ML20235P238
| ML20235P238 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 02/14/1989 |
| From: | Calvo J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20235P241 | List: |
| References | |
| GL-88-06, GL-88-6, NUDOCS 8903020149 | |
| Download: ML20235P238 (9) | |
Text
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NUCLEAR REGULATORY COMMISSION j
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WOLF CREEK NUCLEAR-0PERATING CORPORATION WOLF CREEK GENERATING STATION DOCKET NO. 50-482 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 24 License No. NPF-42 1.
The Nuclear Regulatory Comission (the Comission) 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 October 19, 1988, complies with the standards and require-ments of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter I; i
B.
The facility will operate in ccnformity with the application, as amended, the provisions of the Act, and the rules and regulations of the Comission; C.
There is reasonable assurance:
(1) 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 Comissior.'s regulations; D.
The issuance of this license 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.
i 8903020149 890214 PDR ADOCK 05000482 P
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. 2.
Accc Jingly, the license is amended by changes to the Technical Specif1-cat 1w.s as indicated in the attachment to this license amendment and Paragraph 2.C.(2) of Facility Operating License No. NPF-4? is hereby amended to read as follows:
2.
Technical Specifications The Technical Specifications contained in Appendix A, as ravised through Amendment No. 24, and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, Ere hereby incorporated in the license. The Corporation shall operate
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the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
The license amendment is effective as of its date of issuance.
FORTHENUCLEIRREGULATORYCOMMISSION N
frt Jose A. Calvo, Director Project Directorate - IV Division of Reactor Projects - III, IV, V and Special Projects Office of Nuclear Reactor Regulation
Attachment:
Chonges to the Technical Specifications Date of Issuance: February 14, 1989 l
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1 ATTACHMENT TO LICENSE AMENDMENT NO. 24 FACILITY OPERATING LICENSE NO. NPF-42 DOCKET NO. 50-482 Revise Appendix A Technical Specifications by removing the pages identified below and inserting the enclosed pages. The revised pages are identified by l
1 amendment number and contain marginal lines indicating the area of change.
The corresponding overleaf pages are also provided to maintain document completeness.
REMOVE PAGES INSERT PAGES 1
XX XX 6-1 6-1 l
6-2 6-2 6-3 6-3 6-4 6-4 l
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DESIGN FEATURES SECTION PAGE 5.1 SITE 5.1.1 EXCLUSION AREA..............................................
5-1 5.1.2 LOW POPULATION 20NE.........................................
5-1 5.1.3 MAPS DEFINING UNRESTRICTED AREAS AND SITE BOUNDARY FOR RADIOACTIVE GASEOUS AND LIQUID EFFLUENTS..............
5-1 FIGURE 5.1-1 EXCLUSION AREA.......................................
5-2 FIGURE 5.1-2 LOW PO PU LATI ON 2 0N E..................................
5-3 FIGURE 5.1-3 BOUNDARY FOR GASEOUS EFFLUENTS.......................
5-4.
FIGURE 5.1-4 BOUNDARY FOR LIQUID EFFLUENTS........................
5-5
- 5. 2 CONTAINMENT 5.2.1 CONFIGURATION...............................................
5-1 5.2.2 DESIGN PRESSURE AND TEMPERATURE.............................
5-1 5.3 REACTOR CORE 5.3.1 FUEL ASSEMBLIES.............................................
5-6 5.3.2 CONTROL ROD ASSEMBLIES......................................
5-6 5.4 REACTOR COOLANT SYSTEM 5.4.1 DESIGN PRESSURE AND TEMPERATURE.............................
5-6 5.4.2 V0LUME......................................................
5-6 I
5.5 METEOROLOGICAL TOWER LOCATION.................................
5-6 5.6 FUEL STORAGE 5.6.1 CRITICALITY.................................................
5-7 5.6.2 DRAINAGE....................................................
5-7 5.6.3 CAPACITY....................................................
.5-7 FIGURE 5.6-1 MINIMUM REQUIRED FUEL ASSEMBLY EXPOSURE AS A
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FUNCTION OF INITIAL ENRICMMENT TO PERMIT STORAGE
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IN REGION 2........................................
5-8 1
5.7 COMPONENT CYCLIC OR TRANSIENT LIMIT...........................
5-7 TABLE 5.7-1 COMPONENT CYCLIC OR TRANSIEN1 LIMIT...................
5-9 WOLF CREEK - UNIT 1 XIX I
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ADMINISTRATIVE CONTROLS.
SECTION PAGE i
6.1 RESPONSIBILITY................................................
6-1 l
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- 6. 2 ORGANIZATION
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6.2.1 ONSITE AND OPERATING CORPORATION ORGANIZATION...............
6-1 6.2.2 UNIT STAFF...................................................
6-1 FIGURE 6.2-1 DELETED..............................................
