ML20072C658
| ML20072C658 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 08/11/1994 |
| From: | Quay T Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20072C662 | List: |
| References | |
| NUDOCS 9408180033 | |
| Download: ML20072C658 (9) | |
Text
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+4 UNITED STATES j
NUCLEAR REGULATORY COMMISSION f
WASHINGTON, D.C. 20066-0001
'S 9......o WOLF CREEK NUCLEAR OPERATING CORPORATION WOLF CREEK GENERATING STATION DOCKET NO. 50-482 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 75 License No. NPF-42 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment to the Wolf Creek Generating Station (the facility) Facility Operating License No. NPF-42 filed by the Wolf Creek Nuclear Operating Corporation (the Corporation), dated May 24, 1994, 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, as amended, 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 license amendment will not be inimical to the commen 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.
I 9408180033 940811 PDR ADOCK 05000482 p
4 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment
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and Paragraph 2.C.(2) of Facility Operating License No. NPF-42 is hereby amended to read as follows:
2.
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 75, and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated in the license. The Corporation shall operate the facility in accordance wita the Technical Specifications and the Environmental Protection Plan.
3.
The license amendment is effective as of its date of issuance and shall be implemented within 120 days of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION hs&$Na}
Theodore R. Quay, Director Project Directorate IV-2 Division of Reactor Projects III/IV-Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
August 11, 1994 n
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J-ATTACHMENT TO LICENSE AMENDMENT Nd. 75 FACILITY OPERATING LICENSE NO. NPF-42 DOCKET NO. 50-482 Replace the following pages of the Appendix A Technical Specifications with the attached pages. The revised pages are identified by Amendment number and contain marginal lines indicating the areas of change.
The corresponding overleaf pages are also provided to maintain document completeness.
REMOVE INSERT VI y1 3/4 3-44 3/4 3-44 3/4 3-45 3/4 3-45 3/4 3-46 3/4 3-46
[fMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 4
SECTION BK 3/4:2 POWER DISTRIBUTION LIMITS 3/4.2.1 AXIAL FLUX DIFFERENCE (AFD)..............................
3/4 2-1 3/4.2.2 NEAT FLUX N07 CHANNEL FACTOR - F.(X, Y,Z)................. 3/4 2-4 3/4.2.3 NUCLEAR ENTHALPY RISE HDT CHANNEL FACTOR
-F,(X,Y).............................................
3/4 2-9 3/4.2.4 QUADRANT POWER TILT RATI0................................
3/4 2-II 3/4.2.5 DNS PARAMETERS...........................................
3/4 2-14 TABLE 3.2-1 DNB PARAMETERS........................................
3/4 2-16 l
3/4.3 1NSTRUMENTATION 3/4.3.1 REACTOR TRIP SYSTEM INSTRUMENTATION......................
3/4 3-1 TABLE 3.3-1 REACTOR TRIP SYSTEM INSTRUMENTATION...................
3/4 3-2 TABLE 3.3-2 REACTOR TRIP SYSTEM INSTRUMENTATION RESPONSE TIMES 3/4 3-7 TABLE 4.3-1 REACTOR TRIP SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS........................................
3/4 3-9 3/4.3.2 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION........................................
3/4 3-13_
TABLE 3.3-3 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION.....................................
3/4 3-14 TABLE 3.3-4 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION TRIP SETP0!NTS......................
3/4 3-22 TABLE 3.3-5 ENGINEERED SAFETY FEATURES RESPONSE TIMES.............
3/4 3-29 TABLE 4.3-2 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATI0"i SURVEILLANCE REQUIREMENTS...........
3/4 3-34 NOLF CREEK - UNIT I V
Amendment No. 61
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LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION IMGf INSTRUMENTATION (Continued) 3/4.3.3 MONITORING INSTRUMENTATION Radiation Monitoring for Plant Operations................
3/4 3-39 TABLE 3.3-6 RADIATION MONITORING INSTRUMENTATION FOR PLANT 0PERATIONS................................
3/4 3-40 TABLE 4.3-3 RADIATION MONITORING INSTRUMENTATION FOR PLANT OPERATIONS SURVEILLANCE REQUIREMENTS........................................
3/4 3-42 Movabl e I ncore Detectors.................................
3/4 3-43 Seismic Instrumentation..................................
DELETED TABLE 3.3-7 SEISMIC MONITORING INSTRUMENTATION....................
DELETED TABLE 4.3-4 SEISMIC MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS...........................
DELETED Meteorol ogical Instrumentation...........................
3/4 3-47 TABLE 3.3-8 METEOROLOGICAL MONITORING INSTRUMENTATION.............
3/4 3-48 TABLE 4.3-5 METEOROLOGICAL MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS...........................
3/4 3-49 Remote Shutdown Instrumentation..........................
3/4 3-50 TABLE 3.3-9 REMOTE SHUTDOWN MONITORING INSTRUMENTATION............
3/4 3-51 TABLE 4.3-6 REMOTE SHUTDOWN MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS...........................
3/4 3-52 Accident Monitoring Instrumentation......................
3/4 3-53 TABLE 3.3-10 ACCIDENT MONITORING INSTRUMENTATION..................
3/4 3-54 TABLE 4.3-7 ACCIDENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS...........................
3/4 3-55 Chlorine Detection Systems...............................
DELETED Loose-Part Detection System........................
3/4 3-57 Radioactive Liquid Effluent Monitoring Instrumentation...
DELETED TABLE 3.3-12 RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION....................................
DELETED WOLF CREEK - UNIT 1 VI Amendment No. 15,42,55, 75
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INSTRUMENTATION 4
MOVABLE INCORE DETECTORS LIMITING CONDITION FOR OPERATION 3.3.3.2 The Movable Incore Detection System shall be OPERABLE with:
a.
At least 75% of the detector thimbles, b.
A minimum of two detector thimbles per core quadrant, and Sufficieni svable detectdrs, drive, and readout equipment to map c.
these thimbles.
APPLICABILITY:
When the Movable Incore Detection System is used for:
Recalibration of the Excore Neutron Flux Detection System, a.
b.
Monitoring the QUADRANT POWER TILT RATIO, or Measurement of F,(X,Y,Z) and F,,(X,Y).
c.
ACTION:
With the Movable Incore Detection System inoperable, do not use the a.
system for the above applicable monitoring or calibration functions.
b.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE RE001REMENTS 4.3.3.2 The Movable Incore Detection System shall be demonstrated OPERABLE at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by normalizing each detector output when required for:
Recalibration of the Excore Neutron Flux Detection System, or a.
b.
Monitoring the QUADRANT POWER TILT RATIO, or Measurement of F,(X,Y,Z) and F,,(X,Y).
c.
WOLF CREEK - UNIT 1 3/4 3-43 Amendment No.61
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WOLF CREEK - UNIT 1 3/4 3-44 Amendment No. 75 i
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