ML13326A728
| ML13326A728 | |
| Person / Time | |
|---|---|
| Site: | San Onofre |
| Issue date: | 12/28/1982 |
| From: | Crutchfield D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML13326A727 | List: |
| References | |
| DPR--13-A-066 NUDOCS 8301040211 | |
| Download: ML13326A728 (21) | |
Text
.oUNITED STATES I t.
NUCLEAR REGULATORY COMMISSION o
WASHINGTON, D. C. 20555 SOUTHERN CALIFORNIA EDISON COMPANY SAN DIEGO GAS & ELECTRIC COMPANY DOCKET NO. 50-206 AMENDMENT TO PROVISIONAL OPERATING LICENSE Amendment No. 66 License No. DPR-13
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment by Southern California Edison Company and San Diego Gas and Electric Company (the licensees) dated December 18, 1981, as modified August 5, 1982, 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; 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.
83010o40211 821226 PDR ADOCK 05000206 P
-2
- 2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment of this license amendment and Paragraph 3.B of Provisional Operating License No. DPR-13 is hereby amended to read as follows:
B. Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 66, are hereby incorporated in the license. Southern California Edison Company shall operate the facility in accordance with the Technical Specifications.
- 3. This license amendment is effective upon issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Dennis M. Crutchfield, Chief Operating Reactors Branch #5 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance:
December 28, 1982
ATTACHMENT TO LICENSE AMENDMENT NO. 66 PROVISIONAL OPERATING LICENSE NO. DPR-13 DOCKET NO. 50-206 Revise Appendix A Technical Specifications and Bases and Appendix B Environmental Technical Specifications by removing the following pages and inserting the enclosed pages. The revised pages contain the captioned amendment number and vertical lines indicating the areas of change.
Remove Pages Insert Pages 68 68 69 69 70 70 70a 72 72 72a 72a 73 73 74 74 75 75 75a and 75b*
79 79*
79a 79a (Appendix B) 5-2 through 5-2 through 5-7 5-7
- There are no changes to the provisions contained on this page; it is merely included for pagination purposes.
- 68 6.0 ADMINISTRATIVE CONTROLS 6.1 RESPONSIBILITY 6.1.1 The Station Manager shall be responsible for overall facility operation and shall delegate in writing the suc cession to this responsibility during his absence.
6.2.
ORGANIZATION OFFSITE 6.2.1 The offsite organization for facility management and technical support shall be as shown on Figure 6.2.1.1 FACILITY STAFF 6.2.2 The Facility organization shall be as,shown on Figure 6.2.2.2
-and:
- a. Each on-duty shift shall be composed of at least the.
minimum shift crew composition shown in Table 6.2.2.2-4 Amendment 'No.,1 66
CHAIRMAN OF THE BOARD EXECUTIVE VICE PRESIDENT I
I I
VICE PRESIDENT VICE PRESIDENT VICE PRESIDENT VICE PRESIDENT VICE PRESIDENT VICE PRESIDENT NULTEAR (FUEL SUPPLY)
(NUCLEAR ENGINEERING (POWER SUPPLY)
(SYSTEM (ENGINEERING & (ADVANCEDOR AND OPERATIONS)
DEVELOPMENT)
CONSTRUCTION)
ENGINEERING)
BOARD NUCLEAR AUDIT AND REVIEW COMMITTEE MANAGER OF MANAGER OF MANAGER OF MANAGER OF NUCLEAR ENGINEERING, NUCLEAR ENVIRONMENTAL ENGINEERING SAFETY & LICENSING OPERATIONS AFFAIRS DESIGN DIRECTOR
- MANAGR, RESEARCH AND QUALITY DEVELOPMENT ASSURANCE PROJECT MANAGER MANAGER, NUCLEAR MANAGER, TRAINING MANAGERCAL SAN ONOFRE UNIT 1 ENGINEERING &
NUCLEAR MANAGER BIOLOGICAL RETROFIT PROJECTS SAFETY LICENSING SYSTEMS R&D HEADQUARTERS STAFF t
STATION ONSITE STAFF STATION REVIEW MANAGER COMMITTEE 6.2.1.1 OFFSITE ORGANIZATION Amendment No.
