ML16138A731
| ML16138A731 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 05/01/1992 |
| From: | Matthews D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML16138A732 | List: |
| References | |
| NUDOCS 9205200331 | |
| Download: ML16138A731 (20) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555 DUKE POWER COMPANY DOCKET NO. 50-269 OCONEE NUCLEAR STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 193 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 January 2, 1992, as supplemented February 14, 1992, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations 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 license 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:
9205200331 920501 PDR ADOCK 05000269 P
-2 Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.193, 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 and shall be implemented within 30 days from the 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:
May 1, 1992
- tkkREG, UNITED STATES o
NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555 DUKE POWER COMPANY DOCKET NO. 50-270 OCONEE NUCLEAR STATION, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 193 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 January 2, 1992, as supplemented February 14, 1992, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations 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 license 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. 193, 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 and shall be implemented within 30 days from the 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: May 1, 1992
NkREG&LZ UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555 DUKE POWER COMPANY DOCKET NO. 50-287 OCONEE NUCLEAR STATION, UNIT 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.190 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 January 2, 1992, as supplemented February 14, 1992, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations set forth in 10 CFR Chapter 1; 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 1; D. The issuance of this license 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. 190, 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 and shall be implemented within 30 days from the 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:
May 1, 1992
ATTACHMENT TO LICENSE AMENDMENT NO. 193 FACILITY OPERATING LICENSE NO. DPR-38 DOCKET NO. 50-269 AND TO LICENSE AMENDMENT NO.193 FACILITY OPERATING LICENSE NO. DPR-47 DOCKET NO. 50-270 AND TO LICENSE AMENDMENT NO.190 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 6.1-1 6.1-1 6.1-la 6.1-1a 6.1-2 6.1-2 6.1-3 6.1-3 6.1-3a 6.1-3a(1) 6.1-3a(2) 6.1-3b 6.1-3b 6.1-4 6.1-4 6.1-5 6.1-5 6.1-5a 6.1-5a 6.1-6 6.1-6 6.2-1 6.2-1 6.3-1 6.3-1
6.0 ADMINISTRATIVE CONTROLS 6.1 ORGANIZATION, REVIEW, AND AUDIT 6.1.1 Organization Onsite and offsite organizations shall be established for unit operation and corporate management, respectively.
The onsite and offset organizations shall include the positions for activities affecting the safety of the nuclear power plant.
6.1.1.1 Lines of authority, responsibility, and communication shall be established and defined for the highest management levels through intermediate levels to and including all operating organizatiohn positions.
These relationships shall be documented and updated, as appropriate, in the form of organization charts, functional descrip tions of departmental responsibilities and relationships, and job descriptions for key personnel positions, or in equivalent forms of documentation.
These requirements shall be documented in the FSAR.
6.1.1.2 The Station -Manager shall be responsible for overall plant safe operation and shall have control over those onsite activities necessary for safe operation and maintenance of the plant and shall delegate in writing the succession to this responsibility during his absence.
6.1.1.3 The Vice President, Oconee Nuclear Site, shall have corporate responsibility for overall plant nuclear safety and shall take any measures needed to ensure acceptable performance of the staff in operating, maintaining, and providing technical support to the plant to ensure nuclear safety.
The Senior Vice President, Nuclear Generation Department will be the Senior Nuclear Executive and have corporate responsibility for overall nuclear safety.
6.1.1.4 Incorporated in the staff of the station shall be personnel meeting the minimum requirements encompassing the training and experience described in Section 4 of ANSI/ANS-3.1-1978, "Selection and Training of Nuclear Power Plant Personnel" except for the Radiation Protec tion Manager, the Operations Superintendent and the Shift opera tions Manager.
The Radiation Protection Manager shall have a bachelor's degree in a science or engineering subject or the equivalent in experience, including some formal training in radiation protection, and shall have at least five years of professional experience in applied radiation protection of which three years shall be in applied radiation protection work in one of Duke Power Company's nuclear stations.
A qualified individual who does not meet the above requirements, but who has demonstrated the required radiation protection management capabilities and professional experience in applied radiation protection work at one of Duke Power Company's multi-unit nuclear stations, may be appointed to the position of Radiation Protection Manager by the Station Manager, based on the recommendations of OCONEE UNITS 1,2,3 6.1-1 Amendment no. 193 (Unit 1)
Amendment No. 193 (Unit 2)
Amendment No. 190 (Unit 3)
the Nuclear Technical Services Manager and as approved by the Site Vice President, Nuclear Operations.
