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ATTACHMENT 1

CONDUCT OF OPERATIONS

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INDEX


PAGE

1.01.11.1.11.1.21.1.2.11.1.2.1.11.1.2.1.21.1.2.1.2.11.1.2.1.2.21.1.2.1.2.2.11.1.2.1.2.2.21.1.2.1.2.31.1.2.1.2.41.1.2.1.2.51.1.2.1.31.1.2.1.3.11.1.2.1.3.21.1.2.1.3.31.1.2.1.3.41.1.2.1.3.51.1.2.1.3.61.1.2.1.41.1.2.1.51.1.31.21.2.11.2.21.2.2.11.2.2.1.11.2.2.1.1.11.2.2.1.1.1.11.2.2.1.1.1.21.2.2.1.1.1.31.2.2.1.1.1.41.2.2.1.1.21.2.2.1.1.31.2.2.1.1.41.2.2.1.1.51.2.2.1.1.61.2.2.21.2.2.2.11.2.2.2.21.2.2.2.31.2.2.2.41.2.2.2.51.2.2.31.2.2.3.1

ORGANIZATIONAL STRUCTURE OF APPLICANTManagement 6 Technical Support OrganizationTechnical Support for OperationsAPS Organizational ArrangementAPS Nuclear OrganizationVice President Nuclear Production OrganizationDirector Site ServicesManager SecurityManager Emergency Planning and ServicesFire Protection DepartmentEmergency Planning DepartmentManager TrainingManager Material ControlManager Administrative ServicesDirector Engineering and ConstructionManager Nuclear EngineeringManager Participant ServicesManager Records ManagementManager Cost and ScheduleManager ConstructionManager Nuclear FuelsDirector Nuclear Safety and LicensingDirector Quality AssuranceQualification of Headquarters StaffOnsite Operating OrganizationOnsite Station OrganizationStation Personnel Responsibilities and AuthoritiesVice President-Nuclear ProductionPlant ManagerOperations ManagerShift SupervisorsAssistant Shift SupervisorNuclear Operator IIINuclear Operator I and IIRadwaste SupervisorMaintenance ManagerWork Control ManagerRadiation Protection ManagerChemisty ManagerAssistant Vice President-Nuclear Production SupportWater Reclamation Facility (WRF) ManagerOutage Management ManagerCentral Maintenance ManagerRadwaste Support ManagerCentral Radiation Protection ManagerDirector Standards and Technical SupportEngineering Evaluation Manager

1-1l-l1-1l-ll-l1-21-31-31-41-41-41-51-51-51-61-61-71-71-81-91-91-91-101-10l-ll1-111-11l-ll1-121-121-121-131-131-131-131-131-141-141-141-141-141-151-151-151-151-151-16

INDEX

CONDUCT OF OPERATIONSContinued)

PAGE

1.2.2.3.1.11.2.2.3.1.21.2.2.3.1.31.2.2.3.1.41.2.2.3.1.4.11.2.2.3.21.2.2.3.31.2.2.3.41.31.3.11.3.21.41.4.11.4.21.4.2.11.4.2.21.4.2.3

Reactor Engineering SupervisorTest Engineer SupervisorShift Technical Advisor (STA) SupervisorSystem Engineering SupervisorSupervisor of Station StatisticsOperations Computer Systems ManagerRadiation Protection and Chemistry ManagerPlant Standards and Control ManagerQualifications of Nuclear Plant PersonnelQualification RequirementsQualifications of Plant PersonnelReview and AuditOnsite ReviewIndependent ReviewNuclear Safety Group (NSG)Independent Safety Engineering Group (ISEG)Audit Program

1-161-161-161-161-171-171-171-171-181-181-211-211-211-221-221-221-22

POSITION FUNCTION CROSS REFERENCE~1~

Existin Function New Function

President and Chief OperatingANPP Executive Vice PresidentV.P. Nuclear ProductionPlant Manager

Operations Manager

Ops. Supt.

Day Shift Supv.

Shift Supv.

Assist. Shift Supv.

Supervisor Ops. Support

Officer President and Chief Operating OfficerANPP Executive Vice PresidentV.P. Nuclear ProductionPlant Managers

None

Operations Manager

Operations Support SupervisorShift Supv.

Assist. Shift Supv.

None

Site Manager, Maintenance

MCC Superintendent

IGC/Elec. Work Control Supv.

Mech. Work Control Supv.

IGC Maintenance Supt.Electrical Maintenance Supt.Mechanical Maintenance Supt.Plant Services Manager

Maintenance Manager

Central Maintenance Manager

None

None

None

IGC Maintenance SupervisorElectrical Maintenance SupervisorMechanical Maintenance SupervisorDirector, Site Services

Mgr., Outage Management

Outage Supt.

Central Outage Management Mgr.

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)


Ops Engineering Manager

STA Supv.

Tech. Engineering Supervisor

Engineer-Mech. Supervisor

Engineer-Elec./IGC SupervisorReactor Engineering Supervisor

Engineering Evaluation Manager

STA Supv.

Test Engineering SupervisorOR

System Engineering SupervisorOR

Station Statistics SupervisorReactor Engineering Supervisor

Radiation Prot. and Chemistry Mgr.

Radiation Mat'ls Control Mgr.

Radwaste Supv.

Radwaste Support Supv.

Radiological Services Mgr.

Radiation Protection Support Supv.

Supv.

Radiation Protection 6 Chemistry Mgr.Radwaste Support Manager

Operations Support SupervisorRadwaste Support Manager

Radiation Protection Manager

Central Radiation Protection Manager

Chemical Service Mgr.

Unit Chemistry Supv.

ALARA Supv.

Ops Computer System

Hardware Maintenance Supv.

Process Computer Engr. Supv.

Computer Support Supv. (Vacant)Plant Services Manager

Operations Security Mgr.

Assist. V.P.-Nuclear Production

HRF Superintendent

Administrative Services Mgr.

Material Control Supv.

Inventory Control Supv.

Transportation Supv.

Emergency Planning Mgr.

None

Unit Chemistry Manager

Radiation Protection Manager

Ops Computer Manager

Hardware Maintenance Supv.

Process Computer Engr. Supv.

Computer Support Supv.

Director, Site Services (in part:)Security Mgr.

Assist. V.P.-Nuclear ProductionSupport

MRF Mgr.

Administrative Services Manager

Material Control Supv.

Inventory Control Supv.

Transportation Supv.

Emergency Planning 6 Services Mgr.-iv-

POSITION FUNCTION CROSS REFERENCE(l~Continued


Training Mgr.

General Training Supv.

Operator Training Supv.

Training Support Supv.

Project Mgr. of Accred.Transition Mgr.

Training Mgr.

General Training Supv.

Operator Training Supv.

Training Support Supv.

Project Mgr. of Accred.None (Job was completed)

Director, Technical ServicesNuclear Engineering Mgr.

Production Mgr.

Electrical Engineering Supv.

Mech. & Chem. Engineering Supv.

Civil & Arch. Eng. Supv.

I&C Engineering Supv.

Corp. Health Phys. Supv.

Analysts, Lead

Methods Trg. Compliance, Lead

Nuclear Construction Mgr.Nuclear Construction PersonnelN.P. Records Mgmt. Mgr.

Nuclear Records Personnel

Nuclear Fuel Mgmt. Mgr.

Fuel Cycle Serv. Supv.

Nuclear Analysis Supv.

Safety Analysis Supv.

Technical Projects Supv.

Nuclear Licensing Mgr.

Director, Engineering and ConstructionEngineering Mgr.

Engineering Mgr.

Electrical Engineering Supv.

Mech. & Chem. Engineering Supv.

Civil & Arch. Eng. Supv.

I&C Engineering Supv.

None (Moved under Radiation and

Chemistry Manager

Reliability Analysis Supv.

Methods Trg. Compliance, Lead

Nuclear Construction Mgr.

Nuclear Construction PersonnelN.P. Records Mgmt. Mgr.

Nuclear Records PersonnelNuclear Fuel Mgmt. Mgr.

Fuel Cycle Serv. Supv.

Nuclear Analysis Supv.

Safety Analysis Supv.

Technical Projects Supv.

Nuclear Licensing Mgr.

POSITION FUNCTION CROSS REFERENCE(1)Continued


None

NSG/ISEG Manager

Director Nuclear Safety and LicensingManager Nuclear Safety Group;

Manager ISEG

Director, Corporate QA/QC

Assistant Director QA/QC

Quality Systems and EngineeringManager

Procurement Quality Manager

Quality Audits and MonitoringManager

Quality Control Manager

Director, Corporate QA/QC

None

Quality Systems and EngineeringManager

Procurement Quality Manager

Quality Audits and MonitoringManager

Quality Control Manager

NOTE:

This table represents a cross reference of job functions from the

existing organization to the new (proposed) organization. Job functionsfrom existing to new are meant to show the best match. In some cases a

new function may have less or more responsibilities than the existingCfunction.

ATTACHMENT 1


1. ORGANIZATIONAL STRUCTURE

1.1 Mana ement and Technical Su ort Or anization

This section provides information relative to the corporateorganization and its functions and responsibilities and the number andqualifications of personnel participating in the operation of theunits 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 andChief Executive Officer of APS as the Corporate Officer responsiblefor providing management and technical support services for PVNGS(Refer to Figure 1-1).'he Executive Vice President, ANPP hasestablished under him groups and departments as discussed inSection 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 changeis being made to this structure as a result of the ANPPorganizational changes. The organizational arrangement forproviding onsite and offsite technical support for nuclearoperations 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 theoperation and technical support of PVNGS. This position hasthe overall responsibility and authority to ensure that allactivities associated with APS'uclear facilities are carriedout with the highest standards of safety. Figure 1-2 reflectsthe organization of the Executive Vice President, ANPP.Reporting directly to the Executive Vice President, ANPP arethe following: Vice President-Nuclear Production, DirectorSite Services, Director Engineering and Construction, DirectorNuclear Safety and Licensing and Director Corporate QA/QC.This organization is discussed in the following sections.

1-1

Vice President, Nuclear Production Or anization

The Vice President, Nuclear Production reports to theExecutive Vice President, ANPP. This position isresponsible to operate and maintain the three PVNGS unitsand the Water Reclamation Facility (WRF). The majorfunctions of this position are: Operate and maintain thethree Units and the WRF to ensure compliance withregulatory requirements and approved procedures; Plan andschedule the Units activities; Provide functional supportrequired for the operation and maintenance, such as plantwide chemical and , radiological services and wastedisposal, and maintenance planning; Assure standardizationof procedures and practices among the Units; Performanceof direct technical and engineering support for plantoperations and maintenance, including approval of designimprovements and changes to operational requirements, aswell as the design and installation of minor plantmodifications and validation testing of all modifications.This position is charged with the authority to ensure thatthese activities related to nuclear safety are completedwith the highest standards of safety and it has theauthority to allocate resources under this area ofresponsibility.

Figure 1-3 reflects the organization of the VicePresident-Nuclear Production.

To carry out his responsibilities, the Vice President-Nuclear Production has established the groups discussedlater in Section 1.2.2.1. In the absence of the VicePresident-Nuclear Production, the Assistant VicePresident-Nuclear Production Support shall be delegatedthose nuclear safety responsibilities and authorities andshall 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 forthe Units and the WRF. Previous ancillaryresponsibilities for all aspects of the facility such as;Security, Training, Emergency Planning, AdministrativeServices, Offsite Engineering and Construction, NuclearRecords and Licensing are " placed elsewhere in theorganization (Refer to current FSAR Figure 13.1-3 for thisposition's past organization).

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

1-2

1.1.2.1.2 Director, Site Services

The Director, Site Services reports to the Executive VicePresident, ANPP. This onsite position is responsible toprovide administrative and special site services thatsupport the operation of PVNGS by satisfying commitmentsto regulatory agencies and oversight groups. Theseservices include Plant Security, Training, EmergencyPlanning and Services, Material Control and AdministrativeServices. The major functions of this position are:Implement an On-Site Security Program to prevent sabotageand unwarranted intrusion by unauthorized persons forwhatever reason, in accordance with the NRC-approved plan;Provide training programs for PVNGS personnel in concertwith the requirements of the NRC, other agencies, and theCompany; Implement programs in the area of fireprotection, and emergency preparedness; Provideadministrative services support for the nuclear facilitiesincluding site transportation needs, clerical, wordprocessing, duplicating, and mail distribution services;Manage the Material Control Department to providecoordinated services for procurement, purchasing,inventory control, and warehousing of materials.

Figure 1-4 reflects the organization of the Director, SiteServices. The department managers which report directlyto the Director of the Site Services Group are discussedin the following sections which include functions of theprevious Manager, Administrative Services, and Manager,Training (current FSAR Figure 13.1-3A) Manager, EmergencyPlanning (current FSAR Figure 13.1-3A), Manager, Securityand Supervisor, Fire, Protection (current FSAR Figure13.1-6D).

lt

Chan es to the Site Services Grou

The Director, Site Services is a new position title. Thefunctions of departments now reporting to this positionpreviously 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 managethe PVNGS Security Program. These responsibilitiesinclude Operations Security, Security TrainingSupport, Security Access and Badging, and IndustrialSecurity. Figure 1-5 reflects the organization of theSecurity Manager.

Chan es to the Mana er, Securit

There are no changes of responsibilities to thisexisting position. This position previously reported

1-3

directly to the Plant Services Manager (Refer to thecurrent FSAR Figures 13.1-6 and 13.1-6D and FSARSection 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 isresponsible to the Director, Site Services toimplement programs in the areas of fire protection andemergency preparedness. Reporting to the position arethe Fire Protection Supervisor and the EmergencyPlanning Supervisor. Figure 1-6 reflects theorganization of the Emergency Planning Manager.

