ML20150F073
| ML20150F073 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 07/12/1988 |
| From: | Matthews D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20150F076 | List: |
| References | |
| TAC-68222, TAC-68223, NUDOCS 8807180122 | |
| Download: ML20150F073 (29) | |
Text
{{#Wiki_filter:. 'o UNITED STATES "g NUCLEAR REGULATORY COMMISSION n { Y WASHING TON, D. C. 20656 \\...../ GEORGIA POWER C0ftPANY OGLETHORPE POWER CORPORATION MUNICIPAL ELECTRIC AUTHORITY OF GEORGIA CITY OF DALTON, GEORGIA DOCKET NO. 50-321 EDWIN I. HATCH NUCLEAR PLANT, UNIT NO. 1 AMENDitENT TO FACILITY OPERATING LICENSE Amendment No. 155 License No. DPR-57 1. The Nuclear Regulatory Comission (the Comission) has found that: A. The application for amendment to the Edwin I. Hatch Nuclear Plant, Unit 1 (the facility) Facility Operating License No. DPR-57 filed by Georgia Power Company, acting for itself, Oglethorpe Power Corporation, Municipal Electric Authority of Georgia, and City of Dalton, Geurgia, (the licensee) dated liay 6, 1988, supplemented June 7, 1988, 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; The facility will operate in conformity with the application, the B. provisions of the Act, and the rules and regulations of the Comission; C. Thereisreasonableassurance(i)thattheactivitiesauthorizedby 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 Comission's regulations set forth in 10 CFR Chapter I; D. The issuance of this amendrrent will not be inimical to the comon 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 Counission's regulations and all applicable requirements have been satisfied. 4 t 8807180122 880719 z DR ADOCK 05000321 PDC +
d 2-2. Accordingly, the license is arrended by changes to the Technical Specifi-cations as indicated in the attachment to this license amsndment, and paragraph 2.C.(2) of Facility Operating License No. OPR-57 is hereby amended to read as follows: (2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment !!o. 155, 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 implernented within 60 days of issuance. FOR THE NUCLEAR REGULATORY COMMISSION Original signed by: l David Se Patthews, Director Project Directorate II-3 Division of Reactor Projects 1/II i
Attachment:
l Changes to the Technical i Specifications i Date of Issuance: July 12, 19*8 i 1 l l OFFICIAL RECORD C0P I Y LA:Ppj!-3 PM: DII-3 GC-W 3D!!-3 itRo' tid LCrocker:pw %0 DBHatthews I ]/f /88 7/f/88 // /88 ]/y88
ATTACHMENT TO LICENSE AltENDMENT N0. 155 FACILITY OPERATING LICENSE 110. OPR-57 DOCKET fl0. 50-321 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages. The revised pages are identified by amendment nunber and contain vertical lines indicating the areas of change. Remove Page Insert Page 6-1 6-1 6-la 6-2 6-2 6-3 6-3 6-7 6-7 6-8 6-8 6-9 6-9 6-10 6-10 6-11 6-11 6-12 6-12 6-13 6-13 5-1 ETS 5-1 5-10 ETS
6.0 ADMINISTRATIVE CONTROLS 6.1 RESPONSIBILITY 6.1.0 The General Manager - Nuclear Plant shall provide direct executive oversight over all aspects of Plant Hatch. 6.1.1 The Plant Manager shall be responsible for overall unit operation, except for the Radiological Environmental Monitoring Program as described below and for delegation in writing of the succession of this responsibility during his absence. Certain plant support functions shall be the responsibility of the Plant Support Manager. 6.1.2 The Manager Radiological Safety shall be responsible for the Radiological Environmental Monitoring Program as described in the Specification 3/4.16 of Unit 1 and for the writing of the Annual Radiological Environmental Surveillance Report. The Manager Radiological Safety shall review the proposed changes to plant systems or equipment, provided that such changes are identified by the Plant Review Board (PRB) as having a potential radiological environmental impact. 6.1.3 Each of the above-mentioned individuals is responsible for the accuracy of the procedures needed to implement his responsibilities. 6.2 ORGANIZATION 6.2.1 0FFSITE AND ONSITE ORGANIZATIONS 1 Onsite and offsite organizations shall be established for unit operation and cor-1 porate management, respectively. The onsite and offsite organizations shall include the positions for activities affecting the safety of the nuclear power plant. a. Lines of authority, responsibility, and communication shall be i established and defined for the highest management levels through intermediate levels to and including all operating organization positions. These relationships shall be documented and updated, as appropriate, in the form of organization charts, functional descriptions 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 Plant Hatch Unit 2 updated FSAR. b. The Plant Manager shall be responsible for overall unit safe operation and shall have control over those onsite activities necessary for safe operation and maintenance of the plant. c. The Vice President - Nuclear shall have corporate responsibility for overall plant nuclear safety and shall take any measures needed to j ensure acceptable performance of the staff in operating, maintaining and providing technical support to the plant to ensure nuclear safety. HATCH - UNIT 1 6-1 Amendment No. 155
