ML20136C094
| ML20136C094 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 11/12/1985 |
| From: | Vassallo D Office of Nuclear Reactor Regulation |
| To: | Power Authority of the State of New York |
| Shared Package | |
| ML20136C098 | List: |
| References | |
| DPR-59-A-096 NUDOCS 8511210021 | |
| Download: ML20136C094 (6) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION F
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j WASHINGTON, D. C. 20555 1
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POWER AUTHORITY OF THE STATE OF NEW YORK DOCKET NO. 50-333 JAMES A. FITZPATRICK NUCLEAR POWER PLANT AMENDMENT TO FACILITY OPEftATING LICENSE Amendment No. 96 ticense No. DPR-59 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by the Power Authority of the State of New York (the licensee) dated January 28, 1985, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations
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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 Comission'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 license amendment and paragraph 2.C(2) of Facility Operating License No.
DPR-59 is hereby amended to read as follows:
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. t (2) Technical Specifications l
The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 96, 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.
FOR THE NUCLEAR REGULATORY COMMISSION Domenic B. Vassallo, Chief Operating Reactors Branch #2 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance:
November 12, 1985 i
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ATTACHMENT TO LICENSE AMENDMENT NO. 96 FACILITY OPERATING LICENSE NO. DPR-59 DOCKET NO. 50-333 Replace the following pages of the Appendix A Technical Specific &tions with the enclosed pages. The revised areas are indicated by marginal lines.
Pages 144 153 W
157 - 162 4
MW.
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JAFNPP 3.6 (cont'd) 4.6 (cont'd)
F.
Structural Inteerity F.
Structural'Inteority The structural integrity of the 1.
Nondestructive inspections shall Reactor Coolant System shall be be performed on the ASME Boiler maintained at the level required and Pressure Vessel Code Class 1, i
by the original acceptance stan-
'2 and 3 components and supports l
i dards throughout the life of the in accordance with the requirements j
Plant.
I of the weld and support inservice in-l spection program.
This inservice
' inspection program is based on an 1
NRC approved edition of, and addenda to,Section XI of the ASME Boiler and Pressure Vessel Code which is in effect 12 months or less prior to the beginning of the inspection interval.
2.
An augmented inservice inspection program is required for those high stressed circumferential piping joints i
in the main steam and feedwater lines larger than 4 inches in diameter, where no restraint against pipe whip j
is provided. The augmented inservice
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inspection program shall consist of j
i 100 percent inspection of these welds per inspection interval.
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G.
Jet Puans G.
Jet PumDs l
Whenever the reactor is in the Whenever there is recirculation flow j
startup/ hot standby or run modes, with the reactor in the startup/ hot i
all jet pumps shall be operable.
standby or run modes, jet pump oper-1 If it is determined that a jet pump ability shall be checked daily by is operable, the reactor shall be verifying that the following conditions l
placed in a cold condition within do not occur simultaneously:
24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
l Amendment No. 96 i
144 1
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3.6 and 4.6 BASBS (cont'd) not required to be operable (reactor several locations on the main steam f
coolant temperature 212*F and the lines and feedwater lines are not
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reactor vessel vented or the reactor restrained to prevent pipe whip in
,I vessel head removed).
Permitting the event of pipe failure at these physics testing and operator
' locations.
The physical layout training under these conditions within the drywell precludes re-would not place the plant in an straints at these points.
Unre-j unsafe condition.
strained high stress areas have
'been identified in these lines where i
F.
Structural Inteerity breaks could result in pipe whip i
such that the pipe could impact the
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A pre-service inspection of the primary containment wall.
Augmented I
l ASNE Code Class 1 components was inservice inspection of these weld l
performed after site erection to locations shall be performed during assure the system was free of gross each inspection period.
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defects.
An initial inspection program as detailed in Appendix F In addition, visual inspection in ac-i of the FSAR was developed and cordance with the approved ASME code wil based on an approved edition of the be made during periodic pressure and ASME Code.
hydrostatic tests of critical systems.
ll The inspection program specified on-compasses the major areas of the The program has been expanded to in-vessel and piping system within l
l clude the requirements of later, the drywell.
The. inspection period is approved ASME Code editions and based on the observed rate of defect i
addenda as far as practicable.
The growth from fatigue studies sponsored importance of these inspections is by the AEC.
recognized, and efforts to develop practical new alternative methods These studies show that thousands i
of assuring plant inservice integrity of stress cycles, at stresses be-j will continue.
This inspection pro-yond any expected to occur in a j
gram should assure the detection of Reactor Coolant System, were required
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problem areas well before they re-to propagate a crack.
The test i
present a significant impact on j
safety.
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Amendment No. 96 I.
i 153 i
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JAFNPP i
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l PAGES 157 THROUGH AND INCLUDING 162 HAVE BEEN INTENTIONALLY LEFT BLANK i
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1 Amendment No. 96 j
157-162 c
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