Chan es to the Emer enc Plannin and ServicesDe artment

The functions of this department are unchanged exceptthe Fire Protection Section has been added. The FireProtection Section previously reported to the PlantServices Manager under the Plant Manager (Refer tocurrent FSAR Figure 13.1-6D and FSAR Section13.1.2.2.4.1). The Fire Protection Section'sresponsibilities have not changed. The EmergencyPlanning Section previously reported to the AssistantVice President-Nuclear Production (Refer to currentFSAR Figures 13.1.3A and 13.1.3I and FSAR Section13.1.1.2.2.1'1).

1.1.2.1.2.2.1 Fire Protection

The Fire Protection Supervisor reports onsite tothe Manager, Emergency Planning and Services and isresponsible for establishing and supervising theFire Protection program at the Plant. The FireProtection program is discussed in FSAR Section9.5.1.5.1.

Chan es to the Fire Protection Section

The responsibilities of this section have notchanged. (Refer to the current FSAR Section13.1.2.2.4.1). The Fire Protection sectionpreviously reported to the Plant Services Manager.(Refer to the current FSAR Figure 13.1-6D and FSARSection 13.1.2.2.4.1.

1.1.2.1.2.2.2 Emer enc Plannin

The Emergency Planning Supervisors are responsiblefor the development and implementation of the PVNGS

Emergency Plan. Figure 1-6 reflects theorganization of the Emergency Planning and ServicesManager.

1.1.2.1.2.3 Mana er, Trainin

The Manager, Nuclear Training is responsible to theDirector, Site Services for the preparation,coordination and conduct of PVNGS training. TheLicensed Operator Training, General Training, andTraining Support Supervisors report to t'e TrainingManager. Figure 1-7 reflects the organisation of theTraining Manager.

Chan es to the Trainin De artment

None. This department previously reported to theAssistant Vice President-Nuclear Production (Refer tothe current FSAR Figure 13.1.3A and Section13.1.1.2.2.1.3).

1.1.2.1.2.4 Mana er Material Control

The Manager, Material Control is responsible onsite tothe 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 existingrelated functions of Materials and Purchasing andContracts which previously existed in differentdepartments. Material Control and Inventory Controlpreviously existed onsite under the AdministrativeServices Manager who previously reported to theAssistant Vice President-Nuclear Production (Refer tocurrent FSAR Figure 13.1-3A and FSAR Section13.1.1.2.2.1.2).

Purchasing and Contracts previously existed under theDirector, Project Services who previously reported tot'e Executive Vice President, ANPP (Refer to thecurrent FSAR Figure 13.1-28 and FSAR Section13.1.1.2.1.1).

Having the two sections which purchase and controlplant material in the same department will enhancecoordination and parts availability for the plant.

1.1.2.1.2.5 Mana er, Administrative Services

The Manager, Administrative Services is responsibleonsite to the Director, Site Services for officeservices and site transportation services for PVNGS.

1-5

Chan es to the Administrative Services De artment

This is an existing position by name. It previouslyreported to the Assistant Vice President-NuclearProduction. Previous responsibilities for InventoryControl and Material Control were deleted from thisposition's responsibililty. The reporting point hasbeen changed from reporting to the Assistant VicePresident, to a Director, so that senior managementattention is not drawn away from plant operation.

1.1.2.1.3 Director, En ineerin and Construction

The Director, Engineering and Construction is responsibleoffsite to the Executive Vice President, ANPP to provideEngineering, Construction, Records Management, Cost andScheduling, Nuclear Fuels Management and Participant OwnerServices. The Director, Engineering and Construction isassisted in the performance of his duties by severaldepartments reporting directly to him. Figure 1-8reflects the organization of the Director, Engineering andConstruction.

Chan es to the En ineerin and Construction Grou s

This is a new position title, but it is similar to theprevious Director, Technical Services shown on theexisting FSAR Figure 13.1-3D and FSAR Section 13.1.1.2.2.2except as follows: The Nuclear Licensing Department(current FSAR Figure 13.1-3J) no longer reports to thisposition. The Participant Services Department (currentFSAR 13.1-2B) previously reporting to the Director,Project Services, now reports to this Group.

A new Cost and Scheduling Group, developed frompositions previously reporting to the Director,Services (current FSAR Figures 13.1-20 and13.1.1.2.1.1), now reports to this group. TheFuel Management, Construction Department andDepartment functions remain unchanged.

existingProjectSectionNuclearRecords

1.1.2.1.3.1 Mana er, En ineerin

The Manager, Engineering is responsible to theDirector, Engineering and Construction to providequalified di,scipline engineering capability to performdesign functions, prepare specifications, coordinatevendor/contractor service activities, and prepare testspecifications and engineering validation criteria formajor improvements, modifications and additions toPlant facilities.

1-6

The sections within the Engineering Departmentthat'rovidetechnical support for PVNGS are Electrical

Engineering, Instrumentation and Controls Engineering,Chemical/Mechanical Engineering, Civil/StructuralEngineering, Reliability Analysis, and Methods/Training. The Discipline Supervisors report to theEngineering Manager, Figure 1-9 reflects theorganization of the Nuclear Engineering Manager.

Chan es to the Nuclear En ineerin Department

The responsibilities of the Nuclear EngineeringDepartment include most of the same responsibilitiesexisting previously. The offsite Corporate HealthPhysicist function has been transferred onsite underthe Radiation Protection and Chemistry Manager. TheProduction Manager position is eliminated andfunctions transferred to the new engineering manager.(Refer to the current FSAR Figure 13.1-3E and FSARSection 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 tothe Director, Engineering and Construction to provideinformation services and coordination for plantinterfaces with the PVNGS owner companies and theircommittees 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 thesame. Previously this group reported to the Director,Project Services (Refer to the current FSAR Figure13.1-2B 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 providesonsite and offsite support for PVNGS, Construction,Engineering, and outside consultants and contractorsin the areas of documentation, drawing control andassociated reference informational material by themeans of hardcopy, micromedia and/or computer assistedretrieval.

The Nuclear Records Management Manager directs thetechnical and administrative activities within theNuclear Records Management Department. The NuclearRecords Management Department is comprised of fivesections:

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 supportsthe sections within and coordinates the turnoveractivities of documentation to the department fromoutside departments, organizations and contractors.The section supervisors report to the Nuclear RecordsManagement Manager. Figure 1-10 reflects, theorganization of the Nuclear Records Department.

Chan es to the Nuclear Records De artment

The responsibilities and reporting point of thisdepartment remains the same. (Refer to the currentFSAR 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 theDirector, Engineering and Construction to provide costestimating, scheduling and monitoring services forengineering and modification projects.

Chan es to the Cost and Schedule De artment

This is a new department created from personnel fromother existing areas of both Cost and Scheduling,particularly those under the existing Director,Project Servies (Refer to the current FSAR Figure13.1-2B 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 theDirector, Engineering and Construction to provide forsite related Construction Activities to manage theconstruction, modification and/or installation ofmajor structures, systems and equipment that representphysical changes or additions to PVNGS facilities.

1-8

Chan es to the Construction De artment

None. (Refer to the current FSAR Figure 13.1-3F andFSAR 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 fuelsmanagement and core analysis for PVNGS.

The Manager, Nuclear Fuels provides nuclear fueldesign, contracting and utilization expertise, nuclearfuel core and plant transient and accident analysisand alternative core operating strategies. Figure1-11 reflects the organization of the Nuclear FuelsDepartment.

Chan es to the Nuclear Fuels De artment

None. (Refer to the current FSAR Figure 13.1-3H andFSAR Section 13.1.1.2.5).

1.1.2.1.4 Director, Nuclear Safet and Licensin

The Director, Nuclear Safety and Licensing is responsibleto the Executive Vice President, ANPP to coordinatelicense document changes, responses to NRC requests and toserve as the plant interface with NRC, This positiondirects management activities of the offsite NuclearSafety Group, the onsite Independent Safety EngineeringGroup, the onsite Compliance Department (to provide forcompliance monitoring of PVNGS regulatory commitments),offsite Technical Data section (to disseminate technicaland performance data from ANPP to others) and the offsiteLicensing Department.

Figure 1-12 reflects the organization of the NuclearSafety and Licensing Group. Also, the onsite ComplianceDepartment is matrixed to the Director, Standards andTechnical Support.

Chan es to the Nuclear Safet and Licensin Grou

This is a new group resulting from combining together theexisting Licensing, Nuclear Safety Group (NSG)',Independent 'afety Engineering Group (ISEG), andCompliance Departments and addition of a new TechnicalData section. The NSG and ISEG are divided under twomanagers rather than one to provide further attention totheir activities. Figure 1-12 reflects the organization

1-9

of the Nuclear Safety and Licensing Group. (Refer to thecurrent FSAR Figure 13.1-3K, FSAR Section 13.1.1.2.9, FSARFigure 13.1-3J and FSAR Section 13.1.1.2.7 and FSAR Figure13.1-6 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 ExecutiveVice President, ANPP to provide implementation of the QAand QC activities. Refer to the current FSAR Chapter 17,Section 17.2 "Quality Assurance during the OperationsPhase" for the responsibilities and interface of theQuality Assurance Group. FSAR Figure 17.2-1 reflects theprevious organization of the Quality Assurance Group.

Chan es to the Qualit Assurance Grou

The nuclear functions and responsibilities of this groupremain the same. The Assistant Director QA/QC positionhas been eliminated.

1.1.3 Qualifications of Head uarters Staff

The qualifications of headquqarters staff technical personnel isdiscussed in the current FSAR Section 13.1.1.3 and remains ineffect.

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

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

The Director, Engineering and Construction position correspondsmost closely to that identified as "engineer in charge" by ANSI/ANS3.1-1978, and the minimum requirements for this position are thoseof 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 responsibilityfor the operation of the PVNGS Units. The PVNGS Plant Managers haveresponsibility for the safe, reliable and efficient operation of theUnits. Refer to Figure 1-3.

1-10

1.2.1 Onsite Station Or anization

The PVNGS onsite station organization is divided into three groupswhich report to the Vice President-Nuclear Production. Each groupis divided into subordinate departments. Each PVNGS unit isdivided into the same departments. One other onsite support group(Director, Site Services) was discussed previously.

Plant GroupPVNGS Units 1, 2 and 3—Operations—Maintenance-- Work Control—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 theoverall station operations. The Plant Managers are responsible foroperations of their assigned unit.

The Unit organization is shown on Figure 1-13. Sufficient manpoweris 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 ExecutiveVice President, ANPP and has direct responsibility for thesafe, reliable, and efficient operation of PVNGS.

The Vice President-Nuclear Production is totally and solelycommitted to the management of APS'uclear facilities. Thisposition is charged with the responsibility to ensure that APS

'uclear facilities are operated and maintained in accordancewith regulatory requirements and with the highest level ofsafety in accordance with APS policy. Accordingly, thisposition is charged with the authority necessary to ensure thatthe appropriate resources are available to support the nuclear

1-11

unit operational activities. The fact that ancillary supportis available to the Vice President-Nuclear Production shall notdiminish the authority and responsibility of this position norshall it prevent this position from obtaining any and allresources, both within and outside APS, necessary to achievethese goals. In the absence of the Vice President-NuclearProduction, the responsibilities for the day-to-day operation,maintenance, and performance of the station are assigned to theAssistant Vice President-Nuclear Production. In the event ofunexpected contingencies of a temporary nature, when neitherthe Vice President-Nuclear Production nor the Assistant VicePresident-Nuclear Production is available at the station, oneof the Plant Managers will be assigned this responsibility.

The Plant Managers 're responsible to theVice'resident-NuclearProduction for the safe, reliable, and

efficient operation of their assigned Unit. This positiondirects the Operations Manager, Maintenance Manager, WorkControl Manager, Radiation Protection Manager, and theChemistry Manager of the assigned unit. (Refer to Figure1-13 for the Unit Specific Organization).

1.2.2.1.1.1 0 erations Mana er

The Operations Manager is responsible to the PlantManager for the conduct of the unit operations in asafe and efficient manner in accordance with technicalspecifications and station procedures. This positionsupervises the activities of the unit's operatingpersonnel. At the time of initial core. loading orappointment to the position, the Operations Managersshall hold a Senior Reactor Operator license inaccordance with ANSI/ANS 3.1-1978 Section 4.2.2. Thisposition is similar to the previous Superintendent ofOperations shown on current FSAR Figure 13.1-6B anddiscussed in FSAR Section 13.1.2.2.3.1. This positionwill serve as the Plant Manager's principle alternateper 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 theOperations Manager for the safe, reliable, andefficient operation of the unit during the assignedshift. The shift supervisor directs the activitiesof the operators on each shift. The ShiftSupervisor will possess a Senior Reactor OperatorLicense. This position does not change due to thisreorganization.

1-12

1.2.2.1.1.1.2 Assistant Shift Su ervisor

The Assistant Shift Supervisor provides a backup tothe Shift Supervisor and supervises shift personnelin conduct of operations as assigned. TheAssistant Shift Supervisor will possess a SeniorReactor Operator License. This position does notchange due to this reorganization. (Refer to thecurrent FSAR Section 13.1.2.2.1.3).

1.2.2.1.1.1.3 Nuclear 0 erator IIIThe Nuclear Operator III manipulates the reactorplant controls. The Nuclear Operator III willpossess a Reactor Operator License. This positiondoes not change due to this reorganization. (Referto the current FSAR Section 13.1.2.2.3.1.4).

1.2.2.1.1.1.4 Nuclear 0 erator I and IIThe Nuclear Operator I and II are responsible,under the direction of the Shift Supervisor andAssistant Shift Supervisor, for operating auxiliarysystems and assisting in the refueling of the plantas directed. These positions do not change due tothis reorganization. (Refer to the current FSARSection 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 tothe Operations Manager and is responsible for theoverall preparation, coordination, and conduct of theradioactive waste management programs and demineralizeroperations including approval of radioactive wastedisposal activities. This position will provide abackup to the Operations Manager and hold an SROlicense on PVNGS. This is a new position.