6.0 ADMINISTRATIVE CONTROL' d. The individuals who train the operating staf f and those who carry out health physics and quality assurance functions may report to the appropriate onsite manager; however, they shall have sufficient organizational freedom to ensure their independence from operating pressures. 6.2.2 UNIT STAFF a. Each on duty shift shall be composed of at least the minimum shift crew composition shown in table 6.2.2-1. b. At least one licensed Operator shall be in the control room for each reactor containing fuel. c. At least two licensed Operators shall be present in the control room for each reactor in the process of start-up, scheduled reactor shutdown and during recovery f rom reactor trips. d. An individual cualified to implement radiation protection procedures shall be on site when fuel is in either reactor. e. All CORE ALTERATIONS shall be directly supervised by either a licensed Senior Reactor Operator or Senior Reactor Operator Limited to Fuel Handling who has no other concurrent responsibilities during this operation. f. A Fire Team of at least five members shall be maintained onsite at all times. The Fire Team shall not include the minimum shif t crew necessary for safe shutdown on Units I and 2 or any personnel required for other essential functions during a fire emergency. g. Administrative procedures shall be developed and implemented to limit the working hours of Unit staff who perform safety-related functions; e.g., senior reactor operators, reactor operators, auxiliary operators, health physicists, and key maintenance personnel. Adequate shif t coverage shall be maintained without routine heavy use of overtime. The objective shall be to have operating personnel work a nominal 40-hour week while the plant is ope ra t ing. However, in the event that unforeseen problems require substantial amounts of overtime to be used or during extended periods of shutdown for refueling, major maintenance, or major plant modifications, the following guidelines shall be followed on a temporary basis: (1) An individual should not be permitted to work more than 16 hours straight, excluding shif t turrover time. (2) An individual should not be permitted to work more than 16 hours in any 24-hour period, nor more than 24 hours in any HATCH - UNIT 1 6-2 Amendment No. 155 l [
6.0- ADMINISTRATIVE CONTROLS e i 48-hour period, nor more than 72 hours in any 7-day period, all excluding shift turnover time. (3) A break of at least 8 hours should be allcwed between work periods, including shift turnover time. j (4) Except during extended shutdown periods, the use of overtime 1 should be considered on an individual basis and not for the entire staff on a shift. Any deviation from the above guidelines shall be authorized by the Plant Manager or higher levels of management, in accordance with established procedures and with documentation of the basis for granting the deviation. Controls shall be included in the procedures such that individual overtime shall be reviewed monthly by the Plant Manager or his designee to assure that excessive hours have not been assigned. Routine deviation from the above guidelines is not authorized, h. The Operations Superintendent, Operations Supervisor, and Shift Supervisors shall hold a senior reactor operator license. The plant operators and assistant plant operators shall hold a reactor operator license. HATCH - UNIT 1 6-3 Amendment No. 155
I ADMINISTRATIVE CONTROLS a i MEETING FREQUENCY 6.5.1.4 The PRB shall meet at least once per calendar month and as convened by the PRB Chairman or his designated alternate. i QUORUM 6.5.1.5 The minimum quorum of the PRB necessary for the performance of the PRB responsibility and authority provisions of these Technical Specifications shall consist of the Chairman or his designated alternate and three voting members including alternates. RESPONSIBILITIES 6.5.1.6 The PRB shall be responsible for: a. Review of all procedures required by Specification 6.8 and changes thereto, except those for the Radiological Environmental Monitoring Program, any'other proposed procedures or changes thereto as deter-mined by the Plant Manager to affect nuclear safety. b. Review of all proyosed tests and experiments that affect nuclear safety. c. Review of all. proposed changes to Appendix A Technical Specifications, d. Review of all proposed changes or modifications to unit systems or equipment that affect nuclear safety. I e. Investigation of all reportable violations of the Technical Specifi-i cations including the preparation and forwarding of reports covering evaluation and recommendations to prevent recurrence to the General Manager - Nuclear Plant, the Vice President - Nuclear, and to the Safety Review-Board-(SRB). f. Review of all REPORTABLE EVENTS. . g. Review of unit operations to detect potential nuclear safety hazards. h. Performance of special reviews, investigations or analyses and reports thereon as requested by the Plant Manager or the SRB. HATCH - UNIT 1 6-7 Amendment No. 155 I 6
ADMINISTRATIVE CONTROLS RESPONSIBILITIES (Continued) 1. Review of the Security Plan and implementing procedures and shall submit reconnended changes to the SRB.
- j. Review of the Emergency Plan and implementing procedures and shall submit recommended changes to the SRB.
