ML17059A934
| ML17059A934 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 09/11/1995 |
| From: | Marsh L NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML17059A935 | List: |
| References | |
| NUDOCS 9509140223 | |
| Download: ML17059A934 (24) | |
Text
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 WTTWRTOOWOOORW POWIR OOOOOIUITIOR DOCKFT ND~50-4 0
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S Amendment No.
69 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 6,
- 1995, 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 witlIout endangering the health and safety of the pI!blic, and (ii) that such activities will be conducted in compliance witI1 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 tho 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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The Technical Specifications containad in Appendix A and the,.
Environmental Protection Plan contained in Appendix D, both of. which are attached
- hereto, as revised through Amendment No. 69 are hereby incorporated into this license.
Niagara Mohawk Power Corporation shall oper ate the facility'in accordance with the Techhical 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
~ Ledyard B. Marsh, Director Project Directorate I-l Division of Reactor Projects I/II Office of Nuclear Reactor Regulation Date of Issuance:
September ll, 1995
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~69 O~FII Y 0 IST NS
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Revise Appendix A as follows:
Re ove es 3/4 3-81 3/4 3-82 3/4 3-83 3/4 3-84 3/4 3-85 3/4 3-86 3/4 3-87 3/4 4-10 3/4 4-11 3/4 3-81 3/4 3-82 3/4 3-83 3/4 3-84 3/4 3-85 3/4 3-86 3/4 3-87 3/4 4-10 3/4 4-11
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I 3.3.7.5 The accident monitoring instrumentation cliannels shown in Table 3.3.7.6-1 shall bo OPERABLE.
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a.
With one or more accident monitoring instrumentation channels inoperable, take the ACTION required by Table 3.3.7.5-1.
b.
The provisions of Specification 3.0.4 are not applicable.
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R IREME T 4.3.7.5 Each of the above required accident monitoring instrumentation channels shall be demonstrated OPERABLE by performance of the CHANNEL CHECK and CHANNEL CALIBRATION operations at the frequencies shown in Table 4.3.7.5-1.
NINE MILE POINT, - UNIT 2 3/4 3-01 Amondment No. 69
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TABLE
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Reactor Vessel Pressure 2.
Fuel Zone b.
Wide Range 3.
Suppression Pool Water Level a.
Narrow Range b.
Wide Range 4.
Suppression Pool Water Temperature 5.
Suppression Chamber Pressure 5.
Suppression Chamber AirTemperature 7.
Drywall Pressure a.
Narrow Range b.
Wide Range 8.
Drywall AirTemperature 9.
Drywell Oxygen Concentration 10.
Drywall Hydrogen Concentration Analyzer and Monitor REQUIRED NUMBER OF
~HANMEL 2
2 2
2 2/Quadrant 2
2 AX LQE 80
'80 80 80
~80 80 80 80 80 80
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Cz h3 ACCIDENT MONIT RING IN TR MENTATIO N
MEN 11.
Drywell High Range Radiation Monitors
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Penetration Flow Path Pr!mary Containment Isolation Valve Position Indication*
REQUIRED NUMBER OE QHHABNEL I-'-+A~~IN I
81 Col M
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Not required <or isolation valves whose assoc!ated flow path is isolated by at least one closed and deactivated automatic valve, closed manua! valve, blind flange, or check, valve with flow through the valve secured.
Only one position indication channel is required f":penetration flow paths with only one control room indication channel.
If this one channel becomes inoperable, entry into ACTION 80b is required.
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ACTION 80" Q.
With th numb. r of OPERAN.F. accIdent monitoring instrumentation channels for orie or more functions ono Icosa than tho Required Number of Channels shown in Table 3.3.7.5-1, restcre the inoperable channel(s) to OPERABLE status within 30 days or prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within the following 14 days outlining the preplanned alternate method of monitoring, the cause of the inoperability, and the plans and schedule for restoring the instrumentation channel(s) of the function(s) to OPERABLE status.
b.
