ML17300B004

Proposed Tech Spec Section 6, Administrative Controls.

ML17300B004
Person / Time
Site:	Palo Verde
Issue date:	08/10/1987
From:	ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR
To:
Shared Package
ML17300B002	List: ML17300A999 ML17300B004
References
TAC-66798, TAC-66799, TAC-66800, NUDOCS 8708240324
Download: ML17300B004 (128)

Text

ATTACHMENT 1 CONDUCT OF OPERATIONS 82~0~ 4 870810 ADQQQ Pgpppgg

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INDEX CONDUCT OF OPERATIONS PAGE 1.0 ORGANIZATIONAL STRUCTURE OF APPLICANT 1-1 1.1 Management 6 Technical Support Organization l-l 1.1.1 Technical Support for Operations 1-1 1.1.2 APS Organizational Arrangement l-l 1.1.2.1 APS Nuclear Organization l-l 1.1.2.1.1 Vice President Nuclear Production Organization 1-2 1.1.2.1.2 Director Site Services 1-3 1.1.2.1.2.1 Manager Security 1-3 1.1.2.1.2.2 Manager Emergency Planning and Services 1-4 1.1.2.1.2.2.1 Fire Protection Department 1-4 1.1.2.1.2.2.2 Emergency Planning Department 1-4 1.1.2.1.2.3 Manager Training 1-5 1.1.2.1.2.4 Manager Material Control 1-5 1.1.2.1.2.5 Manager Administrative Services 1-5 1.1.2.1.3 Director Engineering and Construction 1-6 1.1.2.1.3.1 Manager Nuclear Engineering 1-6 1.1.2.1.3.2 Manager Participant Services 1-7 1.1.2.1.3.3 Manager Records Management 1-7 1.1.2.1.3.4 Manager Cost and Schedule 1-8 1.1.2.1.3.5 Manager Construction 1-9 1.1.2.1.3.6 Manager Nuclear Fuels 1-9 1.1.2.1.4 Director Nuclear Safety and Licensing 1-9 1.1.2.1.5 Director Quality Assurance 1-10 1.1.3 Qualification of Headquarters Staff 1-10 1.2 1.2.1 Onsite Operating Organization Onsite Station Organization l-ll 1-11 1.2.2 Station Personnel Responsibilities and Authorities 1-11 1.2.2.1 1.2.2.1.1 Vice President-Nuclear Production Plant Manager l-ll 1-12 1.2.2.1.1.1 Operations Manager 1-12 1.2.2.1.1.1.1 Shift Supervisors 1-12 1.2.2.1.1.1.2 Assistant Shift Supervisor 1-13 1.2.2.1.1.1.3 Nuclear Operator III 1-13 1.2.2.1.1.1.4 Nuclear Operator I and II 1-13 1.2.2.1.1.2 Radwaste Supervisor 1-13 1.2.2.1.1.3 Maintenance Manager 1-13 1.2.2.1.1.4 Work Control Manager 1-14 1.2.2.1.1.5 Radiation Protection Manager 1-14 1.2.2.1.1.6 Chemisty Manager 1-14 1.2.2.2 Assistant Vice President-Nuclear Production Support 1-14 1.2.2.2.1 Water Reclamation Facility (WRF) Manager 1-14 1.2.2.2.2 Outage Management Manager 1-15 1.2.2.2.3 Central Maintenance Manager 1-15 1.2.2.2.4 Radwaste Support Manager 1-15 1.2.2.2.5 Central Radiation Protection Manager 1-15 1.2.2.3 Director Standards and Technical Support 1-15 1.2.2.3.1 Engineering Evaluation Manager 1-16

INDEX CONDUCT OF OPERATIONS Continued)

PAGE 1.2.2.3.1.1 Reactor Engineering Supervisor 1-16 1.2.2.3.1.2 Test Engineer Supervisor 1-16 1.2.2.3.1.3 Shift Technical Advisor (STA) Supervisor 1-16 1.2.2.3.1.4 System Engineering Supervisor 1-16 1.2.2.3.1.4.1 Supervisor of Station Statistics 1-17 1.2.2.3.2 Operations Computer Systems Manager 1-17 1.2.2.3.3 Radiation Protection and Chemistry Manager 1-17 1.2.2.3.4 Plant Standards and Control Manager 1-17 1.3 Qualifications of Nuclear Plant Personnel 1-18 1.3.1 Qualification Requirements 1-18 1.3.2 Qualifications of Plant Personnel 1-21 1.4 Review and Audit 1-21 1.4.1 Onsite Review 1-21 1.4.2 Independent Review 1-22 1.4.2.1 Nuclear Safety Group (NSG) 1-22 1.4.2.2 Independent Safety Engineering Group (ISEG) 1-22 1.4.2.3 Audit Program 1-22

POSITION FUNCTION CROSS REFERENCE~1~

Existin Function New Function President and Chief Operating Officer President and Chief Operating Officer ANPP Executive Vice President ANPP Executive Vice President V.P. Nuclear Production V.P. Nuclear Production Plant Manager Plant Managers Operations Manager None Ops. Supt. Operations Manager Day Shift Supv. Operations Support Supervisor Shift Supv. Shift Supv.

Assist. Shift Supv. Assist. Shift Supv.

Supervisor Ops. Support None Site Manager, Maintenance Maintenance Manager Central Maintenance Manager MCC Superintendent None IGC/Elec. Work Control Supv. None Mech. Work Control Supv. None IGC Maintenance Supt. IGC Maintenance Supervisor Electrical Maintenance Supt. Electrical Maintenance Supervisor Mechanical Maintenance Supt. Mechanical Maintenance Supervisor Plant Services Manager Director, Site Services Mgr., Outage Management Central Outage Management Mgr.

Outage Supt. Work Control Manager None Director, Nuclear Safety & Licensing Mgr., Compliance Mgr., Compliance Mgr., Technical Support Director, Standards and Technical Support None Plant Standards and Control Manager

POSITION FUNCTION CROSS REFERENCE(1)

(Continued)

Existin Function New Function Ops Engineering Manager Engineering Evaluation Manager STA Supv. STA Supv.

Tech. Engineering Supervisor Test Engineering Supervisor OR Engineer-Mech. Supervisor System Engineering Supervisor OR Engineer-Elec./IGC Supervisor Station Statistics Supervisor Reactor Engineering Supervisor Reactor Engineering Supervisor Radiation Prot. and Chemistry Mgr. Radiation Protection 6 Chemistry Mgr.

Radiation Mat'ls Control Mgr. Radwaste Support Manager Radwaste Supv. Operations Support Supervisor Radwaste Support Supv. Radwaste Support Manager Radiological Services Mgr. Radiation Protection Manager Radiation Protection Support Supv. Central Radiation Protection Manager Supv.

Chemical Service Mgr. None Unit Chemistry Supv. Unit Chemistry Manager ALARA Supv. Radiation Protection Manager Ops Computer System Ops Computer Manager Hardware Maintenance Supv. Hardware Maintenance Supv.

Process Computer Engr. Supv. Process Computer Engr. Supv.

Computer Support Supv. (Vacant) Computer Support Supv.

Plant Services Manager Director, Site Services (in part:)

Operations Security Mgr. Security Mgr.

Assist. V.P.-Nuclear Production Assist. V.P.-Nuclear Production Support HRF Superintendent MRF Mgr.

Administrative Services Mgr. Administrative Services Manager Material Control Supv. Material Control Supv.

Inventory Control Supv. Inventory Control Supv.

Transportation Supv. Transportation Supv.

Emergency Planning Mgr. Emergency Planning 6 Services Mgr.

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POSITION FUNCTION CROSS REFERENCE(l~

Continued Existin Function New Function Training Mgr. Training Mgr.

General Training Supv. General Training Supv.

Operator Training Supv. Operator Training Supv.

Training Support Supv. Training Support Supv.

Project Mgr. of Accred. Project Mgr. of Accred.

Transition Mgr. None (Job was completed)

Director, Technical Services Director, Engineering and Construction Nuclear Engineering Mgr. Engineering Mgr.

Production Mgr. Engineering Mgr.

Electrical Engineering Supv. Electrical Engineering Supv.

Mech. & Chem. Engineering Supv. Mech. & Chem. Engineering Supv.

Civil & Arch. Eng. Supv. Civil & Arch. Eng. Supv.

I&C Engineering Supv. I&C Engineering Supv.

Corp. Health Phys. Supv. None (Moved under Radiation and Chemistry Manager Analysts, Lead Reliability Analysis Supv.

Methods Trg. Compliance, Lead Methods Trg. Compliance, Lead Nuclear Construction Mgr. Nuclear Construction Mgr.

Nuclear Construction Personnel Nuclear Construction Personnel N.P. Records Mgmt. Mgr. N.P. Records Mgmt. Mgr.

Nuclear Records Personnel Nuclear Records Personnel Nuclear Fuel Mgmt. Mgr. Nuclear Fuel Mgmt. Mgr.

Fuel Cycle Serv. Supv. Fuel Cycle Serv. Supv.

Nuclear Analysis Supv. Nuclear Analysis Supv.

Safety Analysis Supv. Safety Analysis Supv.

Technical Projects Supv. Technical Projects Supv.

Nuclear Licensing Mgr. Nuclear Licensing Mgr.

4 POSITION FUNCTION CROSS REFERENCE(1)

Continued Existin Function New Function None Director Nuclear Safety and Licensing NSG/ISEG Manager Manager Nuclear Safety Group; Manager ISEG Director, Corporate QA/QC Director, Corporate QA/QC Assistant Director QA/QC None Quality Systems and Engineering Quality Systems and Engineering Manager Manager Procurement Quality Manager Procurement Quality Manager Quality Audits and Monitoring Quality Audits and Monitoring Manager Manager Quality Control Manager Quality Control Manager NOTE:

This table represents a cross reference of job functions from the existing organization to the new (proposed) organization. Job functions from existing to new are meant to show the best match. In some cases a new function may have less or more responsibilities than the existing function.

C

0 ATTACHMENT 1 CONDUCT OF OPERATIONS

1. ORGANIZATIONAL STRUCTURE 1.1 Mana ement and Technical Su ort Or anization This section provides information relative to the corporate organization and its functions and responsibilities and the number and qualifications of personnel participating in the operation of the units and the offsite support of the units.

1.1.1 Technical Su ort for 0 erations The Executive Vice President of Arizona Nuclear Power Project (ANPP), through the President of Arizona Public Service Company (APS), has been designated by the Chairman, Board of Directors and Chief Executive Officer of APS as the Corporate Officer responsible for providing management and technical support services for PVNGS (Refer to Figure 1-1).'he Executive Vice President, ANPP has established under him groups and departments as discussed in Section 1.1.2.1 and as shown on Figure 1-2.

1.1.2 APS Or anizational Arran ement Figure l-l reflects the current APS Master Organization. No change is being made to this structure as a result of the ANPP organizational changes. The organizational arrangement for providing onsite and offsite technical support for nuclear operations is described in the following sections.

1.1.2.1 APS Nuclear Or anization The Executive Vice President, Arizona Nuclear Power Project (ANPP) has the overall responsibility and authority for the operation and technical support of PVNGS. This position has the overall responsibility and authority to ensure that all activities associated with APS'uclear facilities are carried out with the highest standards of safety. Figure 1-2 reflects the organization of the Executive Vice President, ANPP.

Reporting directly to the Executive Vice President, ANPP are the following: Vice President-Nuclear Production, Director Site Services, Director Engineering and Construction, Director Nuclear Safety and Licensing and Director Corporate QA/QC.

This organization is discussed in the following sections.

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Vice President, Nuclear Production Or anization The Vice President, Nuclear Production reports to the Executive Vice President, ANPP. This position is responsible to operate and maintain the three PVNGS units and the Water Reclamation Facility (WRF). The major functions of this position are: Operate and maintain the three Units and the WRF to ensure compliance with regulatory requirements and approved procedures; Plan and schedule the Units activities; Provide functional support required for the operation and maintenance, such as plant wide chemical and , radiological services and waste disposal, and maintenance planning; Assure standardization of procedures and practices among the Units; Performance of direct technical and engineering support for plant operations and maintenance, including approval of design improvements and changes to operational requirements, as well as the design and installation of minor plant modifications and validation testing of all modifications.

This position is charged with the authority to ensure that these activities related to nuclear safety are completed with the highest standards of safety and authority to allocate resources under this area of it has the responsibility.

Figure 1-3 reflects the organization of the Vice President-Nuclear Production.

To carry out his responsibilities, the Vice President-Nuclear Production has established the groups discussed later in Section 1.2.2.1. In the absence of the Vice President-Nuclear Production, the Assistant Vice President-Nuclear Production Support shall be delegated those nuclear safety responsibilities and authorities and shall have direct access to the Executive Vice President, ANPP for support and decisions as required.

I Chan es to the Vice President-Nuclear Production Position This position will now be responsible for Operation, Maintenance and support of operation and maintenance for the Units and the WRF. Previous ancillary responsibilities for all aspects of the facility such as; Security, Training, Emergency Planning, Administrative Services, Offsite Engineering and Construction, Nuclear Records and Licensing are placed elsewhere in the organization (Refer to current FSAR Figure 13.1-3 for this position's past organization).

The Manager, Transition position previously reporting to the Vice President-Nuclear Production (Refer to current FSAR Figure 13.1-2 and FSAR Section 13.1.1.2.8 and 14.2) has completed its functions and is being eliminated.

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1.1.2.1.2 Director, Site Services The Director, Site Services reports to the Executive Vice President, ANPP. This onsite position is responsible to provide administrative and special site services that support the operation of PVNGS by satisfying commitments to regulatory agencies and oversight groups. These services include Plant Security, Training, Emergency Planning and Services, Material Control and Administrative Services. The major functions of this position are:

Implement an On-Site Security Program to prevent sabotage and unwarranted intrusion by unauthorized persons for whatever reason, in accordance with the NRC-approved plan; Provide training programs for PVNGS personnel in concert with the requirements of the NRC, other agencies, and the Company; Implement programs in the area of fire protection, and emergency preparedness; Provide administrative services support for the nuclear facilities including site transportation needs, clerical, word processing, duplicating, and mail distribution services; Manage the Material Control Department to provide coordinated services for procurement, purchasing, inventory control, and warehousing of materials.

Figure 1-4 reflects the organization of the Director, Site Services. The department managers which report directly to the Director of the Site Services Group are discussed in the following sections which include functions of the previous Manager, Administrative Services, and Manager, Training (current FSAR Figure 13.1-3A) Manager, Emergency Planning (current FSAR Figure 13.1-3A), Manager, Security and Supervisor, Fire, Protection (current FSAR Figure 13.1-6D).

lt Chan es to the Site Services Grou The Director, Site Services is a new position title. The functions of departments now reporting to this position previously existed but reported to different points.

1.1.2.1.2.1 Mana er, Securit The Security Manager is responsible to the Director, Site Services to plan, develop, implement and manage the PVNGS Security Program. These responsibilities include Operations Security, Security Training Support, Security Access and Badging, and Industrial Security. Figure 1-5 reflects the organization of the Security Manager.

Chan es to the Mana er, Securit There are no changes of responsibilities to this existing position. This position previously reported 1-3

directly to the Plant Services Manager (Refer to the current FSAR Figures 13.1-6 and 13.1-6D and FSAR Section 13.1.2.2.4.2).

1.1.2.1.2.2 Mana er, Emer enc Plannin and Services The Manager, Emergency Planning and Services is responsible to the Director, Site Services to implement programs in the areas of fire protection and emergency preparedness. Reporting to the position are the Fire Protection Supervisor and the Emergency Planning Supervisor. Figure 1-6 reflects the organization of the Emergency Planning Manager.

Chan es to the Emer enc Plannin and Services De artment The functions of this department are unchanged except the Fire Protection Section has been added. The Fire Protection Section previously reported to the Plant Services Manager under the Plant Manager (Refer to current FSAR Figure 13.1-6D and FSAR Section 13.1.2.2.4.1). The Fire Protection Section's responsibilities have not changed. The Emergency Planning Section previously reported to the Assistant Vice President-Nuclear Production (Refer to current FSAR Figures 13.1.3A and 13.1.3I and FSAR Section 13.1.1.2.2.1'1).

1.1.2.1.2.2.1 Fire Protection The Fire Protection Supervisor reports onsite to the Manager, Emergency Planning and Services and is responsible for establishing and supervising the Fire Protection program at the Plant. The Fire Protection program is discussed in FSAR Section 9.5.1.5.1.

Chan es to the Fire Protection Section The responsibilities of this section have not changed. (Refer to the current FSAR Section 13.1.2.2.4.1). The Fire Protection section previously reported to the Plant Services Manager.

(Refer to the current FSAR Figure 13.1-6D and FSAR Section 13.1.2.2.4.1.

1.1.2.1.2.2.2 Emer enc Plannin The Emergency Planning Supervisors are responsible for the development and implementation of the PVNGS Emergency Plan. Figure 1-6 reflects the organization of the Emergency Planning and Services Manager.

1.1.2.1.2.3 Mana er, Trainin The Manager, Nuclear Training is responsible to the Director, Site Services for the preparation, coordination and conduct of PVNGS training. The Licensed Operator Training, General Training, and Training Support Supervisors report to t'e Training Manager. Figure 1-7 reflects the organisation of the Training Manager.

Chan es to the Trainin De artment None. This department previously reported to the Assistant Vice President-Nuclear Production (Refer to the current FSAR Figure 13.1.3A and Section 13.1.1.2.2.1.3).

1.1.2.1.2.4 Mana er Material Control The Manager, Material Control is responsible onsite to the Director, Site Services for Inventory Control, Material Control and Purchasing and Contracts.

Chan es to the Material Control De artment This is a new position title combining the existing related functions of Materials and Purchasing and Contracts which previously existed in different departments. Material Control and Inventory Control previously existed onsite under the Administrative Services Manager who previously reported to the Assistant Vice President-Nuclear Production (Refer to current FSAR Figure 13.1-3A and FSAR Section 13.1.1.2.2.1.2).