k. Review of any unplanned onsite release of radioactive material to the environs when such release is in excess of 1 Ci, excluding dissolved and entrained gases and tritium for liquid effluents, and in excess of 150 Ci of noble gases or 0.02 Ci of radioiodines for gaseous effluents. Also included is the preparing and forwarding to the Plant Manager and the SRB reports covering evaluation, recommendations and disposition of the corrective action to prevent recurrence. 1. Review of changes to the PROCESS CONTROL PROGRAM and the OFFSITE DOSE CALCULATION MANUAL (ODCM), except for the section on the Radiological Environmental Monitoring Program in the ODCM. m. Review of proposed changes to plant systems and equipment to determine whether the proposed change has a potential radiological environmental impact. Such change (s) will be reported to the Manager-Radiological Safety. AUTHORITY 6.5.1.7 The PRB shall: a. Recommend in writing to the Plant Manager approval or disapproval of items considered under 6.5.1.6(a) through (d) above, b. Render determinations in writing with regard to whether or not each item considered under 6.5.1.6(a) through (e) above constitutes an unreviewed safety question. c. Provide written notification within 24 hours to the General Manager - Nuclear Plant, the Vice President - Nuclear, and the SRB of disagreement between the PRB and the Plant Manager; however, the Plant Manager shall have responsibility for resolution of such disagreements pursuant to 6.1.1 above. RECORDS 6.5.1.8 The PRB shall maintain written minutes of each PRB meeting that, at a minimum, document the results of all PRB activities performed under the responsi-bility and authority provisions of these Technical Specifications. Copies shall be provided to the General Manager - Nuclear Plant, the Vice President - Nuclear, and the SRB. . RATCH - Unit 1 6-8 Amendment No. 155 i i
ADMINISTRATIVE CONTROLS 6.5.2 SAFETY REVIEW BOARD'(SRB) FUNCTION The SRB shall function to provide independent review and audit of ced activities in the areas of: 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. Quality assurance practices. COMPOSITION 6.5.2.2 The SRB shall be composed of a minimum of five persons who as a group-provide the expertise to review and audit the' operation of a nuclear power plant. The Chairman and other members shall be appointed by the Vice President - Nuclear or his designee. The composition of the SRB shall meet the requirements of ANSI N18.7-1976. ALTERNATES 6.5.2.3 All alternate members shall be appointed in writing by the SRB Chairman to serve on a temporary basis; however, no more than a minority of alternates shall participate as voting members in SRB activities at any one time. However in extenuating circumstances, the Vice President - Nuclear may designate the use l of additional alternates with voting authority when regular 2 embers are not available within necessary time constraints. CONSULTANTS i 'i 6.5.2.4 Consultants shall be utilized as determined by the SRB Chairman to pro-4 vide expert advice to the SRB. HEETING FREQUENCY 6.5.2.5 The SRB shall meet at least once per calendar quarter during the initial year of unit operation following fuel loading and at least once per 6 months thereafter. KATCH - UNIT 1 6-9 Amendment No. 155 l
ADMINISTRATIVE CONTROLS OV0 RUM 6.5.2.6. The minimum quorum of the SRB necessary for the perfornance of the SRB review and audit functions of these Technical Specifications shall consist of the Chairman or his designated alternate and at least a majority of the members including alternates. No more than a minority of the quorum l shall have line responsibility for operation of the unit. REVIEW 6.5.2.7. The SRB shall be responsible for the review of: a. The safety evaluations for (1) changes to procedures, equipment, or systems and (2) tests or experiments completed under the provi ion of section 50.59, 10 CFR, to verify that such actions did not constitute 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. Proposed changes to Technical Specifications or this Operating License. Violations of codes, regulations, orders, Technical Specifications, e. license requirements, or of internal procedures or instructions having nuclear safety significance, f. Significant operating abnornalities or deviations from normal and expected perfornance of unit equipment that affect nuclear safety. g. All REPORTABLE EVENTS. h. All recognized indicatic.1s of an unanticipated deficiency in some aspect of design or operation of structures, systems, or components that could affect nuclear safety.
- i. Reports and meetings minutes of the Plant Review Board.
HATCH - UNIT 1 6-10 Amendment No. 155
ADMINISTRATIVE CONTROLS AUDITS 6.5.2.8 Audits of unit actis _cies shall be performed under the cognizance of the SRB. Each inspection or audit shall be performed within the specified time interval with: 1. A maximum allowabic extension not to exceed 25 percent of the inspection or audit interval. 2. A total maximum combined interval time for any three consecutive inspec-tions or audit intervals not to exceed 3.25 times the specified inspection or audit interval. These audits shall encompass: a. The conformance of unit operation to provisions contained within the Technical Specifications and applicable license conditions at least once per 12 months. b. The performanca, training and qualifications of the entire unit staff at least once per 12 months. c. The results of actions taken to correct deficiencies occurring in unit equipment, structures, systems or method of operation that affect nuclear safety at least once per 6 months. d. The performance of activities required by the Operational Qaality Assur-ance Program to meet the criteria of Appendix B, 10 CFR 50, at least once per 24 months. e. The Emergency Plan and implementing procedures at least once per 12 months shall be performed by individuals who have no direct responsibility for implementation of this plan. f. The Security Plan and implecenting procedures at least once per 12 months shall be performed by individualo who have no direct responsibility for implementation of this plan. g. Any other area of unit operation considered appropriate by the SRB or the Vice President - Nuclear. h. The Fire Protection Program and implementing procedures at least once per 24 months.
- i. An independent fire protection and loss prevention inspection and audit shall be performed annually utilizing either qualified of fsite licensee personnel or an outside fire protection firm.
- j. An inspection and audit of the fire protection and loss prevention program shall be performed by an outside qualified fire consultant at intervals no greater than 3 years. During the year in which the inspection or audit occura, the requirements of 6.5.2.8.1 can be affected concurrently.