The Operations Superintendent shall have a minimum of eight Years of responsible nuclear or fossil station experience, of which a minimum of three years shall be nuclear station experience.
A max imum o f two years of the remaining five years of experience may be fulfilled by academic training, or related technical training, on a one-for one time basis.
The Operations Superintendent shall hold or have held a Senior Reactor Operator license.
The Shift operations Manager shall have a minimum of eight years of responsible nuclear or fossil station experience, of which a minimum of three years shall be nuclear station experience.
A maximum of two years of the remaining five years of experience may be fulfilled by academic training, or related technical training on a one-for-one time basis.
The Shift Operations Manager shall hold a Senior Reactor Operator license.
6.1.1.5 The individuals who train the operating staff and those who carry out radiation protection and quality assurance functions may report to the appropriate onsite manager; however, they shall have suffi cient organizational freedom to ensure their independence from operating pressures.
6.1.1.6 Minimum operating shift crew requirements shall be as specified in Table 6.1-1.
6.1.1.7 Retraining and replacement of station personnel shall be in accor dance with Section 5.5 of the ANSI/ANS-3. -1978, "Selection and Training of Nuclear Power Plant Personnel."
6.1.1.8 A training program for the fire brigade shall meet or exceed the requirements of Section 27 of the NFPA Code-1975, except that training sessions may be held quarterly.
6.1.1.9j The Shift Manager is an experienced SRO, who has been instructed in additional academic
- subjects, and will be assigned on-shift to provide the accident assessment capability.
The operating experience assessment function will be provided by the Station Safety Review Group.
OCONEE UNITS 1,2,3 6.1-1a Amendment No. 193 (Unit 1)
Amendmeit". No. 193 (Unit-2)
Amendment No. 190 (Unit 3)
6.1.2 Technical Review and Control 6.1.2.1 Activities
- a.
Procedures required by Technical Specification 6.4 and other procedures which affect station nuclear safety, and changes (other than editorial or typographical changes) thereto, shall be prepared by a qualified individ ual/organization.
Each such procedure, or procedure change, shall be reviewed by an individual/group other than the individual/group which prepared the procedure, or procedure change, but who may be from the same organization as the individual/group which prepared the procedure, or procedure change.
Such procedures and procedure changes may be approved for temporary use by two members of the station staff, at least one of whom holds a Senior Reactor Operator's License on the unit(s) affected.
Procedures and procedure changes shall be approved prior to use or within seven days of receiving temporary approval by a group manager, superin tendent/manager, or one of their designated direct reports.
- b.
Proposed changes to the Technical Specifications shall be prepared by a qualified individual/organization.
The preparation of each proposed Technical Specifications 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 Specifi cations shall be approved by the Station Manager.
- c.
Proposed modifications to station nuclear safety-related structures, systems and components shall be designed by a qualified individual]
organization.
Each such modification shall be reviewed by an individu al/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 for the Station Manager by the Mechanical Superintendent, the Operations Superintendent, the I and E Superintendent, or the Work Control Superintendent, as previously desig nated by the Station Manager.
- d.
Individuals responsible for reviews performed in accordance with 6.1.2.1
.a, 6.1.2.1.b, and 6.1.2.1.c shall be members of the Site supervisory staff, previously designated by the Site Vice President to perform such reviews.
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 personnel.
- e.
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 for the Station Manager by the Mechanical Superintendent, the Operations Superintendent, the I and E Superintendent, or the Work Control Superintendent, as previously desig nated by the Station Manager.
- f.
Incidents reportable pursuant to Technical Specification 6.6.2.1 and violations of Technical Specifications shall be investigated and a report prepared which evaluates the occurrence and which provides recommenda tions to prevent recurrence.
Such reports shall be approved by the Manager, Safety Assurance and transmitted to the Site Vice President; and to the Director of the Nuclear Safety Review Board.
- g.
The Manager, Safety Assurance shall assure the performance of special reviews and investigations, and the preparation and submittal of reports thereon, as requested by the Site Vice President.
- h.
Deleted I
Amendment No. 193 (Unit 1)
OCONEE UNITS 1,2,3 6.1-2 Amendment No. 193 (Unit 2)
Amendment No.. 190 (Unit 3)
1*
Deleted
- j. The
- manager, Safety Assurance shall assure that an independent fire protection and lose prevention inspection and audit shall be performed annually utilizing qualified off-site personnel and that an inspection and audit by a qualified fire consultant shall be performed at intervals no greater than three years.
