ML20065S130
| ML20065S130 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 07/30/1990 |
| From: | Capra R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20065S133 | List: |
| References | |
| NUDOCS 9012200104 | |
| Download: ML20065S130 (4) | |
Text
._.
_ = - _ _. - -
.--.-----------------7 e
4 f,'pa snow *\\,
UNITED STATES e
a NUCLEAR REGULATORY COMMISSION 3
I wAssiNotoN,0. c. 20sss J'
POWER AUTHORITY OF THE STATE OF NEW YORK DOCKET NO. 50 333 JAMES A. FIT 2 PATRICK. NUCLEAR POWER PLANT AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.163 License No. DPR-59 1.
The Nuclear Regulatory Commission (the Comission) has found that:
A.
The application for amendment by Power Authority of the State of New York (the licensee) dated March 9,1990, 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 wi11' operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
Thereisreasonableassurance(1)thattheactivitiesauthorized by this amendment can be conducted without endangering the health i
and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations; D.
The ipsuance of this amendment will not be inimical to the common defense and security or to the hetith and safety of the public;.
and I.
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, i
l 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-59 is hereby_ amended to read as folius:
l l
l 9012200104 900730
{DR ADOCK0500g3
t' 2
(2)
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 163, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technica:
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 U0 '
W Robert A. Capra, Director Project Directorate i-1 Division of Reactor Projects - 1/l!
Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of issuance: July 30. 1990
k ATTACHMENT TO LICENSE AMEWOMENT NO.163.
FACILITY OPERATING. LICENSE NO. DPR 59 DOCKET NO. 50-333 Revise Appendix A as follows:
Remove Page Insert. Pace 217 217 l
i
A JAFNPP 3 9 (cont'd) 4S (cont'd) 3.
Frorn and after the time that one of the Emergency Desel 3.
The emerger.cy diesel generator system imtrumentation -
l Generator Systems is made or found to be inoperable, shall be checked during the monthry generator test.
continued reactor operation is permissible for a period not to exceed 7 days provided that the two incoming power sources are avail.sbie and that the remaining Dese!
Generator System is operable. At the end of the 7-day period, the reactor shall be placed in a cold condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, unless the affected diesel generator system is made operable sooner.
4.
When both Emergency Diesel Generator Systems are 4
Once each operating cycle, the conditiom under which the made or found to be inoperable, a reactor shutdown shall Emergency Desel Generator System is required will be be initiated within two hours and the reactor placed in a simulated to demonstrate that the pair of diesel generators cold condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after initiation of shutdown will start, accelerate, force parallel, and accept the emergency loads in the prescribed sequence.
5.
Once within one hour and at least once per twenty.our hours thereafter while the reactor is being operated in accordance with Specifications 3S.B.1,3S.B2, or 33.8.3 the availability of the operable Emergency Desci Generators shall be demonstrated by manual starting and force para:! cling where applicable.
I Amendment No. )6.ps,[l63 2t7
_