ML20078A399
| ML20078A399 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 01/10/1986 |
| From: | Ramsey W GEORGIA POWER CO. |
| To: | |
| Shared Package | |
| ML20078A351 | List:
|
| References | |
| PROC-860110, NUDOCS 9406010184 | |
| Download: ML20078A399 (1000) | |
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Georgia Power Comp;ny Vogt:e Project Readiness Review Post office Box 282 Waynesboro. Georgia 30830 2'~N Telephone 404 724-8114 4(] 404 554 9961 Vogtle Project f
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t DATE: January 10, 1986
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V Mr. D. O. F ost er Vice President and General Manag er Vogtle Project Waynesboro, Ga. 30830 RE: Readiness Review Program Mo dule No. 7 Plant Operations an6 Suppor t FILE: X7BD102 1
LOG: RR-528 l
Dear Mr. Foster:
1 Pursuant to your instructions I am enclosing Module 7, Plant
, Operations and Support, of the Readiness Review Program. This module reports the wor k of the Readiness Review Team and has )
been prepared to present you with an accurate picture of the readiness for operations of the Vogtle Project, based upon a close examination of the programs for plant operations and s up po r t .
1 The Readiness Review process included an initial assessment and I review of basic licensing documents to identify Project connitments within the scope of the module. The Readiness {
l Review Team then verified implementation processes designed to meet those commitments, including prograns and controls relating to work within the scope of the module.
The team then engaged in a process designed to verify that
's implementation programs were operating as described in
/(,) procedur es, policy stateme nts , and o ther documents . In concluding this ver. fication process, the team then verified that the licensing ;onnitments identified during the process were being fulfilled and met.
iW an as PDR
/ k k_) Mr. D. O. Poster Readiness Review Program - Module 7 December 23, 1985 Page 2
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The Readiness Review Team employed a sampling method for conducting the overall verification process. The verification process included consideration of relevant project QA audits, NRC inspection reporte, and problems experienced by other near-term operating license utilities in their prograns for plant
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C_ s operations and support.
We are confident that the sampling and verification methodology used allowed Readiness Review Program to properly appraise the actual condition of the prograns for plant operations and support and provided a valid means of assessing the quality of the prograns having also considered applicable past audits, inspection reports, and problems experienced by other utilities.
Based upon our review process, as described in detail in the module, the Readiness Review Team concluded that the programs for plant opera tions and support at Plant Vogtle are of sound (j quality and principally comply with the commitments set forth in th e FS AR .
Members of the Readiness Review Team and I will be prepared to discuss this module with you if you so desire. If we can provide you with any further information or assistance regarding this matter please contact me.
Verygtruly y s, William C. Ramsey SAB/WCR/bjd cc: R. E. Conway Readiness Review Board Members Document Control
(~T Reading File G
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VOGT"sE ELECTRIC GENERATING PLANT UNIT 1 READINESS REVIEW MODULE 7 - PLANT OPERATIONS AND SUPPORT C
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INDEX TO READINESS REVIEW MODULES AND APPENDIXES Module Title
- 1. Reinforrad C;ncrete Structures
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s_ 2. Operations Training and Qualification 3A. Initial Test Program, Preoperational Test Phase 3B. (Combined with Module 7)
- 4. Mechanical Equipment and Piping
- 5. Operations Organization and Administration
- 6. Electrical Equipment O,' 7. Plant Operations and Support 7B. (Cancelled as a module)
- 8. Structural Steel 9A. Radiological Protection 9B. Chemistry
- 10. (Combined with Module 7)
- 11. Pipe Supports
- 12. Electrical Cables and Terminations 13A. Foundation Materials and Backfill 13B. Coatings 13C. Post-Tensioned Containment
- 14. (Combined with Module 7)
() 16.
17.
Nuclear Steam Supply System Raceways 18A. Heating, Ventilation, and Air-Conditioning ,
18B. Fire Protection 18C. DietA? Generators 18D. Radwaste *
- 19. Electrical Supports
- 20. Instrumentation and Controls General Appendixes (formerly titled Module 21)
A. Organization B. Design Control C. Procurement D. Document Control
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(_/
E.
F.
Material Control Inspector Qualification / Certification G. Measuring and Test Equipment H. Nonconformances I. Project Quality Assurance Organization Supplement: Quality Concerns J. Equipment Qualification Os K. Construction Completion
- 22. Independent Design Review O
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() PREFACE Georgia Power Company (GPC), in order to gain added assurance of the operational readiness of the Vogtle Electric Generating Plant (VEGP), is conducting a pilot Readiness Review P:ogram.
O The VEGP pilot Readiness Review program is a systematic, in-depth self-assessment of work processes and verification of compliance with regulatory commitments. To accomplish the VEGP ,
pilot Readiness Review program, the work processes and regulatory commitments were divided into manageable segments calle'd " modules." There are approximately 20 modules. Each O module is a predefined scope of VEGP activities.
Each module is intended to provide a brief description of the method of complying with project licensing commitments, pertaining to the module scope, found in the FSAR and is not intended to make further commitments or revise in any way prior commitments. Any differences between the commitments discussed in this document and the FSAR, if any, are unintentional and the FSAR governs.
Activities common to several modules are provided as General Appendixes. There are approximately 10 appendixes. These appendixes, as appropriate, are referenced in the modules and O are augmented in each module with module-scope-specific details as needed.
The VEGP Readiness Review program is being conducted on a schedule to provide added operational readiness assurance to GPC management in support of the VEGP Unit 1 operating license.
However, conclusions reached regarding programmatic and technical adequacy through review of VEGP Unit 1 are indicative 6
of Unit 2 since both units are being designed and constructad together under a single Quality Assurance program, and like management controls, procedures, etc., and to the same specifications and criteria.
Stone and Weboter Engineering Corporation has been contracted to O provide technical management for and technical personnel to implement an independent design review as a part of the Readiness Review program. Additionally, Stone and Webster is reviewing project responses to Readiness Review findings for technical adequacy.
) The VEGP Readiness Review program is not intended to eliminate or diminish any authorities or regulatory responsibilities now assigned to or exercised by the Nuclear Regulatory Commission or Georgia Power Company. Further, the Readiness Review program is not intended to change the techniques of inspections or assurance of quality program activities.
O Rather, the VEGP Readiness Review program is an added program initiated by GPC management to assess the VEGP, and provide additional feedback v
( .
to management so that they may initiate any needed corrective actions in an orderly and timely manner.
The scope of work processes and regulatory commitment compliance O covered by each module will be assessed by and the module prepared and reviewed by individuals collectively familiar with the design, c o ns t.:u c t ion , and operational processes of nuclear power plants. It is the collective opinion of the Readiness Review Task Force, Readiness Review Board, and GPC management that, based on their experience, the methodology used in the module process will assess, on a programmatic basis, the adequacy of project commitment implementation.
Readiness Review Discrepancy Reports and resulting dispositions are reviewed by the Readiness Review program quality assurance staff and are input into the normal project process for safety significance and potential reportability evaluations in accordance with regulatory requirements.
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EXECUTIVE
SUMMARY
Introduction This module documents a review program to ascertain whether
's certain Nuclear Operations proorams for plant operatiot ond support comply with licensing commitments and whether compliance is verifiable using existing project documentation.
The scope of Module 7 includes Nuclear Operations initial startup and routine testing, plant operation, plant maintenance, and plant engineering programs. Health physics and chemistry Os are discussed in detail in Modules 9A and 9B, respectively. The Initial Test Program, preoperational test phase is discussed in Module 3A.
The activities within the scope of this module will be fully functional when the operational quality assurance (QA) program requirements and controls are implemented at least 90 days prior to Unit 1 fuel load. However, Nuclear Operations is phasing in operational QA requirements and controls on a scheduled basis as programs are developed. Even though many programs are not required at this stage of the project and have not been phased in, programs were evaluated to operational QA requirements when assessing compliance with licensing commitments.
O A summary of the method used to classify findings and a summary of the review are provided below.
Findino Classification 6
Following evaluation, findings were subjected to categorization as follows to indicate their relative importance:
Level I - Violation of licensing commitments, project procedures, or engineering requirements with indication of safety concern.
Level II - Violation of licensing commitments or Q(m/ engineering requirements with no safety concern.
Level III - Violations of project procedures with no safety concern.
Verificacion Summary The Readiness Review Task F3rce verification activities discussed in this module con isted of a review of commitment implementation and a review of activities and project documentation. The review encompassed a total of 3346 individual program elements. These reviews confirmed and O documented the effectiveness of the operations and support programs and also identified 57 program elements which were not vii l
in compliance with licensing commitments. These 57 program l elements were grouped by subject into 16 findings which were issued to the Project. Fifteen findings were categorized as Level II and one as Level III. The Project subsequently evaluated the findings and submitted responses to correct them.
Additionally, the Readiness Review Board technical consultant provided independent technical oversight and concurrence, and ,
Readiness Review quality assurance personnel provided QA surveillance of the review activities. Statements from the technical consultant and QA regarding their involvement and conclusions reached are provided in section 7 of this module.
Review of Commitment Implementation A review was performed to ascertain whether commitments were incorporated into presently approved plant procedures, were specifically identified for inclusion in planned procedures, or were contained in the Nuclear Operations commitment tracking system for future dispositioning.
The review consisted of an assessment of 1266 corsitments identified in the implementation matrix (sectior,3.3). Of these commitments. 1239 were adequately addressed. Assessment of the 27 remaining commitments resulted in identification of approved a
procedures which did not adequately incorporate commitments.
Subjects covered by procedures which did not adequately l incorporate commitments were inservice inspection and testing; l startup testing: procedure writing, review, and approval; cleanliness control; housekeeping; overtime administration; and storage of material. These were identified as 13 of the 16 Readiness Review Findings, all Level II.
The procedures have been or are being revised. The root causes l of procedures not adequately implementing commitments were !
errors in screening and assigning commitments for implementation i and insufficient guidance to procedure writers and reviewers. A )
complete review of commitments performed by Nuclear Operations '
resulted in reassignment of some commitments to the proper functional departments. Improved communication among Nuclear ;
Operations departments regarding commitments has enhanced the 1 process of commitment assignment. Additionally, departments have implemented procedure reviewer qualification programs. gl I Procedure writer's guides have been and are being revised to provide more complete guidance to writers and reviewers. These revisions are scheduled for completion by February 1986. These actions are adequate to ensure that accurate and complete procedures will be available when the operational quality assurance program requirements and controls are implemented.
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Details of the results of the review of commitment implementation and corrective actions are found in section 6.2. I O
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) Review of Activities and Proiect Documentation Plant operations and support activities and records were reviewed to ascertain whether the activities satisfy requirements.
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(_) The activities associated with the 10 programs which were functioning under operational quality assurance program requirements were reviewed. These activities were assessed to ascertain compliance with plant procedures and commitments.
Activities which were found not to be in compliance were identified as findings and resolved.
Five of the 16 Readiness Review Findings were identified during the review of programs and records, of which 4 were Level II findings and 1 was a Level III finding. There were no Level I findings. A brief discussion of the Level II findings follows.
Findinc 7-5 involved documentation of procedure reviewer qualification. Objective evidence that maintenance procedures had been reviewed by appropriately qualified personnel was not available and some engineering procedures were approved prior to issuing the procedure on reviewer qualification. Also, the governing plant procedure regarding review and approval of procedures did not require that reviewers be appropriately qualified. Resumes for personnel who reviewed a representative O' sample of maintenance and engineeting procedures showed that the reviewers were qualified. The corrective action was to locate evidence of the qualification of reviewers of maintenance and engineering procedures and send it to Document Control for retention. Additionally, procedure 00051-C, Procedures Review and Approval, was revised to state that reviewers will meet departmental requirements. Departmental procedures governing qualification of procedure reviewers have been issued. None of the approved procedures required additional reviews as a result of this finding.
Findinc 7-6 involved revisions to permanent maintenance procedures. Seven of 850 maintenance procedures were revised in O accordance with an initial test program procedure which implements construction quality assurance requirements. The plant administrative procedure for revising permanent plant procedures implements operational quality assurance requirements. Permanent plant procedures should be revised in accordance with the operations quality assurance program. The O Initial Test Program procedure SUM-12A, Construction Acceptance Test Implementation, was written to control the changing of maintenance procedures so that maintenance personnel could correct mistakes in the procedures discovered during the initial use of the procedures. However, procedure SUM-12A does not implement adequate controls to assure that changes made in O accordance with SUM-12A are reviewed and incorporated into the procedures in accordance with permanent plant procedure 00051-C, 1X
Procedure Review and Approval, prior to the procedures being used in the operations phase. Procedure SUM-12A will be revised to include controls to ensure that procedures revised in accordance with SUM-12A are reviewed and revised in accordance lh with procedure 00051-C. This action is scheduled f'or completion in December 1985. None of the procedures identified by this finding affected activities functioning under the operational QA program.
Findino 7-9 involved temporary changes to procedures. Two of O four temporary changes to procedures issued at the time of verification were processed improperly. The two affected procedures have been properly revised. Procedure 00052-C, Temporary Changes to Procedures, will be revised to clarify the routing sequence. Document Control personnel will be instructed in the proper handling of temporary changes to procedures. h These actions are scheduled for completion in December 1985.
The two procedures identified by this finding did not affect activities functioning under the operational QA program.
F_indino 7-10 involved standing orders. One of 38 standing orders in effect at the time of verification remained in effect for more than 1 year, contrary to FSAR requirements, and one monthly review of standing orders was not performed, contrary to a VEGP procedure. The next monthly review, performed in August, terminated the standing order. Responsibility for performing this review has been formally assigned to a specific individual. A program has been developed for scheduling periodic administrative activities of the Operations g
w Department. The existence of the standing order for more than 1 year did not affect safety, hardware, or completed quality documentation.
Details of the results of the review of activities and records and corrective action are found in section 6.2.
Readiness Review Conclusion A review was performed to ascertain whether commitments were incorporated into presently approved plant procedures, were specifically identified for inclusion in planned procedures, or were contained in the Nuclear Operations commitment tracking h system for future dispositioning. In addition, a review of plant operations and support activities and records was performed to ascertain whether the activities satisfy requirements. As a result of these reviews and the resulting corrective actions, the Readiness Review Team concludes that no safety issues exist and adequate controls are now in place to ensure the quality of h work and implementation of licensing commitments when the operational quality assurance program requirements are implemented. Moreover, the programs for plant operations and support, within the scope identified in this module, meet O
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regulatory requirements and are verifiable with existing project i records.
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() TABLE OF CONTENTS 1.0 Introduction 1.1 Scope O 1.2 Status and Schedule of Operations Activities 1.2.1 Equipment and Plant Status Controls 1.2.2 Housekeeping and Cleanliness 1.2.3 Fire Prevention and Fire Fighting -
N 1.2.4 Equipment Labeling
) 1.2.5 Control Room Design Review 1.3 Status and Schedule of Maintenance and Modification Activities 1.3.1 Maintenance and Instrumentation Shopo 1.3.2 Nuclear Operations Warehouse 1.3.3 Spare and Replacement Parts 1.3.4 Diesel Generator Program 1.3.5 Work Planning Group 1.3.6 Control of Modifications 1.4 Status and Schedule of Coordination Activities 1.4.1 Procedures 1.4.2 Data Processing Systems 1.4.3 Planning and Scheduling 2.0 Organization and Division of Responsibility 2.1 Current Organization 2.1.1 Opetations Department 2.1.2 Maintenance Department 2.1.3 Plant Engineering and Services Department 2.1.4 Southern Company Services, Nuclear Plant O 2.1.5 Support Department
^
GPC Engineering Liaison Department 2.2 Operations Department Division of Responsibility 2.2.1 Operations Superintendent rS ij 2.2.2 Senior Shift Technical Advisor s,
2.2.3 Shift Technical Advisor 2.2.4 Operations Supervisor 2.2.5 Shift Supervisor 2.2.6 Plant Operator 2.2.7 Assistant Plant Operator O 2.2.8 Plant Equipment Operator xiii
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I l 2.3 Maintenance Department Division of Responsibility i
l 2.3.1 Maintenance Superintendent l 2.3.2 Maintenance Supervisor 2.3.3 Maintenance Foreman 2.3.4 Nuclear Plant Mechanic and Electrician 2.3.5 Controls and Instrumentation Supervisor 2.3.6 Controls and Instrumentation Foreman 2.3.7 Instrument Technician 2.3.8 Plant Engineering Supervisor 2.3.9 Plant Engineer 2.3.10 Plant Material Supervisor 2.3.11 Foreman (Materials) 2.3.12 Storekeeper l 2.3.13 Telecommunications Supervisor 2.4 Plant Engineering and Services Department Division of Responsibility 2.4.1 Superintendent, Plant Engineering and Services l
2.4.2 Plant Engineering Supervisor (Cost and Scheduling) 2.4.3 Plant Engineering Supervisor (Computers) 2.4.4 Plant Engineering Supervisor (Reactor Engineering) 2.4.5 Plant Engineering Supervisor (Instrumentation) 2.4.6 Plant Engineering Supervisor (Mechanical) 2.4.7 Plant Engineer 2.5 Southern Company Services, Nuclear Plant Support l Department Division of Responsibility 2.5.1 Manager, Nuclear Plant Support Department -
Vogtle 2.5.2 Project Engineer, Nuclear Plant Support Department - Vogtle Field Office 2.5.3 Supervisor, Modification Coordination and Review Section 2.5.4 Engineer, Modification Coordination and Review Section 2.5.5 Lead Engineer and Engineer, Planning, 2.5.6 Preparation, and Packaging Section Material Coordinator, Planning. Preparation, g
and Packaging Section 2.5.7 Supervisor, Engineering Design and Support Section 2.5.8 Engineer and Designer. .ngineering Design and Support Section 2.5.9 Technical Specialist, Engineering Design and Support Section O
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() 2.6 GPC Engineering Liason Department Division of Responsibility 2.6.1 Vogtle Engineering Liason Manager 2.6.2 Engineer 1
() 2.7 Significant Organization Changes 3.0 Commitments 3.1 Definitions
() 3.2 3.3 Commitment Matrix Implementation Matrix 4.0 Program Description 4.1 Operations Activities I
4.1.1 Conduct of Operations 4.1.2 Equipment and Plant Status Controls 4.1.3 Hot sekeeping and Cleanliness 4.1.4 Fi'.e Prevention and Fire Fighting 4.1.5 Centrol Room Design Review O 4.1.6 4.1.7 4.1.8 Plant Performance Monitoring Fuel Management Refueling 4.2 Maintenance and Modification Activities 4.2.1 Control of Maintenance 4.2 2 Control of Modifications 4.2.3 Measuring and Test Equipment 4.2.4 Special Processes 4.2.5 Materials Management 4.2.6 Preventive and Predictive Mainrenance 4.2.7 Diesel Generator Program
() 4.3 Testing Activities 4.3.1 Surveillance Tests 4.3.2 Inspections 4.3.3 Initial Test Program. Startup Test Phase 4.3.4 Special Tests O 4.4 Coordiation Activities 4.4.1 Procedures 4.4.2 Manuals and Drawings 4.4.3 Data Processing Systems
() 4.4.4 Planning and Scheduling XV
5.0 Audits and Special Investigations 5.1 Audit Summaries g 5.1.1 GPC Quality Assurance Audits 5.1.2 NRC Audits 5.1.3 INPO Evaluation Visit 5.1.4 Special Audit 5.1.5 Plant E.1. Hatch Management Assistance Visit 6.0 Program Verification 4
6.1 Verification Plan 6.2 Findings and Responses 6.2.1 Summary Evaluation 6.2.2 Collective Evaluations 6.2.3 Specific Evaluations 7.0 As s es sraent 7.1 Summary of Open Corrective Action 7.2 Quality Assurance Statement 7.3 Technical Consultant Statement 7.4 General Manager Nuclear Operations 7.5 Readiness Review Board 7.6 Resumes el e
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( l.0 INTRODUCTION 1.1 SCOPE a
f- This module presents a description and evaluation of Nuclear
(_j Operations' activities for operation and support of Vogtle Electric Generating Plant (VEGP), Unit 1. The activities which comprise Module 7 include: startup and routine testing, operations, maintenance, and modification. Also included are the methods used to coordinate the activities. The activities are shown schematically on Figure 1.1-1.
The activities within the scope of this module will be fully functional when the operational quality assurance (QA) program requirements and controls are implemented at least 90 days prior to Unit 1 fuel load. However Nuclear Operations is pbasing in operations OA requirements and controls on a scheduled basis as programs are developed.
Module 7 contains descriptions of the functioning and planned elements of each activity. The adequacy of the functioning elements and the adequacy of preparations to implement the planned elements are evaluated in the module. Although health physics and chemistry are elements of each activity, they are O, discussed in Modules 9A and 9B respectively. Interfaces with the Health Physics and Chemistry Departments, as they apply to the activities, are identified in this module.
The activities in Module 7 are the responsibilities of three departments within Nuclear Operations: Operations Department, Maintenance Department, and Plant Engineering and Services Department. Support is provided by the Georgia Power Company (GPC) Engineering Liaison Departmsut (general office) and Southern Company Services (SCS) Nuclear Plant Support Department. Each department is described in this module.
Further support is provided by GPC Nuclear Engineering and Engineering and Construction Services Departments. Their functions are described in Module 5.
' O Commitments from the VEGP Final Safety Analysis Report (FSAR),
responses to generic letters and inspection and enforcement bulletins, and other official correspondence to the NRC and their implementing documents are tabulated in section 3. The audits and special investigations in section 5 took place in O 1984 and 1985. The verification in section 6 took place from June 1985 through December 1985.
Twenty-one Readiness Review Team members, having 271 years of nuclear experience, produced this module. The members were from GPC: Westinghouse Electric Corporation: Stone and Webster O Engineering Corporation: Alabama Power Company: Louisiana Power and Light: Union Electric Company: Speer Consultants, Inc; and JVS Corporation.
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MODULE 3A MODULES 5. 7,9A 98,15 DESIGN AND CONSTRUCTION MODULES g i I DESIGN ST ARTUP AND ,
I PR E&E R ATION AL I 7 7 ROUTINE F OPE R ATE 7 DECOMMISSION AND 8 ButLD TESTS A
i I MAINT AIN MOOf FY Figure 1.1-1 Life Cycle of VEGP Unit 1 i s s 34.s
l 1.2 STATUS AND SCHEDULE OF OPERATIONS ACTIVITIES This section summarizes the status of activities which support j plant operation.
1.2.1 EQUIPMENT AND PLANT STATUS CONTROLS l
Safety of personnel working on plant equipment is assured through the implementation of clearance and tagging controls.
Clearance and tagging controls are fully implemented.
i Key controls are used to control areas and protect equipment within the plant protected area. Round sheets are used to 1 record, monitor, and evaluate the status of-plant equipment.
. Round sheets and key control are implemented for systems when
, appropriate during the Initial Test Program.
j System alignments, operability status indication, and independent verification will be fully implemented by fuel load.
1.2.2 HOUSEKEEPING AND CLEANLINESS Housekeeping and cleanliness controls are implemented for areas as they are turned over from Nuclear Construction to Nuclear Operations. Nuclear Construction is responsible for
- housekeeping and cleanliness controls before area turnover. l 1
i 1.2.3 FIRE PREVENTION AND FIRE FIGHTING Fire protection training for fire brigade members has begun and i will continue as required to meet fire protection program i requirements.
I The fire protection program for any area where fuel is stored will be in place prior to receiving fuel in the specific area.
The complete fire protection program will be in place one month prior to fuel load.
i Until the time when all areas are completed, turned over, and released to the Operations Department, the Nuclear Construction
()
Department provides fire protection for the plant.
1.2.4 EQUIPMENT LABELING Valve labeling is completed as valves are turned over from 4
i O Nuclear Construction to Nuclear Operations. Approximately one-third of the 20.000 Unit 1 valves are labeled. Major
l equipment labeling began recently. Room labeling has not started. Equipment labeling will be completed by fuel load. I 1.2.5 CONTROL ROOM DESIGN REVIEW Control room architectural modifications have been completed.
Resolution of human engineering discrepancies and communications modifications are in progress. Remaining main control board g work, operating experience reviews, and control room surveys W will be completed prior to fuel load.
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l O 1.3 STATUS AND SCHEDULE OF MAINTENANCE AND MODIFICATION ACTIVITIES 1.3.1 MAINTENANCE AND INSTRUMENTATION SHOPS The primary work locations for Maintenance Department personnel i are complete. The maintenance building houses the shop and offices for mechanics. electricians, and their supervisors. The instrument shop and offices are located in the service building.
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Satellite shops are being built and will be located in the power block to provide work space and storage for contaminated tools ,
i ~ and equipment. Work involving contaminated tools and equipment ,
, will be performed in hot shops. Instrumentation support for the !
- control room will be performed in a satellite shop located near l the control room.
1.3.2 NUCLEAR OPERATIONS WAREHOUSE The Nuclear Operations warehouse and receiving dock is complete. The warehouse includes a parts storage area and office facilities. The receiving area includes space for 1
temporary storage of parts in transit and the performance of quality control inspections. An outside processing and storage O area will be constructed in 1986 for bulk weatherproof material.
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1.3.3 SPARE AND REPLACEMENT PARTS 1
Ordering of the initial allowance of spare and replacement parts is complete. Receipt of these parts is progressing and will continue into 1986. As additional spare and replacement parts are identified procurement is coordinated through the materials section. 4 l
l 1.3.4 DIESEL GENERATOR PROGRAM
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The Transamerica Delaval (TDI) Diesel Generator Owners Group modifications have been completed for Unit 1 diesel generators.
Unit 1 diesels have been inspected. Preoperational testing of the Unit 1 diesels, scheduled to begin in December 1985, will O- include TDI vendor participation.
1.3.5 WORK PLANNING GROUP O The Work Planning Group is functioning in support of the Initial Test Program. It will function in a similar manner during the operational phase.
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1.3.6 COMTROL OF MODfFICATIONS Engineering support for the operations phase of VEGP is in the planning stage. Georgia Power Company (general office) and Southern Company Services organizations for support of nuclear plants have been functioning for some time in support of the Hatch and Farley nuclear power plants. Both organizations are expanding to support VEGP. Procedures governing control of modifications are planned for approval by December 1985.
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() 1.4 STATUS AND SCHEDULE OF COORDINATION ACTIVITIES This section summarizes the status of activities which coordinate plant operations and support functions.
() 1.4.1 PROCEDURES Approved procedures for plant operations and support are 76 l percent complete. The status of the individual categories of I procedures as of November 15, 1985 is as follows: I
() Category Percent Approved Scheduled Completion Operations Department procedures 83 June 1986 Maintenance Department procedures 90 February 1986 Plant Engineering and Services 61 September 1986 Department procedures l Plant administrative procedures 72 September 1986 l
Startup Manual procedures 100 Startup test procedures 60 June 1986 1.4.2 DATA PROCESSING SYSTEMS The following subsections tell the present status of data processing systems which support plant operations.
1.4.2.1 Nuclear Plant Management Information Systems Information is being entered into the data base of the nuclear plant management information system (NPMIS). The information
() includes equipment data, preventive maintenance data, surveillance data, and inventory control data. The system is now capable of printing work orders, repetitive maintenance tasks, and shelf tags for the Nuclear Operations warehouse.
The initial scope of system functions is fully operational.
() Additional functions may be added as they are needed.
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1.4.2.2 Nuclear Plant Reliability Data System The purpose of the nuclear plant reliability data system (NPRDS)
() is to provide reliability statistics for safety-related systems and components.
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Preliminary work is being done on the system. Information will l be entered and the system will be fully operational by fuel load. g 1.4.2.3 Nuclear Network 1
Nuclear network, a computerized electronic communication system, j is fully operational and is being used by plant personnel. The ,
system allows for the exchange of information on design, construction, and operations among subscribers.
1.4.2.4 Nuclear Operations Records Management System The nuclear operations records management system is the computer system used for the retrieval of documents from the document control vault. The system is fully operational.
1.4.3 PLANNING AND SCHEDULING Planning and scheduling consists of support for startup activities. The planning and scheduling program to support the operational phase of VEGP will be fully implemented at fuel load.
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l B l ORGANIZATION AND DI'IISION OF RESPONSIBILITY
( 2.0 i This section defines the organizations involved in plant
- operations and support for VEGP. Startup testing is within the
! scope of this module: however, the Initial Test Program organization and division of responsibility is covered in Module
(} 3A. ;
, overall responsibility for the safe and reliable operation of VEGP rests with the general manager, nuclear operations. The j
, general manager delegates authority to carry out the necessary '
- I tasks to his staff. The overall Nuclear Operations organization !
j at VEGP is shown in Figure 2.0-1. Both the GPC general office and GPC's parent company, the Southern Company through its ,
service company, Southern Company Services, are providing I support to VEGP during the construction and initial testing ,
e phase and will continue to support VEGP into commercial l operation. ;
i This module discusses the duties and responsibilities of the l j superintendents designated for Module 7 on Figure 2.0-1. Their l q departments are also discussed in depth.
Two organizations which provide engineering support are also discussed in this module. They ace the GPC Engineering Liason Department at the general office and Southern Company Services i Nuclear Plant Support Department.
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} l Two organizations which support VMGP which are not discussed in this module are the Nuclear Enginoering and the Engineering and Constructica Services Departments at the general office. Both f departments are discussed in Modu.e 5.
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(} 2.1 CURRENT ORGANIZATION 2.1.1 OPERATIONS DEPARTMENT 1
The organization chart for the Operations Department is shown on l Figure 2.1-1. The organization is headed by the operations O superintendent, who reports to the manager, unit operations.
)
The Operations Department was established in the summer of 1983 when the first operators were assigned to VEGP and began training. Operation of plant equipment began in April 1984 with the first system turnover from construction. Around-the-clock O' shift operation began in fall 1984 and has been continuous since.
)
l The operations superintendent and his staff are currently j developing operating procedures, assisting with development of 1 the technical specifications, and performing a detailed control room design review. Operations supervisoro participate in the Plant Review Board, the Test Review Board, and the Work Planning Group.
l 2.1.2 MAINTENANCE DEPARTMENT A)
(_ The organization chart for the Maintenance Department is shown in Figure 2.1-2. The organization is headed by the maintenance superintendent, who reports to the initial test manager. ,
1 1
The Maintenance Department was established in 1982. Since then, I positions have been filled in order to provide support for plant 1 maintenance and the Initial Test Program.
I The maintenance superintendent has a staff that is responsible i for the maintenance of plant equipment. Reporting directly to I the maintenance superintendent are the plant materials supervisor, the controls and inst :umentation supervisor, the telecommunications supervisor, ma.ntenance supervisors, and the plant engineering supervisor.
2.1.3 PLANT ENGINEERING AND SERVICES DEPARTMENT The organization chart for Plant Engineering and Services O Department is shown in Figure 2.1 3. The organization is headed by the superintendent of plant engineering and services, who reports to the initial test manager.
The Plant Engineering and Services Department was established in 1981. The department provides technical support for other plant departments and manages & number of technical programs. The O plant engineering and r.ervices staff includes the plant engineering superviser (cost and ichedule), the plant
engineering supervisor (computers), the plant engineering supervisor (reactor engineering), the plant engineering supervisor (instrumentation), the plant engineering supervisor (mechanical), and the plant engineer (procurement review). h 2.1.4 SOUTilERN COMPANY SERVICES, NUCLEAR PLANT SUPPORT DEPARTMENT The organization chart for the Southern Company Services.
Nuclear Plant Support Department is shown in Figure 2.1-4. The lh Nuclear Plant Support Department - Vogtle Field Office will be a permanently staffed organization located on the VEGP site. This organization will be staffed with the necessary management, engineers, and technical and clerical support personnel to allow it to perform its function. The function of the Nuclear Plant Support Department - Vogtle Fielo Office is to provide support to the VEGP Nuclear Operations Department in the implementation of engineering and design changes.
2.1.5 GPC ENGINEERING LIAISON DEPARTMENT The organization chart for the GPC Engineering Liaison Department is shown in Figure 2.1-5. The organization will coordinate the activities of organizations performing engineering work affecting VEGP during the operations phase.
O O
O 00569/344-5 2.1-2 r
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Figure 2.1-1 Operations Department Organization
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PROJECT E NGIN E E R NPSD-VOGTLE F BE LD OF FICE -
1 SUPE RVISOR SUPE RVISOR SUPE RVISOR PL ANNtNG, MOD. COORD E NGIN E E RIP 9G PR E PA R A flON AND DESIGN AND AND PACK AGf NG REVIEW SECTION SUPPOR T bf C TION SECTION i
M A T E RI AL ,_ TE CHNtCAL j T ECHNfCAL COOR DINA T OR AIDE M4 AIDE a
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E NGINE E R f NGINF E R E NGINE E R E NGtNE E R i
NOTE: SHADED POstTtONS INDICATE OtSCUSSION NOT REQUIRED j Figure 2.1-4 Nuclear Plant Support Department - Vogtle Organization 1
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NOTE 1: DISCUSSION NOT REQUIRED NOTE 2: POSITIONS ARE NOT APPLICABLE TO VEGP Figure 2.1-5 Engineering Liaison Department Organization.
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~g 2.2 OPERATIONS DEPARTMENT DIVISION OF RESPONSIBILITY (G Responsibility for safe and efficient plant operation rests with the general manager, nuclear operations. Responsibilities of l Operations Department personnel are described in the following section.
(~3 xs 2.2.1 OPERATIONS SUPERINTENDENT l
The operations superintendent is responsible for the overall l
- management of the Operations Department to ensure safe and f
(~S efficient operation of VEGP. His responsibilities include:
b o Safe and efficient operation of each unit.
o Managing the housekeeping of buildings and grounds.
o Development and use of plant operating procedures. ;
i o Staffing and qualification of operations personnel.
2.2.2 SENIOR SHIFT TECHNICAL ADVISOR The cenior shift technical advisor reports to the operations
(_) superintendent. Specific duties and responsibilities include:
o Supervising the activities of shift technical advisors l not assigned shift work and monitoring the performance of on-shift shift technical advisors. )
1 l
0 Providing technical and administrative support to the l operations superintendent. 1 o Reviewing plant design changes to ensure timely revision of operating procedures.
o Maintaining emergency operating procedures and abnormal r3 operating procedures.
b o Coordinating operations experience assessment program activities pertaining to plant operation (with the Regulatory Compliance Section).
2.2.3 SHIFT TECHNICAL ADVISOR One shift technical advisor normally will be assigned to each .
operating shift. The shift technical advisor reports functionally to the on-shift operations supervisor and administratively to the senior shift technical advisor. The O, shift technical advisor provides technical and administrative
%d"$s ?
support for shift operations. Specific duties and responsibilities include:
o Providing engineering expertise during operational emergencies tr. help the on-shift operations supervisor lh and shift supervisor assess the status of the plant and to assist in implementing emergency operating procedures or abnormal operating procedures.
O Preparing reactor trip reports and assessing the status h of the plant following a reactor trip.
o Coordinating on-shift reactor engineering duties with the Plant Engineering and Services Department.
o Assisting in implementing operations surveillance h procedures and evaluating results.
o Leading the fire brigade.
2.2.4 OPERATIONS SUPERVISOR The on-shift operations supervisor reports to the operations.
superintendent. He is a senior licensed operator.
The on-shift operations supervisor is the senior operations representative on each shift and is responsible for the safe and efficient operation of the plant. His responsibilities include:
o Functioning as senior management representative for {
plant operations on shift.
o Providing approval to start the reactor (each unit).
o Declaring emergencies in accordance with the VEGP Emergency Plan and functioning as site emergency director until relieved by a higher ranking manager.
o Ensuring that plant operations are conducted in accordance with the technical specifications and ;
approved procedures. '
o Ensuring shift relief is conducted properly.
o Ensuring standing orders and night orders are carried out.
o Ensuring that the shift is properly manned.
o Ensuring notifications 7f reportable ocenrr nces are performed.
o Maintaining a broad perspective of operational conditions affecting the safety of the plant as a matter of highest priority at all times.
2.2-2
O o Not becoming involved in any single operation that distracts him when multiple operations are required in the control room. During plant transients or an emergency, he does not become totally involved in any single operation that distracts him from the rest of the operations required in the control room.
o Ensuring that shift activities are conducted in a manner that keeps personnel radiation exposures as low as responsible achievable.
o Ensuring temporary procedure changes are properly
() administered on shift. !
The operations supervisor (administration) reports to the operations superintendent. His responsibilities include:
o Functioning as operations superintendent in his absence.
o Ensuring plant operations are conducted in accordance with the technical specifications and approved procedures.
o Conducting routine administration and scheduling of operations shift activities, and coordinating these O activities with the other plant departments.
o Providing information to the Training Department for development and conduct of training and qualification of
, Operations Department personnel.