1.2.2.1.1.3 Maintenance Mana er

The Maintenance Manager is responsible to the PlantManager for the performance of surveillance testing,preventative maintenance, and minor repairs on plantsystems and equipment housekeeping and decontamination.This is a new position, the current maintenanceorganization is discussed in FSAR Section 13.1.2.2.3.2and shown on FSAR Figure 13.1-6C.

1-13

1.2.2.1.1.4

Reporting to the Maintenance Manager areMechanical, Electrical, and InstrumentationControl supervisors and personnel.

Work Control Mana er

theand

The Work Control Manager is responsible for providinga planning and scheduling function which efficientlyutilizes the resources and the capabilities of theoperation, maintenance, radiation protection,chemistry and other work groups assigned to thisunit. This position is responsible for the technicalcontent of work control packages used in theperformance of maintenance tasks.

1.2.2.1.1.5 Radiation Protection Mana er

The Radiation Protection Manager is responsible to thePlant Manager for coordination, and conduct of theradiological protection programs in the unit.

1.2.2.1.1.6 Chemistr Mana er

The Chemistry Manager is responsible to the PlantManager for the coordination, and conduct ofchemistry, and radiochemistry programs. This is a newunit position developed from the existing unitChemistry Supervisor positions. These unit ChemistrySupervisor positions were previously matrixed to eachunit under direction of the Manager, Chemical Servicereporting to the Manager, Radiation Protection andChemistry 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 isresponsible for the onsite management of the Water ReclamationFacility, Central Outage Management, Central Maintenance,Radwaste Support, and Central Radiation Protection. (Refer toFigure 1-14). This position is assigned the responsibilitiesof the Vice President-Nuclear Production in the Vice President-Nuclear Productions absence.

1.2.2.2.1 Water Reclamation Facilit (WRF) Mana er

e

The WRF Manager is responsible for the maintenance andoperation of the WRF, as well as the incoming pipeline.This position coordinates these activities with the UnitOperations Manager. This is an existing position shown onthe current FSAR Figure 13.1-2 (i.e., Superintendent WaterReclamation).

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1.2.2.2.2 Outa e Mana ement Mana er

The Outage Management Manager is responsible to provide anintegrated outage schedule for both planned and unplannedoutages and an integrated schedule for modifications toensure proper work controls for the units. This is anexisting function at PVNGS.

1.2.2.2.3 Central Maintenance Mana er

The Central, Maintenance Manager is responsible to providemaintenance support'nd assistance to the Units.

Reporting to the Central Maintenance Manager are theMechanical Support, Electrical Support, Instrumentationand Control Support and the Station Services sections.The Station Services organization is responsible forproviding support services such as site building andgrounds maintenance.

1.2.2.2.4 Radwaste Su ort Mana er

The Radwaste Support Manager is responsible to providesupport of the power block radwaste activities. Thisposition provides radwaste activities that lend themselvesto centralization (e.g., data review and interpretation,laundering contaminated clothing, and radioactivematerials shipping and receiving). This is an existingfunction at PVNGS.

1.2.2.2.5 Central Radiation Protection Mana er

The Central Radiation Protection Manager is responsible toprovide support of the radiation protection activities.This position is to provide support to plant radiationprotection activities and conduct common radiationprotection functions that lend themselves tocentralization (e.g., dosimetry, ALARA reviews, andradiation protection instrumentation calibration andrepair). This is a new position.

1.2.2.3 Director, Standards and Technical Su ort

The Director, Standards and Technical Support is responsible tothe Vice President-Nuclear Production for the onsite technicalsupport required to ensure proper functioning of the nuclearplant. This position directs the Plant Standards and ControlManager, Engineering Evaluations Manager, Radiation Protectionand Chemistry Manager, and the Operations Computer SystemsManager in the performance of their duties. The ComplianceDepartment which provides compliance monitoring under theDirector, Nuclear Safety and Licensing, is matrixed to theDirector, Standards and Technical Support. (Refer to Figure1-15). 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 theDirector, Standards and Technical Support for onsiteengineering and technical work required for properoperation of the Units. He directs the supervisors of theonsite engineering sections in the performance of theirduties. This position is similar in function to theexisting Operations Engineering Manager discussed in thecurrent FSAR Section 13.1.2.2.2.1 and shown on FSAR Figure13.1-6A.

1.2.2.3.1.1 Reactor En ineerin Su ervisor

The Reactor Engineering Supervisor is responsible forcore monitoring and in-core fuel management programs.

This position coordinates with onsite operatingpersonnel and with offsite support organizations asnecessary in performing these functions. No changesare being made to this position. This is a previousposition discussed in the current FSAR Section13.1.2.2.2.1.1 and shown on Figure 13.1-6A under thepresent Manager, Operations Engineering.

1.2.2.3.1.2 Test En ineerin Su ervisor

The Test Engineering Supervisor is responsible to theEngineering Evaluations Manager for onsite engineeringtesting required by the Technical Specificationsincluding ILRT, LLRT, and ASME Section XI and theinservice inspection program. Personnel from theprevious Operations Engineering organization haveperformed these functions.

1.2.2.3.1.3 Shift Technical Advisor (STA) Su ervisor

The STA Supervisor is responsible to the EngineeringEvaluations Manager for providing Shift TechnicalAdvisors. However, the STA's will be matrixed to thePlant Managers and will receive their day to daydirection from the Plant Manager. No changes arebeing made to this function. (This position reportedto the Manager of Operations Engineering (FSAR Figure13.1-6A 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 toprovide engineering expertise in the operation andmaintenance of all major plant systems includingmonitoring and trending of system and componentperformance, and review of system performance during

1-16

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

1.2.2.3.1.4.1 Su ervisor of Station Statistics

The Supervisor of Station Statistics is responsibleto maintain station generating and performancestatistics to satisfy NRC, ACC and INPO statisticalrequirements including production of requiredreports.

1.2.2.3.2 0 erations Com uter S stems Mana er

The Operations Computer Systems Manager is responsible tothe Director, Standards and Technical Support forcoordinating onsite computer activities, includinghardware and software. No changes are being made to thisposition. (This position reported to the onsite TechnicalSupport Manager. Refer to the current FSAR Section13.1.2.2.2.1.3 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 isresponsible to the Director, Standards and TechnicalSupport for the site-wide preparation, coordination ofstation radiological protection, chemistry, andradiochemistry programs. This includes developing anoperating philosophy, procedures and proceduralstandardization for the site Radiation Protection andChemistry programs including maintaining occupationalradiation 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 positionsC.l.b.3.(g), (h), (i) and (j) since these activities areperformed by other positions. This function is somewhatsimilar to that of the previous Radiation Protection andChemistry Manager under the previous Director, TechnicalSupport. (Refer to the current FSAR Figure 13.1-6A andFSAR 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 fordeveloping operations and maintenance standards andensuring that the operating procedures and maintenanceprocedures used in the three Units are identical and to

1-17

ensure that they are applied uniformly. This is a newmanagement position developed to ensure consistency ofoperation and maintenance, by providing standardprocedures and to provide sharing of lessons learned amongthe 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 Selectionand Training, are used as the basis for establishing minimumqualifications for nuclear power plant personnel.

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

1-18

POSITION ANSI/ANS 3.1— POSITION(PARAGRAPH NO. )

Plant HanagerOperations Manager

Operations Support Supervisor

Shift Supervi,sorsAssistant Shift SupervisorsNuclear Operator IIINuclear Operators I & II

Unit Maintenance ManagerUnit I & C SupervisorUnit I & C TechnicianUnit Electrical Supervisor

ElectriciansUnit Mechanical Supervisor

MechanicsUnit Work Control ManagerUnit Radiation Protection Mgr.Unit Chemistry ManagerAssist. V.P.-Nuclear Production

SupportOutage Management ManagerI & C Support SupervisorElectrical Support Supervisor

Central Maintenance ManagerMechanical Support Supervisor

Station Services Supervisor

Radwaste Support ManagerCentral Rad. Prot. Mgr.Director, Standards & Tech.

SupportPlant Standards & Control Mgr.Engineering Evaluations Mgr.Operations Computer Systems Mgr.Radiation Protection & Chemistry

Mgr.Reactor Engineering Supervisor

Engineering & Construction DirectorEngineering Manager

Site Services DirectorSecurity ManagerTraining ManagerAdministrative Services Manager

Nuclear Safety & Licensing DirectorISEG Personnel

Plant Manager (4.2.,1)Operations Mgr. (4.2.2)Plant Mgr. Principal Alternate (4.2.1)Supervisor Requiring NRC License (4.3.1)Plant Operations Mgr. Principle Alternate(4.2.2)Supervisor Requiring NRC License (4.3.1)

Supervisor Requiring NRC License (4.3.1)Operators (Licensed) (4.5.1)Operator (Not Licensed)Maintenance Manager (4.2.3)I & C (4.4.2)Technician (4.5.2)

Supervisor Not Requiring NRC License(4.3.2)

Maintenance Personnel (4.5.3)Supervisor Not Requiring NRC License(4.3.2)Maintenance Personnel (4.5.3)

Mgr. Not Requiring NRC License (4.3.2)Radiation Protection (Note a)Chemistry & Radiochemistry (4.4.3)Technical Manager (4.2.4)

Mgr. Not Requiring NRC License (4.3.2)I&C (4.4.2)Supervisor Not Requiring NRC License(4.3.2)Maintenance Hgr. (4.2.3)

Supervisor Not Requiring NRC License(4.3.2)Supervisor Not Requiring NRC License(4.3.2)

Mgr. Not Requiring NRC License (4.3.2)Radiation Protection (Note a)Technical Manager (4.2.4)

Mgr. Not Requiring NRC License (4.3.2)Technical Manager (4.2.4)Mgr. Not Requiring NRC License (4.3.2)Radiation Protection (4.4.4)

Reactor Engineer (4.4.1)Engineer in Charge (4.2.4, 4.6.1)

Technical Manager (4.2.4)Mgr. Not Requiring NRC License (4.3.2)

Mgr. Not Requiring NRC License (4.3.2)Mgr. Not Requiring NRC License (4.3.2)Hgr. Not Requiring NRC License (4.3.2)

Mgr. Not Requiring NRC License (4.3.2)Note b

Quality Assurance DirectorQuality Assurance Managers

Quality Assurance (4.4.5)Quality Assurance (4.4.5) as defined inSection 1.1.3 of this description

1-19

NOTES:

a. The Central Radiation Protection Manager, and the Unit RadiationProtection Managers, shall have a minimum of five years experience inradiation protection at a nuclear facility. A minimum of two years ofthis five years experience should be related technical training butexception is taken to the degree requirement in ANSI/ANS 3.1 Section4.4.4. A maximum of four years of this five years experience may befulfilled by related technical or academic training. Two years of thisfive years experience shall be at a professional level.

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

1-20

1.3.2 Qualifications of Plant Personnel

Resumes of the appointees to key plant managerial positions areprovided in Attachment 2. Shift Supervisor level information hasbeen previously provided to NRC as part of operator licensing andis not included here.

1.4 Review and Audit

Operating phase activities that affect nuclear safety are reviewed andaudited. The review and audit program is implemented prior to initialfuel loading and ensures proper review and evaluation of proposedchanges, tests, experiments, and unplanned events. The programcomplies with the requirements of Paragraph 50.59 of 10CFR50 relatingto proposed changes, tests, and experiments and is conducted followingthe recommendations of Regulatory Guide 1.33, Quality AssuranceProgram Requirements (Operation), as discussed in Section 1.8. TheExecutive Vice President-ANPP has overall responsibility for safeoperation of PVNGS.

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

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

1.4.1 Onsite Review

Onsite review is performed by the Plant Review Board (PRB) whichhas the responsibility to review plant activities andadministrative controls as related to nuclear safety. A detaileddescription of the PRB is provided in the PVNGS TechnicalSpecifications as part of the description of administrativecontrols.

The PRB is composed of those individuals specified in the PVNGSTechnical Specifications. Collectively, they possess the type anddegree of expertise required to properly review proposed changes tosystems, procedures, tests, experiments, and unplanned events thateffect nuclear safety. The PRB meets at least once per calendarmonth and maintains written minutes of each meeting, which arereviewed by the Nuclear Safety Group.

1-21

Changes to the PRB representatives are being made as a result ofthis proposed PVNGS reorganization (Refer to the marked upTechnical 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 performsall-encompassing reviews to ensure the safe operation of PVNGSin accordance with License requirements. The NSG Managerreports to and advises the Director, Nuclear Safety andLicensing, who, in turn, reports to the Executive VicePresident-ANPP.

The Nuclear Safety Group is a staff organization composed of atleast four Nuclear Safety engineers and a Manager. Theirprimary function is to provide competent technical review ofplant operations to ensure nuclear safety. The NSG alsomaintains cognizance of QA audits and may utilize technicalspecialists from other APS organizations and outsideconsultants with expertise in special areas, as determinednecessary by the NSG Manager.

h

, The details of the function, composition, review and auditrequirements, authority, records and meeting frequency of NSGare described in the PVNGS Technical Specification, Section6.5.3.

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

1.4.2.2 Inde endent Safet En ineerin Grou (ISEG)

The review function of the ISEG is provided in the current FSARSection 18.I.B.1.2 and in PVNGS Technical Specification Section6.2.3. No changes are being made to this group's function.

The audit program is as described in FSAR Section 13.4.3. Nochanges are being made to this program.

1-22

CORPORATE COUNSEL CHAIRMAN,BOARD OF DIRECTORSCHIEF EXECUTIVEOFFICER

PUBLIC AFFAIRSMANAGER

FEDERALAFFAIRS

PRESIDENTCHIEF OPERATING OFFICER

CORPORATE FINANCEPLANNING8 CONTROL

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ARIZONANUCLEARPOWER PROJECTEXECUTIVE VICE

PRESIDENT

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EMPLOYEERELATIONS

VICE PRESIDENT

ENGINEERINGVICE PRESIDENT

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VICE PRESIDENT

VICE PRESIDENT& CONTROLLER

RATESVICE PRESIDENT

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TREASURER ANDASSISTANT SEC.