66
STATION MANAGER 70 DEPUTY STATION MANAGER
- MANAGER, MANAGER,
- MANAGER, MANAGER,4 MATERIAL AND STATION CONFIGURATION STATION ADMINISTRATIVE SECURITY CONTROL AND EMERGENCY SERVICES COMPLIANCE PREPAREDNESS SAI I
- MANAGER, MANAGER,
- MANAGER, MANAGER, OPERATIONS MAINTENANCE TECHNICAL HEALTH PHYSICS PLANT SUPT. 1 SUPERVISING SO GS 1 COMPUTER ENGINEER MAINTENANCE SUPERVISING HP PLANNING ENGINEER SUPERVISOR SUPERVISOR NSSS SONGS 1 SUPERVISING RADWASTE ENGINEER SUPERVISOR NSSS SUPPORT SUPERVISOR OF SUPERVISING NUCLEAR PLANT ENGINEER DOSIMETRY MAINTENANCE SHIFT TECH.
SUPERVISOR ADVISORS SUPERVISOR
_SUPERVISOR H.P. ENGR'G SHIFT 2 OF PLANT OF I&C GROUP SUPERVISORS COORDINATION SUPERVISOR OPERATING2 SUPERVISOR FOREMAN COORDINATORS OF CHEMISTRY SHI[T3 PERSONNEL 1At time of appointment to the position, Senior Reactor Operator license required.
2Senior Reactor license required.
3Control and Assistant Control Operators are holders of Reactor Operator licenses.
41ncludes fire protection.
FIGURE 6.2.2.2 FACILITY ORGANIZATION Amendment No. 41.54. 66
-72
- b. At least one licensed Operator shall be at the controls when fuel is in the reactor.*
During refueling operations this operator is permitted to step outside the red line to update the refuel.ing status board.
- c. At least two licensed Operators shall be present in the control room during reactor startup, scheduled reactor shutdown and during recovery from reactor trips.** One of the two licensed Operators is permitted to be present in the Chemical Laboratory or the area around and behind the vertical instrumentation boards for short periods of time for the purpose of checking necessary instrumentation.
- d. An individual qualified in radiation protection supervision shall be on site when fuel is in the reactor.
- e. All core alterations after the initial fuel loading shall be directly supervised by a licensed Senior Reactor Operator.
- f.
A Fire Brigade of at least five members shall be maintained on site at all times. This excludes members of the minimum shift crew necessary for safe shutdown of Unit 1 and any personnel required for other essential functions during a fire emergency.
"At the controls means within the area bounded by the three vertical instrumentation boards and the red line on the floor of the control room.
Reactor startup, reactor shutdown and recovery from reactor trips means operations between keff = 0.99 and the attainment of E% indicated thermal power.
Amendment No. SJ. Ad' 66
.* 72a *
-. 6.3 Unit Staff Qualifications 6.3.1 Each member of the facility staff shall meet or exceed the minimum qualifications of ANSI N18.1-1971, "Selection and Training of Personnel for Nuclear Power Plants," for comparable positions.
The Manager, Health Physics shall meet or exceed the minimum qualifications of Regulatory Guide 1.8, September 1975. The Shift Technical Advisor shall have a bachelor's degree or equivalent in a scientific or engineering discipline with specific training in plant design, and response and analysis of the plant for transients and accidents.
6.4 Training 6.4.1 A retraining and replacement training program for the faciity staff shall be maintained under the direction of the Training.
Manager and shall meet or exceed the requirements and recommendations of Section 5.5 of ANSI N18.1-1971 and Appendix "A" of 10 CFR Part 55.
6.4.2 A training program for the Fire Brigade shall be maintained under the direction of the Training Manager and shall meet or exceed the requirements of Section 27 of the National Fire Protection Association Code -
1976."
Amendment No.
-66
73 6.5 REVIEW AND AUDIT 6.5.1 Onsite Review Committee (OSRC)
FUNCTION 6.5.1.1 The Onsite Review Committee shall function to advise the Station Manager on all matters related to nuclear safety.
