ML17056C217
| ML17056C217 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 01/08/1993 |
| From: | Capra R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17056C218 | List: |
| References | |
| NUDOCS 9301130281 | |
| Download: ML17056C217 (12) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555 NIAGARA MOHAWK POWER CORPORATION DOCKET NO. 50-220 NINE MILE POINT NUCLEAR STATION UNIT NO.
1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.
138 License No.
DPR-63 t(
1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Niagara Mohawk Power Corporation (the licensee) dated September 25,
- 1992, 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 I; 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. 'ccordingly; 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:
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'P3011302Bi 930108 PDR ADOCK 05000220
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(2)
Technical S ecifications The Technical Specifications contained in Appendices A and B,
as revised through Amendment.No.
- 138, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance to be implemented within 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION w~a'~
Robert A. Capra, Director Project Directorate I-I Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to'he Technical Specifications Date of Issuance:
January 8, 1993
TTACHMENT TO LICENSE AMENDMENT AMENDMENT NO. 138 TO FACILITY OPERATING LICENSE NO.
DPR-63 DOCKET NO. 50-220 Revise Appendix A as follows:
Remove Pa es 191 196 196a Insert Pa es 191 196 196a
Table 3.6.2a IN TR MENTATI N HA INITIA E RAM Li iin ndii nf 0
r in
~Pr ~m~r Minimum No.
of Tripped or Operable Minimum No. of Operable Instrument Channels per Operable
~ePoin Reactor Mode Switch Position in Which Function Must Be C
0 D
8 M
LL (1)
Manual Scram (2)
High Reactor Pressure (3)
High Drywall Pressure
< 1080 psig
< 3.5 psig x
x (p) x x
x (a)
(a)
(4)
Low Reactor Water Level
> 53 inches (Indicator Scale) x x
x (5)
High Water Level Scram Discharge Volume
< 45 gal.
(b) x x
Amendment Mo.~~~~,
138
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NOIKS FOR TABLES 3.6.2a 4.6.2a May he bypassed when necessary far containment inertiny.
May he bypassed in the refuel and s1lutdawn positians of the reactar mode switch with a keylock switch.
May be bypassed in the re~1 and startup positians of the reactar mode switch when reactor pressure is less than 600 psi, ar far the purpose of perfarnuxlg reactar coolant sy.~n pressure testing and/ar control rod scram time testing with the reaq~ mode switch in the refuel position.
No mme than one of the fear IBM inputs to each trip. system shall he bypassed.
No ants than tso C or D local LHM lntstts to an APRM shall he hypassed and only fteto Patt!1 lntstts to an hatt shall '
be ~essed in order far the APBM to be cansidered curable.
No mare than ane of the fear AHlM inputs to eaW trip system shall he bypassed prove% that the AH% in the other instruIM.nt channel in the sama care quadrant is nat ~lassed.
A Travelling In-Care Probe (TIP) chamber may be used as a substitute APBM input ifthe TIP is positiamd in close pmxixtu.ty to the failed LPRM it is replacing.
Calibrate prior to starting and normal shutdown and thereafter check ance per shift and test came per week until no longer required.
IBM's are bypassed when APRM's are onscale.
APRM downscale is bypassed when IRM's are onscale.
Each of the four isolation valves has two limit switches.
Each limit switch provides input to one of two instruaent channels in a single trip sy ~.
May be bypassed when reactor power level is below 45%.
Trip upon loss of oil pressure to the acceleratian relay.
May be bypassed when placing the reactor mode switch in the SHUIDCNN positian and all control rods are fully inserted e Only the trip circuit willbe calibrated and tested at the frequencies specified in Table 4.6.2a, the primary.
sensar willhe calibrated and tested ance per operating cycle.
Ktus calibration shall consist of the adjustment of the APRM channel to conform to the power values calculated by a heat balance during reactor operation when 'QKXÃhL HWER > 25% of RATH) 'HKRMAL POWER.
Adjust the APRM channel if the absolute difference is greater than 2t of RATED THERMAL POWER.
Any APBM channel gain adjustalent made in Amendment No.~~~
138 196
NOZES FCR TABUH 3.6.2a and 4.6.2a cont (n)
Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> priar to the planned start of the hydrogen injection test with the reactar power at greater than 2'ated power, the nannal full~awer radiatian bacLagzmnd level and associated trip and alarm setpoints may be ckmxpxi based an a calculated value of the radiation level expected during the test.
'Ibe bacRgxmuxl radiation level and associated trip and alarm setpoints may be adjusted during the test program based on either calculatices th A
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normal radiatian ocgpletion of the hydrogen injectian ar within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> of=establishipg Kyat~
power levels belnr
'ower, while these functions are recpired to be operable.
At reactar ~ levels below 2(A rated power, hydn~ injectian shall be terminated and the injection system secured.
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A channel rey he placed in an incperahle status for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for required surveillamms without placinl the ~
Trip Systan in the tr~ candition presided at least one operable channel in the sana trip system is monitoring that parameter.
'Ibis time interval is extended up to 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> far the High Radiatian Main-Steam Line Instrument Channel Calibration surveillance.
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May be bypassed during reactor coolant system pressure testing and/or control rod scram time testing.
Amendment No. pV, ~,
138 196a
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