1 o Developing and maintaining personnel records.
o Serving on the Plant Review Board.
The operations supervisor (work planning) reports to the operations superintendent. His responsibilities include: 1
! O o Providing operations information to the Work Planning Group. i i
o Providing operations information to outage work schedules.
O-o performing appropriate reviews of the equipment clearance logs, o Coordinating preparation and review of plant procedures.
l o Functioning as operations superintendent when I -
designated.
I l
l j 2.2-3 L"** _
2.2.5 SHIFT SUPERVISOR One shift.
shift supervisor is assigned to each operating unit on each He is the senior operator assigned to the unit. He is -
responsible for the safe and efficient operation of the assigned unit. The shift supervisor reports to the on-shift operations supervisor and his responsibilities include:
o Ensuring that unit operations are conducted in accordance with technical specifications and approved procedures.
o Directing that the reactor be shut down when:
(1) Safety of the reactor is in jeopardy, or (2) Operating parameters exceed any of the reactor protection system trip setpoints and automatic reactor trip does not occur, or (3) Personnel or equipment safety require it, or (4) Unusual circumstances warrant it.
o Directing operational activities of the assigned unit from the control room unless properly relieved by a
, qualified person.
o Authorizing maintenance and testing activities on the assigned unit, and ensuring plant conditions are suitable for performing such activities, o Maintaining status of equipment, and determining operability of equipment upon return to service.
o Issuing equipment clearances and ensuring proper control i of tags. '
o Ensuring proper control of temporary jumpers, lifted wires, and pulled annunciator cards.
o Explaining plans, procedures, and safety precautions to shift operating personnel prior to infrequent or unusual activities.
o Ensuring shift relief is properly conducted.
o Maintaining the shift supervisor narrative log and administering logkeeping. I 1
o Controlling keys for plant operation.
o Maintaining c o nd i t i or.,
operating work spaces in a clean and orderly and ensuring good housekeeping practices by i operators assigned to the unit.
2.2-4
i i 1
5 ' o Conducting periodic safety meetings for operators on
, shift, enforcing safe practices, ensuring appropriate protective equipment is used, preparing accident reports, and obtaining medical attention, when needed.
o Limiting access to the control room.
2.2.6 PLANT OPERATOR 1
The plant operator reports to the shift supervisor. He is the
~; licensed operator assigned to operate the reictor and related '
controls from the control room. His responsibilities include:
o Maintaining the unit in a safe condition, including shutting down the reactor when safety of the reactor is 4
in jeopardy, when operating parameters exceed any of the reactor protection circuit setpoints and automatic shut-down does not occur, or when required to protect personnel and equipment.
Initiating immediate actions necessary to maintain the o
unit in a safe condition during abnormal and emergency operations.
I o Performing shift operations and surveillance testing in
() accordance with approved procedures, standing orders, and the technical specifications.
i l o Exercising continuous surveillance of unit conditions l and system parameters, remaining at the controls unless {
properly relieved.
i o Directing the assistant plant operator and the plant equipment operators to perform prescribed plant operations.
o Manipulating the controls and equipment to start up, change output, and shut down the unit as required by operating schedules and load demand.
o Maintaining the unit control log, completing rounds sheets, and maintaining recorder charts for his work j station.
o O Promptly notifying the shift supervisor of unusual conditions.
I o Remaining alert and knowledgeable of all unit operations in progress that involve the functioning of equipment controlled from the control room.
2.2-5
&6
o Directing the removal of plant equipment from operation by writing clearances and tagging orders subject to approval of the shift supervisor.
o Functioning as a team member during conduct of the VEGP Emergency Plan.
O o Coordinating startup and shutdown operations of the reactor, turbine generator, and auxiliary equipment.
o Responding to the load dispatcher's requests at the O direction of the shift supervisor.
2.2.7 ASSISTANT PLANT OPERATOR The assistant plant operator is a second licensed operator assigned to each unit.
O He reports to the plant operator or shift supervisor. He normally operates balance-of-plant equipment and controls. Specific duties and responsibilities include:
o Maintaining the unit in a safe condition, including shutting down the reactor when safety of the reactor is in jeopardy, when operation parameters exceed any of the reactor protection circuit setpoints and automatic shutdown does not occur, when required to protect personnel and equipment.
o Initiating the immediate actions necessary to maintain the unit in a safe condition during abnormal or emergency operations.
o Performing shift operations and surveillance testing in i
accordance with approved procedures, standing orders, and technical specifications.
o Exercising continuous surveillance of unit conditions and system parameters.
o Receiving direction from the plant operator.
o Completing rounds sheets for his position, maintaining recorder charts for his work station, and assisting the lh plant operator in maintaining the unit control log:
maintaining the control room in a clean and orderly condition.
o Promptly notifying the shift supervisor of unusual h conditions.
o Remaining alert and knowledgeable of all unit operations i j
in progress that involve the functioning of equipment i under his control.
1 1
2.2-6 i I
m 7
o Functioning as a team member during conduct of the VEGP Emergency Plan.
o Performing reactor core component and fuel handling operations when assigned, o Directing activities of plant equipment operators as required.
o Relieving the plant operator when authorized by the shift supervisor.
2.2.8 PLANT EQUIPMENT OPERATOR There will normally be four plant equipment operators on shift for each unit: a turbine building operator, an auxiliary building operator, an outside area operator, and a rover. The plant equipment operators report to the shift supervisor, but may also receive direction from the plant operator or assistant plant operator. Specific duties and responsibilities include:
o Performing rounds to ensure proper operation of equipment in assigned work areas.
o Executing routine shift duties as directed by the shift
{s supervisor.
o Removing equipment from service and executing clearance orders restoring equipment to service and removing clearances as directed by the shift supervisor.
o Maintaining a clean and orderly work area.
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0034g/344-5 g,,
9
O 2.3 MAINTENANCE DEPARTMENT DIVISION OF RESPONSIBILITY The Maintenance Department is responsible for ensuring the availability of an adequate inventory of spare parts, pertorming tests, and corrective and planned maintenance of plant equipment
() and components. The responsibilities of Maintenance Department personnel are provided in the following sections.
2.3.1 MAINTENANCE SUPERINTENDENT
() The maintenance superintendent is responsible for maintenance of plant equipment required for the safe and efficient operation of the plant. Specific duties include:
o Establishing department policies and procedures.
o Managing department administrative requirements such as manpower planning, budget, safety program, Plant and Test Review Board, training, action items, and special projects.
o Managing maintenance support programs for preoperational and initial startup testing.
o Developing and implementing maintenance programs for support of plant operation including work planning, planned maintenance, predictive maintenance, corrective maintenance, surveillance testing, containment testing, outage activities, and spare parts and materials storage and procurement.
o Developing and implementating the plant ASME section XI repair and replacement program. J l
1 2.3.2 MAINTENAh2E SUPERVISOR
() Maintenance supervisors are responsible for ensuring that maintenance is performed according to procedures and with a high degree of quality and efficiency. Specific responsibilities include:
o Supervising the activities of personnel to ensure that
() maintenance is performed with the highest efficiency and quality, o Assisting in planning and administering the maintenance budget to ensure an adequate supply of equipment is available to perform mainter.ance activities.
E
i o Providing necessary training and leadership to maintain a competent and productive work force.
o Providing startup support in area of responsibility necessary to meet schedules and goals of the project.
o Assisting in formulation, implementation, and monitoring of the Maintenance Department work plan.
The maintenance supervisor (work planning) is responsible for coordination of maintenance activities to ensure the safe, economical, and timely startup and operation of plant equipment. Specific responsibilities include:
o Supervising the activities of personnel to ensure that maintenance is performed with the highest efficiency and quality.
o Assisting in planning and administering the maintenance budget to ensure an adequate supply of equipment is available to perform maintenance activities.
o Providing necessary training and leadership to maintain a competent and productive work force.
o Providing startup support in area of responsibility necessary to meet schedules and goals of the project.
o Assisting in formulation, implementation, and monitoring h of the Maintenance Department work plan.
2.3.3 MAINTENANCE FOREMAN Maintenance foremen are responsible for supervising personnel performing electrical and mechanical maintenance on plant systems. Specific responsibilities include:
o Supervising personnel in performing electrical and mechanical maintenance activities to ensure the safe, efficient, economical, and timely :epair and maintenance of plant equipment.
o Determining maintenance priorities and assigning personnel accordingly.
o Assisting in scheduling and planning surveillance and maintenance to ensure that all applicable requirements are met.
o Maintaining equipment maintenance records.
o Identifying training needs for crew members.
O 2.3-2
a
.L 1
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- o Assisting in coordination of maintenance activities of )
offsite personnel. )
1 o Assisting in formulation, implementation, and monitoring of work plan and budget.
4
() The maintenance foreman (work planning) reports to the maintenance supervisor (work planning) and is responsible for coordination of mechanical and electrical maintenance activities. Specific responsibilities include: ,
o Coordinating mechanical and electrical maintenance activities, including preparation of work packages and scheduling of maintenance to ensure safe, economical, and timely maintenance of plant equipment.
a o Reviewing maintenance work packages.
The maintenance foreman (toolroom) is cesponsible for .
supervision of toolroom personnel to ensure availability of j tools, equipment, and measuring and test equipment to support i maintenance activities. Some specific responsibilities l include: I o Supervising toolroom personnel to ensure equipment I support for maintenance personnel.
o Maintaining the measuring and test equipment control program. 1 o Maintaining tool and equipment records.
j o identifying training needs for crew members. l o Assisting in coordination of maintenance activities of offsite personnel.
o Assisting in formulation, implementation, and monitoring of work plan and budget.
O 2.3.4 NUCLEAR PLANT MECllANIC AND ELECTRICIAN 3 The nuclear plant mechanics and electricians are responsible for 4
g maintaining and repairing mechanical and electrical plant j equipment. Their specific responsibilities include:
o Selecting and using proper equipment.
o Complying with license requirements ano approved plant procedures, s
4 2.3-3 ..
-, ,-- . = . . -
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2.3.5 CONTROLS AND INSTRUMENTATION SUPERVISOR The controls and instrumentation supervisor is responsible for the supervision of controls and instrumentation foremen and instrument technicians to support the Initial Test Program and plant operation. Some specific responsibilities include:
o Identifying, writing, and issuing controls and instrumentation procedures that provide guidelines and direction for Initial Test Program and commercial operation.
o Providing controls and instrumentation startup support to support scheduled activities.
o Maintaining a test equipment program which will support the Initial Test program and commercial operation.
2.3.6 CONTROLS AND INSTRUMENTATION FOREMAN Controls and instrumentation foremen report to the controls and instrumentation supervisor and supervise technicians in support of the Initial Test Program and operation. Specific responsibilities include:
o Supervising instrument technicians in the maintenance, repair, calibration, and surveillance of plant control and instrumentation equipment.
o Scheduling and coordinating the maintenance and testing of equipment with other plant personnel to ensure efficient completion of maintenance and testing.
o Ensuring calibration and surveillance procedures are
- written or updated as necessary, o Ensuring the measuring and test equipment program is carried out according to approved procedures.
o providing input to the control and instrumentation supervisor for development of control and instrumentation work plan and budget.
The controls and instrumentation foreman (work planning) reports to the maintenance supervisor (work planning) and is responsible for coordination of controls and instrumentation maintenance activities. Specific tesponsibilities include:
h o Coordinating controls and instrumentation maintenance activities, including preparation of work packages and scheduling of maintenance to ensure safe, economical, and timely maintenance of plant controls and instrumentation.
l 2.3-4
r i
.i i
- i o Review of maintenance work packages.
5 l
i ;
j 2.3.7 INSTRUMENT TECHNICIAN
- Instrument technicians are responsible for the performance of
] testing, calibration, maintenance, and repairs to plant j instruments and controls. Specific responsibilities include: i 4
2 o Complying with license requirements and approved plant procedures, and reporting of events that effect plant
() parameters.
j o Writing and revising functional test and calibration j procedures.
1 o Ordering parts and writing work orders.
i .
Certifying, tracking, and issuing measuring and test-o equipment and consumables retained in the instrument l shop.
7 i
i 2.3.8 PLANT ENGINEERING SUPERVISOR ,
The plant engineering supervisor for maintenance is responsible j
for providing engineering support for the maintenance department to support the Initial Test Program and commercial operation.
} Specific responsibilities include:
1 i o Preparing, issuing, and maintaining mechanical and j electrical maintenance procedures.
l o Developing and implementing the predictive maintenance ,
j program.
! o Providing administrative support to the maintenance
}
i superintendent and compiling individual discipline worft plans and budgets into a Maintenance Department work l .
plan and budget.
i i o Developing, implementing, and updating of an action item
{ tracking system for the maintenance department.
, o Administering an ASME Boiler and Fressure Vessel Code,Section XI. repair and replacement program.
~
j o Serving as the Maintenance Department representative to i the Plant Review Board.
l i
l',y 2.3-5
2.3.9 PLANT ENGINEER Plant engineers in the Maintenance Department are responsible for performing various engineering functions in support of the Maintenance Department. Specific responsibilities include:
o Developing and implementing the plant predictive maintenance program.
o Developing an ASME Doiler and Pressure Vessel Code,Section XI, repair and replacement program.
O o Analyzing the causes of malfunctions and resolving deficiencies in order to ensure efficient operation of plant systems.
l o Providing technical support to the Initial Test Program, o Formulating and tracking the budget and work plans for the Maintenance Department.
The plant engineer (work planning) is responsible for providing engineering support to the Work Planning Group. Specific duties include:
o Providing technical support to the Work Planning Group.
o Reviewing work orders for completeness and correctness.
o Providing engineering support for the nuclear plant management information system (NPMIS).
2.3.10 PLANT MATERIAL SUPERVISOR The plant material supervisor is responsible for the procurement, receipt, storage, handling, shipping, and issue of parts, material and supplies required for the efficient operation of the plant. Specific responsibilities include:
o Implementing and maintaining materials procedures, and maintaining established procurement and materials organization procedures and policies.
o Ensuring a sufficient stock of spare parts, material, and supplies required to support the Initial Test Program and plant operation.
o Maintaining an inventory control system. O o Interfacing with other departnents on materials-related matters.
O Preparing material section work plans and budgets.
l 2.3-6
i- imaismum
~,.
h "1 ,
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if O 2.3.11 FOREMAN (MATERIALS)
Q 3p The materials foreman is responsible for the supervision of i #5 materials personnel in the course of receipt, shipping, @
handling, storage, and issue of materials and supplies. c;i -y' Specific responsibilities include:
o Implementing and maintaining materials procedures.
o Assisting in maintaining a sufficient inventory of spare
, parts, material, and supplies for support of the Initial
(} o Test Program and plant operation.
Ensuring proper physical and commercial receipt, receipt inspections, handling, storage, issue, and shipping of spare parts, materials, and supplies at the site.
o Conducting and documenting periodic material area inspections, directing spot inventories, and assisting with maintenance of an inventory control system.
o Assisting with training of material personnel in accordance with procedures and safety standards.
o Assisting with disposal of scrap, salvage, and hazardous
() material.
o Preparing materials section work plans and budgets.
o performing duties of the materials supervisor in his absence.
2.3.12 STOREKEEPER Storekeepers are responsible for the receipt, shipping, storage, handling, and issue of materials in the Nuclear Operations warehouse in accordance with approved plant procedures.
O 2.3.13 TELECOMMUNICATIONS SUPERVISOR The telecommunications supervisor is responsible for the maintenance of plant communications equipment.
O O
0035g/350-5 2.3-7
l
- 2.4 PLANT ENGINEERING AND SERVICES DEPARTMENT DIVISION OF i RESPONSIBILITY t Overall responsibility for technical support of the plant rests with the initial test manager. Duties (other than system specific topics) of the Plant Engineering and Services
()
Department personnel are described in the following sections.
- 2.4.1 SUPERINTENDENT, PLANT ENGINEERING AND SERVICES The superintendent, plant engineering and services has the
, responsibility for technical support of VEGP. Specific duties include:
! o Providing technical support for Nuclear Operations and coordinating offsite engineering support.
o Conducting engineering surveillance tests.
o Managing plant modifications program.
i o Managing computer system support for Nuclear Operations.
o Providing cost and scheduling information for plant activities.
4 o Supervising the Nuclear Operations procurement review section. {
o Managing the equipment qualification program.
3 o Managing the plant fire protection program.
o Managing the ASME Boiler and Pressure Vessel Code, l Section XI, programs.
o Managing reactor engineering.
() o Managing plant performance monitoring.
2.4.2 PLANT ENGINEERING SUPERVISOR (COST AND SCHEDULING)
The plant engineering supervisor (cost and scheduling),
supervises personnel responsible for activiti.es within the
' Os group. The responsibilities include:
J o Supervising the advanced planning and scheduling of refueling outages and establishing a priority list of maintenance work orders to be worked.
O Preparing cost / benefit analysis of plant modifications,
, plant enhancements, or safety modifications.
-w r
i
! o Maintaining a unit specific and overall plant refueling l
and modification schedule.
o Maintaining the necessary computer support to aid in I
l planning and scheduling activities and providing lh
! graphics support.
o Preparing budgets for the superintendent, plant engineering and services.
o Maintaining a list of scheduled work to be performed O during unplanned shutdowns.
2.4.3 PLANT ENGINEERING SUPERVISOR (COMPUTERS)
I The plant engineering supervisor (computers) supervises the h personnel responsible for the activities within the group. The responsibilities include:
o Providing technical support for the plant's PROTEUS computer system.
o Developing procedures for computer modifications.
o Providing technical support for the security system. ,
o Developing plant performance procedures.
o Monitoring plant performance.
o Developing the nuclear plant reliability data system (NPRDS).
o Providing technical assistance for users of personal computers and minicomputers.
o Providing technical support for the nuclear plant management information system (NPMIS).
2.4.4 l PLANT ENGINEERING SUPERVISOR (REACTOR ENGINEERING) ;
The plant engineering supervisor (reactor engineering) h '
supervises the personnel reEponsible for the activities within the group. The responsibilities include:
o Preparing and performing reactor engineering procedures, j refueling procedures, and special nuclear material l procedures. '
o Receiving, inspecting, storing, and inventorying the nuclear fuel.
O 2.4-2 m oe w-sw+=4 -me om
1
- /"' o Performing or supervising technical specification surveillances regarding hot channel factors, nuclear burnup, and power distribution limits.
o Supervising physics tests as defined in the technical specifications.
o Reviewing pertinent plant operating data to ensure the safety and effectiveness of plant equipment and i procedures.
I' 2.4.5 i (s)T PLANT ENGINEERING SUPERVISOR (INSTRUMENTATION)
The plant engineering supervisor (instrumentation) supervises the personnel responsible for the activities within the group.
+
The responsibilities include:
o Performing design reviews and providing technical advice for electrical and instrumentation related functions.
o Ensuring assigned surveillance tests are completed on schedule, 1*
o Coordinating revision to protective device setting data sheets and instrument scaling data sheets.
%)
2.4.6 PLANT ENGINEERING SUPERVISOR (MECEIANICAL)
The plant engineering supervisor (mechanical) supervises the personnel responsible for the activities within the group.
r es pons ibilit ies include:
The o Performing design reviews and providing technical 4
advice.
j o Coordinating the fire protection program.
O' o Supervising the preservice and inservice examination of 1
welds and the reactor vessel.
o Providing technical support and coordination with the Operations Department for preservice and inservice testing of pumps and valves.
o Providing technical support and coordination with the Maintenance and Quality Control Department for preservica and inservice testing of snubbers and hangers.
O o Supervising the eddy current examination of steam generators.
2.4-3
2.4.7 PLANT ENGINEER Plant engineers perform various functions within the department. The responsibilities include:
lf o Evaluating requests for engineering review.
o Preparing requests for offsite engineering assistance.
o Coordinating design changes requests and design package preparation and implementation. lh o Preparing as-built notices.
o Analyzing program critical paths.
o Analyzing outage schedules. O o Evaluating schedule change requests for impact to existing test programs.
o Ensuring that schedules comply with project procedures, o Providing technical support of the PROTEUS computer.
o Providing technical support of the security system.
o Monitoring plant performance.
o Maintaining the NPRDS data base.
o Providing technical assistance in support of personnel computers and minicomputers.
o Providing technical support for NPMIS.
o Reviewing changes to computer software.
o Preparing and performing reactor engineering procedures, refueling procedures, and special nuclear material procedures.
o Receiving, inspecting, storing, and inventorying the h nuclear fuel.
o Staying abreast of recent regulatory changes and operational experience.
o Performing or supervising technical specification surveillances regarding hot channel factors, nuclear h burnup, and power distribution limits.
O 2.4-4
N o Supervising physics tests as defined in the technical
. specifications.
o Reviewing pertinent plant operating data to ensure the safety and cost effectiveness of plant equipment and procedures.
o Training of other plant personnel as necessary in core physics and fuel surveillance.
o Analyzing plant electrical systems design and the
- details of design change implementation.
o Analyzing and generating setpoints applied to control and protective instrumentation.
o Supervising tests and other data gathering activities which supplement or support plant electrical systems design or operation.
o Responding to questions or concerns raised by regulatory or other agencies concerning plant electrical systems design or operation.
o Providing representation to the steam generator owners g group.
U o Reviewing and evaluating inservice surveillance test 4 results.
o Reviewing inservice inspection plans and programs, o Coordinating inservice inspection and testing.
Plant engineers (fire protection) are responsible for ensuring
, the effective implementation of the fire protection program. Specific responsibilities include:
4 o Reviewing and evaluating fire protection surveillance tests and test results.
o Ensuring that fire protection records are maintained properly.
1 o performing periodic inspections to assess the effectiveness of fire protection and administrative k'_")% controls.
o Periodically reviewing work activities to ensure that fire protection concerns are being addressed.
4 o Assisting in the critiquing of fire drills to determine
{~}/
- s. the effectiveness of training.
1 2.4-5 a _ - - - - -~
o Ensuring that the plant fire fighting equipment is compatible with the equipment of offsite fire departments.
o Providing technical guidance to the superintendent O
nuclear training in developing the fire training program.
o Ensuring the availability and adequacy of fire fighting equipment.
The plant engineer (procurement review) is responsible for the review of procurement documents and maintaining the environmental and seismic qualification of safety-related equipment. His responsibilities include:
o Supervising the review of requisitions to ensure that appropriate technical and quality requirements are specified and documentation reviewed is technically adequate.
o Supervising the activities of the equipment materials documentation engineer.
o Ensuring personnel assigned to the procurement review section are qualified to perform their job functions.
o Ensuring the environmental and seismic qualification of safety-related equipment is maintained by assisting and g supervising the equipment qualification eng}.neers. W i
l 1
0 00369/346-5 lh 2.4-6
2.5 SOUTHERN COMPANY SERVICES, NUCLEAR PLANT SUPPORT DEPARTMENT DIVISION OF RESPONSIBILITY Responsibilities of Southern Company Services, Nuclear Plant Support Department are described in the following sections:
2.5.1 MANAGER, NUCLEAR PLANT SUPPORT DEPARTMENT - VOGTLE l i
The manager, nuclear plant support department - Vogtle will have the responsibility for matters relating to the design and O engineering required for the operational support of VEGP.
Responsibilities include: j o Managing design and engineering tasks assigned by GPC in the Birmingham home office.
o Providing administrative and technical direction for the Nuclear Plant Support Department - Vogtle Field Office, o Managing design and engineering tasks assigned by GPC that require interface with vendors or other '
architect / engineering firms.
o Ensuring that Nuclear Plant Support Department - Vogtle
() maintains a qualified staff and that required support functions from other Southern Company Services l
departments are available~to support plant operation.
o Providing budget and schedule directicn for the Nuclear Plant Support Department Vogtle.
I 2.5.2 PROJECT ENGINEER, NUCLEAR PLANT SUPPORT DEPARTMENT -
VOGTLE FIELD OFFICE The project engineer, nuclear plant support department - Vogtle field office, will direct the operation of the field support p group. He will report to the manager, nuclear plant support
\_/ department - Vogtle for administrative and technical direction, and to the superintendent, plant engineering and services for functional direction. Responsibilities include:
o Keeping management advised of the status of in-progress design changes.
o Assisting Nuclear Operations in coordinating plant activities related to design change implementation.
o Assembling design change packages for implementation.
o Providing plant engineering and planning support to the implementation group for design changes.
3
5 o Producing plant design changes within guidelines of design approval authority.
, 2.5.3 SUPERVISOR, MODIFICATION COORDINATION AND REVIEW SECTION O
The supervisor, modification coordination and review section, will report to the project engineer, nuclear plant support department - Vogtle field office. Responsibilities include:
o Reviewing design change requests for clarity and cost estimation.
o Reviewing design change notices for completeness and usability.
o Preparing required tests for design changes.
l o Providing supervision for the engineers assigned to the
)
section.
l l
2.5.4 ENGINEER, MODIFICATION COORDINATION AND REVIEW SECTION l The engineers assigned to this section will be responsible for performing the tasks listed as the responsibilities of the section supervisor. This staff of engineers will be made up of personnel from the electrical, mechanical, civil, and instrument and control disciplines. Responsibilities include:
h o Identifying materials necessary for the implementation of design changes.
o Developing draft requisitions for material required to implement design changes.
o Assembling implementation packages and delivering completed packages to Nuclear Operations.
o Identifying and preparing installation test procedures.
o Tracking the status of design change packages.
2.5.5 LEAD ENGINEER AND ENGINEER, PLANNING, PREPARATION, AND PACKAGING SECTION The lead engineers and engineers assigned to the planning, preparation, and packaging section will perform the sectiot responsibilities for their area of engineering.
O 2.5-2
2.5.6 MATERIAL COORDINATOR, PLANNING, PREPARATION, AND PACKAGING SECTION The material coordinator will report to the project engineer, nuclear plant support department - Vogtle field office.
Responsibilities include:
o Reviewing the draft requisitions prepared by the J planning, preparation, and packaging section. 1 l
o Maintaining the status of material purchaces required for implementation of design changes. l o Providing information to the section on material cost in I support of the preparation of cost estimates for design j change packages. j l
2.5.7 SUPERVISOR. ENGINEERING DESIGN AND SUPPORT SECTION l
The supervisor, engineering design and support section will {
report to and receive direction from the project engineer, nuclear plant support department - Vogtle field office.
Responsibilities include:
() o Developing field isometric drawings to facilitate the installation of pipe instrumentation, conduit, and other field work.
o Preparing as-built notices and drawings.
o Providing plant drafting services.
o Providing field pipe support designs.
o Preparing and issuing design changes within the scope of the field office approved design authority.
2.5.8 ENGINEER AND DESIGNER, ENGINEERING DESIGN AND SUPPORT SECTION The engineers and designers assigned to this section will be responsible for the engineering and design required to accomplish the tasks listed as responsibilities of the O supervisor of this section.
2.5.9 TECHNICAL SPE7IALIST, ENGINEERING DESIGN AND SUPPORT SECTION The responsibilities of the technical specialist will be to support the section in areas such as stress analysis, support design, and code and standard requirements.
00389/350-5 2.5-3
O 2.6 GPC ENGINEERING LIAISON DEPARTMENT DIVISION OF RESPONSIBILITY Responsibility for the efforts of this department lies with the manager, engineering liaison.
() The responsibilities of Engineering Liaison Department are provided in the following sections. personnel At the present, E. I. this organization is being developed in support of Hatch Nuclear Electric Plant. By the time VEGP requires this group's support, its final form will be
() established.
organization. The VEGP organization will parallel the Hatch 2.6.1 VOGTLE ENGINEERING LIAISON MANAGER The Vogtle Services engineering liaison manager is a Southern Company (SCS) engineering liaison employee who reports functionally to the manager but technically and administratively to the manager, nuclear plant support department-Vogtle. The manager, engineering liaison is the Nuclear Operations Department. responsible for supporting requests from He will be responsible t'or determining the The responsibilities ofscope of work and assigning the work to SCS.
this position include:
o v Supervising engineers under his direction and documenting their performance.
o Assuring assigned, successful, on-time completion of all work o
Providing information for budgets.
o Serving as the focal point for liaison work between the plant and SCS, SCS subcontractors, or vendors.
o Keeping to VEGP. abreast of industry occurrences that may apply O o Assuring VEGP uniformity and the of information application E. I. Hatch to both Nuclear Plant.
2.6.2 ENGINEER O
The engineers are SCS employees with administrative, functional, and liaisontechnical manager.tiesTheidentical to those of the Vogtle engineering responsibilities include:
o Reviewing and approving material O o requisitions.
Reviewing vendor for engineering information notices, issuing requests assistance.
o Reviewing, approving, distributing, and tracking of design change requests.
o Writing and reviewing procedures.
o Keeping abreast of engineering codes and standards and their applications.
O O
O l
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O 0044g/351-5 h 2.6-2
2.7 SIGNIFICANT ORGANIZATION CHANGES There have been no significant changes in the Operations i
Department or Maintenance Department since the issuance of Module 5.
() A change in the Plant Engineering and Services Department was the division of startup and system-specific activities under a new position, the superintendent, engineering (liaison). This supports the current needs of.the Initial Test Program and future needs for system-specific technical support.
() Georgia Power Company (GPC) and Southern Company Services (SCS)
~
have provided support'to tne Farley and Hatch Nuclear plants for years. Recent changes have defined how these organization will support VEGP.
l I
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O O
0037g/344-5
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() 3.0 COMMITMENTS This section contains a listing of licensing and project ;
commitments and the corresponding implementing documents '
applicable to plant operations and support. These are presented in two matrixes, the commitment matrix and the implementation
()
matrix. A brief explanation of the development process for each matrix is also included.
l l
Differences between the commitments discussed in this section l and the FSAR are unintentional, and the FSAR prevails. ;
1 I'
\ Additionally, the Project has a commitment to comply with j 10 CFR 50, Appendix B, Quality Assurance Criteria, and other i
commitments such as ANSI 18.7. Although they were not identified as specific commitments in this module. Readiness Review considered the applicable requirements of these types of !
commitments in preparing and assessing the scope of work '
represented by this module.
l O
l C:) 00399/351-5 l
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l
i l
4
- 3.1 DEFINITIONS i i Commitments are defined as project obligations to regulatory ;
- guides, industry; standards, branch technical positions -and -!
other licensing requirements to the extent defined in the FSAR 1 and other official documents. An implementing document is-a
{. working level document that fulfills a project commitment
- applied to a specific activity.
ld f
G 6
6 i
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O 0040g/351-5
~ g , e,
'8 -- - . - , _ . , _ _ _ _ _ _ _ _ _ _ , _ _
I
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3.2 COMMITMENT MATRIX
\
Commitments covered by this report are identified from the i following sources: j o FSAR, including chapter 6 to the technical )
() specifications and responses to NRC questions.
o Responses to generic letters.
o Responses to inspection and enforcement bulletins.
) o Self-initiated correspondence.
These sources are reviewed for commitments based upon guidelines developed from the definition (section 3.1).
Once identified, the commitments are placed on the commitment matrix. The matrix includes:
o Commitment source.
O Source section and subject.
o The commitment itself (document or feature). l o The title of commitment document (if applicable).
o Module or modules to which the commitment is 1 applicable.
Any relevant comments concerning the commitments or subject of a l
! section are indicated in the remarks column. {
l The commitment matrix is presented as Table 3.2-1. Commitments on t he table are accurate as of October 15, 1985. This repr esents amendment 18 to the FSAR.
O I
O O
- 004'.g/346-5 l
l
4V c. o MITENTS I SORTED BY SOURCE AND SECTION COPWITENT (X)Pm t1ENT CDPMITENT DOCUENT/
NUPEER SOURCE SECT 10N S4BJECT FEATURE T1TLE PODULE EMARKS EXPLANATION OF FIELDS NL9EER - A reference number that corresponds to the appropriate line entry in tne implementation matrix '
I COPNITMENT SOURCE - The document containing the commitment (FSAR, Generic Letter, I.E. Bulletin Response, etc.)
COPmlT ENT SECTION - identifies the FSAR section, letter number, or question nunber l
[
s C0pelTENT SUBJECT - The subject of the FSAR section or Generic Letter
- DOCUMENT / FEATURE - The document discussed in the FSAR section or the plant feature described in the FSAR section TITLE - T itle of the conrni tment '
MODULE - The Readiness Review modules applicable to the commitment under discussion i
i i
i 5
. _ . . _ _ m.. . . .._m_ . . . ~ . - . . . - . _ _ . _ . ._.__.___.._..m._ . . . . _. ._. ._ .m.. _ .. _
Pste No. I r- TABLE 3.2-f COMMITMENTS FOR PLANT
===========================, j OPERATIONS AND SUPPORT c' ================
COMMITMENT DOCUMENT / FEATURE TITLE MODULE REMARES NUMBER COMMITMENT COMMITMENT
' SOURCE SECTION SUBJECT
== ========== ================ ==================== ====================== ================ ====== ==============
I r
2706 FSAR 1. 2. 2.8 UNIT SEPARATION PRIOR TO START OF UNIT 07 1 OPERATION, ELECTRICAL, VENTILATION, AND PROCESS STSTEMS IN CONSTRUCTION AREA C7 UNIT 1 ARE SEGREGATED ;
FROM SIMILAR STSTEMS IN THE CONSTRUCTION AREA 0F UNIT 2.
i 2707 FSAR I. 2, 2.C UNIT SEPARATION ACCESS BETWEEN THE 07 UNIT UNDER CONSTRUCTION AND THE OPERATING UNIT IS CONTROLLED.
72R FSAR I. 2. 2.E PLANT STATUS SRARED STSTEMS AND 07 CONTROLS INTERFACES BETWEEN UNITS WILL BE ISOLATED FROM UNIT 2 AND/OR COMPLETED AND CRECEED OUT FOR UNIT I PRIOR TO START OF OPERATION OF UNIT 1.
729 FSAR 1. 9. 6 PLANT STATUS RG 1.6, MARCR 1971 INDEPENDENCE 07. CON FO RM ANC E IS CONTROLS BETWEEN DISCUSSED IN SECTION REDUNDANT 1.9.6.2 OF THE FSAR.
STANDBT (ONSITE)
PONER SOURCES AND BETWEEN THEIR DISTRIBUTION STSTEMS i
730 FSAR I. 9. 7 OPERATIONS RG 1.7, R/2 CONTROL OF 07 CONFORMANCE IS FACILITIES AND- COMBUSTIBLE GAS DISCUSSED IN SECTION EQUIPMENT CONCENTRATIONS 6.2.5.1.1 OF TRE IN CONTAINMENT FSAR.
l FOLLOWING A LOSS OF COOLANT
- { ACCIDENT ,
(
,C
__.-._2. . _ _ . . _ _ _ . _ _ _ _ _ _ _ _ _ . , _ _ _ _ . _ , , . , . _ _ _ _ _ _ _ _ _ , , _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ___ _
Page No. 2 12/02/85
, TABLE 3.2-1 COMMITMENTS FOR PLANT
======================
OPERATIONS AND SUPPORT
-=========e===
COMMITMENT DOCUMENT / FEATURE TITLE MODULE REMARES NUMBER COMMITMENT COMMITMENT SOURCE SECTION SUBJECT
== ========== ================ ==================== =============== ====== ====-=========== ====== ==============
20 VIBRATION A SS E S SM r.N T RG 1.20 R/2 COMPRERENSIVE 03A,07 CONFORMANCE IS 743 FSAR 1. 9.
PROGRAM VIBRATION DISCUSSED IN SECTION ASSESSMENT SECTION 3.9.N.2.4.
PROGRAN FOR OF THE FSAR.
REACTOR INTERNALS DURING PREOPERATIONAL AND START-UP TESTING.
- 1. 23 ONSITE RC 1.23, FEBHUARY 1972 ONSItB 07.9A, CONFORMANCE IS 746 FSAR 9.
METEOROLOGICAL METEOROLOGICAL 15 DISCUSSED IN SECTION PROGRAMS PROGRAMS 1.9.23.2 OF THE FSAR.
753 FSAR 1. 9. 30 INSTHUMENTATION AND RG 1.30 AUGUST 1972 QUALITT 03A,05 CONFORMANCE IS ELECTRICAL QA ASSURANCE 07,98 DISCUSSED IN SECTION REQUIREMENTS REQUIREMENTS FOR 1.9.30.2 OF TRE TRE FSAR.
INSTALLATION, INSPECTION AND TESTING OF INSTRUMENTS AND ELECTRICAL EQUIPMENT 754 rSAR 1. 9. 30 INSTRUMENTATION AND ANSI N45.2.4-1972 INSTALLATION, 03 A,05 CONTORMANCE IS ELECTRICAL QA INSPECTION AND 07,9B DISCUSSED IN SECTION PROGRAMS TESTING 1.9.30.2 OF THE REQUIREMENTS FOR FSAR.