6-3
' FIGURE 6.2-2 DELETED..............................................
6-4 TABLE 6.2-1 MINIMUM SHIFT CREW COMPOSITION........................
6-5 15. 2. 3 INDEPENDENT SAFETY ENGINEERING GROUP (ISEG)
Function....................................................
6 Composition.................................................
6-6 Responsibilities............................................
6-6
. Records.....................................................
6-6 6.2.4 SHIFT TECHNICAL ADVIS0R.....................................
6-6 6.3 UNIT STAFF QUALIFICATIONS.....................................-
6-6
- 6. 4 TRAINING......................................................
6-7 6.5 REVIEW AND AUDIT 6.5.1 PLANT SAFETY REVIEW COMMITTEE (PSRC)
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Function....................................................
6-7 Composition.................................................
6-7
. Alternates..................................................
6-7 Meeting Frequency...........................................
6-8 Quorum......................................................
6-8 Responsibilities............................................
6-8 1
1 Records.....................................................
6-9 i
WOLF CREEK - UNIT 1 XX Amendment No. 24 l
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ADMINISTRATIVE CONTROLS 6.1 RESPONSIBILITY 6.1.1 The Plant Manager shall be responsible for overall Unit operation and shall delegate in writing the succession to this responsibility during his absence.
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6.1.2 The Supervising Operator, under the Shift Supervisor, shall be responsible for the control room command function. A management directive to this effect, signed by the President and Chief Executive Officer shall be reissued to all station personnel on an annual basis.
6.2 ORGANIZATION 6.2.1 Onsite and Operatina Corporation Organization Onsite and operating corporation organizations shall be established for unit operation and corporate management, respectively.
The onsite and operating corporation organizations shall include the positions for the activities affect-ing the safety of the nuclear power plant.
a.
Lines of authority, responsibility, and communication shall be estab-lished and defined for the highest management levels through inter-mediate levels to and including all operating organization positions.
These relationships shall be documented and updated, as appropriate, in the form of organization charts, functional descriptions of depart-mental responsibilities and relationships, and job descriptions for key personnel positions, or equivalent forms of documentation.
These requirements shall be documented in the Updated Safety Analysis Report.
b.
The Plant Manager shall be responsible for overall unit safe operation and shall have control of those onsite activities necessary for safe operation and maintenance of the plant.
The President and Chief Executive Officer shall have corporate respon-c.
sibility for overall plant nuclear safety and shall take any measures needed to ensure acceptable performance of the staff in operating, maintaining, and providing technical support to the plant to ensure nuclear safety.
d.
The individuals who train the operating staff and those who carry out the health physics and quality assurance functions may report to the appropriate onsite manager; however, they shall have sufficient organizational freet'om to ensure their independence from operating pressures.
6.2.2 Unit Staff a.
Each on duty shift shall be composed of at least the minimum shift crew composition shown in Table 6.&l; WOLF CREEK - UNIT 1 6-1 Amerdment No. #, 24
ADMINISTRATIVE CONTROLS Unit Staff (Continued) b.
At least one licensed Operator shall be in the control room when fuel is in the reactor.
In addition, while the Unit is in MODE 1, 2, 3 or 4, at least one licensed Senior Operator shall be in the control room; c.
An individual from the Health Physics Group *, qualified in radiation protection procedures, shall be on site when fuel is in the reactor; d.
ALL CORE ALTERATIONS shall be observed and directly supervised by either a licensed Senior Operator or licensed Senior Operator Limited to Fuel Handling who has no other concurrent responsibilities during this operation; e.
A site Fire Brigade of at least 5 members
- shall be maintained onsite at all times.
The Fire Brigade shall not include the Shift Supervisor, and the two other members of the minimum shift crew necessary for safe shutdown of the Unit and any personnel required for other essential functions during a fire emergency; and f.
Administrative procedures shall be developed and implemented to limit the working hours of Unit Staff who perform safety-related functions; e.g., Senior Operators, Operators, Health Physicists, Auxiliary opera-tors, and key maintenance personnel.
The amount of overtime worked by Unit Staff members performing safety-related functions shall be limited in accordance with the NRC Policy Statement on working hours (Generic Letter No. 82-12).
g.
The Operations Supervisor shall hold a senior reactor operator license.
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- May be less than the minimum requirements for a period of time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in order to accommodate unexpected absence provided immediate action is taken to fill the required positions.
WOLF CREEK - UNIT 1 6-2 Amendment No.24 L__- _ _- _.
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Figure 6.2-1 This figure has been deleted I
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WOLF CREEK - UNIT I 6-3 Amendment No. f.29,24 m
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Figure 6.2-2 This figure has been deleted j -.
l WOLF CREEK - UNIT 1 6-4 Amendment No. 2,23,29,24 1
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