Purchasing and Contracts previously existed under the Director, Project Services who previously reported to t'e Executive Vice President, ANPP (Refer to the current FSAR Figure 13.1-28 and FSAR Section 13.1.1.2.1.1).

Having the two sections which purchase and control plant material in the same department will enhance coordination and parts availability for the plant.

1.1.2.1.2.5 Mana er, Administrative Services The Manager, Administrative Services is responsible onsite to the Director, Site Services for office services and site transportation services for PVNGS.

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4 Chan es to the Administrative Services De artment This is an existing position by name. It previously reported to the Assistant Vice President-Nuclear Production. Previous responsibilities for Inventory Control and Material Control were deleted from this position's responsibililty. The reporting point has been changed from reporting to the Assistant Vice President, to a Director, so that senior management attention is not drawn away from plant operation.

1.1.2.1.3 Director, En ineerin and Construction The Director, Engineering and Construction is responsible offsite to the Executive Vice President, ANPP to provide Engineering, Construction, Records Management, Cost and Scheduling, Nuclear Fuels Management and Participant Owner Services. The Director, Engineering and Construction is assisted in the performance of his duties by several departments reporting directly to him. Figure 1-8 reflects the organization of the Director, Engineering and Construction.

Chan es to the En ineerin and Construction Grou s This is previous a new position title, but it is similar to the Director, Technical Services shown on the existing FSAR Figure 13.1-3D and FSAR Section 13.1.1.2.2.2 except as follows: The Nuclear Licensing Department (current FSAR Figure 13.1-3J) no longer reports to this position. The Participant Services Department (current FSAR 13.1-2B) previously reporting to the Director, Project Services, now reports to this Group.

A new Cost and Scheduling Group, developed from existing positions previously reporting to the Director, Project Services (current FSAR Figures 13.1-20 and Section 13.1.1.2.1.1), now reports to this group. The Nuclear Fuel Management, Construction Department and Records Department functions remain unchanged.

1.1.2.1.3.1 Mana er, En ineerin The Manager, Engineering is responsible to the Director, Engineering and Construction to provide qualified di,scipline engineering capability to perform design functions, prepare specifications, coordinate vendor/contractor service activities, and prepare test specifications and engineering validation criteria for major improvements, modifications and additions to Plant facilities.

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The sections within the Engineering Department technical support for PVNGS are Electrical that'rovide Engineering, Instrumentation and Controls Engineering, Chemical/Mechanical Engineering, Civil/Structural Engineering, Reliability Analysis, and Methods/

Training. The Discipline Supervisors report to the Engineering Manager, Figure 1-9 reflects the organization of the Nuclear Engineering Manager.

Chan es to the Nuclear En ineerin Department The responsibilities of the Nuclear Engineering Department include most of the same responsibilities existing previously. The offsite Corporate Health Physicist function has been transferred onsite under the Radiation Protection and Chemistry Manager. The Production Manager position is eliminated and functions transferred to the new engineering manager.

(Refer to the current FSAR Figure 13.1-3E and FSAR Section 13.1.1.2.2 for previous responsibilities).

1.1.2.1.3.2 Mana er, Partici ant Services The Manager, Participant Services is responsible to the Director, Engineering and Construction to provide information services and coordination for plant interfaces with the PVNGS owner companies and their committees on matters of contracts, budgetary plans, cash forecasts and rate case information coordination.

Chan es to the Partici ant Services De artment The responsibilities of this department remain the same. Previously this group reported to the Director, Project Services (Refer to the current FSAR Figure 13.1-2B and FSAR Section 13.1.1.2.1.1).

1.1.2.1.3.3 Mana er, Records Mana ement The Nuclear Records Management Department provides onsite and offsite support for PVNGS, Construction, Engineering, and outside consultants and contractors in the areas of documentation, drawing control and associated reference informational material by the means of hardcopy, micromedia and/or computer assisted retrieval.

The Nuclear Records Management Manager directs the technical and administrative activities within the Nuclear Records Management Department. The Nuclear Records Management Department is comprised of five sections:

Drawing and Document Control offsite Drawing and Document Control onsite Nuclear Indexing Micrographics (on and offsite)

As-Built Records Management In addition, the Nuclear Records Management supports the sections within and coordinates the turnover activities of documentation to the department from outside departments, organizations and contractors.

The section supervisors report to the Nuclear Records Management Manager. Figure 1-10 reflects, the organization of the Nuclear Records Department.

Chan es to the Nuclear Records De artment The responsibilities and reporting point of this department remains the same. (Refer to the current FSAR Section 13.1.1.2.4 and FSAR Figure 13.1-3G).

1.1.2.1.3.4 Mana er Cost and Schedule The Manager, Cost and Schedule is r sponsible to the Director, Engineering and Construction to provide cost estimating, scheduling and monitoring services for engineering and modification projects.

Chan es to the Cost and Schedule De artment This is a new department created from personnel from other existing areas of both Cost and Scheduling, particularly those under the existing Director, Project Servies (Refer to the current FSAR Figure 13.1-2B and FSAR Section 13.1.1.2.1.1.1).

1.1.2.1.3.5 Mana er, Construction The Manager, Construction is responsible to the Director, Engineering and Construction to provide for site related Construction Activities to manage the construction, modification and/or installation of major structures, systems and equipment that represent physical changes or additions to PVNGS facilities.

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Chan es to the Construction De artment None. (Refer to the current FSAR Figure 13.1-3F and FSAR Section 13.1.1.2.3).

1.1.2.1.3.6 Mana er, Nuclear Fuels The Manager, Nuclear Fuels reports to the Director, Engineering and Construction.

Nuclear Fuels Department is responsible for fuels management and core analysis for PVNGS.

The Manager, Nuclear Fuels provides nuclear fuel design, contracting and utilization expertise, nuclear fuel core and plant transient and accident analysis and alternative core operating strategies. Figure 1-11 reflects the organization of the Nuclear Fuels Department.

Chan es to the Nuclear Fuels De artment None. (Refer to the current FSAR Figure 13.1-3H and FSAR Section 13.1.1.2.5).

1.1.2.1.4 Director, Nuclear Safet and Licensin The Director, Nuclear Safety and Licensing is responsible to the Executive Vice President, ANPP to coordinate license document changes, responses to NRC requests and to serve as the plant interface with NRC, This position directs management activities of the offsite Nuclear Safety Group, the onsite Independent Safety Engineering Group, the onsite Compliance Department (to provide for compliance monitoring of PVNGS regulatory commitments),

offsite Technical Data section (to disseminate technical and performance data from ANPP to others) and the offsite Licensing Department.

Figure 1-12 reflects the organization of the Nuclear Safety and Licensing Group. Also, the onsite Compliance Department is matrixed to the Director, Standards and Technical Support.

Chan es to the Nuclear Safet and Licensin Grou This is a new group resulting from combining together the existing Licensing, Nuclear Safety Group (NSG)',

Independent 'afety Engineering Group (ISEG), and Compliance Departments and addition of a new Technical Data section. The NSG and ISEG are divided under two managers rather than one to provide further attention to their activities. Figure 1-12 reflects the organization 1-9

of the Nuclear Safety and Licensing Group. (Refer to the current FSAR Figure 13.1-3K, FSAR Section 13.1.1.2.9, FSAR Figure 13.1-3J and FSAR Section 13.1.1.2.7 and FSAR Figure 13.1-6 and FSAR 13.1.2.2.5).

1.1.2.1.5 Director, Cor orate A/QC The Director, Corporate QA/QC reports to the Executive Vice President, ANPP to provide implementation of the QA and QC activities. Refer to the current FSAR Chapter 17, Section 17.2 "Quality Assurance during the Operations Phase" for the responsibilities and interface of the Quality Assurance Group. FSAR Figure 17.2-1 reflects the previous organization of the Quality Assurance Group.

Chan es to the Qualit Assurance Grou The nuclear functions and responsibilities of this group remain the same. The Assistant Director QA/QC position has been eliminated.

1.1.3 Qualifications of Head uarters Staff The qualifications of headquqarters staff technical personnel is discussed in the current FSAR Section 13.1.1.3 and remains in effect.

The Quality Systems and Engineering Manager, the Procurement Quality Manager, the Quality Audits and Monitoring Manager and Quality Control Manager shall meet the minimum qualification requirements of Section 4.4.5 of ANSI/ANS 3.1-1978.

Resumes for key headquarters staff personnel providing technical support are provided in Attachment 2.

The Director, Engineering and Construction position corresponds most closely to that identified as "engineer in charge" by ANSI/ANS 3.1-1978, and the minimum requirements for this position are those of Paragraph 4.6.1 of ANSI/ANS 3.1-1978.

1.2 Onsite 0 eratin Or anization The Vice President-Nuclear Production, has direct line responsibility for the operation of the PVNGS Units. The PVNGS Plant Managers have responsibility for the safe, reliable and efficient operation of the Units. Refer to Figure 1-3.

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1.2.1 Onsite Station Or anization The PVNGS onsite station organization is divided into three groups which report to the Vice President-Nuclear Production. Each group is divided into subordinate departments. Each PVNGS unit is divided into the same departments. One other onsite support group (Director, Site Services) was discussed previously.

Plant Group PVNGS Units 1, Operations 2 and 3 Maintenance

-- Control Work Radiation Protection Chemistry Nuclear Production and Support Group WRF Outage Management Central Maintenance Radwaste Support Central Radiation Protection Standards and Technical Support Group Radiation Protection and Chemistry Engineering Evaluations Operations Computer Systems Plant Standards and Control Compliance (Matrix)

The Vice President-Nuclear Production is responsible for the overall station operations. The Plant Managers are responsible for operations of their assigned unit.

The Unit organization is shown on Figure 1-13. Sufficient manpower is normally available to provide six operating shift crews.

Overall staffing consists of current APS plant and support staff.

1.2.2 Station Personnel Res onsibilities and Authorities 1.2.2.1 Vice President, Nuclear Production The Vice President-Nuclear Production reports to the Executive Vice President, ANPP and has direct responsibility for the safe, reliable, and efficient operation of PVNGS.

The Vice President-Nuclear Production is totally and solely committed to the management of APS'uclear facilities. This position is charged with the responsibility to ensure that APS

'uclear facilities are operated and maintained in accordance with regulatory requirements and with the highest level of safety in accordance with APS policy. Accordingly, this position is charged with the authority necessary to ensure that the appropriate resources are available to support the nuclear 1-11

unit operational activities. The fact that ancillary support is available to the Vice President-Nuclear Production shall not diminish the authority and responsibility of this position nor shall it prevent this position from obtaining any and all resources, both within and outside APS, necessary to achieve these goals. In the absence of the Vice President-Nuclear Production, the responsibilities for the day-to-day operation, maintenance, and performance of the station are assigned to the Assistant Vice President-Nuclear Production. In the event of unexpected contingencies of a temporary nature, when neither the Vice President-Nuclear Production nor the Assistant Vice President-Nuclear Production is available at the station, one of the Plant Managers will be assigned this responsibility.

The Plant Managers 're responsible to the Production for the safe, reliable, and Vice'resident-Nuclear efficient operation of their assigned Unit. This position directs the Operations Manager, Maintenance Manager, Work Control Manager, Radiation Protection Manager, and the Chemistry Manager of the assigned unit. (Refer to Figure 1-13 for the Unit Specific Organization).

1.2.2.1.1.1 0 erations Mana er The Operations Manager is responsible to the Plant Manager for the conduct of the unit operations in a safe and efficient manner in accordance with technical specifications and station procedures. This position supervises the activities of the unit's operating personnel. At the time of initial core. loading or appointment to the position, the Operations Managers shall hold a Senior Reactor Operator license in accordance with ANSI/ANS 3.1-1978 Section 4.2.2. This position is similar to the previous Superintendent of Operations shown on current FSAR Figure 13.1-6B and discussed in FSAR Section 13.1.2.2.3.1. This position will serve as the Plant Manager's principle alternate per ANSI/ANS 3.1-1978 Section (4.2.1).

1.2.2.1.1.1.1 Shift Su ervisors The Shift Supervisors are responsible to the Operations Manager for the safe, reliable, and efficient operation of the unit during the assigned shift. The shift supervisor directs the activities of the operators on each shift. The Shift Supervisor will possess a Senior Reactor Operator License. This position does not change due to this reorganization.

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1.2.2.1.1.1.2 Assistant Shift Su ervisor The Assistant Shift Supervisor provides a backup to the Shift Supervisor and supervises shift personnel in conduct of operations as assigned. The Assistant Shift Supervisor will possess a Senior Reactor Operator License. This position does not change due to this reorganization. (Refer to the current FSAR Section 13.1.2.2.1.3).

1.2.2.1.1.1.3 Nuclear 0 erator III The Nuclear Operator III manipulates the reactor plant controls. The Nuclear Operator possess a Reactor Operator License.

III will This position does not change due to this reorganization. (Refer to the current FSAR Section 13.1.2.2.3.1.4).

1.2.2.1.1.1.4 Nuclear 0 erator I and II The Nuclear Operator I and II are responsible, under the direction of the Shift Supervisor and Assistant Shift Supervisor, for operating auxiliary systems and assisting in the refueling of the plant as directed. These positions do not change due to this reorganization. (Refer to the current FSAR Section 13.1.2.2.3.1.5).

1.2.2.1.1.2 0 erations Su ort Su ervisor The Operations Support Supervisor acts as assistant to the Operations Manager and is responsible for the overall preparation, coordination, and conduct of the radioactive waste management programs and demineralizer operations including approval of radioactive waste disposal activities. This position will provide a backup to the Operations Manager and hold an SRO license on PVNGS. This is a new position.

1.2.2.1.1.3 Maintenance Mana er The Maintenance Manager is responsible to the Plant Manager for the performance of surveillance testing, preventative maintenance, and minor repairs on plant systems and equipment housekeeping and decontamination.

This is a new position, the current maintenance organization is discussed in FSAR Section 13.1.2.2.3.2 and shown on FSAR Figure 13.1-6C.

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0 Reporting to the Maintenance Manager are the Mechanical, Electrical, and Instrumentation and Control supervisors and personnel.

1.2.2.1.1.4 Work Control Mana er The Work Control Manager is responsible for providing a planning and scheduling function which efficiently utilizes the resources and the capabilities of the operation, maintenance, radiation protection, chemistry and other work groups assigned to this unit. This position is responsible for the technical content of work control packages used in the performance of maintenance tasks.

1.2.2.1.1.5 Radiation Protection Mana er The Radiation Protection Manager is responsible to the Plant Manager for coordination, and conduct of the radiological protection programs in the unit.

1.2.2.1.1.6 Chemistr Mana er The Chemistry Manager is responsible to the Plant Manager for the coordination, and conduct of chemistry, and radiochemistry programs. This is a new unit position developed from the existing unit Chemistry Supervisor positions. These unit Chemistry Supervisor positions were previously matrixed to each unit under direction of the Manager, Chemical Service reporting to the Manager, Radiation Protection and Chemistry reporting to the Manager, Technical Support.

(Refer to the current FSAR Figure 13.1-6A).

1.2.2.2 Assistant Vice President-Nuclear Production Su ort The Assistant Vice President-Nuclear Production Support is responsible for the onsite management of the Water Reclamation Facility, Central Outage Management, Central Maintenance, Radwaste Support, and Central Radiation Protection. (Refer to Figure 1-14). This position is assigned the responsibilities of the Vice President-Nuclear Production in the Vice President-Nuclear Productions absence.

1.2.2.2.1 Water Reclamation Facilit (WRF) Mana er The WRF Manager is responsible for the maintenance and operation of the WRF, as well as the incoming pipeline.

This position coordinates these activities with the Unit Operations Manager. This is an existing position shown on the current FSAR Figure 13.1-2 (i.e., Superintendent Water Reclamation).

e 1-14

0 0

1.2.2.2.2 Outa e Mana ement Mana er The Outage Management Manager is responsible to provide an integrated outage schedule for both planned and unplanned outages and an integrated schedule for modifications to ensure proper work controls for the units. This is an existing function at PVNGS.

1.2.2.2.3 Central Maintenance Mana er The Central, Maintenance Manager is responsible to provide maintenance support'nd assistance to the Units.

Reporting to the Central Maintenance Manager are the Mechanical Support, Electrical Support, Instrumentation and Control Support and the Station Services sections.

The Station Services organization is responsible for providing support services such as site building and grounds maintenance.

1.2.2.2.4 Radwaste Su ort Mana er The Radwaste Support Manager is responsible to provide support of the power block radwaste activities. This position provides radwaste activities that lend themselves to centralization (e.g., data review and interpretation, laundering contaminated clothing, and radioactive materials shipping and receiving). This is an existing function at PVNGS.

1.2.2.2.5 Central Radiation Protection Mana er The Central Radiation Protection Manager is responsible to provide support of the radiation protection activities.

This position is to provide support to plant radiation protection activities and conduct common radiation protection functions that lend themselves to centralization (e.g., dosimetry, ALARA reviews, and radiation protection instrumentation calibration and repair). This is a new position.

1.2.2.3 Director, Standards and Technical Su ort The Director, Standards and Technical Support is responsible to the Vice President-Nuclear Production for the onsite technical support required to ensure proper functioning of the nuclear plant. This position directs the Plant Standards and Control Manager, Engineering Evaluations Manager, Radiation Protection and Chemistry Manager, and the Operations Computer Systems Manager in the performance of their duties. The Compliance Department which provides compliance monitoring under the Director, Nuclear Safety and Licensing, is matrixed to the Director, Standards and Technical Support. (Refer to Figure 1-15). This is a new senior management position.

1-15

1.2.2.3.1 En ineerin Evaluation Mana er The Engineering Evaluations Manager is responsible to the Director, Standards and Technical Support for onsite engineering and technical work required for proper operation of the Units. He directs the supervisors of the onsite engineering sections in the performance of their duties. This position is similar in function to the existing Operations Engineering Manager discussed in the current FSAR Section 13.1.2.2.2.1 and shown on FSAR Figure 13.1-6A.