INSTRUMENTS AND ELECTRICAL EQUIPMENT DURING CONSTRUCTION OF MUCLEAR POWER PLANTS 755 FSAR 1. 9. 31 MATERIALS MANAGEMENT RG 1.31, R/3 CONTROL OF 07 CONFORMANCE IS FERRITE CONTENT DISCUSSED IN SECTION IN STAINLESS 1.9.31.2 OF TRE i STEEL WELD FSAR.
MATERIAL O O O O O O O
Page No. 3 ,
12/02/85 TABLR 3.2-1 COMMITMENTS FOR PLANT F
=3e===================
OPERATIONS AND SUPPORT e ================== ==
NUMBER COMMITMENT COMMITMENT DOCUMENT / FEATURE TITLE MODULE REMARES COMMITMENT SOURCE SECTION SUBJECT *
====== == ========== ===============s =========== ======== ====================e= ================ ====== ==================== r 764 1. 33 QUALITY ASSUHANCE RG 1.33 R/2 QUALITY 02.05, CONFORMANCE IS j FSAR 9.
07,9A, DISCUSSED IN SECTION PROGRAM REQUIREMENTS ASSURANCE ,
(OPBEATION) PROGRAM 95.15 1.9.33.2 0F THE REQUIREMENTS FSAR.
(OPERATION) 765 FSAR 1. 9. 33 QUALITY ASSURANCE ANSI 18.7-1976 ADMINISTRATIVE 02.05, CONFORMANCE IS PROGRAM REQUIREMENTS CONTROLS AND 07,9A. DISCUSSED IN SECTION j (OPERATION) QUALITY 98.15 1.9.33.2 0F THE ASSURANCE FOR FSAR.
THE OPERATIONAL PEASE OF NUCLEAR POWER PLANTS !
4 768 FSAR 1. 9. 35 MAINTENANCE RG 1.35 R/2 INSERVICE 07 CONFORMANCE IS l PROCEDURES AND INSPECTION OF DISCUSSED IN SECTION ,
DOCUMENTATION UNGROUTED 1.9.35.2 0F THE TENDOMS IN FSAR.
PWESTRESSED CONCRETE CONTAINMENT STRUCTURES t
769 FSAR 1. 9. 36 MAINTENANCE RG 1.36 FEBRUARY 1973 NONMETALLIC 07 CON FORM ANCE IS PROCEDURES AND TRERMAL DISCUSSED IN SECTION DOCUMENTATION INSULATION FOR 1.9.36.2 0F TRE AUSTENITIC FSAR.
STAINLESS STEEL l
774 FSAR 1. 9. 37 REQUIREMENTS FOR RG 1.37, MARCH 1973 QUALITY 03A,05 CONFORMANCE IS CLEANING FLUID ASSURANCE 07,98 DISCUSSED IN SYSTEM REQUIREMENTS FOR SECTIONS 14.2.17.1 ,
CLEANING OF AND 1.9.37.2 0F THE FLUID SYSTEMS FSAR.
AND ASSOCIATED COMPONENTS OF WATER-COOLED NUCLEAR POWER PLANTS
(
- (
Page No. 4 12/02/85 TABLE 3.2-1 COMMITMENTS FOR PLANT e === =====================-======
OPERATIONS AND SUPPORT
-===============
DOCUMENT / FEATURE TITLE MODULE REMARKS NUMBER COMMITMENT COMMITMENT COMMITMENT SOURCE SECTION SUBJECT
=== == ========== ================ ==================== ====================== ================ ====== ================-
37 REQUIREMENTS FOR ANSI N45.2.1-1973 CLEANING OF 03A,05 CONFORMANCE IS 775 FSAR 1. 9.
CLEANING FLUID FLUID SYSTEMS 07,98 DISCUSSED IN SYSTEM AND ASSOCIATED SECTIONS 14.2.17.1 COMPONENTS AND 1.9.37.2 0F THE DURING FSAR.
CONSTRUCTION PHASE OF NUCLEAR POWER PLANTS
ASSURANCE DISCUSSED IN SECTION REQUIREMENTS FOR 1.9.38.2 OF THE PACKAGING, FSAR.
SHIPPING, RECEIVING, STORAGE AND HANDLING OF ITEMS FOR WATER-COOLED NUCLEAR POWER PLANTS 780 FSAR 1. 9. 38 MATERIALS MANAGEMENT ANSI M45.2.2-1972 PACEAGING, 05,07 CONFORMANCE IS SHIPPING, DISCUSSED IN SECTION RECEIVING, 1.9.38.2 0F THE STORAGE AND FSAR.
HANDLING OF ITEMS FOR NUCLEAR POWER PLANTS 784 FSAR 1. 9. 39 CONDUCT OF RG 1.39, 2/2 HOUSEKEEPING 03A,05 OPERATIONS REQUIREMENTS FOR ,07,9A WATER-COOLEL 98 NUCLEAR PC'WER PLANTS 785 FSAR 1. 9. 39 CONGUCT OF ANSI N45.2.3-1973 HOUSEEEEPING 03A,05 OPERATIONS REQUIREMENTS FOR 07,9A A WATER-COOLED 98
- 1 NUCLEAR POWER
, PLANTS I
O O O O O O O
O O O O O- O O Page No. 5 12/02/85 TABLE 3.2-1 COMMITMENTS FOR PLANT
======================
OPERATIONS AND SUPPORT
-===== ===============
NUMBER COMMITMENT COMMITMENT COMMITMENT DOCUMENT / FEATURE TITLE MODULE REMARKS I SOURCE SECTION SUBJECT
= == ========== ================ ==================== ========= =e========== ================ ====== ================
787 FSAR 1. 9. 40 TECHNICAL SUPPORT RG 1.40, MARCR 1973 QUALIFICATION. 07 CONFORMANCE IS PROCEDURES AND TESTS OF DISCUSSED IN SECTION DOCUMENTATION CONTINUOUS-DUTY 1.9.40.2 0F THE MOTORS INSTALLED FSAR.
INSIDE THE CONTAINMENT OF NATER-COOLED NUCLEAR POWER PLANTS 789 FSAR 1 " 45 OPERATIONS RG 1.45, MAY 1973 REACTOR COOLANT 07 CONFORMANCE IS FACILITIES AND PRESSURE DISCUSSED IN SECTION EQUIPMENT BOUNDARY LEAEAGE 5.2.5 OF THE FSAR.
DETECTION SYSTEM 790 FSAR 1. 9. 47 PLANT STATUS RG 1.47, MAY 1973 BYPASSED AND 07 CONFORMANCE IS CONTROLS INOPERABLE DISCUSSED IN STATUS SECTIONS 7.5.5 AND INDICATION FOR 10.4.9.5 0F THE NUCLEAR POWER FSAR.
PLANTS SAFETY SYSTEMS 793 FSAR 1. 9, 52 ATMOSPHERE CLEANUP RG 1.52 R/2 DESIGN, TESTING, 03A,07 CONFORMANCE IS SYSTFM AND MAINTENANCE DISCUSSED IN SECTION CRITERIA FOR 1.9.52.2 0F THE POST ACCIDENT FSAR.
ENGINEERED SAFETY FEATURE ATMOSPEERE l CLEANUP SYSTEM, AIR FILTRATION AND ADSORPTION UNITS FOR LIGHT WATER COOLED NUCLEAR POWER PLANTS.
I 794 FSAR 1. 9. 52 ATMOSPRERE CLE ANUP ANSI M509-1980 NUCLEAR POWER 03A,07 CONFORMANCE IS SYSTEM PLANT AIR DISCUSSED IN SECTION CLEANING UNITS 1.9.52.2 0F THE
, AND COMPONENTS FSAR.
C
. ~ . - _ .
Page No. 6 12/02/85 TABLE 3.2-1 COMMITMENTS FOR PLANT
======================
OPERATIONS AND SUPPORT
==========
NUMBER COMMITMENT COMMITMENT COMMITMENT DOCUMENT /FCATURE TITLE MODULE REMARES SOURCE SECTION SUBJECT A ====== == ===e====== ================ ==========e========= ====================== ================ ====== ====================
795 FSAR 1. 9. 52 ATMOSPHERE CLEANUP ANSI N510-1980 TESTING OF 03A,07 CONFORMANCE IS STSTEM NUCLEAR AIR DISCUSSED IN SECTION CLEANING SYSTEMS 1.9.52.2 OF THE FSAR.
796 FSAR 1. 9. 54 MAINTENANCE HG 1.54 R/l QUALITT 07 CONFORMANCE IS PROCEDURES AND ASSURANCE DISCUSSED IN SECTION DOCUMENTATION REQUIREMENTS FOR 1.9.54.2 OF THE PROTECTIVE FSAR.
COATINGS APPLIED TO WATER COOLED NUCLEAR REACTOR PLANTS 797 FSAR I. 9. 54 MAINTENANCE ANSI N101.4-1972 QUALITT 07 CONFORMANCE IS PROCEDURES AND ASSURANCE DISCUSSED IN DOCUMENTATION REQUIREMENTS FOR SECTIONS 1.9.54.2 PROTECTIVE AND 6.1.2.1 OF THE COATINGS APPLIED FSAR.
TO NUCLEAR FACILITIES 804 FSAR 1. 9. 64 DESIGN CHANGE RG 1.64 R/2 QUALITT 05,07 CONFORMANCE IS CONTROL ASSURANCE DISCUSSED IN SECTION REQUIREMENTS FOR 1.9.64.2 OF THE THE DESIGN OF FSAR.
NUCLEAR POWER PLANTS 805 FSAR 1. 9. 64 DESIGN CHANGE ANSI M45.2.ll-1974 QUALITT 05.07 CONFORMANCE IS CONTROL ASSURANCE DISCUSSED IN SECTION REQUIREMENTS FOR 1.9.64.2 OF THE THE DESIGN OF FSAR.
MUCLEAR POWER PLANTS 806 FSAR 1. 9. 65 MAINTENANCE RG 1.65. OCTOSER 1973 MATERIALS AND 07 CON FO RM ANC E IS PROCEDURES AND INSPECTIONS FOR DISCUSSED IN SECTION DOCUMENTATION REACTOR YESSEL 1.9.65.2 OF THE CLOSURE STUDS FSAR.
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2 O Page No. 7 '
12/02/85 TABLE 3.2-1 COMMITMENTS FOP PLANT
3==t====3====%====t======="=
OPERATIONS AND SUPPORT -
4 TITLE MODULE REMARES COMMITMENT COMMITMENT DOCUMENT / FEATURE NUMBER COMMITMENT SOURCE SECTION SUBJECT
== ========== ===-============ =================e== =============_======== ================ ====== ==============
R/2 INITIAL TEST 03A,07 CONFORMANCE 15 i 808 FSAR 1. 9. 68 INITIAL TEsi PROGRAM RG 1.G8 PROGRAMS FOR DIECUSSED IN WATER-COOLED SECTIONS 1.9.68.2 NUCLEAR PONER AND 14.2 0F THE PLANTS FSAR.
INITIAL TEST PROGRAM RG 1.68.2, R/l INITIAL STARTUP 03A 07 CONFORMANCE IS ,
811 FSAR 1. 9. 68. 3 TEST PROGRAMS TO DISCUSSED IN CHAPTER DEMONSTRATE 14 0F THE FSAR.
REMOTE SHUTDOWN CAPABILITY FOR NATER-COOLED NUCLEAR PONER PLANTS DECEMBER 1973 WELDER 07 CONFORMANCE IS 815 FSAR 1. 9. 71 WELDER QUALIFICATION EG 1.71 DISCUSSED IN QUALIFICATIONS FOR AREAS OF SECTIONS 1.9.71.2 LIMITED AND 5.2.3 0F THE ACCESSIBILITY FSAR.
RG 1.73 JANUARY 1974 . QUALIFICATION 07 CON FO RM A NC E IS 816 'SAR 1. 9. 73 TECHNICAL SUPPORT DISCUSSED IN SECTION PROCEDURES AND TESTS OF ELECTRIC VALVE 1.9.73.2 0F THE DOCUMENTATION OPERATORS FSAR.
INSTALLED INSIDE 1
THE CONTAIMMENT OF NUCLEAR POWER PLANTS 1
RG 1.82 JUNE 1974 SUMPS FOR 07 CONFORMANCE IS 820 FSAR 1. 9. 82 OPERATIONS FACILITIES AND EMERGENCY CORE DISCUSSED IN SECTION l
EOUIPMENT COOLING AND 1.9.82.2 0F THE CONTAINMENT FSAR.
SPRAY SYSTEMS I INSERVICE 07 THE INSERVICE FSAR 1. 9. 83 TECHNICAL SUPPORT RG 1.83 R/l 821 INSPECTION OF INSPECTION PROGRAM PROCEDURES AND IS DISCUSSED IN THE I DOCUMENTATION PRESSURIZED WATER REACTOR TECH. SPEC.
! STEAM GENERATOR TUBES
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Page No. 8 12/02/R5 COMMITMENTS FOR PLANT TABLE 3.2-1 =======
,,=,=e======,==========-==
OPERATIONS AND SUPPORT
=-========
DOCUMENT / FEATURE TITLE MODULE REMARES NUMBER COMMITMENT COMMITMENT COMMITMENT SOURCE SECTION SUBJECT ====== ====================
e=====e=
== = =======- ================ ==================== ================
RG 1.89, NOVEMBER 1974 QUALIFICATION OF 07 CONFORMANCE IS 826 FSAR 1. 9. 89 TECHNICAL SUPPORT DISCUSSED IN SECTION PROCEDURES AND CLASS lE EQUIPMENT FOR 1.9.89.2 OF THE DOCUMENTATION FSAR.
NUCLEAR POWER PLANTS RG 1.93, DECEMBER 1974 AVAILABILITY OF 07 CONFORMANCE IS IN 827 FSAR 1. 9. 93 PLANT STATUS ACCORDANCE WITH THE CONTROLS ELECTRIC POWER SUPPLIES TECHNICAL SPECIFICATIONS.
RG 1.95, R/l PROTECTION OF 07 CONFORMANCE IS 828 FSAR I. 9. 95 OPERATIONS NUCLEAR POWER DISCUSSED IN SECTION FACILITIES AND 6.4.4.2 OF THE FSAR.
EQUIPMENT PLANT CONTROL ROOM OPERATORS AGAINST AN ACCIDENTAL CRLORINE RELEASE
- 1. 9. 97 POST ACCIDENT RG 1.97 R/2 INSTRUMENTATION OT,9A, CONFORMANCE IS 829 FSAR 98 DISCUSSED IN SECTION INSTRUMENTATION FOR LIGHT-WATER-COOL 7.6 OF THE FSAR.
ED NUCLEAR POWER PLANTS TO ASSESS PLANT CONDITIONS DURING AND FOLLOWINO AN ACCIDENT INSTRUMENT SETPOINTS RG 1.105, R/l INSTRUMENT 07 CONFORMANCE IS 832 FSAR 1. 9.105 DISCUSSED IN SECTION SETPOINTS 7.1 OF THE FSAR.
THERMAL OVERLOAD RG 1.106 R/l THERMAL OVERLOAD 03A,07 CONFORMANCE IS 833 FSAR 1. 9.106 PROTECTION FOR MOTOR PROTECTION FOR DISCUSSED IN SECTION OPERATED VALVES ELECTRIC MOTORS 1.9.106.2 OF TRE ON FSAR.
MOTOR-OPERATED VALVES 3
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'O o Pete No. 9 12/02/85 TABLE 3.2-1 COMMITMENTS FOR PLANT
============================.====e OPERATIONS AND SUPPORT
==========
COMMITMENT DGCUMENT/FEkfURE TITLE MODULE REMARES NUMBER COMMITMENT COMMITMENT SOURCE SECTION SUBJECT
== ========== ================ ==================== ====================== ================ ====== ==============
DIESEL GENERATOR RG 1.108 R/l PERIODIC TESTING 03A,07 CONFORMANCE IS IN 835 FSAR 1. 9.108 ACCORD ANCE WITH THE TESTING OF DIESEL GENERATOR UNITS TECHNICAL USYD AS ONSITE SPECIFICATIONS.
ELECTRIC POWER SYSTEMS AT NUCLEAR POWER PLANTS CONDUCT OF RG 1.114 R/l GUIDANCE ON 07 840 FSAR 1. 9.114 OPERATIONS BEING AN OPERATOR AT THE CONTROLS OF A NUCLEAR POWER PLANT
- 1. 9.116 MECHANICAL QA RG 1.116, R/O-R QUALITY 03 A,05 CONFORM ANCE IS 845 FSAR 07,98 DISCUSSED IN SECTION REQUIREMENTS ASSURANCE REQUIREMENTS FOR 1.9.116.2 0F THE
' INSTALLATION, FSAR.
INSPECTION AND TESTING OF MECHANICAL EQUIPMENT AND SYSTEMS
- 1. 9.116 MECHANICAL QA ANSI M45.2.8-1975 SUPPLEMENTARY 03A,05 CONFORMANCE IS 846 FSAR REQUIREMENTS QUALITY 07,98 DISCU$5ED IN SECTION ASSURANCE 1.9.116.2 0F TRE REQUIREMENTS FOR FSAR.
1 INSTALLATION, j
INSPESTION AND TESTING OF MECHANICAL l EQUIPMENT AND j
SYSTEMS FOR THE
- CONSTRUCTION i
PHASE OF NUCLEAR POWER PLANTS I
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Page No. 10 I 12/02/85 TABLE 3.2-1 COMMITMENTS FOR PLANT
=============================-
OPERATIONS AND SUPPORT n===========.========-
I TITLE MODULE REMARES COMMITMENT DOCUMENT / FEATURE NUMBER COMMITMENT COMMITMENT SOURCE SECTION SUBJECT tr
re== -= ========== ======s========= ==================== ====================== ================ ====_= ===
H/2 PBMAUuit isSTING 03A,07 CONFORMANCE IS 849 FSAR 1. 9.118 TESTING OF ELECTRIC RG 1.118 OF ELECTRIC DISCUSSED IN SRCTION POWER AND PROTECTION PONER AND 1.9.118.2 OF THE SYSTEMS FSAR.
PROTECTION SYSTEMS CRITERIA FOR THE 03A,07 CONFORMANCE IS 850 FSAR 1. 9.118 TESTING OF ELECTRIC IEEE 338-1977 PERIODIC TESTING DISCUSSED IN SECTION POWER AND PROTECTION 1.9.118.2 OF THE OF NUCLEAR POWER STSTEMS FSAR.
GENERATING STATION SAFETT SYSTEMS RG 1.120 R/l FIRE PROTECTION 07 CONFORMANCE IS H51 FSAR 1. 9.120 FIRE PROTECTION DISCUSSED IN PROGRAM GUIDELINES FOR NUCLEAR POWER APPENDIE 9B OF TRE PLANTS FSAR.
RC 1 121 AUGUST 1976 BASES FOR 07 CONFORMANCE IS 852 FSAR 1. 9.121 TECHNICAL SUPPORT DISCUSSED IN SECTION PLUGGING PROCEDURES AND 1.9.121.2 OF THE DOCUMENTATION DEGRADED PWR STRAM OENERATOR FSAR.
TUBES QUALITY 05,07 CONFORMANCE IS
- 1. 9.123 MATERIALS MANAGEMENT RG 1.123, R/l 855 FSAR ASSURANCE DISCUSSED IN SECTION REQUIREMENTS FOR 1.9.123.2 OF TRE CONTROL OF FSAR.
PROCUREMENT OF ITEMS AND SERVICES FOR NUCLEAR POWER PLANTS QUALITT 05,07 CONFORMANCE IS 856 FSAR 1. 9.123 MATERIALS MANAGEMENT ANSI M45.2.13-1976 DISCUSSED IN SECTION ASSURANCE REQUIREMENTS FOR 1.9.123.2 OF THE CONTROL OF FSAR.
PROCUREMENT OF ITEMS AND SERVICES FOR NUCLEAR PLANTS
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Page No. 11 12/02/85 ;
TABLE 3.2-1 COMMITMENTS FOR PLANT l
sse=====================
OPERATIONS AND SUPPORT
=================
COMMITMENT DOCUMENT / FEATURE TITLE MODULE REMARES NUMBER COMMITMENT COMMITMENT SOURCE SECTION SUBJECT
== =========- ================ ==================== ====================== ================ ====== ==============
TESTING STORAGE RC 1.129 R/l MAINTENANCE, 03A,07 CONFORMANCE IS 859 FSAN 1. 9.129 BATTERIES TESTING AND DISCUSSED IN SECTION REPLACEMENT OF 1.9.129.2 0F THE LARGE LEAD FSAR.
STORAGE BATTERIES FOR NUCLEAR POWER PLANTS
- 1. 9.129 iTING STORAGE IEEE 450-1975 IEEE RECOMMENDED 03A,07 CONFORMANCE IS 860 FSAR
..'TERIES PRACTICE FOR DISCUSSED IN SECTION MAINTENANCE, 1.9.129.2 0F THE TESTING AND FSAR.
REPLACEMENT OF LARGE LEAD STORAGE BATTERIES
- 1. 9.131 TECHNICAL SUPPORT RG 1.131 AUGUST 1977 QUALIFICATION 07 CONFORMANCE IS 861 FSAR PROCEDURES AND TESTS OF DISCUSSED IN SECTION DOCUMENTATION ELECTRICAL 1.9.131.2 0F THE CABLES, FIELD FSAR.
SPL1CES, AND CONNECTIONS FOR LIGRT-WATER-COOL ED NUCLEAR POWER PLANTS
- 1. 9.133 LOOSE PART DETECTION RG 1.133, R/l LOOSE-PART 034,07 863 FSAR DETECTION PROGRAM FOR THE PRIMARY SYSTEM 0F LIGHT-WATER-COOL ED REACTORS 866 FSAR 1 9.137 OPERATIONS RG 1.137 R/l FUEL OIL SYSTEMS 07 CONFORMANCE IS IN FACILITIES AND -FOR STANDET ACCORDANCE WITH THE BQUIPMENT DIESEL TECNNICAL GENERATORS SPECIFICATIONS.
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Page No. 12 12/02/85 COMMITMENTS FOR PLANT TABLE 3.2-1
======================
OPERATIONS AND SUPPORT e==================e==
f TITLE MODULE REMARES COMMITMENT COMMITMENT COMMITMENT DOCUMENT / FEATURE NUMBER SOURCE SECTION SUBJECT ====== ====================
_===== == ===e====== ================ ===== ============== ====================== =============e==
ANSI N195-1976 FUEL OIL SYSTEMS 07 CONFORMANCE 15 IN 867 FSAR I. 9.137 OPERATIONS ACCORDANCE WITH THE FACILITIES AND FOR STANDBY DIESEL TECHNICAL EQUIPMENT GNEERATORS SPECIFICATIONS.
RG 1.139, MAY 1978 GUIDANCE FOR 03A,07 CONFORMANCE IS 716 9 FSAR l. 9.139 RESIDUAL HEAT REMOVAL RESIDUAL HEAT DISCUSSED IN SECTION REMOVAL 1.9.139.2 0F THE FSAR.
873 FSAR 1. 9.140 VENTILATION EIRAUST RG 1.140. OCTOBER 1979 DESIGN, TESTING. 03A,07 CONFORMANCE IS AIR FILTRATION UNITS AND M AINTENANCE DISCUSSED IN SECTION CRITERIA FOR 1.9.140.2 0F TRE NORMAL FSAR.
VENTILATION EXHAUST AIR FILTRATION UNITS VENTILATION EXHAUST ANSI N510-1980 TESTING OF 03A,07 CONFORMANCE IS 874 FSAR 1. 9.140 AIR FILTRATION UNITS NUCLEAR AIR DISCUSSED IN SECTION CLEANING SYSTEMS 1.9.140.2 0F THE FSAR.
VENTILATION EXHAUST ANSI M509-1980 NUCLEAR POWER 03A,07 CONFORMANCE IS 875 FSAR 1. 9.140 DISCUSSED IN SECTION AIR FILTRATION UNITS PLANT AIR CLEANING UNITS 1.9.140.2 OF THE AND COMPONENTS FSAR.
TECHNICAL SUPPORT RG 1.141 APRIL 1978 CONTAINMENT 07 CONFORMANCE IS 876 FSAR 1. 9.141 PROCEDURES AND ISOLATION DISCUSSED IN SECTION DOCUMENTATION PROVISIONS FOR 6.2.4 0F THE FSAR.
FLUID SYSTEMS
- 1. 9.147 TECHNICAL SUPPORT RG 1.147 R/2 INSERVICE 07 877 FSAR PROCEDURES AND INSPECTION CODE DOCUMENTATION CASE ACCEPTABILITY, ASME SECTION II, DIVISION 1 O O O O O O O
E b
Page No. I 13 12/02/85 TABLE 3.2 1 COMMITMENTS FOR PLANT
=e===========================-
OPERATIONS AND SUPPORT *
======:-==
I NUMBER COMMITMENT COMMITMENT COMMITMENT DOCUMENT / FEATURE TITLE MODULE REMARES ;
SOURCE SECTION SUBJECT
====-= == ========ve =======e======== ==============-===== =====-================ ================ ====== ==================== ;
878 FSAR 1. 9.147 TECHNIC AL SUPPORT ASME, SECTION XI. ASME BOILER AND 07 :
PROCEDURES AND DIVISION 1 PRESSURE VESSEL CODE I DOCUMENTATION 881 FSAR 1. 9.150 TECHNICAL SUPPORT RG 1.150, FEBRUARY ULTRASONIC 07 CONFORMANCE !3 PROCEDURES AND 1983 TESTING OF DISCUSSED IN SECTION DOCUMENTATION REACTOR VESSEL 5.2.4 OF THE FSAR. ;
WELDS DURING PRESERVICE AND INSERVICE EXAMINATIONS 904 FSAR 2. 3. 3 MAINTENANCE METEORLOGICAL 07 PROCEDURES AND INSTRUMENT PREVENTIVE DOCUMENTATION MAINTENANCE IS PERFORMED BT GPC PERSONNEL IN '
i ACCORDANCE WITR INSTRUCTION MANUALS
.' SUCH TNAT 90% DATA RECOVERY IS MAINTAINED.
3 MAINTENANCE METEOROLOGICAL 07
- 905 FSAR 2. 3.
PROCEDURES AND INSTRUMENT LOG OF
, DOCUMENTATION INSPECTIONS AND MAINTENANCE IS
' COMPLETED DURING PACR INSPECTION OF TRE METEOROLOGICAL EQUIPMENT.
' 906 FSAR 2. 3. 3 MATERIALS MANAGEMENT METEOROLOGICAL 07 INSTRUMENT SPARE PARTS INVENTORY IS MAINTAINED BT REPAIR PERSONNEL AND NEW 4
f PARTS ARE ORDERED AS THEY ARE USED 1
- .c i
a Page No. 14 12/02/R5 TABLE 3.2 1 COMMITMENTS FOR PLANT
======= ============-===- ======--
OPERATIONS AND SUPPORT
==========
TITLE MODULE REMARKS COMMITMENT COMllTMENT DOCUMENT / FEATURE NUMBER COMMITMENT SOURCE SECTION SUBJECT ==1= == =================e==
== =-======== ================ ==================== ====================== ==========
SURVET READING IS 07 911 FSAR 2. 5. 4.13. 2 PLANT PERFORMANCE MONITORING TAKEN ON EACH SETTLEMENT MARKER AT APPR011MATELT 60-DAT INTERVALS PRIOR TO STARTUP AND AT 30-DAT INTERVALS AFTER STARTUP.
RECEIPT INSPECTION AND 07 918 FSAR 3. 2. 2. 3. 4 FIRE PROTECTION PROGRAM THE TESTING OF FIRE PROTECTION SYSTEMS ARE PERFORMED Ih ACCORDANCE WITH APPLCABLE PORTIONS OF NFPA CODES. WHICH INVOKE ANSI B 31.1 AWWA, API AND OTHER CODES.
FINAL PlPE WHIP 07 920 FSAR 3. 6. 1-2 PLANT PERFORMANCE MONITORING RESTRAINT GAP WILL BE VERIFIED DURING HOT FUNCTIONAL TESTING AND TRUS WILL ACCOUNT FOR ANT DIFFERENTIAL SETTLEMENT,
- 1. 7, 2 PREVENTIVE ESTABLISH A LONG TERM 07 923 FSAR 3. 8.
MAINTENANCE SURVFILLANCE PROGRAM FOR POST TENSIONING OF CONTAINMENT TENDONS WBCIH CONTORMS TO REGULATORT GUlr1 1.35, REVISION 2.
MAINTENANCE INSPECTION OF DISCUSSED IN SECTION UNGROUTED 1.9.35.2 0F THE TENDONS IN FSAR.
PRESTRESSED CONCRETE CONTAINMENT STRUCTURES
, O 9 O O O O O
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= ==: ===- ====================
OPERATIONS AND SUPPORT
== =====-=
TITLE MODULE REMARKS NUMBER COMMITMENT COMMITMENT COMMITMENT DOCUMENT / FEATURE SOURCE SECTION SUBJECT
=== == === ====== ==========-,-=====-====-==========================-=========================================='
7 SURVEILLANCE TESTING PEH10DIC TESTING OF 07 924 FSAR 3. 8. 2.
PROGRAM 5 THOSE CLASS MC ITEMS OR CLASS 2 PIPING ASSEMBLIES LISTED IN PARAGRAPH 3.8.2.1 IS PLANNED IN ACCORDANCE WITF 10CFR50, APPENDIX J.
7 SUHVEILLANCE TESTING 10CFR50 APPENDIX J PRIMARY REACTOR 07 925 FSAR 3. 8. 2.
CONTAINMENT PROGRAMS LEAKAGE TESTING FOR WATER-COOLED POWER REACTORS
- 9. 4. 4 OPERATIONS CONTROL ROD DRIVE 07 926 FSAR 3.
PROCEDURES AND MECHANISM TRIP TIME DOCUMENTATION REQUIREMENT OF 2.2 SECONDS FROM START OF RCCA MOTION TO DASH POT ENTRY WILL BE CONFIRMED FOR EACR CRDM PRIOR TO INITIAL REACTOR OPERATION.
PIPING VIBRATION AND VERIFT THAT PIPING AND 03A,0T 937 FSAR 3. 9.B. 2. I TRERMAL EXPANSION PIPING RESTRAINTS WILL WITHPTAND DYNAMICS EFFEvTS DUE TO TRANSIENTS AND THAT PIPING VIBRATIONS ARE WITRIN ACCEPTABLE LEVELS.
938 FSAR 3. 9.8. 2. 1 PIPING VIBRATION AND THERMAL EXPANSION - 03A.0T THERMAL EXPANSION PIPING SYSTEMS ARE OBSERVED PERIODICALLT DURING INITIAL PLANT REATUP TO VERIFT PROPER EXPANSION.
EXPANSION DATA IS RECORDED AT THE END OF HEATUP.
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Page No. 16 12/02/85 TABLE 3.2-1 COMMITMENTS FOR PLANT
======================
OPERATIONS AND SUPPORT
==========
COMMITMENT DOCUMENT / FEATURE TITLE MODULE REMARES NUMBER COMMITMENT COMMITMENT SOURCE SECTION SUBJECT
== ========== ================ ==================== =======e============== ================ ====== ==============
939 FSAR 3. 9.B. 2. I PIPING VIBRATION AND PRE-OP TESTING PROGRAM 034.07 THERMAL EXPANSION FOR CLASS I,2, & 3 AND HIGH BNERGY PIPING SYSTEMS IS TO SIMULATE ACTUAL OPERATING MODES TO DEMONSTRATE TRAT COMPONENTS MEET DESIGN AND VIBRATION IS WITRIN ACCEPTABLE LIMITS.
I PIPING VIBRATION AND PIPING VIBRATION. 03A,07 940 FSAR 3. 9.B. 2.
THERMAL EXPANSION TRERMAL EXPANSION AND DYNAMICS EFFECTS PROGRAM, AS DETAILED IN THE PREOPERATIONAL TEST PROGRAM PLAN SUBMITTED TO NRC AT LEAST 60 DAYS PRIOR TO ITS INITIATION.
PIPING VIBRATION AND VERIFY OPERABILITY OF 03A,07 941 FSAR 3. 9.B. 2. 1 THERMAL EXPANSION ESSENTIAL PIPING SNUBBERS BT RECORDING ROT AND COLD POSITIONS.
942 FSAR 3. 9.8. 2. I PIPING VIBRATION AND NRC IS PROVIDED WITH 03A,07 THERMAL EXPANSION DOCUMENTATION OF CORRECTIVE ACTION TAKEN AS A RESULT OF TESTING. ANALYSIS VERIFTING ACCEPTABLE SYSTEM RESPONSE WILL BE ON FILE.
943 FSA: 3. 9.B. 2. I PIPING VIBRATION AND SYSTLM VIBRATION - 03A.07 TRRRMAL EXPAMSION ACCEPTANCE CRITERIA-MAX.
AMPLITUDE SH ALI, NOT INDUCE STRESS IN PIPING GREATER THAN 1/2 LIMIT (ASME III).
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Pnge No. 17 12/02/H5 TABI.E 3.2-1 COMMITMENTS FOR PLANT
=====-====-========-=======-==-,
OPERATIONS AND SUPPORT
==================- =~
TITLE MODULE REMARKS NUMBER COMMITMENT COMMITMENT COMMITNENT DOCUMENT / FEATURE SOURCE SECTION SUBJECT
--- = =r-- - - - ====.=====---== -- ========= ==~==== =====-================ ================ ====== ============-=======
03A,07 944 FSAR 3. 9.B. 2. 1 PIPING VIBRATION AND TRERMAL EXPANSYON DATA THERMAL ERPAMSION - SCRATCR PLATES, STRAIN GAGE LOCATIONS, AND CRITERIA FOR EVALUATION OF DATA ARE PROVIDED IN TEST PROCEDURES.
03A,07 945 FSAR 3. 9.B. 2. I PIPING VIBRATION AND IF EXCESSIVE PIPING THERMAL EXPANSION VIBRATION IS OBSERVED, CORRECTIVE MEASURES ARE TAKEN AND TEST IS RERUN FOR ADEQUACY.
1 SURVEILLANCE TESTING AFTER SAFETY-RELATED 034,07 949 FSAR 3. 9.B. 3. 2.
PROGRAMS BOP ACTIVE PUMPS ARE INSTALLED. THEY UNDERGO APPLICABLE PERIODIC INSERVICE INSPECTIONS TO ASSURE PUMP FUNCTIONAL ABILITT AND RELIABILITY FOR THE DESIGN LIFE OF THE PLANT.
2 SURVEILLANCE TESTING AFTER INSTALLATION, 03A,07 950 FSAR 3. 9.B. 3. 2.
PROGRAMS BOP SAFETT-RELATED ACTIVE VALVES UNDERGO PERIODIC INSERVICE TESTS TO VERIFY AND ENSURE FUNCTIONAL RELIABILITY OF THE VALVE.
9.N. 2 4 FLOW-INDUCED REACTOR INTERNAL 034,07 THE EXAMINATION 958 FSAR 3.
VIBRATION OF REACTOR VIBRATION INCLUDES IN EXCESS INTERNALS RECOMMENDATIONS OF OF 30 FEATURES REG. GUIDE 1.20 ARE ILLUSTRATED IN
- SATISFIED BY FIGURE 3.9.N.2-1.
CONDUCTING THE CONFIRkiATORY PRE- AMD POST-HOT FUNCTIONAL EXAMINATION FOR INTEGRITY.
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Page No. 18 12/02/85 TABLE 3.2-1 COMMITMENTS FOR PLANT
=================.====
OPERATIONS AND SUPPORT
==========
COMMITMENT DOCUMENT / FEATURE TITLE MODULE REMARKS NUMBER COMMITMENT COMMITMENT SOURCE SECTION SUBJECT
_==_=== =========-============ ========= ==_:== ===e== ========-==========
===== == ========== ==============_: ========-e
4 FLOW-INDUCED REACTOR INTERNAL 03A,07 959 FSAR 3. 9.N. 2.
VIBRATION OF RE ACTOR C AN ALS INSPECTION IS INTERNALS MADE USING A SX OR 10X MAGNIFYING GLASS OR OTHER APPROPRIATE INSPECTION.
9.N. 2. 4 FLOW-]NDUCED REACTOR INTERNAL 03A,07 9GO FSAR 3.
VIBRATION OF REACTOR VIBRATION DURING ROT INTERNALS FUNCTIONAL TESTS ARE SUBJECTED TO A TOTAL OPERATING TIME (4 PUMP OPERATION) OF AT LEAST 240 HOURS.