- k.
Unplanned onsite releases of radioactive material to the environs 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 Manager, Safety Assurance and transmitted to the Site Vice President, or designee, and to the Director of the Nuclear Safety Review Board.
- 1.
Licensee-initiated changes to the Offsite Dose Calculation Manual ODCM) shall be documented and records of reviews performed shall be retained for the duration of the unit operating license.
This documentation shall contain:
- 1)
Sufficient information to support the change together with the appropriate analyses or evaluations justifying the change(s); and,
- 2)
A determination that the change will maintain the level of radioactive effluent control required by 10 CFR 20.106, 40 CFR Part 190, 10 CFR 50.36a, and.Appendix I to 10 CPR Part 50 and not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations; and, OCONEE UNITS 1,2'3 Amendment No. 193 (Unit 1) 6.1-3 Amendment No.193 (Unit 2)
Amendment No. 190 (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 Semiannual Radioactive Effluent Re lease Report for the period of the report in which any change to the ODCM was made. Each change shall be identi fied 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 regu lations; and,
- 3)
Changes shall become effective upon review and acceptance by the Station Manager and a qualified individual/organi zation.
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.
Amendment No. 193 (Unit 1)
OCONEE UNITS 1,2,3 6.1-3a(1)
Amendment No. 193 (Unit 2)
Amendment No. 190 (Unit 3)
- b.
The NSRB shall be composed of at least five members, including the Director, Members of the NSRB may be from the Nuclear Generation Depart ment, from other departments within the Company or from external to the Amendment No. 193 (Unit 1)
OCONEE UNITS 1,2,3 Amendment No. 193 (Unit 2)
Amendment No. 190 (Unit 3)
Company. A maximum of one member of the NSRB may be from the Oconee Nuclear Site staff.
C.
Consultants may be utilized by the NSRB to provide expert advice to the NSRB, as determined necessary by the Director of the NSRB.
- d.
Staff assistance may be provided to the NSRB in order to promote the proper, timely and expeditious performance of its functions.
- e.
The NSRB shall meet at least once per six months.
The period between such meetings shall not exceed eight months.
- f.
A quorum of the NSRB shall consist of the Director, or his designated alternate, and at least two other NSRS members or alternate members.
No more than a minority of the quorum shall have line responsibility for operation of Oconee Nuclear Station.
Amendment No. 193 (Unit 1)
OCONEE UNITS 1,2,3 6.1-3b Amendment No. 193 (Unit 2)
Amendment No&. 190 (Unit 3)
6.1.3.3 Subjects Requiring Review The following subjects shall be reported to and reviewed by the NSRB:
- a.
The safety evaluations for (1) changes to procedures, equipment or systems, and (2) tests or experiments completed under the provisions of 10 CFR 50.59(a)(1) to verify that such actions did not constitute an unreviewed safety question.
- b.
Proposed changes to procedures, equipment or systems which involve an un reviewed safety question as defined in 10 CFR 50.59.
- c.
Proposed tests or experiments which involve an unreviewed safety question as defined in 10 CFR 50.59.
- d.
Proposed changes in Technical Specifications or the Facility Operating Licenses.
- e.
Violations of applicable statutes, codes, regulations, orders, Technical Specifications, license requirements, or of internal procedures or instructions having nuclear safety significance.
- f.
Significant operating abnormalities or deviations from normal and expect ed performance of station equipment that affect nuclear safety.
- g.
Incidents that are the subject of non-routine reports submitted to the Commission.
- h.
Quality Verification Department audits relating to station operations and actions taken in response to these audits.
Amendment No. 193 (Unit 1)
OCONEE UNITS 1,2,3 6.1-4 Amendment No. 193 (Unit 2)
Amendment No. 190 (Unit 3)
6.1.3.4 Audits Audits of Site activities shall be performed under the cognizance of the NSRB.
These audits shall encompass:
- a.
The conformance of station operation to provisions contained within the Technical Specifications and applicable facility operating license conditions.
- b.
The performance, training and qualifications of the station staff.
- c.
The results of actions taken to correct deficiencies occurring in equip
- ment, structures, systems or methods of operation that affect nuclear safety.
- d.
The performance of activities required by the quality assurance program to meet the criteria of Appendix B to 10 CFR 50.
- e.
The station emergency plan and implementing procedures.