1.2.2.3.1.1 Reactor En ineerin Su ervisor The Reactor Engineering Supervisor is responsible for core monitoring and in-core fuel management programs.

This position coordinates with onsite operating personnel and with offsite support organizations as necessary in performing these functions. No changes are being made to this position. This is a previous position discussed in the current FSAR Section 13.1.2.2.2.1.1 and shown on Figure 13.1-6A under the present Manager, Operations Engineering.

1.2.2.3.1.2 Test En ineerin Su ervisor The Test Engineering Supervisor is responsible to the Engineering Evaluations Manager for onsite engineering testing required by the Technical Specifications including ILRT, LLRT, and ASME Section XI and the inservice inspection program. Personnel from the previous Operations Engineering organization have performed these functions.

1.2.2.3.1.3 Shift Technical Advisor (STA) Su ervisor The STA Supervisor is responsible to the Engineering Evaluations Manager for providing Shift Technical Advisors. However, the STA's will be matrixed to the Plant Managers and will receive their day to day direction from the Plant Manager. No changes are being made to this function. (This position reported to the Manager of Operations Engineering (FSAR Figure 13.1-6A and FSAR Section 13.1.2.2.2.1.4)).

1.2.2.3.1.4 S stem En ineerin Su ervisor The System Engineering Supervisor is responsible to provide engineering expertise in the operation and maintenance of all major plant systems including monitoring and trending of system and component performance, and review of system performance during 1-16

P 0

transients or trips. The System Engineering Supervisor is also responsible to develop and/or review proposed modifications and provide onsite, liaison with the Engineering and Construction group to insure such proposed modifications are needed and proposed designs satisfy operating needs.

1.2.2.3.1.4.1 Su ervisor of Station Statistics The Supervisor of Station Statistics is responsible to maintain station generating and performance statistics to satisfy NRC, ACC and INPO statistical requirements including production of required reports.

1.2.2.3.2 0 erations Com uter S stems Mana er The Operations Computer Systems Manager is responsible to the Director, Standards and Technical Support for coordinating onsite computer activities, including hardware and software. No changes are being made to this position. (This position reported to the onsite Technical Support Manager. Refer to the current FSAR Section 13.1.2.2.2.1.3 and FSAR Figure 13.1-6A (i.e.,

Superintendent Operations Computer)).

1.2.2.3.3 Radiation Protection and Chemistr Mana er The Radiation Protection and Chemistry Manager is responsible to the Director, Standards and Technical Support for the site-wide preparation, coordination of station radiological protection, chemistry, and radiochemistry programs. This includes developing an operating philosophy, procedures and procedural standardization for the site Radiation Protection and Chemistry programs including maintaining occupational radiation exposures as low as is reasonably achievable.

His position corresponds to "Radiation Protection Manager" as discussed in Regulatory Guides 1.8 and 8.8, however, exception is taken to Regulatory Guide 8.8 positions C.l.b.3.(g), (h), (i) and (j) since these activities are performed by other positions. This function is somewhat similar to that of the previous Radiation Protection and Chemistry Manager under the previous Director, Technical Support. (Refer to the current FSAR Figure 13.1-6A and FSAR Section 13.1.2.2.2.2).

1.2.2.3.4 Plant Standards and Control Mana er The Plant Standards and Control Manager is responsible for developing operations and maintenance standards and ensuring that the operating procedures and maintenance procedures used in the three Units are identical and to 1-17

ensure that they are applied uniformly. This is a new management position developed to ensure consistency of operation and maintenance, by providing standard procedures and to provide sharing of lessons learned among the units and central groups.

1.3 Qualifications of Nuclear Plant Personnel 1.3.1 Qualification Re uirements The recommendations of Regulatory Guide 1.8, Personnel Selection and Training, are used as the basis for establishing minimum qualifications for nuclear power plant personnel.

The minimum requirements for station personnel are keyed to ANSI/ANS 3.1-1978 as follows:

1-18

POSITION ANSI/ANS 3.1 POSITION (PARAGRAPH NO. )

Plant Hanager Plant Manager (4.2.,1)

Operations Manager Operations Mgr. (4.2.2)

Plant Mgr. Principal Alternate (4.2.1)

Operations Support Supervisor Supervisor Requiring NRC License (4.3.1)

Plant Operations Mgr. Principle Alternate (4.2.2)

Shift Supervi,sors Supervisor Requiring NRC License (4.3.1)

Assistant Shift Supervisors Supervisor Requiring NRC License (4.3.1)

Nuclear Operator III Operators (Licensed) (4.5.1)

Nuclear Operators I II

& Operator (Not Licensed)

Unit Maintenance Manager Maintenance Manager (4.2.3)

Unit I & C Supervisor I & C (4.4.2)

Unit I & C Technician Technician (4.5.2)

Unit Electrical Supervisor Supervisor Not Requiring NRC License (4.3.2)

Electricians Maintenance Personnel (4.5.3)

Unit Mechanical Supervisor Supervisor Not Requiring NRC License (4.3.2)

Mechanics Maintenance Personnel (4.5.3)

Unit Work Control Manager Mgr. Not Requiring NRC License (4.3.2)

Unit Radiation Protection Mgr. Radiation Protection (Note a)

Unit Chemistry Manager Chemistry & Radiochemistry (4.4.3)

Assist. V.P.-Nuclear Production Technical Manager (4.2.4)

Support Outage Management Manager Mgr. Not Requiring NRC License (4.3.2)

I& C Support Supervisor I&C (4.4.2)

Electrical Support Supervisor Supervisor Not Requiring NRC License (4.3.2)

Central Maintenance Manager Maintenance Hgr. (4.2.3)

Mechanical Support Supervisor Supervisor Not Requiring NRC License (4.3.2)

Station Services Supervisor Supervisor Not Requiring NRC License (4.3.2)

Radwaste Support Manager Mgr. Not Requiring NRC License (4.3.2)

Central Rad. Prot. Mgr. Radiation Protection (Note a)

Director, Standards & Tech. Technical Manager (4.2.4)

Support Plant Standards & Control Mgr. Mgr. Not Requiring NRC License (4.3.2)

Engineering Evaluations Mgr. Technical Manager (4.2.4)

Operations Computer Systems Mgr. Mgr. Not Requiring NRC License (4.3.2)

Radiation Protection & Chemistry Radiation Protection (4.4.4)

Mgr.

Reactor Engineering Supervisor Reactor Engineer (4.4.1)

Engineering & Construction Director Engineer in Charge (4.2.4, 4.6.1)

Engineering Manager Technical Manager (4.2.4)

Site Services Director Mgr. Not Requiring NRC License (4.3.2)

Security Manager Mgr. Not Requiring NRC License (4.3.2)

Training Manager Mgr. Not Requiring NRC License (4.3.2)

Administrative Services Manager Hgr. Not Requiring NRC License (4.3.2)

Nuclear Safety & Licensing Director Mgr. Not Requiring NRC License (4.3.2)

ISEG Personnel Note b Quality Assurance Director Quality Assurance (4.4.5)

Quality Assurance Managers Quality Assurance (4.4.5) as defined in Section 1.1.3 of this description 1-19

I '

NOTES:

a. The Central Radiation Protection Manager, and the Unit Radiation Protection Managers, shall have a minimum of five years experience in radiation protection at a nuclear facility. A minimum of two years of this five years experience should be related technical training but exception is taken to the degree requirement in ANSI/ANS 3.1 Section 4.4.4. A maximum of four years of this five years experience may be fulfilled by related technical or academic training. Two years of this five years experience shall be at a professional level.

b. The ISEG shall be composed of at least five, dedicated, full time engineers located onsite. Each shall have a Bachelor's Degree in Engineering or related science and at least two years professional level experience in his field.

1-20

0 1.3.2 Qualifications of Plant Personnel Resumes of the appointees to key plant managerial positions are provided in Attachment 2. Shift Supervisor level information has been previously provided to NRC as part of operator licensing and is not included here.

1.4 Review and Audit Operating phase activities that affect nuclear safety are reviewed and audited. The review and audit program is implemented prior to initial fuel loading and ensures proper review and evaluation of proposed changes, tests, experiments, and unplanned events. The program complies with the requirements of Paragraph 50.59 of 10CFR50 relating to proposed changes, tests, and experiments and is conducted following the recommendations of Regulatory Guide 1.33, Quality Assurance Program Requirements (Operation), as discussed in Section 1.8. The Executive Vice President-ANPP has overall responsibility for safe operation of PVNGS.

The Plant Managers have onsite responsibility for safe operation of PVNGS. They are kept abreast of each unit's operating conditions by their department managers in the areas of operations, maintenance, work control, radiation protection and chemistry who are knowledgeable and experienced in their areas of job responsibility. These department managers perform timely and continuing monitoring of operating and maintenance activities as part of their normal job duties.

In addition, a formal review and audit program is carried out for changes to systems, procedures, tests, and experiments and for the after-the-fact review and evaluation of unplanned events that affect nuclear safety. This program is implemented through staff review, Plant Review Board, Independent Safety Engineering Group (ISEG), and an offsite Nuclear Safety Group (NSG).

1.4.1 Onsite Review Onsite review is performed by the Plant Review Board (PRB) which has the responsibility to review plant activities and administrative controls as related to nuclear safety. A detailed description of the PRB is provided in the PVNGS Technical Specifications as part of the description of administrative controls.

The PRB is composed of those individuals specified in the PVNGS Technical Specifications. Collectively, they possess the type and degree of expertise required to properly review proposed changes to systems, procedures, tests, experiments, and unplanned events that effect nuclear safety. The PRB meets at least once per calendar month and maintains written minutes of each meeting, which are reviewed by the Nuclear Safety Group.

1-21

'l i

Changes to the PRB representatives are being made as a result of this proposed PVNGS reorganization (Refer to the marked up Technical Specification changes).

1.4.2 Inde endent Review 1.4.2.1 Nuclear Safet Grou (NSG)

The NSG is an independent, off-site organization which performs all-encompassing reviews to ensure the safe operation of PVNGS in accordance with License requirements. The NSG Manager reports to and advises the Director, Nuclear Safety and Licensing, who, in turn, reports to the Executive Vice President-ANPP.

The Nuclear Safety Group is a staff organization composed of at least four Nuclear Safety engineers and a Manager. Their primary function is to provide competent technical review of plant operations to ensure nuclear safety. The NSG also maintains cognizance of QA audits and may utilize technical specialists from other APS organizations and outside consultants with expertise in special areas, as determined necessary by the NSG Manager.

h

, The details of the function, composition, review and audit requirements, authority, records and meeting frequency of NSG are described in the PVNGS Technical Specification, Section 6.5.3.

No changes are being made to the Nuclear Safety Group's function.

1.4.2.2 Inde endent Safet En ineerin Grou (ISEG)

The review function of the ISEG is provided in the current FSAR Section 18.I.B.1.2 and in PVNGS Technical Specification Section 6.2.3. No changes are being made to this group's function.

The audit program is as described in FSAR Section 13.4.3. No changes are being made to this program.

1-22

CHAIRMAN,BOARD OF DIRECTORS PUBLIC AFFAIRS CORPORATE COUNSEL MANAGER CHIEF EXECUTIVE OFFICER FEDERAL AFFAIRS PRESIDENT CHIEF OPERATING OFFICER CORPORATE FINANCE PLANNING 8 CONTROL ARIZONANUCLEAR EXECUTIVE VICE POWER PROJECT EXECUTIVE VICE CUSTOMER 8 EMPLOYEE PRESIDENT AND ELECTRIC PRESIDENT ADMINISTRATIVE RELATIONS ENGINEERING CHIEF FINANCIAL OPERATIONS SERVICES VICE PRESIDENT VICE PRESIDENT OFFICER VICE PRESIDENT VICE PRESIDENT VICE PRESIDENT VICE PRESIDENT NUCLEAR CORPORATE

& CONTROLLER PRODUCTION RESOURCES RELATIONS AND PLANNING MARKETING VICE PRESIDENT VICE PRESIDENT CONSTRUCTION CUSTOMER VICE PRESIDENT SERVICES RATES STATE REGION VICE PRESIDENT VICE PRESIDENT MARKETINGAND ENERGY MANAGEMENT VICE PRESIDENT FINANCIALAND TAX SERVICES TREASURER AND ASSISTANT SEC.

APS MASTER ORGANIZATION Figure l-l

j ~

PRESIDENT 8 CHIEF OPERATING OFFICER EXECUTIVE VICE PRESIDENT VICE PRESIDENT NUCLEAR PRODUCTION PLANT DIRECTOR DIRECTOR DIRECTOR DIRECTOR MANAGER ENGINEERING 8 NUCLEAR SAFETY CORPORATE SITE SERVICES UNIT 1 CONSTRUCTION 8 LICENSING QA/QC PLANT MANAGER UNIT 2 PLANT MANAGER UNIT3 ASSISTANT VICE PRESIDENT NUCLEAR PRODUCTION SUPPORT APS NUCLEAR DIRECTOR STANDARDS 8 EXECUTIVE TECHNICAL VICE PRESIDENT ANPP SUPPORT Figure 1-2

VICE PRESIDENT NUCLEAR PRODUCTION ASSISTANT DIRECTOR PLANT MANAGER PLANTMANAGER PLANTMANAGER VICE PRESIDENT STANDARDS 6 UNIT 1 UNIT2 UNIT3 NUCLEAR PROD. TECH. SUPPORT SUPPORT OPERATIONS WATER REC. PLANT STAN-OPERATIONS OPERATIONS MANAGER FACILITY DARDS & CONT.

MANAGER MANAGER MANAGER MANAGER OUTAGE ENGINEERING MAINTENANCE MAINTENANCE MAINTENANCE MANAGEMENT EVALUATIONS MANAGER MANAGER MANAGER MANAGER MANAGER WORK WORK WORK CENTRAL OPERATIONS CONTROL CONTROL CONTROL MAINTENANCE COMPUTER SYS MANAGER MANAGER MANAGER MANAGER MANAGER RADIATION RADIATION RADIATION RADIATION RADWASTE PROTECTION 8 PROTECTION PROTECTION PROTECTION SUPPORT CHEMISTRY MANAGER MANAGER MANAGER MANAGER MANAGER CENTRAL CHEMISTRY CHEMISTRY CHEMISTRY RADIATION COMPLIANCE MANAGER MANAGER MANAGER PROTECTION MANAGER APS NUCLEAR PRODUCTION Figure 1-3

~ E DIRECTOR SITE SERVICES EMERGENCY MATERIAL ADMINISTRATIVE SECURITY TRAINING PLANNING & CONTROL SERVICES MANAGER MANAGER SVS. MANAGER MANAGER MANAGER APS NUCLEAR SITE SERVICES Figure 1-4

MANAGER OPERATIONS SECURITY SUPERVISOR SUPERVISOR SUPERVISOR SUPERVISOR SECURITY SECURITY SECURITY, INDUSTRIAL OPERATIONS TRAINING ACCESS & SECURITY SUPPORT BADGING CAPTAIN SHIFT SECURITY SERGEANT SHIFT SECURITY APS NUCLEAR SECURITY Figure 1-5

MANAGER EMERGENCY PIANNING R SERVICES SUPERVISOR SUPERVISOR SUPERVISOR FIRE ONSITE OFFSITE PROTECTION EMERGENCY EMERGENCY PLANNING PLANNING DAY SHIFT CAPTAIN FIRE TEAM 'EMERGENCY EMERGENCY PLAN PLAN COORDINATORS COORDINATORS SHIFT CAPTAIN FIRE TEAM A SHIFT CAPTAIN FIRE TEAM 8 SHIFT CAPTAIN FIRE TEAM C SHIFTCAPTAIN FIRE TEAM D SHIFT CAPTAIN FIRE TEAM E APS NUCLEAR EMERGENCY PLANNING 5 SERVICES Figure 1-6

MANAGER NUCLEAR TRAINING SUPERVISOR SUPERVISOR SUPERVISOR GENERAL LICENSED TRAINING TRAINING OPERATOR SUPPORT TRAINING LEAD LEAD INSTRUCTORS INSTRUCTORS APS NUCLEAR TRAINING Figure 1-7

DIRECTOR ENGINEERING 8.

CONSTRUCTION PARTICIPANT RECORDS COST AND ENGINEERING CONSTRUCTION NUCLEAR FUEL SERVICES MANAGEMENT SCHEDULE MANAGER MANAGER MANAGEMENT MANAGER MANAGER MANAGER MANAGER APS NUCLEAR ENGINEERING AND CONSTRUCTION Figure 1-8

a.