9 N. 4 FLOW-INDUCED RG 1.20, R/2 COMPREHENSIVE 03A,07 CONFORMANCE IS
- 96) FSAR 3. 2.
VIBRATION OF REACTOR VIBRATION DISCUSSED IN SECTION INTERNALS ASSESSMENT 3.9.N.2.4 OF THE PROGRAM FOR FSAR.
REACTOR INTERNALS DURING PREOPERATIONAL AND START-UP TESTING 964 FSAR 3.11.B PLANT PERFORMANCE MECHANICAL & 07 MONITORING ELECTRICAL EQUIPMENT IN A MILD ENVIRONMENT IS QUALIFIED BT DESIGN /PURCRASE SPECIFICATION AND MAINTENANCE /SURVEILLAN CE PROGRAM WHICH ASSURES EQUIPMENT MEETS DESIGN SPEC. FOR DESIGN LIFE.
965 FSAR 3.ll.B. 1. 1 TECHNICAL SUPPORT NUREG 0588 INTERIM STAFF 07 PROCEDURES AND POSITION ON DOCUMENTATION ENVIRONMENTAL QUALIFICATION OF SAFETT RELATED ELECTRICAL EQUIPMENT 4
O O O O O O O
O O O O O O O .
i Page No. 19 12/02/85 TABLE 3.2-1 COMMITMENTS FOR PLANT !
========================
OPERATIONS AND SUPPORT
==========
NUMBER COMMITMENT COMMITMENT COMMITMENT DOCUMENT / FEATURE TITLE MODULE REMARKS SOURCE SECTION SUBJECT
== ==-======= ================ ==================-= ====================== ================ ====== ==============
967 FSAR 3.11.B. 3-1 TECHNICAL SUPPCRT VEGP CONFORMANCE TO 07 ORGANIZATION AND 5.1 0F NUREG-0588 ADMINISTRATION QUALIFICATION DOCUMENTATION OF SAFETY-RELATED EQUIPMENT WILL BE IN AN AUDITABLE FILE.
968 FSAR 3.ll.B. 3-1 TECHNICAL SUPPORT NUREG 0588, 07 PROCEDURES AND CONFORMANCE -
DOCUMENTATION GUIDELINES FOR DOCUMENTATION IN IEEE 323-1974 WHEN FULLY IMPLEMENTED ARE ACCEPTABLE.
DOCUMENTATION SHOULD BE SUFFICIENT TO ADDRESS REQUIRED INFORMATION IN APPENDIX E.
969 FSAR 3.ll.N. 2. 2 PLANT PERFORMANCE PROGRAM FOR 07 MONITORING ENVIRONMENTAL QUALIFICATION OF ACTIVE MBCRANICAL COMPONENTS IS BASED ON DESIGN, TEST AND ANALTSIS OF CRITIC #L SUBCOMPONENTS.
SUPPORTED BY PERIODTC PLANT TEST, MAINTENAMeR AND SURVEIL 'x?M.
970 FSAR 3.ll.N. 3-1 TECHNICAL SUPPORT NUREG 0588 CATEGORY l 07 PROCEDURES AND POSITION (5.1) -
DOCUMENTATION NESTINGROUSE HAS SUPPLIED UTILITIES: - i 3 IDENTIFICATION OF THE LIMITS TO ANY ENVIRONMENTAL !
f QUALIFICATION. -
COPIES OF ALL REFERNCED WESTINGBOUSE !
TOPICAL REPORTS.
j4 C
. - _ - . . _ _ = _ _ _ _ _ _ - - _ - _ - _ _ . - _ _ _ _ _ _ _ _ _ - - _ _ _ _ - . _ _ _ - - _ _ _ _ _ - _ _ - _ _ _ _ _ _ _ _ _ _ _ _ - . . _ _ _ _ _ _ _ _ _ , _ _ _ - _ - - _ _ _ _ _ _ .
Page No. 20 12/02/85 TABLE 3.2-1 COMMITHENTS FOR PLANT
===========e-=========
OPERATIONS AND SUPPORT
==========
COMMITMENT COMMITMENT DOCUMENT / FEATURE TITLE MODULE REMARKS NUMBER COMMITMENT SOURCE SECTION SUBJECT
== ========== ================ ==================== ====================== ================ ====== ==============
3 REACTOR ENGINEERING FOR THE FIRST CORE, A 07 971 FSAR 4. 2. 2. 3.
NEUTRON SOURCE IS PLACED IN THE REACTOR TO PROVIDE A POSITIVE NEUTRON COUNT OF AT LEAST TWO COUNTS PER SECOND ON THE SOURCE RANGE DETECTORS.
4 REACTOR ENGINEERING IN THE CASE OF THE 07 973 FSAR 4. 2. 4.
FULL-LENGTH RCAA*S BOTH MANUFACTURING TESTS / INSPECTIONS AND FUNCTIONAL TESTING AT TPE PLANT SITE ARE PERFORMED.
- 4. 4 REACTOR ENGINEERING CONTROL RODS ARE 07 974 FSAR 4. 2.
FUNCTIONALLT TESTED, FOLLOWING CORE LOADING BUT PRIOR TO CRITICALITT, TO DEMONSTRATE RELIABLE OPERATION OF THE ASSEMBLIES.
4 REACTOR ENGINEERING TEST AND INSPECTIONS 07 975 FSAR 4. 2. 4.
ARE PERFORMED ON BACR REACTIVITY CONTROL ROD TO VERIFY THE MECHANICAL CHARACTERISTICS.
- 4. 4 REACTOR ENGINEERING FOLLOWING CORE LOADING 07 976 FSAR 4. 2.
BUT PRIOR TO CRITICALITY, EACR ROD CONTROL CLUSTER f ASSEMBLY IS OPERATED (AND TRIPPED) ONE TIME AT NO-FLOW / COLD CONDITIONS AND ONE TIME AT FULL-FLOW / HOT CONDITIONS.
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k Page No. 21 12/02/85 TABLE 3.2-1 COMMITMENTS FOR PLANT u========e========================
OPERATIONS AND SUPPORT r ==== ====== - ======
NUMBER COMMITMENT COMMITMENT COMMITMENT ..,uMENT/ FEATURE TITLE MODULE REMf1ES SOURCE SECTION SUBJECT
== == ========== ================ ==================== ====================== ================ ===e== =======: =====e
977 FSAR 4. 2. 4. 4 REACTOR ENGINEERING FOLLOWING CORE 07 LOADING. BUT PRIOR TO CRITICALITY. SELECTED ROD CONTROL CLUSTER ASSEMBLIES (15 TO 20%)
ARE OPERATED AT NO-FLOW OPERATING TEMP. CONDITIONS AND FULL-FLOW AMBIENT CONDITIONS.
978 FSAR 4. 2. 4. 4 REACTOR ENGINEERING FOLLOWING CORE 07 LOADING. BUT PRIOR TO CRITICALITT. THE SLOWEST ROD CONTROL CLUSTER ASSEMELY AND FASTEST RCCA ARE TRIPPED 10 TIMES AT NO FLOW / AMBIENT AND AT FULL FLOW /0PERATING TEMPERATURE CONDITIONS.
979 FSAR 4. 2. 4. 6 REACTOR ENGINEERING PROGRAM FOR INSPECTION 07 0F IRRADIATED FUEL ASSEMBLIES WILL ESTABLISR THE SCERDULE. GUIDELINEF.
AND INSPECTION CRITERIA FOR CONDUCTING VISUAL INSPECTION OF IRRADIATED FUEL AND INSERT COMPONENTS.
980 FSAR 4. 2. 4. 6 REACTOR ENGINEERING IRRADIATED FUEL Of INSPECTION PROGRAM RAS CRITERIA FOR ADDITIONAL INSPECTION REQUIREMENTS IF UNUSUAL CHARACTERISTICS ARE NOTICED OR PLANT INSTRUMENTATION AND SUBSEQUENT ANALYSIS INDICATES FAILED FUEL.
(
Page No. 22 12/02/85 TARLE 3.2-1 COMMITMENTS FOP PLANT
-e========================
OPERATIONS AND SUPPORT
=========r ==-
TITLE MODULE R$ 4 ARES COMMITMENT COMMITMENT DOCUMENT / FEATURE NUMBER COMMITMENT SECTION SUBJECT SOURCE ====-==============2r= -=============== ====== ===================e
e== == ========== ================ =================
07 981 FSAR 4. 2. 4. 7 REACTOR ENGINEERING WRITTEN PROCEDURES ARE USED BT STATION STAFF FOR POST-SHIPMENT INSPECTION OF NEW FUEL AND ASSOCIATED COMPONENTS, SUCR AS CON'?ROL RODS. PLUGS AND INSERTS.
07 982 FSAR 4. 2. 4, 7 REACTOR ENGINEERING FUEL HANDLING PROCEDURES SPECIFY THE SEQUENCE IN WHICH FUEL HANDLING AND INSPECTION TAKES PLACE.
07 983 FSAR 4. 2. 4. 7 REACTOR ENGINEERING LOADED FUEL CONTAINERS, WHEN RECEIVED ON SITE. ARE EXTERNALLY INSPECTED TO ENSURE LABELS AND MAREINGS ARE INTACT AND SEALS ARE UNBROBEN.
07 984 FSAR 4. 2. 4. 7 REACTOR ENGINEERING AFTER THE CONTAINEWS ARF OPENED. TRE SROCK i
INDICATORS ATTACHED TO
! THE SUSPENDED INTERNALS ARE i
I INSPECTED TO DETERMINE IF MOVEMENT DDRING
! SRIPMENT RAS EXCEEDED
' DESIGN LIMITATIONS.
7 REACTOR ENGINEERING FOLLOWING REMOVAL OF 07 985 FSAR 4. 2. 4.
FUEL ASSEMBLT FROM THE CON?AINER. FUEL
! ASSEMBLY PLASTIC WRAPPER IS REAMINED FOR EVIDENCE OF DAMAGE. WRAPPER IS THEN REMOVED, AND THE ENTIRE BCNDLE IS VISUALLT INSPECTED.
s O O O O O O O
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- Page No. 23 12/02/85 TABLE 3.2-1 COMMITMENTS FOR PLANT
e=====================
OPERATIONS AND SUPPORT
==========
DOCUMENT / FEATURE TITLE MODULE REMARES NUMBER COMMITMENT COMMITMENT COMMITMENT SOURCE SECTION SUBJECT
== ========== =-============== ==================== ====================== ================ ====== ==============
07 986 FSAR 4. 3. 2. 2. 7 REACTOR TNGINEERING DATA WITH UNUSUAL VALUES OF ARIAL OFFSET ARE OBTAINED AS PART OF TRE BRCORE DETECTION CALIBRATION EXERCISE PERFORMED MONTHLY.
07 987 FSAR 4. 3. 2. 2. 7 REACTOR ENGINEERING EXCORE CALIBRATION EXBRCISES ARE PERFORMED MONTELY TO OSTAIN ARIAL OFFSET VALUES.
07 988 FSAR 4. 3. 2. 2. 8 REACTOR ENGINEERING EXTENSIVE SERIES OF PBYSICS TESTS WILL BE PERFORMED ON THE FIRST CORE.
07 989 FSAR 4. 3. 2. 3. 4 REACTOR ENGINEERING EXPERIMENTAL EVALUATION OF THE REACTIVITY COEFFICIENTS WILL BE PERFORMED DURING THE PHYSICS STARTUP TESTS.
REACTOR ENGINEERING CRITICALITY OF FUEL 07 990 FSAR 4. 3. 2. 6 ASSEMBLIES OUTSIDE THE REACTOR IS PRECLUDED SY DESIGN OF FUEL TRANSFER. SHIPPING AND STORAGE FACILITIES AND BY ADMINISTRATIVE PROCEDURES.
07 991 FSAR 4. 4. 2. 9. 2 REACTOR ENGINEERING TESTS ON THE PRIMARY SYSTEM PRIOR TO INITIAL CRITICALITY WILL BE MADE TO VERIFY
'( TNAT A CONSERVATIVE PRIMARY SYSTEM COOLANT FLOW RATE MAS BEEN 7 USED IN THE DESIGN AND ANALYSES OF THE PLANT.
(
l4 e
- Page No. 24 12/02/85 TABLE 3.2-1 COMMITMENTS FOR PLANT
===========================e
OPERATIONS AND SUPPORT
==========
f TITLE MODULE REMARES COMMITMENT COMMITMENT DOCUMENT / FEATURE NUMBER COMMITMENT SOURCE SECTION SUBJECT
========== ====== ==============
===== =e ========== ================ ==================== ====================e
07 992 FSAR 4. 4. 5. 1 REACTOR ENGINEERING RC FLOW TEST IS PERFORMED FOLLOWING FUEL LOADING PRIOR TO CRITICALITY. COOLANT LOOP PRESSURE DROP DATA OBTAINED IS USED IN CONJUNCTION WITH RCP PERFORMANCE TO DETERMINE OPERATING COOLANT FLOW RATES.
REACTOR ENGINEERING CORE POWER 07 993 FSAR 4. 4, 5. 2 DISTRIBUTION MEASUREMENTS ARE MADE AT SEVERAL CORE POWER LEVELS TO INSURE TRAT CONSERVATIVE PEAKING FACTOR 8 ARE USED IN CORE THERMAL AND HYDRAULIC ANALTSIS.
- 4. 1 MAINTENANCE PROCEDURES SHOULD BE 07 WESTINGHOUSE PROCESS I003 FSAR 5. 2. 3.
i PROCEDURES AND IN PLACE FOR RANDLING. SPECIFICATIONS i DOCUMENTATION PROTECTION, STORAGE DEFINE THESE AND CLEANING STAINLESS REQUIREMENTS.
STEEL COMPONENTS.
- 4. 6 MATERIALS MANAGEMENT CONTROL OF FERRITE IN 07 1004 FSAh 5. 2. 3.
STAINLESS STEEL WdLD METAL AND METRODS USED.
5, 4 SURVEILLANCE TESTING INSERVICE INSPECTION 07 1005 FSAR 2.
l PROGRAMS WILL COMPLY WITH g IOCFR50.55A(0) AND NRC j
i GUIDELINEDS ATTACHED TO SECTION 121 OF f' " GUIDANCE FOR PREPARING PSI AND ISI PROGRAMS AND RELIEF REQUESTS PURSUANT TO 10CFR50.55A(G)."
9 O O O O O O
O Pete No. 25 IF '02/85 TABLE 3.2-1 COMMITMENTS FOR PLANT
========s=============
OPERATIONS AND SUPPORT
==========
DOCUMENT / FEATURE TITLE MODULE REMARES NUM8ER COMMITMENT COMMITMENT COMMITMENT SOURCE SECTION SUBJECT
== ========== ================ ==================== ====================== ================ ====== ===========
SURVEILLANCE TESTING 10CFR50.55A(G) INSERVICE 07 1006 FSAR 5. 2. 4 PROGRAMS INSPECTION REQUIREMENTS SURVEILLANCE TESTING REACTOR VESSEL 07 1007 FSAR 5. 3. 1. 6 PROGRAMS MATERIAL SURVEILLANCE PROGRAM AND SCREDULE FOR REMOVAL CONFORMS ,
TO ASTM E-185-79 CONDUCTING SURVEILLANCE TESTS FOR PWR REACTOR VESSELS, AND 10 CFR 50 APPENDIX R.
SURVEILLANCE TESTING ASTM E-185-79 CONDUCTING 07 2713 FSAR 5. 3. 1. 6 PROGRAMS SURVEILLANCE TESTS FOR LIGHT-WATER-COOL RD NUCLEAR REACTOR VESSELS SURVEILLANCE TESTING 10CFR50, APPENDIX H RE ACTOR VESSEL 07 2711 FSAR 5. 3. 1. 6 PORGRAMS MATERIAL
, SURVEILLANCE PROGRAM REQUIREMENTS SURVEILLANCE TESTING TEMPERATURE LIMITS FOR 07 1008 FSAR 5. 3. 2. I PROGRAMS INSERVICE LEAR AND HTDRO TESTS OF THE REACTOR VESSEL WILL BE CALCULATED IN ACCORDANCE WITH ASMEIII, APPENDIX G.
4 SURVEILLANCE TESTING ASME, SECTION III, ASME BOILER AND 07 2715 FSAR 5. 3. 2. 1 PRESSURE VESSEL i PROGRAMS APPENDIX G CODE
, t 4
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Page No. 26 12/02/85 TABLE 3.2-1 COMMITMENTS FOR PLANT
======================
OPERATIONS AND SUPPORT
===========e
TITLE MODULE REMARES COMMITMENT COMMITMENT DOCUMENT / FEATURE NUMBER COMMITMENT SOURCE SECTION SUBJECT
================ ================ ====== ==============
== ========== ================ ========e=====
07 1011 FSAR 5. 4. 10. 3. 1 CONDUCT OF OPERATONS AFTER A SAFETT INJECTION SIGNAL, PROCEDURES ALLOW MANUAL RE-ENERGIZATION OF NON-CLASS IE BUSES UNDER ADMIN. CONTROL.
MAINTENANCE PROTECTIVE COATINGS 07 1014 FSAR 6. 1. 2. 1 PROCEDURES AND USED INSIDE DOCUMENTATION CONTAINMENT.
PROCEDURES AND CONTROLS WILL BE IN PLACR THAT MEET TRE INTENT OF ANSI N101.4(1972) AND R.G.
1.54(JUNE 1973)
RG 1.54 R/l QUALITT 07 CONFORMANCE IS 1015 FSAR 6. I, 2. I MAINTENANCE DISCUSSED IN SECTION PROCEDURES AND ASSURANCE DOCUMENTATION REQUIREMENTS FOR 1.9.54.2 OF TRE PROTECTITE FSAR.
COATINGS APPLIED A TO WATER COOLED NUCLEAR POWER PLANTS MAINTENANCE ANSI N101.4-1972 QUALITT 07 CONFORMANCE IS 2716 FSAR 6. 1. 2. I PROCEDURES AND ASSURANCE DISCUSSED IN DOCUMENTATION REQUIREMENTS FOR SECTIONS 1.9.54.2 PROTECTIVE AND 6.1.2.1 OF TRE COATINGS APPLIED FSAR.
TO NUCLEAR FACILITIES
- 2. 1. 4 PREVENTIVE CONTAINMENT COOLER 07 1018 FSAR 6. 2.
MAINTENANCE FANS ARE RUN AND MONITORED DURING PLANT SRUTDOWN IN ACCORDANCE
' WITR THE PLANNED
MAINTENANCE PROGRAM.
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O O O O O O O
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_ _._........m.m . ..
. -.m.. . _ . _ __ ._, . . . ._ ,
4 4 Pege No. 27 12/02/85 TABLR 3.2-1 COMMITMENTS FOR PLANT
=================================-
OPERATIONS AND SUPPORT !
==========
NUMBEE COMMITMENT COMMITMENT COMMITMENT DOCUMENT / FEATURE TITLE MODULE REMARKS '
, SOURCE SECTION SUBJECT
e==============s=== v==e====e=============-===ee=====e===== ====== =====e=============
== ========== ==========
1024 FSAR 6. 2. 2. 2. 4. CONDUCT OF PEHlopiC OPERATIONAL 07
- 2. 2 OPERATIONS TESTING OF THE SPRAY EDUCTORS AND SPRAY ADDITIVE TANK ISOLATION VALVES NILL BE PERFORMED.
1025 FSAR 6. 2. 5. 1. PLANT STATUS POST LOCA RYDROGEN 07 2.D CONTROLS PURGE - OUTSIDE ISOLATION VALVE IS ;
LOCKED CLOSED AND j MANUALLY CONTROLLED BY THE OPERATOR.
1050 FSAR 6. 2. 6. 2 SURVEILLANCE TESTING CONTAINMENT LEAK RATE 07 PROGRAMS PENETRATIONS 68 AND 87 AND ENCAPSULATION VESSELS FOR
- PENETRATIONS 36 TRROUGH 39 ARE TYPE B i TESTED.
l 1061 FSAR 6. 3. 1 PLANT STATUS MANIPULATION OF VALVES 07 CONTROLS DURING SURVEILLANCE
) TESTING - PROCEDURES !
l' NRITTEN TO ENSURE POSITIVE CONTROL OVER ALL VALVE OPS AND INDEPENDENTLY VERIFY EACH VALVE RETURNED TO i ORIGINAL POSITION.
t j 1062 FSAR 6. 3. I PLANT STATUS AFTER EXTENDED OUTAGES 07 t
CONTROLS SYSTEMS ARE ALIGNED BY i INDIVIDUAL PROCEDURES.
SAFETY RELATED SYSTEMS ARE ALIGNED
{
AGAIN USING FLON PATH VERIFICATION i E SURVEILLANCE PROCEDURE I TO PROVIDE INDEPENDENT l VERIFICATION 4 (
i 1
l C 4
.. _ . - _ - . . - . . . _ - _ _ . . _ _ _ ..- __ - _ . - - _ - - - . _ _ _ _ . _ . . _ _ _ _ _ _ _ _ _ - - . _ _ _ . - - . -. - _ _ _ - _ - - - _ _ -__ _ _ _ _ _ _ - . . _ _ _ _ _ . - - - _ - ~ .
Page No. 28 12/02/85 TABLE 3.2-1 COMMITMENTS FOR PLANT
e========e==================
OPERATIONS AND SUPPORT
=================e
NUMBER COMMITMENT COMMITMENT COMMITMENT DOCUMENT / FEATURE TITLE MODULE REMARES SOURCE SECTION SUBJECT
== ========== ==== =========== ==================== ====================== ================ ====== ==============
1063 FSAR 6. 3. 2. 2.16 SURVFILLANCE TESTING PERIODIC VISUAL 07 PROGRAMS INSPECTION OF ECCS MOTOR-OPERATED VALVES ENSURE NO POTENTIAL FOR IMPAIRMENT OF VALVE OPERABILITT DUE TO BORIC ACID CRYSTALLIZATION MRICH COULD RESULT FROM VALVE STEM LRAEAGE.
1064 FSAR 6. 3. 2. 2.17 PLANT STATUS MANUALLY OPERATED CATE 07 CONTROLS VALVE ON THE SUCTION LINE FROM THE RWST IS LOCEED OPEN.
ADMINISTRATIVELY CONTROLLED.
1065 FSAR 6. 3. 2. 2.17 PLANT STATUS ECCS MANUAL VALVES ARE 07 CONTROLS GENERALLY USED FOR MAINTENANCE ISOLATION OR THROTTLING VALVES.
WHEN USED FOR THESE FUNCTIONS. THEY ARE UNDER ADMINISTRATIVE CONTROL - LOCEED IN THE CORRECT POSITION.
1066 FSAR 6. 3. 2. 2.17 PLANT STATUS BRANCR LINE 07 CONTROLS CONNECTIONS IN ECCS t.R E PROVIDED WITH DOUBLE ISOLATION OR SEALED BARRIERS, AND PLACED UNDER ADMINISTRATIVE CONTROL.
1071 FSAR 6. 3. 4. 2 SURVEILLANCE TESTING DURING PERIODIC SYSTEM 07 PROGRAMS (ECCS) TESTING A VISUAL INSPECTION OF PUMP SEALS, VALVE g
PACKINGS. FLANGED CONNECTIONS, AND RELIEF VALVES IS MADE TO DETECT LEARAGE.
- 9 9 9 9 9 9 9
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Page No. 29 12/02/85 TABLE 3.2-1 COMMITMENTS FOR PLANT
======================
OPERATIONS AND SUPPORT e
==========
NUMBER COMMITMENT COMMITMENT COMMITMENT DOCUMENT / FEATURE TITLE MODULE REMARES SOURCE SECTION SUBJECT
== ========== ================ =================e== ====================== ================ ====== ==============
1078 FSAR 6. 4. 5. I SURVEILLANCE TESTING PERIODIC LABORATORT 07 PROGRAMS TEST OF IMPREGNATED, ACTIVATED CARBON (OF CONTROL ROOM HVAC FILTERS) IS USED TO VERIFY IODINE REMOVAL EFFICIENCIES IN ACCORDANCE WITH POSITION C.6 AND TABLE 2 OF REG GUIDE 1.52.
1079 FSAR 6. 4. 5. 2 SURVEILLANCE TESTING HEPA FILTERS'ARE. 07 PROGRAMS TESTED IN PLACE INITIALLY PRIOR TO OPERATION AND SEMIANNUALLY THEREAFTER TO CONFIRM THAT THE MARIUM ALLOWABLE PEMETRATION AS DEFINED IN REGULATORT GUIDE 1.52 IS NOT EXCEEDED.
1080 FSAR 6. 4. 5. 2 SURVEILLANCE TESTING HEPA FILTER CARBON 07 PROGRAMS ADSORBERS ARE FREON LEAE TESTED IN ACCORDANCE WITH ANSI N510 TO VERIFY BYPASS LEAEAGE IS LESS TRAM ALLONED BY REG GUIDE 1.52.
1081 FSAR 6. 4. 5. 2 SURVEILLANCE TESTING IMPLACE TESTING OF 07 PROGRAMS HEPA FILTERS WILL BE PERFORMED ACCORDING TO ANSI M510, AS DISCUSSED IN PARAGRAPH 1.9.52.2.
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Page No. 30 12/02/85 TABLE 3.2-1 COMMITMENTS FOR PLANT
===== ==eze======================-
OPERATIONS AND SUPPORT
===========2=======
COMMITMENT DOCUMENT / FEATURE TITLE MODULE REMARKS NUMBER COMMITMENT COMMITMENT SOURCE SECTION SUBJECT
,== == ====e=:-== r=============== -==:====-====e====== ===- =========== = === -=============== ====== =================
2 SURVEILLANCE TRSTING RG 1.52 R/2 DESIGN. TESTING. 07 CONFORMANCE IS 1082 FSAR 6. 4. 5.
DISCUSSED IN SECTION PROGRAMS AND MAINTENANCE CRITERIA FOR 1.9.52.2 OF THE POST ACCtDENT FSAR.
ENGINEERED SAFETY FEATURE ATMOSPHERE CLEANUP SYSTEM, AIR FILTRATION AND ADSORPTION UNITS FOR LIGHT WATER COOLED NUCLEAR POWER PLANTS 2 MAINTENANCE ANSI N510-1980 TESTING OF 07 CONFORMANCE IS 1083 FSAN 6. 4. 5.
PROCEDURES AND NUCLEAR AIR DISCUSSED IN SECTION DOCUMENTATION CLEANING SYSTEMS 1.9.52.2 OF THE FSAR.
PROGRAMS ARE TESTED IN PLACE PRIOR TO OPERATION TO VERIFY EFFICIENCY OF AT LEAST 99.97 PERCENT IN ACCORDANCE WITH ANSI N510 AND CONFORMS WITH POSITION C.S.B OF REG GUIDE 1.52.
1087 FSAR 6. 5. 1. 4. I SURVEILLANCE TESTING FANS ARE TESTED 07 PROGRAMS ACCORDING TO THE AIR MOVING AND CONDITIONING ASSOCIATES STANDARD 210. MOISTURE SEPARATERS ARE TESTED l
TO ANSI N509 PARAGRAPH 5.4.
4 I
l l O O O O O O O l - - - - - _ - - - -- --- ------
a 5
Page No. 31 12/02/RS TABLE 3.2-1 COMMITMENTS FOR PLANT
======== =============
OPERATIONS AND SUPPORT
:-==================
COMMITMENT DOCUMENT / FEATURE TITLE MODULE REMARES NUMBER COMMITMENT COMMITMENT SOURCE SECTION SUBJECT "
== =r======== ================ ==================== ====================== ==-============= ====== ==============
1088 FSAR 6. 5. 1. 4. I SURVEILLANCE TESTING ORIGINAL AND 07 PROGRAMS REPLACEMENT BATCHES OF IMPREGNATED ACTIVATED <
CARBON ARE BATCH TESTED ACCORDING TO REG GUIDE 1.52 PRIOR TO LOADING INTO ADSORBER SECTION.
SURVEILLANCE TESTING INSERVICE INSPECTION 07 1089 FSAR 6. 6. 1 PROGRAMS AND TESTING OF CLASS 1, 2 AND 3 PRESSURE-RETAINING COMPONENTS SHALL BE PERFORMED IN j ACCORDANCE WITH ASME XI. SUBSECTIONS IWC AND IWD IN ACCORDANOE WITH 10CFR 50.55A(G).
1090 FSAR 6. 6. I SURVEILLANCE TESTING ASME, SECTION XI. ASME BOILER AND 07 PROGRAMS DIVISION 1 PRESSURE VESSEL CODE 8 $URVEILLANCE TESTING AUGMENTED ISI WILL BE 07 1091 FSAR 6. 6.
PROGRAMS PROVIDED FOR HIGH-ENERGY SYSTEMS PIPING BETWEEN CONTAINMENT ISOLATION VALVES OR BETWEEN THE FIRST RIGID PIPE CONNECTION TO CONTAINMENT OR FIRST PIPE WHIP RESTRAINT
< INSIDE.
1092 FSAR 6. 6. 8 SURVEILLANCE TESTNG AUGMENTED ISI PROGRAM 07 PROGRAMS WILL INCLUDE 100 PERCENT VOLUMETRIC EXAM OF WELDS IN THE
, AFFECTED PIPING DURING
- EACR INTERVAL, WILL BE
! CONDUCTED PER ASME XI,
' AND COVER HIGH ENERGY j SYSTEMS PER 3.6.1 AND I 3.6.2.
l C
Page No. 32 12/02/85 TABLE 3.2-1 COMMITMENTS FOR PLANT
=======:===-========
OPERATIONS AND SUPPORT
-====================-
COMMITMENT DOCUMENT / FEATURE TITLE MODULE REMARKS NUMBER COMMITMENT COMMITMENT SOURCE SECTI"N SUBJECT
== == ========== ==_ ============ ==================== ==eee========== .=====- ================ ====== ============ ==
2, PLANT STATUS ACCESS TO MhANS FOR 07 1094 FSAR 7. 2. 2.
3.N CONTROLS MANUALLY BYPASSING CHANNELS (REACTOR TRIP SYSTEM) OR PROTECTIVE FUNCTIONS IS ADMINISTRATIVELY CONTROLLED.
ACCESS TO SETPOINT 07 1095 FSAR 7. 2. 2. 2. PLANT STATUS 3.R CONTROLS ADJUSTMENTS. MODULE CALIBRATION ADJUSTMENTS, AND TEST POINTS IS ADMINISTRATIVELY CONTROLLED.
7, 2 MAINTENANCE LINEARITY OF DELTA T 03A,07 1098 FSAR 2. 2. 3.
PROCEDURES AND MEASUREMENTS OBTAINED DOCUMENTATION FROM HOT LEG AND COLD LEG BYPASS LOOP RESISTANCE TEMPERATURE DETECTORS, AS A FUNCTION OF PLANT POWER. IS ALSO CHECERD DURING PLANT STARTUP TESTS.
2 MAINTENANCE BYPASS LOOP RESISTANCE 07 1099 FSAR 7. 2. 2. 3.
PROCEDURES AND TEMPERATURE DETECTOR DOCUMENTATION SIGNALS WILL BE COMPARED WITH THE CORE EXIT TRh8MOCOUPLE SIGNALS.
FSAR 2. 2 OPERATIONS REACTOR TRIP STSTEM 03A,07 1100 7. 2. 3.
PROCEDURES AND ACCURACT OF TRE RTD DOCUMENTATION BYPASS LOOP TEMPERATURE MEASUREMENTS IS DEMONSTRATED DURING PLANT STARTUP TEST.
O O O O O O O
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O O O Page No. 33 12/02/85 TABLE 3.2-1 COMMITMENTS FOR PLANT
============.========-====== =-
OPERATIONS AND SUPPORT
:2================
TITLE MODULE REMARKS COMMITMENT COMMITMENT COMMITMENT DOCUMENT / FEATURE NUMBER
- SOURCE SECTION SUBJECT
== ========== ================ ==================2= ============= ======== ================ ====== ==============
WRITTEN TEST 07 1101 FSAR 7. 2. 2. 5 OPERATIONS PROCEDURES AND PROCEDURES AND DOCUMENTATION DOCUMENTATION, CONFORMING TO THE.
REQUIREMENTS OF IEEE 338-1977 (FOR TESTING THE REACTOR TRIP SYSTEM) WILL BE AVAILABLE FOR AUDIT BY RESPONSIBLE PERSONNEL.
IEEE 338-1977 CRITERIA FOR THE 07 CONFORMANCE IS 1102 FSAR 7. 2. 2. 5 TECHNICAL SUPPORT DISCUSSED IN SECTION PROCEDURES AND PERIODIC TESTING DOCUMENTATION OF NUCLEAR POWER 1.9.118.2 OF THE GENERATING FSAR.
STATION SAFETT SYSTEMS REFUELING OUTAGE 07 1105 FSAR 7. 3. 1. 2. 2. TECHNICAL SUPPORT PROCEDURES AND MAINTENANCE CHECKS,
- 5. 2 DOCUMENTATION SUCR AS SIGNAL CABLE RESISTANCE TO GROUND IN RADIATION ENVIRONMENTS ARE BASED ON QUALIFICATIOM TEST DATA WHICH IDENTIFIES ACCEPTABLE RADIATION, TRERMAL DEGRADATION COMMUNICATION IS 07 1106 FSAR 7. 3. 1. 2. 2. CONDUCT OF
- 5. 8 OPERATIONS ESTABLISRED BETWEEN THE CONTROL ROOM AND THE ESFAS TEST CABINETS DURING FINAL ACTUATION DEVICE OR ACTUATED EQUIPMENT TESTING.
APPROPRIATE 07 1107 FSAR 7. 3. 3. PLANT STATUS 2.C.14 CONTROLS ADMINISTRATIVE CONTROLS WILL BE-APPLIED TO ENSURE TRAT
- ACCESS TO MEANS FOR MANUALLT BTPASSING THE CONTAINMENT
( COMBUSTIBLE GAS
'I CONTROL SYSTEM IS
' PROTECTED.
C
-. -_ . _ _ . ~_ _ _ _ _ _ _ _ _______ ______ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ._ _ ____ __ __ __
Page No. 34 12/02/85 TABLE 3.2-1 COMMITMENTS FOR PLANT
======================
OPERATIONS AND SUPPORT
==~m =====
TITLE MODULE REMARES COMMITMENT COMMITMENT DOCUMENT / FEATURE NUMBER COMMITMENT SOURCE SECTION SUBJECT ====== ====================
e===============
== ========== ================ ==================== ================
ADMINISTRATIV2 07 1108 FSAR 7. 3. 3. CONDUC1 OF 2.C.18 MAINTENANCE CONTROLS ARE APPLIED TO ENSURE THAT ACCESS TO THE MEANS FOR ADJUSTING, CALIBRATING AND TESTING THE CONTAINMENT COMBUSTIBLE GAS CONTROL SYSTEM IS ADEQUATELY PROTECTED.
RG 1.118, R/2 PERIODIC TESTING 07 CONFORMANCE IS 1110 FSAR 7. 5. 2. 3. 1. CONDUCT OF DISCUSSED IN SECTION MAINTENANCE OF ELECTRIC 3 1.9.118.2 OF THE POWER AND
. PROTECTION FSAR.
SYSTEMS SERVICING, TESTINC AND 07 1111 FSAR T. 5. 2. 3. 1. CONDUCT OF 3.D MAINTENANCE CALIBRATION PROGRAMS ARE SPECIFIED TO MAINTAIN THE CAPABILITY OF THE CATEGORY l ACCIDENT MONITORING INSTRUMENTATION.
- 1. CONDUCT OF PERIODIC TESTING OF 07 1112 FSAR 7. 5. 2. 3.
3.J MAINTENANCE CATEGORY l ACCIDENT MONITORING SYSTEMS ARE PERFORMED IN ACCORDANCE MITH APPLICABLE PORTIONS OF REG. GUIDE 1.118
" PERIODIC TESTING OF ELECTRIC POWER AND PROTECTION SYSTEMS."
- 2. CONDUCT OF SERVICING. TESTING, 07 1113 FSAR 7. 5. 2. 3.
. 3.C MAINTENANCE AND CALIBRATION PROGRAMS ARE SPECIFIED TO MAINTAIN THE CAPABILITY OF THE CATEGORY 2 MONITORING INSTRUMENTATION.
t O O O O O O O
4 Page No. 35 12/02/85 TABLE 3.2-1 COMMITMENTS FOR PLANT
======================
OPERATIONS AND SUPPORT
-=====-=========
COMMITMENT DOCUMENT / FEATURE TITLE MODULE REMARES NUMBER COMMITMENT COMMITMENT SOURCE SECTION SUBJECT
ze=== == ========== ================ ==================== ====================== ================ ====== ===================
l 1114 FSAR 7. 5. 2. 3. 2. PLANT STATUS ADMINISTRATIVE 07 3.D CONTROLS CONTROLS EXIST FOR ACCESS AND REMOVAL OF SEISMIC CATEGORY 2 SAFETY-RELATED CRANNELS FROM SERVICE.
