ML20099L491
| ML20099L491 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 12/21/1995 |
| From: | Marsh L NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20099L492 | List: |
| References | |
| GL-91-04, GL-91-4, NUDOCS 9601020094 | |
| Download: ML20099L491 (5) | |
Text
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UNITED STATES
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NUCLEAR REGULATORY COMMISSION f
WASHINGTON, D.C. 20066-0001
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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 OPERATING LICENSE Amendment No. 230 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 May 12, 1995, 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 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 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 license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-59 is hereby amended to read as follows:
9601020094 951221 PDR ADOCK 05000333 p
' (2) Technical Soecifications The Technical Specifications co tained in Appendices A and B, as revised through Amendment No. 220, 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
$ ledyard 8. Marsh, Director Project Directorate I-I Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: December 21, 1995
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ATTACHMENT TO LICENSE AMENDMENT NO. 230 FACILITY OPERATING LICENSE NO. DPR-59 DOCKET NO. 50-333 Revise Appendix A as follows:
Remove Paaes Insert Paaes 240 240 241 241 l
JAFNPP f
3.11 (cont'd) 4.11 (Cont'd)
D.
Emeroency Service Water System D. Emeraency Service Water System
- 1. To ensure adequate equipment and area cooling, both ESW
- 1. Surveillance of the ESW system shall be performed as systems shall be operable when the requirements of follows:
specification 3.5.A and 3.5.B must be satisfied, except as specified below in specification 3.11.D.2.
ilam Freauency a.
Simulated Automatic Once every 24 months l
Actuation Test -
b.
Flow Rate Test - Each Once/3 mxiths ESW pump shall deliver at least 1500 gpm to its respective loop. The pump total developed head shall be greater than or equal to the corresponding point on the I
pump curve, reduced by a maximum of 7%, for the measured flow.
c.
Pump Operability Once/ month d.
Motor Operated Once/ month i
Valves
.I Amendment No. 71,134, 223, 230 240
JAFNPP 3.11 (cont'd) 4.11 (cont'd) e.
ESW instrumentation i
check Once/ day ESW instrument l
channel calibration Once/3 months l
i f.
Logic System Once every
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Functional Test 24 months i
f l
2.
From and after the time that one Emergency Service 2.
ESW will not be supplied to RBCLC system during Water System is made or found to be inoperable for any testing.
reason continued reactor operation is permissible for a j
period not to exceed 7 days, provided that.
the operable Emergency Diesel Generator System is t
demonstrated to be operable immediately and daily thereafter; and, all Emergency Diesel Generator System emergency loads are verified operable immediately and daily thereafter.
[
3.
If specification 3.11.D.2 cannot be met the reactor shall 3.
Not Used be placed in the cold condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
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Amendment No. liS, 192, 230 241 1
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