ML20217F597
| ML20217F597 | |
| Person / Time | |
|---|---|
| Site: | Callaway  |
| Issue date: | 03/23/1998 |
| From: | Westreich B NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20217F600 | List: |
| References | |
| NUDOCS 9804010056 | |
| Download: ML20217F597 (6) | |
Text
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UNITED STATES
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NUCLEAR REGULATORY COMMISSION I
WASHINGTON, D.C. 20066 0001
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UNION ELECTRIC COMPANY CALLAWAY PLANT UNIT 1 DOCKET NO. 50-483 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.122 License No. NPF-30 1.
The Nuclear Regulatory Commission (the Commission) has found that:
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A.
The application for amendment to the Callaway Plant Unit 1(the facility) Facility Operating License No. NPF-30 filed by the Union Electric Company (the Company), dated April 24,1997, as supplemented by letters dated June 6,1997, and June 27,1997, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and i
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 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. NPF-30 is hereby amended to read as follows:
9804010056 980323 PDR ADOCK 05000403 P
d (2)
Technical Soecificeans and EnvirDamentaL2rolastionfian The Technical Specifications contained in Appendix A, as revised through Amendrnent No.122 and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license. The licensee shall operate 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.
FOR THE NUCLEAR REGULATORY COMMISSION
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Barry. Westreich, Project Manager Project Directorate IV-2 Division of Reactor Projects lil/IV -
Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of issuance: March 23,1998
,e ATTACHMENTTO LICENSE AMENDMENT NO.122 FACILITY OPERATING LICENSE NO. NPF-30 DOCKET NO. 50-483 Replace the following pages of the Appendix A Technical Specifications with the attached pages. The revised pages are identified by Amendment number and contain marginallines indicating the areas of change. The overleaf pages are provided to maintain document completeness.
REMOVE INSERT 6-1 6-1 6-14 6-14 6-15 6-15 i
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a ADMINISTRATIVE' CONTROLS 6.1 RESPONSIBILITY 6.1.1 The Manager. Callaway Plant, shall be responsible for overall unit operation and shall delegate in writing the succession to this responsibility during his absence.
6.1.2 The Shift Supervisor (or during his absence from the control room, a designated individual) shall be responsible for the control room command function. A management directive to this effect. signed by the Vice President-and Chief Nuclear Officer shall be reissued to all station personnel on an annual basis, 6.2 ORGANIZATION 6.2.1 Onsite and Offsite Oraanization An onsite and offsite organization shall be established for unit operation and corporate management. The onsite and offsite organization shall include the positions for activities affecting the safety of the. nuclear power plant.
a.
Lines of authority, responsibility and communication shall be established and defined for the highest management levels through intermediate levels to and including all operating organization positions. These relationships shall be documented and updated, as appropriate, in the form of organizational charts. functional descri]tions of departmental responsibilities and relationships.
and jo) descriptions for key personnel positions, or equivalent forms of documentation. These' requirements shall be documented in i
the FSAR and updated in accordance with 10 CFR 50.71(e).
b.
The Manager, Callaway Plant shall have responsibility for overall unit safe operation and shall have control over those onsite activities necessary for safe operation and maintenance of the plant.
c.
The Vice President and Chief Nuclear Officer shall have corporate l
responsibility 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 in 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 freedom to ensure their independence from operating pressures.
CALLAWAY. UNIT 1 6-1 Amendment No. 37-A9,122
ADMINISTRATIVE CONTROLS 6.2 ORGANIZATION (Continued)
UNIT STAFF 6.2.2 The Unit organization shall be subject to the following:
Each on duty shift shall be composed of at least the minimum shift l
a.
crew composition shown in Table 6.2-1; At least one licensed Operator shall be in the control room when b.
fuel is in the reactor.
In addition, while the unit is in MODE 1, 2, 3 or 4, at least on's licensed Senior Operator shall be in the control room; An individual from the Health Physics organizationf, qualified in radiation protection procedures, shall be on site when fuel is in c.
the reactor; All CORE ALTERATIONS shall be observed and :lirectly supervised by d.
either a licensed Senior Operator or licensed Senior Operator Limited to Fuel Handling who has no other concurrent responsibil-ities during this operation; A site Fire Brigade of at least five membersi shall be maintained The Fire Brigade shall not include the Shift
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e.
onsite at all times.
Supervisor, and the two other members of the minimum shift crew n: -
necessary for safe shutdown of the unit and any personnel required for other essential functions during a fire emergency; Administrative procedures shall be developed and implemented to f.
limit the working hours of unit staff who perform safety-related functions; e.g., licensed Senior Operators, licensed Operators, health physics personnel, equipment operators, 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);
and The Superintendent, Operations, Shift Supervisors, and Operating The Unit g.
