ML20081L620
| ML20081L620 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 07/01/1991 |
| From: | Capra R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20081L626 | List: |
| References | |
| NUDOCS 9107050217 | |
| Download: ML20081L620 (5) | |
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- i NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. ?"iP y
POWER AUTHORITY 0F,,TH,E,,S,TA,TE OF t;EW Y0,RK p0CKETNO.50-m J AM E S A F 1,T Z P A,T R,1,,C K,,N,U,C,L,E AR,,P,0,W E,R, P,L,Att T At1ENDt4EtiT TO FACILITY OPERATit4G LICENSE Amendn.ent !!o,171 License flo. DPR-59 1.
The fluclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Power Authority of the State of New York (the licensee) dated June 21, 1990, 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 Conanission; i
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.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this licesa amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-59 is hereby amended to read as follows:
9107050217 910701 ADOCK0500g3 pos P
2 (2) Techn i_ca,1,,Sp_e,cif i ca t i on s The Technical Specifications contained in Appendices A and B, as revised through Amendment No.171, 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 Robert A. Capra, Director Project Directorate 1-1 Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: July 1,1991 1
ATTACHMENT T0,y_CE!(SE, AM!ipg!1T $171_
FACILITY OPERATitiG LICENSE NO. DPR-59 DOCKET NO. 50.-333 Revise Appendix A as follows:
Remove Pages Insert Pages 114 114 116 116
(
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 determined that one Core Spray System is Systems is made or found inoperable for any reason, inoperabic, the operable Core Spray System, and both continued reactor operation is permissible during the IPCI subsystems, shall be verified to be operable succeeding 7 days unless the system is made operable immediately. The remaining Core Spray System shall be earlier, provided that during the 7 days all active verified to be operable daily thereafter.
components of the other Core Spray System and the LPCI System shall be operable.
3.
LPCI System testing shall be as sper" Teed n 4 a, b, c.
3.
Both LPCI subsystems of the RHR System shall be d,Iand g except that each RHR : ump sh at least-operable whenever irradiated fuel is in the reactor and prior 8,910 gpm against a system F.ed oc~'
N oa 1
to reactor startup from a cold condition, except as reactor vessel to primary cr.Atainmer..
- 'lpressure specified below.
of greater than or equal to 20 psia.
l a.
From the time that one of the LPCI subsystems is a.
When it is determined that one LPCI subsystem is made or found to be inoperable for any reason, inoperable, the operable LPCI suosystem and both continued reactor operation is permissible during the
-Core Spray Systems shall be verified to be operable succeeding 7 days unless that subsystem is made immediately and daily thereafter.
operable earlier provided that during these 7 days the operable LPCI subsystem and both Core Spray l
Systems sha!! be operable.
Amendment No.1/,4[,9 1[4,1
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, 1 71 114
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JAFNPP 3.5 (cont'd) 4.5 (cont'd) 2.
Should one RHRSW pump of the cornponents required in 2.
When it is deterrmned that one. RHRSW pump of the 35.B.1 above be made or found inoperable, continued components required in 3.5.B.1 above is anoperable, the reactor operation - is ' permissible only during the remaining curvipcimrds of the contamment cooling mode succeedmg 30 days provxied that during such 30 days all subsystems shall be verified to be operable immediately_
remaining components of the containment cooling mode
.. and daily thereafter.
subsystems are operable.
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3.
Should.one of the ' containment cooling subsystems When one contamment cooling subsystem loop becomes 3;
' operable, the redundant contamment coolmg subsystem m
become inoperable or should two of the RHRSW pumps loop shall be venfied to be operable immodately and daily i'
become inoperable, continued reactor operation is thereafter. When two of the RHRSW pumps become permissible for a period not to exceed 7 days.
inoperable, the remammg co ipeids of the contamment t
4.
If the requirements of 3.5.B2 or 3.5.B.3 cannot be met, the N.
stern (s) M M haw to M reactor shall be placed in a cold condition within 24 hr.
p
@ W % tkW<
Low power physics testing and reactor operator training 5.
shall ' be permitted with. reactor coolant temperature f
<212 F with an inoperable component (s) as specifkx1 in
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3.5.8 above.
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, 171
- Amendment No.
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