ML20204C791
| ML20204C791 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point |
| Issue date: | 03/16/1999 |
| From: | Bajwa S NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20204C797 | List: |
| References | |
| NUDOCS 9903230289 | |
| Download: ML20204C791 (6) | |
Text
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q UNITED STATES j
NUCLEAR REGULATORY COMMISSION t
WASHINGTON, D.C. 2055HXX)1
%...../
NIAGARA MOHAWK POWER CORPORATION DOCKET NO. 50-220 NINE MILE POINT NUCLEAR STATION. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE f
Amendment No. 165 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 December 30,1998, 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 (1) 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:
9903230289 990316 PDR ADOCK 05000220 P
2 (2)
Technical Specifications and Environmental Protection Plan l
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. 165 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 arnendment is effective as of the date of its issuance to be implemented within 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION
.W S. Singh Bajwa, Director Project Directorate 1-1 Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation At' 5 ment:
Cha..ges to the Technical Specifications Date of issuance: March 16, 1999
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ATTACHMENT TO LICENSE AMENDMENT NO.165 l
TO FACILITY OPERATING LICENSE NO. DPR-63 DOCKET NO. 50-220 i
i Replace the following pages of the Appendix A Technical Specifications with the attached pages.
Remove Insert 290 290 293 293 305 305 1
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a TABLE 3.6.14-2 (cont'd)
RArMOACTIVE GASEOUS EFFLUENT MOMTORING INSTRUMENTATION t
Minimum instrument Channels Oostable AnolicablRtv Action f
3.
Condenser Air Ejector Radio-activity Monitor (Recombiner discharge or air ejector discharge) i a.
Noble Gas Activity 1
(g)
(c) b.
Offgas System Flow Rate 1'
l Measuring Devices i
c.
Sampler Flow Rate 1
(c)
Measuring Devices 4.
Emergency Condenser System
)
a.
Noble Gas Activity Monitor 1 per vent (h) 1 During operation of the main condenser air ejector
- ' During power operating conditions and whenever the reactor coolant temperature is greater then 212*F except for hydrostatic testing with the reactor not critical.
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AMENDMENT NO. //d 165 200
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I NOTES FOR TABLE 4.6.14-2 j
(c)
At all times.
(b)
The channel calibration ->
be performed using one or more of the reference standards certified by the National Bweau of 4
Standards, standards th traceable to the National Bureau of Standards or using actual samples of gaseous effluent that have j
been analyzed on a syste.. snet has been calibrated with National Bureau of Standards traceable sources. These standards shall j
permit calibrating the system over its intended range of energy and measurement.
(c)
The channel function test shall demonstrate that control room slarm annunciation occurs if either of the following conditions exist:
[
1)
Instrument indicates measured levels above the Hi or Hi Idi alarm se90 int.
- c) instrument indicstes a downscale failure.
4 i
The channel function test shall also demonstrate that autornatic isolation of this pathway occws if either of the following conditions exist:
i 1)
Instruments indicate two channels above Hi Hi alarm setpoint.
2) instruments indicate one channel above Hi Hi alarm setooint and one channel downscale.
l (d)
During main condenser offgas treatment system operation.
(::)
The channel calibration shall include the use of standard gas samples containing a nominal:
4 1.
One volume percent hydrogen, balance nitrogen.
2.
Four volume percent h;drogen, balance nitrogen.
(f)
During operation of the main condenser air ejector.
4 l
(g)
The channel test shall produce upscale and downscale annunciation.
(h)
During power operating conditions and whenever the reactor ccolant temperature is greater than 212*F except for hydrostatic j
testing with the reactor not critical.
r AMENDMENT NO. /dd 165 293
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LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENT I
c.
The poss radioactivity (beta r" 'ar gammal rate The radioactivity rate of noble gases at the l
of noble gases measured at the recombiner recombiner discharge shall be continuously j
obcharge shall be limited to less than or equal to monitored in accordance with Table 3.6.14-2.
500,000 pCi/sec. This limit can be raised to 1 Ci/sec. for a period not to exceed 60 days The gross radioactivity (beta and/or gammal rate provided the offgas treatment system is in of noble gases from the recombiner discharge operation.
shall be determined to be within the limits of Specification 3.6.15 at the following frequencies l
With the gross radioactivity (beta and/or gammal by performing an isotopic analysis of a represent-rate of noble gases at the recombiner discharge ative sample of gases taken at the recombiner excaeding the above limits, restore the gross discharge:
I radioactivity rate to within its limit within 72 i
hours or be in at least Hot Shutdown within the Monthly:
I next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
Within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> following an increase on the d.
Uranium Fuel Cycle recombiner discharge monitor of yester then 50%, factoring out increases due to changes l
The annual (calender year) dose or dose in thermal power level and dilution flow I
commitment to any member of the public due to changes.
releases of radioactivity and to radiation from l
uranium fuel cycle sources shall be limited to less d.
Uranium Fuel Cycle than or equal to 25 maams to the total body or any organ, except the thyroid, which shall be Cumulative dose contributions from liquid and j
limited to less than or equal to 75 mroms.
gaseous effluents shall be determined in accordance with Specifications 4.6.15.a.(2),
4.6.15.b.(2) and 4.6.15.b.(3) and in accordance l l
with the methodology and parameters in the Offsite Dose Calculation Manuel.
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1 AMENDMENT NO. //d 165 305
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