HATCH - UNIT 1 6-11 Amendment No. 155
ADMINISTRATIVE CONTROLS k. The Radiological Environmental Monitoring Program and the results thereof annually. 1. The ODCM, Process Control Program, and implementing procedures at least once pee 24 months. AUTHORITY 6.5.2.9 The SRB shall report to and advise the Vice President - Nuclear on those 'l areas of responsibility specified in sections 6.5.2.7 and 6.5.2.8. RECORDS 6.5.2.10 Records of SRB activities shall be prepared, approved and distributed as indicated below: a. Minutes of each SRB meeting shall be prepared, approved and forwarded to the Vice President - Nuclear within 14 days following each meeting. l b. Reports of reviews encompassed by section 6.5.2.7 above, shall be pre-pared, approved and forwarded to the Vice President - Nuclear within 14 l_ days following completion of the review. c. Audit reports encompassed by sectic. 6.5.2.8 above, shall be forwarded to the Vice President - Nuclear and to the management positions respon-l sible for the areas audited within 30 days after completion of the audit. 6.6 REPORTABLE EVENT ACTION 6.6.1 The following actions shall be taken for REPORTABLE EVENTS: The Commission shall be notified and/or a report submitted pursuant to a. the requirements of section 50.73 to 10 CFR Part 50, and b. Each REPORTABLE EVENT shall be reviewed by the PRB and the results of this review shall be submitted to the SRB, the General Manager - Nuclear Plant, and the Vice President - Nuclear. 6.7 SAFETY LIMIT VIOLATION 6.7.1 The following actions shall be taken in the event a Safety Limit is violated: a. The unit shall be placed in at least HOT SHUTDOWN within 2 hours, b. The Safety Limit violation shall be reported to the Commission as soon as practical and in all cases within 1 hour of occurrence. The General Manager - Nuclear Plant, and Vice President - Nuclear, and the SRB shall be notified within 24 hours. HATCH - UNIT 1 6-12 Amendment No. 155
ADMINISTRATIVE CONTROLS SAFETY LIMIT V70LATION (Continued) c. A Licer see Event Report shall be prepared pursuant to.10 CFR 50.73. d. The Licensee Event Report shall be submitted to the Commission in accordance with 10 CFR 50.73, and to the PRB, the SRB, the General Manager - Nuclear Plant, and the Vice President - Nuclear within 30 days of the violation. 6.8 PROCEDURES 6.8.1 Written procedures shall be established, implemented and maintained cover-ing the activities referenced below: a. The applicable procedures recommended in Appendix A of Regulatory Guide 1.33, Revision 2, February 1978. b. Refueling operations. c. Surveillance and test activities of safety related equipment. d. Security Plan implementation. e. Emergency Plan implementation. f. Fire Protection Program implementation. g. PROCESS CONTROL PROGRAM implementation. h. ODCM implementation. 6.8.2 Each procedure of 6.8.1 and other procedures which the Plant Mana8er.or Plant Support Manager has determined to affect nuclear safety, and changes thereto, shall be reviewed by the PRB and approved by the appropriate member of plant man-agement, designated by the Plant Manager or Plant Support Manager prior to imple-mentation. The Plant Manager or Plant Support Manager eill approve administrative procedures, security plan implementing procedures, and thanges thereto. The Manager-Plant Training and Onsite Emergency Preparedness shall approve the emer-gency plan implementing procedures and changes thereto. All other proc 2dures of this specification and changes thereto will be approved by the department head destenated by the Plant Manager or Plant Support Manager. The procedures of this specification shall be reviewed periodically as set forth in administrative pro-cedures. 6.8.3 Temporary changes to procedures of 6.8.1 above may be made provided: a. The intent of the original procedure fs not altered. HATCH - UNIT 1 6-13 Amendment No. 155 -..~
5.0 Administrative Controls This section descr'bes administrative and management controls established to implement the Ene -nmental Technical Specifications (ETS). Measures speci ied ~ in this section include assignments of responsibility, review and audit func. ions, procedures, and reporting requirements. Corporate responsibility _for implementing the ETS and for assuring that the station is operated in such a way as to provide protection for the environment l rests with the Vice President - Nuclear. Responsibilities for compliance with the ETS and for the environmental monitoring program required by the ETS are given below. Independent audit shall be provided, as discussed in section 5.3.2, by the General Manager-Quality Assurance. 5.1 Responsibility 5.1.1 The Plant Manager is resnonsible for the environmental monitoring programs. The Plant Manager is also resptasible for implemencing the special surveillance activities described in section 4. 5.1.2 The General Manager-Quality Assurance is responsible for assuring that the periodic audits of plant operation and the environmental monitoring activities to ensure conformance with the ETS are conducted, 5.2 organization Company organization relative to environmentcl matters is presented in Chapter 13 of the Plant Hatch Unit 2 updated Final Safety Analysis Report. I l HATCH - UNIT 1 5-1 Amendment No. 155 ...... ~., -.