- f.
The station security plan and implementing procedures.
- g.
Any other area of station operation considered appropriate by the NSRB or the Executive Vice President, Power Generation Department.
- h.
The station fire protection program and implementing procedures.
- i.
The Offsite Dose Calculation Manual and implementing procedures.
- j.
The Radiological Environmental Monitoring Program and the results thereof.
- k.
The Process Control Program and implementing procedures for solidifica tion of radioactive wastes.
- 1.
The performance of activities required by the Quality Assurance Program to meet the criteria of Regulatory Guide 1.21 Revision 1, June 1974 and Regulatory Guide 4.1 Revision 1, April 1975.
Amendment No. 193 (Unit 1)
OCONEE UNITS 1,2,3 6.1-5 Amendment No. 193 (Unit 2)
Amendment No. 190 (Unit 3)
6.1.3.5 Responsibilities and Authorities
- a.
The NSRB shall report to and advise the Executive Vice President, Power Generation on those areas of responsibility specified in Specifications 6.1.3.3 and 6.1.3.4.
- b.
Minutes shall be prepared and forwarded to the Senior Vice President, Nuclear Generation, and to the Executive Vice President, Power Genera tion, within 14 days following each formal meeting of the NSRB.
- c.
Records of activities performed in accordance with Specifications 6.1.3.3 and 6.1.3.4 shall be maintained.
- d.
Audit reports encompassed by Section 6.1.3.4 shall be forwarded to the Senior Vice President, Nuclear Generation and to the Executive Vice President, Power Generation, and to the management position responsible for the areas audited within 30 days of completion of each audit.
Amendment No. 193 (Unit 1)
OCONEE UNITS 1,2,3 6.1-5a Amendment No. 193 (Unit 2)
Amendment No. 190 (Unit 3)
TABLE 6.1-1 MINIMUM OPERATING SHIFT REQUIREMENTS (With Fuel in the Three Reactor Vessels)
One Two All All Unit Units Units Units Operatinq*
Operating*
Operating*
Shutdown Shift Supervisor (SRO) 1 1
1 1
Additional SRO
.1 2**
2 NONE Shift Manager (SRO) 1 1
1 NONE Reactor Operator 4
5**
5 3
Nuclear Equipment Operator 4
5 5
5 Above cold shutdown Only one SRO and four Reactor Operators required if both units are operated from one Control Room.
AmendMent No. 193 (Unit 1)
OCONEE UNITS 1,2,3 6.1-6 Amendment No. 193 (Unit 2)
Amendment No. 190 (Unit 3)
6.2 ACTION TO BE TAKEN IN THE EVENT OF A REPORTABLE OCCURRENCE 6.2.1 The
- Manager, Safety Assurance shall assure that any reportable event is promptly investigated.
6.2.2 The Site Vice President shall be notified of any reportable event.
A written report shall be prepared which describes the circumstances leading up to and resulting from the incident and shall recommend appropriate action to prevent or minimize the probability of a recurrence.
The report shall be submitted to the Site Vice Presi dent, and the Director of the Nuclear Safety Review Board.
6.2.3 The Commission shall be notified and/or a report submitted pursuant to the requirements of Specification 6.6.2 and 10 CFR 50.73.
Amendment No. 193 (Unit 1)
OCONEE UNITS 1,2,3 Amendment No. 193 (Unit 2)
Amendment No. 190 (Unit3)
6.3 ACTION TO BE TAKEN IN THE EVENT A SAFETY LIMIT IS EXCEEDED 6.3.1 If a safety limit is exceeded, the reactor shall be shut down immediately and maintained in a safe shutdown condition until the Commission authorizes resumption of operation.
6.3.2 The violation of a safety limit shall be reported to the Commission, the Site Vice President and the Director of the Nuclear Safety Review Board.
6.3.3 A report shall be prepared which describes (1) applicable circumstances preceding the violation, (2) effects of the violation upon structures, systems, or components, and (3) corrective action taken to prevent recurrence.
The report shall be reviewed by the Operations Superintendent and the Station Manager. The report shall be submitted to the Site Vice President and the Director of the Nuclear Safety Review Board.
6.3.4 A report of the violation, with appropriate analyses and corrective action to prevent recurrence shall be submitted to the Commission within 10 days of the violation.
Amendment No. 193 (Unit 1)
OCONEE UNITS 1,2,3 Amendment No. 193 (Unit 2)
Amendment No. 190 (Unit 3)