ENGINEERING MANAGER METHODS/

TRAINING STAFF MECHANICAL/ CIVIL/ RELIABILITY CHEMICAL ELECTRICAL IBC SUPERVISOR STRUCTURAL ANALYSIS SUPERVISOR SUPERVISOR SUPERVISOR SUPERVISOR APS NUCLEAR ENGINEERING Figure 1-9

MANAGER NUCLEAR RECORDS MANAGEMENT ADMINISTRATOR ANALYST SUPERVISOR SUPERVISOR SUPERVISOR SUPERVISOR SUPERVISOR EQUIP MENT 8 NUCLEAR AS-BUILT DRAWING AND NUCI EAR NUCLEAR DRAWING AND TRAINING RECORDS RECORDS DOCUMENT MICROGRAPHICS MANAGEMENT DOCUMENT MANAGEMENT CONTROL COMPUTER CONTROL DEER VALLEY SYSTEM PVNGS DEER VALLEY PVNGS COORDINATOR COORDINATOR LEAD LEAD NUCLEAR AS-BUILT MICROGRAPHICS MICROGRAPHIC RECORDS RECORDS SPECIALIST SPECIALIST MANAGEMENT COORDINATOR NUCLEAR RECORDS COORDINATOR NUCLEAR RECORDS EQUIPMENT TECHNICIAN ANALYST NUCLEAR RECORDS APS NUCLEAR RECORDS MANAGEMENT Figure 1-10

MANAGER NUCLEAR FUELS SUPERVISOR SUPERVISOR SUPERVISOR SUPERVISOR FUEL CYCLE NUCLEAR SAFETY TECHNICAL SERVICES ANALYSIS ANALYSIS PROJECTS APS NUCLEAR FUELS Figure l-l1

DIRECTOR NUCLEAR SAFETY LICENSING NUCLEAR ISEG NUCLEAR TECHNICAL COMPLIANCE SAFETY GROUP MANAGER LICENSING INFORMATION MANAGER MANAGER MANAGER SUPERVISOR APS NUCLEAR SAFETY AND LICENSING Figure 1-12

f 0

UNITX PLANT MANAGER OPERATIONS MAINTENANCE WORK RADIATION MANAGER CONTROL PROTECTION CHEMISTRY MANAGER MANAGER MANAGER MANAGER SHIFT SHIFT SHIFT SHIFT SHIFT SHIFT OPERATIONS SUPERVISOR (A) SUPERVISOR (B) SUPERVISOR (C) SUPERVISOR (D) SUPERVISOR (E) SUPERVISOR (F) SUPPORT (SRO) (SRO) (SRO) (SRO) (SRO) (SRO) SUPERVISOR SRO ASST. SHIFT ASST. SHIFT ASST. SHIFT ASST. SHIFT ASST. SHIFT ASST. SHIFT SUPERVISOR SUPERVISOR SUPERVISOR SUPERVISOR SUPERVISOR SUPERVISOR (SRO) (SRO) (SRO) (SRO) (SRO) (SRO)

NUCLEAR NUCLEAR NUCLEAR NUCLEAR NUCLEAR NUCLEAR OPERATOR III OPERATOR III OPERATOR III OPERATOR III OPERATOR III OPERATOR III (RO) (RO) RO (RO) (RO) (RO)

NUCLEAR NUCLEAR NUCLEAR NUCLEAR NUCLEAR NUCLEAR OPERATOR OPERATOR OPERATOR OPERATOR OPERATOR OPERATOR I & II I& II I & II I & II l8 II l8 II APS NUCLEAR UNIT SPECIFIC ORGANIZATION Figure 1-13

ASSISTANT VICE PRESIDENT NUCLEAR PRODUCTION 8 SUPPORT WRF OUTAGE CENTRAL RAD WASTE CENTRAL MANAGER MANAGEMENT MAINTENANCE SUPPORT RADIATION MANAGER MANAGER MANAGER PROTECTION MANAGER ELECTRICAL MECHANICAL STATION ISC SUPPORT SUPPORT SUPPORT SERVICES APS NUCLEAR PRODUC7ION SUPPORT Figure 1-14

DIRECTOR STANDARDS 8 TECHNICAL SUPPORT RADIATION OPERATIONS PLANT PROTECTION 8 ENGINEERING STANDARDS 5 COMPUTER CHEMISTRY EVALUATIONS CONTROL SYSTEMS MANAGER MANAGER MANAGER MANAGER RADIATION PLANT SHIFT OPERATIONS PROTECTION 5 STANDARDS 8 TECHNICAL COMPUTER CHEMISTRY CONTROL ADVISORS PERSONNEL PERSONNEL PERSONNEL ENGINEERING PERSONNEL MANAGER COMPLIANCE REACTOR ENGINEERING SYSTEM ENGINEERS MATRIX APS NUCLEAR STANDARDS @

TECHNICAL SUPPORT Figure 1-15

I

~ )

0

~ r~ ~ l CQNTRQLLED BY USER AOHINISTRATIV CONTROLS

6. 1 RESPONSI BILITY 6.1.1 Th~~~Plant Hanager shall be responsible for overall unit operation and shall delegate in writing the succession to this responsibility during his absence.

6. 1.2 The Shift Supervisor, or during his absence from the Control Room, a designated individual per T'able 6.2-1, shall be responsible for the Control Room command function. A management directive to this effect, signed by the Vice President-Nuclear Production shall be reissued .o all station personnel on an annual basis.

6. 2 ORGAN:ZATION OFF SITE 6.2.1 The offsite organization for unit management and technical support shall be as shown in Figure 6.2-1.

UNIT STAFF

6. 2.2. 1 The unit organization shall be as shown in. Figure 6.2-2 and:

Each on-duty shift shall be composed of at least the minimum shift crew composition shown in Table 6.2-1.

At least one licensed Reactor Operatol shall be in the Control Room when fuel is in the reactor. In addition, while the reactor is in HOG= 1, 2, 3, or 4, at least one licensed Senior Reactor Operator shall be in the Control Room.

C. A radiation protection technician" shall be onsite when fuel is in the reac or.

All COR ALTERATIONS shall be observed and directly supervised by either a licensed Senior Reactor Operator or Senior Reac or Operator Limited to Fuel Handling who has no other concurrent responsibilities during this operation.

A site Fire Team of at least five members shall be maintained onsite at all times". The Fire Team shall not include the Shift Supervisor, the STA, nor the 3 other members of the minimum shift crew necessary for safe shu down of the unit and any personnel required for other essential func ions during a fire emergency.

6. 2. 2. 2 The unit staff working hours shall be as follows:

Administrative procedures shall be develt ped and implemented to limit the working hours of uni t staff who perform safety-related functions; e.g., Senior Reactor Operators, Reactor Opera.ors, radiation protection technicians, auxiliary operators, and key maintenance personnel.

"The radiation protection technician and Fire Team composition may be less than the minimum requirements for a period of time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, in order to accommodate unexpected absence, provided immediate ac ion is taken to fill the required positions.

PALO VERDc UNIT 1 6-1

%Lese 8,ua'tplece. u sb< PRKSIOEttT

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EXECUTIVE V.P.

V.P, HUCLEAR PRODUCT)OH ASST. MGR.

PVH OIR. OIR.

. V.P. NUCLEAR HUCLEAR SAFETY PLAHT MAt GER 7 EC lltllCAL SERVICES CORPORATE OA O PROOUC T IOH ISEG/tiSG 0

Z MGR. MGR. MGR MGR. ASST. MGR.

EMERGEtlCY PLAtl OPERATIOHS TRhtl TIOtl HUCLEAR EHGItlEERIHG CORPORATE OA U

NGR.

t MGRo UJ MGR. NGRa AOMIttI5TRATIVE OUALITY SYSTEMS/ C NAIHTEHAHCE HUCLEAR COtlSTRUCTIOH SERVICES EHGIHEERltlG rn 33

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MGR, MGR. MGR.

TRAIHltlG 0 AGE HUCLEAR FUELS PROCUREMEHT OUALITY-lAGEMEHT MGR.

ttRF MGR.

MGR. RECOROS OUALITY AUOITS/

SUPERIHTEtlOEHT PLhtlT SERVICES MOtllTORlttG

~ MGR. MGR. I.ICEtlSItlG MGR.

TECllHICAL SUPPORT OUALITY COHTROL

+ LOCATEO OHSITE F IGURE 6. 2-1 NhlthGER CONPLlhtlCE . OFFS ITE ORGntIIZATIOH

PRESIDENT 8 Cl-IIEF OPERATING OFFICER

'I.OCATEO ONSITE EXECUTIVE VICE PRESIDENT VICE PAESIDENT DIRECTOR DIRECTOR DIRECTOR NUCLEAR ENGINEERING & DIRECTOR NUCLEAR SAFETY QUALITY PRODUCTION CONS ITIUCTION SITE SERVICES 8 LICENSING ASSURANCE MANAGER MANAGER MANAGER MANAGER fNGINEERING SECUAITY NUCLEAR SAFETY SYS.'UALITY ENGINEERING MANAGER MANAGER MANAGER CONSTRUCTION MANAGER TRAINING PROCUREMENl ISEG QUALIITY MANAGER MANAGER MANAGER COST & EMEAGENCY MANAGER QUALITY/AUDITS SCI IEDULE PLAN 8 LICENSING MONITORING SERVICES MANAGER "

MANAGER NUCLEAR SUPERVISOR MANAGER TfCI.INICAL QUALITY FUEL MATERIAL CONTROL DATA CONTROL MANAGEA PARTICIPANT MANAGER MANAGER SERVICES ADMIN. COMPLIANCE SEA VICES OFFSITE ORGANIZATION Figure 6.2- l

1

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~

'l PYHGS

'LAtlT

'MANAGER OUTAGE CIRIICAL OP ERATIOHS NAIIITBIAHCE P T SERVICES NhtthGENEHT S PORT NAIIAGER NAtlAGER NAHAGER NAHAGER NA GER MANAGER MAIIAGER MAIIAGER SUPERIHTEHOEIIT SUPERIHTEH T CONPL IhflCE OPER AT IOHS OPS EIIGlttEERltt0 UNIT I IIC NAHI lAIICE SECURITY SUPERVISOR SUPERltlTEHOEHT SUPERItlTEHDEHT SUPERVISOR STA UNIT 2 NCC FIRE PROTECTIOH NAIIAGER S RIHTEtlOEHT SUPERIHTBIOEHT RAO. PROT. 1 CIIEN. lllT 3 ELEC. NAIHTEHAtlCE SUPERIHTEIIOE1 SUPERVISOR SUPERIHTBIOEHT OPS CONPI R OPERATIOllS SUPPOR STATIOH SERVICES SYS N SUPERIltTEtlOBIT NEClfhtllCAL Nhltt T Et!At ICE F IGURE 6. 2-2 OHS17E OnGnnllRT10H Co

VICE PRESIDENT NUCLCAR PRODUCTION ASSISTANT DIACCTOR PLANT MANAGER PLANT MANAGER PLANTMANAGER VICE PRESIDENT STANDARDS &

UNIT 1 UNIT2 UNIT3 NUCL'EAR PROD. TECII. SUPPORT SUPPORT OPERATIONS OPERATIONS WATER AEC. PLANT STAN. SUPCAVISOA OPERATIONS MANAGER MANAGER FACILITY OAADS & CONT. OPERATIONS MANAGER MANAGER . MANAGER STtlOS.

SUPERVISOR MAINTENANCE OUTAGE ENGINEERING MAINTENANCE MAINTENANCE MECI I. IAAlkIT.

h4NAGER MANAGEMENT EVALUATIONS MANAGER MANAGER STNQS.

MANAGFR MANAGER SUP EA VISOR WORK WORK WORK CENTRAL OPCRATIONS ELEC. h1AINT.

CONTROL CONTROL CONTROL MAINTENANCC COMPUTER SYS STNOS.

MANAGER MANAGER MANAGER MANAGER MANAGER SUPCAVISOA RADIATION RADIATION RADIATION RADIATION RADWASTE l&C STt<OS.

PROTECTION PROTECTION &

PROTECTION PROTECTION SUPPORT MANAGER MANAGER CklEMISTAY MANAGER MANAGER MANAGER CENTRAL Ck IEhllSTRY Cl IEMISTRY CHEMISTRY RADIATION COMPLIANCE MANAGER MANAGER MANAGER PROTECTION MANAGER 0NSITE ORGANIZATION Figure 6.2-'2 "LOCATED OFFSJTE

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6. 2-1 7(ic~ P~S~

MIHIMUM SHIFT CREW COMPOSITIOH POSITIOH HUMBER OF IHDIVIDUALS REQUIRED TO FILL POSITION MODE 1, 2, 3, OR 4 MODE 5 OR 6 SS 1 1 SRO 1 Hone RO 2 1 AO 2 1 STA 1 Hone SS Shift Supervisor with a Senior Reactor Operators License SRO - Individual with a Senior Reactor Operators License RO Individual with a Reactor Operators License AO Huclear Operator I or II STA - Shift Technical Advi.sor Except for the Shift Supervisor, the Shift Crew Composition may be one less than the minimum requi rements of Table 6. 2-1 for a period of time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in order to accommodate unexpected absence of on-duty shif crew members provided immediate action is taken to restore the Shift Crew Composition to,within the minimum requirements of Table 6.2-1. This provision does not permit any shift crew position to be unmanned upon shift change due to an oncoming shift crewman being late or absent.

During any absence of the Shift Supervisor from the Control Room while the unit is in MODE 1, 2, 3, or 4, an individual (other than the Shift Technical Advisor) with a valid Senior Operator license shall be designated to assume the Control Room command function. During any absence of the Shift Supervisor from the Control Room while the unit is in MODE 5 or 6, an individual with a valid Senior Operator or .Operator. license shall be designated to assume the Control Room command function.

PALO VERDE " UHIT 1 6-5

CQMTRGELED BV USEP AOt)IHISTRATIVE CONTROLS

6. 2. 3 IHOEPEHDFHT SAFETY ENGIHEERIHG GROUP (ISEG)

FUNCTION 6.2.3.1 The ISEG shall iunction to examine plant operating characteristics, HRC issuances, industry advisories, Licensee Event Reports, and other sources oi plant design and ooerating experience information, including plants oi sinilar design, which may indicate areas for improving plant saiety.

COt,1POS IT IOH 6.2.3.2 The IS=G shall oe comoosed oi at least five, dedicated, full-time engineers located on site. Each shall have a Bachelor's Degree in engineering or related science and at least two years professional level experience in his field.

RESPONSIBIL TIES 6.2.3.3 The ISEG shall be responsible for maintaining surveillance of plant aciivities to provide independent verifica ion~ that these activities are performed correctly to reduce human errors as much as practical, and to detect, potential nuclear safety hazards.

AUTHORITY Q>reckon,Auc4n.r Mdg G<d 6.2.3.4 equipment

Hanager, The ISFG and the~~~~r, 61ag~~ p Nuclear Saiety shall make detaile recommendations for revised procedures, modifications, maintenance ctiviiies, operations aciiviiies or other means oi improving plant safety to the Group (HSG).

~4- Plant RECORDS 6.2.3.5 Records oi aciivities performed by ihe ISEG shall be prepared, main-tained, and forwarded each calendar monih to the

'icec+o,a Nuc.(ear Sofcky Gad L<<<~ '~J 6.2.4 SHIFT TECHNICAL ADVISOR 6.2.4.1 The Shiit Technical Advisor (STA) shall provide advisory technical suoport to the Shift Supervisor in the areas of thermal hydraulics, reactor engineering, and plant analysis wiih reaard io the safe operation oi the unit.

The STA shall be onsite and shall be available in the control room wi ihin 10 minutes whenever one or more uniis are in t10DE ', 2, 3, or 4.

6. 3 UNIT STAFF OUALIFICATIONS 6.3.1 Each member of the unit staff shall meet or exceed the minimum qualifica-tions of AHS 3.1-1978 and Regulatory Guide 1.8, September 197', except for the Radiation Protection and Chemistry t1anager who shall meet or exceed the qualifi-cations of Regulatory Guide 1.8, September 1975, and the Shift Technic'.1 Advisor who shall have a bachelor's degree or equivalent in a scientific or engineering discip)ine with specific iraining in plant design and plant operating character-istics, including ransients and accidents.

"Hot respons ib1 e for s ign-o f i func iion.

PALO VERDE - UNIT 1 6 6

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COMTRGLI.t-:D BV USER ADMINISTRATIVE CONTROLS 6.4 TRAINING

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1 A training program for the unit staff shall be maintained under the direction of the or his designer and shall meet or exceed the requirements and recommendations of Section 5.0 i AHS 3. 1-1978 and Appendix A of 10 CFR Part'55 and the supplemental requirement specified in Sections A and C of Enclosure 1 of the March 28, 1980 NRC letter to,all licensees, and shall include familiarization with relevant industry operational experience.

6. 5 REVIEW AHD AUDIT

6. 5. 1 PLANT REVIEM BOARD PRB)

FUNCTION I

6.5.1.1 The Plant Review Board shall function to advise th ~RGW Plant Hanag on all matters related to nuclear safety.

COMPOS ITIOH 6.5. 1.2 The PRB shall be composed of the following personnel:

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Hember: Manager Operati ons-b4eager- W<~~<~~

Member:

Member: /Pl'.cfiaaiag ~

Hai ntenance 44eager >~~~+<<~~ ~/<I ~'~ ~

Hember:

Member: ~/dcddccoc- pgydkfag4eeAeg-Manager- 4+oudorgs 5"i'E'Eve'o~

Hember:

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Member: STA Supervisor Member. d J Member: Radiation Protection and Chemistry Manager Hember: Quality Systems/Engineering Manager i-U<<c'Asia'e~- /VJc(pop. Pvckcy4o&

, The4 shall designate the Chairman and Vice-Chairmen in writing. The Chairman and Vice-Chairmen may be from outside the members listed above provided that they meet ANSI Standard 3.1, 1978.

ALTERHATES 6.5. 1.3 All alternate members shall be appointed in writing by the PRB Chairmar to serve on a temporary basis; however, no more than two alternates shall participate as vo ing memoers in PRB activities at any one tine.

MEETING FREQUENCY 6.5. 1.4 The PRB shall meet at least once per calendar month and as convened by the PRB Chairman, Vice-Chairmen, or his designated alternate.

PALO VERDE - UNIT 1 6-7 AMENDMENT HO. 8

CGNTRGILLED BY USER AOMIHI STRATI VE COHTRQLS OUORUM 6.5.1.5 The quorum of the PRB necessary for the performance of the PRB responsibility and authority provisions of these Technical Specifications shall consist of the Chairman, Vice-Chairmen, or five members including alternates. his designated alternate and RESPONSIBILITIES 6.5.1.6 The PRB shall be responsible for:

'a ~ Review of all administrative control procedures and changes.

b. Review of all proposed changes to Appendix "A" Technical Specifications.

C. Investigation of all violations of the Technical Specifications including the preparation and forwarding of reports tion and recommendations to prevent recurrence to thecovering evalua-Huclear Safety Group (HSG).

d. Review of REPORTABLE EVEHTS r equiring 24-hour written notification to the Commission.

e. Review of unit operations to detect potential nuclear safety hazards.

Performance of special "reviews, investigations or analyses and reports thereon as requested by th

~(c.e. Pres(~'pic A- Alael~n< HdCEvc Pld Review and documentation or judgment concerning prolonged operation

+

g in bypass, channel trip, and/or .repair of defective protection channels of process variables placed ih bypass since the last PRB meeting.

