ML20112D279
| ML20112D279 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 05/30/1996 |
| From: | Berkow H NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20112D282 | List: |
| References | |
| NUDOCS 9606040193 | |
| Download: ML20112D279 (12) | |
Text
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UNITED STATES NUCLEAR REGULATORY COMMISSION f
WASHINGTON, D.C. 20666 0001
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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 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 145 License No. NPF-35 1.
The Nuclear Regulatory Commission (the Commission) 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 January 12, 1995, as supplemented by letter dated June 29, 1995, 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 conformity with the application, the provisions of the Act, 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 safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations set forth in 10 CFR Chapter I; D.
The issuance of this 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.
9606040193 960530 PDR ADOCK 05000413 P
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2.
Accordingly, the license is hereby amended by page 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-35 is hereby amended to read as follows:
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 145, 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 and shall be implemented within 30 days from the date of issuance.
FOR THE NUCLEAR REGU ATORY COMMISSION
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yd Her ert N. Berkow Direc r Pr ject Directorate 11-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Technical Specification Changes Date of Issuance:
May 30, 1996 i
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h UNITED STATE 3 NUCLEAR REGULATORY COMMISSION f
WASHINGTON, D.C. 20086-0001
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DUKE POWER COMPANY NORTH CAROLINA MUNICIPAL POWER AGENCY NO. 1 PIEDMONT MUNICIPAL POWER AGENCY DOCKET NO. 50-414 CATAWBA NUCLEAR STATION. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.139 License No. NPF-52 1.
The Nuclear Regulatory Commission (the Commission) 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 January 12, 1995, as supplemented by letter dated June 29, 1995, 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; 8.
The facility will operate in conformity with the application, 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 set forth in 10 CFR Chapter I; D.
The issuance of this 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.
4q i 2.
Accordingly, the license is hereby amended by page 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-52 is hereby amended to read as follows:
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 139, 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 and shall be implemented within 30 days from the date'of issuance.
FOR THE NUCLE REGULATORY COMMISSION (Y
He ert N. B kow, Director P oject Dire torate II-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Technical Specification Changes Date of Issuance:
May 30,1996
A t
ATTACHMENT TO LICENSE AMENDMENT NO. 145 FACILITY OPERATING LICENSE NO. NPF-35 DOCKET NO. 50-413 AND TO LICENSE AMENDMENT NO. 139 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 pages are identified by amendment number and contain vertical lines indicating the areas of change.
Remove Paaes Insert Paaes 6-7 6-7 6-8 6-8 6-9 6-9 6-10 6-10 6-13 6-13 6-15 6-15 6-21 6-21 l
6
- ~
q ADMINISTRATIVE CONTROLS 6.5 REVIEW AND AUDIT 6.5.1 TECHNICAL REVIEW AND CONTROL ACTIVITIES Programs shall be established for the preparation, review, approval, and retention of documents required by the activities described in Specifications 6.5.1.1. through 6.5.1.11.
Approvals shall be by the head of the appropriate site organization, the head of the appropriate station organization, the head of the appropriate site engineering organization, the head of the environmental organization, or an alternate as specified in other applicable regulatory documents or administrative controls.
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 knowledgeable individual / organization.
Each such procedure, and changes thereto, shall be reviewed by an individual / organization other than the individual / organization which prepared the procedure, or changes thereto.
Procedures, or changes thereto, shall be approved in accordance with Specifications 6.8.2 and 6.8.3.
6.5.1.2 Proposed modifications to unit nuclear safety-related structures, systems, and components shall be designed by a knowledgeable t
individual / organization.
Each such modification shall be reviewed by an individual / organization other than the individual / organization which designed the modification.
6.5.1.3 Individuals responsible for reviews performed in accordance with Specifications 6.5.1.1 and 6.5.1.2 shall be members of the supervisory staff assigned to the site, previously designated by the Site Vice President to perform such reviews.
Review of environmental radiological analysis procedures shall be performed by the General Manager, Environmental Services j
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 site review i
personnel.
6.5.1.4 Proposed changes to the Appendix A Technical Specifications shall be prepared by a knowledgeable individual / organization. The preparation of each proposed Technical Specification change shall be reviewed by an individual /
organization other than the individual / organization which prepared the proposed change.
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 prepared and approved in a manner identical to that of Specification 6.5.1.1.
These proposed tests and experiments shall be reviewed by a knowledgeable individual / organization other than the individual / organization which prepared the proposed tests and experiments.
i CATAWBA - UNITS 1 & 2 6-7 Amendment No.145 (Unit !)
Amendment No. 139 (Unit 2)
D
3 ADMINISTRATIVE CONTROLS TECHNICAL REVIEW AND CONTROL ACTIVITIES (Continued) 6.5.1.6 All REPORTA8LE EVENTS and all violations of Technical Specifications shall.be investigated and a report prepared which evaluates the occurrence and which provides recommendations to prevent recurrence. Such reports shall be i
reviewed by a knowledgeable individual / organization other than the
. individual / organization which prepared the report.
