ML20206B084
| ML20206B084 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 04/02/1987 |
| From: | Jabbour K Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20206B089 | List: |
| References | |
| NUDOCS 8704080324 | |
| Download: ML20206B084 (10) | |
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DUKE POWER COMPANY NORTH CAROLINA ELECTRIC MEMBERSHIP CORPORATION SALUDA RIVER ELECTRIC COOPERATIVE, INC.
DOCKET NO. 50-413 CATAWBA NUCLEAR STATION, UNIT 1 i
AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 27 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 Doerating 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 31, 1985, and supplemented November 8, 1985 March 7 and October 1 and 10, 1986, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and 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 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-35 is hereby amended to read as follows:
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c (2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 27, 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 amendment is effective as of its date of issuance.
FOR THE NdCLEAR REGULATORY COMMISSION Kahtan Jabbour, Project Manager PWR Project Directorate No. 4 Division of PWR Licensing-A
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DUKE POWER COMPANY NORTH CAROLINA MJNICIPAL POWER AC1ENCY NO 1 PIEDMONT MUNICIPAL POWER l'IENCY DOCKET NO. 50-414 CATAWBA NUCLEAR STATION, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.17 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 31, 1985, and supplemented November 8,1985, March 7 and October 1 and 10, 1986, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comission's rules and regulations as set forth in 10 CFR Chapter I; u
B.
The facility will operate in conformity with the application, as amended, the provisions of the fict, and the rules and regulations of the Commission; C.
There is reasonable assurance: (1) that the activities authorized by this amendment can be conducted without endangering the health and l
safety of the public, and (ii) that such activities will be conducted in como11ance 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 The Technical Specifications contained in Appendix A, as revised through Amendment No. 17, 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 amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
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Kahtan Jabbour, Project Manager PWR Project Directorate No. 4 Division of PWR Licensing-A I
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Technical Specification Changes Date of Issuance: April 2, 1987 4
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ATTACHMENT TO LICENSE AMENDMENT NO. 27 FACILITY OPERATING LICENSE NO. NPF-35 DOCKET NO. 50-413 AND TO LICENSE AMENDMENT NO. 17 FACILITY C'ERATING LICENSE NO. NPF-52 DOCKET NO. 50-414 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and contain vertical lines indicating the areas of change. The corresponding overleaf pages are also provided to maintain document completeness.
Amended Overleaf Fage Page 6-7 6-8 6-12 6-11 6-13 6-14 6-21 6-22
ADNINISTRATIVE CONTROLS 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.
6.5 REVIEW AND AUDIT 6.5.1 TECHNICAL REVIEW AND CONTROL ACTIVITIES 6.5.1.1 Each procedure and program required by Specification 6.8 and other procedures which affect nuclear safety, and changes thereto, shall be prepared by a qualified individual / organization.
Each such procedure, and changes thereto, shall be reviewed by an individual / group other than the individual /
group which prepared the procedure, or changes thereto, but who may be from the same organization as the individual / group which prepared the procedure, or changes thereto.
6.5.1.2 Proposed changes to the Appendix A Technical Specifications shall be prepared by a qualified individual / organization.
The preparation of each proposed Technical Specification change shall be reviewed by an individual /
group other than the individual / group which prepared the proposed change, but who may be from the same organization as the individual / group which prepared the proposed change.
Proposed changes to the Technical Specifications shall be approved by the Station Manager.
6.5.1.3 Proposed modifications to unit nuclear safety-related structures systems,andcomponentsshallbedesignedbyaqualifiedindividual/ organization.
Each such modification shall be reviewed by an individual / group other than the individual / group which designed the modification, but who may be from the same organization as the individual / group which designed the modification.
Proposed modifications to nuclear safety-related structures, systems, and components shall be approved prior to implementation by the Station Manager; or by the Operating Superintendent, the Technical Services Superintendent, the Maintenance Superintendent, or the Superintendent of Integrated Scheduling, as previously designated by the Station Manager.
6.5.1.4 Individuals responsible for reviews performed in accordance with Specifications 6.5.1.1, 6.5.1.2, and 6.5.1.3 shall be members of the station supervisory staff, previously designated by the Station Manager to perform such reviews.
Review of environmental radiological analysis procedures shall be performed by the Corporate Syst u Health Physicist or his designee.
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 the appropriate designated station review personnel.
