ML20011F601
| ML20011F601 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 02/28/1990 |
| From: | Boger B Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20011F602 | List: |
| References | |
| NUDOCS 9003070023 | |
| Download: ML20011F601 (5) | |
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UNITED STATES
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NUCLEAR REGULATORY COMMISSION W.
WASHINGTON, D, C. 20555 i-
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P0WER AUTHORITY CF-THE STATE OF NEW YORK DOCKET NO. 50-333 JAMES. A. FITZP ATRICK NUCLEAR POWER PLANT AMENDMENT TO FACILITY OPERATING LICENSE Amendnent No.153 License No. DPR-59 i
1.
The Nuclear Regulatory Comission (the Commission) has found that:
A.
The application for amendment by Power Authority of the State of New York (the licansee) dated February 8,1990, as modified February 21, 1990, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Conmission'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 Comission; C.
There is reasonable assurance (1) that the activities' authorized by this amendnent can be conducted without endar.gering the health and safety of the public, and-(ii).that such activities will be conducted in compliance with the Comission's regulations; D.
The issuance of this amendaent will not be inimical to the conanon defense and security or to the health and safety of the public;
.t and E.
The issuance of this amendment is in accoraance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
r 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendnent, and paragraph 2.C. (2) of Facility Operating License No. DPR-59 is hereby amended to read as follows:
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9003070023 900228
y-2 (2) Technical Specifications 1
The Technical Specifications contained in Appendices A and B, as revised through Amendment No.153, 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 immediately upon receipt, and ends upon start of the 1990 refueling outage.
FOR THE NUCLEAR REGULATORY COMMISSION' kk[l l hjkw
] 'I Bruce A. Boger, Assistant Director for Region I Reactors Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation l
Attachment:
l Changes to the Technical Specifications i
Date of Issuance: February 28. 1990 l
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- ATTACHMENT TO LICENSE AMENDMENT NO.153 FACILITY OPERATING LICENSE NO. DPR L.
DOCKET NO. 50-333
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Revise Appendix ~ A as= follows:
Remove Pages Insert Pages i
114 114 116 116 I
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e JAFNPP 3.5 (cont'd) 4.5 (cont'd) 2.
From and after the date that one of the Core Spray 2.
When it is determmed that one Core Spray System is Systems is made or found inoperable for any reason, moperable, the operable Core Spray System, and both '
continued reactor operation is permissible during the LPCI subsystems, shall be verified to be operable l
succeeding 7 days unless the system is made operable nTwnediately. The remammg Core Spray System shall be earlier, provided that during the 7 days all active venfied to be operable daily thereafter.
l components of the other Core Spray System and the LPCI Systan M M opwah 3.
LPCI System testing shall be as specNed in 4.5.A.1a, b, c, 3.
Both LPCI subsystems of the RHR System shall be d, f and g except that each RHR pump shall delever at least operable whenever irradiated fuel is in.the reactor and prior 9,900 gpm against a system head corrwidis g to a to reactor startup from a cold condition, except as reactor vessel to pnmary contamment differential pressure specified below.
of greater than or equal to 20 psid.t' l
a.
From the time that one of the LPCI subsystems is a.
When it is determned that one LPCI subsystem is made or found to be inoperable for any reason, inoperable, the operable LPC! subsystem and both continued reactor operation is permissible dunng the Core Spray Systems shall be verifimi to be operable succeedmg 7 days unless that subsystem is made nnmediately and daily thereafter.
operable earlier provided that dunng these 7 days the operable LPCI subsystem and both Core Spray l
Systems shall be operable.*
tFor the remander of Cycle 9, RHR pumps "A" and
- LPC! subsystem "A" may be inoperable for a 14 "C" shall each deliver at least 8,910 gpm aganst a day penod. This toinpuitsy LCO exists until the system head correspondmg to a reactor vessel to end of Cycle 9.
primary contamment differential pressure of greater than or equal to 20 psid.
Amendment No. 14,40,95,'134,'1,43,' 153 114
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ma JAFNPP 3.5 (cont'd) 4.5 (cont'd) 3.
Should one RHR pump and/or one RHRSW pump of the 3.
components requred in 3.5.B.1 above be made or found When one contanment coolmg subsystem loop becomes moperable, the ~ cperable loop shall be verdied to 'be inoperable, congnued reactor operadon is permssible only operable immeddefy and daNy thereaner.
during the =% 30 days prended that dunne such 30 : days as remainmg achve components of the containment cooNng mode are operable.
4.
Should one of the contanment coobng subsystems become inoperable, congnued reactor operation is pernssible for a period not to exceed 7 days, unless such subsystem is sooner made operable provided that dunng such 7. days aN actrve components of the other l
contanment cooNng subsystem are operable. ~
- 5.
If the requrements of 3.5.B cannot be met, the reactor j
shall be placed in a cold condshon within 24 hr.
I 6.
Low power physics teshng and reactor operator trammg shaN be pemutted with reactor coolant temperature
<212"F with an inoperable component (s) as spinZ.,J in 3.5.B above.
Containment Cooling subsystem "A" may be inoperable for a 14 day. period. This
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temporary LCO condition exists until the i
end of Cycle 9.
Amendment No. X9tf141f,153 t
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