!(f 'o,, UNITED STATES NUCLEAR REGULATORY COMMISSION o ( k WASHINGTON, D. C, 20555 ,f +.... GEORGIA POWER COMPANY OGLETHORPE POWER CORPORATION MUNICIPAL ELECTRIC AUTHORITY OF GEORGIA CITY OF DALTON, E0RGIA DOCKET N0. 50-366 EDWIN I. HATCH NUCLEAR PLANT, UNIT NO. 2 AMENDMENT TO FACILITY OPCRATING LICENSE Amendment No. 94 License No. NPF-5 1. The Nuclear Regulatory Commission (the Comission) has found that: A. The application for amendment to the Edwin I. Hatch Nuclear Plant, Unit 2 (the facility) Facility Operating License No. NPF-5 filed by Georgia Power Company, acting for itself, Oglethorpe Power Corporation, Municipal Electric Authority of Georgia, and City of Dalton, Georgia, (the licensee) dated May 6, 1988, supplemented June 7, 1988, 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 Comission; 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 Comission's regulations set forth in 10 CFR Chapter I; D. The issuance of this amendment will not be inimical to the comon 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 Comission's regulations and all applicable requirements have been satisfied. l
~ 1 ~ 2. Accordingly, the license is amended by changes to the Technical Specifi-cations as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating. License No. NPF-5 is -hereby amended to read as follows: (2). Technical Specifications-The' Technical Specifications contained.in Appendices A and B, as revised through Amendment No. 94, 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.60 days of issuance. FOR TiiE NUCLEAR REGULATORY COMMISSION Original signed by: . David B. Matthews, Director Project Directorate II-3 Division of Reactor Projects-I/II 1
Attachment:
1 Changes to the Technical Specifications Date of Issuance: July 12, 1988 1 0FFICIAL RECORD C Otl \\ }\\ F.l. GdDII-3 L {I-3 Ph II-3 OGC-{pthi - DBHatthews [ /88 M LCrocker:pw '/ / /88 ' 7 / f/88 ]/p/8C
ATTACHt4ENT TO LICENSE Al4EflDffENT NO. 94 FACILITY OPERATIflG LICENSE f;0. NPF-5 DOCKET fl0. 50-366 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 Page Insert Page-6-1 6-1 6-la 6-? 6-2 6-3 6-3 6-5 6-5 6-6 6-6 6-7 6-7 6-8 6-8 6-9 6-9 G-10 6-10 6-11 6-11 6-12 6-12 5-1 ETS 5-1 5-10 ETS I L
6.0 ADMINISTRATIVE CONTROLS 6.1 RESPONSIBILITY 6.1.0 The General Manager - Nuclear Plant shall provide direct executive oversight over all aspects of Plant Hatch. 6.1.1 The Plant Manager shall be responsible for overall unit operation, except for the Radiological Environmental Monitoring Frogram as described below and for delegation in writing of the succcssion of this responsibility during his absence. Certain plant support functions shall be the responsibility of the Plant Support Manager. 6.1.2 The Manager Radiological Safety shall be responsible for the Radiological Environmental Monitoring Program as described in the Specification 3/4.16 of Unit 1 and for the writing of the Annual Radf ological Environmental Surveillance Report. The Manager Radiological Safety shall review the proposed changes to plant systems or equipment, provided that such char.3es are identified by the Plant Review Board (PRB) as having a potential radiological environmental impact. 6.1.3 Each of the above-mentioned individuals is responsible for the accuracy of the procedures needed to implement his responsibilities. 6.2 ORGANIZATION 6.2.1 0FFSITE AND_0NSITE ORGANIZATIONS Onsite and offsite organizations shall be established for unit operation and cor-porate management, respectively. The onsite and offsite organize.tions shall include the positions for activities affecting the safety of the nuclear power plant. a. Lines of authority, responsibility, and communication shall be established cnd defined for the highest management levels through intermediate levels to and including all operating organization positions. These relationships shall be documented and updated, as appropriate, in the form of organization charts, functional descriptions 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 Plant Hatch Unit 2 updated FSAR. b. The Plant Manager shall be responsible for overall unit safe operation and shall have control over these onsite activities necessary for safe operation and maintenance of the plant. c. The Vice ?rasident - Nuclear shall have colporate 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 *o ensure nuclear safety. HATCH - UNIT 2 6-1 kmendment No. 94 l
6.0 ADMINISTRATIVE CONTROLS d. The individuals who train the operating staff and those who carry out health physics and quality assurance functions may report to the appropriate onsite manager; however, they shall have sufficient organizational freedom to ensure their independence from operating pressures. 6.2.2 UNIT STAFF a. Each on duty shift shall be composed of at least the minimum shift crew composition shown in table 6.2.2-1. b. At least one licensed Operator shall be in the control room for each reactor containing fuel. c. At least two licensed Operators shall be present in the control room for aach reactor in the process of start-up, scheduled reactor shutdown and during recovery from reactor trips. d. An individual qualified to implement radiation protection procedures shall be on site when fuel is in either reactor. All CORE ALTERATIONS shall be directly supervised by either a e. licensed Senior Reactor Operator or Senior Reactor Operator Limited to Fuel Handling who has no other concurrent responsibilities during this operation. f. A Fire Team of at least five members shall be maintained onsite at all times. The Fire Team shall not include the minimum shift crew necessary for safe shutdown on