COMPOSITION 6.5.1.2 The Onsite Review Committee shall be composed of the:
Chairman:
Station Manager Member:
Deputy Station Manager Member:
Manager, Operations Member:
Manager, Technical Member:
Plant Superintendent SONGS 1 Member:
Supervisor of.I&C Member:
Manager, Health Physics Member!
Supervisor of Chemistry Member:
Manager, Maintenance Member:
Supervising Engineer CNSSS, NSSS Support, Computer, or STA)
Member:
San Diego Gas,& Electric Representative, Senior Engineer )
ALTERNATES 6.5.1.3 All alternate members shall be appointed in writing by the OSRC Chairman to serve on a temporary basis; however, no more than two alternates shall participate as Voting members in OSRC activities at any one time.
MEETING FREQUENCY 6.5.1.P4 The OSRC shall meet at least once per calendar month and as convened by the OSRC Chairman or his designated alternate.
QUORUM 6.5.1.5 The minimum quorum of the OSRC necessary for the performance of the OSRC responsibility and authority provisions of these Technical Specifications shall consist of the Chairman or his designated alternate and four members including alternates.
BS degree in Engineering or Physical Science plus at least four years professional level experience in his field. At least one of the four years experience shall be nuclear power plant experience.
Amendment oenda 66
74 RESPONSIBILITIES 6.5.1.6 The Onsite Review Committee shall be responsible for:
- a. Investigation of all violations of the Technical Specifications including the preparation and forwarding of reports covering evaluation and recommendations to prevent recurrence to the Chairman of the Nuclear Audit and Review Committee (NARC).
- b. Review of events requiring 24-hour written notification to the Commission.
- c. Review of unit operations to detect potential nuclear safety hazards.
- d. Performance of special reviews, investigations or analyses and reports thereon as requested by the Station Manager or the Chairman of the NARC.
- e. Review and documentation of judgment concerning prolonged operation in bypass, channel trip, and/or repair of defective protection channels of process variables placed in bypass since the last OSRC meeting.
AUTHORITY 6.5.1.7 The Onsite Review Committee (OSRC) shall:
- a. Render determinations in writing with regard to whether or not items considered under 6.5.1.6(a) above constitute unreviewed safety questions.
- b. Provide written notification within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to the Manager of Nuclear Operations and the Chairman of the NARC of disagreement between the OSRC and the Station Manager; however, the Station Manager shall have responsibility for resolution of such disagreements pursuant to 6.1.1 above.
RECORDS 6.5.1.8 The Onsite Review Committee shall maintain written minutes of each OSRC meeting that, at a minimum, document the results of all OSRC activities performed under the responsibility and authority provisions of these technical specifications. Copies shall be provided to the Chairman of the NARC.
Amendment No.,
4', 66
75 TECHNICAL REVIEW AND CONTROL ACTIVITIES 6.5.1.9 The Station Manager shall assure that each procedure and program required by Specification 6.8 and other procedures which affect nuclear safety, and changes thereto, is 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.
6.5.1.10 Proposed changes to the Appendix "A" 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 Technic4l Specifications shall be approved by the Station Manager.
6.5.1.11 Proposed modifications to unit nuclear safety-related structures, systems and components shall be designed by a qualified individual/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 Drior to implementation by the Station Manager; or by the Manager, Technical as previously designated by the Station Manager.
6.5.1.12 Individuals responsible for reviews performed in accordance with 6.5.1.9, 6.5.1.10 and 6.5.1.11 shall be members of the station supervisory staff, previously designated by the Station Manager to perform such reviews.
Each such review shall included a determination of whether or not additional, cross-disciplinary, review is necessary and a verificationthat the proposed actions do not constitute an unreviewed safety question.
If deemed necessary, such review shall be performed by the appropriate designated review personnel.
6.5.1.13 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; the Manager, Technical; the Manager, Operations; the Manager, Maintenance; the Deputy Station Manager, or the Manager, Health Physics as previously designated by the Station Manager.
Amendment No. 66
75a 6.5.1.14 The station security program, 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 Manager of Nuclear Operations and to the Chairman of the NARC.