1115 FSAR 7. 5. 2. 3. 2. CONDUCT OF PERIODIC TESTING 07 3.1 MAINTENANCE CATEGORY 2 INSTRUMENTATION ARE IN ACCORDANCE WITH APPLICABLE PORTIONS OF REG. QUIDE 1.118 ,
" PERIODIC TESTING OF ELECTRIC POWER AND PROTECTION SYSTEMS."
1116 FSAR 7. 5. 2. 3. 3. CONDUCT OF SERVICING. TESTING. 07 3.A MAINTENANCE AND CALIBRATION PROGRAMS ARE SPECIFIED l TO MAINTAIN THE CAPABILITY OF CATEGORY
{ 3 MONITORING i
INSTRUMENTATION.
1117 FSAR T. 5. 2. 3. 3. PLANT STATUS ADMINISTRATIVE 07 3.B CONTROLS CONTROLS EXIST FOR REMOVAL FROM SERVICE
' AND. ADJUSTMENT OF SEISMIC CATEGORY 3 SAFETY RELATED CRANNELS.
1119 FSAR T. 5. 5. 1 PLANT STAUS CONTROLS UNDER ADMINISTRATIVE 07 4
CONTROL. MANUAL BYPASS j' INDICATION CAN BE SET UP OR REMOVED TO I' FURTRER ENHANCE OPERATOR'S AWARENESS 0F CURRENT STATUS OF ESF SYSTEMS.
1 f
1 k ---,-o.< ~ _ . - - - - - - _ _ . - - . _ _ _ _ - _ - _ - - - - . - - - _ - . - _ . _ -_-- _-__-- _ _ - .
Page No. 36 12/02/85 TABLE 3.2-1 COMMITMENTS FOR PLANT e=================================
OPERATIONS AND SUPPORT
==========
TITLE MODULE REMARES COMMITMENT COMMITMENT DOCUMENT / FEATURE NUMBER COMMITMENT SUBJECT SOURCE SECTION =============e== ====== ====================
== ========== ================ ==================== ================
BYPASS OF RHRS 07 1120 FSAR 7. 6. 2. 2.D PLANT STATUS CONTROLS INTERLOCES AT THE LOCAL STATION IS UNDER STRICT ADMINISTRATIVE CONTROL WITH VALVES LOCEED CLOSED TO PREVENT UNAUTHORIZED OPENING.
ADMIN. CONTROL ENSURES 07 1121 FSAR 7. 6. 4 PLANT STATUS CONTROLS THAT ANT ACCUMULATOR VALVE WHICH HAS BREN CLOSED AT PRESSURES ABOVE SI UNBLOCKING PRESSURE, 15 RETURNED TO AUTO, AND IS VERIFIED TO BE IN FULL OPEN POSITION.
DUST ACCUMULATION ON 07 1141 FSAR 8. 3. 1. 1. CONDUCT OF 3.K OPERATIONS DIESEL GENERATOR CONTROL PANELS WILL BE REMOVED AT PERIODIC INTERVALS TO ENSURE STARTING AND OPERATION OF DIESEL GENERATORS ARE NOT COMPROMISED.
CONDUCT OF EMBRGENCT DIESEL 07 1142 FSAR d. 3. 1. 1.
3.L OPERATIONS GENERATORS WILL NOT BE USED FOR PEAEING SERVICE IN ACCORDANCE WITH BTP ICSB-8, "USE OF DIESEL-GENERATOR SETS FOR PEAKING.*
PLANT PERFORMANCE ALL COMPONENTS OF THE 07 1146 FSAR 8. 3. 2. 1 MONITORING 125-V DC STSTEMS WILL UNDERGO PERIODIC MAINTENANCE TESti TO DETERMINE THE CONDITION OF EACH INDIVIDUAL SUBST5 TEM.
O O O O O O O
O O O O O O O i
Page No. 37
' 12/02/85 TABLE 3.2-1 COMMITMENTS FOR PLANT
=================e====
OPERATIONS AND SUPPORT
==========
COMMITMENT DOCUMENT / FEATURE TITLE MODULE REMARKS NUMBER COMMITMENT COMMITMENT SOURCE SECTION SUBJECT
== ========== ================ ==================== ====================== ================ ====== ==============
I MAINTENANCE TESTING OVERVOLTAGE 07 1147 FSAR 8. 3. 2. '
PROCEDURES AND PROTECTIVE FUNCTIONS DOCUMENTATION IS A PART OF THE-QUALIFICATION OF THE SAFETY-RELATED BATTERY CRARGERS AND IS PERIODICALLY VERIFIED AS A PART OF EQUIPMENT TESTING DURING PLANT OPERATION.
- 1. 1 MAINTENANCE EQUALIZING BATTERY 07 1149 FSAR 8. 3. 2.
PROCEDURES AND CRARGES ARE PERFORMED DOCUMENTATION AFTER A DEEP DISCHARGE OR SEMI-ANNUALLY (AT LEAST 2.33 TO 2.38 V/ CELL OR 137.5 TO 140.4 V/ BATTERY).
PROCEDURES AND TESTING AND j
DOCUMENTATION REPLACEMENT OF LARGB LEAD
! STORAGE BATTERIES FOR NUCLEAR POWER PLANTS B. 3. 1. 5 OPERATIONS AC AND DC POWER 03A,07 1151 FSAR 2.
i PROCEDURES AND SYSTEMS INITIAL i DOCUMENTATION COMPOSITE TEST WILL BE
-PERFORMED AS A i PREREQUISITE TO
' INITIAL FUEL LOADING.
MATERIALS MANAGEMENT BEFORE INSTALLATION. 07 1153 FSAR 8. 3. 2. 2 CELLS ARE STORED IN A CLEAN, LEVEL, DRY AND COOL LOCATION.
EXTREMBLY LOW AMBIENT TEMPERATURES AND LOCALIZED SOURCES OF k HEAT ARE AVOIDED.
l
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l
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i Page No. 38 l 12/02/85 t
TABLE 3.2-1 COMMITMENTS FOR PLANT l
======================
OPERATIONS AND SUPPORT
=== ======
NUMBER COMMITMENT COMMITMENT COMMITMENT DOCUMENT / FEATURE TITLE MODULE REMARKS SOURCE SECTION SUBJECT
================= ===========er========= ===.-============ =====- ===============er
== ========== =====e====
- 1. TECHNICAL SUPPORT PRIOR TO USE. KEW FUEL 07 1154 FSAR 9. 1. 4 PROCEDURES AND STORAGE RACES AND DOCUMENTATION MODULES ARE INSPECTED AND TESTED BY INSERTING A DUMMY FUEL ASSEMBLT INTO THE RACES. NEW FUEL STORAGE RACES ARE PERIODICALLY INSPECTED FOR INTEGRITY.
- 1. 1. SURVEILLANCE TESTING DURING BACH REFUELING 07 1159 FSAR 9. 4. 3.
1 PROGRAMS OUTAGE AND PRIOR TO REMOVING FUEL. THE GRIPPER AND HOIST SYSTEM ARE ROUTINELT LOAD TESTED TO 125% OF THE MAXIMUM SETTING ON THE HOIST LOAD LIMIT SWITCH.
1160 FSAR 9. 1. 4. 4 PLANT PERFORMANCE LIGHT LOAD RANDLING 07 SEE SECTION 9.1.4.4 MONITORING SYSTEM EQUIPMENT OF THE FSAR FOR INSPECTION AND TESTING DETAILS.
REQUIREMENTS.
1161 FSAR 9. 1. 5-5 TECHNICAL SUPPORT DEFLECTION OF THE 07 PROCEDURES AND BRIDGE (SPENT FUEL DOCUMENTATION CASK BRIDOE CRANE) AT ITS CENTER WILL BE MEASURED TO CONFIRM THAT IT IS WITRIN THE LIMITS STATED IN CMAA NO. 70 SECTION 8.2.
1171 FSAR 9. 1. 5. 4 MAINTENANCE NORMAL MAINTENANCE OF 07 PROCEDURES AND THE OVERHEAD REAVY DOCUMENTATION LOAD RANDLING SYSTEM IS PERFORMED IN
- " ACCORDANCE WITH MANUFACTURER'S RECOMMENDATIONS AND ANSI B30.2.
(
O O O O O O O
CL Page No. 39 12/02/85 TABLE 3.2-1 COMMITMENTS FOR PLANT
===u==-======= =======
OPERATIONS AND SUPPORT 4 ======================
COMMITMENT COMMITMENT DOCUMENT / FEATURE TITLE MODULE REMARES NUMBER COMMITMENT i SOURCE SECTION SUBJECT
== ========== ================ ==================== ====================e= ================ ====== ==============
1172 FSAR 9. 1. 5. 4 MAINTENANCE ANSI B30.2-1976 OVERREAD AND 07 PROCEDURES AND GANTRT CRANES DOCUMENTATION 1173 FSAR 9. 1. 5. 4 MAINTENANCE PRIOR TO USE, 0T PROCEDURES AND COMPONENTS AND DOCUMENTATION INTERFACING PORTIONS OF THE OVERREAD REAVT LOAD RANDLING STSTEM COMPONENTS ARE CHECRED TO ENSURE PROPER MATCRUP AMD'VERIFT THET ARE FREE OF FOREIGN OR LOOSE PARTS.
1183 FSAR 9. 2. 5. 4 PLANT PERFORMANCE PERIODIC INSPECTIONS 07 MONITORING OF THE NSCW COOLING TOWER FILL MATERIAL WILL BE CONDUCTED TO DETECT DETERIORATION.
1191 FSAR 9. 3. 1. 4 MAINTENANCE AIR COMPRESSORS AND 07 PROCEDURES AND ASSOCIATED COMPONENTS DOCUMENTATION ON STANDBT, INCLUDING BREATHING AIR STSTEM ARE CRECEFD AND OPERATED PERIODICALLT.
AIR FILTERS ARE INSPECTED AND DESICCANT CHANGED.
1207 FSAR 9. 3. ?-5 PLANT STATUS TURBINE BUILDING DRAIN 07 CONTROLS VALVES A-2412.-547,554,551 AND 553 WILL BE LOCEED CLOSED DURING UNIT 2 CONSTRUCTION.
f 4
i O
Page No. 40 12/02/85 TABLE 3.2-1 COMMITMENTS FOR PLANT
=======e==============
OPERATIONS AND SUPPORT
==========
TITLE MODULE REMARKS NUMBER COMMITMENT COMMITMENT COMMITMENT DOCUMENT / FEATURE SOURCE SECTION SUBJECT
=-==== == ========== ================ ==_========_======== : ============-======= ================ ====== =_=================-
- 4. 1. 6 PLANT PERFORMANCE CONTROL ROOM RVAC 07 1221 FSAR 9.
MONITORING FILTER PRESSURE DROP IS PERIODICALLT CHECKED.
4 SURVEILLANCE TESTING FHB POST-ACCIDENT HEPA 07 1238 FSAR 9. 4. 2. 2.
PROGPAMS FILTER BANKS ARE TRSTED PERIODICALLT PER REG GUIDE I.52. -
ENTIRE FILTRATION TRAINS ARE TESTED REGULARLT PER POSITION C.5 OF REG GUIDE I.52.
- 2. 4 SURVEILLANCE TESTING FHB POST-ACCIDENT 07 1239 FSAR 9. 4. 2.
PROGRAMS ACTIVATED CARBON IS BATCH TESTED PRIOR TO LOADING. AND SAMPLRS ARE TESTED PERIODICALLT.
OPERATIONJ PENETRATIN AREA FILTRATION AND EXHAUST SHALL BE LOCKED IN POSITION WHEN PRESSURE BALANCE IS ATTAINED.
4 SURVEILLANCE TESTING AUX. BUILDING NORMAL 07 1243 FSAR 9. 4. 3. I.
PROGRAMS HVAC FILTER PRESEURE DROP AND RIGR-BFFICIENCY FILTER ARE CHECRED PERIODICALLT. FILTSR AND ADSORBER INTERIM TESTS AND INSPECTION WILL BE PERFORMED PER REG GUIDE 1.140 O O O O O O O
O O O Page No. 41 12/02/85 TABLE 3.2-1 COMMITMENTS FOR PLANT
======================
OPERATIONS AND SUPPORT
==========
NUMBER COMMITMENT COMMITMENT COMMITMENT DOCUMENT / FEATURE TITLE MODULE REMARES SOURCE shCTION SUBJECT
== ========== ================ ==================== ====================== ================ ====== ==============
1244 FSAR 9. 4. 3. 1. 4 SURVEILLANCE TESTING AUX. BUILDING NORMAL 07 PROGRAMS HVAC FILTER PRESSURE DROP AND HIGR-EFFICIENCT FILTER ARE CHECEED PERIODICALLT.
1245 FSAR 9. 4. 3. 1. 4 SURVEILLANCE TESTING IMPLACE FREON LEAK 07 PROGRAMS TESTING OF CHARCOAL ADSORBERS IS PERFORMED IN ACCORDANCE WITH REG GUIDES 1.52 AND 1.140.
1246 FSAR 9. 4. 3. 1. 4 MAINTENANCE AUX BLDG. RVAC - 07 PROCEDURES AND INPLACE TESTING OF DOCUMENTATION CHARCOAL ADSORBERS IS PERFORMED WITH A SUITABLE REFRIGERANT TO CHECK FOR BRD BTPASS LEAEAGES IN ACCORDANCE WITH REG.
GUIDES 1.52 AND 1.140.
1247 FSAR 9. 4. 3. 1. 4 MAINTENANCE AUX BLDG. HVAC FILTER 07 ,
PROCEDURES AND AND ADSORBER INTERIM DOCUMENTATION. TESTS AND INSPECTIONS WILL BE PERFORMED IN ACCORDANCE WITH THE RECOMMENDATIONS OF REGULATORT GUIDE 1.140.
1248 FSAR 9. 4. 3. 1. 4 MAINTENANCE RG 1.52, R/2 DESIGN, TESTING. 07 CONFORMANCE IS PROCEDURES AND AND MAINTENANCE DISCUSSED IN SECTION DOCUMENTATION CRITERIA FOR 1.9.52.2 0F THE
'- POST ACCIDENT FSAR.
ENGINEERED
! SAFETT FEATURE ATMOSPHERE CLEANUP STSTEM.
! AIR FILTRATION AND ADSORTTION-UNITS FOR LIGHT WATER COOLED 1 NUCLEAR POWER
{ PLANTS
.i C
1
l l
l t
Page No. 42 12/02/85 TABLE 3.2-1 COMMITMENTS FOR PLANT
! ==================================
OPERATIONS AND SUPPORT
,=,-==================
TITLE MODULE REMARES NUMBER COMMITMENT COMMITMENT COMMITMENT DOCUMENT / FEATURE SOURCE SECTION SUBJECT
========== ====== ==============
== ========== ================ ==================== ============e===
RG 1.140 DESIGN. TESTING. 07 CONFORMANCE IS 1249 FSAR 9. 4. 3. 1. 4 MAINTENANCE R/l DISCUSSED IN SECTION PROCEDURES AND AND MAINTENANCE DOCUMENTATION CRITERIA FOR 1.9.140.2 OF TRE NORMAL FSAR.
VENTILATICP EIHAUST SYSTEM AIR FILTRATION AND ADSORPTION UNITS OF LIGHT WATER COOLED NUCLEAR POWER PLANTS
- 3. 4 MAINTENANCE IMPREGNATED. ACTIVATED 07 1253 FSAR 9. 4. 2.
PROCEDURES AND CARBON IS BATCH TESTED DOCUMENTATION PRIOR TO LOA 9ING INTO THE ADSORBER BRD.
ACCEPTANCE CRITERIA ARE THOSE DESCRIBED IN TABLE 1 OF REG. GUIDE 1.52 AND RDT-M-16-lT.
4 MAINTENANCE ESF HVAC FILTER 07 1254 FSAR 9. 4. 3. 2.
PROCEDURES AND PRESSURE DROP AND REPA DOCUMENTATION FILTER EFFICIENCY ARE CHECKED PERIODICALLY.
- FILTERS AND ABSORSERS ARE TESTED AFTER INITIAL INSTALLATION AND SUBSEQUENT TO EACH FILTER OR ADSORBER CHANCE.
1255 FSAR 9. 4. 3. 2. 4 PLANT PERFORMANCE REPA FILTER BANES ARE OT MONITORINGS TESTED IN PLACE PRIOR TO OPERATION TO VERIFT EFFICIENCY OF AT LEAST 99.97 PERCENT IN
. ACCORDANCE WITR REG.
- GUIDE 1.52 AS DISCUSSED IN SECTION
'- 1.9.
t O O O O O O O
O O O O O O O Page No. 43 12/02/85 TABLE 3.2-1 COMMITMENTS FOR PLANT
=================e====
OPERATIONS AND SUPPORT
==========
NUMBER COMMITMENT COMMITMENT COMMITMENT DoctfMENT/ FEATURE TITLE MODULE REMARKS SOURCE SECTION SUBJECT
====== == ========== e=============== ==================== ====================== ================ ====== =================-.
1256 FSAR 9. 4. 3. 2. 4 MAINTENANCE ESF RVAC FILTERS .AND 07 PROCEDURES AND ADSORBERS INTERIM DOCUMENTATION TESTS AND INSPECTIONS ARE PERFORMED IN ACCORDANCE WITH RECOMMENDATIONS OF REO. GUIDE 1.52.
i 1257 FSAR 9. 4. 3. 2. 4 SURVEILLANCE TESTING EST HVAC FILTER 07 PROGRAMS PRESSURE DROP AND HEPA FILTER EFFICIENCT ARE CNBCERD PERIODICALLT.
- FILTERS AND ABSORBERS ARE TESTED SUBSEQUENT TO BACH FILTER OR ADSORBER CHANGE PER REG GUIDE 1.52.
1259 FSAR 9. 4. 3. 3. 4 SURVEILLANCE TESTING HEPA FILTER BANKS ARE 034,07 PROGRAMS TESTED IN PLACE PRIOR TO OPERATION IN ACCORDANCE WITH REG.
GUIDE I.140 AS DISCUSSED IN SRCTTON 1.9.
4 1266 FSAR 9. 4. 5. 6 MAINTENANCE REPA FILTERS ARE 07 PROCEDURES AND TESTED PRIOR 70 DOCUMENTATION INSTALLATION IN ACCORDANCE WITH MSL-F-51068C AS MODIFIED BT NRC HEALTH AND SAFETT INFORMATION ISSUE 306, 1267 FSAR 9. 4. 5. 6 MAINTENANCE IMPREONATED. ACTIVATED 07 PROCEDURES AND CARBON IS BATCH TESTED
, DOCUMENTATION PRIOR TO LOADING INTO THE ADSORBER BED.
ACCEPTANCE CRITERIA ARE THOSE DESCRIBED IN j TABLE 1 0F REG. GUIDE e
1.52 AND RDT-M-16-lT.
(
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i
Page No. 44 12/02/85 TABLE 3.2-1 COMMITMENTS FOR PLANT
=========-e===========
OPERATIONS AND SUPPORT
==========
DOCUMRNT/ FEATURE TITLE MODULE REMARES NUMBER COMMITMENT COMMITMENT COMMITMENT SOURCE SECTION SUBJECT
= = == ========== ===========e==== ==================== ====================== == ======== ==== ====== ================-
CONTRCL BUILDIMG EST 07 1268 FSAR 9. 4. 5. 6 PLANT PERFORMANCE MONITORING HVAC FILTER PRESSURE DROP AND REPA FILTER EFFICIENCY ARE CHECRED PERIODICALLT. -
FILTERS AND ADSORBERS ARE TESTED SUBSEQUENT TO EACH FILTER OR ADSORBER CHANGE.
- 6. 4 MAINTENANCE IMPREGNATED, ACTIVATED 07 1271 FSAR 9. 4.
PROCEDURES AND CARBON IS BATCH TESTED DOCUMENTATION PRIOR TO LOADING INTO THE ADSORBER BRD.
ACCEPTANCE CRITERIA ARE THOSE DESCRIBED IN TABLE 1 0F REG. GUIDE 1.52 AND RDT-M-16-lT.
- 4. 4 PLANT PERFORMANCE REPA FILTER BANES ARE 03A,07 1272 FSAR 9. 6.
MONITORING TESTED IN PLACE PRIOR TO OPERATION IN ACCORDANCE NITH REG GUIDE 1.140,
PROGRAMS VENTILATION SYSTEM FANS ARE TESTED IN ACCORDANCE WITH AMCA STANDARD 210.
4 SURVEILLANCE TESTING PIPING PENETRATION 07 1279 FSAR 9. 4. 9. 3.
PROGRAMS VENTILATION SYSTEM FANS ARE TESTED IN ACCORDANCE WITR AMCA STANDARD 210 TO ENSURE FAN CHARACTERISTIC PERFORMANCE CURVES.
O O O O O O O
O O O O O O O Page No. 45 12/02/85 TABLE 3.2-1 COMMITMENTS FOR PLANT
=================================e OPERATIONS AND SUPPORT
=-=============
NUMBER COMMITMENT COMMITMENT COMMITMENT DOCUMENT / FEATURE TITLE MODULE HEMARES ;
I SOURCE SECTION SUBJECT
== ========== ================ ==================== ====================== ================ ====== ==============
12C2 FSAR 9. 5. 1. 2. 1. F1HE PROTECTION USE OF COMPRESSED 07 1 PROGRAM GASES IS CONTROLLED it OPERATIONAL PROCEDURES IN ACCORDANCE WITH NFPA 6 INDUSTRIAL FIRE LOSS PROTECTION.
1283 FSAR 9. 5. 1. 2. 1. FIRE PROTECTION SELF-CLOSING 07 2 PROGRAM OPERABILITY OF FIRE BARRIER DOORS IS MONITORED TRROUGH ADMINISTRATIVE CONTROLS IN PLANT PROCEDURES.
1280 FSAR 9. 5. 1. 2. 1. FIRE PROTECTION DURING THE OPERATION 07 3 PROGRAM OF THE SMORE EIRAUST SYSTEM. FIRE DOORS AND FIRE DAMPERS WILL BE TIGRTLY CLOSED TO PREVENT TRE MOVEMENT OF SMOEE TO OTHER-AREAS OF TRE BUILDING. ;
1290 FSAR 9. 5. 5. 4 PLANT PERFCRMANCE DIESFL GENERATOR 07 MONITORING COOLING WATER SYSTEM IS OPERATIONALLY CHECRED DURING PERIODIC TESTING OF THE DIESEL GENERATOR SYSTEM. .
l 1291 FSAR 9 5. S 4 PLANT PFPFORMANCR EEEP-WARM SYSTEM IS 07 MONITORIPG OPERATIONALLY CHECRED DURING DIESBL .
GENERATOR SHUTDOWN PERIODS.
1294 FSAR 9. 5. 6. 4 PLANT PERFORMANCE STARTING AIR 07
- ' MONITORING COMPRESSOR FOR EACH DIESEL ENGINE IS TESTED PERIODICALLY TO
( ASSURE CONTINUED OPERABILITY.
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- 8 4 ('
Page No. 46 12/02/85 *ABLE 3.2-1 COMMITMENTS FOR PLANT
======================
OPERATIONS AND SUPPORT
==========
TITLE MODULE REMARES COMMITMENT COMMITMENT COMMITMENT DOCUMENT / FEATURE NUMBER SOURCE SECTION SUBJECT
== ========== ==s==========r== ==================== ====================== ================ ====== ==============
DG LUBRICATING SYSTEM 03A,07 1236 FSAR 9. 5. 7. 4 DIESEL GENERATOR LUBRICATING SYSTEM IS OPERATIONALLY TESTED DURING THE STARTUP AND CHECKOUT OF THE DIESEL GENERATOR.
5, 7. 4 MAINTENANCE DIESEL LUBE OIL WILL 07 2718 FSAR 9.
HAVE THE FOLLONING PROCEDURES AND DOCUMENTATION TESTS PERFORMFD:
EINEMATIC VISCOSITT, NATER CONTENT AND NEAR METATL CONTENT.
MAINTENANCE THE FREQUENCY OF LUBE 07 2719 FSAR 0. 5. 7. 4 PROCEDURES AND OIL ANALYSIL L' LL BE DOCUMENTATION MONTHLT FOR THE FIRST 3 'AONTHS OF DIESEL OPERATION, QUARTERLY FOR THE NEXT 9 MONTHS, AND SEMIANNUALLY THEREAFTER.
- 8. 4 PLANT PERFORMANCE DIESEL GENERATOR 07 1298 FSAR 9. 5.
MONITORING COMBUSTION AIR INTAEE AND EIHAUST SYSTEM IS OPERATIONALLT CHECERD DURING PERIODIC TESTING OF THE DIESEL GENERATOR STSTEM.
5 PREVENTIVE TESTING OF DIESEL 07 1299 FSAR 9. 5. 8.
MAINTENANCE ENGINE AIR INTAEM AND EXHAUST STSTEM INSTRUMENTATION WILL
! BE ON A PERIODIC SCHEDULE IN ACCORDANCE WITH MAINTENANCE AND TEST RECOMMENDATIONS MADE BY THE ENGINE MANUFACTURER. ,
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O O O O O O O
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A d
Page No. 47 12/02/85 TABLE 3.1-1 COMMITMENTS FOR PLANT
====_============_========== =,
OPERATIONS AND SUPPORT
-:========,==
DOCUMENT / FEATURE TITLE MODULE REMARES NUMBER COMMITMENT COMMITMENT COMMITMENT SOURCE SECTION SUBJECT
- == == ========== ================ ================-=== ================== === ================ ====== ================
3, $URVEILLANCE TESTING INSERVICE INSPECTIONS. 07 1312 FSAR 10. 2. 6.A PROGRAMS PER ASME SECTION XI, FOR TURBINE ASSEMBLY AND VALVES. INCLUDE:
A. DISASSEMBLY OF THE TURBINE DURING SRUTDOWN. INSPECTION OF PARTS NORMALLY INACCESSIBLE DURING OPERATION.
SURVEILLANCE TESTING TURBINE IS INSPECTED 07 1316 FSAR 10. 2. 3. 6.A PROGRAMS IN SECTIONS SO THAT OVER A 10 TEAR PERIOD TRE ENTIRE TURBINE IS INSPECTED ONCE.
- 3. 6.B SURVEILLANCE TESTING AT LEAST ONE MAIN 07 1315 FSAR 10. 2.
PROGRAMS STEAM STOP VALVE. ONE MAIN STEAM CONTROL VALVE. ONE COMBINED INTERMEDIATE STOP VALVE. AND ONE INTERCEPT VALVE IS DISMANTLED APPROXIMATELY EVERY 3 i YEARS DURING SCHEDULED REFUELING.
SURVEILLANCE TESTING ALL EXTRACTION 07' 2724 FSAR 10. 2. 3. 6.D PROGRAMS NONRETURN VALVES WILL BE TESTED PRIOR TO EACH STARTUP.
i i
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3
=
Page No. 48 12/02/85 TABLE 3.2-1 COMMITMENTS FOR PLANT
- ================================
OPERATIONS AND SUPPORT
==========
COMMITMENT COMMITMENT DOCUMENT / FEATURE TITLE MODULE REMARKS NUMBER COMMITMENT SOURCE SECTION SUBJECT
=== == ========== ================ ==================== ======-=============== ================ ====== ==================
- 4. 4 TURBINh svPAss 10hh1hh BYPASS VALVE 5 03A,07 1344 FSAR 10. 4.
VALVES ARE TESTED FOR OPERABILITT PRIOR TO BEING PLACED IN SERVICE. (10.4.4.4)
FSAR 10. 4. 9. 4 MAINTENANCE TRERE WILL BE DOUBLE 07 2725 PROCEDURES AND VERIFICATION OF PROPER DOCUMENTATION VALVE ALIGNMENT AFTER AURILIARY FEEDWATER SYSTEM MAINTENANCE.
2 PLANT STATUS TWO VALVES (035 AND OT 1356 FSAR lO.A. 2.
CONTROLS 056) IN THE CROSSOVER TIELINE ON THE DISCHARGE SIDE OF THE AFWS MOTOR DRIVEN
.' UMPS ARE NORMALLT LOCKED.
- 11. 4 RADIOACTIVE WASTE ADMINISTRATIVE 07 2726 FSAR 4. 2. 3.
PROCEDURES AND CONTROLS ARE USED AND DOCUMENTATION RECORDS MAINTAINED TO ENSURE SAFE SIDE REQUIREMENTS SUCH AS DRUM INSPECT?ON, PROPER CEMENT QUANTITIES, AND INSERTION OF A DRUM MIRING WEICHT.
2727 FSAR 11, 4. 2. 3. 9 RADIOACTIVE WASTE ADMINISTRATIVE 07 PROCEDURES AND CONTROLS ARE USED AND DOCUMENTATION RECORDS MAINTAINED TO ENSURE THAT THE DRT PRODUCT SOLIDIFICATION STSTEM PROCESS IS OPERATED WITHIN THE ESTABLISHED 4 i BOUNDARIES.
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O O O O. O O O
- o o o o o_ o o Pete No. 49 12/02/85 COMMITMENTS FOR PLANT TABLE 3.2-1
======================
OPERATIONS AND SUPPORT e=============e=======
TITLE MODULE REMARES COMMITMENT COMMITMENT DOCUMENT / FEATURE NUMBER COMMITMENT SOURCE SECTION SUBJECT
e==== == -=====_-=== ======-===e===== =====_ ============= =-==================== ================ ====== ====== =====-======
SOLIDIFIED WASTES ARE 07.9A 49 CFR 173.395fA)(1) 1369 FSAR 11. 4. 2. 3.10 SOLIDIFIED WASTE PACKAGING PACEAGED IN ACCORDANCE WITH 49CFR173.395(A)(1) i 07,9A 1376 FSAR 12. 1. 1. 1 INITIAL TEST PROGRAM DURING INITIAL POWER l OPERATIONS, RADIATION SURVETS WILL BE CONDUCTED.
THE OPENING OF HATCRES 07 2732 FSAR 12. 3. 2. 2. 9 OPERATIONS PROCEDURES AND ON THE FUEL TRANSFER DOCUMENTATION TUBE IS ADMINISTRATIVELT CONTROLLED.
HOUSEEEEPING 03A,07
=
1500 FSAR 12. 5. 3. 2. 9 CONDUCT OF OPERATIONS RECOMMENDATIONS OF REGULATORT GUIDE 1.39 AND THE REFERENCED ANSI M45.2.3 WILL BE IMPLEMENTED TO TRE MAXIMUM PRACTICABLE.
3 TRAINING MEETINGS WILL 07 1564 FSAR 13. 1. 1. l. 2. CONDUCT OF 4 MAINTENANCE BE HELD TO FOSTER SAFETT AWARENESS AND QUALITT OF
' WORKMANSHIP, EXCEPT FOR 07 1565 FSAR 13. 1. 1. 1. 2. CONDUCT OF MAINTENANCE EMERGENCIES, 4
MAINTENANCE WORK WILL BE PREPLANNED.
MAINTENANCE AND 07 1566 FSAR 13. 1. 1. 1. 2. CONDUCT OF 4 MAINTENANCE REPAIRS WILL BB PERFORMED BT QUALIFIED I PERSONNEL IN ACCORDANCE WITH l
WRITTEN WORE ORDERS, MAINTENANCE
' PROCEDURES, STANDING ORDERS, VENDOR i
MANUALS, AND l- APPLICABLE CODES AND
' REGULATIONS.
1
(
PnEe No. 50 12/02/85 COMMITMENTS FOR PLANT TABLE 3.2-1
-====-,===========================
OPERATIONS AND SUPPORT
=================
DOCUMENT / FEATURE TITLE MODULE REMARES NUMBER COMMITMENT COMMITMENT COMMITMENT SOURCE SECTION SUBJECT
== -=======e= ===========e-=== ===================e ====e================= ================ ====== ==============
RECORDS WILL BE REPT 07 1567 FSAR 13. I. 1. 1. 2. PREVENTIVE 4 MAINTENANCE TO ESTABLISH THE MAINTENANCE RISTORY OF MAJOR SAFETT-RELATED EQUIPMENT.
PREVENTIVE SCOPE AND FREQUENCY OF 07 1568 FSAR 13. I. 1. 1. 2.
4 MAINTENANCE PREVENTIVE MAINTENANCE WILL BE BASED ON PAST EXPERIENCE WITH SIMILAR EQUIPMENT AND MANUFACTURER'S RECOMMENDATIONS.
2 OPERATIONS OPERATIONS SUPERVISOR 07 1571 FSAR 13. 1. 2. 2.
ORGANIZATION AND 15 RESPONSIBLE FOR ADMINISTRATION SEEING THAT PLANT OPERATIONS ARE CONDUCTED IN ACCORDANCE WITH STANDING ORDERS.
OPERATING PROCEDURES AND TECH. SPECS.
(NUREG-0737 ITEM I.A.I.2).
- 1. 2. 2. 2 OPERATIONS SUCCESSION TO 07 1572 FSAR 13.
ORGANIZATION AND RESPONSIBILITT: (A)
ADMINISTRATION GMVNO (B) DEPUTT GENERAL MANAGER (C)
MGR. - UNIT OPERATIONS (D) SUPERINTENDENT -
SRIFT SUP
ORGANIZATION AND FUNCTIONALLT TO THE ADMINISTRATION OPERATIONS SUPERVISOR.
e s
O O O O O O O
_ . . _ ~ ~ . -. - . . - ~. . . . - - . . - . . - . - - . - . . - . . _ - . . . - . . . . - . . , . ~ ~ - . . . - ~ - . . - .- ..~ ... .. . . . . ~ ~ .
Page No. 51 12/02/85 TABLE 3.2-1 COMMITMENTS FOR PLANT
=================e====
OPERATIONS AND SUPPORT
==========
NUMBER COMMITMENT COMMITMENT COMMITMENT DOCUMFMT/ FEATURE TITLE MODULE REMARKS SOURCE SECTION SUBJECT
== ========== ================ ==================== -===================== ============ === ====== ==============
1574 FSAR 13. 1. 2. 2. 2 OPERATIONS ON-SRIFT OPERATIONS 07 ORGANIZATION AND SUPERVISOR'S PRINCIPAL ADMINISTRATION RESPONSIBILITY IS ENSURING SAFE PLANT OPERATION DURING HIS ASSIGNED SNIFT AS ADDRESSED IN THE REQUIREMENTS OF ITEM 1.A.I.2 0F NUREG -
0737.
1575 FSAR 13. 1. 2. 2. 2 OPERATIONS NUREG 0737 ITEM CLARIFICATION OF 07 ORGANIZATION AND I.A.I.2 TMI ACTION PLAN ADMINISTRATION REQUIREMENTS 1576 FSAR 13. 1. 2. 2. 2 OPERATIONS STA REPORTS 07 ORGANIZATION AND ADMINISTRATIVELT TO ADMINISTRATION SENIOR STA. SENIOR STA REPORTS TO SUPERINTENDENT -
OPERATIONS. STA POSITION MEETS THE INTENT OF NUREG-0660 AS CLARIFIED BT NURBG 0737, ITEM I.A.I.l.
1577 FSAR 13. 1. 2. 2. 2 OPERATIONS NUREG 0737 ITEM CLARIFICATION OF 07 ORGANIZATION AND I.A.I.1 TM1 ACTION PLAN ADMINISTRATION REQUIREMENTS 15R5 FSAR 13. 1. 2. 2. 5. OPERATIONS INITIAL TEST MANAGER 02,03A 1.A ORGANIZATION AND AND PROGRAM 07 9
~
ADMINISTRATION SUPERINTENDENTS SHALL RAVE A BACHELORS DEGREEE IN ENGINEERING OR RELATED SCIENCE AFL
' 4 TBARS EXPERIENCE IN RESPONSIBLE POSITIONS i INCLUDING 3 TEARS IN j NUCLEAR POWER.
(-
mr Psge No. 52 12/02/05 TABLE 3.2-1 COMMITMENTS FOR PLANT
=============-========
OPERATIONS AND SUPPORT
==========
TITLE MODULE REMAR'S NUMBER COMMITMENT COMMITMENT COMMITMENT DOCUMENT / FEATURE SOURCE SECTION SUBJECT
===== ======e===========-=== ================ ====== e:============
====== == ========== ================ =======e LEAD TEST SUPERVISORS 02,037.