VICE PRESIDENTNUCLEAR

PRODUCTION

CUSTOMERSERVICES

STATE REGIONVICE PRESIDENT

CORPORATERELATIONS AND

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DIRECTORNUCLEARSAFETY

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6. 1 RESPONSI BILITY

6.1.1 Th~~~Plant Hanager shall be responsible for overall unit operationand shall delegate in writing the succession to this responsibility during hisabsence.

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

6. 2 ORGAN:ZATION

OFF SITE

6.2.1 The offsite organization for unit management and technical supportshall be as shown in Figure 6.2-1.

UNIT STAFF

6. 2.2. 1

C.

6. 2. 2. 2

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 shiftcrew composition shown in Table 6.2-1.At least one licensed Reactor Operatol shall be in the Control Roomwhen fuel is in the reactor. In addition, while the reactor is inHOG= 1, 2, 3, or 4, at least one licensed Senior Reactor Operatorshall be in the Control Room.

A radiation protection technician" shall be onsite when fuel is inthe reac or.All COR ALTERATIONS shall be observed and directly supervised byeither a licensed Senior Reactor Operator or Senior Reac or OperatorLimited to Fuel Handling who has no other concurrent responsibilitiesduring this operation.A site Fire Team of at least five members shall be maintained onsiteat all times". The Fire Team shall not include the Shift Supervisor,the STA, nor the 3 other members of the minimum shift crew necessaryfor safe shu down of the unit and any personnel required for otheressential func ions during a fire emergency.

The unit staff working hours shall be as follows:Administrative procedures shall be develt ped and implemented tolimit the working hours of uni t staff who perform safety-relatedfunctions; e.g., Senior Reactor Operators, Reactor Opera.ors,radiation protection technicians, auxiliary operators, and keymaintenance personnel.

"The radiation protection technician and Fire Team composition may be lessthan the minimum requirements for a period of time not to exceed 2 hours,in order to accommodate unexpected absence, provided immediate ac ion is takento fill the required positions.

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MANAGERPROCUREMENl

QUALIITY

MANAGERCOST &

SCI IEDULE

MANAGERNUCLEAR

FUEL

MANAGEAPARTICIPANT

SERVICES

MANAGEREMEAGENCY

PLAN 8

SERVICES

MANAGERMATERIALCONTROL

MANAGERADMIN.

SEAVICES

MANAGERLICENSING

SUPERVISORTfCI.INICAL

DATA

MANAGERCOMPLIANCE

MANAGERQUALITY/AUDITS

MONITORING

" MANAGERQUALITYCONTROL

OFFSITEORGANIZATION

Figure 6.2- l

PYHGS'LAtlT

'MANAGER

i~ r

1 ~'l

OUTAGENhtthGENEHT

NAHAGER

CIRIICALS PORT

NA GER

OP ERATIOHSNAIIAGER

NAIIITBIAHCENAtlAGER

P T SERVICESNAHAGER

MANAGERCONPL IhflCE

MAIIAGEROPS EIIGlttEERltt0

SUPERIHTEHOEIITUNIT I

SUPERIHTEH TIIC NAHI lAIICE

MAIIAGEROPER AT IOHS

SECURITY

SUPERVISORSTA

SUPERltlTEHOEHTUNIT 2

SUPERItlTEHDEHTNCC

SUPERVISOR

FIRE PROTECTIOH

NAIIAGERRAO. PROT. 1 CIIEN.

S RIHTEtlOEHTlllT 3

SUPERIHTBIOEHTELEC. NAIHTEHAtlCE

SUPERIHTEIIOE1OPS CONPI R

SYS N

SUPERVISOROPERATIOllS SUPPOR

SUPERIHTBIOEHTSTATIOH SERVICES

SUPERIltTEtlOBITNEClfhtllCAL

NhlttT Et!At ICE

F IGURE 6. 2-2

OHS17E OnGnnllRT10H

Co

VICE PRESIDENTNUCLCAR

PRODUCTION

PLANTMANAGERUNIT 1

PLANTMANAGERUNIT2

PLANTMANAGERUNIT3

ASSISTANTVICE PRESIDENTNUCL'EAR PROD.

SUPPORT

DIACCTORSTANDARDS &

TECII. SUPPORT

OPERATIONSMANAGER

OPERATIONSMANAGER

OPERATIONSMANAGER

WATER AEC.FACILITY

MANAGER .

PLANT STAN. SUPCAVISOAOAADS & CONT. OPERATIONS

MANAGER STtlOS.

MAINTENANCEMANAGER

MAINTENANCEMANAGER

MAINTENANCEh4NAGER

OUTAGEMANAGEMENT

MANAGFR


MANAGER

SUPERVISORMECII. IAAlkIT.

STNQS.

WORKCONTROLMANAGER

RADIATIONPROTECTION

MANAGER

WORKCONTROLMANAGER

RADIATIONPROTECTION

MANAGER

WORKCONTROLMANAGER

RADIATIONPROTECTION

MANAGER

CENTRALMAINTENANCC

MANAGER


OPCRATIONSCOMPUTER SYS

MANAGER

RADIATIONPROTECTION &

CklEMISTAYMANAGER

SUP EAVISORELEC. h1AINT.

STNOS.

SUPCAVISOAl&C STt<OS.

Ck IEhllSTRYMANAGER

Cl IEMISTRYMANAGER

CHEMISTRYMANAGER

CENTRALRADIATION

PROTECTIONMANAGER

COMPLIANCE

"LOCATED OFFSJTE

0NSITEORGANIZATION

Figure 6.2-'2

J ~

~

I'ABLE

6. 2-1

MIHIMUM SHIFT CREW COMPOSITIOH

lou e ough>

7(ic~ P~S~

POSITIOH HUMBER OF IHDIVIDUALS REQUIRED TO FILL POSITION

SSSRO

RO

AOSTA

MODE 1, 2, 3, OR 4

11221

MODE 5 OR 6

1Hone11Hone

SS — Shift Supervisor with a Senior Reactor Operators LicenseSRO - Individual with a Senior Reactor Operators LicenseRO — Individual with a Reactor Operators LicenseAO — Huclear Operator I or IISTA - Shift Technical Advi.sor

Except for the Shift Supervisor, the Shift Crew Composition may be one lessthan the minimum requi rements of Table 6. 2-1 for a period of time not toexceed 2 hours in order to accommodate unexpected absence of on-duty shifcrew members provided immediate action is taken to restore the Shift CrewComposition to,within the minimum requirements of Table 6.2-1. This provisiondoes not permit any shift crew position to be unmanned upon shift change dueto an oncoming shift crewman being late or absent.

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

PALO VERDE " UHIT 1 6-5

CQMTRGELED BV USEPAOt)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 sourcesoi plant design and ooerating experience information, including plants oisinilar design, which may indicate areas for improving plant saiety.

COt,1POS ITIOH

6.2.3.2 The IS=G shall oe comoosed oi at least five, dedicated, full-timeengineers located on site. Each shall have a Bachelor's Degree in engineeringor related science and at least two years professional level experience in hisfield.

RESPONSIBIL TIES

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

Q>reckon,Auc4n.r Mdg G<dAUTHORITY

6.2.3.4 The ISFG shall make detaile recommendations for revised procedures,equipment modifications, maintenance ctiviiies, operations „aciiviiies or othermeans oi improving plant safety to the .... ', ~4- PlantHanager, and the~~~~r, Nuclear Saiety Group (HSG).

61ag~~ pRECORDS

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«<~ '~J6.2.4 SHIFT TECHNICAL ADVISOR

6.2.4.1 The Shiit Technical Advisor (STA) shall provide advisory technicalsuoport to the Shift Supervisor in the areas of thermal hydraulics, reactorengineering, 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 ihin10 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 theRadiation Protection and Chemistry t1anager who shall meet or exceed the qualifi-cations of Regulatory Guide 1.8, September 1975, and the Shift Technic'.1 Advisorwho shall have a bachelor's degree or equivalent in a scientific or engineeringdiscip)ine with specific iraining in plant design and plant operating character-istics, including ransients and accidents.

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

PALO VERDE - UNIT 1 6 6

~~r,. r~~~ r r r ~ ~~~ ~ e~s r.

COMTRGLI.t-:D BV USER

ADMINISTRATIVE CONTROLS

6.4 TRAINING)] <Qf Q,fe

ZQI"vlcE3'.4.

1 A training program for the unit staff shall be maintained under thedirection of the or his designerand shall meet or exceed the requirements and recommendations of Section 5.0 iAHS 3. 1-1978 and Appendix A of 10 CFR Part'55 and the supplemental requirementspecified in Sections A and C of Enclosure 1 of the March 28, 1980 NRC letterto,all licensees, and shall include familiarization with relevant industryoperational experience.

6. 5 REVIEW AHD AUDIT

6. 5. 1 PLANT REVIEM BOARD PRB)

FUNCTIONI

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

- COMPOS ITIOH

6.5. 1.2 The PRB shall be composed of the following personnel:wlcdi8r<.'ifdqua +«~>

Hember: ManagerMember: Operati ons-b4eager- W<~~<~~Member: /Pl'.cfiaaiag ~ Hai ntenance 44eager—>~~~+<<~~ ~/<I ~'~ ~Hember:Member: ~/dcddccoc- pgydkfag4eeAeg-Manager- 4+oudorgs 5"i'E'Eve'o~

Hember:/Pig@'o f~

Member: STA SupervisorMember. d JMember: Radiation Protection and Chemistry ManagerHember: 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 themembers 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 Chairmarto serve on a temporary basis; however, no more than two alternates shallparticipate 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 convenedby the PRB Chairman, Vice-Chairmen, or his designated alternate.

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

CGNTRGILLED BY USERAOMIHI STRATI VE COHTRQLS

OUORUM

6.5.1.5 The quorum of the PRB necessary for the performance of thePRB responsibility and authority provisions of these Technical Specificationsshall consist of the Chairman, Vice-Chairmen, or his designated alternate andfive members including alternates.

RESPONSIBILITIES

6.5.1.6 The PRB shall be responsible for:'a ~

b.

C.

d.

Review of all administrative control procedures and changes.

Review of all proposed changes to Appendix "A" Technical Specifications.Investigation of all violations of the Technical Specificationsincluding the preparation and forwarding of reports covering evalua-tion and recommendations to prevent recurrence to the Huclear SafetyGroup (HSG).

Review of REPORTABLE EVEHTS r equiring 24-hour written notification tothe Commission.

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

g

Performance of special "reviews, investigations or analyses and reportsthereon as requested by th~(c.e. Pres(~'pic A - Alael~n< HdCEvc Pld +

Review and documentation or judgment concerning prolonged operationin bypass, channel trip, and/or .repair of defective protectionchannels of process variables placed ih bypass since the last PRBmeeting.

AUTHORITY ..6.5.1.7 The PRB shall:

'a ~

b.

Render determinations in writing with regard to whether or not eachitem considered under Specification 6.5. 1.6c. above constitutes anunreviewed safety question.

Provide written noti~f ca<ion within 24 hours to the Vice President-Huclear Production, MRW='~t Manager and HSG of disagreementbetween the PRB and the(AREBB'lant Manager; however, the4%R~~Plant Manager shall have responsibility for resolution of~suedisagreements pursuant to Specification 6. l. 1 above.

PALO VEROE - UNIT 1 6-8

P

CONTPOLLED B~ USERADMINISTRATIVE CONTROLS

RECORDS

6.5. 1.8 The PRB shall maintain written minutes of each PR8 meeting that, at aminimum, document the results of all PRB activities performed under the responsi-bility and authorit visions of these Technical Specifications. Copies shallbe provided to the ..' Plant t1anager and HSG.V6 5 ~ 2 TECilHICAL REVIEM AND CONTROL $ Qj<g Pjg+>g<gf /I/pp/p<p Pjgp(PppQACTIVITIES

Q;qq /gal Q+cr. '(go ck cL~cl Rckh L, S P~+6.5.2. 1 The .. . Ashall assure that each procedure and programrequired by Specification 6.8 anK other proceed res uhich affect nuclear safety,and changes thereto, is prepared by a qualified individual/organization. Eachsuch procedure, and changes thereto, shall be reviewed by an individual/groupother than the individual/group which prepared the procedure, or changesthereto, but who may be from the same organization as the, individual/groupwhich prepared the procedure, or changes thereto.

gvn.>ua+ra<S ~aug~~ Q ic-ec.%0<A Ma<der d~ ~"JG~6.5.2.2 hase I - IV tes s described in the FSAR that are performed bv theplant operat)ons staff shall be approved by th t~~ 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.I6.5.2.3 Proposed modifications to unit nuclear safety-related structures, systemsand components shall be designed by a qualified individual/organization. Eachsuch modification shall be reviewed by an individual/group other than theindividual/group which designed the modification, but who may be rrom the sameorganization as the individual/group which designed the modi iication. Proposedmodifications to nuclear safety-related structures, systems and components snailt

p

a

cbe ap roved prior to implementation by the ~~ Plani Hapn'ger>or @ "he~,~

Techni cg Suppor< as previously desi gnated by hep,. ~ ~Di~eckoP < 5+aNdcrdc a~el AVUear Qt Cd'k<or4.6-5.2.4 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, previouslydesignated by the '

o perform such reviews. Each such revi ewshall include a determination of whether r not additional, cross-disciplinary,review is necessary. If deemed necessary, uch review shall be perrormed bythe appropriate designated review personnel. Vice>rcsic4~j-)4~cleat Prcctdcfionl

6.5.2.5 Proposed tests and experiments which affect station nuclear safety andare not'addressed in ihe FSAR or Technical Specifications shall be reviewedby the ~ I ~ ~ a ~ ) i I ~ I I ~ ~ I 0 Q4V ) v1 ra-

e ~Q,gc QfpQ~+QQ guc)~r Pj agvc ttQ ~

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

Q iree bGr, G. l.e 5 erv hem6.5.2.7 The s! >tion emergency plan and implementing rocedures shall bereviewed. Recommended changes shall be approved by the

9'rcd ~c.k.(oa6.5.2.8 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 ofreports covering the evaluation, recommendations and disposition of the cor-rec ive acr.ion t.o prevent. recurrence>

D 1TQc+a) 6 rU(fell d5 Cth3d Wc I 4<<<< ~ ~~I 9"+ ~

PALO VERDE - UNIT 1 6-9

~~

ADMIHISTRATIVE CONTROLS

g~~o'araS awTE"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"plannedAl 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 beprovided to th . . ~ and the Nuclear Safety Group.

