited until the Main Steam Line Radiation Monitor trip setpoint is restored to its pre-test value.