ML20214J812
| ML20214J812 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 11/20/1986 |
| From: | Jabbour K Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20214J815 | List: |
| References | |
| NUDOCS 8612010481 | |
| Download: ML20214J812 (7) | |
Text
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DUKE POWER COMPANY NORTH CAROLINA ELECTRIC MEMBERSHIP CORPORATION SALUDA RIVER ELECTRIC COOPERATIVE, INC.
DOCKET NO. 50-4,13 CATAWBA NUCLEAR STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 19 License No. NPF-35 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment to the Catawba Nuclear Station, Unit 1 (the facility) Facility Operating License No. NPF-35 filed by the Duke Power Company acting for itself, North Carolina Electric Membership Corporation and Saluda River Electric Cooperative, Inc., (licensees) dated July 9,1986, and supplemented September 12, 1986, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comission's regulations as set forth in 10 CFR Chapter I; B.
The facility will operate in confonnity with the application, as amended, the provisions of the Act, and the rules and regulations of the Comission; 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 Comission's regulations set forth in 10 CFR Chapter I; D.
The issuance # this license amendment will not be inimical to the comon defense and security or to the health and safety of the public; 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.
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2.
Accordingly, the license is hereby amended by page changes to the Technical Specifications as indicated in the attachments to this license amendment and Paragraph 2.C.(2) of Facility Operating License No. NPF-35 is hereby amended to read as follows:
(2) Technical Specifications and Environnental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No.19, and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated into this license.
Duke Power Company shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license arrendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Kahtan Jabbour, Project Manager PWR Project Directorate No. 4 Division of PWR Licensing-A Attachtrent:
Technical Specification Changes Date of Issuance: November 20, 1986
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\\.....J DUKE POWER COMPANY NORTH CAROLINA MUNICIPAL POWER AGENCY NO. 1 PIEDM0NT MUNICIPAL POWER AGENCY DOCKET NO. 50-414 CATAWBA NUCLEAR STATION, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 9 License No. NPF-52 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment to the Catawba Nuclear Station, Unit 2 (the facility) Facility Operating License No. NPF-52 filed by the Duke Power Company acting for itself, North Carolina Municipal Power Agency No. I and Piedmont Municipal Power Agency, (licensees) dated July 9, 1986, and supplemented September 12, 1986, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comission's regulations as set forth in 10 CFR Chapter I; B.
The facility will operate in confonnity with the application, as amended, the provisions of the Act, and the rules and regulations of the Comission; C.
There is reasonable assurance: (1)thattheactivitiesauthorizedby 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 Comission's regulations set forth in 10 CFR Chapter I; 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; 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.
.2.
Accordingly, the license is hereby amended by page changes to the Technical Specifications as indicated in the' attachments to this license amendment and Paragraph 2.C.(2) of Facility Operating License No. NPF-52 is hereby amended to read as follows:
(2) Technical Specifications and Environmental Protection Plan l
The Technical Specifications contained in Appendix A, as revised through Amendment No. 9, and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are l
hereby incorporated into this license. Duke Power Company shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
e 3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION (9
Kahtan Jabbour, Project Manager PWR Project Directorate No. 4-Division of PWR Licensing-A
Attachment:
Technical Specification Changes Date of Issuance: November-202 1986
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f ATTACHMENT TO LICENSE AMENDMENT NO. 19 FACILITY OPERATING LICENSE NO. NPF-35 DOCKET N0. 50-413 AND TO LICENSE AMENDMENT NO. 9 FACILITY OPERATING LICENSE NO. NPF-52 DOCKET NO. 50-414 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised page is identified by Amendment number and contains a vertical line indicating the area of change. The corresponding overleaf page is also provided to maintain document completeness.
Amended Overleaf Page Page 6-6 6-5 I
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TABLE 6.2-1 MINIMUM SHIFT CREW COMPOSITION POSITION NUMBER OF INDIVIDUALS REQUIRED TO FILL POSITION One Unit in Mode Both Units in 1, 2, 3 or 4 and Both Units in MODE 5 or 6 One Unit in Mode 5 MODE 1, 2, 3, or 4 or Defueled or 6 or Defueled SS 1
1 1
SR0 1
None##
1 R0 3#
2#
3#
NE0 3#
3#
3#
STA 1
None 1
Shift Supervisor with a Senior Operator license SS Individual with a Senior Operator license SRO Individual with an Operator license RO Nuclear Equipment Operator NE0 STA -
'A The Shift Crew Composition may be one less than the minimum requirements of
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Table 6.2-1 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 of on-duty shift crew members provided immediate action is taken to restore the shift crew composition to within the minimum requirements of Table 6.2-1.
