ML20046C106
| ML20046C106 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 07/29/1993 |
| From: | Capra R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20046C107 | List: |
| References | |
| NUDOCS 9308090207 | |
| Download: ML20046C106 (6) | |
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UNITED STATES
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NUCLEAR REGULATORY COMMISSION g
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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. 194 License No. DPR-59 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Power Authority of the State of New York (the licensee) dated April 15, 1993, 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 th'is 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:
9308090207 930729 PDR ADOCK 05000323 p
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. (2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 194, 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 I-1 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: July 29, 1993
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4 ATTACHMENT TO LICENSE AMENDMENT NO. 194 FAClllTY OPERATING LICENSE NO. DPR-59 DOCKET NO. 50-333 l
Revise Appendix A as follows:
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212 212 213 213 l
213a 213a d
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i JAFNPP TABLE 4.7-2 EXCEPTION TO TYPE C TESTS CONTAINMENT VALVE PENETRATION PENETRATION FUNCTION NUMBER LOCAL LEAK RATE TEST PERFORMED 35C Traversing in-Core Probe "C" 07EV-104C This valve is an explosive shear valve which cannot be Type C tested.
35D Traversing in-Core Probe "B" 07EV-1048 This valve is an explosive shear valve which cannot be Type C tested.
37A Control Rod Drive 03SOV 120 Will not be tested as lines (there are 137 lines, with 31 to 38 lines per 378 (below piston) 03SOV-123 penetration, and each has the four indicated valves) are sealed by 37C 03AOV-126 process fluid.
37D 03CRD-138 38A Control Rod Drive 03SOV-121 Will not be tested as lines (there are 137 lines, with 31 to 38 lines per 388 (atuvo piston) 03SOV-122 penetration, and each has the three indicated valves) are sealed by 38C 03AOV-127 process fluid.
38D 39A RHR Cont. Spray 10MOV-31 A This valve will be tested in the reverse direction.
398
, RHR Cont. Spray 10MOV-31B This valve will be tested in the reverse direction.
45 Drywell Pressure Sensing 16-1 AOV-101 A This valve will be tested in the reverse direction.
50C Instrumentation - Sensing Various These *nstrument root valves are tested during a Type A test.
DW Pressure
, ljd, [1,194 Amendment No.
JAFNPP-
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TABLE 4.7-2 EXCEPTION TO TYPE C TESTS CONTAINMENT VALVE PENETRATION PENETRATION PUNCTION NUMBER LOCAL LEAK RATE TEST PERFORMED 2028 Vacuum Bresher - Reactor 27AOV-101A These valves will be tested in the reverse detection.
Budding to Suppression 27AOV-1018 Chamber 205 Pressure Suppression 27AOV-117 These votas will be tested in the reverse direction.
Chamber Purge Ehuet 27MOV-117 (Air or Nitrogen) 210A RHR to 9
-::::r. Pool, 10MOV-16A Will not be tested as lines are water sealed by suppression chamber RCIC, Core Spray Test to 10MOV-21 A water.
Suppression Pool 10MOV-34A 10MOV-167A 13MOV 14MOV-5A 14MOV-26A 10RHR-95A 14 CSP-62A 2108 RHR to 95-:::'r. Pool, 10MOV-168 Will not be tested as lines are water sealed by suppression chamber i
HPCI, Core Spray Test to 10MOV-218 water.
suppression Pool 10MOv.348 I
l 10MOV-1578 14MOV-58 14MOV-268 23MOV-25 10RHR-958 14 CSP-628 211A RHR to Suppression Spray 10MOV-38A This volve wig be tested in the reverse direction.
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, 194 Amendment No.
,1
1 JAFNPP TABLE 4.7-2 EXCEPTION TO TYPE C TESTS CONTAINMENT VALVE PENETRATION PENETRATION FUNCTION NUMBER LOCAL LEAK RATE TEST PERFORMED 2118 RHR to Suppression 10MOV-388 This volve will be tested in the reverse direction.
Spray Hooder i
218 Torus Pressure Sensing 16-1 AOV-102B' This valve will be tested in the reverse direction.
220 Torus Purge inlet 27AOV-116 These valves will be tested in the reverse direction.
(Air and/or Nitrogen) 27AOV-132A l
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221 RCIC - Vacuum Pump to Torus 13RCIC-07 Will not be tested as line is sealed by suppression chamber water.
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222 HPCI - Turbine Drain 23HPI-13 Will not be tested as line is water seeied by suppression chamber water.
l Trap to Torus 224 RCIC - Pump 13MOV-39 Will not be tested as lines are water sealed by suppression ciumber Suction (Torus) 13MOV-41 water.
225A MHR - Pump Suction, 10MOV-13A Will not be tested as lines are water sealed by suppression chamber RHR to Redweste 10MOV-13C water.
225B RHR - Pump 10MOV-138 Will not be tested as lines are water sealed by suppression chamber Suction 10MOV-13D water.
1[,194 Amendment No.
213a