6.5.1.7 Special reviews and investigations, and the preparation of reports thereon, shall be performed by a knowledgeable individual / organization.
6.5.1.8 A knowledgeable individual / organization shall review every unplanned i
onsite release of radioactive material to the environs and prepare reports covering evaluation, recommendations, and disposition of the corrective ACTION to prevent recurrence.
l 6.5.1.9 A knowledgeable individual / organization shall review changes to the PROCESS CONTROL PROGRAM, OFFSITE DOSE CALCULATION MANUAL, and Radwaste Treatment Systems.
6.5.1.10 A knowledgeable individual / organization shall review the Fire Protection Program and implementing procedures.
6.5.1.11 Reports documenting each of the activities performed under Specifica-tions 6.5.1.1 through 6.5.1.10 shall. be maintained.
6.5.2 NUCLEAR SAFETY REVIEW BOARD (NSRB)
FUNCTION 6.5.2.1 The NSRB shall function to provide independent review and audit of designated activities in the areas of:
a.
Nuclear power plant operations, b.
Nuclear engineering, c.
Chemistry and radiochemistry, r
CATAWBA - UNITS 1 & 2 6-8 Amendment No.145 (Unit 1)
Amendment No.139 (Unit 21
1 ADMINISTRATIVE CONTROLS FUNCTION (Continued) d.
Metallurgy, e.
Instrumentation and control, f.
Radiological safety, g.
Mechanical and electrical engineering, and l
l h.
Administrative control and quality assurance practices.
l
'The NSRB shall report to and advise the Senior Vice President, Nuclear Genera-l' tion on those areas of responsibility specified in Specifications 6.5.2.8 and 6.5.2.9.
l ORGANIZATION l
6.5.2.2 The Director, members, and alternate members of the NSRB shall be L
appointed in writing by the Senior Vice President, Nuclear Generation and shall have an academic degree in an engineering or physical science field; and in addition, shall have a minimum of 5 years technical experience, of which a minimum of 3 years shall be in one or more areas given in Specification 6.5.2.1.
In special cases, candidates for appointment without an academic l
degree in engineering or physical science may be qualified with a minimum of f
ten years experience in one of the areas in Specification 6.5.2.1.
No more; l
than two alternates shall. participate as voting members in NSRB activities at any one time.
6.5.2.3 The NSRB shall be composed of at least five members, including the Director. Members of the NSRB may be-from the Nuclear Generation Department, I
from other departments within the Company, or from external to the Company. A j
maximum of one member of the NSRB may be from the Catawba Nuclear Site staff.
6.5.2.4 Consultants shall be utilized as determined by the NSRB Director to provide expert advice to the NSRB.
l 6.5.2.5 Staff assistance may be provided to the NSRB in order to promote the l
proper, timely, and expeditious performance of its functions.
6.5.2.6 The NSRB shall meet at least once per calendar quarter during the initial year of unit operation following fuel loading and at least twice per year thereafter.
6.5.2.7 The quorum of the NSRB necessary for the performance of the NSRB review and audit functions of these Technical Specifications shall consist of the Director, or designated alternate, and at least four other NSRB members including alternates. No more than a minority of the quorum shall have line i
responsibility for operation of Catawba Nuclear Station.
1 i
1 CATAWBA - UNITS 1 & 2 6-9 Amendment No.145 (Unit 1)
Amendment No.139 (Unit 2) i
g ADMINISTRATIVE CONTROLS I
REVIEW 6.5.2.8 The NSRB shall be responsible for the review of:
a.
The safety evaluation for:
(1) changes to procedures, equipment, or systems, and (2) tests or experiments completed under the provision of Section 50.59, 10 CFR to verify that such actions did not consti-tute an unreviewed safety question.
b.
Proposed changes to procedures, equipment, or systems which involve an unreviewed safety question as defined in Section 50.59, 10 CFR; c.
Proposed tests or experiments which involve an unreviewed safety question as defined in Section 50.59, 10 CFR; d.
Violations of Codes, regulations, orders, Technical Specifications, license requirements, or of internal procedures or instructions having nuclear safety significance; e.
Significant operating abnormalities or deviations from normal and expected performance of unit equipment that affect nuclear safety; f.
All REPORTABLE EVENTS; l
g.
All recognized indications of an unanticipated deficiency in some l
aspect of design or operation of structures, systems, or components that could affect nuclear safety; h.
Quality Assurance Program audits relating to station operations and l
actions taken in response to these audits; and 1.
Reports of activities performed under the provisions of Specifications 6.5.1.1 through 6.5.1.10.