1586 FSAR 13. 1. 2. 2. 5. OPERATIONS ORGANIZATION AND AND PREOF AND STARTUP 07 1.B ADMINISTRATION PROGRAM SUPERVISORS SHALL HAVE A BACHELORS DEGREE IN ENGR OR SCI AND 3 TEARS OF EXPERIINCE INCL 2 IN NUC PWR OR RS DIPLOMA AND 7 TEARS OF EXPERIENCE INCL 4 IN NUC PNR.
OPERATIONS TEST SUPERVISORS 02,07 1587 FSAR 13. 1. 2, 2 5.
1.E ORGANIZATION AND (STARTUP PHASE) SHALL ADMINISTRL? TON HAVE A BACHELORS DEGREE IN TEGR OR SCI AND 2 TEARS EXPERIENCE INCLUDING 1 TEAR IN NUC PWR OR RS DIPLOMA AND 6 YEARS BKPERIENCE INCLUDING 3 IN NUC PWR.
ORGANIZATION AND FUEL HANDLING ADMINISTRATION ACTIVITIES IN THE REACTOR CONTAINMENT
- 13. 1. 2. 3 OPERATIONS TCTAL MAN POWER IN 07 1592 FSAR ORGANIZATION AND EXCESS OF FIVE FULL ADMINISTRATION SHIFT CRE*WS IS PROVIDED 13, 2, FIRE PROTECTION FIRE BRIGADE INITIAL 07 SEE SECTION 1706 FSAR 2. 1.
9.A PROGRAM TRAINING - PERSOMMEL 13.2.2.1.9.A IN THE ASSIGNED TO ANT FIRE FSAR FOR DETAILS.
BRIGADE WILL COMPLETE TRAINING A3 DESIGNATED IN THE FSAR, APPENDIX 9B BEFORE BEING ASSIGNED.
e f
9 O O O O O O
O c_ ) O Page No. 53 12/02/85 ,
TABLE 3.2-1 COMMITMENTS FOR PLANT
================-=====
OPERATIONS AND SUPPORT
===============
COMMITMENT DOCUMENT / FEATURE TITLE MODULE RFMARES NUMBER COMMITMENT COMMITMENT SOURCE SECTION SUBJECT
== ========== ================ ========== ====e==== ====================== ================ ====== ==============
1707 FSAR 13. 2. 2. 1. FIRE PROTECTION QUARTERLY TRAINING 07 9.B PROGRAM WILL BE PROVIDED TO BACH FIRE BRIGADE MEMBER TO REVIEW CHANGES IN THE FIRE PROTECTION PROGRAM AND PROVIDE REFRESHER TRAINING.
1708 FSAR 13. 2. 2. 1. FIRE PROTECTION QUARTERLY DRILLS SHALL 07 REFER TO APPENDIX 9.B PROGRAM BE PERFORMED AND SRALL 95, 9.5.1.C.E.d(7).
BE REPEATED IN SUFFICIENT FREQUENCY a TO ENSURE THAT EACH MEMBER WILL BE IN 2 DRILLS / TEAR.
- 13. 2. 2. 1. FIRE PROTECTION AT LEAST ONE FIRE 07 1709 FSAR
. 9.B PROGRAM DRILL PER TEAR WILL BE UNANNOUNCED TO DETERMINE THE READIMESS OF TRE FIRE
- BRIGADE.
2747 FSAR 13, 2. 2. 1. FIRE PROTECTION REFRESRER CLASSROOM OT REFER TO APPENDIX 9.B.1 PROGRAM TRAINING COURSES WILL 95, 9.5.1.C.3.d.
BE RELD FOR ALL FIRE SECTIONS (4) AND BRICADE MEMBERS EVERT (5).
4 2 TEARS.
1711 FSAR 13. 2. 2. 1. FIRE PROTECTION AT LEAST ONCE PER 07 REFER TO APPENDIX 9.B.2 PROGRAM TRAR, A DRILL SHALL BE 95, 9.5.1.C.3.d(7).
i PERFORMED ON A "BACE
! SHIFT" FOR BACH SHIFT FIRE BRIGADE.
1710 FSAR 13. 2. 2. 1. FIRE PROTECTION EACH MEMBER OF THE 07 REFER TO APPENDIX 9.C PROGRAM FIRE BRIGADE WILL 95, 9.5.1.C.3.d.
EXPERIENCE ACTUAL FIRE EXTINGUISBMENT ON AN f ANNUAL BASIS. THIS MAT 4 ,
BE DONE IN TBE QUARTERLY TRAINING j .
SESSIONS.
.f l-
Page No. 54 12/02/85 COMMITMENTS FOR PLANT TABLE 3.2-1
-==================se====a==- ==
OPERATIONS AND SUPPORT
=======r ========e=
DOCUMENT / FEATURE TITLE MODULE REMARKS NUMBER COMMITMENT COMMITMENT COMMITMENT SOURCE SECTION SUBJECT
== =====e==== ================ ==================== ====================== ================ ====== ==,===========
9B, 9.5.1.C.3.d.
9.C PROGRAM BE HELD AT LEAST ONCE PER YEAR FOR EACH SHIFT BRIGADE ON THE PROPER METRODS OF FIGHTING POSSIBLE PLANT FIRES. BREATHING APPARATUSES, AND UNDER STREMUOUS CONDITIONS.
- 1. FIRE PROTECTION INSTRUCTION OF THE 07 2749 FSAR 13. 2. 2.
9.D PROGRAM FIRE BRIGADE WILL PE PROVIDED BY OUALIFhED INDIVIDUALS SUITABLY TRAINED IN FIGHTING THE TYPES OF FIRES THAT COULD OCCUR IN THE PLANT. USING THE TYPES OF EQUIPMENT AVAILABLE IN THE PLANT.
- 13. L. FIRE PROTECTION TRAINING FOR EMPLOYEES 07 2750 FSAR 2. 2.
9.E PROGRAM ALLOWED UNESCOURTED ACCESS WILL INCLUDE INSTRUCTIONS IN FIRE PROTECTION ADMIN.
CONTROLS. FIRE BARRIER AND BARRIER PENETRATION SEALS.
RESPONSE TO FIRE ALARMS AND ACTION UPON DISCOVERY OF FIRES.
2751 FSAR 13. 2. 2. 1. FIRE PROTECTION THE CAPABILITY TO 07 9.E PROGRAM EVACUATE THE PLANT FACILITIES WILL BE EVALUATED ANNUALLY.
THIS EVALUATION MAY BE CONDUCTED COINCIDENTALLY WITH EMERGENCY PLAN EXERCISES OR DRILLS.
O O O O O O O
O O PnRe No. 55 12/02/85 TABLE 3.2-1 COMMITMENTS FOR PLANT
--===:============ === ====-e==-==
OPERATIONS AND SUPPORT
= =======
COMMITMENT DOCUMENT / FEATURE TITLE MODULE REMARES NUMBER COMMITMENT COMMITMENT SOURCE SECTION SUBJECT
===========e========== ======e========= ====== ==================== i
e== == ===== ==== ================ =================
1729 FSAR 13. 5. 1. l.A PROCEDURES AND ADMINISTRATIVE 02.05 DOCUMENTATION PROCEDURES ESTABLISH OT.9A.
CONTROLS FOR THE 9B.15 3 L
PREPARATION. REVIEW AND CONTROL OF PLANT PROCEDURES WRICH COVER ACTIVITIES AS DESCRIBED IN APPENDIX ,
A 0F REG GUIDE 1.33 REV. 2. ,
l !
- 1. l.A ADMINISTRATIVE 02.05, i 1730 FSAR 13. 5. PROCEDURES AND DOCUMENTATION PROCEDURES EMSURE TRAT OT.9A.
NEW OR REVISED PLANT 98.15 PROCEDURES ARE REVIEWED FOR ADEQUACT BY APPROPRIATELT QUALIFIED PERSONNEL OTHER TRAN TRE ORIGINATOR.
a
- 13. 1. l.A PROCEDURES AND NUCLEAR OPERATIONS 02,05 1731 FSAR 5.
DOCUMENTATION DEPARTMENT NEADS. 07.94 UNDER DIRECTION OF TRE 98.15 GENERAL MANAGER - l i VOGTLE NUCLEAR OPERATIONS. ARE TRE APPROVING AUTHORITT FOR PROCEDURES COVERING ACTIVITIES WITHIN TREIR AREA OF j
RESPONSIBILITT.
.,6 i 1732 FSAR 13. 5. 1. l.A PROCEDURES AND PROCEDURES ENSURE THAT 02.05 DOCUMENTATION CHANGES OR REVISIONS 07.9A, 4
TO PROCEDURES ARE 98.15 REVIEWED AND APPROVED IN ACCORDANCE WITR THE 4
SAME ADMINISTRATIVE ;
I
' CONTROLS USED FOR NEW
! PROCEDURES.
I
- ( >
1 i
C
_ _ . . _ _ _ . _ _ _ _ _ _ _ _ _ . _ _ _ . _ . . _ _ _ _ _ _ _ _ _ _ . _ _ _ _ . . _ . _ _ _ . _ _ _ _ _ -.__m_ _ _ - . - . _ , _ _ _ . _ - _ _ _ __ _ _________._.___________m_ _ _ . _ _ _ _ _ _
PnEe No. 56 12/02/85 TABLE 3.2-1 COMMITMENTS FOR PLANT
========================-
OPERATIONS AND SUPPORT
ser== ======e=====
NUMBER COMMITMENT COMMITMENT COMMITMENT DOCUMENT / FEATURE TITLE MODULE REMARKS SOURCE SECTION SUBJECT
== ========== ================ ===================- ===========e==-e====== ================ ===== ==============
1733 FSAR 13, 5. 1. l.A PHUCBUUHbb A4D FMOCEDURE5 Eh5URE IH4T 02.C$.
DOCUMENTATIO4 PLANT PROCEDURES ARE 07,9A, REVIEWED AT LEAST 9B.15 EVERY 2 YEARS BY A KNOWLEDGEABLE INDIVIDUAL.
1734 FSAR 13. 5. 1. l.A PROCEDURES AND PROCEDURES ENSURE THAT 02.05, DOCUMENTATION PLANT PROCEDURES, ONCE 07,9A.
APPROVED, ARE 9B,15 DISTRIBUTED APPROPRIATRLY SO THAT ONLY THE MOST CURRENT PROCEDURES ARE USED BY PLANT PERSONNEL.
2755 FSAR 13. 5. 1. l.A PROCEDURES AND REVIEWER SHALL 02,05, DOCUMENTATION ESTABLISR ENOWLEDGE OF 07,9A, THE APPLICABLE 98,15 REQUIREMENTS FOR A PROCEDURE AND SHALL
%ERIFY PROPER INCORPORATION OF THESE REQUIREMENTS IN THE PROCEDURE.
2756 FSAR 13, 5. 1. l.A PROCEDURES AND REVIEWER SHALL ASSESS 02,05, DOCUMENTATION WHETHER THE PROCEDURE 07.9A, OR PROCEDURE REVISION 98,15 POTENTIALLY INVOLVES A CHANGE IN THE YEGP TECHNICAL SPECIFICATIONS OR AN UNREVIEWED SAFETY QUESTION.
2757 FSAR 13. 5. 1. l.A PROCEDURES AND ACCEPTABILITY OF 92,05 DOCUMENTATION PROCEDURE REVIEWS IS 77.9A, ASSURED BY REVIEW AND UB.15 APPROVAL OF REVIEW BY TRE RESPONSIBLE VEGP NUCLEAR OPERATIONS DEPARTMENT READS.
O O O O O O O
O _ _
i Page No. 57 12/02/H5 TABLE 3.2-1 COMMITMENTS FOR PLANT
=============e=================-
OPERATIONS AND SUPPORT
====================== j COMMITMENT DOCUMENT / FEATURE TITLE MODULE REMARES -
NUMBER COMMITMENT COMMITMENT !
SOURCE SECTION SUBJECT
== ========e= ================ ==================== ========e======e====== ================ ====== ==============
- 1. l.A PROCEDURES AND NUCLEAR OPERATIONS 02,05, l 2758 FSAR 13. 5.
07.9A, DOCUMENTATION DEPARTMENT HEADS ENSURE TRAT PROCEDURES 98,15 ;
t DESCRIBED IN SECTION 13.4.1 ARE FORMARDED TO THE PLANT REVIEN BOARD FOR ADDITIONAL REVIEN.
PROCEDURES FOR MAKING 02.05, 1735 FSAR 13. 5. 1. 1.8 PROCEDURES AND 07.9A, !
DOCUMENTATION TEMPORART CRANGES TO APPROVED PLANT 98.15 PROCEDURES INCLUDE A PROVISION TO EMSURE CRANGES ARE APPROVED f j
BT THE ON-DUTT OPERATIONS SUPERVISOR AND ONE OTHER i ENOWLEDGRABLE STAFF MEMBER.
- 1. 1.B PROCEDURES AND PROCEDURES INCLUDE A 02,05, 1736 FSAR 13. 5.
07,9A, DOCUMENTATION PROVISION TO ENSURE
- TEMPORARY 98,15 2 % 4 DURE CRANGES ARE ;
O MENTED AND
')EPORATED AS I krPROPRIATE INTO THE ;
NEXT REVISION OF THE i
" PROCEDURE.
- 13. 1. 1.C PROCEDURES AND PROCEDURES INCLUDE 02.05, a 1737 FSAR 5.
07,9A, 4 DOCUMENTATION MEASURES FOR FEEDBACE OF OPERATING 98,15 1
EXPERIENCE FROM MITRIN AND OUTSIDE PLANT I
- ORGANIZATION TO TRE OPERATORS AND OTHER [
l PERSONNEL PER MUREG-0737 ITEM I.C.S.
1
([
]
^
C
Page No. 58 12/02/85 TABLE 3.2 1 COMMITMENTS FOR PLANT
=e======e=============
OPERATIONS AND SUPPORT
=============- ====e=e NUMBER COMMITMENT COMMITMENT COMMITMENT DOCUMENT / FEATURE TITLE MODULE REMARES SOURCE SECTION SUBJECT
== = ======== -=============== ===,================ =============== ====== ================ ====== ==============
1738 FSAR 13. S. 1. 1.L rNOceDURES AND NUREG 0737, ITEM I.C.0 CL.'."IFICATION CF 02,05, DOCUMENTATION TM1 ACTION PLAN 07.9A, REQUIREMENTS 9B 15 1739 FSAR 13. 5. 1. 1.C PROCEDURES AND PROCEDURES FOR 05.07, DOCUMENTATION FEEDBACK OF OPERATING 9A,9B, EXPERIENCE IDENTIFY 15 THE ORGANIZATIONAL RESPONSIBILITIES FOR REVIEWING AND PRIORITIZING OPERATING EXPERIENCE INFORMATION.
1740 FSAR 13. 5. 1. 1.C PROCEDURES AND PROCEDURES FOR 05.07, DOCUMENTATION FEE 3BACE OF OPERATING 9A 98 INFORMATION IDENTIFY IS ORGANIZATIONAL RESPONSIBILITIES FOR ENSURING DISTRIBUTION OF PERTINENT INFORMATION TO THE APPROPRIATE PLANT PERSONNEL.
1741 FSAR 13. 5. 1. 1.C PROCEDURES AND PROCEDURES FOR 05,07, DOCUMENTATION FEEDB ACK OF OPERATING 9A,98 INFORMATION REQUIRE 15 PERIODIC EVALUATION OF s THE PROGRAM FOR EFFECTIVENESS.
1747 FMAR 13. 5. 1. 1.C PROCEDURES AND PROCEDURES FOR O2.05, DOCUMENTATION FEED 8 ACE OF OPERATING 07.9A, INFORMATION ENSURE 98,15 THAT INFORMATION IS REVIEWED BY INDIVIDUALS OF APPROPRIATE TECHNICAL ENOWLEDGE AND THAT APPROPRIATE CORRECTIVE
, ACTIONS ARE SPECIFIED.
O O O O O O O
..m _ ........ _ _ - .m__m.- . . . . ...m. .._m . _ .. ~ . . _ _ _ _ . . . _ . - . - _
.- a .
s; Page No. 59 12/02/85 TABLE 3.2-1 COMMITMENTS FOR PLANT
=================================- t OPERATIONS AND SUPPORT
==========
NUMBER COMMITMENT COMMITMENT COMMITMRNT DOCUMENT / FEATURE TITLE MODULE REMARKS SOURCE SECTION SUBJECT
====== == ========== ================ ==================== ====================== ================ ====== ==================== l 1743 FSAR 13. 5. 1. 1.0 CONDUCT OF LIMITED ACCESS AREA 0F 07 OPERATIONS THE CONTROL ROOM IS DEFINED BT FSAR FIOURE 13.5.1-1 l
- PROCEDURES FOR CONTROL 07 ;
1744 FSAR 13. 5. 1. 1.D OPERATIONS PROCEDURES AND ROOM ACCESS ESTABLISH
- DOCUMENTATION 000D-CONDUCT RULES FOR I PERSONNEL WITHIN THE CONTROL ROOM AREA TO i AVOID ANY DISRUPTION OF OPERATING ACTIVITY. ;
(NUREO-0737 ITEM !
?
I.C.4)
P 1745 FSAR 13. 5. 1. 1.D OPERATIONS PROCEDURES FOR CONTROL 07 PROCEDURES-AND ROOM ACCESS DIRECT DOCUMENTATION PERSONNEL OTHER TRAN ONSHIFT OPERATIONS CREW AND OPERATIONS CHAIN OF COMMAND TO REQUEST PERMISSION OF THE SHIFT SUPERVISOR TO ENTER THE LIMITED ACCESS AREA 1 .
f
! 1746 FSAR 13. 5. 1. 1.D OPERATIONS NUREG 0737.' ITEM I.C.4 CLARIFICATION OF 07 j PROCEDURES AND -TMI ACTION PLAN DOCUMENTATION REQUIREMENTS r 2764 FSAR 13. S. 1. 1.D PROCEDURES AND SHIFT SUPERVISOR HAS 07 i DOCUMENTATION- AUTHORITY TO REQUIRE THAT ANT INDIVIDUAL !
l_
WHO HAS BREN GRANTED ACCESS TO THE CONTROL l ROOM IMMEDIATELY LEAVE '
IF TRAT INDIVIDUAL i INTERFERES WITH THE 4
g DUTIES OF THE CONTROL
' ROOM OPERATORS.
1 4
i i
l l
Page No. 60 12/02/85 COMMITMENTS FOR PLANT TABLE 3.2-1 l
OPERATIONS AND SUPPORT
-==========e==
TITLE MODULE REMARES COMMITMENT COMMITMENT COMMITMENT DOCUMENT / FEATURE NUMBER SOURCE SECTION SUBJECT ==e=================
--:= = ===e====== ========== ===== ====== ============= ===-= =-============== == ===========-= ====
ADMINISTRATIVE 07 1747 FSAR 13. 5. 1. 1.D OPERATIONS AND E.3 PROCEDURES AND PROCEDURES GIVE THE DOCUMENTATION SHIFT SUPERVISOR AUTHORITY TO LIMIT CONTROL ROOM ACCESS TO THOSE INDIVIDUALS RESPONSIBLE FOR DIRECT OPERATION OR SUPPORT OF THE PLANT. PER NUREG 0737 ITEM 1.C.4.
ON SHIFT OPERATIONS 07 1748 FSAR 13. 5. 1. 1.E CONDUCT OF OPERATIONS SUPERVISOR DOES NOT ROUTINELT PERFORM ADMINISTRATIVE FUNCTIONS SUBORDINATE TO COMMAND FUNCTIONS AND THE RESPONSIBILITY FOR SAFE PLANT OPERATION.
- 1. 1.E OPERATIONS ADMINISTRATIVE 07 1749 FSAR 13. 5.
PROCEDURES AND PROCEDURES OUTLINE DOCUMENTATION DUTIES, RESPONSIBILITIES, AND AUTRORITT FOR CONTROL ROOM PERSONNEL IN CONFORMANCE WITH MUREG 0737 ITEMS I.A.I.2 I.C.3 AND I.C.4.
1750 FSAR I3. 5. 1. 1.E OPERATIONS NUREG 0737 ITEMS CLARIFICATION OF 07 PROCEDURES AND I.A.I.2 I.C.3 AND TMI ACTION PLAN DOCUMENTATION I.C.4 REQUIREMENTS FSAR 1. 1.E OPERATIONS PROCEDURES ESTABLISH 07 1751 13. 5.
PROCEDURES AND THE ONSHIFT OPERATIONS DOCUMENTATION SUPERVISOR AS THE SENIOR OPERATIONS REPRESENTATIVE ON EACH SHIFT, RESPONSIBLE FOR THE SAFE AND EFFICIENT OPERATION OF THE PLANT.
O O O O O O O
E O O .O O O- O O Page No. 61 12/02/85 COMMITMENTS FOR PLANT TABLE 3.2~1
===========z=============
OPERATIONS AND SUPPORT
===========-
TITLE MODULE REMARES NUMBER COMMITMENT COMMITMENT POMMTTMENT DOCUMENT / FEATURE SOURCE SECTION SUBJECT
e= == =====e=e== ==e============e ==e================= ====================== ================ ====== ================
r PROCEDURES DIRECT THE 07 1752 FSAR 13. 5. 1. 1.E OPERATIONS PROCEDURES AND ONSHIFT OPERATIONS DOCUMENTATION SUPERVISOR TO MAIFTAIN A BROAD PERSPECTIVE OF OPERATIONAL CONDITIONS AFFECTING PLANT SAFETY AND NOT BECOME TOTALLY INVOLVED IN ANY SINGLE OPERATION.
PROCEDURES ESTABLISH 07 1753 FSAR 13. 5. 1. 1.E OPERATIONS PROCEDURES AND THE ONSHIFT OPERATIONS DOCUMENTATION SUPERVISOR WITH THE AUTHORITY AND .
RESPONSIBILITY TO DECLARE EMBRGENCIES AND TO FUNCTION AS THE EMERGENCY DIRECTOR UNTIL RELIEVED BY A QUALIFIED MANAGER.
OPERATIONS PROCEDURES ASSIGN THE 07 1754 FSAR 13. 5. 1. 1.E PROCEDURES AND SHIFT SUPERVISOP DOCUMENTATION RESPONSIBILITY FOR THE SAFE AND EFFICIENT
- OPERATION OF HIS UNIT.
OPERATIONS PROCEDURES ENSURE THAT 07 1755 FSAR 13. 5. 1. 1.E i PROCEDURES AND WORE AND VACATION DOCUMENTATION SCREDULES ARE PREPARED BY AN OPERATIONS SUPERVISOR WR0 IS NOT ON SHIFT, AND CLEARANCES ARE ISSUEP BY THE SHIFT SUPERVISOR FOR HIS ASSIGNED UNIT.
- 13. 5. 1. 1.F PROCEDURES AND PROCEDURES ENSURE TRAT 07.9A.
1756 FSAR 95 t
DOCUMENTATION STANDING ORDERS ARE NOT MAINTAINED OVER 1 YEAR BEFORE DELETION i OR CONVERSION INTO A PLANT OPERATING PROCEDURE.
(
_____ __- -_ _ __- - - = _ = _ _ _ _ _ _ - - - _ _ - _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ - _ _ .
Pere No. 62 12/02/85 TABLE 3.2-1 COMMITMENTS FOR PLANT
======================
OPERATIONS AND SUPPORT
= -=-=====
COMMITMENT COMMITMENT DOCUMENT / FEATURE TITLE MODULE REMARKS NUMBER COMMITMENT SOURCE SECTION SUBJECT
== ========== ================ ==================== ====================== ================ ====== ==============
- 13. S. 1. 1.F PROCEDURES AND STANDING ORDERS 07,9A, 1757 FSAR DOCUMENTATION PROVIDE FOR THE ISSUE 9B OF TEMPORARY INSTRUCTIONS TO PLANT OPERATING PERSONNEL TO ADDRESS SUBJECTS NOT COVERED BY EXISTING PROCEDURES.
FSAR 13. 5 1. 1.F PROCEDURES AND PROCEDURES CONTAIN 07.9A, 1758 DOCUMENTATION PROVISIONS FOR 9B MAINTAINING AND IMPLEMENTING APPROVED STANDING ORDERS.
- 13. S. 1. 1.F PROCEDURES AND PROCEDURES DIRECT THAT 07.9A, 1759 FSAR DOCUMENTATION STANDING ORDERS BE 9B PERIODICALLY REVIEWED FOR CONTINUED APPLICABILITT.
1760 FSAR 13. 5. 1. l.G PROCEDURES AND ADMINISTRATIVE 05.07 DOCUMENTATION PROCEDURES RESTRICT 9A,9B TRE USE OF OVERTIME THAT MAT BE SCHEDULED TO MEET SHIFT STAFFING REQUIREMENTS IN ACCORDANCE WITH NUREG-0737 ITEM I.A.I.3 AS REVISED IN NRC GENERIC LETTER 82-12.
1761 FSAR 13. 5. 1. l.G OPERATIONS NUREG 0737 ITEM CLARIFICATION OF 07 THIS ' TEM REVISED BT PROCEDURES AND I.A.I.3 TMI ACTION PLAN GL 82-12.
DOCUMENTATION REQUIRRMENTS 1762 FSAR 13. 5. 1. 1.0 OPERATIONS PROCEDURES ESTABLISH 07 PROCEDURES AND THE NORMAL AND MINIMUM DOCUMENTATION SHIFT POSITIONS THAT MUST BE MANNED FOR OPERATION OF THE PLANT DURING BOTH ONE-UNIT AND TWO-UNIT OPERATION.
O O O O O O O
O Page No. 63 12/02/85 TABLE 3.2-1 COMMITMENTS FoH PLANT
===============================-
OPERATIONS AND SUPPORT
= ===================-
NUMBER COMMITMENT COMMITMENT COMMITMENT DOCUMENT / FEATURE TITLE MODULE REMARES SOURCE SECTION SUBJECT e ==== == ========== ================ == =======e==== ==== e===================== ==e============= ====== ====================
1763 FSAR 13. 5. 1. 1.G PROCEDURES AND PROCEDURES REQUIRE 05.07 DOCUMENTATION THAT USE OF OVERTIME 9A.98 EXCEEDING GUIDELINES STATED IN THIS SECTION BE AUTHORIZED BY TRE MANAGER OF UNIT OPERATIONS OR THE SUPERINTENDENT OF OPERATIONS.
1764 FSAR 13. 5. 1. l.G PROCEDURES AND PROCEDURES REQUIRE 05,07, DOCUMENTATION DOCUMENTATION OF THE 9A,98 BASIS FOR ANY OVERTIME EXCEPTIONS, AND MONTRLY REVIEW OF INDIVIDUAL EXCESS OVERTIME BY THE GMVNO.
2766 FSAR 13. 5. 1. l.G PROCEDURES AND PROCEDURES SHALL LIMIT 05.07 DOCUMENTATION WOREING HOURS OF PLANT 9A,9B STAFF WBO PERFORM SAFETY-RELATED FUNCTIONS E.G. LICENSED OPERATORS, CHEM / RAD TECHNICIANS, AUXILIARY OPERATORS, AND KEY MAINTENANCE PERSONNEL.
2767 FSAR 13. 5. 1. l.G PROCEDURES AND PROCEDURES SHALL 05,07, 4
DOCUMENTATION PROVIDE FOR 9A,9B MAINTAINING ADEQUATE SHIFT COVERAGE WITHOUT ROUTINE HEAVY USE OF OVERTIME, WITH A 40 i
ROUR WERE AS THE
' OBJECTIVE.
1
- 13. 1. 1.G PROCEDURES AND PROCEDURES REQUIRE 05,07 SEE SECTION I g 2768 FSAR 5.
94,95 13.5.1.1.G OF THE DOCUMENTATION TRAT DURING PERIODS OF EXTENDED OUTAGE, FSAR FOR DETAILS.
TEMPORARY USE OF
! ( EXCESSIVE OVERTIME i SRALL FOLLOW THE STATED GUIDELINES, i l
! C' 4 _ _. - - - - - - - _ _ _ _ _ _ - _ - _ _ _ - _ _ _ _ _ _ _ _ . .__ _ _ _ _ _ _ _ _ _ . .. _ _ . _ _ _ _ _ _ . -_
Page No. 64 12/02/85 TABLE 3.2-1 COMMITMENTS FOR PLANT
=========================
OPERATIONS AND SUPPORT
==========
DOCUMENT / FEATURE TITLE MODULE REMARES NUMBER COMMITMENT COMMITMENT COMMITMENT SOURCE SECTION SUBJECT e=======,======= ====== ====================
== ====e===== ================ ==================== ================
OPERATIONS PROCEDURES ESTABLISH 07 1765 FSAR 13. 5. 1. 1.H PROCEDURES AND TO THE OFFGOING ORGANIZATION CONTROL ROOM OPERATOR THE RESPONSIBILITY TO ENSURE HIS RELIEF IS ALERT, COHERENT, AND FULLY CAPABLE OF PERFORMING HIS ASSIGNED DUTIES.
(NUREG-0737 ITEM I.C.2)
- 13. 1. 1.H OPERATIONS NUREG 0737, ITEM I.C.2 CLARIFICATION OF 07 1766 FSAR 5.
TMI ACTION PLAN PROCEDURES AND DOCUMENTATION REQUIREMENTS
- 1. 1.H PROCEDURES AND PROCEDURES ENSURE EACH 07,9A, 1767 FSAR 13. 5.
9B DOCUMENTATION ONCOMING INDIVIDUAL REVIEWS LOGS, ROUND SHEETS, AND CHECELISTS THAT ARE APPLICABLE TO HIS POSITION AND THAT BE DISCUSSES IMPORTANT ITEMS WITH OFFGOING INDIVIDUAL.
- 1. 1.H PROCEDURES AND SHIFT RELIEF AND 07,9A, 1768 FSAR I3. 5.
98 DOCUMENTATION TURNOVER PROCEDURES ENSURE A COMPREHENSIVE EXCHANGE OF INFORMATION SO THAT THE ONCOMING SHIFT IS ANARE OF CRITICAL PLANT STATUS PRIOR TO ASSUMING DUTY PER NUREG-0737, ITEM I.C.2.
- 1. 1.H PROCEDURES AND PROCEDURES ENSURE THAT 07,9A.
1769 FSAR 13. 5.
9B DOCUMENTATION AN INDIVIDUAL IS QUALIFIED FOR THE POSITION THAT HE WILL ASSUME.
O O O O O O O
a o
o o O o o. O Page No. 65 12/02/85 TABLE 3.2-1 COMMITMENTS FOR PLANT
-===========================
OPERATIONS AND SUPPORT
- s====ee==============
COMMITMENT DOCUMENT / FEATURE TITLE MODULE REMARKS NUMBER COMMITMENT COMMITMENT SOURCE SECTION SUBJECT
=- ========== ================ ==================== ========e============= ================ ==== = ==============
- 1. 1.H OPERATIONS PROCEDURES ESTABLISH 07 1770 FSAR 13. 5.
PROCEDURES AND TO THE OFFGOING DOCUMENTATION CONTROL ROOM OPERATOR THE RESPONSIBILITT TO ENSURE RIS RELIEF IS FULLY AWARS OF EXISTING PLANT CONDITIONS.
- 1. 1.1 OPERATIONS PROCEDURES FOR CONTROL 07 1771 FSAR 13. 5.
PROCEDUREN AND OF EQUIPMENT PROVIDE DOCUMENTATION INSTRUCTIONS FOR RELEASING PLANT EQUIPMENT OR SYSTEMS FOR MAINTENANCE.
TESTING. OR INSPECTION IN ACCORDANCE WITH NUREG-0737 ITEMS I.C.6 AND II.E.1.10.
1772 FSAR 13. 5. 1. 1.1 OPERATIONS MUREG 0737 ITEMS CLARIFICATION OF 07 PROCEDURES AND I.C.6 AND II.K.l.10 TMI ACTION PLAN DOCUMENTATION REQUIREMENTS
- 13. 5. 1. 1.1 OPERATIONS PROCEDURES FOR 07 1773 FSAR PROCEDURES AND REMOVING EQUIPMENT DOCUMENTATION FROM SERVICE AND RETURNING TO SERVICE WILL ENSURE OPERABILITT STATUS OF THAT EQUIPMENT IS KNOWN. IN CONFORMANCE WITH ITEM II.K.l.10 OF MURBO-0737.
- 1. l.I OPERATIONS PROCEDURES FOR 07 1774 FSAR 13. 5.
PROCEDURES AND RETURNING EQUIPMENT TO DOCUMENTATION SERVICE REQUIRE A LINEUP VERIFICATION AND MAT REQUIRE ADDITIONAL LINEUP VERIFICATIONS AT PERIODIC INTERVALS, PER NUREG-0737 ITEM II.K.I.10 AND ANSI
- b. N18.7-1976 SECTION 5.2.6.
Page No. 66 12/02/85 TABLI: 3.2-1 COMMITMENTS FOR PLANT
===.== = =============
OPERATIONS AND SUPPORT
========== ======
DOCUMENT / FEATURE TITLE MODULE REMARES NUMBER COMMITMENT COMMITMENT COMMITMENT SOURCE SECTION SUBJECT ====== =========== ========
=,======== ==== ========_== =======--====-====== =====-==============e =- =======e.-
=e
OPERATIONS PROCEDURES INCLUDE 07 1775 FSAR 13. 5. 1. 1.1 PROCEDURES AND STEPS TO RNSURE THAT DOCUMENTATION EQUIPMENT TAKEN OUT OF SERVICE AND PLACED IN A CONTROLLED STATUS IS CLEARLY IDENTIFIED BY THE USE OF TAGGING.
- 1. l.I OPERATIONS PROCEDURES DIRECT A 07 1776 FSAR 13. 5.
PROCEDURES AND SECOND QUALIFIED DOCUMENTATION PERSON TO VERIFT ISOLATION OR RESTORATION OF SAFETT-RELATED COMPONENTS UNLESS FUNCTIONAL TESTING CAN BE PERFORMED OR THERE IS SIGNIFICANT RADIATION EXPOSURE.
- 1. 1.! OPERATIONS EQUIPMENT CONTROL 07 1777 FSAR 13. 5.
AND E.2 PROCEDURES AND PROCEDURES ASSIGN THE DOCUMENTATION SHIFT SUPERVISOR AS THE RESPONSIBLE AUTHORITT FOR ISSUING AND RELEASING CLEARANCES FOR EQUIPMENT TO DE TAKEN OUT OF SERVICE WITRIN HIS ASSIGNED UNIT.
1778 FSAR 13. 5. 1. l.J MAINTENANCE MAINTENANCE OF 07 PROCEDURES AND EQUIPMENT IMPORTANT TO DOCUMENTATION SAFETT IS PERFORMED IN ACCORDAMCE WITH WRITTEN PROCEDURES AS DESCRIBED IN PARAGRAPH 13.5.2.2.
O O O O O O O
_ ~ . - . . .. . ._. .........._.-n-- - . . - _ ... ~ , . _ - _ , . .. .. .
b Page No. 67 ,
12/02/85 TABLE 3.2-1 COMMITMENTS FOR PLANT
e===e=======================
OPERATIONS AND SUPPORT
e=============
COMMITMENT DOCUMENT / FEATURE TITLE MODULE REMARES NUMBFR COMMITMENT COMMITMENT SOURCE SECTION SUBJECT ee================-= ,===================== ================ ====== =================e==
== ========== ==========
- 13. 1. TECHNICAL SUPPORT PLANT HODIFICATIONS 07 1779 FSAR 5. l.J PROCEDURES AND IMPORTANT TO SAFETT DOCUMENTATION ARE PERFORMED IN ACCORDANCE WITH NRITTEN PROCEDURES AS DESCRIBED IN PARAGRAPR 13.5.2.2. ADMIN.
CONTROLS ENSURE COMILIANCE WITH CODES AND REGULATIONS.
PROGRAM PROGRAM IS GOVERNED AND IMPLEMENTED THROUGR USE OF FIRE ,
PROTECTION PROCEDURES.
- 13. 1. 1.E FIRE PROTECTION FIRE PROTECTION 07 i 1781 FSAR 5.
PROGRAM PROCEDURES PROVIDE GUIDELINES FOR ADMINISTRATIVE CONTROLS. STSTEM ,
OPERATION, FIRE FIGRTING. FIRE BRIGADE. AND' AGREEMENTS WITH LOCAL OFFSITE FIRE DEPARTMENTS AS DESCRIBED IN 9.5.1.
FSAR 13. 1. 1.L OPERATIONS PROCEDURES REQUIRE 07 1782 5.