Units 1 and 2 or any personnel required for other essential functions during a fire emergency. g. Administrative procedures shall be developed and implemented to limit the working hours of. Unit staff who perform safety-related functions; e.g., senior reactor operators, reactor operators, auxiliary operators, health physicists, and key maintenance personnel. Adequate shift coverage shall be maintained without routine heavy use of overtime. The objective shall be to have operating personnel work a nominal 40-hour week while the plant is operating. However, in the< event that unforeseen problems require substantial amounts of nyercime to be used or during extended periods of shutdown for refueling, major maintenance, or major plant modifications, the following guidelines shall be followed on a temporary basis: (1) An individual should not be permitted to work more than 16 hours straight, excluding shift turnover time. HATCH - UNIT 2 6-2 Amendment No. 94
ADMINISTRATIVE CONTROLS (2) An individual should not be permitted to work more than 16 hours in any 24-hour period, nor more than 24 hours in any 48-hour period, nor more than 72 hours in any 7-day period, all excluding shift turnover time. (3) A break of at least 8 hours should be allowed between work periods, including shift turnover time. (4) Except during extended shutdown periods, the use of overtime should be considered on an individual basis and not for the entire staff on a shift. Any deviation from the above guidelines shall be authorized by the Plant Manager or higher levels of management, in accordance with established procedures and with documentation of the basis for granting the deviatir;n. Controls shall be included in the procedures such that individual overtime shall be reviewed monthly by the Plant Manager or his designee to assure that excessive hours have not been assigned. Routine deviation from the above guidelines is not authorized. h. The Operations Superintendent, Operations Supervisor, and Shift Supervisors shall hold a senior reactor operator license. The plant operators and assistant plant operators shall hold a reactor operator license. i l Amendment No. 94 HATCH - UNIT 2 6-3 i 4 's,
j i ADMINISTRATIVE CONTROLS 6.3 UNIT STAFF QUALIFICATIONS 6.3.1 Each member of the unit staff shall meet or exceed the minimum qualifications of ANSI N18.1-1971 for comparable positions, except for the Health Physics Superintendent who shall meet or exceed the qualifications of Regulatory Guide 1.8, September 1975, and the Shift Technical Advisor who snall 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 T' RAINING 6.4.1 A retraining and replacement training program for the unit staff shall be maintained under the direction of the Manager of Training 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 fire protection shall be mdintained under the direction of the Senior Regulatory Specialist and shall meet or exceed the requirements of section 27 of the NFPA Code-1975, except for fire protection training sessions which shall be held at least once per 92 days. 6.5 REVIEW AND AUDIT 6.5.1 PLANT REVIEW BOARD (pRB) FUNCTION 6.5.1.1 The PRB shall function to advise the Plant Manager on all matters related to nuclear satety. COMPOSITION 6.5.1.2 The PRB shall be enmposed of, as a minimum, a supervisor or higher levei individual from each of the departments listed below: Operations Maintenance Quality Control (QC) Health Physics Nuclear Safety and Compliance Engineering Support The Chairman, his alternate, and other members of the PRB shall' be designated by the Plant Manager. The Chairman and his de:ignated alternate shall both be managers of one of the six above listed departments or a higher level onsite manager. ALTERNATES 6.5.1.3 All alternate members shall be appointed in waiting by the PR'B Chairman to serve on a temporary basis; however, no more than two alternates shall participate as voting members in PRB activities at any one time. HATCH - UNIT 2 6-5 Amendment No. 94
0 ADMINISTRATIVE CONTROLS MEETING FREQUENCY 6.5.1.4 The PRB shall meet at least once per calendar month and as convened by the PRB Chairman or his designated alternate. QUORUM 6.5.1.5 The minimum quorum of the PRB necessary for the performance of the PRB responsibility and authority provisions of these Technical Specifications shall consist of the Chairman or his designated alternate and three voting members including alternates. RESPONSIBILITIES 6.5.1.6 The PRB shall be responsible for: Review of all procedures required by Specification 6.8 and changes a. thereto, except those for the Radiological Environmental Monitoring Program, any other proposed procedures or changes thereto as deter-mined by the Plant Manager to affect nuclear safety, b. Review of all proposed tests and experiments that affect nuclear safety. c. Review of all proposed changes to Appendix A Technical Specifications. d. Review of all proposed changes or modifications to unit systems or equipment that affect nuclear safety. e. Investigation of all reportable violations of the Technical Specifi-cations including the preparation and forwarding of reports covering evaluation and recommendations to prevent recurrence to the General l Manager - Nuclear Plant, the Vice President - Nuclear, and to the l Safety-Review-Board (SRB). f. Review of all REPORTABLE EVENTS. g. Review of unit operations to detect potential nuclear safety hazards. h. Performance of special reviews, investigations or analyses and reports thereon as requested by the Planc Manager or the SRB. RATCH - UNIT 2 6-6 Amendment No. 94 .. _. _ ~ _ ... ~.