V Icc PIPssc e4/v -Aldcleur,' rcc7Ucbic'<6.5.3 NUCLEAR SAFETY GROUP (HSG)

FUNCTION

6.5: 3. 1 The HSG shall function to provide independent review and shall beresponsible for the audit of designated activi ties in the areas of:

a. nuclear power plant operationsb. nuclear engineeringc. chemistry and radiochemistryd. metallurgye. instrumentation and controlf. radiological safetyg. mechanical and electrical engineeringh. quality assurance practices

COllPOSITIOH

four staff spe-Engineering or theexperience in the

ield. The HSG

ial exoerience.ng requirements:

cialists. The ~~ shall have a Bachelor's Degree inPhysical Sciences. He will also have a minimum of :0 vearspower field with at least 3 of those years in the nuclear f

i»Each staff specialist will have at least one of the followi

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 NuclearGenera ing Station.

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

CONSULTANTSp

Ig(+$ g6.5.3.3 Consultants shall be utilized as determined by the NSG<~~~ toprovide expert advice to the HSG.

RP! IcM

6.5.3.4 The NSG shall revie~:

a. The safety evaluations program and i's implemen"a ion for (1) chancesto procedures, equioment, sys-ems or facilities within the power block,and (2) tests or experimen-s comoleted under the provision of10 CFR 50. 59, to verify that such ac=ions did no cons itute anunreviewed safety question;

PALO VERDE - UNIT I 6-10p„p~~ ~i f'i ~~~ ~ y pt ye Ir ~ Twas ~

CQMTRGLL.ED BY USERADt1IHISTRATIVE CONTROLS

R":~!.EW (Continued

b. Proposed changes to procedures, equipment, systems or facilitieswithin the power block which involve an unreviewed safety questionas defined in 10 CFR 50. 59;

C. Proposed tests or experimen s which involve an unreviewed safetyquestion as defined in 10 CFR 50.59;

Proposed changes to Technical Specifications or this OperatingLicense;

Viola ions of codes, regulations, orders, Technical Specifications,license requirements, or of internal procedures or instructionshaving nuclear safety significance;

Significant operating abnormalities or deviations from normal andexpected performance of unit equipmen+ that affec nuclear safety;

g. All REPORTABLE EVENTS requiring 24 hours written notification;

All recognized indications of an unanticipated deficiency in someaspect of design or operation of structures, systems, or componentsthat 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 ofthe HSG. These audits shall encomoass:

a. The conformance of unit operation to provisions contained within theTechnical Specifications and applicable license conditions at leastonce 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 inunit equipment, structures, systems, or method of opera'on thataffect nuclear safety at leas once per 6 months.

The performance of activities required by the Opera ional equalityAssurance 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 implementingprocedures at least once per 24 months by qualified licensee gApersonnel.

PALO VERDE

CGNTRQLLED BY USI=P-

A01ilNISTRATIVE CONTROLS

AUDITS (Continued}

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

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

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

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

k. The performance of activities required by the Operations guali tyAssurance Criteria manual to meet the provisions of RegulatoryGuide 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 proceduresat least once per 24 months.

AUTHORITY

6.5.3.6 The HSG shall reportthose areas of responsibi li .y

RECOROS

irecSr gmbenrha64q aV~ Lice+ i~to and advise the . . . . 'n

fe

specified in Specifications 5.5.3.4 and 5.5.3.5.

b<ec'Sac>h4c4ar Q4Q Qui~ L <8~

6.S.3.7 Records of HSG activities shall be prepared and maintained. Report ofreviews and audits shall be prepared monthly for thewho will distribute it to he Vice President-Huclear Proauction~~~ PlantHanager, 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:

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

lAaeo~er

b. Each REPORTABLE EVEHT requiring 24 hours written notification shallbe reviewed bv the PPB, and he results of this review shall besu ml ted to the 'iHuclear Safety Group and the VicePresident"Nuclear Produc ion.

PALO VERDE - UNIT 1 6-'2

CGÃ7RGLLEG B'f USERADMINISTRATIVE CONTROLS

6.7 SAFETY LIMIT VIOLATION

6.7.1 The following actions shall be taken in the event a Safety Limit isviolated:

a.

b.

The NRC Operations Center shall be notified by telephone as soon'spossible and 'l cases within 1 hour. The Vice President-Nuclear

Group shall be notified within 24 hours.

A Safety Limit Violation Report shall be prepared. The report shallbe reviewed by the PRB. This report shall describe (1) applicablecircumstances preceding the violation, (2) effects of the violationupon facility components, systems, or structures, and (3) correctiveaction taken to prevent recurrence.

c. The Safety Limit Violation Report shall be submitted to the5%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 authorizedby the Commi ss ion.

6.8 PROCEDURES AND PROGRAMS

6.8. 1 Mritten procedures shall be established, implemented, and maintainedcovering the activities referenced below:

a. The applicable procedures recommended in Appendix A of RegulatoryGuide 1.33, Revision 2, February 1978, and those required forimplementing 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 informationobtained through the Plant Computer - CPC data link shall not be made withoutprior 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 1974and 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 USERADMI HI STRATIVE CONTROLS

HOT=: The licensee shall perform a secondary water chemistry monitoring andcontrol 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 throuchoutthe life of the plant in accordance with the program presented in Table 2. 5-i 8of the PVNGS FSAR or another HRC approved program.

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

p. Fuel Assemoly Surveillance Program ImplementationNOTE: 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 edHovember 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,shall be reviewed as soeciried in oecification 6.5 and aporoved prior oimplementation. Programs, adminis "ative control procedures and implementingprocedures shall be approved by the,„... or desicna ec al erna-ewho is at supervisory level or above. 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 bemade provided:

C.

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 ShiftSupervisor with an SRO on the affected unit. > r < ~ . , c.

DIr<r,~w. DfcraArid5 awd TcI«"CThe 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 ofimplementation. s c&Q8 /U„'c'Qy'~ac,/zan;u

6 8 4 The following procrams shall be establi shed implemented main ained andshall 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 outsidecontainment that could con-ain hiohly radioactive fluids during aserious rarsient or ac icent :o as low as practical levels. Thesystems include the recirculation portion of the high pressure saretyinjec:ion system, the shutdown cooling por.ion of the low pressuresafety 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 heavyuse of overtime. The objective shall be to have operating personnelwork a nominal 40-hour week while the plant is operating. However,in the event that unforeseen problems require substantial amounts ofovertime 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 hoursstraight, excluding shift turnover time.

2) An individual should not be permitted to work more than ~6 hoursin any 24-.nour period, nor more than 24 hours in any 48-hourperiod, nor more than 72 hours in any 7-day period, allexcluding shift turnover time.

3) A break of at least 8 hours should be allowed between workperiods, including shift turnover time.

4) Except during extended shutdown periods, the use of overtimeshould be considered on an individual basis and not fo1 theentire staff on a shift.

c. Any deviation from the~boge guidelines shall be authorized by thePlant Manager or'esignee who is at supervisory level or

above, or higher levels of management, in accordance with establisnedprocedures and with documentation of the basis for granting thedeviation. Controls shall be included in the procedures such thatindividual overtime hall be reviewed monthly by

+I i H

assigned. Routine deviation from the above guide ines is notauthorized.

/0 JIM'<p I a~eh~+ oAv zlh/C~r v'iduols d4

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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 operationand shall delegate in writing the succession to this responsib:lity during hisabsence.

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

.6. 2 ORGANIZATION

OFFSITE

6.2.1 The offsite organization ior unit management and technical suoportshall be as shown in Figure 6.2-1.

UNIT STAFF

6.2.2.1a.

b.

d.

e.

6.2.2.2a ~

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

Each on-auty shift snail be composed oi at least the minimum shiitcrew composition shown fn Table 6.2-1.At least one licensed Reactor Operator shall be in the Comrol Roomwhen iuel is in the reactor. In addition, while the reactor is inttODE 1, 2, 3, or 4, at least one licensed Senior Reac=or Coeratorshall be in the Control Room.

A radiation protection technician" shall be ons ite wren iuel is inthe reac.or.All CORE ALTERATIONS shall be observed and directly s"per.ised byeither a licensed Senior Reactor Operator or Senior Reactor OperatorLimited .o Fuel Handling who has no other concurrent responsibilitiesduring this operation.A site Fire Team of at least five memoers shall .be maintained onsiteat all times". The Fire Team shall not include the Shift Supervisor,the STA, nor the 3 other membens of the minimum shift crew necessaryfor safe shutdown oi the unit and any personnel required for otheressential functions during a fire emergency.

The unit staff working hours shall be as follows:Administrative procedures shall be developed and implemented to limitthe 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 lessthan th'e minimum requi rements for a period of time not to exceed 2 hour s,in order to accommodate unexpected absence, provided immediate action is takento fill the required positions.

pAlo veRDp - ugE>QI ITRGLK~D BY USER

CQMTRGLLED BV USERAOMINISTRATIYE CONTROLS

UNIT STAFF (Continued)

b. Adequate shift coverage shall be maintained without routine heavyuse of overtime. The objective shall be to have operating personnelwork a nominal 40-hour week while the plant is operating. However,in the event that unforeseen problems require substantial amounts ofovertime 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 hoursstraight, excluding shift turnover time.

2) An individual should not be permitted to work more than 16 hoursin any 24-hour period, nor more than 24. hours in any 48-hourperiod, nor more than 72 hours in any 7-day period, allexcluding shift turnover time.


4) Except during extended shutdown periods, the use of overtimeshould. be considered on an individual basis and not for theentire staff on a shift.

. +3~imc. Any deviation from the above guidelines snail be authorized by the„

PVHSS Plant Ma|lager or 'esignees who are at the manager level orabove, or higher levels of managemen~, in accordance with establishedprocedures and with documentation of the "asis for granting thedeviation. Controls shall be included in the procedures such that

g)z<<~ ~~~~~h+s- des nee to assure that excessive hours have not beenassigned. Routin deviation from the above guid lines is notauthorized.

j /LJ +het 2 / 8>pG'A~~ f@4Vp~

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

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

EXECUTIVE V.P.

V.P.HUCLEAR

PROOUCTIOtl

ASST.V.P. NUCLEARI ROOUCTION

+PVtlGS

P A/IT MAtlAGER

MGR.HUCL'EAR SAFETY

ISEG/HSG

OIR.TECHNICAL SE ICES

OIR.CORPORATE OA

MGR.EMERGEtlCY PLAN

MGR.OPERATIONS

MGR.. TRAHSITIOH

MGR.HUCLEAR 'EtlGIHEERIHG


MGR.ADLItttISTRATIVE

SERVICES

MGR.MAItlTEHAHCE

+MGR.

tlUCLEAR CotlSTRUCTIOH

MGR.OUALITY SYSTEMS/

ENGltlEERltlG

MGR.TRAINItlG

MGR.OUTAGE

MAHAGEMEHT

MGR.U LEAR FUELS

MGR.PROCUREMENT OUALITY.

HRFSUP ER ItlT EHOEtlT

GR.PL T SERVICES

MGR. RECOROSMGR.

OUALITY AUOITS/MOHITORltlG

MGR.TECIINICAL SUPPORT

MGR. LICEHSIHG MG

OllALITYCO OL

~ LOCATEO ONSITE

MAtlAGERCOMPLIANCE

FIGURE 6.2-1

OFFSITE ORGANIZATION

5/eA a Ere/.~~it/( . A/>~ ~Jr/z~

ESIOKtlT

(mA7CDm

EXECUTIVE V.P.

V.P.NUCLEAR

PRODUCTION

ASST.V.P. ttUCLEARPRODUCTION

MGR,EhtERGEttCY PLAH

MGR. +

AOMlttlSTRATIVESERVICES

MGR.TRafttlttG

PVHGSP AQT MAIIAGER

MGR.OPERATIONS

MGR.MAINTENANCE

MGR.OUTAGE

MAHAGEhlEHT

MGR.HUCLEAR SAFETY

ISED/HSG

MGR.. TRAHSITIOH

OIR.TECHNICAL S ICES

MGR.ttUCLEAR EHGLNEERIHG

+hlGR.

IIUCLEAR COttSTRUCTION

MGR.t U LEAR FUELS

OIR.CORPORATE OA


MGR.DUALITYSYSTEMS/

EHGlttEERIHG

MGR.PROCUREMEttT QUALITY.

OQz

0

CI

N

ZJ

HRFSUPERlltTEtlOEttT

GR.

PL T SERVICESMGR. RECORDS

MGR.QUALITY AUDITS/

MONITORlttG

mrC)

m ~ LOCATED OWSITE

MGR.TECIINICAL SUPPORT

MANAGERCOMPLlAIICE

FIGURE 6.2-1

OFFSITE ORGANIZATION

MGR. L)CEHSlttG MG

QUALITY CO OL

PRESIDENT 8,

CI IIEF OPERATINGOFFICER

';OCATEO OlJSI TE EXECUTIVEVICE PRESIDENT

VlCC PAESIDEtlTNUCLEAR

PRODUCTION

DIRECTORENGINEERING 8

CONSTRUCTION


OIAECTORNUCLEARSAFETY

8 LICENSING

DIRECTORQUALITY

ASSURANCE

MANAGERENGINEERING

MANAGERSECURITY


MANAGER'UALITYSYS.