AUTHORITY ..

6.5.1.7 The PRB shall:

'a ~ Render determinations in writing with regard to whether or not each item considered under Specification 6.5. 1.6c. above constitutes an unreviewed safety question.

b. Provide written noti~f ca<ion within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to the Vice President-Huclear Production, MRW='~t Manager and HSG of disagreement between the PRB and the(AREBB'lant Manager; however, the4%R~~

Plant Manager shall have responsibility for resolution of~sue disagreements pursuant to Specification 6. l. 1 above.

PALO VEROE - UNIT 1 6-8

P CONTPOLLED B~ USER ADMINISTRATIVE CONTROLS RECORDS 6.5. 1.8 The PRB shall maintain written minutes of each PR8 meeting that, at a minimum, document the results of all PRB activities performed under the responsi-bility and authorit visions of these Technical Specifications. Copies shall be provided to the ..' Plant t1anager Vand HSG.

6 5 2 TECilHICAL REVIEM AND CONTROL

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6.5.2. 1 The .. . Ashall assure that each procedure and program required by Specification 6.8 anK other proceed res uhich 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.

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6.5.2.2 plant operat)ons staff shall be approved by th t~~

hase I - IV tes s described in the FSAR that are performed bv the Technical Supoor-Test results shall be approved by the

.+ Q)fecAag, S+bNcfdcc(S ctkfd!  %+4'coL S4+M7 dR ghe Qgr,ueegIug. 8l/l/va 5'rc.I 6.5.2.3 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 rrom the same organization as the individual/group which designed the modi iication. Proposed t structures, systems and components snail modifications to nuclear safety-related be ap roved prior to implementation by the ~~

Techni cg Suppor< as previously desi gnated by hep,. ~

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6-5.2.4 individuals responsible for reviews perfo ed sn accordance with 6.5.2.1, 6 5.2.2, and 6.5.2.3 shall be members of the station upervisory staff, previously designated by the '

o perform such reviews. Each such revi ew shall include a determination of whether r not additional, cross-disciplinary, review is necessary. If deemed necessary, uch review shall be perrormed by the appropriate designated review personnel. Vice>rcsic4~j-)4~cleat Prcctdcfionl 6.5.2.5 Proposed tests and experiments which affect station nuclear safety and are not'addressed in ihe FSAR or Technical Specifications shall be reviewed b y the ~ I ~ ~ a ) iI

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6.5.2.6 The station security program and implementin procedures shall be reviewed. Recommended changes shall be approved by the and transmitted to the Vice President-Nuclear Production and to the HSG.,

Q iree bGr, G. l.e 5 erv hem 6.5.2.7 The s! >tion emergency plan and implementing rocedures shall be reviewed. Recommended changes shall be approved by the 9'rcd ~c.k.(oa 6.5.2.8 Th .

" .... shall assure the performance of a review by a qualified individual/organization oi every unplanned onsite release oi radio-active material to the environs including the preparation and forwarding of reports covering the evaluation, recommendations and disposition of the cor-rec ive acr.ion t.o prevent. recurrence>

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PALO VERDE - UNIT 1 6-9

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ADMIHI STRATI VE CONTROLS g~~o'araS aw TE"HNICAL REVIEW AH0 CONTROL (Continued) qualified individual/organization of changes to the PROCESS CONTROL PROGRAt1, OFFSITE DOSE CALCULATION ltANUAL, radwaste treatment systems, and the Pre"planned Al ternate Samol ing Program.

6. 5. 2. 10 Reports documenting each of the activities performed under Specifica-tions 6.5.2. 1 through 6.5.2.9 above shall be maintained. Copies shall be provided to th . . ~ and the Nuclear Safety Group.

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6.5.3 NUCLEAR SAFETY GROUP (HSG)

FUNCTION 6.5: 3. 1 The HSG shall function to provide independent review and shall be responsible for the audit of designated activi ties 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 practices COllPOSITIOH cialists. The Physical Sciences.

~~ four staff spe-shall have a Bachelor's Degree in Engineering or the He will also have a minimum of :0 vears experience in the power field with at least 3 of those years in the nuclear field. The HSG i>> ial exoerience.

Each staff specialist will have at least one of the following requirements:

a. Eight years experience in one of the designated areas in Specifica-tion 6.5.3. 1. One of these 8 years will be at Palo Verde Nuclear Genera ing Station.

b.* Bachelor's Degree in Engineering or a related science and 3 years of prof essi onal experi ence.

CONSULTANTS I p g(+$ g 6.5.3.3 Consultants shall be utilized as determined by the NSG<~~~ to provide expert advice to the HSG.

RP! I cM 6.5.3.4 The NSG shall revie~:

a. The safety evaluations program and i's implemen"a ion for (1) chances to procedures, equioment, sys-ems or facilities within the power block, and (2) tests or experimen-s comoleted under the provision of 10 CFR 50. 59, to verify that such ac=ions did no cons itute an unreviewed safety question;

- 6-10 PALO VERDE UNIT I pp~~ ~i f'i ~~~ ~ y pt ye Ir ~ ~

Twas

CQMTRGLL.ED BY USER ADt1IHISTRATIVE CONTROLS R":~!.EW (Continued

b. Proposed changes to procedures, equipment, systems or facilities within the power block which involve an unreviewed safety question as defined in 10 CFR 50. 59; C. Proposed tests or experimen s which involve an unreviewed safety question as defined in 10 CFR 50.59; Proposed changes to Technical Specifications or this Operating License; Viola ions of codes, regulations, orders, Technical Specifications, license requirements, or of internal procedures or instructions having nuclear safety significance; Significant operating abnormalities or deviations from normal and expected performance of unit equipmen+ that affec nuclear safety;

g. All REPORTABLE EVENTS requiring 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> written notification; All recognized indications of an unanticipated deficiency in some aspect of design or operation of structures, systems, or components that could affect nuclear safety; and Repor+s and meeting minutes of the PRB.

AUD.iS 6.5.3.5 Audits oi unit ac ivities shall be performed under the cogrizance of the HSG. These audits shall encomoass:

a. The conformance of unit operation to provisions contained within the Technical Specifications and applicable license conditions at least once per 12 months.

The performance, training, and qualifications of he uni s aff a least once per ~2 months.

The results of actions aken to correct deficiencies occurring in unit equipment, structures, systems, or method of opera'on that affect nuclear safety at leas once per 6 months.

The performance of activities required by the Opera ional equality Assurance Prooram to meet the criteria of Appendix B, 10 CFR Part 50, at least once per 24 months.

Any other area of unit operation considered appropriate by the HSG or the Vice President-Nuclear Production.

The fire protection prog.amma ic controls including the implementing procedures at least once per 24 months by qualified licensee gA personnel.

PALO VERDE

CGNTRQLLED BY USI=P-A01il NI STRATI VE CONTROLS AUDITS (Continued}

g. The fire protection equipment and program implementation at least, once per 12 months utilizing ei ther a qualified offsite licensee fire protection enaineer or an outside independent fire protection consultant. An outside independent fire protection consultant shall be used at least every third year.

h. The radiological environmental monitoring proaram and the results thereof at least once per 12 months.

i. The OFFSITE DOSE CALCULATION HANUAL and implementing procedures at least once per 24 months.

j. The PROC SS CONTROL PROGRAti and implementing procedures for processing and packaging of radioactive wastes at least once per 24 mon hs.

k. The performance of activities required by the Operations guali ty Assurance Criteria manual to meet the provisions of Regulatory Guide 1.21, Revision 1, June 1974 and Regulatory Guide 4. 1, Revision 1, April 1975 at least once per 12 months.

l. The Pre-planned Alternate Sampling Program and implementing procedures at least once per 24 months.

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'n AUTHORITY 6.5.3.6 The HSG shall report to and advisee the . . . .

those areas of responsibi li .y specified f in Specifications 5.5.3.4 and 5.5.3.5.

RECOROS b<ec'Sac >

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6.S.3.7 Records of HSG activities shall be prepared and maintained. Report of reviews and audits shall be prepared monthly for the who will distribute it to he Vice President-Huclear Proauction~~~ Plant Hanager, anti to the management positions responsible for the areas audited..

6. 6 REPORTABLE EVEHT ACTIOH 6.6.1 The following actions shall be taken for REPORTABLE -VENTS:

'i

a. The Commission shall be notified and a report submitted pursuant to the requirements of Section 50.73 to 10 CFR Part 50, and

b. Each REPORTABLE EVEHT requiring 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> written notification shall be reviewed bv the PPB, and he results of this review shall be lAaeo~er su ml ted to the Huclear Safety Group and the Vice President"Nuclear Produc ion.

PALO VERDE - UNI T 1 6-'2

CGÃ7RGLLEG B'f USER ADMINISTRATIVE CONTROLS 6.7 SAFETY LIMIT VIOLATION Safety Limit is

'l 6.7.1 The following actions shall be taken in the event a violated:

a. The NRC Operations Center shall be notified by telephone as soon's possible and cases within 1 hour. The Vice President-Nuclear Group shall be notified within 24 hours.

b. A Safety Limit Violation Report shall be prepared. The report shall be reviewed by the PRB. This report shall describe (1) applicable circumstances preceding the violation, (2) effects of the violation upon facility components, systems, or structures, and (3) corrective action taken to prevent recurrence.

c. The Safety Limit Violation Report shall be submitted to the 5%huaqe~g ommi ss s on, of the NSG and the Vice President-Nuclear Production within 14 days of the violation.

d. Critical operation of the unit shall not be resumed until authorized by the Commi ss i on.

6.8 PROCEDURES AND PROGRAMS 6.8. 1 Mritten procedures shall be established, implemented, and maintained covering the activities referenced below:

a. The applicable procedures recommended in Appendix A of Regulatory Guide 1.33, Revision 2, February 1978, and those required for implementing the requirements of NUREG-0?37.

b. Refueling operations.

c. Surveillance and test activi ties of safety-related equipment.

d. Security Plan implementation.

e. Emergency Plan implementation.

f. Fire Protection Program implementation.

g. Modification of Core Protection Calculator (CPC) Addressable Constants.

NOTE: Modification to the CPC Addressable Constants based on information obtained through the Plant Computer - CPC data link shall not be made without prior approval of tt e PRB.

h. PROCESS CONTROL PROGRAM implementation.

i. OFFSITE DOSE CALCULATION MANUAL implementation.

j. equality Assurance Program for effluent and environmental monitoring, using the guidance in Regulatory Guide 1. 21, Revision 1, June 1974 and Regulatory Guide 4. 1, Revision 1, April 1975.

k. Pre-planned Alternate Sampling Program implementation.

1. Secondary water chemistry program implementation.

PALO VERDE - UNIT 1 6-13 gg~gYRQLILEV BY VSER

CONTRQLLED BY USER ADMI HI STRATI VE CONTROLS HOT=: The licensee shall perform a secondary water chemistry monitoring and control procram that is in con ormance with the program discussed in Sec" tion 10.3.4. 1 of the CESSAR FSAR or another HRC approved program.

m. Post"Accident Sampling System implementation."

n. Settlement Monitoring Program implementation.

NOT=: The licensee shall maintain a settlement monitoring program throuchout the life of the plant in accordance with the program presented in Table 2. 5-i 8 of the PVNGS FSAR or another HRC approved program.

o. CEA Symmetry Test Proaram implementation HOT"=: The licensee shall perform a CEA symmetry test program in conformance with the prog, am discussed in Section 4. 2. 2 of the PVNGS SER dated Hovember ll, 1981.

p. Fuel Assemoly Surveillance Program Implementation NOTE: The licensee shall perform a fuel assembly surveillance procram in con-formance with the prooram discussed in Section 4.2.4 of the PVNGS SER da ed Hovember ll, 1981.

P/'Ps ID8&6 81V'CI8<R &c'GPUCkd ~

6.8.2 Each program or procedure oi Specification 6.8.1, and changes thereto, procedures shall be approved by who is at supervisory level or above.

the,...

shall be reviewed as soeciried in oecification 6.5 and aporoved prior o implementation. Programs, adminis "ative control procedures and implementing or desicna ec al erna-e Programs and procedures oi Specirica-tion 6.8. 1 shall be reviewed periodically as set for;h in acmir.istra-.ive procedures.

6.8.3 Temporary chanoes to procedures of Specification 6.8. 1 above may be made provided:

The in en'f the original procedure is not altered.

The change is approved by two members of the plant supervisory s aff, at least one of whom is a Shift Supervisor or Assis an Shift Supervisor with an SRO on the affected unit.

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C. The chance is documented, reviewed in accordance with Specification .

6.5.2 and approved by the . " or cocnizant department head, as desicnated by the er, wi hin 14 days of implementation. s c&Q 8 /U'c'Qy'~ac,/zan;u 6 8 4 The following procrams shall be establi shed implemented main ained and shall be audited under the cognizance of the HSG at least once per 24 months:

a. Primary Coolan. Sources Out~ide Containment A procram to reduce leakaoe from those por ions of sys ems outside containment that could con-ain hiohly radioactive fluids during a serious rarsient or ac icent :o as low as practical levels. The systems include the recirculation portion of the high pressure sarety injec:ion system, the shutdown cooling por.ion of the low pressure safety injec:ion system, the po'st-accident sampling subsystem of the "Hot recui red until prior to exceeding 5~' o RAT=D T,'-:ER,"NL POMER.

PALO VERDE " VHIT 1 6-14

ADMIH1STRAT1YE COllTROLS UNiT STA.-";" (Continued)

b. Adequate shift coveraoe 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 overtime to be used, or during extended periods of shutdown for re-fueling, major maintenance, or major plant modifications, on a tem-porary basis, the following guidelines shall be followed (this ex-cludes the STA wor! ing hours):

1) An individual should not be permitted to work more than 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> straight, excluding shift turnover time.

2) An individual should not be permitted to work more than ~6 hours in any 24-.nour period, nor more than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in any 48-hour period, nor more than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> in any 7-day period, all excluding shift turnover time.

3) A break of at least 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 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 fo1 the entire staff on a shift.

c. Any deviation from the~boge guidelines shall be authorized by the Plant Manager or'esignee who is at supervisory level or above, or higher levels of management, in accordance with establisned procedures and with documentation of the basis for granting the deviation. Controls shall be included in the procedures such that individual overtime hall be reviewed monthly by

+I i H assigned. Routine deviation from the above guide ines is not authorized.

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PALO VERDE - Ut(iT ~ 0 2

0 CQNTRGLLED BY USER ADt1INISTRATIVE CONTROLS

6. 1 RESPONSIBIL'TY 6.1. 1 The~KM-P.ant Manager shall be responsible for overal. unit operation and shall delegate in writing the succession to this responsib:lity during his absence.

6. 1.2 The Shift Supervisor, or during his absence from the Control Room, a designated individual per Table 6.2"1, shall be responsible for the Control Room command function. A management directive to this effect, signed by the Yice President-Nuclear Production shall be reissued to all station personnel on an annual basis.

.6. 2 ORGANIZATION OFFSITE 6.2.1 The offsite organization ior unit management and technical suoport shall be as shown in Figure 6.2-1.

UNIT STAFF 6.2.2.1 The unit organization sna11 be as shown in Figure 6.2-2 anc:

a. Each on-auty shift snail be composed oi at least the minimum shiit crew composition shown fn Table 6.2-1.

b. At least one licensed Reactor Operator shall be in the Comrol Room when iuel is in the reactor. In addition, while the reactor is in ttODE 1, 2, 3, or 4, at least one licensed Senior Reac=or Coerator shall be in the Control Room.

A radiation protection technician" shall be ons ite wren iuel is in the reac.or.

d. All CORE ALTERATIONS shall be observed and directly s"per.ised by either a licensed Senior Reactor Operator or Senior Reactor Operator Limited .o Fuel Handling who has no other concurrent responsibilities during this operation.

e. A site Fire Team of at least five memoers shall .be maintained onsite at all times". The Fire Team shall not include the Shift Supervisor, the STA, nor the 3 other membens of the minimum shift crew necessary for safe shutdown oi the unit and any personnel required for other essential functions during a fire emergency.

6.2.2.2 The unit staff working hours shall be as follows:

a~ Administrative procedures shall be developed and implemented to limit the working hours oi unit staff who perform safety-re1ated functions;

e. g., Senior Reactor Operator s, Reactor Operators, radiation protec-.

tion technicians, auxiliary operators, and key maintenance personne).

~The radiation protection technician and Fire Team composition may be less than th'e minimum requi rements for a period of time not to exceed 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> s, in order to accommodate unexpected absence, provided immediate action is taken to fill the required positions.

pAlo veRDp - ugE>QI ITRGLK~D BY USER

CQMTRGLLED BV USER AOMINISTRATIYE CONTROLS UNIT STAFF (Continued)

b. 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 overtime to be used, or during extended periods of shutdown for re-fueling, major maintenance, or major plant modifications, on a tem-porary basis, the following guidelines shall be followed (this ex-cludes the STA working hours):

1) An individual should not be permitted to work mor: e than 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> straight, excluding shift turnover time.

2) An individual should not be permitted to work more than 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> in any 24-hour period, nor more than 24. hours in any 48-hour period, nor more than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> in any 7-day period, all excluding shift turnover time.

3) A break of at least 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 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.

. +3~im

c. Any deviation from the above guidelines snail be authorized by the PVHSS Plant Mallager or 'esignees who are at the manager level or above, or higher levels of managemen~, in accordance with established procedures and with documentation of the "asis for granting the deviation. Controls shall be included in the procedures such that g)z<<~ ~~~~~h+s- des nee to assure that excessive hours have not been assigned. Routin deviation from the above guid lines is not authorized.

j /LJ +het 2 / 8>pG'A~~

f@4Vp~

7 ~eh CEO Atda/88o lt~dl~de/~ o~

Q/~Q ~ grp!/JAN+ l-~ ES IOE tlT lU>~

EXECUTIVE V.P.

V.P.

HUCLEAR PROOUCTIOtl

+

ASST. MGR.

PVtlGS OIR. OIR.