PROCEDURES AND CRANE OPERATORS WHO DOCUMENTATION OPERATE CRANES OVER l FUEL POOLS WILL BE QUALIFIED AND CONDUCT TREMSELVES IN ACCORDANCE WITH ANSI B30.2-1976 CHAPTERS 2 AND 3. OVERREAD AND GANTRT CRANES.
i C
Page No. 68 12/02/05 TABLE 3.2-1 COMMITMENTS FOR PLANT
==-=== ========================e-OPERATIONS AND SUPPORT
=======.:=e=====:
COMMITMENT DOCUMENT / FEATURE TITLE MODULE REMARES NUMBER COMMITMENT COMMITMENT SOURCE SECTION SUBJECT
== -========= =======~======== ===============-==== ====================== ================ ====== ==============
- 1. l.M & OPERATIONS TEMPORARY PROCEDURES 05,07, 1783 FSAR 13. 5. 9A,9B 5.2.1.G PROCEDURES AND ARE ISSUED AS REQUIRED DOCUMENTATION TO PROVIDE DETAILED INSTRUCTIONS FOR SPECIFIC JOBS THAT ARE OF A SPECIFIC DURATION.
j
- 13. 1. 1.N TECHNICAL SUPPORT PROCEDURES ARE 05,07 i 1784 FSAR 5.
' PROCEDURES AND DEVELOPED FOR DOCUMENTATION COLLECTION OF EMERGENCY CORE COOLING SYSTEM OUTAGE DATA IN ACCORDANCE WITH NUREO-0737 ITEM II.E.3.17. THIS DATA WILL BE REPORTED TO NRC PER TECHNICAL SPECIFICATIONS.
{
1785 FSAR 13. 5. 1. 1.N TECHNICAL SUPPORT NURBO 0737 ITEM CLARIFICATION OF 07 PROCEDURES AND II.E.3.17 TMI ACTION PLAN DOCUMENTATION REQUIREMENTS 1728 FSAR 13. S. 1. 1.0 ITP ADMIN PROCEDURES ITP, ADMIN PROCEDURES 03A,07 SEE ALSO FSAR THAT ESTABLISH SECTION 14.2.2.
CONTROLS FOR ITP PRIOR TO FUEL LOAD DESCRIBED
! IN SUM. ADMIN CONTROLS FOR ITP AFTER FUEL l LOAD IN PAPM OR SUM.
2769 FSAR 13. 5. 1. 1.0 PROCEDURES AND PROCEDURES REQUIRE 03A,07 DOCUMENTATION THAT MODIFICATIONS AND l REPAIRS IDENTIFIED
$ DURINO THE IMITIAL
( TEST PROGRAM ARE l DOCUMENTED AND TRACKED TO COMPLETION ON THE
- MASTER TRACRING SYSTEM.
I _ _- _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ .
O O O O O O Page No. 69 12/02/85 TABLE 3.2-1 COMMITMENTS FOR PLANT
e-==e=========e====-=========
ps OPERATIONS AND SUPPORT
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NUMBER COMMITMENT COMMITMENT COMMITMENT DOCUMENT / FEATURE TITLE MODULE REMARKS SOURCE SECTION SUBJECT
== =========- e=============== ==e===============s= ===== ================ -======ee======= ====== ==============
2770 FSAR 13. 5. 1. 160 PROCEDURES AND PERMANENT PLANT 03A,07 DOCUMENTATION EQUIPMENT MODIFICATIONS TO SAFETT-RELATED EQUIPMENT DURING INITIAL TEST PROGRA ARE REVIEWED BT TRE ORIGINAL OR OTHER DESIGNATED ORGANIZATION.
2771 FSAR 13. 5. 1. 1.0 PROCEDURES AND DURING THE INITIAL 03A,07 DOCUMENTATION TEST PROGRAM MAINTENANCE WORK ORDERS ESTABLISH CONTROLS TO ASSURE APPROPRIATE RETESTING f IS PERFORMED FOLLOWING MODIFICATIONS AND REPAIRS.
2772 FSAR 13. 5. 1. 1.0 FROCEDURES AND INCLUDED IN CONTROLS 03A.07 DOCUMENTATION FOR INITIAL TEST ,
PROGRAM ARE PROVISIONS FOR ADRERENCE TO PROCEDURES. i 1791 FSAR 13. S. 2. 1 OPERATIONS PROCEDURES FOR 07 PROCEDURES AND EQUIPMENT OPERATION -
DOCUMENTATION- COMPLETED APPROX. 6 MONTRS PRIOR TO FUEL LOADING TO PROVIDE VERIFICATION OF CORRECT PERFORMANCE 06 OPERATINC ACTIVITIES AND REDUCE ERROR (NUREG 0737 ITEM I.C.6).
L'
( 'l
Page No. 70 12/02/85 TABLE 3.2-1 COMMITMENTS FOR Pl. A NT
======================
OPERATIONS AND SUPPORT
--.=======
NUMBER COMMITMENT COMMITMENT COMMITMENT DOCUMENT /FFATURE TITLE MODULE REMARES SOURCE SECTION SUBJECT
== ========== ================ =========e========== ====================== ================ ====== ==============
1792 FSAR 13. S. 2. 1 OPERATIONS NUREG 0737 ITEM I.C.6 CI.ARIFICATION OF 07 PROCEDURES AND TMI ACTION PLAN DOCUMENTATION REQUIREMENTS 1793 FSAR 13. 5. 2. 1 OPERATIONS PROCEDURE FORMAT - SEE 07 PROCEDURES AND FSAR 1.9.33.2 WHICH DOCUMENTATION ENDORSES ANSI N18.7-1976 SECTION 5.3.2.
1794 FSAR 13. 5. 2. 1.D OPERATIONS ANNUNCIATOR RESPONSE 07 PROCEDURES AND PROCEDURES WILL BE DOCUMENTATION INDEXED BT LIGHT BOARD NUMBER AND ALARM WINDOW COORDINATES.
1795 FSAR 13. 5. 2. 1.D OPERATIONS ANY ANNUNCIATOR 07 PROCEDURES AND RESPONSE PROCEDURE DOCUMENTATION PROVIDING RESPONSE TO AN EMBRGENCY CONDITION WILL REFERENCE THE APPROPRIATE EMERGENCY OPERATING PROCEDURE.
1796 FSAR 13. 5. 2. 1.F OPERATIONS EOP'S ARE DEVELOPED 07 PROCEDURES AND USING THE WESTINGHOUSE DOCUMENTATION OWNER'S GROUP GUIDELINES, PLANT SPECIFIC BACEGROUND/ SUPPORT INFORMATION, ROP WRITER'S GUIDE. AND THE INPO IMPLEMENTATION GUIDELINE.
1797 FSAR 13. S. 2. 1.F OPERATIONS EACH COMPLETED BOP 15 07 PROCEDURES AND VERIFIED BY REVIEW FOR DOCUMENTATION WRITTEN CORRECTNESS AND TECHNICAL ACCURACY.
O O O O O O O
+
O O O O O- O O PaBe No. 71 12/02/85 TABLE 3.2-1 COMMITMENTS FOR PLANT
e=============================
OPERATIONS AND SUPPORT
==========
NUMBER COMMITMENT COMMITMENT COMMITMENT DOCUMENT / FEATURE TITLE MODULE REMARES SOURCE SECTION SUBJECT
== ========== ================ ==================== ====================== ==-============= ====== ==============
1798 FSAR 13. 5. 2. 1.F OPERATIONS AFTER VERIFICATION 07 PROCEDURES AND E0P'S ARE VALIDATED BT DOCUMENTATION AT LEAST ONE OF THE FOLLOWING: A) PLANT SPECIFIC SIMULATOR i
DEMONSTRATION B)
ACTUAL PLANT DEMONSTRATION C)
DETAILED REVIEN.
1799 FSAR 13. 5. 2. 1.F OPERATIONS EACR GENERIC TECENICAL 07 PROCEDURES AND GUIDELINE IS REVIEWED DOCUMENTATION TO DETERMINE THE INFORMATION NEEDED TO GENERATE PLANT-SPECIFIC PROCEDURES.
1800 FSAR 13. 5. 2. 1.F OPERATIONS USE OF WOG TECR. 07 PROCEDURES AND GUIDELINES AND i DOCUMENTATION SUPPLEMENTAL INFO IN
)' ACCORDANCE WITH EOP ACTION PLAN MEETS TRE j INTENT OF NUREG-0899, ITEMS I.C.I'AND I.C.8,
' AS CLARIFIED BT NUREG-0737 SUPPLEMENT 1.
- 1801 FSAR 13. 5. 2. 1.F OPERATIONS MUREG 0737 ITEMS CLARIFICATION OF 07 PROCEDURES AND 1.C.1 AND 1.C.8 TMI ACTION PLAN DOCUMENTATION REQUIREMENTS 1802 FSAR 13. 5. 2. 2 TECRMICAL SUPPORT PLANT MAINTENANCE AND 07
- PROCEDURES AND MODIFICATIONS ARE
! DOCUMENTATION GOVERNED BT I ADMINISTRATIVE
- PROCEDURES.
I i
t
!C i
lC=
1
_ . - , _ _ _ _ _ . , _ _ _ _ _ _ _ ....,._m_ _ . . . _ _ . - - . _ _ __ ,_____,,
Page No. 72 12/02/85 COMMITMENTS FOR PLANT TABLE 3.2-1
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TITLE MODULE REM 4RES COMMITMENT COMMITMENT DOCUMENT / FEATURE NUMBER COMMITMENT SOURCE SECTION SUBJECT =======-=====e======
==========
=== == ========== ================ ==================== ==================n
SPECIAL PROCEDURES 07 1803 FSAR 13. S. 2. 2 MAINTENANCE PROCEDURES AND PROVIDE INSTRUCTIONS DOCUMENTATION FOR MAINTENANCE, REPAIR, CALIBRATION AND FUNCTIONAL TESTING OF HEALTR PHYSICS, FIRE PROTECTION, AND SECURITY EQUIPMENT.
REFUELING PROCEDURES 07 1804 FSAR 13. 5. 2. 3 TECHNICAL SUPPORT PROCEDURES AND PROVIDE FOR DOCUMENTATION PREPARATION AND PERFORMANCE OF REFUELING. INCLUDING PROCEDURES TO DISASSEMBLE COMPONENTS, REFUELING EQUIPMENT PREUSE CHECEOUTS, AND METHODS AND LIMITS FOR OPERATIONS.
COGNIZANT DESIGN 03A,07 1816 FSAR 14. 2. 2. 1 OPERATIONS PROCEDURES AND ORGANIZATION WILL DOCUMENTATION REVIEW THE OBJECTIVES AND ACCEPTANCE CRITERIA 0F THE ITP PROCEDURE PRIOR TO PROCEDURE IMPLEMENTATION.
OPERATIONS COMMENTS RESULTING 03A,07 1817 FSAR 14. 2. 2. 1 PROCEDURES AND FROM THE DESIGN DOCUMENTATION ORGANIZATION REVIEW WILL BE PROVIDED FOR ANT TECHNICAL COMMENTS NOT INCORPORATED.
OPERATIONS FORMAT AND CONTENT OF 03A,07 1318 FSAR 14. 2, 2. 1 PROCEDURES AND THE TEST PROCEDURES DOC UM E NT A T ION RRFLECT THE GUIDANCE PROVIDED IN REG. GUIDE l.68.
O O O O O O O
._.___...~._m._..m __-..mm.m--.. m.._.. . - - - ..m_ _ _. - ._.m _ ..~ . _ ._-.m. .._.._.._m.m.__m. _ _ _ _ . _ . - . .
Y
~ O-Page No. 73 12/02/85 TABLE 3.2-1 COMMITMENTS FOR PLANT
===========es=========
OPERATIONS AND SUPPORT
-=================---- ,
DOCUMENT / FEATURE TITLE MODULE REMARES MUMRER COMMITMENT COMMITMENT COMMITMENT ;
SOURCE SECTION SUBJECT ====== ====================
e================ =====e=====
==== == ========== ============== r= =================e
HG 1.68, H/2 INITIAL TEST 03A,07 CONFORMANCE IS 1819 FSAR 14. 2. 2. I OPERAtt0NS DISCUSSED IN SECTION i PROCEDURES AND PROGRAMS FOR DOCUMENTATION WATER-COOLED 1.9.68.2 0F TRE NUCLEAR POWER FSAR. ;
PLANTS 03A,05 EACH CTCLE INCLUDEF 1820 FSAR 14. 2. 2. 2 PROCEDURE REVIEW AND IN GENERAL PREOP AND APPROVAL STARTUP TEST 07 REVIEWS BT GPC TEST
' PROCEDURES GO TRPOUCR SUPERVISOR, BPC A MINIMUM OF 2 REVIEW REPRESENTATIVE, ,
CTCLES PRIOR TO AND/OR WESTINGROUSE "
SUBMITTAL TO THE TRB REPRESENTATIVE AS FOR PREOP TESTS AND APPROPRIATE.
' PRB FOR STARTUP TESTS. ,
03A,05 TEST PROCEDURES TRAT 1822 FSAR 14. 2. 2. 2 PROCEDURE REVIEW AND THE TRB AND PRB i APPROVAL RECOMMEND APPROVAL TO 07 ARE NOT SATISFACTORY THE GENERAL MANAGER - ARE RESOLVED UNDER V0GTLE NUCLEAR DIRECTION OF THE OPERATIONS OR HIS BOARD PRIOR TO DESIGNER IF PROCEDURES RECOMMENDATION FOR ARE FOUND ACCEPTABLE. APPROVAL.
03A,05 1823 FSAR 14. 2. 2. 2 PROCEDURE REVIEW AND SUBSEQUENT REVISIONS APPROVAL TO PREOPERATIONAL AND 07 STARTUP TEST PROCEDURES ARE RANDLED IN A MANNER SIMILAR TO i NEW PROCEDURES.
PROCEDURE REVIEW AND TRE GENERAL MANAGER - 03A,05 THE GENERAL MANAGER 1824 FSAR 14. 2. 2. 2 '
APPROVAL VOGTLE NUCLEAR 07 OR RIS DESIGNER OPERATIONS, OR HIS APPROVES PREOP AND j DESIGNER, THE INITIAL STALTUP TEST ;
TEST PROGRAM MANAGER, PROCEDURES.
IS RESPONSIBLE FOR THE j j REVIEW AND APPROVAL OF
' PREOPERATIONAL AND
' STARTUP TEST
' 3 PROCEDURES.
4 4
4
' +
C .
1 i
PREe No. 74 12/02/85 COMMITMENTS FOR PLANT TABLE 3.2-1
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===== ====
TITLE MODULE REMARES NUMBER COMMITMENT COMMITMENT COMMITMENT DOCUMENT / FEATURE SOURCE SECTION SUBJECT
== ========== :n===========e== ===================- =============:-===== = ================ ====== ==============
05,07 1825 FSAR 14. 2. 2. 2 PROCEDURE REVIEW AND STARTUP TEST APPROVAL PROCEDURES (LISTED IN CHAP. 14) WILL BE SUBMITTED TO THE PRB FOR REVIEW.
3 CONDUCT OF STARTUP TEST PHASE 07 1830 FSAR 14. 2. 2.
OPERATIONS WILL BE GOVERNED BY THE STARTUP MANUAL AND PLANT PROCEDURES CONDUCT OF TEST ALL PHASES OF TESTING 03A,07 2773 FSAR 14. 2. 2. 3 PROGRAM WITH THE EXCEPTION OF CERTAIN CONSTRUCTION-PERFORMED TESTS ARE UNDER THE CONTh0L OF THE STSTEM TEST SUPERVISOR.
- 2. 4 REVIEW, EVALUATION UPON COMPLETION OF A 03A,07 1831 FSAR I4. 2.
AND APPROVAL OF TEST PREOPERATIONAL OR RESULTS STARTUP TEST. THE TEST SUPERVISOR PREPARES A TEST RESULTS PACKAGE AND SUBMITS IT FOR REVIEW.
- 14. 4 REVIEW, EVALUATION THE GENERAL MANAGEP - 03A,05 THE GENERAL MANAGER 1832 FSAR 2. 2.
07 OR DESIGNEE APPROVES AND APPROVAL OF TEST V0GTLE NUCLEAR RESULTS OPERATIONS OR HIS THE TEST RESULTS DESIGNER, THE INITIAL PACKAGE AS COMPLETE.
TEST PROGRAM MANAGER, IS RESPONSIBLE FOR THE REVIEW AND APPROVAL OF PREOP AND STARTUP TEST RESULTS.
- 14. 2. 4 REVIEW, EVALUATION IN GENERAL, PREOP AND 03A,05 THIS INCLUDES A 1834 FSAR 2.
07 REVIEW BY THE GPC AND APPROVAL OF TEST STARTUP TEST RESULTS ARE REVIEWED AND TEST SUPERVISOR. BPC fl RESULTS APPROVED BT THE SAME REPRESENTATIVE, ORGANIZATIONS AND AND/OR WESTINGHOUSE LEVELS OF AUTHORITY REPRESENTATIVE AS THAT REVIEWED AND APPROPRIATE.
APPROVED THE PREOP AND STARTUP TEST PROCEDURES. AS A B ED H T B.
L_______ . _ . _ __ _ . _ _ _ _ _ . _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _
d k:
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'D~~ 1 O Page No. 75 12/02/85 TABLE 3.2 1 COMMITMENTS FOR PLANT
-2=2,====== :=====2.=========== :===
OPERATIONS AND SUPPORT
==========
NUMBER COMMITMENT COMMITMENT COMMITMENT DOCUMENT /FEATL E TITLE MODULE REMARES SOURCE SECTION SUBJECT
== ========== ================ ==================== ====================== ===============e ====== ==============
1835 FSAR 14. 2. 2. 4 REVIEW, EVALUATION TRE TRB REVIEWS 03A,05 TEST RESULTS AND APPROVAL OF TEST PREOPERATIONAL TEST 07 PACEAGES THAT ARE RESULTS RESULTS PACEACES AND NOT SATISFACTORT ARE TRE PRB REVIEWS RESOLVED UNDER TRE STARTUP TEST RESULTS DIRECTION OF TRE PACEAGES. TRE BOARDS BOARD PRIOR TO RECOMMEND APPROVAL TO RECOMMENDATON OF THE GEMBRAL MANAGER OR PACEAGES FOR RIS DESIGNEE FOR APPROVAL.
PACEAGES FOUND ACCEPTABLE.
1839 FSAR 14. 2. 2. 4 REVIEW, EVALUATION COMPLETED TESTS WILL 03A,05 AND APPROVAL OF TEST BECOME PART OF TRE 07 RESULTS PERMANENT PLANT RECORD.
1847 FSAR 14. 2. 4 CONDUCT OF VARIOUS LISTED 03A,05 OPERATIONS DOCUMENTS WILL BE 07 REVIEWED ON A CONTINUING BASIS AND PERTINENT INFORMATION ROUTED TO PLANT MANAGER FOR REVIEW AND INCLUSION IN ITP IF DEEMED NECESSART.
1848 FSAR Id
- 5 TRIAL USE OF EMBRGENCT PROCEDURES 07 I OPERATING AND ARE VERIFIED TO TRE EMERGENCT PROCEDURES EXTENT PRACTICAL DURING THE PLANT STARTUP AS PLANT CONDITIONS. TESTING AND TRAINING WARRANT.
TRIAL USE OF SURVEILLANCE TESTS ARE 07,9A, 1849 FSAR 14. 2. 5 OPERATING AND PERFORMED AS THE TEST 95 EMERGENCT PROCEDURES PROGRAM PERMITS TO DEMONSTRATE TRE
' ADEQUACT OF TRE
) PROCEDURES.
- c l'
(?
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OPERATIONS AND SUPPORT
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TITLE MODULE REMARKS COMMITMENT COMMITMENT DOCUMENT / FEATURE NUMBER COMMITMENT SOURCE SECTION SUBJECT
== ========== ======-========= ==================== ====================== =========
TRIAL USE OF OPERATING PROCEDURES O2.03A 1852 FSAR 14. 2. 5 07.9A OPERATING AND ARE USED DURING THE
,9B EMERGENCY PROCEDURES ITP TO SUPPORT TESTING. MAINTAIN CONDITIONS, AND FACILITATE TRAINING.
ALARM IN CONTAINMENT 07 1854 FSAR 14. 2. 6. I OPERATIONS PROCEDURES AND AND TRE MAIN CONTROL DOCUMENTATION ROOM IS COUPL5D TO THE SOURCE RANGE CHANNELS AND HAS A SETPOINT EQUAL TO OR LESS THAN 5 TIMES THE CURRENT COUNT RATE.
PLANT STATUS CONTAINMENT STRUCTURE 07 1855 FSAR 14. 2. 6. 1 CONTROLS WILL BE COMPLETE AND CONTAINMENT INTEGRITY ESTABLISHED AND MAINTAINED DURING FUEL LOADING.
OPERATIONS CORE MODERATOR 07,9B 1856 FSAR 14. 2. 6. 1 PROCEDURES AND CHEMISTRY CONDITIONS DOCUMENTATION ARE PRESCRIBED IN THE CORE LOADING PROCEDURE AND ARE VERIFIED PERIODICALLY PRIOR TO AND DURING CORE LOADING.
OPERATIONS MULTIPLE CHECKS ARE 07 1857 FSAR 14. 2. 6. I PROCEDURES AND MADE OF COMPONENT DOCUMENTATION SERIAL NUMBERS AND TYPES AT SUCCESSIVE TRANSFER POINTS AND FUBL ASSEMBLY STATUS BOARDS ARE MAINTAMED 3
i THROUGHOUT THE CORE LOADING.
. O O O O O O O
) % g r
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OPERATIONS AND SUPPORT
===e=2:==e
TITLE MODULE REMARES NUMBER COMMITMENT COMMITMENT COMMITMENT DOCUMENT / FEATURE SOURCE SECTION SUBJECT ,
== == ======= ==e=======e===== ==================== ====================== ================ ====== ======s===s===
- 14. I OPERATIONS PERMANENT SOURCE RANGE 07 18'58 FSAR 2. 6.
PROCEDURES AND CHANNELS ARE MONITORED DOCUMENTATION IN THE MAIN CONTROL ROOM BT LICENSED PLANT ,
t OPERATORS.
OPERATIONS WATER LEVEL WILL BE 07 1859 FSAR 14. 2. 6. 1 PROCEDURES AND ABOVE TRE BOTTOM OF THE NOZZLES AND DOCUMENTATION RECIRCULATION WILL BE MAINTAINED TO ENSURE UNIFORM BORON CONCENTRATION.
OPERATIONS RESPONSE CHECE OF 07 1860 FSAR 14. 2. 6. 1 PROCEDURES AND NUCLEAR INSTRUMENTS TO DOCUMENTATION A NEUTRON SOURCE SHALL BE PERFORM 5D WITRIN 8 ROURS PRIOR TO LOADING OF THE CORE OR RESUMPTION OF LOADINO IF DELAT IS FOR MORE THAN 8 HOURS.
- 14. 2. OPERATIONS STANDARD PROCEDURES 07 1861 FSAR 6. 1 PROCEDURES AND FOR THE CONTROL OF DOCUMENTATION PERSONNEL AND MAINTENANCE OF CONTAINMENT SECURITT ARE ESTABLISRED PRIOR ;
TO FUEL LOADING.
- 14. 2. OPERATIONS TEMPORART SOURCE RANGE 07 1862 FSAR 6. 1 '
PROCEDURES AND CHANNELS ARE INSTALLED DOCUMENTATION IN THE CONTAINMENT STRUCTURE AND ARE '
MONITORED BT TEST PERSONNEL.
C
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OPEdATIONS AND SUPPORT
===e=============
COMMITMENT DOCUMENT / FEATURE TITLE MODULE REMARES NUMBER COMMITMENT COMMITMENT SOURCE SECTION SUBJECT
e=== == ========== ================ ====e====e========e= =e.=================== =============== ====== ==================
OPERATIONS MINIMUM COUNT RATES OF 07 1863 FSAR 14. 2. 6. 1 PROCEDURES AND 2 CPS ARE REQUIRED ON DOCUMENTATION AT LEAST 2 0F THE 4 NEUTRON SOURCE CHANNELS AT ALL TIM' FOLLOWING INSTALLA' OF THE IN ITI A L NU' 0F FUEL ASSEMBLIE;
- 14. OPYRATIONS FUEL HANDLING TOOLS 07 1864 FSAR 2. 6. 1 PROCEDURES AhD AND EQUIPMENT WILL DOC"~~4TATION HAVE BREN CRECRED OUT AN* 'uY RUNS CC' - 'O.
1865 FSAR 14. 2. 6. 1 OPERATIONS F1 ,ADING 07 6EE SECTION 14.2.6.1 PROCEDURES AND PRG. s0RES CONTAIN OF THE FSAR FOR 3 DOCUMENTATION REQUIREMEhYS THAT CRITERIA.
LOADING STOP IF ANT OF THE G2VEN SITUATIONS OCCUR.
2774 FSAR 14. 2. 6. 1 OPERATIONS THE TEMPORART CHANNELS 07 PROCEDURES AND INDICATE ON SCALERS DOCUMENTATION WITH A MINIMUM OF ONE CHANNEL RECORDED ON A STRIP CHART RECORDER.
2775 FSAR 14. 2. 6. 1 OPERATIONS AT LEAST TWO NEUTRON 07 PPOCEDURES AND SOURCES ARE INTRODUCED DOCUMENTATION INTO THE CORE DURING THE LOADING PROGRAM TO ENSURE A DETECTOR RESPONSE OF AT LEAST 2 CPS ATTRIBUTABLE TO NEUTRONS.
2776 FSAR 14. 2. 6. 1 OPERATIONS FUEL ASSEMBLIES AND 07 PROCEDURES AND OTHER INSERTED DOCUMENTATION COMPONENTS ARE PLACED IN THE REACTOR VESSEL ONE AT A TIME ACCORDING TO A PREVIOUSLT ESTABLISRED AND APPROVED SEQUENCE.
O O O O O O O
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=======e==
NUMBER COMMITMENT COMMITMENT COMMITMENT DOCUMENT / FEATURE TITLE MODULE REMARES
< SOURCE SECTION SUBJECT
== ========== e=============== ===============,==== ==================== = ================ ====== ==============
2777 FSAR I4. 2. 6. I OPERATIONS CORE LOADING 07 PROCEDURES AND PROCEDURES INCLUDE DOCUMENTAT.'N DETAILED TABLULAR CHECK SHEETS WHICR PRESCRIBE AND VERIFY THE SUCCESSIVE MOVEMENTS OF EACR FUEL ASSEMBLY AND ITS SPECIFIED INSERTS FROM STORAGE RACE TO CORE.
2778 FSAR I4. 2. 6. I OPERATIONS EACH SUBSEQUENT FUEL 07 TBE RESULTS OF EACR PROCEDURES AND ADDITION IS STEP ARE ETALUATED DOCUMENTATION ACCOMPANIED BT BEFORE THE NEET DETAILED NUETRON COUNT PREECRIBRD STEP IS RATE MONITORING TO STARTED.
DETECT IECESSIVE
! INCREASE IN COUNT RATE
' AND UNEEPLAINED e DECREABE IN INVERSE COUNT RATE RATIO.
I4, 2. OPERATIONS THE CONTAINMENT 07 WHEN SOUNDED DURIMO
,' 2779 FSAR 6. 1 CORE LOADING AND PROCEDURES AND EVACUATION ALARM DOCUMENTATION REQUIRES AN IMMEDIATE AFTER IT IS STOP OF OPERATIONS DETERMINED TRAT NO l PERSONNEL RAZARD UNTIL THE SITUATION IS EVALUATED. REISTS. PERSONNEL i
MAY ENTER
- CONTAINMENT To EVALUATE THE CAUSE AND DETERMINE FUTURE ACTION.
i I OPERATIONS CORE LOADING OT 2700 FSAR 14. 2. 6.
PROCEDURES AND PROCEDURES SPECIFT DOCUMENTATION CONDITIONS TO PREVENT Y INADVERTENT DILUTION 0F THE RCS. SPECIFY
' ~ ' THE MOVEMENT OF FUEL, i PRESCRIBE THE CONDITIONS UNDER WRICR LOADING CAN PROCEED, IDENTIFT RESP. AND AUTH., AND PROVIDE l ( FUEL ACCOUNTABILITY.
i (
4
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COMMITMENT DOCUMENT / FEATURE TITLE MODULE REMARKS NUMBER COMMITMENT COMMITMENT SOURCE SECTION SUBJECT
=========- == ============= ==-e== ==============
=== == ====e===== ================ ==================== =e
- 14. 2 OPERATIONS AT NO TIME MAT A 07 1866 FSAR 2. 6.
PROCEDUHES AND SUSTAINED STAN1UP RATE DOCUMENTATION OF 1 DECADE / MIN BE EXCEEDED.
1867 FSAR 14. 2. 6. 2 OPERATIONS ACTUAL CONTROL ROD 07 PROCEDURES AND ASSEMELT DROP TIMES DOCUMENTATION ARE MEASURED.
1868 FSAR 14. 2. 6. 2 OPERATIONS BCRON CONCENTRATION TO 07 PROCEDURES AND BE MAINTAINED IN DOCUMENTATION ACCORDANCE WITR TECH SPECS. DURING CRDM TESTING.
1869 FSAR 14. 2. 6. 2 OPERATIONS COMPLETE FUNCTIONAL 07 PROCEP"RES AND ELECTRICAL AND DOCUMENTATION MECHANICAL CHECK IS MADE OF THE INCORE NUCLEAR FLUI MAPPING SYSTEM AT OPERATING TEMPERATURE AND PRESSURE.
1870 FSAR 14. 2. 6. 2 OPERATIONS COUNT RATE OF AT LEAST 07 PROCEDURES AND 1/2 CPS. SRALL DOCUMENTATION REGISTER ON THE STARTUP CH ANNELS AND SNR SRALL BE GREATER THAN 2 PRIOR TO
' BEGINNING THE APPROACH TO CRITICALITT.
1871 FSAR 14. 2. 6. 2 OPERATIONS INVERSE COUNT RATE 07 PROCEDURES AND RATIO DATA ARE PLOTTED DOCUMENTATION AS A FUNCTION OF ROD 8ANK POSITION DURING BOD MOTION AND AS A FUNCTION OF PRIMART
' WATER ADDITION DURING BORON DILUTION.
1
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Page No. 81 12/02/85
- TABLE 3.2-1 COMMITMENTS FOR PLANT
ee===========e =========
OPERATiows AND SUPPORT
==========
NUMBER COMMITMENT COMMITMENT COMMITMENT DOCUMENT / FEATURE TITLE MODULE REMARES SOURCE SECTION SUBJECT
e= == ==e======= =e=============e ==================:- =2======e=========e=== ================ ====== ================
1872 FSAR 14. 2. 6. 2 OPERATIONS CORE RESPONSE DURING 07 PROCEDURES AND BANE WITHDRAWAL AND DOCUMENTAIONS BORIC ACID DILUTION WILL BE MONITORED IN THE MAIN CONTROL ROOM ON PERMANENT NIS.
1873 FSAR I4. 2. 6. 2 OPERATIONS MECHANICAL AND 07 PROCEDURES AND ELECTRICAL TESTS ARE DOCUMENTATION PERFORMED ON THE CONTROL ROD DRIVE MECHANISMS, INCLUDINO OPERATIONAL CHECEOUT OF THE MECHANISMS AND CALIBRATION OF RPI SYSTEM.
1874 FSAR I4. 2. 6. 2 OPERATIONS PRECRITICAL TESTS 07 PRO.EDURES AND SHALL BE COMPLETED AND DOUCMENTATION RESULTS EVALUATED PRIOR TO INITIAL CRITICALITY.
1975 FSAR I4. 2. 6. 2 OPERATIONS PREDICTED BORON 07 PROCEDURES AND CONCENTRATION FOR DOCUMENTATION CRITICALITY WILL BE DETERMINED FOR THE BANE CONFIOURATION SPECIFIED IN TRE INITIAL CRITICALITY PROCEDURE.
1876 FSAR I4. 2. 6. 2 OPERATIONS REACTOR CONTROL AND 07 PROCEDURES AND PROTECTION SYSTEM IS DOCUMENTATION CBBCEED WITH VARIOUS SIMULATED SIONALS TO PRODUCE A TRIP SIGNAL.
, 1877 FSAR I4. 2. 6. 2 OPERATIONS REACTOR TRIP CIRCUITS 07 PROCEDURES AND TESTED FOR MANUAL TRIP DOCUMENTATION OPERATION.
+
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- _ %eww'+e+c --_ mm --c-_o-w_ yu- +- e-_______w - -
_m .__ ____ _ _ _ _ ___ _
Page No. 82 I2/02/85 COMMITMENTS FOR PLANT TABLE 3.2-1
e-========================
OPERATIONS AND SUPPORT
======= ==
TITLE MODULE REMARES COMMITMENT COMMITMENT COMMITMENT DOCUMENT / FEATURE NUMBER SOURCE SECTION SUBJECT ====== ============== =,=e=
= == ======s==- ================ ==================== ====================== ==========e
14, 2 OPERATIONS PROCEDURS SAMPLES OF THE PRIMARY 07.9B 1878 FSAR 2. 6.
AND DOCUMENTATION COOLANT ARE OBTAINED AND ANALYZED FOR BORON CONCENTRATION THROUGHOUT THE POST LOADING PERIOD.
OPERATIONS PREREQUISITES ARE 07 SPECIAL TEST 2781 FSAR 14. 2. 6. 2 INSTRUMENTS NOT PROCEDURES AND SPECIFIED IN DOCUMENTATION INDIVIDUAL TEST NEEDED FOR FUTURE PROCEDURES. SEQUENCE USE ARE REMOVED AND OF TESTING IS IN A THE REMOVAL IS STRTUP TEST SEQUENCE. VERIFIED.
SPECIAL TEST INSTRUMENTS REQUIRED ARE SPECIFIED TO BE INSTALLED, CALIBRATED, AND CHEREED IN THE TEST PROCEDURE.
14, 2 OPERATIONS DURING INDIVIDUAL ROD 07 2782 FSAR 2. S.
PROCEDURES AND CLUSTER CONTROL DOCUMENTATION ASSEMBLT OR ROD CLUSTER CONTROL BANK MOTION, SOURCE RANGE INSTRUMENTATION IS MONITORED FOR UNEXPECTED CHANGES IN CORE REACTIVITT.
1879 FSAR 14, 2. 6. 3 LOW-PONER TESTING CONCURRENT TESTS ARE 07 CONDUCTED ON INSTRUMENTATION INCLUDING SOURCE AND INTERMEDIATE RANGE CHANNELS.
1880 FSAR 14. 2. 6. 3 LOW-PONER TESTING GAMMA AND NEUTRON 07,9A RADIATION SURVETS ARE PERFORMED AT SELECTED POINTS TRROUGHOUT THE PLANT.
4 O O O O O O O
. . . . . & - . ..._& . .. _ - ..m.__m ._.--._ m ..a. . . ._.._.m. - .. -.-.--.m._ _ _ _ _ _ - . . . - - . . . . - . _ . . ,- .m I
Page No, 83 12/02/HS TABLE 3.2-1 COMMITMENTS FOR PLANT
=========== ==========
OPERATIONS AND SUPPORT
: ==========
COMMITMENT DOCUMENT / FEATURE TITLE MODULE REMARKS NUMBEH COMMITMENT COMMITMENT SOURCE SECTION SUBJECT
==,= ===== ========== ====== =========e====
= == ==e======= ================ ================- == ====se
14, 6. 3 LOW-POWER TESTING MEASUREMENTS ARE MADE 07 1R81 FSAR 2.
TO VERIFY: A)
CALCULATED VALUES OF CONTROL ROD BANK REACTIVITY WORTHS.
- 14. 3 LOW-POWER TESTING MEASUREMENTS ARE MADE 07 1882 FSAR 2. 6.
TO VERIFY: B)
ISOTHERMAL TEMPERATURE COEFFICIENT UNDER VARIOUS CORE CONDITIONS.
LOW-POWER TESTING MEASUREMENTS ARE MADE 07 1883 FSAR 14. 2. 6. 3 TO VERIFY: C)
DIFFERENTIAL BORON CONCENTRATION REACTIVITY WORTH.
14, 6. 3 LOW-POWER TESTING MEASUREMENTS ARE MADE 07 1884 FSAR 2.
TO VERIFT: D)
CRITICAL BORON CONCENTRATION AS FUNCTIONS OF CONTROL ROD CONFIGURATION.
LOW-POWER TESTING MEASUREMENTS OF THE OT 1885 FSAR 14. 2. 6. 3 RELATIVE POWER DISTRIBUTIONS ARE MADE.