ENGINEERING

MANAGERCONSlTIUCTION

MANAGERTRAIIIING

MANAGERISEG

MANAGERPROCUREMENl

QUALIITY

MANAGERCOST 8

SCI IEDULE

MANAGER.NUCLEAR

I'UEL

MANAGERPAA'I'ICIPANT

SLI'IVICES

MANAGEREMERGENCY

PLAN 8

SERVICES

MANAGERMATERIALCONTROL

MANAGERADMIN.

SEAVICES

MANAGERLICENSING

SUPERVISORTECI.INICAL

DATA

MANAGERCOMPLIANCE

MANAGERQUALITY/AUDITS

MONITORING

MANAGERQUALITYCONTROL

OFFSITEORGANIZMION

Figure 6.2-1

ICD

Pep/~cp ~sr'r( u~D8/pq/Q ~ PVHGS

PLAIITMAtIAGER

a. ~ ~l

OUTAGELIAHAGEIIEHT

MAHAGCR

TEClltIICALSUPPORT

MAtIAGER

OPERATIOtISWAIIAGER

MAltITBIAHCEWAHAGER

AHT SERVICESMAItAGER

LIAIIAGERCOWPL IAtICE

MAHAGEROPS EttG)IIEERIHO

SUPERV)SORSTA

MAtIAGERRAO. PROT. 4 CHELI.

SUPERIIITBIOEHTUHIT I

SUPERIIITEtIOBITUHIT Z

PERltITEHOBITUHIT 3

SUPERIHTEJIIIEHTILC M/AI HEHAHCE

SUPERltITEHOEHTMCC

SUPERIHTEIIOEtITELEC. MAIIITEHAtICE

MAHAGEROPERATIOIIS

SECURITY

SUPERVISORFIRE PROTECTIOII

OOzXl.OI

mUW

XI

SIIPERIHT5HbBITOl'S )OIIPIITER~SYSTEM

SUPERVISOROPERATIOIIS SUPPORT

SIIPERIHTEIIOEIITSTATIOH SERVICE%

&1

C3

Dl

CD FIGURE 6. 2-2

OnSITE ORC~NIZnTIOu

SUPERlttTBIOEHTL[ECHAHICAL

WAIHTEHAHCE0

CD

VllACA)

v(CE PRESIDENTNUCLEAR

PRODUCTION

PLANTMANAGERUNIT I

PLANTMANAGERUNIT2

PLANTMANAGERUNIT3

ASSISTANTVICE PRESIDENTNUCI.EAR PROD.

SUPPORT

DIRECTORSTANDARDS tt

TECH. SUPPORT

OPERATIONSMANAGER

MAINTENANCEMANAGER

WORKCONTROLMANAGER

RADIATIONPAOTECTION

MAtIAGEA

OPERATIONSMANAGER

MAINTENANCEMANAGER

WORKCONTROLMANAGER

RADIATIONPROTECTtON

MANAGER

OPERATIONSMANAGER

MAINTENANCEM<tINAGER

WORKCONTROLMANAGER

RADIATIONPROTECTION

MANAGER

WATER AEC.FACILITY

MANAGER

OUTAGEMANAGEMENT

MANAGER

CENTRALMAINTENANCE

MANAGER

RAOWASTESUPPORTMANAGER

PLANTSTAN.DAADS 6 CONT.

MANAGER

ENGINEEAINGEVALUATIONS

MANAGER


MANAGER

RADIATIOt<PROTECTION 8

CI IEMISTAYMANAGER

SUPP AVISOflOPEAATIOIIS

STtIOS.

SUPERVISORMEC) I. I.IAItIT.

STNDS.

SUPERVISORELEC. MhlttT.

STNOS.

SUPEA VISOA18C STNOS.

CIIEMISTRYt IAt<AGEA

Cl-IEMISTRYMANAGER

CHEMISTRYMANAGER

CENTRALRADIATION

PROTECTIONMANAGER

COMPLIANCE

"LOCATED OFFSXTE

ONSITE<ORGANIZATION

Figurc 6.2-2

CGNYRGLLED BY USERgg C,'o.iJ p5

TABLE 6.2-1TIA<5 P'

MINIMUM SHIFT CREM COMPOSITION

POSITION NUMBER OF INDIVIDUALS REQUIRED TO, ILI POSITION

SS

SRO

RO

AO

STA

MODE 1, 2, 3, OR 4 MODE 5 OR 6

1None1J

1Hone

SS - Shift Supervisor with a Senior Reactor Operators LicenseSRO - Individual with a Senior Reactor Operators LicenseRO - Individual with a Reactor Operators LicenseAO - Nuclear Operator I or IISTA - Shift Technical Advisor

The Shift Crew Composition may be one less than the minimum requirements ofTable 6.2-1 for a period of time not to exceed 2 hours in order to accommodateunexpected absence of on-duty shift crew members provided immediate action istaken to restore the Shift Crew Composition to within the minimum requirementsof Table 6.2"1. This. provision does not permit any shift crew position to beunmanned upon shift change due to an oncoming shift crewman being late orabsent.

During any absence of the Shift Supervisor from the Control Room while theunit is in MODE 1, 2, 3, or 4, an individual with a valid Senior Operatorlicense shall be designated to assume the Control Room command function.During any absence of the Shift Supervisor from the Control Room while theunit is in MODE 5 or 6, an individuaT with a valid Senior Operator or Operatorlicense shall be designated to assume the Control Room command function.

PALQ vERDE - Utgjgl LITQ[QLLPB BY USER

if

CC)MYROLLED BY USiER


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 sourcesof plant design and operating experience information, including plants ofsimilar 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-timeengineers located on site. Each shall have a Bachelor's Degree in engineeringor related science and at least two years professional level experience in hisfield.

RESPONSIBILITIES

6.2.3.3 The ISEG shall be responsible for maintaining surveillance of plantactivities to provide independent verification" that these activities areperformed correctly to reduce human errors as much as practical, and to detectpotential nuclear safety hazards.

gfJgldad Safe/ Q,<jj grceeis ujAUTHORI f Y

~ '

~

~

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

RECORDS >I~~~g ~

6.2.3.5 Records of activities performed by the ISEG shall be prepared, main-d, «d d

6. 2. 4 SHIFT TECHNICAL ADVISOR

6.2.4.1 The Shift Technical Advisor (STA) shall provide advisory technicalsupport to the Shift Supervisor in the areas of thermal hydraulics, reactorengineering, 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 within10 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 theRadiation Protection and Chemistry Manager who shall meet or exceed the qualifi-cations of Regulatory Guide 1.8, September 1975, and the Shift Technical Advisorwho shall have a bachelor's degree or equivalent in a scientific or engineeringdiscipline 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 WYRGLLED 8 i( USERADMINISTRATIVE CONTROLS

6. 4 TRAINING I)<rema., SL&e SeMtc< s

6.4.1 A trainin program for the unit staff shall be maintained under thedi i f tt A 'M or his designeeand shall'meet or exceed the requirements and recommendations of Section 5.0 ofANS 3. 1-1978 and Appendix A of 10 CFR Part 55 and the supplemental requirementsspecified in Sections A and C of Enclosure 1 of the March 28, 1980 NRC letterto all licensees, and shall include familiarization with relevant industryoperational 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 Manageron 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: ManagerMember: Operations &sacer- ~W~Aio«~+ ~"i '"~'~'~Member ~louie~~ Maintenance Haaager ~4«a>~~> ~</«<'~~Member:Member +p hicuc god&~ anager ~~» 4 ~~~

M b: Qp ti «~ f lilt.l,llit2,3 . f)'/otiose E'.8 ~

Member: STA SupervisorMember: .roc~ ss.~Member: Radiati'on Protection and Chemistry ManagerMember: quality Systems/Engineering Manager

i Vice /rPsicle~f - pgcfeo~ po6'ee,/~adThe%I/465-Reneger-shall designate the Chairman and Vice-Chairmenin writing. The Chairman and Vice-Chairmen may be from outside themembers 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 Chairmanto serve on a temporary basis; however, no more than two alternates shallparticipate as voting members in PRB activities at any one time.

MEETING FREQUENCY


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

I GNTRGLLED BY USERADt1INISTRATIVE CONTROLS

QUORUM

6 ~ 5.1.5 The quorum of the PRB necessary for the performance of thePRB respons)bility and authority provisions of these Technical Specificationsshall consist of the Chairman, Yice-Chairmen, or his designated alternate andfive members including alternates.

RESPONSIBILITIES

6.5.1.6 The PRB shall be responsible for:

a.

b.

C.


Review of all proposed changes to Appendix "A" Technical Specification

Investigation of all violations of the Technical Specificationsincluding the preparation and forwarding of reports covering evalua-tion and recommendations to prevent recurrence to'he Nuclear SafetyGroup (NSG).

'.

Review of REPORTABLE EYENTS.

e.

g.

Review of unit operations to detect potential nuclear safety hazards.

s'erformanceof special reviews, .investigations or analyses and reportsthereon as requested by ther

Q ~Ce, reSil~et- /Uu'Cfedf/ PfC)gdQ7c'0 4Review and documentation of judgment concerning prolonged opera-ionin bypass, channel trip, and/or repair of defective protectionchannels of process variables placed in bypass since he last PRB

meeting.

AUTHORITY

6. 5.1. 7 The PRB sha 1 1:

a 4 Render determinations in writing with regard to whether or not eachitem considered under Specification 6.5.1.6c. above constitutes anunreviewed safety question.

b. provide written notification within 24 hours to the Vice president-Ruclear Product.ion --agt Manager and MRG of disagre esttbetween the PRB and theiRUU~8$ Plant Manager; however, thePlant Manager shall have responsibility for resolution of sucdisagreements 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-

bilityy

and authority~rovisions of these Technical Specifications. Copies shallbe provided to the(MMES Plant, Manager,iand NSG.

r'-V« ~ /Pe si f.h-.v'I - iVdclP~q

PALO vERDE - URI1'QPITQic(]gQ Bs'f uS1C

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. Eachsuch procedure, and changes thereto, shall be reviewed by an individual/groupother than the individual/group which prepared the procedure, or changesthereto, but who may be from the same organization as the individual/groupwhich 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 theplant operations sta e approved by the Henag~ Technical Support

b R~ 1ggl g d 1 lyd lg dby gggggdggimager. Test results shall be approved by the

Up~~ ~DdnCfnd,5+dyudaygdS dy& Zee(PCoC S~'.PPZ 'FrA-tliP Fug~in/eeet Eigalva F~ r$1awagp'W ~

6.S.2.3 Proposed modifications to unit nuclear safety-related structures, systerand components shall be designed by a qualified individual/organization. Eachsuch modification shall be reviewed by an individual/group other than the

'ndividual/groupwhich designed the modification, but who may be from the same .

organization as the individual/group which designed the modification. Proposeamodifications to nuclear safety-related str uZes, systems and comoonents shall.be a roved prior to implementation by th 'Pla t ga gr.~ p~)Pp„z g~«r.

Techgicpl Support as previously designated b Eh'ger.JI(YCtG>d BfadGfttr<85 QVg I)uCleaa gmCk'eke~6.5.2.5 Individuals responsible fo s erformed in accordance with 6.5.2.16.5.2.2, and 6.5.2.3 shall be members of 'the sta 1o supervisory staff, previousldesignated. by the +to perform such reviews. 'ach such reviewshall include a determination of whether~ r not additional, cross-disciplinary,review is necessary. If deemed necessary, such review shall be performed bythe appropriate designated review personnel. U'ice Qesl de~%- Alucfear 'Vrcdvc&o~

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

.~gicp Pcesid'elf.- lVch,(eau 'Poo'vigior4'.~)pp~for Sg0c SRP.fv>cd'.

6.5,2.6 The station security program and implement1~proc)dures shall bed. 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 bed. R d d h g h ll b bb d by h

designated alternate and transmitted to the Vice President-Nuclear Productionand 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 ofreports covering the evaluatio'n, recommendations and disposition of the cor-rective action to prevent recurrence.

Ql r p C, Qc) r, 5+5 I~C4 rC4 Q hiC~ +~< ~ lJ lr ci ~ ! I

h ~ ~

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

CGNTRGLLED 8'f USi'RADMINISTRATIVE CONTROLS

O it'dTECHNICAL 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 aqualified individual/organization of changes to the PROCESS CONTROL PROGRAM,OFFSITE DOSE CALCULATION MANUAL, radwaste treatment systems, and the Pre-plannedAlternate 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 beprovided to the ~VNGS-Ptant-Nanager- and the Nuclear Safety Group.

V(f'-c' c"szckaJ7 -AJDI~< j rdacfefidD6.5.3 NUCLEAR SAFETY GROUP (NSG)

FUNCTION

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

a. nuclear power plant operationsb. nuclear engineeringc. chemistry and radiochemistryd.'etallurgye. instrumentation and controlf. radiological, safetyg. mechanical and elect ical engineeringh. 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 thePhysical Sciences. He will also have a minimum of 10 years experience in thepower 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 NuclearGenerating Station.

