ML16138A764
| ML16138A764 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 09/24/1993 |
| From: | Matthews D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML16138A765 | List: |
| References | |
| NUDOCS 9310070082 | |
| Download: ML16138A764 (10) | |
Text
0 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 DUKE POWER COMPANY DOCKET NO. 50-269 OCONEE NUCLEAR STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 202 License No. DPR-38
- 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment to the Oconee Nuclear Station', Unit 1 (the facility) Facility Operating License No. DPR-38 filed by the Duke Power Company (the licensee) dated February 25, 1993, as supplemented May 20 and August 31, 1993, 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 (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.
- 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 3.B of Facility Operating License No. DPR-38 is hereby amended to read as follows:
9310070082 930924 PDR ADOCK 05000269 P
-2 Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 202, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
- 3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION David B. Matthews, Dirctor Project Directorate 11-3 Division of Reactor Projects -
I/II' Office of Nuclear Reactor.Regulation
Attachment:
Technical Specification Changes Date of Issuance:
September 24, 1993
egkREG(
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 DUKE POWER COMPANY DOCKET NO. 50-270 OCONEE NUCLEAR STATION, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 202 License No. DPR-47
- 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment to the Oconee Nuclear Station*,
Unit 2 (the facility) Facility Operating License No. DPR-47 filed by the Duke Power Company (the licensee) dated February 25, 1993, as supplemented May 20 and August 31, 1993, 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 (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.
- 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 3.B of Facility Operating License No. DPR-47 is hereby amended to read as follows:
- 2 Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 202, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
- 3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION David B. Matthews, Director Project Directorate 11-3 Division of Reactor Projects -
I/II Office of Nuclear Reactor Regulation
Attachment:
Technical Specification Changes Date of Issuance: September 24, 1993
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 DUKE POWER COMPANY DOCKET NO. 50-287 OCONEE NUCLEAR STATION, UNIT 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.
199 License No. DPR-55
- 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment to the Oconee Nuclear Station, Unit 3 (the facility) Facility Operating License No. DPR-55 filed by the Duke Power Company (the licensee) dated February 25, 1993, as supplemented May 20 and August 31, 1993, 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 (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.
- 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 3.B of Facility Operating License No. DPR-55 is hereby amended to read as follows:
-2 Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.199, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
- 3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION David B. Matthews, Director Project Directorate 11-3 Division of Reactor Projects -.I/LI.
Office of Nuclear Reactor Regulation
Attachment:
Technical Specification Changes Date of Issuance:
September 24, 1993
ATTACHMENT TO LICENSE AMENDMENT NO. 202 FACILITY OPERATING LICENSE NO. DPR-38 DOCKET NO. 50-269 AND TO LICENSE AMENDMENT NO. 202 FACILITY OPERATING LICENSE NO. DPR-47 DOCKET NO. 50-270 AND TO LICENSE AMENDMENT NO. 199 FACILITY OPERATING LICENSE NO. DPR-55 DOCKET NO. 50-287 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 Pages Insert Pages 1-5 1-5 6.1-3a(1) 6.1-3a(1) 6.6.1 6.6.1
1.8 RADIOLOGICAL EFFLUENT CONTROL 1.8.1 Source Check A Source Check is the qualitative assessment of channel response when the channel sensor Is exposed to a radioactive source.
1.8.2 Offsite Dose Calculation Manual (ODCM)
The OFFSITE DOSE CALCULATION MANUAL shall contain the methodology and parameters used in the calculation of offsite doses due to radioactive gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitoring alarm/trip setpoints, and in the conduct of the Environmental Radiological Monitoring Program.
FSAR Chapter 16 shall also contain (1) the Radioactive Effluent Controls and Radiological Environmental Monitoring Programs required by Sections 6.4.6 and 6.4.7 and (2) descriptions of the information that should be included In the Annual Radiological Environmental Operating and Annual Radioactive Effluent Release Reports required by Speciflc tions 6.6.1.4 and 6.6.1.5.
1.8.3 Process Control Program (PCP)
The PROCESS CONTROL PROGRAM (PCP) shall contain the current forrmulas, sampling, analyses, test, and determinations to be made to ensure that processing and packaging of solid radioactive wastes based on demonstrated processing of actual or simulated wet solid wastes will be accomplished In such a way as to assure compliance with 10 CFR Parts 20, 61, and 71, State regulations, burial ground requirements, and other requirements governing the disposal of solid radioactive waste.
1.8.4 Not Used 1.8.5 Gaseous Radwaste Treatment System A Gaseous Radwaste Treatment System is any system designed and installed to reduce radioactive gaseous effluents by collecting primary coolant system offgases from the primary system and providing for delay or holdup for the purpose of reducing the total radioactivity prior to release to the environment.