V.P. NUCLEAR HUCL'EAR SAFETY P A/IT MAtlAGER TECHNICAL SE ICES CORPORATE OA I ROOUCTION ISEG/HSG MGR. MGR. MGR. MGR. ASST. MGR.

EMERGEtlCY PLAN OPERATIONS . TRAHSITIOH HUCLEAR 'EtlGIHEERIHG CORPORATE OA

+

MGR. MGR.

MGR. MGR.

ADLItttISTRATIVE OUALITY SYSTEMS/

MAItlTEHAHCE tlUCLEAR CotlSTRUCTIOH SERVICES ENGltlEERltlG MGR.

MGR. MGR. MGR.

TRAINItlG OUTAGE U LEAR FUELS PROCUREMENT OUALITY.

MAHAGEMEHT MGR.

HRF GR.

MGR. RECOROS OUALITY AUOITS/

SUP ER ItlT EHOEtlT PL T SERVICES MOHITORltlG MGR. MG MGR. LICEHSIHG TECIINICAL SUPPORT OllALITY CO OL

~ LOCATEO ONSITE FIGURE 6.2-1 MAtlAGER COMPLIANCE OFFSITE ORGANIZATION

5/eA a Ere/.~ ESIOKtlT

~it/( A/>~ .

~Jr/z~

(

m A7 EXECUTIVE V.P.

CD m

V.P.

NUCLEAR PRODUCTION ASST. MGR.

PVHGS OIR. OIR.

V.P. ttUCL EAR HUCLEAR SAFETY P AQT MAIIAGER TECHNICAL S ICES CORPORATE OA PRODUCTION ISED/HSG O

Q MGR, EhtERGEttCY PLAH MGR.

OPERATIONS .

MGR.

TRAHSITIOH MGR.

ttUCLEAR EHGLNEERIHG ASST. MGR.

CORPORATE OA z

0

+ +

MGR. MGR.

MGR. hlGR.

AOMlttlSTRATIVE DUALITY SYSTEMS/ CI MAINTENANCE IIUCLEAR COttSTRUCTION SERVICES EHGlttEERIHG N MGR.

MGR. MGR. MGR.

TRafttlttG OUTAGE ZJ t U LEAR FUELS PROCUREMEttT QUALITY.

MAHAGEhlEHT MGR.

HRF GR.

MGR. RECORDS QUALITY AUDITS/

SUPERlltTEtlOEttT PL T SERVICES MONITORlttG MGR. MG MGR. L)CEHSlttG TECIINICAL SUPPORT QUALITY CO OL mr C)

~ LOCATED OWSITE m FIGURE 6.2-1 MANAGER COMPLlAIICE OFFSITE ORGANIZATION

PRESIDENT 8, CI IIEF OPERATING OFFICER

';OCATEO OlJSI TE EXECUTIVE VICE PRESIDENT VlCC PAESIDEtlT DIRECTOR OIAECTOR DIRECTOR NUCLEAR ENGINEERING 8 DIRECTOR NUCLEAR SAFETY QUALITY PRODUCTION CONSTRUCTION SITE SERVICES 8 LICENSING ASSURANCE MANAGER MANAGER MANAGER MANAGER ENGINEERING SECURITY NUCLEAR SYS.

'UALITY SAFETY ENGINEERING MANAGER MANAGER MANAGER MANAGER CONSlTIUCTION TRAIIIING PROCUREMENl ISEG QUALIITY MANAGER MANAGER MANAGER COST 8 EMERGENCY MANAGER QUALITY/AUDITS SCI IEDULE PLAN 8 LICENSING MONITORING SERVICES MANAGER.

MANAGER NUCLEAR SUPERVISOR MANAGER QUALITY I'UEL TECI.INICAL MATERIAL CONTROL DATA CONTROL MANAGER PAA'I'ICIPANT MANAGER MANAGER SLI'IVICES ADMIN. COMPLIANCE SEA VICES OFFSITE ORGANIZMION Figure 6.2-1

~,

a. ~~

l Pep/~cp ~sr'r( u~D I

8/pq/Q ~ PVHGS PLAIIT MAtIAGER CD OUTAGE TEClltIICAL OPERATIOtIS MAltITBIAHCE AHT SERVICES LIAHAGEIIEHT SUPPORT WAIIAGER WAHAGER MAItAGER MAHAGCR MAtIAGER LIAIIAGER MAHAGER MAHAGER SUPERIIITBIOEHT SUPERIHTEJIIIEHT COWPL IAtICE OPERATIOIIS OPS EttG)IIEERIHO UHIT I ILC M/AI HEHAHCE SECURITY O

O SUPERV)SOR SUPERIIITEtIOBIT SUPERltITEHOEHT SUPERVISOR z

STA UHIT Z MCC FIRE PROTECTIOII Xl.

O I

m U

MAtIAGER PERltITEHOBIT SUPERIHTEIIOEtIT W RAO. PROT. 4 CHELI. UHIT 3 ELEC. MAIIITEHAtICE XI SIIPERIHT5HbBIT SUPERVISOR SIIPERIHTEIIOEIIT Ol'S )OIIPIITER STATIOH SERVICE%

OPERATIOIIS SUPPORT

~SYSTEM SUPERlttTBIOEHT

&1 L[ECHAHICAL C3 WAIHTEHAHCE 0

Dl CD Vl lA C

CD FIGURE 6. 2-2 A)

OnSITE ORC~NIZnTIOu

v(CE PRESIDENT NUCLEAR PRODUCTION ASSISTANT DIRECTOR PLANT MANAGER PLANTMANAGER PLANT MANAGER VICE PRESIDENT STANDARDS tt UNIT I UNIT 2 UNIT3 NUCI. EAR PROD. TECH. SUPPORT SUPPORT OPERATIONS OPERATIONS WATER AEC. PLANT STAN. SUPP AVISOfl OPERATIONS MANAGER MANAGER FACILITY DAADS 6 CONT. OPEAATIOIIS MANAGER MANAGER MANAGER STtIOS.

SUPERVISOR MAINTENANCE OUTAGE ENGINEEAING MAINTEN ANCE MAINTENANCE MEC) I. I.IAItIT.

M<tINAGER MANAGEMENT EVALUATIONS MANAGER MANAGER STNDS.

MANAGER MANAGER SUPERVISOR WORK WORK WORK CENTRAL OPERATIONS ELEC. MhlttT.

CONTROL CONTROL CONTROL MAINTENANCE COMPUTER SYS STNOS.

MANAGER MANAGER MANAGER MANAGER MANAGER SUPEA VISOA RADIATION RADIATIOt<

RADIATION RADIATION RAOWASTE 18C STNOS.

PROTECTtON PROTECTION PROTECTION 8 PAOTECTION SUPPORT MANAGER CI IEMISTAY MAtIAGEA MANAGER MANAGER MANAGER CENTRAL CIIEMISTRY Cl-IEMISTRY CHEMISTRY RADIATION COMPLIANCE t IAt<AGEA MANAGER MANAGER PROTECTION MANAGER ON SITE<

ORGANIZATION Figurc 6.2-2 "LOCATED OFFSXTE

CGNYRGLLED BY USER TABLE 6.2-1 gg C,'o.iJ p5 TIA<5 P' MINIMUM SHIFT CREM COMPOSITION POSITION NUMBER OF INDIVIDUALS REQUIRED TO, ILI POSITION MODE 1, 2, 3, OR 4 MODE 5 OR 6 SS 1 SRO None 1

RO J AO 1 STA Hone SS - Shift Supervisor with a Senior Reactor Operators License SRO - Individual with a Senior Reactor Operators License RO - Individual with a Reactor Operators License AO - Nuclear Operator I or II STA - Shift Technical Advisor The Shift Crew Composition may be one less than the minimum requirements of Table 6.2-1 for a period of time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in order to accommodate unexpected absence of on-duty shift crew members provided immediate action is taken to restore the Shift Crew Composition to within the minimum requirements of Table 6.2"1. This. provision does not permit any shift crew position to be unmanned upon shift change due to an oncoming shift crewman being late or absent.

During any absence of the Shift Supervisor from the Control Room while the unit is in MODE 1, 2, 3, or 4, an individual with a valid Senior Operator license shall be designated to assume the Control Room command function.

During any absence of the Shift Supervisor from the Control Room while the unit is in MODE 5 or 6, an individuaT with a valid Senior Operator or Operator license shall be designated to assume the Control Room command function.

PALQ vERDE - Utgjgl LITQ[QLLPB BY USER

if CC)MYROLLED BY USiER ADMINISTRATIVE CONTROLS

6. 2. 3 IHDEPENDENT SAFETY EHGINEERIHG GROUP (ISEG)

FUNCTION 6.2.3.1 The ISEG shall function to examine plant operating characteristics, NRC issuances, industry advisories, Licensee Event Reports, and other sources of plant design and operating experience information, including plants of similar design, which may indicate areas for improving plant safety:

COMPOSITION 6.2.3.2 The ISEG shall be composed of at least five, dedicated, full-time engineers located on site. Each shall have a Bachelor's Degree in engineering or related science and at least two years professional level experience in his field.

RESPONSIBILITIES 6.2.3.3 The ISEG shall be responsible for maintaining surveillance of plant activities to provide independent verification" that these activities are performed correctly to reduce human errors as much as practical, and to detect potential nuclear safety hazards.

gfJgldad Safe/ Q,<jj grceeis uj AUTHORI f Y

~' ~

6.2.3.4 ~ The ISEG.shall make detailed recommendations for revised procedures, equipment modifications, maintenance. a tivities, operations activitaas or other means of improving plant safety to the~Managev-~uc4ea~a4e@y-, -PVHGS- Plant Manager, and th~Sv~4se~, Nuclear Safety Group (NSG).

RECORDS >I~~~g ~

6.2.3.5

6. 2. 4 d, <<d Records of activities performed d

SHIFT TECHNICAL ADVISOR by the ISEG shall be prepared, main-6.2.4.1 The Shift Technical Advisor (STA) shall provide advisory technical support to the Shift Supervisor in the areas of thermal hydraulics, reactor engineering, and plant analysis with regard to the safe operation of the unit.

The STA shall be onsite and shall be available in the control room within 10 minutes whenever one or more units are in MODE 1, 2, 3, or 4.

6. 3 'NIT STAFF UALIFICATIONS 6.3.1 Each member of the unit staff shall meet or exceed the minimum qualifica-tions of ANS 3. 1-1978 and Regulatory Guide 1.8, September 1975, except for the Radiation Protection and Chemistry Manager who shall meet or exceed the qualifi-cations of Regulatory Guide 1.8, September 1975, and the Shift Technical Advisor who shall have a bachelor's degree or equivalent in a scientific or engineering discipline with specific training in plant design and plant operating character-istics, including transients and accidents.

"Not responsible for sign-off function.

PALO YERDE - UHQQN i jQQLQQD

C G WYRG LLED 8 i( USER

'M ADMINISTRATIVE CONTROLS

6. 4 TRAINING I)<rema., SL&e SeMtc< s 6.4.1 A trainin program for the unit staff shall be maintained under the di i f tt A or his designee and shall'meet or exceed the requirements and recommendations of Section 5.0 of ANS 3. 1-1978 and Appendix A of 10 CFR Part 55 and the supplemental requirements specified in Sections A and C of Enclosure 1 of the March 28, 1980 NRC letter to all licensees, and shall include familiarization with relevant industry operational experience.

6.5 REVIEM AND AUDIT 6.5.1 PLANT REVIEW BOARD (PRB)

FUNCTION 6.5.1.1 The Plant Review Board shall function to advise thedRK2r-Plant Manager on all matters related to nuclear safety.

COMPOSITION 6.5.1.2 The PRB shalT be composed of the following personnel:

WN inJQHcci& EJDlu'a Ao& 5

~

Member: Manager Member: Operations &sacer- ~W~Aio<<~+ ~"i '"~'~'~

Member Member:

Member M b:

Member:

Member:

+p

~louie~~

hicuc god&~

Qp

.roc ti 3 .

