ML20086C132
| ML20086C132 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 11/07/1983 |
| From: | Vassallo D Office of Nuclear Reactor Regulation |
| To: | Power Authority of the State of New York |
| Shared Package | |
| ML20085C841 | List: |
| References | |
| DPR-59-A-076 NUDOCS 8311230007 | |
| Download: ML20086C132 (12) | |
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UNITED STATES
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'i NUCLEAR REGULATORY COMMISSION yg, 9l WASWNGTON, D. C. 20555 y-)
POWER AUTHORITY OF THE STATE OF NEW YORK DOCKET NO. 50-333 JNES A. FITZPATRICK NUCLEAR POWER PLANT AMENDMENT TO FAC,IJ ITY OPERATING LICFNSE Amendment No. 76 License 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't dated April 22, 1983, cc:aplies with the standan ds 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 Comission; 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 comon 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 Comission'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 hereoy amended to read as follows:
8311230007 831107 PDR ADOCK 05000333 P
. (2)
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 76, 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 1NE NUCLEAR REGULATORY COMMISSION Domenic B. Vassallo, Chief Operating Reactors Branch #2 Division of Licensing
Attachment:
Changes to the Technical l
Speci fications
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Date of Issuance: November 7,1983 1
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ATTACHENT TO LICENSE AMENDMENT NOL 76 FACILITY OPERATING LICENSE NO. OPR-59 DOCKET NO. 50-333 Revise the Appendix "A" Technical Specifications as follows:
Remove Replace 222c 222c 222d 224a 226 226 e
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F
JAFNPP 3.9 (cont'd) 4.9 (cont'd) 3.
From and after the time both power supplies are made or found inoperable the reactor shall be brought to cold i
condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
i G.
REACTOR PRQTECTION. SYSTEM _ ELECTRICAL G.
REA_CTOR _PRQTECTIQN.. SYSTEM ELECTRICAL PROTECTION ASSEMBLIES PROTECTION ASSEMBLIES Two RPS electrical protection assemb-lies for each inservice RPS MG set The RPS electrical protection assemblies and inservice a.lternate source instrumentation shall be determined shall be operable except as specified operable by:
below:
1.
At least once every 6 months, 1.
With one RPS electrical protection performing a channel functional assembly for an inservice RPS MG test.
set or an inservice alternate power supply inoperable, restore the 2.
At least once per operating c'ycle, inoperable channel to operable demonstrating the operability of status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or remove over-voltage, under-voltage and I
the associated RPS MG set or under-frequency protective instrumentation; alternate power supply from by performance of a channel calibration service.
including simulated automatic actuation of the protective relays, tripping 2.
With two RPS electrical protection logic and output circuit breakers and assemblies for an inservice RPS verifying the following set points:
MG set or an inservice alternate power supply inoperable, restore at least one to operable status RPS..MG SET SOURCE within 30 minutes or remove the associated RPS MG set or alternate OVER-VOLTAGE
$L132V power supply from service.
SE4s Time Delay UNDER-VOLTAGE 2108V
$3s Time Delay UNDER-FREQUENCY 7tS7HZ 514s Time Delay Amendment No.
jE[,76 222c (continued on page 222d)'
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O JAFNPP 3.9.G (cont'd) 4.9.G (cont.' d) j-3.
With the reactor in the RUN mode, at least one (1) RPS division ALTERNATE SOURCE shall be powered from the MG OVER-VOLTAGE sl32V set except as specified below:
14s Time Delay i
With both RPS divisions powered UNDER-VOLTAGE
> 108V from the alternate sources, at 44s Time Delay least one division power source i
shall be restored to a MG set UNDER-FREQUENCY 2P57HZ with operable electrical
~ s;4s Time Delay protection assemblies within seven (7) days or the reactor.
shall be brought to the cold condition within the subsequent 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
Amendment No. 76 222d
O JAFNPP 3.9 BASES (cont'd)
F.
Reactor Protection System Power Suppl,ies l
Each of two RPS divisions may be supplied power from it's respective RPS MG set or i
i from an alternate source which der.ives power from the same electrical division.
The MG sets and alternate sources for 1
both divisions are provided with redundant, seismic qualified, class lE electrical 1
i protection assemblies between the power source and the RPS bus.
Any abnormal output type failure in either of the MG sets or alternate sources (if in service) would result in a trip of one or both of the electrical protection assemblies producing a half scram on that RPS division and retaining full scram capability in the other RPS division.
Limiting operating conditions in Section 3.9.G provide a high degree of assurahce that RPS buses are protected as d.escribed above.
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Amendment No. 76 224a
i JAFNPP i
2 i
4.9 BASES (cont'd)
D.
Battery System j
Measurements and electrical tests are conducted at specified intervals i
to provide indication of cell condition
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and to determine the discharge capability j
of the batteries.
E.
LPCI,MOV_ Independent P,ower Supply Measurement and electrical tests are cond6cted at specified intervals to provide indication of cell condition, to determine the discharge capability of the battery.
F.
Reactor Protection Power Supplies Functional testes of the electrical protection assemblies are conducted once each six (6) months utilizing a built-in test device and once per operating cycle by performing an instrument calibration which verifles operation within the limits of Section 4.9.G.
Amendment No. )MI, 76 226