1.8.6 Ventilation Exhaust Treatment System A Ventilation' Exhaust Treatment System is any system designed and installed to reduce gaseous radloiodine or radioactive material in particulate form In effluents by passing ventilation or vent exhaust gases through charcoal absorbers and/or HEPA filters for the purpose of removing iodines or particulates from the gaseous exhaust stream prior to the release to the environment. Engineered Safety Feature (ESF) atmospheric cleanup systems are hot considered to be Ventilation Exhaust Treatment System components.
1.8.7 Purge-Purging Purge or Purging is the controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration or other operating condition, In such a manner that replacement air or gas Is required to purify the confinement.
Oconee 1, 2,
and 3 1-5 Anenanent No. 202 (Uniit 1)
Amndtent No. 202 (Unit 2)
A tnennt No. 199 (Unit 3)
- 3)
Shall become effective upon review and acceptance by the Station Manager and a qualified individual/organization;
- and,
- 4)
Shall be submitted to the Commission in the form of a complete, legible copy of the entire ODCM as a part of or concurrent with the Annual Radioactive Effluent Re lease Report for the period of the report in which any change to the ODCM was made.
Each change shall be identified by markings in the margin of the affected pages, clearly indicating the area of the page that was changed, and shall indicate the date (e.g., month/year) the change was implemented.
- m.
Licensee-initiated changes to the Process Control Program shall be documented and records of reviews performed shall be retained for the duration of the unit license.
This documentation shall contain:
- 1)
Sufficient information to support the change together with the appropriate analyses or evaluations justifying the change(s);
- 2)
A determination that the change will maintain the overall conformance of the solidified waste product to existing requirements of Federal,
- State, or other applicable regulations; and,
- 3)
Changes shall become effective upon review and acceptance by the Station Manager and a qualified individual/organization.
6.1.2.2 Records Records of the above activities shall be maintained.
6.1.3 Nuclear Safety Review Board 6.1.3.1 Function 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
- d.
Metallurgy
- e.
Instrumentation and control
- f.
Radiological safety
- g.
Mechanical and electrical engineering
- h.
Administrative control and quality assurance practices 6.1.3.2 Organization
- a.
The Director, members and alternate members of the NSRB shall be formally appointed by the Executive Vice President, Power Generation, and shall have an academic degree in an engineering or physical science field; and in addition, shall have a minimum of five years technical experience, of which a minimum of three years shall be in one or more areas given in 6.1.3.1.
In special cases, candidates for appointment without an academic degree in engineering or a physical science may be qualified with a minimum of ten years experience in one of the areas specified in Specification 6.1.3.1.
Oconee 1, 2, and 3 6.1-3a(1)
Anndnent No. 202 (Unit 1)
Anendrent No. 202 (hnit 2)
Anendent No. 199 (Unit 3)
6.6 STATION REPORTING REQUIREMENTS 6.6.1 Routine Reports In addition to the applicable reporting requirements of Title 10, Code of Federal Regulations, the following reports shall be submitted to the Regional Administrator Region II unless otherwise noted.
6.6.1.1 Startup Report A summary report of unit startup and power escalation testing shall be submitted following (1) receipt of an operating license, (2) amendment to the facility 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. Startup reports shall be submitted (1) within 90 days following completion of the startup test program, (2) 90 days following resumption of commencement of commercial power operation, or (3) nine months following initial criticality, whichever occurs first.
If a startup report does not cover all three events, i.e., initial criticality, completion of the startup test program and resumption or commencement of commercial power operation supplementary reports shall be submitted at least every three months until all three events are completed.
6.6.1.2 Monthly Operating Report Routine reports of operating statistics and shutdown experience shall be submitted on a monthly basis to the Director, Office of Management Information and Program Control, U. S. Nuclear Regulatory Commission, Washington, D. C., 20555, with a copy to the appropriate Regional Office, to be submitted by the fifteenth of each month following the calendar month covered by the report.
6.6.1.3 Personnel Exposure and Monitoring Report Prior to March 1 of each year, a tabulation shall be submitted to the NRC of the number of station, utility and other personnel (including contractors) receiving exposures greater than 100 mrem/yr and their associated man-rem exposure according to work and job functions, e.g., reactor operations and surveillance, inservice inspection, routine maintenance, special maintenance (describe maintenance), waste processing, and refueling. The dose assignment to various duty functions may be estimates based on pocket dosimeter, TLD, or film badge measurements. Small exposures totalling less than 20% of the individual total dose need not be accounted for. In the aggregate, at least 80% of the total body dose received from external sources shall be assigned to specific major work functions.
6.6.1.4 The Annual Radi oactive Effluent Release Report*
The Annual Radioactive Effluent Release Report covering the operation of the unit during the previous calendar year shall be submitted before May 1 of each year.
- A single submittal may be made for a multiple unit station. The submittal should combine those sections that are common to all units at the station; however, for units with separate Radwaste Systems, the submittal shall specify the release of radioactive material from each unit.
Oconee 1, 2, and 3 6.6.1 Aendient No. 202 (Unit 1)
Anndnent No. 202 (Unit 2)
Amnytrant Nr-1CA (Ibnit 'A)