6.5.1.5 Proposed tests and experiments which affect station nuclear safety and are not addressed in the FSAR or Technical Specifications shall be reviewed by the Station Manager; or by the Operating Superintendent, the Technical Services Superintendent, the Maintenance Superintendent, or the Superintendent of Integrated Scheduling, as previously designated by the Station Manager.
CATAWBA - UNITS 1 & 2 6-7 Amendment No. 27 Unit 1 Amendment No.17 Unit 2
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ADMINISTRATIVE CONTROLS t
j TECHNICAL REVIEW AND CONTROL ACTIVITIES (Continued) i
- 6. 5.1. 6 All REPORTABLE EVENTS and all violations of Technical Specifications l
shall be investigated and a report prepared which evaluates the occurrence and which provides recommendations to prevent recurrence.
Such reports shall be approved by the Station Manager and transmitted to the Vice President, Nuclear Production, and to the Director of the Nuclear Safety Review Board.
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6.5.1.7 The Station Manager shall assure the performance of special reviews l
and investigations, and the preparation and submittal of reports thereon, as i
requested by the Vice President, Nuclear Production.
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- 6. 5.1. 8 The station security program, and implementing procedures shall be
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reviewed at least once per 12 months.
Recommended changes shall be approved by the Superintendent of Station Services and transmitted to the Vice President, l
1 Nuclear Production, and to the Director of the Nuclear Safety Review Board.
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- 6. 5.1. 9 The station emergency plan, and implementing procedures, shall be reviewed at least once per 12 months.
Recommended changes shall be approved by the Station Manager and transmitted to the Vice President, Nuclear l
Production, and to the Director of the Nuclear Safety Rr. view Board.
6.5.1.10 The Station Manager shall assure the peiformance of a review by a j
qualified individual / organization of every unplanned onsite release of radio-i active material to the environs including the preparation and forwarding of reports covering evaluation, recommendations, and disposition of the corrective ACTION to prevent recurrence to the Vice President, Nuclear Production and to l
the Nuclear Safety Review Board.
6.5.1.11 The Station Manager shall assure the performance of a review by a i
j qualifed individual / organization of changes to the PROCESS CONTROL PROGRAM,
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l OFFSITE DOSE CALCULATION MANUAL, and Radwaste Treatment Systems.
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6.5.1.12 Reports documenting each of the activities performed under Specifications 6.5.1.1 through 6.5.1.11 shall be maintained.
Copies shall be provided to the Vice President, Nuclear Production, and the Nuclear Safety l
Review Board.
6.5.2 NUCLEAR SAFETY REVIEW BOARD (NSR8)
FUNCTION I
i 6.5.2.3 The NSR8 shall function to provide independent review and audit of designated activities in the areas of:
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a.
Nuclear power plant operations, b.
Nuclear engineering, i
c.
Chemistry and radiochemistry, l
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CATAW8A - UNITS 1 & 2 6-8 Amendment No. 27 (Unit 1)
Amendment No.17 (Unit 2)
ADMINISTRATIVE CONTROLS RECORDS (Continued) b.
Reports of reviews encompassed by Specification 6.5.2.8 above, shall be prepared, approved, and forwarded to the Vice President, Nuclear Production, and to the Executive Vice President, Power Operations, within 14 days following completion of the review; and c.
Audit reports encompassed by Specification 6.5.2.9 above, shall be forwarded to the Vice President, Nuclear Production, and to the Execu-tive Vice President, Power Operations, and to the management post-tions responsible for the areas audited within 30 days after completion of the audit by the auditing organization.
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 to 10 CFR Part 50 and b.
Each REPORTABLE EVENT shall be reviewed by the Station Manager; or by (1) Operating Superintendent; (2) Technical Services Superintendent; (3) Maintenance Superintendent; or (4) Superintendent of Integrated Scheduling, as previously designated by the Station Manager, and the results of this review shall be submitted to the NSRB and the Vice President-Nuclear Production.
6.7 SAFETY LIMIT VIOLATION I
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 telephone 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-Nuclea,-
Production 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 />, f
b.
A Safety Limit Violation Report shall be prepared.
The report shall be reviewed by the Operating Superintendent and Station Manager.
This report shall describe:
(1) applicable circumstances preceding the violation, (2) effects of the violation upon facility components, systems, or structures, and (3) corrective action taken to prevent recurrence; c.
The Safety Limit Violation Report shall be submitted to the Commission, the NSRB and the Vice President-Nuclear Production within 14 days of the violation; and d.