6.5.1.15 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 Manager of Nuclear Operations and to the Chairman of the NARC.
6.5.1.16 The Station Manager shall assure the performance of a review by a qualified individual/organization of changes to the radwaste treatment systems.
6.5.1.17 Reports documenting each of the activities performed under Specifications 6.5.1.9 through 6.5.1.16 shall be maintained. Copies shall be provided to the Manager of Nuclear Operations and the Chairman of the NARC.
Amendment No.
66
75b 6.5.2 NUCLEAR AUDIT AND REVIEW COMMITTEE (NARC)
FUNCTION 6.5.2.1 The NARC provides independent review and audit of designated activities in the area of nuclear safety (see Appendix A, DPR-13) and environmental impact (see Appendix B, DPR-13).
COMPOSITION 6.5.2.2 The NARC shall be composed of the:
Manager of Engineering Design Manager of Environmental Affairs Manager of Nuclear Engineering, Safety & Licensing Manager, Quality Assurance Manager of Nuclear Operations Manager, Nuclear Engineering & Safety Manager, Biological Systems Research and Development San Diego Gas & Electric Representative Chairmanship shall be designated by the Nuclear Control Board.
ALTERNATES 6.5.2.3 Alternate members shall be appointed in writing by the NARC Chairman to serve on a temporary basis; however, no more than two alternates shall participate in NARC activities at any one time.
CONSULTANTS 6.5.2.4 Consultants shall be utilized as determined by the NARC Chairman.
MEETING FREQUENCY 6.5.2.5 The NARC shall meet at least once per six months.
Amendment No.)2,> 4 66
- b. Review-and approve recommended changes to the Technical Speci fi cations.
C. Submit proposed changes to the Technical Specifications to the Commnission.
- d. Maintain management control with respect to nuclear safety.
6.6 DELETED 6.7 SAFETY LIMIT VIOLATION 6.7.1 "he following actions shall be taken in the event a Safety Limit is violated:
- a. The provisions of 10 CFR 50.36 (c)(1)(i) shall be complied with immediately.
- b. The Safety Limit violation shall be reported to the Commission, the Manager of Nuclear Operations and to the 9 NARC Chairman immediately."
- c. A Safety Limit Violation Report shall be prepared.
The report shall be reviewed by the OSRC.
This report shall describe (1) applicable circumtances preceding the violation, (2) effects of the violation upon facility components, systems or structures, and (3) corrective action taken to prevent recurrence.
- d. The Safety Limit Violation Report shall be submitted to the Commission, the NARC and the Manager of Nuclear Operations, within 14 days of the violation."
6.8 PROCEDURES 6.8.1 Written procedures and administrative policies shall be established, iuPlefmntedland maintained that meet or exceed the requirements and recomm-endations of Sections 5.1 and 5.3 of ANSI 118.7-1976, Administrative Controls for Nuclear Power Plants; Appendix "A' of USNRC Regulatory Guide 1.33, Rev. 1, Quality Assurance Program Requirements (Operation); and Paragraph 2.2.1 of Fire Protectio Prcram Review, ST?
APCS8 9.5-1, San Onofre TIc e neratin Sy:g-n- -n-t March, 19/7; except as proviael in 6.8.2 and 6.8.3 Delow.
Amendment No. 3H E9, 66
79a 6.8.2 Each procedure of 6.8.1 above, and changes thereto, shall be reviewed and approved by the Station Manager; or by (1) the Manager, Operations, (2) the Manager, Technical, (3) the Manager, Maintenance, (4) the Deputy Station Manager, (5) the Manager, Health Physics, (6) the Manager, Station Security, (7) the Manager, Configuration Control and Compliance, (8) the Manager, Station Emergency Preparedness, or (9) the Manager, Material and Administrative Services, 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 6.8.1 above 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 Reactor Operator's License on the unit affected.
- c. The change is documented, reviewed and approved by the Station Manager; or by (1) the Manager, Operations, (2) the Manager, Technical, (3) the Manager, Maintenance, (4) the Deputy Station Manager, (5) The Manager, Health Physics, (6) the Manager, Station Security, (7) The Manager, Configuration Control and Compliance, (8) the Manager, Station Emergency Preparedness, or (9) the Manager, Material and Administrative Services, as previously designated by the Station Manager; within 14 days of implementation.