ADMINISTRATIVE CONTROLS RESPONSIBILITIES 0 antinued) 1. Review o
- he Security Plan and implementing procedures and shall submit recomme-ed changes to the SRB.
j. Revie' of the Emergency Plan and implementing procedures and shall subm! recommended :hanges to the SRB. k. Review of any unplanned onsite release of radioactive material to the environs when sv;h release is in excess of 1 C1, excluding dissolved and entrained gases and tritium for liquid effluents, and in excess of 150 Ci of noble gases or 0.02 Ci of radioiodines for gaseous effluents. Also included is the preparing and forwarding to the Plant Manager and the SRB reports covering evaluation, recommendations and disposition of the morreceive action to prevent recurrence. 1. Review of chany,es to the PROCESS CONTROL PROGRAM and the OFFSITE DOSE CALCULATION MAN'jAL (ODCM), except for the section on the Radiological Environmental Monitoring Program in the ODCM. m. Reui:s of proposed changes to plant systems and equipment to determine vnether the proposed change has a potential radiological environmental impact. Such change (s) will be reported to the Manager-Radiological Safety. n. Review of the Fire Protection Program and implementing procedures and shall submit recommended changes to the SRB. AUTHORITY 6.5.1.7 The PRB chall: a. Recommend in writing to the Plant Manager approval or disapproval of itema considered under 6.5.1.6(a) through (d) above, b. Render determinations in writing with regard to whether or not each item considered under 6.5.1.6(a) through (e) above constitutes an unreviewed safety question, c. Provide written notification within 24 hours to the General Manager - Nuclear Plant, the V!.ce President - Nuclear, and the SRB of disagreement between the PRB and the Plant Manager; however, the Plant hanager shall have responsibility for restlution of such disagreements pursuant to 6.1.1 above. 1 RECORDS l 6.5.1.8 The PRB shall maintain written minutes of each PRB meeting that, at a l minimum, document the results of all PRB activities performed under the responsi-bility and authority provisions of these Technical Specifications. Copies shall be provided to the General Manager - Nuclear Plant, the Vice President - Nuclear, and the SRB. m Q-J M. A
ADMINISTRATIVE CONTROLS 6.5.2 SAFETY REVIEW BOARD (SRB) FUNCTION 6.5.2.1 The SRB 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. Quality assurance practi-es. COMPOSITION 6.5.2.2 The SRB shall be composed of a minimum of five persons who as a group provide the expertise to review and audit the operation of a nuclear power plant. The Chairman and other members shall be appointed by the Vice President - Nuclear or his designee. The composition of the SRB shall meet the requirements of ANSI N18.7-1976. ALTERNATES 6.5.2.3 All alternate members shall be appointed in writing by the SRB Chairman to serve on a temporary basis; however, no more than a minority of alternates shall participate as voting members in SRB activities at any one time. However in extenuating circumstances, the Vice President - Nuclear may designate the use l of additional alternates with voting authority when regular members are not available within necessary time constraints. CONSULTANTS 6.5.2.4 Consultants shall be utilized as determined by the SRB Chairman to pro-vide expert advice to the SRB. MEETING FREQUENCY 6.5.2.5 The SRB shall meet at least once per calendar quarter during the initial year of unit operation following fuel loading and at least once per 6 months thereafter. RATCH - UNIT 2 6-8 Amendment No. 94
ADMINISTRATIVE CONTROLS QUORUM 6.5.2.6 The minimum quorum o' the SRB necessary for the performance of the SRB review and audit f#metions of these Technical Specifications shall consist of the Chairman er his designated alternate and at least a majority of the members including titernates. No more than a minority of the quorum l shall have line responsibility for operation of the unit. REVIEW 6.5.2.7 The SRB shall be responsible for the review of: The safety evaluations for (1) changes to procedures, equipment, a. or systems and (2) tests or experiments completed under the provision of section 50.59, 10 CFR, to verify that such actions did not constitute an unreviewed safety question, b. Ficpe::d changes to procedures, equipment or systems which involve an unreviswed safety question as defined in section 50.59, 10 CFR. c. Proposed tests or experiments which involve an unraviewed safety question as defined in section 50.59, 10 CFR. d. Proposed changes to Technical Speci:'ications or this Operating License. Violations of codes, regulations, orders, Technical Specifications, e. license requirements, or of internal procedures or instructions having nuclear safety significance. f. Significant operating abnormalities or deviations from normal and expected performance of unit equipment that affect nuclear safety. g. All REPORTABLE EVENTS. h. All recognized indications of an unanticipated deficiency in h some aspect of design or operation of structures, systems, or components that could affect nuclear safety. i. Reports and meetings minutes of the PRB. HATCH - UNIT 2 6-9 Amendment No. 94
l ADMINISTRATIVE CONTROLS 1 l AUDITS 1 6.5.2.8 Audits of unit activities shall be performed under the cognizance of tne SRB. Each inspection or audit shall be performed within the specified time interval with: 1. A maximum allowable extension not to exceed 25 percent of the inspection or audit interval. 2. A total maximum combined interval time for any three consecutive inspec-tions or audit intervals not to exceed 3.25 times the specified inspection or audit interval. These audits shall encompass: a. The conformance of unit operation to provisions contained within the Technical Specifications and applicable license conditions at least once per 12 months. b. The performance, training and qualifications of the entire unit staff at least once per 12 months. c. The results of actions taken to correct deficiencies occurring in unit equipment, structures, systems or method of operation that affect nuclear safety at least once per 6 months. d. The performance of activities required by the Operational Quality Assur-ance Program to meet the criteria of Appendix B, 10 CFR 50, at least once per 24 months. e. The Emergency Plan and implemet. ting procedures at least once per 12 months shall be perfcrmed by inolviduals who have no direct responsibility for implementation of this plan. f. The Security Plan and implementing procedures at least once per 12 months shall be performed by individuals who have no direct responsibility for implementation of this plan. g. Any other area of unit operation considered appropriate by the SRB or the Vice President - Nuclear. h. The Fire Protection Program and implementing procedures at least once per 24 months,
- i. An independent fire protection and loss prevention inspection and audit shall be performed annually utilizing either qualified offsite licensee personnel or an outside fire protection firm.