With the number of OPERABLE accident monitoring instrumentation channels for one or more functions two less than the Required Number of Channels shown in Table 3.3.7.5-1, restore the inoperable channel(s) to OPERABLE status within 7 days or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
ACTION 81 - a.
With the number of OPERABLE Drywell High Range Radiation Monitors one less than the Required Number of Channels shown in Table 3.3.7.5-1, restore the inoperable channel to OPERABLE status within 30 days or prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within the following 14 days outlining the prep'lanned alternato method of monitoring, the cause of the inoperability, and the plans and schedule for restoring the instrumentation channel of the function to OPERABLE status.
Witlitlie number of OPFRABLE Drywc!I High Range Radiation Monitors two less than the (required Number of Channels sliown in Table 3.3.7.5-1, restoro the inoperable channel(s) to OPERABLE status within 7 days or prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within the following 14 days outlining the preplanned alternate method of monitoring, the cause of the inoperability, and the plans and schedule for restoring the instrumentation channel(s) of the function to OPERABLE status.
NINF MILE POINI', - UNIT 2 3/4 3-64 Amendment No. 69
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69
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Reactor Vessel Pressure CHANNEL CHANNEL
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3.
4.
5.
6.
7.
8.
9.
Reactor Vessel Water Leve!
a.
Fuel Zone b.
Wide Range Suppression Pool Water Level a.
Narrow Range b.
Wide Range Suppression Pool Water Temperature Suppression Chamber Pressure Suppression Chamber AirTemperature Drywall Pressure a.
Narrow Range b.
Wide Range Dry'well AirTemperature Drywall Oxygen Concentration M
M M
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Drywall Hydrogen Concentration Anelyier and Monitor 11.
Drywell High Range Radiation Monitors M
12.
Penetration Flow Path Primary Containment Isolation Valve Position Indication Mtt
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Excludes sensors; server compaiison rko!I ho dona in lieu of e:.nsor calibration.
Using sample gas containing:
a.
One volume percent hydrogen, balance nitrogen.
b.
Four volume percent hydrogen, balance nitrogen.
- The CHANNEL CALIBRATIONshall consist of position indication verification using ASME Section XI IWV-3300 test criteria.
t The CHANNEL CALIBRATIONshall consist of an electronic calibration of the channel, not including the detector, for range decades above 10 R/hr and a one point calibration check of the detector below 10 R/hr with an installed or portable gamma source.
tt Red, Green or other indication shall be verified as indicating valve position.
NINE MILF. I OINT - UNIT 2 3/4 3-87 Amendment No. 69
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. LIMITI 3.4.2 The safety valve function of at least 16 of Cha 'ollowing reactor coolant systar~c safety/relief valves shall be OPERABLF. with tho spocifiod code safety valvo function liftsottings>>:
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2 safety/relief valves 9 1148 psig a1%
4 safety/relief valves 5 1175 psig a1%
4 safety/relief valves 5 1185 psig ~1%
4 safety/relief valves 5 1195 psig s1%
4 safety/relief valves 5 1205 psig s1%
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a 0 With the safety valve function of one or more of the above required 16 safety/relief valves inoperable, be in at least HOT SHUTDOWN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
b.
With one or more safety/relief valves stuck open, provided that the average water temperature in the suppression pool is less than 110'F, close the stuck-open safety/relief valve(s); if unable to close the open valve(s) within 5 minutes or if the average water temperature in the suppression pool is 110'I= or more, place the roactor mode switch in the Shutdown position.
The liftsetting pressure shall correspond to ambient conditions of the valves at nominal operating temperatures and pressures.
NINE MILE POINT - UMIY2 3/4 4-10 Amendment No. 69
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4A.Q No requirements other than 8pacifieation 4.0.b.
NINE MILF. POINT - UNIT 2 Amendment Ro. E7, 69
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