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

CONSULTANTS'eagen6.5.3.3 Consultants shall be utilized as determined by the NSG< or toprovide 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 of10 CFR 50.59, to verify that such actions did not constitute anunr eviewed safety question;

PALO YERGE —UNIT(+2 fgjTQCLLKIQ !g>f

CGE>37RGiLLiED BY USERAOHIHISTRATIVE CONTROLS

C'J v

REVIEM (Continued j gl)

b. Proposed changes to procedures, equipment, systems or facilitieswithin the power block which involve an unreviewed safety questionas defined in 10 CFR 50.59;

c. Proposed tests or experiments which involve an unreviewed safetyquestion as defined in 10 CFR 50.59;


e. Violations of codes, regulations, orders, Technical Specifications,license requirements, or of internal procedures or instructionshaving nuclear safety significance;

Significant operating abnormalities or deviations from normal andexpected performance of unit equipment that affect nuclear safety;

All REPORTABLE EVENTS requiring 24 hours written notification;


1

Reports and meeting minutes of the PRB.

AUOITS

6.5.3.5 Audits of unit activities shall be performed under the cognizance ofthe HSG. These audits shall encompass:

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

b. The performance, training, and qualifications of he unit staff atleast once per 12 months.

c. The results of actions taken to correct deficiencies occurring i nunit equipment, structures, systems, or method of operation thataffect nuclear safety at least once per 6 months.

d.

e.

The performance of activities required by the Operational gualityAssurance Program to meet the criteria of Appendix B, 10 CFR



or the Vice President-Huclear Production.

The fire protectio programmatic controls including the implementingprocedures at least once per 24 months by qualified licensee gApersonnel.

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

CG~~)TRQLLIEi9 B'f USERADMINISTRATIVE CONTROLS

AUDITS (Continued)

The fire protection equipment and program implementation at leastonce per 12 months utilizing either a qualified offsite licenseefire protection engineer or an outside independent fire protectionconsultant. An outside independent fire protection consultant shallbe used at least every third year.

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

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

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

k. The performance of activities required by the Operations equalityAssurance Criteria Manual to meet the provisions of RegulatoryGuide 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/elyQ&d biceps. u 9

6.5.3.6 The.NSG shall report to and aavise theV'Manager-of-Nuclear-SM~ onthose areas ot responsibility specified in Specifications 6.5.3.4 and 6.5.3.5:

RECORDS h;cent;e.,u.a4. 5'kQ ALice Ms~~~

6.5.3.7 Records of NSG activities shall be prepared and maintained. Report ofreviews and audits'hall be prepared monthly for th Haaeg~e4 "<cab ar—Sa+etywho will distribute it to the Vice President-Nuclear Production,~~@ PlantManager, 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 ofSection 50.72 to 10 CFR Part 50, and a report submitted pursuantto the requirements of Section 50.73 to 10 CFR Part 50, and

b'. Each REPORTABLE EVENT shall be reviewed by the PRB, and the resultsof this review shall be submitted to the S~mvi~or~f Nuclear SafetyGroup and the Vice President-Nuclear Production.

PALO YEROE - llNIPi&2/„I 'J RFML" 6. 5 8

COIN7iRQLLED BY USERAOMINISTRATIVE CONTROLS

6. 7 SAFETY LIHIT VIOLATION

The following actions shall be taken in the event a Safety Limit is violated:

a.

b.

The'NRC Operations Center shall be notified by telephone as soon aspossible and in all cases within 1 hour. The Vice President-NuclearProduction, FR~ Plant Hanager and or Nuclear SafetyGroup shall be notified within 24 hours.

A Safety Limit Violation Report shall be prepared. The report shallbe reviewed by the PRB. This report shall describe (1) applicablecircumstances preceding the violation, (2) effects of .the violationupon facility components, systems, or strvctures, and (3) correctiveaction taken to prevent recurrence.

c. The Safet Limit Violation Reoort shall be submitted to thefAgua~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 authorizedby the Commission.

6.8 PROCEDURES AND PROGRAHS

.r6.8.1 Mritten procedures shall be established, implemented, and maintainedcovering the activities referenced below:

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

b. Refueling operations.c. Surveillance and test activities of safety-related equipment.




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

~ svfficient margin is maintained in CPC Type I Addressable Constantsto avoid excessive operator interaction with the CPCs during reactoroperation.

HOTES: (1) Hodification to the CPC Addressable Constants based on informationobtained 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 changesin fuel cycle specific data) shall be performed in accordance with the mostrecent 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 ordeletions 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 1974and 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 andcontrol 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 throughoutthe life oi the plant in accordance with the program presentea in Table 2.5-:3oi the PVNGS FSAR or another HRC approved program.

o. CEA Svmmetry Test Program implementationNOTE: The licensee shall perform a CEA symmetry test progr m in coniormance ~itthe 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 datedNovember 11, 198l.

~$ «g PreSiC&Qt — «U 'C(eel 7r„dEPC.4&6.8.2 Each program or procedure of Specification 6.8. 1, ana changes thereto,shall be reviewed as specified in Specification 6.5 and approved orior toimplementation. Programs, administrative control procedures and implementing .procedures shall be approved by thetPVNGS-Pl.ant-Hanover, or designated alternatewho is at supervisory level or above. Programs and procedures oi Speci iica-tion 6.8.1 shall be reviewed periodically as set forth in acministrative procedur

6.8. 3 Temporary changes to procedures of Soeciiication 6. 8. 1 above may bemade provided:

C.

The intent of the original procedure is not altered.The change is approved by two members of the plant supervisory staii,at least one of whom is a Shift Supervisor or Ass'.stant ShiitSupervisor with an SRO on the afiected unit.r—-Vi-.~~~or, > ee>dcrrcl's aE.'c«Pi''>~~<The change is documented, ireviewed in accordance with Speci iication6.5.2 and approved by the>PVNG~~~arrager or cognizant departmenthead, as designated by the~PVNGS-plant-manage~, within 14 days of.

imp 1 ementa tion.R

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

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

~ \ ~

CONTROLLED BY USER

ADMIN! ST RAT IVE CONT ROL 5

6. 1 RESPONSI81LITY

6.1.1 The~M~-Plant Manager shal1 be responsible for overall unit operationand shall delegate in writing the succession to this responsibility during hisabsence.

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

6. 2 ORGANIZATION

OFFSITE

6.2.1 The offsite organization for unit management and technical supportshall be as shown in Figure 6.2-1.

UNIT STAFF

6.2.2.1

b.

C.

e.

6.2.2.2a ~

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 shiftcrew composition shown in Table 6.2-1.At least one licensed Reactor Operator shall'be in the Control Roamwhen fuel is in the reactor. In addition, while the reactor is inMODE 1, 2, 3, or 4, at least one licensed Senior Reactor Operatorshall be in the Control Room.

A radiation protection technician" shall be onsite when fuel is inthe reactor.All CORE ALTERATIONS shall be observed and directly supervised byeither a licensed Senior Reactor Operator or Senio~ Reactor Operator .

Limited to Fuel Handling who has no other concur rent

responsibilities

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

The unit staff working hours shall be as follows:Administrative procedures shall be developed and implemented to limitthe 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 lessthan the minimum requirements for a period of time not to exceed 2 hours,in order to accommodate unexpected absence, provided immediate action is takento fill the required positions.

PALO VERDE - UNIT 3 6" 1


CONTROLLED 8Y USER

UNIT STAFF (Continued)0

b. Ade uate shiq ft'overage shall be maintained without routine heavyuse of overtime. The objective shall be to have operating personnelwork a nominal 40-hour week while the plant is operating. However,in the event that unforeseen problems require substantial amounts ofovertime 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 hoursstraight, excluding shift turnover time.


2) An individual should not be permitted to work more than 16 hoursin any 24-hour period, nor more than 24 hours in any 48-hour

. period, nor more than 72 hours in any 7-day period, allexcluding shift turnover time.

+Re. a.

/d f(8i//. /<>Q>'6<<

| $ //ops

4) Except during extended shutdown periods, the use of overtimeshould be considered on an individual basis and not for theentire 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 orabove, or higher levels of management, in accordance with establishedprocedures and with documentation of the basis for granting thedeviation. Controls shall be included in the procedures such thatindividual overtimeyshall be reviewed monthly by the-IQNGS-Pleat

/tassigned. Rout' deviation from the above guidelines is notauthorized.

7'3ese a.R<c~.~eJ'NHiv'idu~L5OK

cgp~gg~g- /gag P//'sill@/8 /V~<i@E PKccl(Jcfea

5//py/,„f,J// / /.-Q~ 5da&orÃs //~'a

PALO VEROE - UNIT 3

O

OD(mA7CD

/ g . + g/Qg /p /c~lV/7 4F(p'a~m

PRESIDENT

EXECUTIVE V.P.

.V.P.HUCLEAR

PRODUCTION

ASST.V.P. ttUCLEARPROOUCTIOtt

MGR.EMERGEttCY PLAN

MCR.ADMI t tl ST RAT IVE

SERVICES

MGR.TRAlttlttG

PVHGSPLAHT MAttAGER

MCR.OPERATIOHS

MGR.MAIHTEHAHCF.

MGIt.0+AGE

MANAGEMENT

MGR.NUCLEAR SAFETY

ISED/ttSG

MGR.~ TOAIIOQIT OII

DIR.TE HttICAL SERVICES

MGR.ttUCLEAR EttGIHEERING

MGR.NUCLEAR CONSTRUCTION

MGR.HUCLEAR FUELS

OIR.CORPORATE OA


MGR.DUALITYSYSTEMS/

ENGlttEERlttG

MGR.PROCUREMEttT QUALITY

n0z270IlalO

0)Ttl

I

HRFSUPERINT fttOEtt T

MGR.PLAHT SERVICES

MGR. RECORDSMGR.

DUALITY AUDITS/lt ONI7 OR INC

4MGR.

TECIIHICAL SUPPORTMGR. LICEttSIHG MGR,

OltALITYCONT

0 LOCATED ONSI 7 EFIGURE 6.2-1

+MANAGER

COMI'LlhttCE OFFSITE ORGANIZATION

PRESIDENT 8CI.IIEF OPERATING

OFFICER

"I.OCATEO 0/JSI TE EXECUTIVEVICE PRESIDENT


PRODUCTION

DIRECTORENGINEERING 8,

CONSTRUCTION



8 LICENSING

DIRECTORQUALITY

ASSURANCE

MANAGERENGINEERING

MANAGERSECURITY


MANAGER'UALITYSYS.

ENGINEERING

MANAGERCONSTRUCTION

MANAGERTRAINING

MANAGERISEG

MANAGERPROCUREMENl

QUAI.IITY

MANAGERCOST I

SCI IEDULE

MANAGERNUCLEAR

FUEL

MANAGERPAfITICIPANT

SERVICES

MANAGEREMERGENCY

PI.AN &

SFRVICES

MANAGERMATEfIIALCONTROL

MANAGERADMIN.

SEflVICES

MANAGERLICENSING

SUI'ERVISORTECI.INICAL

DATA

MANAGERCOMPLIANCE

MANAGERQUALITY(AUDITS

MONITORING

MANAGERQUALITYCONTROL

OFFSITD<ORGANIZATION

Figure 6.2-1

(mCDm

6'~cZ/ Pyi/c?cg ~yPr(A/dcu'id Ks~ PVtlGS

PLA}lTMAttAGER

OUTAGE

MAtlAGEMEHTMAtlAGER

T EClltllChl.SUPPORT

MAWAGER

OPERATIOHSMAtlAGER

MAIHTBIAHCEMANAGER

PLANT SERVICESMANAGER

MANAGERCOWPL IAtlCE

MAN ICER

OPS EtlGINEE INGSUPERIHTENOENT

UNIT ISUPERIHTENOEHT

~llC MAIHTEHAtlCE

MANAGEROPERATIONS

SECURITY

SUP ER VISOR

STA

MAHAGERRAO. PROT. 4 CHEM.

SUP ERIHTEtl0)HTUNIT 2~

SUPERIIITEHOEIITUtIIT 3

SUPERIHTEHOEHTMCC

SUPERIHTEHOENTELEC. MAINTEtlAHCE

SUPERVISORFIRE PROTECTION

O0

U03

SUPERINTBlOEHTOPS COMPUTER

SYSTFM

SUPERVISOROPERATIOtls SUPPORT

~SUPERIHTEHOEHTSTATIOH SERVICES

/'

SUPERINTENOEHT'~MECHAttlCAL

MAINTENAWCE

FIGURE 6.2-2

ON SITE ORGAN I ZATION

VICE PRESIDENTNUCLEAIl

PRODUCTION

PLANTMANAGERUNIT 1

PLANTMANAGERUNIT2

PLANTMANAGERUNIT3

ASSISTANTVICE PRESIDENTNUCLEAR PROD.

SUPPORT

DlflLCTORSTANDARDS 8

TECH. SUPPORT

OPERATIONSMANAGER

MAINTENANCEMANAGER

WORKCONTROLMANAGER

RADIATIONPROTECTION

MAtIAGER

OPERATIONSMANAGER

MAINTEHANCEMANAGER

WORKCONTROLMANAGER

RADIATIONPROTECTION

MANAGER

OPERATIONSMANAGER

MAINTENANCEMANAGER

WORKCONTROLMANAGER

RADIATIONPROTECTION

MANAGER

WATER REC.FACILITY

MANAGER

OUTAGEMANAGEMENT

MANAGER

CENTRALMAINTENANCE

MANAGER


P&HTSTAN.DAllDS 8 CONT.

MANAGER

ENGINEEllIHGEVALUATIONS

MANAGER


MANAGER


Cl IEMISTRYMANAGER

SUPEIlVISOIlOPLllATIOt1S

STHDS.

SUPERVISORMECI». MAIHT.

STHDS.

SUPF IlVISOBELEC. MhlttT.

STHDS.

SUPERVISORl8 C STNDS.