Critical operation of the unit shall not be resumed until authorized by the Commission.
CATAWBA - UNITS 1 & 2 6-12 Amendment No. 27 Unit 1 Amendment No.17 Unit 2
I ADMINISTRATIVE CONTROLS 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 require-ments of NUREG-0737 and Supplement No. 1 to NUREG-0737 as stated in Generic Letter No. 82-33; c.
Security Plan implementation;*
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Emergency Plan implementation; e.
PROCESS CONTROL PROGRAM implementation; f.
OFFSITE DOSE CALCULATION MANUAL implementation; and g.
Quality Assurance Program implementation for effluent and environmental monitoring.
6.8.2 Each procedure of Specification 6.8.1, and changes thereto, shall be reviewed and approved by the Station Manager; or by:
(1) Operating Superin-tendent, (2) Technical Services Superintendent, (3) Maintenance Superintendent, or (4) Superintendent of Integrated Scheduling, as previously designated by the Station Manager; prior to implementation and shall be reviewed periodically as set forth in administrative procedures.
6.8.3 Temporary changes to procedures of Specification 6.8.1 may be made pro-vided:
a.
The intent of the original procedure is not altered; b.
The change is approved by two members of the plant management staff, at least one of whom holds a Senior Operator license on the unit affected; and c.
The change is documented, reviewed, and approved by the Station Manager; or by:
(1) Operating Superintendent, (2) Technical Services Superintendent, (3) Maintenance Superintendent, or (4) Superintendent of Integrated Scheduling, as previously designated by the Station Manager; within 14 days of implementation.
6.8.4 The following programs shall be established, implemented, and maintained:
a.
Primary 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 containment spray, Safety Injection, chemical
- Review and approval may be performed by the Superintendent of Station Services.
Amendment No. 27 Amendment No.17 (Unit 1)
CATAWBA - UNITS 1 & 2 6-13 (Unit 2)
D ADMINISTRATIVE CONTRO}S RECORD RETENTION (Continued) h.
Records of inservice inspections performed pursuant to these Technical Specifications; i.
Records'of reviews performed for changes made to procedures or equipment or revius of tests and experiments pursuant to 10 CFR 50.59; j.
Records of meetings of the NSRB and reports required by Specification 6.5.1.10; k.
Records of the service lives of all hydraulic and mechanical snubbers required by Specification 3.7.8 including the date at which the service life commences and associated installation and maintenance records; 1.
Records of secondary water sampling and water quality; and m.
Records of analyses required by the Radiological Environmental Monitoring Program that would permit evaluation of the accuracy of the analysis at a later date.
This should include procedures effective at specified times and QA records showing that these procedures were followed.
6.10.3 Records of quality assurance activities required by the Operational Quality Assurance Manual shall be retained for a period of time as recommended by ANSI N.45.2.9-1974.
E.11 RADIATION PROTECTION PROGRAM 6.11 Procedures for personnel radiation protection shall be prepared consistent with the requirements of 10 CFR Part 20 and shall be approved, maintained, and adhered to for all operations involving personnel radiation exposure.
6.12 HIGH RADIATION AREA 6.12.1 In lieu of the " control device" or " alarm signal" required by paragraph 20.203(c)(2) of 10 CFR Part 20, each high radiation area, as defined in 10 CFR Part 20, in which the intensity of radiation is equal to or less than 1000 mR/h at 45 cm (18 in.) from the radiation source or from any surface which the radiation penetrates shall be barricaded and conspicuously posted as a high radiation area and entrance thereto shall be controlled by requiring issuance of a Radiation Work Permit (RVP).
Individuals qualified in radiation protection procedures (e.g., Health Physics Technician) or personnel continu-ausly escorted by such individuals may be excmpt from the RWP issuance require-ment during the performance of their assigned duties in high radiation areas with exposure rates equal to or less than 1000 mR/h, provided they are other-wise following plant radiation protection procedures for entry into such high radiation areas.
Any individus1 or group of individuals permitted to enter such areas shall be provided with or accompanied by one or more of the following:
a.
A radiation monitoring device which continuously indicates the radiation dose rate in the area; or b.
A radiation monitoring device which continuously integrates the radiation dose rate in the area and alarms when a preset integrated CATAWBA - UNITS 1 & 2 6-21 Amendment No. 27 (Unit 1)
Amendment No.17 (Unit 2)