Amendment No.
66
CHAIRMAN OF THE BOARD EXECUTIVE VICE PRESIDENT I
II VICE PRESIDENT VICE PRESIDENT VICE PRESIDENT VICE PRESIDENT VICE PRESIDENT VICE PRESIDENT NUCLEAR (FUEL SUPPLY)
(NUCLEAR ENGINEERING (POWER SUPPLY)
(SYSTEM (ENGINEERING &
(ADVANCED CONTROL AND OPERATIONS)
DEVELOPMENT)
CONSTRUCTION)
ENGINEERING)
BOARD NUCLEAR AUDIT AND REVIEW COMMITTEE MANAGER OF MANAGER OF MANAGER OF MANAGER OF NUCLEAR ENGINEERING, NUCLEAR ENVIRONMENTAL ENGINEERING SAFETY & LICENSING OPERATIONS AFFAIRS DESIGN DIRECTOR OF
- MANAGER, RESEARCH AND QUALITY DEVELOPMENT ASSURANCE PROJECT MANAGER MANAGER, NUCLEAR MANAGER, TRAIlING
- MANAGER, SAN ONOFRE UNIT 1 ENGINEERING &
NUCLEAR MANAGER BIOLOGICAL RETROFIT PROJECTS SAFETY LICENSING SYSTEMS R&D HEADQUARTERS STAFF STATION STAFF STATION ONSITE MANAGER REVIEW COMMITTEE.
5.2-1 OFFSITE ORGANIZATION Amendment No.
66 L-2
STATION MANAGER DEPUTY STATION MANAGER
- MANAGER, MANAGER, MANAGER
,4 MATERIAL AND STATION CONFIGURATION STATION ADMINISTRATIVE SECURITY CONTROL AND EMERGENCY SERVICES COMPLIANCE PREPAREDNESS I
I
- MANAGER, MANAGER,
- MANAGER, MANAGER, OPERATIONS MAINTENANCE TECHNICAL HEALTH PHYSICS PLANT SUPT. 1 SUPERVISING SONGS 1 COMPUTER ENGINEER MAINTENANCE SUPERVISING HP PLANNING ENGINEER SUPERVISOR SUPERVISOR NSSS SONGS 1 SUPERVISING RADWASTE ENGINEER SUPERVISOR NSSS SUPPORT SUPERVISOR OF SUPERVISING NUCLEAR PLANT ENGINEER DOSIMETRY MAINTENANCE SHIFT TECH.
SUPERVISOR ADVISORS SUPERVISOR SUPERVISOR H.P. ENGR'G.
SHIFT2 OF PLANT OF I&C GROUP SUPERVISORS COORDINATION SUPERVISOR OPERATING2 SUPERVISOR FOREMAN COORDINATORS OF CHEMISTRY SHIFT3 PERSONNEL 1At time of appointment to the position, Senior Reactor Operator license required.
2Senior Reactor license required.
3Control arid Assistant Control Operators are holders of Reactor Operator licenses.
41ncludes fire protection.
FIGURE 5.2-2 SAN ONOFRE NUCLEAR GENERATING STATION (UNIT 1) ORGANIZATION 4
5.3.1 Onsite Review Committee (OSRC)
FUNCTION 5.3.1.1 The Onsite Review Committee shall function to advise the Station Manager on all matters related to environmental impact of the station and its operation.
COMPOSITION 5.3.1.2 The Onsite Review Committee shall be composed of the:
Chairman:
Station Manager Member:
Deputy Station Manager Member:
Manager, Operations Member:
Manager, Technical Member:
Plant Superintendent SONGS 1 Member:
Supervisor of I&C Member:
Manager, Health Physics Member:
Supervisor of Chemistry Member:
Manager, Maintenance Member:
Supervising Engineer CNSSS, NSSS Support, Computer, or STA)
Member:
San Diego Gas & Electric Representative, Senior Engineerr1 )
ALTERNATES 5.3.1.3 All alternate members shall be appointed in writing by the OSMC Chairman to serve on a temporary basis; however, no more than two alternates shall participate as votingmembers in OSRC activities at any one time.