CHEMISTRYMANAGER

CI.IEMISTRYMANAGER

CHEMISTRYMANAGER

CENTRAIRADIATION

PROTECTIONMANAGER

COMPLIANCE

"LOCATED OFFSITE

ONSITEORGANIZATION

Figure 6.2-2

CONTROLLED BY USER

TABLE 6. 2-1

MIHIMUM SHIFT CREW COMPOSITIOH

POSITION

SS

SRG

RO

AO

STA

NUMBER OF INDIVIDUALS REQUIRED TO FILL POSITION

MODE 1, 2, 3, OR 4 . MODE 5 OR 6

1None11Hone

SS - Shift Supervisor with a Senior Reactor Operators LicenseSRO - Individual with a Senior Reactor Operators LicenseRO - Individual with a Reactor Operators LicenseAO - Nuclear Operator I or IISTA - Shift Technical Advisor

The Shift Crew Composition may be one less than the minimum requirements ofTable 6.2-1 for a period of time not to exceed 2 hours in order to accommodateunexpected absence of on-duty shift crew members provided. immediate action istaken to restore the Shift Crew Composition to within the minimum requirementsof Table 6.2-1. This provision does not permit any shift crew position to beunmanned upon shift change due to an oncoming shift crewman being late orabsent.

During any absence of the Shift Supervisor from the Control Room while theunit is in MODE 1, 2, 3, or 4, an individual with a valid Senior Operatorlicense shall be designated to assume the Control Room command function.During any absence of the Shift Supervisor from the Control Room while theunit is in MODE 5 or 6, an individual with a valid Senior Operator or Operatorlicense shall be designated to assume the Control Room command function.

PALO YERDE - UNIT 3 6-5

CONTROLLEO BY USER

AOMIH 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 sourcesof plant design and operating experience information, including plants ofsimilar 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-timeengineers located on site. Each shall have a Bachelor's Degree in engineeringor related science and at least two years professional level experience in hisfield.

RESPONSIBILITIES

6.2.3.3 The ISEG shall be responsible for maintaining surveillance of plantactivities to provide independent verification" that these activities areperformed correctly to reduce human errors as much as practical, and to detectpotential nuclear safety hazards.

Q<~e,c(~~ k~gc,(cur Sak~y g.gd LE.cowsi~AUTHORITY

6.2.3.4 The ISEG shall make detailed recommendations for revised procedures,equipment modifications, maintenance ctivities, operations activities or other

11 I 'I I«' I-I~.IIIIIIManager, and the~Sup~i-ser-, Nuclear Safety Group (NSG).

RECORDS4Aapaw

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 technicalsupport to the Shift Supervisor in the areas of thermal hydraulics, reactorengineering, 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 within10 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 theRadiation Protection and Chemistry Manager who shall meet or exceed the qualifi-cations of Regulatory Guide 1. 8, September 1975, and the Shift Technical Advisorwho shall have a bachelor's degree or equivalent in a scientific or engineeringdiscipline 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 theN

I'ndshall meet or exceed the requirements and recommendations of Section 5.0 ofANS 3. 1-19?8 and Appendix A of 10 CFR Part 55 and the supplemental requirementsspecified in Sections A and C of Enclosure 1 of the March 28, 1980 HRC letterto all licensees, and shall include familiarization with relevant industryoperational 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 Manageron all matters related to nuclear safety.

COMPOSITION

6.5.1.2 The PRB shall be composed of the following personnel:i tlJPe&rmcj gv'N lvQ gco&$,

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

Member: g>ol~uuiccr ~ Haintenance Reneger Skate'«d~Hember: P aaagerHember: Ekcgzicac. ggc+g4t~ '+anJdarc)5 ~ope<~i~~~

Member: 0 i ~f i 1,Ui 2

Uni t 3 ~~~<9 e+>Hember: STA SupervisorHember; per~endent S~ae'darCh &~e~i~a~Member: Radiation Protection and Chemistry ManagerMember: equality Systems/Engineering Manager

ic e P~>rde'&f —/UJclda'K Pleducfcc4The t VHGS-N-ant-Mana@~ shall designate the Chairman and Vice-Chairmenin writing. The Chairman and Vice-Chairmen may be from outside themembers 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 Chairmanto serve on a temporary basis; ho~ever, no more than two alternates shallparticipate as voting members in PRB activities at any one time.

HEETING FRE UEHCY


PALO VEROE - UNIT 3 6-7

COi~lTROLLED BY USER


gUORUtd

6.5. 1.5 The quorum of the PRB necessary for the performance of thePRB responsibility and authority provisions of these Technical Specificationsshall consist of the Chairman, Vice-Chairmen, or his designated alternate andfive members including alternates.

RESPONSIBILITIES

6.5. 1.6 The PRB shall be responsible for:

b.

C.

d.


Revie~ of all proposed changes to Appendix "A" Technical'pecifications

Investigation of all violations of the Technical Specificationsincluding. the preparation and forwarding of reports covering evalua-tion and recommendations to prevent recurrence to the Nuclear SafetyGroup (HSG).

Review of REPORTABLE EVENTS.

e.

AUTHORITY

Review of unit operations to detect potential nuclear safety hazards.

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

fJjpg(gp~r - /ifiJc/E'8'iz PldJU('cb DReview and documentation of judgment concerning prolonged operationin bypass, channel trip, and/or repair of defective protection

. channels of process variables placed in bypass since the last PRB

meeting.

6.5.1.7 The PRB shall:

b.

RECORDS

Render determinations in writing with regard to whether or not eachitem considered under Specification 6.5. 1.6c. above constitutes anunreviewed safety question.

Provide written notif ion within 24 hours to the Vice President,-Nuclear Production, nt Manager and NSG of disagreemenbetween the PRB and e 3%RES'lant Manager; however, thPlant Manager shall have responsibility for resolution of suchdisagreements pursuant to Specification 6. l. 1 above.

that, at athe responsi-Copies shall

jlCCl'(„:gfpgig

6.5. 1.8 The PRB shall maintain written minutes of each PRB meetingminimum, document the results of all PRB activities performed underbility and authority-px;ayisions of these Technical Specifications.be provided to thd:fRRK Plant Manager,and HSG.

<y„, pip„ye<(- st/~c/ec«-PALO VERDE - UNIT 3 6"8


CONTROLLED BY USER

bqecbr, &>a&ar85 aaiotTHc-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 programrequired by Specification 6.8 and other procedures which affect nuclear safety,and changes thereto, is prepared by a qualified individual/organization. Eachsuch procedure, and changes thereto, shall be reviewed by an individual/groupother than the individual/group which prepared the procedure, or changesthereto, 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 /NayJ ag d ~

6.5.2.2 Phase I - V tests describe3 in the FSAR t ~~ performed by thed ~ET i 5

or the Herag~W Engineeringgas previously designated by the A'NSS=Mant~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, systemsand components shall be designed by a qualified individual/organization. Eachsuch modification shall be reviewed by an individual/group other than theindividual/group which designed the modification, but who may be from the sameorganization as the individual/group which designed the modification. Proposedmodifications to nuclear safety-related structures, systems and components shallbe approved prior to implementation by the MN88 Plapt panacgr ri,py th~m(~g„,~

rgTechnjca) Support as previously designated by the~N t-Manager-.s<'echof-, &oaf,iced«at& a.v 4 VCICaC Pf f,C(svC.&CC~

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 station„supervisory staff, previouslydesignated 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, uch review shall be performed bythe appropriate designated review personnel. l/«c'~ ~ac~~~

6.5.2.5 Proposed tests and experiments. which affect station nuclear safety andare not addressed in the FSAR or Technical Specifications shall be reviewedby-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 bereviewed. Recommended changes shall be approved byo&~H~Mnt-Manage~ordesignated alternate and transmitted to the Vice President-Huclear Productionand to the NSG.

I

6.5.2.7 The station emergency plan and implementing rocedures shall bereviewed. Recommended changes shall be approved by the~PVHGS-I&ant-Manager ordesignated alternate and transmitted to the Vice President-Nuclear Productionand 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.

/'r-ecPop 5'ra.t Parcels awed /c<'n A'ff:ai - ~vjrpdw'~

PALO VERDE - UNIT 3 6" 9

CONTROLLED BY USER


TECHNICAL REVIE'IIv'ND CONTROL ACTIVITIES Continued)6.5.2.9 The-PVNGS-f%anb-Manage+>shall assure the performance of a revie~ by aqualified individual/organization of changes to the PROCESS CONTROL PROGRAM,OFFSITE DOSE CALCULATION MANUAL, radwaste treatment systems, and the Pre-plannedAlternate 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 beprovided to the PVNGS-PlantManager>and the Nuclear Safety Group.

(.g«p« „g<,gt-- rKic(e<~ +aduzKia>

FUNCTION

6.5.3. 1 The NSG shall function to provide independent review and shall beresponsible for the audit'of designated activities in the areas of:

a. nuclear power plant operationsb. nuclear engineeringc. chemistry and radiochemistryd. metallurgye. instrumentation and controlf. radiological safetyg. mechanical and electrical engineeringh. quality assurance practices

COMPOSITION yl,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 thePhysical Sciences. He will also have a minimum of 10 years experience in thepower 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 NuclearGenerating Station.

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

CONSULTANTS/8tudaye~

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

REVIEW

6.5.3.4 The NSG shall review:

a. The safety evaluations program and its implementation for (1) changesto procedures, equipment, systems or facilities within the po~er block,and (2) tests or experiments completed under the provision of10 CFR 50.59, to verify that such actions did not constitute an

unreviewed safety question;PALO VERDE - UNIT 3 6-10

CONTROLLED BY USER

eu Sue~~AOHIHISTRATIVE CONTROLS

REVIEW (Continued

b.

C.

Proposed changes to procedures, equipment, systems or facilitieswithin the power block which involve an unreviewed safety questionas defined in 10 CFR 50.59;

Proposed tests or experiments which involve an unreviewed safetyquestion as defined in 10 CFR 50.59;


e.

h.

l.

AUDITS

Violations of codes, regulations, orders, Technical Specifications,license requirements, or of internal procedures or instructionshaving nuclear safety significance;

Significant operating abnormalities or deviations from normal andexpected performance of unit equipment that affect nuclear safety;

All REPORTABLE EVENTS requiring 24 hours written notification;


Reports and meeting minutes of the PRB.

6.5.3.5 Audits of unit activities shall be performed under the cognizance ofthe HSG. These audits shall encompass:

a.

b.

c ~

d.

The conformance of unit operation to provisions contained within theTechnical Specifications and applicable license conditions at leastonce per 12 months.

The performance, training, and qualifications of the unit staff atleast once per 12 months.

The results of actions taken to correct deficiencies occurring inunit equipment, structures, systems, or method of operation thataffect nuclear safety at least once per 6 months.

The performance of activities required by the Operational equalityAssurance Program to meet the criteria of Appendix B, 10 CFR



or the Vice President-Huclear Production.

The fire protection programmatic controls including the implementingprocedures at least once per 24 months by qualified licensee gA

personnel.

PALO VERDE " UHIT 3 6" 11

CONTROLLED BY USER


AUDITS (Continued)

g. The fire protection equipment and program implementation at leastonce per 12 months utilizing either a qualified offsite licenseefire protection engineer or an outside independent fire protectionconsultant. An outside independent fire protection consultant shallbe used at least every third year.

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

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

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

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

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

AUTHORITY Q (-gc$op g„' recur Qc~'fQ ('t Q.kidL 'l c. e < ~ q Qr~

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/yclead 4i c en3gi~q

6.5.3.7 Records of NSG activities shall be prepared nd maintained. Report ofreviews and audits shall be prepared monthly for the cLea.~af.e t.ywho will distribute it to the Vice President-Nuclear Production, ~S PlantManager, 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 ofSection 50.72 .to 10 CFR Part 50, and a report submitted pursuantto the requi rements of Section 50.73 to 10 CFR Part 50, and

Each REPORTABLE EVENT shall be reviewed by the PRB, and the resultsof this review shall be submitted .to the .Superv+sor+of Huclear SafetyGroup and the Vice President-Nuclear Production.

4 ) AQ Mc <j P

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VERDE - UNIT 3 6" 12

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6.7 SAFETY LIMIT VIOLATION'

The following actions shall be taken in the event a Safety Limit is violated:

b.

C.

[AcUnge+

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

wGroup shall be notified within 24 hours.

A Safety Limit Violation Report shall be prepared. The report shallbe reviewed by the PRB. This report shall describe (1) applicablecircumstances preceding the violation, (2) effects of the violationupon facility components, systems, or structures, and (3) correctiveaction taken to prevent recurrence.

The Safet Limit Violation Report shall be submitted to theommission, 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 authorizedby the Commission.

6.8 PROCEDURES AND PROGRAMS

6.8.1 Written procedures shall be established, implemented, and maintainedcovering the acti'vities referenced below:

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

b. Refueling operations.c. Surveillance and test activities of safety-related equipment.




g. Modification of Core Protection Calculator (CPC) AddressableConstants--These procedures should include provisions to ensure thatsufficient margin is maintained in CPC Type I Addressable Constan'sto avoid excessive operator i nteraction with the CPCs during reactoroperation.

NOTES: (1) Modification to the CPC Addressable Constants based on informationobtained through the Plant Computer - CPC data link shall not be made withoutprior approval of the PRB.

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

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GONTROLLED BY USER


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 1974and 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 andcontrol 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 throughoutthe life of the plant in accordance with the program presented in Table 2.5-18of the PVNGS FSAR or another NRC approved program.

o. CEA Symmetry Test Program implementationNOTE: The licensee shall perform a CEA symmetry test program in conformance withthe 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 datedNovember 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,.toimplementation. Programs, administrative control procedures and implementingprocedures shall be approved by the , or designated alternatewho 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 bemade provided:

a.

b.

C.

The intent of the original procedure is not, altered.

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

roicec+ir ~~occkarc4 g~ J Tech,ijica( 4 '/p,r fThe change is documented,lreviewed 3n accordance with Specification6.5.2 and approved by the~RN&S-Hant-Manager or cognizant departmenthead, as designated by the~PVNGS-R.ant-Manager —

, within 14 days ofimplementation. itic, Preside.vt.- ~,c'~Pa- Vrcgvc.'/cy J

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

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