ML20127E510
| ML20127E510 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 01/06/1993 |
| From: | Matthews D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20127E515 | List: |
| References | |
| NUDOCS 9301190349 | |
| Download: ML20127E510 (8) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION n
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WASHING TON, D. C. 20555
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DUKE POWER COMPANY' NORTH CAROLINA ELECTRIC MEMBERSHIP CORPORATION SALUDA RIVER ELECTRIC COOPERATIVE. INC.
DOCKET NO. 50-413 f
CATAWBA NUCLEAR STATION. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 104 License No. NPF-35 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment to the Catawba Nucie r 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 November 5, 1992, as supplemented December 9 and 18, 1992, complies with the standards and requirements of the. Atomic-Energy Act of 1954, as amended (the Act), and the Commission's rules and r_egulations 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.
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9301190349 930106 PDR-ADOCK-05000413 P
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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 Soecifications The Technical Specifications contained in Appendix A, as revised through Amendment No.104, 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 l
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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David B. Matthews, Director Project Directorate 11-3 Division of Reactor Projects-1/II Office of Nuclear Reactor Regulation
Attachment:
Technical Specification Changes Date of Issuance: January 6, 1993 l
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UNITED STATES:
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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.98 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.1 =and Piedmont Municipal' Power Agency 1(licensees) dated November 5, 1992, as supplemented December 9 and'18,J1992,_
complies with the standards _and requirements of the Atomic Energys Act ofz l954, as amended (the Act), and the Comission'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 Comission; -
y C.
There is reasonable-assurance (1) that-the activities authorized byl this amendment'can be conducted without endangering. the health:and -
y 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;-
h D.
The issuance of'this amendment will not be inimicallto the comon defense and security or to the health and safety of the public; and-t 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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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. 98, and the Environmental Protection Plan contained in Appendix B, both of which arc 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 l
David B.'Hatthews, Director Project Directorate II-3 Division of Reactor Projects-I/II Office of Nuclear Reactor Regulation
Attachment:
Technical Specification Changes Date of Issuance: January 6, 1993
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ATTACHMENT TO LICENSE AMENDMENT N0. 104 FACILITY OPERATING LICENSE NO. NPF-35 DOCKET NO. 50-413
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AND TO LICENSE AMENDMENT NO. 98 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 6-15 6-15 6-15a 6-15b
ADMIN'ISTRATIVE CONTROLS PROCEDURES AND PROGRAMS (Continued) e.
Post-Accident Sampling 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 Program 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
- ODCM, 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, l
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 00CM, 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, i
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 ODCM 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.104 (Unit 1)
Amendment No. 98 (Unit 2)
ADMINISTRATIVE CONTROLS PROCEDURES AND PROGRAMS (Continued) the guidelines for the annual dose or dose commitment conforming to Appendix I to 10 CFR Part 50, 7)
Limitations on the dose rate resulting from radioactive material released in gaseous effluents from the site to areas at or beyond the SITE BOUNDARY shall be limited to the following:
a.
For noble gases:
Less than or equal to a dose rate of 500 mrems/yr to the total body and less than or equal to a dose rate of 3000 mrems/yr to the skin, and b.
For iodine-131, iodine-133, tritium, and for all radionuclides in particulate form with half-lives greater than 8 days:
Less than or equal to a dose rate of 1500 mrems/yr to any organ.
8)
Limitations on the annual and quarterly air doses resulting from noble gases released in gaseous effluents from each unit to areas beyond the SITE BOUNDARY conforming to Appendix I to 10 CFR Part 50, 9)
Limitations on the annual and quarterly doses to a MEMBER OF THE PUBLIC from Iodine-131, Iodine-133, tritium, and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents released from each unit to areas beyond the SITE BOUNDARY conforming to Appendix I to 10 CFR Part 50, and
- 10) Limitations on the annual dose or dose commitment to any MEMBER OF THE PUBLIC due to releases of radioactivity and to radiation from uranium fuel cycle sources conforming to 40 CFR Part 190.
g.
Radiological Environmental Monitoring Program A program shall be provided to monitor the radiation and radionuclides in the environs of the plant.
The program shall provide (1) representative measurements of radioactivity in the highest potential exposure pathways, and (2) verification of the accuracy of the effluent monitoring program and modeling or environmental exposure pathways.
The program shall (1) be contained in Chapter 16 of the FSAR, (2) conform to the guidance of Appendix I to 10 CFR Part 50, and (3) include the following:
1)
Monitoring, sampling, analysis, and reporting of radiation and radionuclides in the environment in accordance with the methodology and parameters in the ODCM, 2)
A Land Use Census to ensure that changes in the use of areas at and beyond the SITE BOUNDARY are identified and that modifications to the monitoring program are made if required by the results of this census, and CATAWBA - UNITS 1&2 6-15a Amendment 104 (Unit 1)
Amendment 98 (Unit 2)
ADMINISTRATIVE CONTROLS g.
Radiological Environmental Monitoring Program (Continued) 3)
Participation in a Interlaboratory Comparison Program to ensure that independent checks on the precision and accuracy of the measurements of radioactive materials in the environmental sample matrices are performed as part of the quality assurance program for environmental monitoring.
6.9 REPORTING REQUIREMENTS ROUTINE REPORTS 6.9.1 In addition to the applicable reporting requirerents of Title 10, Code of Federal Regulations, the following reports shall be submitted to NRC in accordance with 10 CFR 50.4.
STARTUP REPORT
- 6. 9.1.1 A summary report of plant startup and power escalation testing shall be submitted following (1) receipt of an Operating License, (2) amendment to the license involving a planned increase in power level, (3) installation of fuel that has a different design or has been manufactured by a different fuel supplier, and (4) modifications that may have significantly altered the nuclear, thermal, or hydraulic performance of the unit.
6.9.1.2 The Startup Report shall address each of the tests identified in the Final Safety Analysis Report and shall include a description of the measured values of the operating conditions or characteristics obtained during the test program and a comparison of these values with design predictions and specifica-tions.
Any corrective actions that were required to obtain satisfactory operation shall also be described.
Any additional specific details required in license conditions based on other commitments shall be included in this report.
6.9.1.3 Startup Reports shall be submitted within:
(1) 90 days following completion of the Startup Test Program, (2) 90 days following resumption or commencement of commercial power operation, or (3) 9 months following initial criticality, whichever is earliest.
If the Startup Report does not cover all three events (i.e., initial criticality, completion of Startup Test Program, and resumption or commencement of commercial operation), supplementary reports shall be submitted at least every 3 months until all three events have been completed, i
CATAWBA - UNITS 1&2 6-15b Amendment No.104(Unit 1) l Amendment No. 98(Unit 2)
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