- j. An inspection and audit of the fire protection and loss prevention program shall be performed by an outside qualified fire consultant at intervals no greater than 3 years.
During the year in which the inspection or audit occurs, the requirements of 6.5.2.8.1 can be affected concurrently. HATCH - UNIT 2 6-10 Amendment No.94
e L ADMINISTRATIVE CONTROLS k. The Radiological Environmental Monitoring Program and the results thereof annually. 1. The 00CM, Process Control Program, and implementing procedures at least once per 24 months. AUTHORITY t 1 6.5.2.9 The SRB shall report to and advise the Vice President - Nuclear on those l areas of responsibility specified in sections 6.5.2.7 and 6.5.2.8. l L RECORDS l 6.5.2.10 Records of SRB activities shall be prepared, approved and distributed as indicated below: a. Minutes of each SRB meeting shall be prepared, approved and forwarded to the Vice President - Nuclear within 14 days following each meeting. l j b. Reports of reviews encompassed by section 6.5.2.7 above, shall be pre-pared, approved and forwarded to the Vice President - Nuclear within 14 l days following completion of the review. c. Audit reports encompasse ! by section 6.5.2.8 above, shall be forwarded to the Vice President - Nuclear and to the management positions respon-l sible for the areas audited within 30 days after completion of the audit. l 6.6 REPORTABLE EVENT ACTION 6.6.1 The following actions shall be taken for REPORTABLE EVENTS: a. The Commission shall be notified and/or a report submitted pursuant to the requirements of section 50.73 to 10 CFR Part 50, and b. Each REPORTABLE EVENT shall be reviewed by the PRB and the results of this review shall be submitted to the SRB, the General Manager - Nue* 'r Plant, and the Vice President - Nuclear. 6.7 SAFETY LIMIT VIOLATION 6.7.1 The following actions shall be taken in the event a Safety Limit is violated: a. The unit shall be placed in at least HOT SHUTDOWN within 2 hours, b. The Safety Limit violation shall be reported to the Comission as soon as practical and in all cases within 1 hour of occurrence. The General Manager - Nuclear Plant, and Vice President - Nuclear, and the SRB shall be notified within 24 hours. [ b HATCH - UNIT 2 < 6-11 Amendment No. 94 t L h b
ADMINISTRATIVE CONTROLS SAFETY LIMIT VIOLATION (Continued) c. A Licensee Event Report shall be prepared pursuant to 10 CFR 50.73. d. The Licensee Event Report shall be submitted to the Commission in accordance with 10 CFR 50.73, and to the PRB, the SRB, the General Manager - Nuclear Plant, and the Vice President - Nuclear within 30 days of the violation. 6.8 PROCEDURES 6.8.1 Written procedures shall be established, implemented aad maintained cover-ing the activities referenced below: a. The applicable proceduros recommended in Appendix A of Regulatory Guide 1.33, Revision 2, February 1978. b. Refueling operations, c. Surveillance and test activities of safety related equipment. d. Security Plan implementation. e. Emergency Plan implementation. f. Fire Protection Program implementation, g. PROCESS CONTROL PROGRAM implementation. h. ODCM implementation. 6.8.2 Each procedure of 6.8.1 and other procedures which the Plant Manager or Plant Support Manager has determined to affect nuclear safety, and changes thereto, shall be reviewed by the PRB and approved by the appropriate member of plant man-agement, designated by the Plant Manager or Plant Support Manager prior to imple-mentation. The Plant Manager or Plant Support Manager will approve administrative procedures, security plan implementing procedures, and changes thereto. The Manager-Plant Training and Onsite Emergency Preparedness shall approve the emer-gency plan implementing procadures and changes thereto. All other procedures of this specification and changes thereto will be approved by the department head designated by the Plant Manager or Plant Support Manager. The procedures of this specification shall be reviewed periodically as set forth in administrative pro-cedures. 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. HATCH - UNIT 2 6-12 Amendment No. 94
e t 5.0 Afministrative Controls This section describes administrative and management controls established to implencnt the Environmental Technical Specifications (ETS). Measures specified in this section include assignments of responsibility, review and audit functions, procedures, and reporting requirements. Corporate responsibility for implementing the ETS and for assuring that the station is operated in such a way as to provide protection for the environment rests with the Vice President - Nuclear. { Responsibilities for compliance with the ETS and for the environmental monitoring program required by the ETS are given below. Independent audit shall be provided, as discussed in section 5.3.2, by the General Manager-Quality Assurance. 3.1 Responsibility 5.1.1 The Plant Manager is responsible for the environmental monitoring programs. The Platit Manager is also responsible for implementing the special surveillance activities described in section 4. 5.1.2 The General Manager-Quality Assurance is responsible for assuring that the periodic audits of plant operation and the environmental monitoring activities to ensure conformance with the ETS are conducted. 5.2 organization Company organization relative to environmental matters is presented in Chapter 13 of the Plant Hatch Unit 2 updated Final Safety Analysis Report. HATCH - UNIT 2 5-1 Amendment No. 94 -.. _ - _ _.}}