MEETING FREQUENCY 5.31.4P The OSRC shall meet at least once per calendar month and as convened by the OSRC Chairman or his designated alternate.
QUORUM 5.3.1.5 The minimum quorum of the OSRC necessary for the performance of the OSRC responsibility and authority provisions of these Technical Specifications shall consist of the Chairman or his designated alternate and four members including alternates. For environmental matters, either the Manager, Health Physics or the Supervisor of Chemistry or the respective designated alternate(s) shall be present.
BS degree in Engineering or Physical Science plus at least four years professional level experience in his field. At least one of theefour years experience shall be nuclear power plant experience.
Amendment No. dar 66
5-5 RESPONSIBILITIES 5.3.1.6 The Onsite Review Committee shall be responsible for:
- a. Investigation of all violations of the Technical Specifications including the preparation and forwarding of reports covering evaluation and recommendations to prevent recurrence to the Chairman of the Nuclear Audit and Review Committee (NARC).
- b. Review of events requiring 24-hour written notification to the Commission.
- c. Review of unit operations to detect potential environmental hazards.
- d. Performance of special reviews, investigations or analyses and reports thereon as requested by the Station Manager or the Chairman of the NARC.
AUTHORITY 5.3.1.7 The Onsite Review Committee (OSRC) shall:
- a. Render determinations in writing with regard to whether or not items considered under 5.3.1.6(a) above significantly alter the environmental impact of the facility.
- b. Provide written notification within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to the Manager of Nuclear Operations and the Chairman of the NARC of disagreement between the OSRC and the Station Manager; however, the Station Manager shall have responsibility for resolution of such disagreements.
RECORDS 5.3.1.8 The Onsite Review Committee shall maintain written minutes of each OSRC meeting that, at a minimum, document the results of all OSRC activities performed under the responsibility and authority provisions of these technical specifications. Copies shall be provided to the Chairman of the NARC.
Amendment No.
66
5-6 TECHNICAL REVIEW AND CONTROL ACTIVITIES 5.3.1.9 The Station Manager shall assure that each procedure and program required by Specification 5.5 and other procedures which relate to the environmental impact of the station and its operation, and changes thereto, is 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.
5.3.1.10 Proposed changes to the Appendix "B" 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.
5.3.1.11 Proposed modifications to the facility which relate to the environmental impact of the station and its operation shall be designed by a qualified individual/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 the facility which relate to the environmental impact of the station and its operations shall be approved prior to implementation by the Station Manager; or by the Manager, Technical as previously designated by the Station Manager.
5.3.1.12 Individuals responsible for reviews performed in accordance with 5.3.1.9, 5.3.1.10 and 5.3.1.11 shall be members of the station supervisory staff, previously designated by the Station Manager to perform such reviews.
Each such review shall include a determination of whether or not additional, cross-disciplinary, review is necessary and a verification that the proposed actions will not significantly alter the environ mental impact of the facility. If deemed necessary, such review shall be performed by the appropriate designated review personnel.
5.3.1.13 Proposed tests and experiments which relate to the environmental impact of the station and its operation and are not addressed in the FSAR or Technical Specifications shall be reviewed by the Station Manager; the Manager, Technical; the Manager, Operations; the,Manager, Maintenance; the Deputy Station Manager, or the Manager, Health Physics as previously designated by the Station Manager.
Amendment No. 66
5-7 5.3.1.14 The Station Manager shall assure the performance of a review by a qualified individual/organization of every uncontrolled or unplanned release of radioactivity or chemicals to the environs including the preparation and forwarding of reports covering evaluation, recommendations and disposition of the corrective action to prevent recurrence to the Manager of Nuclear Operations and to the Chairman of the NARC.
5.3.1.15 Reports documenting each of the activities performed under Specifications 5.3.1.9 through 5.3.1.14 shall be maintained. Copies shall be provided to the Manager of Nuclear Operations and the Chairman of the NARC."
Amendment No. 66