<<~

Maintenance Haaager ~4<<a>~~> ~</<<<'~~

STA Supervisor anager f)'/otiose

~~>> 4 E'.8 ~

ss.~

~~~

f lilt.l,llit2, Member: Radiati'on Protection and Chemistry Manager Member: quality Systems/Engineering Manager i Vice /rPsicle~f - pgcfeo~ po6'ee,/~ad The%I/465-Reneger-shall designate the Chairman and Vice-Chairmen in writing. The Chairman and Vice-Chairmen may be from outside the members listed above provided that they meet ANSI Standard 3. 1, 1978.

ALTERNATES 6.5.1.3 All alternate members shall be appointed in writing by the PRB 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.

MEETING FREQUENCY 6.5. 1.4 The PRB shall meet at least once per calendar month and as convened by the PRB Chairman, Vice-Chairmen, or his designated alternate.

PAL0 YERRE - UNIJQ2IW] ~QQLLE'-,Q jf

I GNTRGLLED BY USER ADt1INISTRATI VE CONTROLS QUORUM 6~ 5.1.5 The quorum of the PRB necessary for the performance of the PRB respons)bility and authority provisions of these Technical Specifications shall consist of the Chairman, Yice-Chairmen, or his designated alternate and five members including alternates.

RESPONSIBILITIES 6.5.1.6 The PRB shall be responsible for:

a. Review of all administrative control procedures and changes.

b. Review of all proposed changes to Appendix "A" Technical Specification C. Investigation of all violations of the Technical Specifications including the preparation and forwarding of reports covering evalua-tion and recommendations to prevent recurrence to'he Nuclear Safety Group (NSG).

Review of REPORTABLE EYENTS.

e. Review of unit operations to detect potential nuclear safety hazards.

s'erformance of special reviews, .investigations or analyses and reports thereon as requested by ther Q ~Ce, reSil~et- /Uu'Cfedf/ PfC)gdQ7c'0 4

g. Review and documentation of judgment concerning prolonged opera-ion in bypass, channel trip, and/or repair of defective protection channels of process variables placed in bypass since he last PRB meeting.

AUTHORITY

6. 5.1. 7 The PRB sha 1 1:

a4 Render determinations in writing with regard to whether or not each item considered under Specification 6.5.1.6c. above constitutes an unreviewed safety question.

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 Vice president-bilityy Ruclear Product.ion --agt Manager and MRG of disagre estt between the PRB and theiRUU~8$ Plant Manager; however, the Plant Manager shall have responsibility for resolution of suc disagreements pursuant to Specification 6. l. 1 above.

RECORDS

6. 5. 1. 8 The PRB shall maintop> n written minutes oi each PRB meeting that, at, a minimum, document the results of all PRB activities performed under the responsi-and authority~rovisions of these Technical Specifications. Copies shall be provided to the(MMES Plant, Manager,iand NSG.

V<< ~ /Pe si f.h-.v'Ir'-- iVdclP~q PALO vERDE - URI1'QPITQic(] gQ Bs'f uS1 C

AOl'1IHISTRATIVE CONTROLS

6. B.2 TECHNICAL REVIEM AHO CONTR L ACTIVITIES 6.5.2.1 The ~Rpvt 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 c)anges thereto.,i-ec+p g~udargS aUa P~nlud. 5-ious f)1a~~d'e pm /

6.5.2,2 Phase I IV tests described in the FS that, are performed by the plant operations sta e approved by the Henag~ Technical Support b R~ Test 1ggl results shall g d 1 be approved by the lyd lg dby gggggdgg imager. dy& Zee(PCoC S~'.PPZ 'FrA-Up~~ ~DdnCfnd,5+dyudaygdS tliP Fug~in/eeet Eigalva F~ r$ 1awagp'W ~

6.S.2.3 Proposed modifications to unit nuclear safety-related structures, syster and components shall be designed by a qualified individual/organization. Each such modification shall be reviewed by an individual/group other than the which designed the modification, but who may be from the same 'ndividual/group .

organization as the individual/group which designed the modification. Proposea modifications to nuclear safety-related str uZes, systems and comoonents shall.

be a roved prior to implementation by th Techgicpl Support as previously designated b JI(YCtG>d BfadGfttr<85 QVg 6.5.2.5 Individuals responsible fo I) uCleaa gmCk'eke~

s Eh'ger.

'Pla t ga gr.~ p~)Ppz g~<<r.

erformed in accordance with 6.5.2.1 6.5.2.2, and 6.5.2.3 shall be members of 'the sta 1o supervisory staff, previousl

+to perform such reviews. 'ach such review

~

designated. by the shall include a determination of whether~ r not additional, cross-disciplinary, review is necessary. If deemed necessary, such review shall be performed by the appropriate designated review personnel. U'ice Qesl de~%- Alucfear 'Vrcdvc&o~

6.5.2.S Proposed tests and experiments which affect station nuclear safety and are not addressed in the FSAR or Technical Specifications shall be reviewed by the h~fteg~pera-

.~gicp Pcesid'elf.-~)pp~for lVch,(eau 'Poo'vigior4'.

Sg0c SRP.fv>cd'.

6.5,2.6 The station security program and implement1~proc)dures shall be

d. R d g' 11 b " d by d designated alternate and transmitted to the Vice President-Huclear Production .

and to the HSG. birec4er, SAe Sc.->iced 6.5. 2.? The station emergency plan and implement1ng ocedures shall be

d. R d d h g h ll b bb d by h designated alternate and transmitted to the Vice President-Nuclear Production and to the HSG.

6.5.2.8 The .. " , shall assure the performance of a review by a qualified ind1v1dual/organization of every unplanned onsite release of radio-active material to the environs including the preparation and forwarding of reports covering the evaluatio'n, recommendations and disposition of the cor-rective action to prevent recurrence.

Ql r p C, Qc) 5+5 I~C4 r C4 Q hi C~ +~< ~ lJ l r ci ~

r, !I h ~ ~

PALO VERDE - Ugggll )TRG Lying p B ( US Ill~I

CGNTRGLLED 8'f USi'R ADMINISTRATIVE CONTROLS O it'd TECHNICAL REVIEW AND CONTROL ACTIVITIES (Continued) pM 7E'.4-A~'ccdl C ~it'>~ ~

6.5.2.9 The-PVNGG-Rant-Manage shall assure the performance of a review by a qualified individual/organization of changes to the PROCESS CONTROL PROGRAM, OFFSITE DOSE CALCULATION MANUAL, radwaste treatment systems, and the Pre-planned Alternate Sampling Program.

6.5.2. 10 Reports documenting each of the activities performed under Spec'ifica-tions 6. 5. 2. 1 through 6. 5. 2. 9 'bove shall be maintained. Copies shall be provided to the ~VNGS-Ptant-Nanager- and the Nuclear Safety Group.

V(f'-c' c"szckaJ7 -AJDI~< j rdacfefidD 6.5.3 NUCLEAR SAFETY GROUP (NSG)

FUNCTION 6.5.3.1 The NSG shall function to provide independent review and shall be responsible for the audit of designated activities in the areas of:

a. nuclear power plant operations

b. nuclear engineering

c. chemistry and radiochemistry d.'etallurgy

e. instrumentation and control

f. radiological, safety

g. mechanical and elect ical engineering

h. quality assurance.E tices COMPOSITION

WguO.)e~

6.5.3.2 The NS shall consist of a<Qye~~r and at least four staff spe-cialists. Thegs~erv+se+ shall have a 'Bachelor 's Degree in Engineering or the Physical Sciences. He will also have a minimum of 10 years experience in the power field with at least 3 of those years in the nuclear field. The NSG Plgdap~~~Superv~ will have at least 2 years of supervisor/managerial experience.

Each staff specialist will have at least one of the following requirements:

a. Eight years .experience in one of the designated areas in Specifica-tion 6.5.3. 1. One of these 8 years',will be at Palo Verde Nuclear Generating Station.

b. Bachelor's Degree in Engineering or a related science and 3 years of professional experience.

CONSULTANTS'eagen 6.5.3.3 Consultants shall be utilized as determined by the NSG< or to provide expert advice to the NSG.

REVIEN 6.5.3.4 The NSG shall review:

a. The safety evaluations program and its implementation for (1) changes

. to procedures, equipment, systems or facilities within the power block, and (2) tests or experiments completed under the provision of 10 CFR 50.59, to verify that such actions did not constitute an unr eviewed safety question; PALO YERGE UNIT(+2 fgjTQCLLKIQ !g>f

CGE>37RGiLLiED BY USER C'J v AOHIHISTRATI VE CONTROLS (Continued j gl)

REVIEM

b. Proposed changes to procedures, equipment, systems or facilities within the power block which involve an unreviewed 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; Proposed changes to Technical Specifications or this Operating License;

e. Violations of codes, regulations, orders, Technical Specifications, license requirements, or of internal procedures or instructions having nuclear safety significance; Significant operating abnormalities or deviations from normal and expected performance of unit equipment that affect nuclear safety; All REPORTABLE EVENTS requiring 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> written notification; All recognized indications of an unanticipated deficiency in some aspect of design or operation of structures, systems, or components that could affect nuclear safety; and 1

Reports and meeting minutes of the PRB.

AUOITS 6.5.3.5 Audits of unit activities shall be performed under the cognizance of the HSG. 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 he unit staff at least once per 12 months.

c. The results of actions taken to correct deficiencies occurring i n 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 guality Assurance Program to meet the criteria of Appendix B, 10 CFR Part 50, at least once per 24 months.

e. Any other area of unit operation considered appropriate by the HSG or the Vice President-Huclear Production.

The fire protectio programmatic controls including the implementing procedures at least once per 24 months by qualified licensee gA personnel.

PALO VERGE - UNIT +2,jkj j Q/QLL6~&gl P (:JJ

CG~~)TRQLLIEi9 B'f USER ADMINISTRATIVE CONTROLS AUDITS (Continued)

The fire protection equipment and program implementation at least once per 12 months utilizing either a qualified offsite licensee fire protection engineer or an outside independent fire protection consultant. An outside independent fire protection consultant shall be used at least every third year.

The radiological environmental monitoring program and the results thereof at least once per 12 months.

The OFFSITE DOSE CALCULATION MANUAL and implementing procedures at least once per 24 months.

j. The PROCESS CONTROL PROGRAM and implementing procedures for orocessing and packaging of radioactive wastes at least once per 24 montns.

k. The performance of activities required by the Operations equality Assurance Criteria Manual to meet the provisions of Regulatory Guide 1.21, Revision 1, June 1974 and Regulatory Guide 4. 1, Revision 1, April 1975 at least once per 12 months.

AUTHORITY ziieeche. 4~c/em< Sa/ely Q&d biceps. u 9 6.5.3.6 The.NSG shall report to and aavise theV'Manager-of-Nuclear-SM~ on those areas ot responsibility specified in Specifications 6.5.3.4 and 6.5.3.5:

RECORDS h;cent;e.,u.a4.

Lice Ms~~~

5'kQ A 6.5.3.7 Records of NSG activities shall be prepared and maintained. Report of reviews and audits'hall be prepared monthly for th Haaeg~e4 "<cab ar Sa+ety who will distribute it to the Vice President-Nuclear Production,~~@ Plant Manager, and to the management positions'esponsible for the areas audited.

4 6.6 REPORTABLE EVENT ACTION The following actions shall be taken for REPORTABLE EVENTS:

a. The Commission shall be notified pursuant to the requirements of Section 50.72 to 10 CFR Part 50, and 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 S~mvi~or~f Nuclear Safety Group and the Vice President-Nuclear Production.

PALO YEROE - llNI Pi&2/I 'J RFML" 6. 5 8

COIN7iRQLLED BY USER AOMINI STRATI VE CONTROLS

6. 7 SAFETY LIHIT VIOLATION The following actions shall be taken in the event a Safety Limit is violated:

a. The'NRC Operations Center shall be notified by telephone as soon as possible and in all cases within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. The Vice President-Nuclear Production, FR~ Plant Hanager and or Nuclear Safety Group shall be notified within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

b. A Safety Limit Violation Report shall be prepared. The report shall be reviewed by the PRB. This report shall describe (1) applicable circumstances preceding the violation, (2) effects of .the violation upon facility components, systems, or strvctures, and (3) corrective action taken to prevent recurrence.

c. The Safet Limit Violation Reoort shall be submitted to the fAgua~ql- ommission, the of the HSG and the Vice President-Nuclear

~ Production within 30 days of the violation.

d. Critical operation of the unit shall not be resumed until authorized by the Commission.

6.8 PROCEDURES AND PROGRAHS

.r 6.8.1 Mritten procedures shall be established, implemented, and maintained covering the activities referenced below:

a. The applicable procedvres recommended in Appenaix A of Regulatory Guide 1.33, Revision 2, February 1978, arid those requirea for implementing the requirements of NUREG-0737.

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. Hodification of Core Protection Calcvlator (CPC) Addressable Constants--These procedures should include provisions to ensure that,

~

svfficient margin is maintained in CPC Type I Addressable Constants to avoid excessive operator interaction with the CPCs during reactor operation.

HOTES: (1) Hodification to the CPC Addressable Constants based on information obtained through the Plant Computer - CPC data link shall not be made without, prior approval of the PR8.

(2) Hodifications to the CPC software (including algorithm changes and changes in fuel cycle specific data) shall be performed in accordance with the most recent version of CEN-39(A)-P, "CPC Protection Algorithm Software Change Pro -e-dure," that has been determined to be applicable to the facility. Additions or deletions to CPC Addressable Constants or changes to Addressable Const nt soft-ware limit values shall not be imolemented without prior HRC approval.

"QGKYRCLLPB BY USER

6 D~~]'TRQILLED BY U52%

ADMINISTRATIVE CONTROLS PROCEDURES ANO PROGRAI'15 (Continued)

h. PROCFSS CONTROL PROGRAtl implementation.

i. OFFSITE "OSE CALCULATION MANUAL implementation.

j. equality assurance Program for effluent and environmental monitoring, using the guidance in Regulatory Guide 1.21, Revision 1, June 1974 and Regulatory Guide 4. 1, Revision 1, April 1975.

0

k. Pre-pl armed Alternate Sampl ing Program implementation.

1. Secondary water chemistry program implementation.

NOTE: The licensee shall perform a secondary water chemistry monitoring and control program that is in conformance with the program discussed in Sec-tion 10.3.4. 1 of the CESSAR FSAR or another NRC approved program.

m. Post-Acc'.dent Sampling System implementation."

n. Settlement t1onitoring Program implementation.

NOTE: The licensee shall maintain a settlement monitoring ".rogram throughout the life oi the plant in accordance with the program presentea in Table 2.5-:3 oi the PVNGS FSAR or another HRC approved program.

o. CEA Svmmetry Test Program implementation NOTE: The licensee shall perform a CEA symmetry test progr m in coniormance ~it the program'iscussed in Section 4.2.2 oi the PVNGS SER dateo November ll, 1981.

p. Fuel Assembly Su'rvei llance Program Implementation NOTE: The licensee shall perform a fuel assembly surveillance program in con-formance with the program discussed in Section 4.2.4 oi the PVNGS SER dated November 11, 198l.

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C. The change is documented, ireviewed in accordance with Speci iication 6.5.2 and approved by the>PVNG~~~arrager or cognizant department head, as designated by the~PVNGS-plant-manage~, within 14 days of.

imp 1 ementa ti on. R

~ \ ~

~Not required until prior to exceeding 5;.'r RATED THERHAL POWER.

PALO YEROE UNt'QQI QjQ) j Q Q~(

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CONTROLLED BY USER ADMI N! ST RAT I VE CONT ROL 5

6. 1 RESPONSI81LITY 6.1.1 The~M~-Plant Manager shal1 be responsible for overall unit operation and shall delegate in writing the succession to this responsibility during his absence.

6. 1.2 The Shift Supervisor, or during his absence from the Control Room, a designated individual per Table 6.2-1, shall be responsible for the Control Room command function. A management directive to this effect, signed by the Vice President-Nuclear Production shall be reissued to all station personnel on an annual basis.

6. 2 ORGANIZATION OFFSITE 6.2.1 The offsite organization for unit management and technical support shall be as shown in Figure 6.2-1.

UNIT STAFF 6.2.2.1 The unit organization shall be as shown in Figure 6.2-2 and:

Each on-duty shift shall be composed of at least the minimum shift crew composition shown in Table 6.2-1.

b. At least one licensed Reactor Operator shall'be in the Control Roam when fuel is in the reactor. In addition, while the reactor is in MODE 1, 2, 3, or 4, at least one licensed Senior Reactor Operator shall be in the Control Room.

C. A radiation protection technician" shall be onsite when fuel is in the reactor.

responsibilities All CORE ALTERATIONS shall be observed and directly supervised by either a licensed Senior Reactor Operator or Senio~ Reactor Operator .

Limited to Fuel Handling who has no other concur rent during this operation.

e. A site Fire Team of at least five members shall be maintained onsite at all times". The Fire Team shall not include the Shift Supervisor, the STA, nor the 3 other members of the minimum shift crew necessary for safe shutdown of the unit and any personnel required for other essential functions during a fire emergency.

6.2.2.2 The unit staff working hours shall be as follows:

a ~ 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, radiation protec-tion technicians, auxiliary operators, and key maintenance personnel.

"The radiation protection technician and Fire Team composition may be less than the minimum requirements for a period of time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, in order to accommodate unexpected absence, provided immediate action is taken to fill the required positions.

PALO VERDE - UNIT 3 6" 1

0 CONTROLLED 8Y USER ADMINISTRATIVE CONTROLS UNIT STAFF (Continued) 0

b. Ade q uate shi ft'overage 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 overtime to be used, or during extended periods of shutdown for re-fueling, major maintenance, or major plant modifications, on a tem-porary basis, the following guidelines shall be followed (this ex-cludes the STA working hours):

1) An individual should not be permitted to work more than 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> straight, excluding shift turnover time.

2) An individual should not be permitted to work more than 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> in any 24-hour period, nor more than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in any 48-hour

. period, nor more than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> in any 7-day period, all excluding shift turnover time.

3) A break of at least 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 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.

QQ.jp Any deviation from the above guidelines shall be authorized by the~

PONCHO" Plant Hanager o designees who are at the manager level or above, 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 overtimeyshall be reviewed monthly by the-IQNGS-Pleat

+Re. a. /t assigned. Rout' deviation from the above guidelines is not authorized.

7'3ese a.R<c~.~e

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MANAGER COMI'LlhttCE OFFSITE ORGANIZATION

PRESIDENT 8 CI.IIEF OPERATING OFFICER "I.OCATEO 0/JSI TE EXECUTIVE VICE PRESIDENT VICE PRESIDENT DIRECTOR DIRECTOR DIRECTOR NUCLEAR ENGINEERING 8, DIRECTOR NUCLEAR SAFETY QUALITY PRODUCTION CONSTRUCTION SITE SERVICES 8 LICENSING ASSURANCE MANAGER MANAGER MANAGER MANAGER ENGINEERING SECURITY NUCLEAR SYS.'UALITY SAFETY ENGINEERING MANAGER MANAGER MANAGER CONSTRUCTION MANAGER TRAINING PROCUREMENl ISEG QUAI.IITY MANAGER MANAGER COST I EMERGENCY MANAGER MANAGER QUALITY(AUDITS SCI IEDULE PI.AN & LICENSING MONITORING SFRVICES MANAGER SUI'ERVISOR MANAGER NUCLEAR MANAGER TECI.INICAL QUALITY FUEL MATEfIIAL DATA CONTROL CONTROL MANAGER PAfITICIPANT MANAGER MANAGER SERVICES ADMIN. COMPLIANCE SEflVICES OFFSITD<

ORGANIZATION Figure 6.2-1

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OPERATIOHS MAIHTBIAHCE PLANT SERVICES MAtlAGEMEHT SUPPORT MAtlAGER MANAGER MANAGER MAtlAGER MAWAGER MANAGER MANAGER MAN ICER SUPERIHTENOENT SUPERIHTENOEHT IAtlCE OPERATIONS COWPL OPS EtlGINEE ING UNIT I ~llC MAIHTEHAtlCE SECURITY O

0 SUP ER VISOR SUP ERIHTEtl0)HT SUPERIHTEHOEHT SUPERVISOR STA UNIT 2~ MCC FIRE PROTECTION SUPERIIITEHOEIIT U

MAHAGER SUPERIHTEHOENT 03 RAO. PROT. 4 CHEM. UtIIT 3 ELEC. MAINTEtlAHCE SUPERINTBlOEHT SUPERVISOR ~SUPERIHTEHOEHT OPS COMPUTER OPERATIOtls SUPPORT STATIOH SERVICES SYSTFM

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SUPERINTENOEHT'~

MECHAttlCAL MAINTENAWCE FIGURE 6.2-2 ON SITE ORGAN I ZATION

VICE PRESIDENT NUCLEAIl PRODUCTION ASSISTANT DlflLCTOR PLANT MANAGER PLANTMANAGER PLANTMANAGER VICE PRESIDENT STANDARDS 8 UNIT 1 UNIT 2 UNIT3 NUCLEAR PROD. TECH. SUPPORT SUPPORT OPERATIONS OPERATIONS WATER REC. P&HT STAN. SUPEIlVISOIl OPERATIONS MANAGER MANAGER FACILITY DAllDS 8 CONT. OPLllATIOt1S MANAGER MANAGER MANAGER STHDS.