AUDITS 6.5.2.9 Audits of site activities shall be performed under the cognizance of the NSRB. These audits shall encompass:
a.
The conformance of unit operation to provisions contained within the Technical Specifications and applicable license conditions; b.
The performance, training, and qualifications of the entire station staff; l
i CATAWBA - UNITS 1 & 2 6-10 Amendment No.145 (Unit 1)
Amendment No.139 (Unit 2) 1
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. I to NUREG-0737 as stated in Generic Letter No. 82-33; c.
Deleted d.
Deleted e.
PROCESS CONTROL PROGRAM implementation; f.
OFFSITE DOSE CALCULATION MANUAL implementation; g.
Quality Assurance Program implementation for effluent and environmental monitoring;
- h.. Technical Review and Control Program implementation.
i.
Fire Protection Program implementation; j.
Plant Operations Review Committee implementation.
k.
Commitments contained in FSAR Chapter 16.0.
6.8.2 Each procedure of Specification 6.8.1, and changes thereto, shall be reviewed and approved by an appropriate division manager, superintendent /
l manager, or one of their designated direct reports prior to implementation and i
shall be reviewed periodically as set forth in administrative procedures.
For i
procedures which implement offsite environmental', technical and laboratory activities, the above review and approval may be performed by the General Manager, Environmental Services or designee.
6.8.3 Temporary changes to procedures of Specification 6.8.1'may be made' provided:
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 1
affected; and c.
The change is approved by an appropriate division manager, superintendent / manager or one of their designated direct reports 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 redura 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 CATAWBA - UNITS 1 & 2 6-13 Amendment No.145 (Unit 1)
Amendment No.139 (Unit 2)
ADMINISTRATIVE CONTROLS PROCEDURES AND PROGRAMS (Continued) e.
Post-Accident S=alina A program which will ensure the capability to obtain and analyze reactor coolant, radioactive iodines and particulates in plant gaseous effluents, and containment atmosphere samples under accident conditions. The program shall include the following:
1)
Training of personnel, 2)
Procedures for sampling and analysis, and 3)
Provisions for maintenance of sampling and analysis equipment.
f.-
Radioactive Effluent Controls Proaram A program shall be provided conforming with 10 CFR 50.36a for the control of radioactive effluents and for maintaining the doses to MEMBERS OF THE PUBLIC from radioactive effluents as low as reasonably achievable. The program (1) shall be contained in Chapter 16 of the FSAR, -(2) shall be implemented by operating procedures, and '(3) shall include remedial actions to be taken whenever the program limits are exceeded. The program shall include the following elements:
1)
Limitations on the operability of radioactive. liquid and gaseous monitoring instrumentation including surveillance tests and set-point determination in accordance with the methodology in the Offsite Dose Calculation Manual (0DCM),
l 2)
Limitations on the concentrations of radioactive material released in liquid effluents to UNRESTRICTED AREAS conforming to 10 times 10 CFR Part 20.1001-20.2401, Appendix B, Table 2, Column 2, 3)
Monitoring, sampling, and analysis of radioactive liquid and gaseous effluents in accordance with 10 CFR 20.1302 and with the methodology and parameters in the ODCM, 4)
Limitations on the annual and quarterly doses or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released from each unit to UNRESTRICTED AREAS conform-ing to Appendix I to 10 CFR Part 50, 5)
Determination of cumulative and projected dose contributions
. from, radioactive effluents for the current calendar quarter and current calendar year in accordance with the methodology and parameters in the 00CM at least every 31 days, 6)
Limitations on the operability and use of the liquid and gaseous effluent treatment systems to ensure that the appropriate portions of these systems are used to reduce releases of radioactivity when the projected doses in a 31-day period would exceed 2 percent of CATAWBA - UNITS 1 & 2 6-15 Amendment No.145 (Unit !)
Amendment No.139 (Unit 2)
q ADMINISTRATIVE CONTROLS 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 reviews of tests and experiments pursuant to 10 CFR 50.59; j.
Records of meetings of the NSRB and reports required by Specification 6.5.1.11; 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; 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; and n.
Records of reviews performed for changes made to Section 16.11 (Radiological Effluent Controls) of the FSAR.
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.
6.11 RADIATION PROTECTION PROGRAM 6.11 Procedures for personnel radiation protection shall be prepared consis-tent with the requirements of 10 CFR Part 20 and shall be approved, main-tained, 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 para-graph 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 (RWP).
Individuals qualified in radiation protection procedures (e.g., Radiation Protection Technician) or personnel continuously escorted by such individuals may be exempt from the RWP issuance requirement 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 otherwise following plant radiation protection procedures for entry into such high radiation areas. Any individual 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 CATAWBA - UNITS 1 & 2 6-21 Amendment No.145 (Unit 1)
Amendment No.139 (Unit h