This provision does not permit any shift crew position to be unmanned upon shift change due to an oncoming shift crewman being late or absent.
During any absence of the Shift Supervisor from the control room while the unit is in MODE 1, 2, 3, or 4, an individual (other than the Shift Technical Advisor *) with a valid Senior Operator license shall be designated to assume the control room command function.
During any absence of the Shift Supervisor from the control room while the unit is in MODE 5 or 6, an individual with a valid Senior Operator license or Operator license shall be designated to assume the control room command function.
- 0n occasion when there is a need for both the Shift Supervisor and the SR0 to be absent from the control room, the STA shall be allowed to assume the control room command function and serve as the SRO in the control room provided that:
(1) the Shift Supervisor is available to return to the control room within 10 minutes, (2) the assumption of SR0 duties by the STA be limited to periods not in excess of 15 minutes duration and a total time not to exceed I hour during any 8-hour shift, and (3) the STA has a Senior Operator license on the unit.
- At least one of the required individuals must be assigned to the designated position for each unit.
- At least one licensed Senior Operator or licensed Senior Operator Limited to Fuel Handling must be present during CORE ALTERATIONS on either unit, who has no other concurrent responsibilities.
CATAWBA - UNITS 1 & 2 6-5
ADMINISTRATIVE CONTROLS 6.2.3 CATAWBA SAFETY REVIEW GROUP FUNCTION 6.2.3.1 The Catawba Safety Review Group (CSRG) shall function to examine plant operating characteristics, NRC issuances, industry advisories, REPORTABLE EVENTS, and other sources which may indicate areas for improving plant safety. The CSRG shall make detailed recommendations for revised pro-cedures, equipment modifications, or other means of improving plant safety to the Director, Nuclear Safety Review Board.
COMPOSITION 6.2.3.2 The CSRG shall be composed of a chairman and at least four dedicated, full-time qualified individuals located onsite.
RESPONSIBILITIES 6.2.3.3 The CSRG shall be responsible for maintaining surveillance of plant activities to provide independent verification
- that these activities are performed correctly and that human errors are reduced as much as practical.
RECORDS 6.2.3.4 Records of activities performed by the CSRG shall be prepared, main-tained, and forwarded each calendar month to the Director, Nuclear Safety Review Board.
6.2.4 SHIFT TECHNICAL ADVISOR 6.2.4.1 The Shift Technical Advisor shall serve in an advisory capacity to the Shift Supervisor.
6.3 UNIT STAFF QUALIFICATIONS 6.3.1 Each member of the unit staff shall meet or exceed the minimum qualifi-cations of ANSI N18.1-1971 for comparable positions, except for the Radiation Protection Manager, who shall meet or exceed the qualifications of Regulatory Guide 1.8, Septcmber 1975.
The licensed Operators and Senior Operators shall also meet or exceed the minimum qualifications of the supplemental require-ments specified in Sections A and C of Enclosure 1 of the March 28, 1980 NRC letter to all licensees.**
6.4 TRAINING 6.4.1 A retraining and replacement training program for the unit staff shall be maintained under the direction of the Station Manager and shall meet or exceed the requirements and recommendations of Section 5.5 of ANSI N18.1-1971 and Appendix A of 10 CFR Part 55 and the supplemental requirements specified in Sections A and C of Enclosure 1 of the March 28, 1980 NRC letter to all licensees, and shall include familiarization with relevant industry operational experience identified by the CSRG.
l
- Not responsible for sign-off function.
- Except that the experience and other considerations described in Duke Power i
l Company's letters dated August 28, 1985, and July 8, 1986, are acceptable for i
the six and two applicants for SR0 licenses identified therein, respectively.
CATAWBA - UNITS 1 & 2 6-6 Amendment No.19(Unit 1)
Amendment No. 9(Unit 2)
.