SUPERVISOR MAINTENANCE OUTAGE ENGINEEllIHG MAINTENANCE MAINTEHANCE MECI>>. MAIHT.

MANAGER MANAGEMENT EVALUATIONS MANAGER MANAGER STHDS.

MANAGER MANAGER SUPF IlVISOB WORK WORK WORK CENTRAL OPERATIONS ELEC. MhlttT.

CONTROL CONTROL CONTROL MAINTENANCE COMPUTER SYS STHDS.

MANAGER MANAGER MANAGER MANAGER MANAGER SUPERVISOR RADIATION RADIATION RADIATION RADIATION RADWASTE l8 C STNDS.

PROTECTION PROTECTION 8 PROTECTION PROTECTION SUPPORT MANAGER Cl IEMISTRY MAtIAGER MANAGER MANAGER MANAGER CENTRAI CHEMISTRY CI.IEMISTRY CHEMISTRY RADIATION COMPLIANCE MANAGER MANAGER MANAGER PROTECTION MANAGER ONSITE ORGANIZATION Figure 6.2-2 "LOCATED OFFSITE

CONTROLLED BY USER TABLE 6. 2-1 MIHIMUM SHIFT CREW COMPOSITIOH POSITION NUMBER OF INDIVIDUALS REQUIRED TO FILL POSITION MODE 1, 2, 3, OR 4 . MODE 5 OR 6 SS 1 SRG None RO 1 AO 1 STA Hone SS - Shift Supervisor with a Senior Reactor Operators License SRO - Individual with a Senior Reactor Operators License RO - Individual with a Reactor Operators License AO - Nuclear Operator I or II STA - Shift Technical Advisor The Shift Crew Composition may be one less than the minimum requirements of Table 6.2-1 for a period of time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in order to accommodate unexpected absence of on-duty shift crew members provided. immediate action is taken to restore the Shift Crew Composition to within the minimum requirements of Table 6.2-1. This provision does not permit any shift crew position to be unmanned upon shift change due to an oncoming shift crewman being late or absent.

During any absence of the Shift Supervisor from the Control Room while the unit is in MODE 1, 2, 3, or 4, an individual with a valid Senior Operator license shall be designated to assume the Control Room command function.

During any absence of the Shift Supervisor from the Control Room while the unit is in MODE 5 or 6, an individual with a valid Senior Operator or Operator license shall be designated to assume the Control Room command function.

PALO YERDE - UNIT 3 6-5

CONTROLLEO BY USER AOMI H I ST RAT I VE CONTROLS 6.2.3 INDEPENDENT SAFETY ENGINEERING GROUP (ISEG)

FUNCTION 6.2.3. 1 The ISEG shall function to examine plant operating characteristics, HRC issuances, industry advisories, Licensee Event Reports, and other sources of plant design and operating experience information, including plants of similar design, which may indicate areas for improving plant safety.

COMPOSITION 6.2.3.2 The ISEG shall be composed of at least five, dedicated, full-time engineers located on site. Each shall have a Bachelor's Degree in engineering or related science and at least two years professional level experience in his field.

RESPONSIBILITIES 6.2.3.3 The ISEG shall be responsible for maintaining surveillance of plant activities to provide independent verification" that these activities are performed correctly to reduce human errors as much as practical, and to detect potential nuclear safety hazards.

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AUTHOR I TY 6.2.3.4 The ISEG shall make detailed recommendations for revised procedures, equipment modifications, maintenance 11 I 'I I<<'

Manager, and the~Sup~i-ser-, Nuclear Safety Group (NSG).

I-I~.IIIIII ctivities, operations activities or other RECORDS 4A apaw 6.2.3.5 Records of activities performed by the ISEG shall be prepared, main-tained, and forwarded each calendar month to th "I

6.2.4 SHIFT TECHNICAL ADVISOR 6.2.4.1 The Shift Technical Advisor (STA) shall provide advisory technical support to the Shift Supervisor in the areas of thermal hydraulics, reactor engineering, and plant analysis with regard to the safe operation of the unit.

The STA shall be onsite and shall be available in the control room within 10 minutes whenever one or more units are in HOOE 1, 2, 3, or 4.

6. 3 UNIT STAFF UALIFICATIOHS 6.3. 1 Each member of the unit staff shall meet or exceed the minimum qualifica-tions of ANS 3. 1-1978 and Regulatory Guide 1,8, September 1975, except for the Radiation Protection and Chemistry Manager who shall meet or exceed the qualifi-cations of Regulatory Guide 1. 8, September 1975, and the Shift Technical Advisor who shall have a bachelor's degree or equivalent in a scientific or engineering discipline with specific training in-plant design and plant operating charac'er-istics, including transients and accidents.

"Hot responsible for sign-off function.

PALO VERDE - UNIT 3 6"6

CONTROLLED BY USER AOHINISTRATIVE CONTROLS

6. 4 TRAINING 6.4.1 A trainin program for the unit staff shall. be maintained under the N

shall meet or exceed the requirements and recommendations of Section 5.0 of I'nd ANS 3. 1-19?8 and Appendix A of 10 CFR Part 55 and the supplemental requirements specified in Sections A and C of Enclosure 1 of the March 28, 1980 HRC letter to all licensees, and shall include familiarization with relevant industry operational experience.

6. 5 REVIEW AHO AUOIT 6.5.1 PLANT REVIEW BOARO (PRB)

FUNCTION 6.5.1.1 The Plant Review Board shall function to advise the WHYS-Plant Manager on all matters related to nuclear safety.

COMPOSITION 6.5.1.2 The PRB shall be composed of the following personnel:

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Member: a+cal-Su~ Manager Member: Operations Ravager- Dka~4a'ar J~ ~<8'e~~'

Member: g>ol~uuiccr ~ Haintenance Reneger Skate'<<d~

Hember:

Hember: Ekcgzicac. ggc+g4t~

P i

'+anJdarc)5 aaager

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i 1,Ui 2 Member: 0 t

Uni 3 ~~~<9 e+>

Hember: STA Supervisor Hember; per~endent S~ae'darCh &~e~i~a~

Member: Radiation Protection and Chemistry Manager Member: equality Systems/Engineering Manager ic e P~>rde'&f /UJclda'K Pleducfcc4 The t VHGS-N-ant-Mana@~ shall designate the Chairman and Vice-Chairmen in writing. The Chairman and Vice-Chairmen may be from outside the members listed above provided that they meet ANSI Standard 3.1, 1978.

ALTERNATES 6.5. 1.3 All alternate members shall be appointed in writing by the PRB Chairman to serve on a temporary basis; ho~ever, no more than two alternates shall participate as voting members in PRB activities at any one time.

HEETING FRE UEHCY 6.5. 1.4 The PRB shall meet at least once per calendar month and as convened by the PRB Chairman, Vice-Chairmen, or his designated alternate.

PALO VEROE - UNIT 3 6-7

COi~lTROLLED BY USER ADMINISTRATIVE CONTROLS gUORUtd 6.5. 1.5 The quorum of the PRB necessary for the performance of the PRB responsibility and authority provisions of these Technical Specifications shall consist of the Chairman, Vice-Chairmen, or his designated alternate and five members including alternates.

RESPONSIBILITIES 6.5. 1.6 The PRB shall be responsible for:

Review of all administrative control procedures and changes.

b. Revie~ of all proposed changes to Appendix "A" Technical'pecifications C. Investigation of all violations of the Technical Specifications including. the preparation and forwarding of reports covering evalua-tion and recommendations to prevent recurrence to the Nuclear Safety Group (HSG).

d. Review of REPORTABLE EVENTS.

e. Review of unit operations to detect potential nuclear safety hazards.

Performance of special reviews, investigations or. analyses and.reports thereon as requested by the> er.

fJj pg(gp~r - /ifiJc/E'8'iz Pld JU('cb D 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 PRB meeting.

AUTHORITY 6.5.1.7 The PRB shall:

Render determinations in writing with regard to whether or not each item considered under Specification 6.5. 1.6c. above constitutes an unreviewed safety question.

b. Provide written notif ion within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to the Vice President,-

Nuclear Production, nt Manager and NSG of disagreemen between the PRB and e 3%RES'lant Manager; however, th Plant Manager shall have responsibility for resolution of such disagreements pursuant to Specification 6. l. 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-px;ayisions of these Technical Specifications. Copies shall be provided to thd:fRRK Plant Manager,and HSG.

<y, pipye<(- st/~c/ec<<- jlCCl'(:gfpgig PALO VERDE - UNIT 3 6" 8

0, CONTROLLED BY USER bqecbr, &>a&ar85 aaiot ADMINISTRATIVE CONTROLS THc-kL'ice U 5u paz H 6.5.2 TECHNICAL REVIEW AND CONTROL ACTIVITIES 6.5.2. 1 The r 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. Q<rl.c4r, &@Mar&, o~~

~

~Ma/u'adfsfn/5 /Nay J ag d 6.5.2.2 Phase I - V tests describe3 in the FSAR t d ~ET or the Herag~W Engineeringgas previously designated by the A'NSS=Mant

~~ performed by the i 5

~iianapar. Test results shall be approved by the aww t4o,w +lie dnigfa/defy.fute Hvnl~4f'd~S rV/dPQager 6.5.2.3 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 prior to implementation by the MN88 Plapt panacgr ri,py th~m(~g,~

rgTechnjca) Support as previously designated by the~N t-Manager-.

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6.5.2.4 Individuals responsible for reviews perform >n accordance with 6.5.2.1, 6.5.2.2, and 6.5.2.3 shall be members of the stationsupervisory staff, previously designated by'he PVNGS=PlwWHarragergo perform such reviews. Each such revie~,

shall include a determination'of whether not additional, cross-disciplinary, review is necessary. If deemed necessary, uchl/<<c'~ review shall be performed by the appropriate designated review personnel. ~ac~~~

6.5.2.5 Proposed tests and experiments. which affect station nuclear safety and are not addressed in the FSAR or Technical Specifications shall be reviewed by-the-PYNGS-P 1 ant-Manager, &he.-Manager-Techn j cal-Sgu port;Qegaoayr Opera-tions.;or=the-Manager-Maintenance.~ ' f ~ 'J ~~ "' j "

~jg DifVCk~a >f e S~l Off'.+5 6.5.2.6 The station security program and implemenging procedures shall be reviewed. Recommended changes shall be approved byo&~H~Mnt-Manage~or designated alternate and transmitted to the Vice President-Huclear Production and to the NSG.

I 6.5.2.7 The station emergency plan and implementing rocedures shall be reviewed. Recommended changes shall be approved by the~PVHGS-I&ant-Manager or designated alternate and transmitted to the Vice President-Nuclear Production and to the NSG.

6.5.2.8 ThV lufH85-picot-lianagev shall assure the performance of a review by a qualified individual/organization of every uriplanned onsite release of radio-active material to the environs including the preparation and forwarding of

( reports covering the evaluation, recommendations and disposition of the cor-Xrective action to prevent recurrence.

Pop 5'ra.t Parcels awed /c<'n A'ff:ai - ~vjrpdw'~ /'r-ec PALO VERDE - UNIT 3 6" 9

CONTROLLED BY USER ADMINISTRATIVE CONTROLS TECHNICAL REVIE'IIv'ND CONTROL ACTIVITIES Continued) 6.5.2.9 The-PVNGS-f%anb-Manage+>shall assure the performance of a revie~ by a qualified individual/organization of changes to the PROCESS CONTROL PROGRAM, OFFSITE DOSE CALCULATION MANUAL, radwaste treatment systems, and the Pre-planned Alternate Sampling Program.

6.5.2. 10 Reports documenting each of the activities performed under Specifica-tions 6. 5. 2. 1 through 6. 5. 2. 9 above shall be maintained. Copies shall be provided to the PVNGS-PlantManager>and the Nuclear Safety Group.

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FUNCTION 6.5.3. 1 The NSG shall function to provide independent review and shall be responsible for the 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 practices COMPOSITION y

l,tgg//gal/

jHgd0qg4 6.5.3.2 The N G shall consist of a~Svperv+sor and at least four staff spe-cialists. Thekstrpervisor shall have a Bachelor's Degree in Engineering or the Physical Sciences. He will also have a minimum of 10 years experience in the power field with at least 3 of those years in the nuclear field. The NSG pLOOfgt'~ Sup+~or will have at least 2 year s of supervisor/managerial experience.

Each staff specialist will have at least one of the foIlowing requirements:

Eight years experience in one of the designated areas in Specifica-tion 6.5.3. l. One of these 8 years will be at Palo Verde Nuclear Generating Station.

b. Bachelor's Degree in Engineering or a related science and 3 years of professional experience.

CONSULTANTS

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6-5.3.3 Consultants shall be utilized as determined by the NSG~4epe~isor to provide expert advice to the NSG.

REVIEW 6.5.3.4 The NSG shall review:

a. The safety evaluations program and its implementation for (1) changes to procedures, equipment, systems or facilities within the po~er block, and (2) tests or experiments completed under the provision of 10 CFR 50.59, to verify that such actions did not constitute an unreviewed safety question; PALO VERDE - UNIT 3 6-10

CONTROLLED BY USER AOHIHISTRATIVE CONTROLS eu Sue~~

REVIEW (Continued

b. Proposed changes to procedures, equipment, systems or facilities within the power block which involve an unreviewed 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; Proposed changes to Technical Specifications or this Operating License;

e. Violations of codes, regulations, orders, Technical Specifications, license requirements, or of internal procedures or instructions having nuclear safety significance; Significant operating abnormalities or deviations from normal and expected performance of unit equipment that affect nuclear safety; All REPORTABLE EVENTS requiring 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> written notification;

h. All recognized indications of an unanticipated deficiency in some aspect of design or operation of structures, systems, or components that could affect nuclear safety; and

l. Reports and meeting minutes of the PRB.

AUDITS 6.5.3.5 Audits of unit activities shall be performed under the cognizance of the HSG. 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 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 equality Assurance Program to meet the criteria of Appendix B, 10 CFR Part 50, at least once per 24 months.

Any other area of unit operation considered appropriate by the HSG or the Vice President-Huclear Production.

The fire protection programmatic controls including the implementing procedures at least once per 24 months by qualified licensee gA personnel.

PALO VERDE " UHIT 3 6" 11

0 CONTROLLED BY USER ADMINISTRATIVE CONTROLS AUDITS (Continued)

g. The fire protection equipment and program implementation at least once per 12 months utilizing either a qualified offsite licensee fire protection engineer or an outside independent fire protection consultant. An outside independent fire protection consultant shall be used at least every third year.

h. The radiological environmental monitoring program and the results thereof at least once per 12 months.

The OFFSITE DOSE CALCULATION MANUAL and implementing procedures at least once per 24 months.

j. The PROCESS CONTROL PROGRAM and implementing procedures for processing and packaging of radioactive wastes at least once per 24 months.

k. The performance of activities required by the Operations equality Assurance Criteria Manual to meet the provisions of Regulatory Guide 1.21, Revision 1, June 1974 and Regulatory Guide 4.1,

,Revision 1, April 1975 at least once per 12 months.

AUTHORITY Q (-gc$ Lop'l g' recur Qc~'fQ ('t Q.kid

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q 6.5.3.6 The HSG shall repor t to and advise the%aaager-ef-Nuclea~~ on

those areas of. responsibility specified in Specifications 6.5.3.4 and 6.5.3.5.

RECORDS +git ec.4c.z., Qgc.(au S~i4/y clead 4i c en3gi~q 6.5.3.7 Records of NSG activities shall be prepared nd maintained. Report of reviews and audits shall be prepared monthly for the cLea.~af.e t.y who will distribute it to the Vice President-Nuclear Production, ~S Plant Manager, and to the, management positions responsible for the areas audited.

6.6 REPORTABLE EVENT ACTION The following actions shall be taken for REPORTABLE EVENTS:

a ~ The Commission shall be notified pursuant to the requirements of Section 50.72 .to 10 CFR Part 50, and a report submitted pursuant to the requi rements of Section 50.73 to 10 CFR Part 50, and Each REPORTABLE EVENT shall be reviewed by the PRB, and the results of this review shall be submitted .to the .Superv+sor+of Huclear Safety Group and the Vice President-Nuclear Production.

4) A Q Mc <j P P'ALO VERDE - UNIT 3 6" 12

CONTROLLED BY USER ADMINISTRATIVE CONTROLS 6.7 SAFETY LIMIT VIOLATION The following actions shall be taken in the event a Safety Limit is violated:

The NRC Operations Center shall be notitied by telephone as soon as possible and in all cases within 1 hour. The Vice President-Nuclear w

Group shall be notified within 24 hours.

b. A Safety Limit Violation Report shall be prepared. The report shall be reviewed by the PRB. This report shall describe (1) applicable circumstances preceding the violation, (2) effects of the violation upon facility components, systems, or structures, and (3) corrective action taken to prevent recurrence.

C. The Safet Limit Violation Report shall be submitted to the

[AcUnge+ ommission, th Her of the NSG and the Vice President-Nuclear Production within 30 days of the violation.

d. Critical operation of the unit shall not be re'sumed until authorized by the Commission.

6.8 PROCEDURES AND PROGRAMS 6.8.1 Written procedures shall be established, implemented, and maintained covering the acti'vities referenced below:

a. The applicable procedures recommended in Appendix A of Regulatory Guide l. 33, Revision 2, February 1978, and those required for implementing the requirements of NUREG-073?.

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. Modification of Core Protection Calculator (CPC) Addressable Constants--These procedures should include provisions to ensure that sufficient margin is maintained in CPC Type I Addressable Constan's to avoid excessive operator i nteraction with the CPCs during reactor operation.

NOTES: (1) Modification to the CPC Addressable Constants based on information obtained through the Plant Computer - CPC data link shall not be made without prior approval of the PRB.

(2) Modifications to the CPC software (including algorithm changes and changes in fuel cycle specific data) shall be performed in accordance with the most recent version of CEN-39(A)-P, "CPC Protection Algorithm Software Change Proce-dure," that has been determined to be applicable to the facility. Additions or deletions to CPC Addressable Constants or changes to Addressable Constant soft-ware limit values shall not be implemented without prior NRC approval.

PALO VERDE " UNIT 3 6-13

GONTROLLED BY USER ADMINISTRATIVE CONTROLS PROCEDURES AND PROGRAMS (Continued)

~

h. PROCESS CONTROL PROGRAM implementation.

i. OFFSITE DOSE CALCULATION MANUAL implementation.

J. Quality Assurance Program for effluent and environmental monitoring, using the guidance in Regulatory Guide 1.21, Revision 1, June 1974 and Regulatory Guide 4. 1, Revision 1, April 1975.

k. Pre-planned Alternate Sampling Program implementation.

1. Secondary water chemistry program implementation.

NOTE: The licensee shall perform a secondary water chemistry monitoring and control program that is in conformance with the program discussed in Sec-tion 10.3.4. 1 of the CESSAR FSAR or another NRC approved program.

m. Post-Accident Sampling System implementation.*

n. Settlement Monitoring Program implementation.

NOTE: The licensee shall maintain a settlement monitoring program throughout the life of the plant in accordance with the program presented in Table 2.5-18 of the PVNGS FSAR or another NRC approved program.

o. CEA Symmetry Test Program implementation NOTE: The licensee shall perform a CEA symmetry test program in conformance with the program discussed in Section 4.2.2 of the PYNGS SER dated November 11, 1981.

p. Fuel Assembly Sur veil lance Program Implementation NOTE: The licensee shall perform a fuel assembly surveillance program in con-formance with the program discussed in Section 4.2.4 of the PYNGS SER dated November 11, 1981.

6. 8. 2 Each program or procedure of pecification 6.8. 1, and changes thereto, shall be reviewed as specified in Specification 6.5 and approved prior,.to implementation. Programs, administrative control procedures and implementing procedures shall be approved by the , or designated alternate who is at supervisory level or above. Programs and procedures of Specifica-tion 6.8. 1 shall be reviewed periodically as set forth in administrative procedures.

6. 8. 3 Temporary changes to procedures of Specification 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 supervisory staff, at least one of whom is a Shift Supervisor or Assistant Shift Supervisor with an SRO on the affected unit.

C.

roicec+ir ~~occkarc4 g~ J Tech,ijica( 4 '/p,r The change is documented,lreviewed 3n accordance with Specification f

6.5.2 and approved by the~RN&S-Hant-Manager or cognizant department head, as designated by the~PVNGS-R.ant-Manager , within 14 days of implementation. itic, Preside.vt.- ~,c'~Pa- Vrcgvc.'/cy J

• Not required until prior to exceeding 5~ of RATED THERMAL POKER.

PALO YEROE - UNIT 3 6-14

4

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