Supervisors shall hold a senior reactor operator license.
Reactor Operator shall hold a reactor operator license or a senior reactor operator license.
WMay 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.
6-2 AmendmentNo.#1,86 CALLAWAY - UNIT 1
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ADMINISTRATIVE CONTROLS ACTIVITIES (Continued) d.
Individuals responsible for reviews performed in accordance with Specifications 6.5.3. la.
6.5.3. lb.. and 6.5.3.lc., shall be members of the management staff previously designated by the Manager. Operations Support.
Each such review shall include a determination of whether or not additional, cross-disciplinary, review is necessary.
If deemed necessary, such review shall be performed by qualified personnel of the appropriate discipline; e.
Each review shall include a determination of whether or not an unreviewed safety question is involved.
Pursuant to Section 50.59, 10 CFR. NRC approval of items involving unreviewed safety questions shall be obtained prior to the Manager. Callaway Plant approval for implementation; and f.
The Plant Security Plan and Radiological Emergency Response Plan, and implementing procedures, shall be reviewed at least once per 12 months.
Recommended changes to the implementing procedures shall be approved in accordance with 6.5.3.1.a.
Recommended changes to the Plans shall be reviewed pursuant to the Operational Quality Assurance Manual and ap3 roved by the Manager. Callaway Plant.
NRC approval shall be o]tained as appropriate.
RECORDS 6.5.3.2 Records of the above activities shall be provided to the Manager.
Callaway Plant. ORC and/or NSRB as necessary for required reviews.
6.6 REPORTABLE EVENT ACTION 6.6.1 The following actions shall be taken for REPORTABLE EVENTS:
a.
The Commission shall be notified and a report submitted pursuant to the requirements of Section 50.73 of 10 CFR Part 50, and b.
Each REPORTABLE EVENT shall be reviewed by the ORC and submitted to the NSRB and the Vice President and Chief Nuclear Officer.
l 6.7 SAFETY LIMIT VIOLATION 6.7.1 The following actions shall be taken in the event a Safety Limit is violated:
a.
The NRC Operations Center shall be notified by '.elephone as soon as possible and in all cases within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
The Vice President and Chief Nuclear Officer and the NSRB shall be notified within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />; b.
A Safety Limit Violation Report shall be pre)ared.
The report shall be reviewed by the ORC.
This report s1all describe:
(1) applicable circumstances preceding the violation; (2) effects of the violation upon facility components, systems or structures; n d (3) corrective action taken to prevent recurrence; CALLAWAY - UNIT 1 6-14 Amendment No. 25.39.107.122
ADMINISTRATIVE CONTROLS SAFETY LIMIT VIOLATION (Continued) c.
The Safety Limit Violation Report shall be submitted to the Commission, the NSRB and the Vice President and Chief Nuclear Officer within 14 days of the violation; and d.
Critical operation of the unit shall not be resumed until authorized by the Commission.
6,8 PROCEDURES AND PROGRAMS 6.8.1 Written procedures shall be established, implemented. and maintained covering the activities referenced below:
a.
The applicable procedures recommended in Appendix A, of Regulatory Guide 1.33. Revision 2. February 1978:
b.
The emergency operating procedures required to implement the requirements of NUREG-0737 and Supplement 1 to NUREG-0737 as stated in Section 7.1 of Generic Letter No. 82-33; c.
Plant Security Plan implementation; d.
Radiological Emergency Response Plan implementation; e.
PROCESS CONTROL PROGRAM implementation, f.
OFFSITE DOSE CALCULATION MANUAL implementation, g.
Quality Assurance Program implementation for effluent and environmental monitoring. and h.
Fire Protection Program implementation.
6.8.2 Each procedure and administrative policy of Specification 6.8.1 above.
and changes thereto, including temporary changes shall be reviewed prior to implementation as set forth in Specification 6.5 above.
6.8.3 The plant Administrative Procedures and changes thereto shall be reviewed in accordance with the Operational Quality Assurance Manual and approved in accordance with Saecification 6.5.3.1.
The associated implementing procedures and clanges thereto shall be reviewed and approved in accordance with Specification 6.5.3.1.
6.8.4 The following programs shall be established implemented and maintained:
a.
Reactor Coolant Sources Outside Containment A program to reduce leakage from those portions of systems outside containment that could contain highly radioactive fluids during a serious transient or accident to as low as practical levels.
The systems include the recirculation )ortion of the Containment Spray System. Safety Injection System. Clemical and Volume Control System, and RHR System.
The program shall include the following:
1)
Preventive maintenance and periodic visual inspection requirements, and CALLAWAY - UNIT 1 6-15 Amendment No. 30.39.103.107.122