1886 FSAR 14. 2. 6. 3 LOW-POWER TESTING. PERIODIC SAMPLING IS 07.9B i PERFORMED TO VERIFY CHEMICAL AND RADIO-CHEMICAL ANALYSIS OF THE REACTOR COOLANT.
3 OPERATIONS PROCEDURES SPECIFY THE 07 2783 FSAR 14. 2. 6.
4
( PROCEDURES AND SEQUENCE OF TESTS AND DOCUMENTATION MEASUREMENTS TO BE CONDUCTED AND THE I
CONDITONS UNDER WHICH EACH IS 70 SE PERFORMED. IT TEST b
2 RESULTS ARE ABNORMAL, lHE PLANT IS PLACED IN A SAFE AND STABLE
( CONDITION.
Page No. 84 12/02/85 COMMITMENTS FOR PLANT TABLE 3.2-1
=====================
OPERATIONS AND SUPPORT
=========== =====,
TITLE MODULE REMARKS NUMBER COMMITMENT COMMITMENT COMMITMENT DOCUMENT / FEATURE SOURCE SECTION SUBJECT ====== =====~==============
er=======
====== == = ======== ================ ========--========== --==-================= ====--
POWER LEVEL AT DESIGNATED POWER 07 THE MINIMUM TEST 1887 ISAR 14. 2. 6. 4 REQUIREMENTS FOR ASCENSION 1. E V E LS , HOLD POINTS ARE PROVIDED TO BACR SUCCESSIVE EVALUATE AND APPROVE STAGE OF POWER TEST RESULTS PRIOR TO ASCENSION ARE PROCEFDING TO THE NEXT SPECIFIED IN THE POWER LEVEL. APPLICABLE STARTUP TEST PROCEDURES.
POWEH LEVEL DYNAMIC RESPONSE OT 1888 FSAR 14. 2. 6. 4 ASCENSION CRARACTERISTICS OF THE PRIMARY AND SECONDARY SYSTEMS ARE EVALUATED AT PRESCRIBED POWER LEVELS.
6 4 POWER LEVEL GAMMA AND NEUTRON 07,94 1889 FSAR 14. 2.
ASCENSION RADIATION SURVEYS ARE TAEEN AT VARIOUS PONER LEVELS.
- 14. 4 POWER LEVEL MEASUREMENTS ARE MADE 07 1890 FSAR 2. 6.
ASCENSION TO DETERMINE THE RELATIVE POWER DISTRIBUTION AS FUNCTIONS OF POWER LEVEL AND CONTROL BANE POSITION.
1891 FSAR 14. 2. 6. 4 PONER LEVEL PERIODIC SAMPLING 07.98 ASCENSION PERFORMED TO VERIFT CREMICAL AND RADIO-CREMICAL ANALYSIS OF THE REACTOR COOLANT.
1892 FSAR 14. 2. 6. 4 POWER LEVEL RCS ABILITY TO RESPOND OT ASCENSION TO PRIMART AND SECONDARY a INSTRUMENTATION SIGNALS UNDER A VARIETY OF NORMAL 7
OPERATING CONDITIONS IS VERIFIED.
O O O O O O 9
O O O ~
O O. O O PaEe No. 85 12/02/85 TABLE 3.2-1 COMMITMENTS FOR PLANT
e=========================
OPERATIONS AND SUPPORT
==========
DOCUMENT / FEATURE TITLE MODULE REMARES NUMBER COMMITMENT COMMITMENT COMMITMRNT SOURCE SECTION SUBJECT
=====e===r=== e==============e====== ================ ====== ==============
== ========== ==========
POWER LEVEL SYSTEM RESPONSE 07 1893 FSAR 14. 2. 6. 4 ASCENSION CHARACTERISTICS ARE MEASURED FOR: A)
DESIGN STEP-LOAD CHANGES.
POWER LEVEL STSTEM RESPONSE 07 1894 FSAR 14. 2. 6. 4 ASCENSION CHARACTERISTICS ARE MEASURED FOR: B)
RAPID LOAD REDUCTION.
POWER LEVEL STSTEM RESPONSE 07 1895 FSAR 14. 2. 6. 4 ASCENSION CHARACTERISTICS ARE MEASURED FOR: C)
PLANT TRIPS.
j PROCEDURES AND FINAL LEAE. RATE TEST DOCUMENTATION
- 2. 2 OPERATIONS TEST ABSTRACT - 07 2014 FSAR 14. 2. 8.
PROCEDURES AND PRESSURIZER REATER AND DOCUMENTATION SPRAT CAPABILITT AND CONTINOUS SPRAT FLOW VERIFICATION TEST
PROCEDURES AND FLOW MEASUREMENT TEST.
DOCUMENTATION
PROCEDURES AND BTPASS VALVE FLOW DOCUMENTATION MEASUREMENT TEST.
PROCEDURES AND FLOW COASTDOWN TEST.
DOCUMENTATION
- 2. 6 OPERATIONS TEST ABSTRACT - 07 f- 2018 FSAR 14. 2. 8.
4 ' PROCEDURES AND REACTOR PROTECTION DOCUMENTATION TEST.
(
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^ ^ - - - . . ,
Page No. 86 12/02/85 TABLE 3. 2 -1 COMMITMENTS FOR PLANT
== =========-=========
OPERATIONS AN9 SUPPORT
======e===
TITLE MODULE REMARKS COMMITMENT COMMITMENT COMMITMENT DOCUMENT / FEATURE NUMBER SOURCE SECTION SUBJECT === ============ ==,=== =~ ====-============
=== == ====- ==== -=============== ============ ======= ===== ============e
7 OPERATIONS TEST ABSTRACT - CORE 07 2019 FSAR 14. 2. 8. 2.
PROCEDURES AND LOADING DOCUMENTATION INSTRUMENTATION AND NEUTRON SOURCE '
REOUIREMENTS.
8 OPERATIONS TEST ABSTRACT - 07 2020 FSAR 14. 2. 8. 2.
PROCEDURES AND THFRMAL POWER DOCUMENTATION MEASUREMENT AND STATEPOINT DATA COLLECTION.
TEST ABSTRACT - INCORE 07 202] FSAR 14. 2. 8. 2. 9 OPERATIONS PROCEDURES AND DETECTOR TEST.
DOCUMENTATION H. 2.10 OPERATIONS TEST ABSTRACT - 07 2022 FS4H 14. 2.
PROCEDURES AND OPERATIONAL ALIGNMENT DOCUMENTATION OF NUCLEAR 4
INSTRUMENTATION
- 14. 2. 8. 2.12 OPERATIONS TEST ABSTRACT - ROD 07 2023 FSAR PROCEDURES AND CONTROL STSTEM TEST.
DOCUMENTATION 2.13 OPERATIONS TEST ABSTRACT - CRDM 07 2024 FSAR 14. 2 8.
PROCEDURES AND OPERATIONAL TEST DOCUMENTATION
- 14. 2.14 OPERATIONS TEST ABSTRACT - ROD 07 2025 FSAR 2. 8.
PROCEDURES AND DROP TIME MEASUREMENT.
DOCUMENTATION
- 14. 2.15 OPERATIONS TEST ABSTRACT - ROD 07 2026 FSAR 2. 8.
PROCEDURES AND POSITION INDICATION DOCUMENTATION
- 14. OPERATIONS TEST ABSTRACT - 07 2027 FSAR 2, 8. 2.16 PROCEDURES AND OPERATIONAL ALIGNMENT DOCUMENTATION OF PROCESS TEMPERATURE INSTRUMENTATION.
O O O O O O O
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2 O ,
Page No. 87 12/02/85 a TABLE 3. 2 - 1 COMMITMENTS FOR PLANT ;
-================================= j OPERATIONS AND SUPPORT
==========
DOCUMENT / FEATURE TITLP MODULE REMARKS NUMBER COMMITMENT COMMITMENT COMMITMENT 1 SOURCE SECTION SUBJECT i
== ========== ================ ==================== ====================== ================ ====== ===
TEST ABSTRACT - 07 2028 FSAR 14. 2. 8. 2.17 OPERATIONS PROCEDURES AND STARTUP ADJUSTMENTS OF DOCUMENTATION RCS.
- 14. 2, 8. 2.18 OPERATIONS TEST ABSTRACT - RCS 07.9B 2032 FSAR PROCEDURES AND SAMPLING FOR CORE DOCUMENTATION LOADING.
TEST ABSTRACT - METAL 07 2033 FSAR 14. 2 8. 2.19 OPERATIONS PROCEDURES AND IMPACT MONITORING DOCUMENTATION SYSTEM TEST.
OPERATIONS TEST ABSTRACT - 07 2034 FSAR 14. 2. 8. 2.20 PROCEDURES AND INITIAL FUEL LOADING.
DOCUMENTATION OPERATIONS TEST ABSTRACT - 07 2035 FSAR 14. 2. 8. 2.21 PROCEDURES AND INVERSE COUNT RATE DOCUMENTATION RATIO MONITORING FOR FUEL LOADING.
OPERATIONS TEST ABSTRACT - 07 2036 FSAR 14. 2. 8. 2.22 PROCEDURES AND DETERMINATION OF CORE I DOCUMENTATION POWER RANGE FOR PRTSICS TESTING.
OPERATIONS TEST ABSTRACT - CORE 07
! 2037 FSAR 14. 2. 8. 2.23 PROCEDURES AND LOADING TEST SEQUENCE.
DOCUMENTATION i
2.24 OPERATIONS TEST ABSTRACT - 07 2038 FSAR 14. 2. 8.
PROCEDURES AND DYNAMIC AUT0MATIC DOCUMENTATION STEAM DUMP CONTROL.
I 2.25 OPERATIONS TEST ABSTRACT - 07 2039 FSAR 14. 2. 8.
PROCEDURES AND AUTOMATIC SG LEVEL DOCUMENTATION CONTROL.
- 8. 2.26 OPERATIONS TEST ABSTRACT - POWER 07 2040 FSAR 14. 2.
- (~ PROCEDURES AND COEFFICIENT 4 DOCUMENTATION DETERMINATION.
f a
d C
- . C
_ m . . ,_. . _ m.
Page No. 88 12/02/85 COMMITMENTS FOR PLANT TABLE 3.2-1
==================-===
OPERATIONS AND SUPPORT
==========
TITLE MODULE REMARES COMMITMENT COMMITMENT COMMITMENT DOCUMENT / FEATURE NUMBER SOURCE SECTION SUBJECT
=- =======e== ================ =========e========== ===================-== =============== ====== -=============
TEST ABSTRACT - LOAD 07 2041 FSAR 14. 2. 8. 2.27 OPERATIONS PROCEDURES AND SWING TEST.
DOCUMENTATION TEST ABSTRACT - 07,98 2044 FSAR 14. 2. 8. 2.28 OPERATIONS PROCEDURES AND PROCESS AND EFFLUENT DOCUMENTATION RADIATION MONITORING TEST.
TEST ABSTRACT - AXIAL 07 2045 FSAR 14. 2. 8. 2.29 OPERATIONS PROCEDURES AND FLUX DIFFERENCE DOCUMENTATION INSTRUMENTATION CALIBRATION OPERATIONS TEST ABSTRACT - FLUX 07 2046 FSAR 14. 2. 8. 2.30 r
PROCEDURES AND MAP.
DOCUMENTATION OPERATIONS TEST ABSTRACT - 07 2047 FSAR 14. 2. 8. 2.31 PROCEDURES AND AUTOMATIC REACTOR DOCUMENTATION CONTROL.
- 8. 2.32 OPERATIONS TEST ABSTRACT - 07 2048 FSAR 14. 2.
DROPPED CONTROL ROD PROCEDURES AND DOCUMENTATION TEST.
OPERATIONS TEST ABSTRACT - PSUEDO 07 2049 FSAR 14. 2. 8. 2.34 PROCEDURES AND ROD EJECTION TEST.
DOCUMENTATION OPERATIONS TEST ABSTRACT - RCCA 07 2050 FSAR 14. 2. 8. 2.35 PROCEDURES AND AND BANE WORTH DOC UME NT A T ION MEASUREMENT AT ZERO POWER.
2.37 OPERATIONS TEST ABSTRACT - BORON 07 2051 FSAR 14. 2. 8.
PROCEDURES AND END POINT DOCUMENTATION DETERMINATION.
.h
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i Page No. 89 12/02/85 TABLE 3.2-1 COMMITMENTS FOR PLANT
- =============e===============e= =
OPERATIONS AND SUPPORT
==========
NUMBER COMMITMENT COMMITMENT COMMITMENT DOCUMENT / FEATURE TITLE MODULE REMARKS SOURCE SECTION SUBJECT
== ========== ================ ==========e====e==== ==================ee== ================ ====== ==============
2052 FSAR 14. 2. 8. 2.38 OPERATIOSN TEST AB5 TRACT - 07 PROCEDURES AND INVERSE COUNT RATE DOCUMENTATION RATIO FOR THE APPROACR TO INITIAL CRITICALITT 2053 FSAR 14. 2. 8. 2.39 OPERATIONS TEST ABSTRACT - 07 PROCEDURES AND INITIAL CRITICALITT DOCUMENTATION 2054 FSAR 14. 2. 8. 2.40 OPERATIONS TEST ABSTRACT - ISO 07 PROCEDURES AND THERMAL TEMPERATURE
! DOCUMENTATION COEFFICIENT
' MEASUREMENT.
07 i 2055 FSAR 14. 2. 8. 2.41 OPERATIONS TEST ABSTRACT - I PROCEDURES Ah1 INITIAL CRITICALITT DOCUMENTATION AND LOW POWER TEST ,
SEQUENCE.
- 14. OPERATIONS TEST ABSTRACT - 07,9A :
2056 FSAR 2. 8. 2.42 PROCEDURES AND BIOLOGICAL SHIELD DOCUMENTATION SURVET 2057 FSAR 14. 2. 8. 2.43 OPERATIONS TEST ABSTRACT - 07 i PROCEDURES AND DTNAMIC RESPONSE TEST.
DOCUMENTATION 4
2058 FSAR 14. 2. 8. 2.45 OPERATIONS TEST AB5 TRACT - REMOTE 07 PROCEDURES AND SHUTDOWN.
DOCUMENTATION 2 -
l 2059 FSAR 14. 2. 8, 2.46 OPERATIONS TEST ABSTRACT - LOSS 07
! PROCESURES AND OF OFF-SITE PONER AT ,
! DOCUMENTATION GREATER TNAN 10 PERCENT POWER i
e
- 8. 2.47 OPERATIONS- TEST ABSTRACT - 07 j 2060 FSAR 14. 2.
PROCEDURES AND LOW-POWER NATURAL DOCUMENTATION CIRCULATION.
a i
4 4
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Pmg* No. 90 12/02/85 TABIE 3.2-1 COMMITMENTS FOR PLANT
-================ ==========- ====
OPERATIONS AND SUPPORT ,
==========-========e
DOCUMENT / FEATURE TITLE MODULE REMARES NUMBER COMMITMENT COMMITMENT COMMITMENT SOURCE SECTION SUBJECT ===-== =========-==== .====
,==--= == r===== ==- =============r== ==,= ===== ==-==== = :- =========.=====-==- re--=======r====
TEST ABSTRACT - 07 206] FSAR 14. 2. 8. 2.40 OPERATIONS PROCEDURES THERMAL. EXPANSION.
- 14. 2. 8. 2.49 OPERATIONS TEST ABSTRACT - 07.98 2063 FSAR PRIMARY AND SECONDARY PROCEDURES AND DOCUMENTATION CHRMISTRY.
TEST ABSTRACT - POWER 07 2064 FSAR 14. 2. 9. 2.50 OPERATIONS PROCEDURES AND ASCENSION TEST DOCUMENTATION SEQUENCE.
OPERATIONS TEST ABSTRACT - RODS 07 2065 FSAR 14. 2. H. 2.51 PROCEDURES AND DROP AND PLANT TRIP.
DOCUMENTATION R. 2.52 GPERATIONS TEST ABSTRACT - LARGE 07 2066 FS4R 14. 2.
PROCEDURES AND LOAD REDUCTION.
DOCUMENTATION OPERATIONS TEST ABSTRACT - PLANT 07 2067 FSAR 14. 2. 8. 2.53 PROCEDURES AND TRIP FROM 100 PERCENT DOCUMENTATION POWER.
B. 2.54 OPERATIONS TEST ABSTRACT - STEAM 07 2068 FSAR 14. 2.
PROCEDURES AND GENERATOR MOISTURE DOCUMENTATION CARRTOVER 14, 2.55 OPERATIONS TEST ABSTRACT - PLANT 07 2069 FSAR 2. 8.
PROCEDURES AND PERFORMANCE.
DOCUMENTATION OPERATIONS TEST ABSTRACT - 07 2070 FSAR 14. 2. 8. 2.56 PROCEDURES AND NUCLEAR STEAM SUPPLT DOCUMENTATION SYSTEM ACCEPTANCE TEST.
OPERATIONS TEST ABSTRACT - 07 2071 FSAR 14. 2. 8. 2.57 PROCEDURES AND AT-POWER DOCUMENTATION INTERCOMPARISON OF REACTOR SYSTEM AND PLANT COMPUTER INPUTS.
O O O O O O O
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Page No. 91 12/02/85 TABLE 3.2 -1 COMMITMENTS FOR PLANT
e= =====================
OPERATIONS AND SUPPORT
==========
NUMBER COMMITMENT COMMITMENT COMMITMENT DOCUMENT / FEATURE TITLE MODULE REMARKS SOURCE SECTION SUBJECT
== ========== ================ =================s== ====================== -=============== ====== ==============
2072 FSAR 14. 2. 8. 2.58 OPENATIONS Tssi ABSTRACT - 07 PROCEDURES AND VENTILATION CAPABILITY DOCUMENTATION TEST.
2073 FSAR 14. 2. 8. 2.59 OPERATIONS TEST ARSTRACT - GROSS 07 PROCEDURES AND FAILED FUEL DETECTOR DOCUMENTATION TEST.
2784 FSAR 15. O. 1. 5 OPERATIONS GENERIC GUIDELINES TO OT PROCEDURES AND PRECLUDE VOID DOCUMENTATION FORMATION IN THE UPPER 8EAD WERE DEVELOPED BT WESTINGROUSE AND SUBMITTED TO NRC.
THESE GUIDELINES WILL BE USED IN THE DEVELOPMENT OF THE VEGP SPECIFIC PROCEDURES.
2074 FSAR 15. O. 6 ASSUMED TRIP POINTS DURING PLANT STARTUP 03A.07 AND TIME DELAYS IN TESTS, IT WILL BE ACCIDENT ANALYSES DEMONSTRATED THAT ACTUAL INSTRUMENT TIME DELAYS ARE EQUAL TO OR LESS THAN THE ASSUMED VALUES. (15.0.6) 2076 FSAR 15. 2. 8. 2. 1 OPERATIONS SPECIFIC REQUIREMENTS 07 SEE SECTION PROCEDURES AND SRALL BE INCLUDED IN 15.2.8.2.1 0F THE DOCUMENTATION EMERGENCY OPERATING FSAR FOR DETAILS.
PROCEDURES REGARDING FEEDWATER PIPE RUPTURE.
2078 FSAR 15. 4. 6. 2. 1. OPERATIONS REACTOR MAEEUP WATER 07 1 PROCEDURES AND DURING REFUELING WILL DOCUMENTATION BE SUPPLIED FROM THE RMST VIA THE RHR PUMPS.
i
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Page No. 92 12/02/85 TABLE 3.2 I COMMITMENTS FOR PLANT
=========== ====-========
OPFRATIONS AND SUPPORT
- =- = ===- === ===-
COMMITMENT DOCUMENT / FEATURE TITLE MODULE REMARKS NUMBER COMMITMENT COMMITMENT SOURCE SECTION SUBJECT
-e=== ==- =- -========= =========
= == === ==-=- ================ =====-==- == ====== ==== =-===- ====-===-- == ===
PLANT STATUS DILUTION DURING 07 SEE ALSO QUESTION 207') FSAR 15. 4. 6. 2. 1.
CONTROLS REFUELING IS PREVENTED 440.116 1
BY ADMINISTRATIVE CONTROLS WHICH ISOLATE RCS FROM POTENTIAL SOURCE OF UNBORATED WATER.
TECHNICAL SUPPORT DURING CORE LOADING. 07 20R0 FSAR 15. 4. 7. 1 PROCEDURES AND FUEL ASSEMBLY DOCUMENTATION IDENTIFICATION NUMBER WILL BE CHECKED BEFORE EACH ASSEMBLY IS MOVED INTO THE CORE. NUMBERS READ DURING MOVEMENT ARE SUBSEQUENTLY RECORDED ON THE LOADING DIAGRAM.
- 15. 1. REACTOR ENGINEERING DURING PLANT STARTUP 07 2081 FSAR 4. 8. 2.
I PHYSICS TESTING.
EJECTED ROD WORTHS AND POWER DISTRIBUTIONS ARE MEASURED IN ZERO AND FULLPOWER CONFIGURATIONS AND COMPARED TO VALUES USED IN NUCLEAR DESIGN CODE ANALYSIS.
2083 FSAR 15. 7. 4. 5. 1. TECHNICAL SUPPORT IN ADDITION TO AREA 07.94 1.8 PROCEDURES AND AND EFFLUENT RADIATION DOCUMENTATICN MONITORS IN CONTAINMENT. PORTABLE MONITORS CAPABLE OF SOUNDING AUDIDLE ALARMS ARE TO BE LOCATED IN THE FUEL HANDLING AREA DURING s REFUELING.
O O O O O O O
k O O O O O- O O Page No. 93 12/02/85 TABLE 3.2-1 COMMITMENTS FOR PLANT
======================
OPERATIONS AND SUPPORT
n===_== =
NUMBER COMMITMENT COMMITMENT COMMITMENT DOCUMENT / FEATURE TITLE MODULE REMARES SOURCE SECTION SUBJECT
====== == ========== ================ ==================== ====================== ========-======= ====== ==================== ,
2084 FSAR 15. 7. 4. 5. 1. TEr:FICAL SUPPORT DOORS IN THE FUEL 07 1.B PkOCEDURES AND BUILDING ARE REPT DOCUMENTATION CLOSED TO ENSURE CONTROL OF LEAEAGE IN THE SPENT FUEL POOL REGION DURING OPERATIONS INVOLVING IRRADIATED FUEL.
2085 FSAR 17. 2. 1, 2 OPERATIONS QA SUPERINTENDENTS AND 02.05, PROGRAM SUPERVISORS WILL BE 07.9A, RESPONSIBLE FOR 98 IMPLEMENTATION OF OQAP FOR ACTIVITIES UNDER THEIR PURVIEW.
2086 FSAR 17, 2. 1. 2 & ERATIONS QA PLANT STAFF WILL 02.05, ROGRAM PERFORM SAFETT RELATED 07,9A, ACTIVITIES IN 98 ACCORDANCE WITH WRITTEN APPROVED PROCEDURES WHICH INCLUDE QUALITY ASSURANCE REQUIREMENTS.
2821 FSAR 17. 2. 1. 2. 4 OPERATIONS QA TRE SUPERINTENDENT OF 05.07 PROGRAM MAINTENANCE IS RESPONSIBLE FOR EFFECTIVE IMPLEMENTATION OF THE 00AP TO APPLICABLE MECHANICAL.
ELECTRICAL, AND I&C MAINTENANCE OF PLANT EQUIPMENT. STSTEMS, OR STRUCTURES.
, 2822 FSAR 17. 2. 1. 2. 5 OPERATIONS QA THE SUPERINTENDENT OF 05.07 PROGRAM OPERATIONS RAS THE RESPONSIBILITT TO ENSURE THAT THE PLANT g
IS OPERATED IN ACCORDANCE WITH APPROVED PROCEDURES AND LICENSE REQUIREMENTS.
i l (
. .- t Page No. 94 12/02/85 TABLE 3.2-1 COMMITMENTS FOR PLANT
======================
OPERATIONS AND SUPPORT
=========,==:-=== =
NUMBER COMMITMENT COMMITMENT COMMITMENT DOCUMENT / FEATURE TITLE MODULE REMARKS SOURCE SECTION SUBJECT
=e ==== ===== ================ =====er ============ ==-=================== ================ ====== ==============
l 17. 1.
"823 FSAR 2. 2. 6 OPERATIONS QA THE SUPERINTENDENT OF 05.07 PROGRAM PLANT ENGINEERING AND SERVICES IS HRSPONSIBLE FOR PROVIDING ENGINEERING RELATED TECHNICAL SERVICES IN SUPPORT OF VEGP OPERATIONS. HE ASSISTS IN PROCUREMENT AND SHALL COORDINATE DESIGN CHANGES.
2R25 FSAR 17. 2. 1. 2. 8 OPERATIONS QA THE MATERIALS 07 PROGRAM SUPERVISOR IS RESPONSIBLE FOR MATERIAL AND EQUIPMENT CONTROL AND MATERIAL REQUISITIONING TO MAINTAIN STOCE LEVELS.
HE IS RESPONSIBLE FOR RECEIVING, RANDLING, AND STORING MATERIALS.
2827 FSAR 17. 2. 1. 2.12 OPERATIONS QA THE SUPERINTENDENT OF 05,07 PROGRAM ENGINEERING LIASON HAS RESPONSIBILITY FOR COORDINATING CONSTRUCTION AND TECHNICAL SUPPORT ACTIVITIES IN MAKING PLANT MODIFICATIONS.
2828 FSAR 17. 2. l. 2.13 OPERATIONS QA THE PROCUREMENT REVIEW 07 PROGRAM SECTION SITE SUPERVISOR IS RESPONSIBLE FOR ENSURING THAT REQt11SITIONS "PECIFT THE CORRECT f PROCUREMENT LEVEL AND TECHNICAL QUALITT REQUIREMENTS. HE ENSURES THAT DOCUMENTATION RECIEVED IS ADEQUATE.
O O O O O O O
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TABLE 3.2-1 COMMITMENTS FOR PLANT
======================
OPERATIONS AND SUPPORT
2===========
NUMBER COMMITMENT COMMITMENT COMMITMENT DOCUMENT / FEATURE TITLE MODULE REMARES SOURCE SECTION SUBJECT
== ========== ==============se ====eze============= ========e3============ ================ ====== ==============
2830 FSAR 17. 2. 1. 4 OPERATIONS QA kUCLEAR OPERATIONS 05.07 PROGRAM DEPARTMENT HAS OVERALL RESPONSIBILITT FOR ASSURING THE AVAILABILITY OF.
PROVIDING. OR SECURING ADEQUATE ENGINEERING AND TECHNICAL SUPPORT FOR VEGP.
2831 FSAR 17. 2. 1. 4 OPERATIONS QA THE NUCLEAR OPERATIONS 07 PROGRAM ENGINEERING PROJECT MANAGER IS THE PRINCIPAL INTERFACE BETWEEN NUCLEAR OPERATIONS DEPARTMENT AND APPROPRIATE ARCHITECETURAL ENGINEERING ORGANIZATIONS FOR SUPPORT OF VEGP.
2832 FSAR 17. 2. 1. 4 OPERATIONS QA SOUTHERN COMPANT 07 SCS ADMINISTERS THE PROGRAM SERVICES IS THE CONTRACT FOR ARCHITECT ENGINEER FOR ENGINEERING SERVICES TEGP DURING OPERATION. PROVIDED BT BBCRTEL i SCS ALSO PROVIDES QA POWER CORPORATION. !
l SUPPORT INCLUDING AUDITS. SUPPLIER
. QUALIFICATION AND j SURVIELLANCE, AND ;
ENGINEERING PROCEDULE REVIEWS. $
2833 FSAR 17. 2. 1. 4 OPERATIONS QA SOUTRERN COMPANT 07 PROGRAM SERVICES-ACTIVITIES IN SUPPORT OF VEOP ARE GOVERNED BT THE SCS VEGP OPERATIONAL SUPPORT POLICT AND 4
PROCEDURE MANUAL AND l g THE SCS ENGINEERING POLICT AND PROCEDURE i MANUAL. BOTE MANUALS ARE REVIEWED AND C CONCURRED BT SCS QA.
a
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. . . . - . . - _ . ---._--.-_.---.-x- . - - - - _ . - _ _ _ _ . _ _ _ - - _ - _ - _ _ _ . - - - _ _ . _ , _ - - - _ _ - - - _ . _ . _ - _ - - - . _ _ _ _ _ . _ - - . _ _ _-_-__- _- -
_ _ _m ._ ._. _ . . _ .
Page No. 96 12/02/85 TABLE 3.2-1 COMMITMENTS FOR PLANT
==== -e===============
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NUMBER COMMITMENT COMMITMENT COMMITMENT DOCUMENT / FEATURE TITLE MODULE REMARKS SOURCE SECTION SUBJECT
======== ====s
= == ========== ================ ==================== ====================== ==========e
2093 FSAR 17. 2. 2 OPERATIONS QA SAFETY RELATED JOES 05,07 PROGRAM ARE CARRIED OUT UNDER 9A,9B SUITABLT CONTROLLED CONDITIONS, WITR WRITTEN APPROVED PROCEDURES AND APPROP.
EQUIP. F OPER ENVIRON.
COND. AND ASSURANCE PREREQ.*S HAVE BEEN MET.
2097 FSAR 17. 2. 2 OPERATIONS QA QUALITT AFFECTING 02,05, PROGRAM PROCEDURES REQUIRED 07,9A, FOR THE ADMINISTRATION 99,15 OF THE OQAP ARE REVIEWED FOR CONSISTENCT WITH PROGRAM COMMITMENTS AND CORPORATE POLICIES AND ARE PROPERLY DOCUMENTED AND CONTROLLED.
2099 FSAR 17. 2. 2 OPERATIONS QA ANSI N18.7-1976 ADMINISTRATIVE O2,05, CONFORMANCE IS PROGRAM CONTROLS AND 07,9A, DISCUSSED IN SECTION QUALITT 98.15 1.9.33.2 OF THE ASSSURANCE FOR FSAR.
THE OPERATIONAL P8ASE OF NUCLEAR POWER PLANTS 2101 FSAR 17. 2. 2 OPERATIONS QA CONTROL SHALL BE 05.07 PROGRAM ESTABLISHED FOR TURNOVER OF RESPONSIBILITIES AND RECORDS FROM MSSS VENDOR AND A/E TO GPC.
2104 FSAR 17. 2. 2 OPRRATIONS QA CONTRACTORS QA/QC 02,05,
- 07,9A, PROGRAM PROGRAM WILL BE COMMENSURATE WITH THE 98,15 SCOPE OF TREIR ACTIVITIES.
APPLICABLE SECTIONS OF ANSI N18.7-1976 WILL APPLT.
O O O O O O O
4 O O . O O O_ O O
=M Page No. 97 12/02/R5 TABLE 3.2-1 COMMITMENTS FOR PLANT
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~
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COMMITMENT DOCUMENT / FEATURE TITLE MODULE REMARKS NUMBER COMMITMENT COMMITMENT SOURCE SECTION SUBJECT e=============== ====== ====================
== ========== ================ ==================== ================
OPERATIONS QA INITIAL FUEL LOADING 07 2835 FSAR 17. 2. 2 PROGRAM PROCEDURES WILL BE REVIEWED FOR ADBQUATE QUALITY AND SPECIFIED AUDITS OF THE LOADING ACTIVITIES WILL BE PERFORMED.
OPERATIONS QA THE Q LIST IS 07 2836 FSAR 17. 2. 2 PROGRAM CONTROLLED BY NUCLEAR OPERATIONS DURING PLANT OPERATION.
2 OPERATIONS QA DOCUMENTED PROCEDURES 02,05, SEE SECTION 17.2.2 2837 FSAR 17. 2. 07,9A. OF THE FSAR FOR PROGRAM CONTROL THE ACTIONS OF THE OROANIZATIONS 98,15 DETAILS.
INVOLVED. THESE
- ACTIVITIES INCLUDE BUT ARE NOT LIMITED TO 22 ASPECTS AS THEY APPLY TO SAFETY RELATED STRUCTURES, EQUIPMENT, 1
AND SYSTEMS.
t
- 17. OPERATIONS QA STARTUP AND POWER 07 j do41 esan 2. 2 PROGRAM ASCENSION TESTING WILL BE CONTROLLED BY WRITTEN TEST PROCEDURES, REVIEWED FOR ADEQUATE CONTROL TO EMSURE QUALITY CERTAIN TEST REQUIREMENTS MUST BE SUCCESSFULLY COMPLETED, DOCUMENTED, AND REVIEWED BEFORE CONTINUING.
07 A
2109 FSAR I7. 2. 3 DESIGN CHANGE WRITTEN PROCEDURES j- , CONTROL WILL IDENTIFY THE POSITION OR ORGANIZATIONS RESPONSIBLE FOR DESIGN VERIFICATION AND DEFINE THEIR AUTHORITY
[7 AND RESPONSIBILITY.
.=
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DOCUMENT / FEATURE TITLE MODULE REMARES NUMBER COMMITMENT COMMITMENT COMMITMENT SOURCE SECTION SUBJECT
== ========== ================ e==-========r======= -===================== ================ ====== ==============
OPERATIONS QA INITIAL FUEL LOADING 07 2835 FSAR 17. 2. 2 PROGRAM PROCEDURES WILL BE REVIEWED FOR ADEQUATE QUALITT AND SPECIFIED AUDITS OF THE LOADING ACTIVITIES WILL BE PERFORMED.
OPERATIONS QA THE Q LIST IS 07 2836 FSAR 17. 2. 2 PROGRAM CONTROLLED BY NUCLEAR OPERATIONS DURING PLANT OPERATION.
DOCUMENTED PROCEDURES 02.05, SEE SECTION 17.2.2 2837 FSAR 17. 2. 2 OPERATIONS QA PROGRAM CONTROL THE ACTIONS OF 07.9A, OF THE FSAR FOR THE ORGANIZATIONS 98.15 DETAILS.
INVOLVED. TBESE ACTIVITIES INCLUDE BUT ARE NOT LIMITED TO 22 ASPECTS AS TRET APPLT TO SAFETT RELATED STRUCTURES, EQUIPMENT, AND STSTEMS.
OPERATIONS QA STARTUP AND POWER 07 zoet saan 17. 2. 2 PROGRAM ASCENSION TESTING WILL BE CONTROLLED BT WRITTEN TEST PROCEDURES, REVIEWEb FOR ADEQUATE CONTROL TO ENSURE QUALITT CERTAIN TEST REQUIREMENTS MUST BE SUCCESSFULLT COMPLETED, DOCUMENTED, AND REVIEWED BEFORE CONTINUING.
3 DESIGN CRANGE WRITTEN PROCEDURES 07 2109 FSAR 17. 2.
4 ,
CONTROL WILL IDENTIFT THE POSITION OR
' ORGANIZATIONS RESPONSIBLE FOR DESIGN VERIFICATION AND DEFINE THEIR AUTHORITT
( AND RESPONSIBILITT.
(?
i
Page No. 98 12/02/85 TABLE 3.2-I COMMITMENTS FOR PLANT
===-==============r =============-
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=====-============
COMMITMENT DOCUMENT / FEATURE TITLE MODULE REMARES NUMBER COMMITMENT COMMITMENT SOURCE SECTION SUBJECT
== =;==== === ================ ======= ===e = ===== - =====e============== ================ =- === ======= ======
2111 FSAR 17. 2. 3 DESIGN CHANGE DESIGN CHANGES MADE TO 07 SEE SECTION 17.2.3 CONTROL VEGP ARE ACCOMPLISHED OF THE FSAR FOR IN A PLANNED AND DETAILS.
CONTROLLED MANNER IN ACCORDANCE WITH WRITTEN, APPROVED PROCEDURES. THE PROCEDURES INCLUDE 7 PROVISIONS AS NECESSARY.
2115 FSAR 17. 2. 3 DESIGN CHANGE RG 1.64, R/2 QUALITY 05,07 CONFORMANCE IS CONTROL ASSURANCE DISCUSSED IN SECTION REQUIREMENTS FOR 1.9.64.2 OF THE THE DESIGN OF FSAR.
NUrtPAR POWEP PLANTS 2118 FSAR 17. 2. 3 DESIGN CHANGE THE ADEQUACT OF DESIGN 07 SEE SECTION 17.2.3 CONTROL CHANGES SRALL BE OF THE FSAR FOR VERIFIED BT DETAILS.
PERFORhANCE OF DESIGN REVIEWS, ALTERNATE CALCULATIONS, OR QUALIFICATION TESTING.
SEVEN CONTROL MEASURES ARE LISTED.
2119 FSAR 17, 2. 3 DESIGN CHANGE QUALITY ASSURANCE 05.07 CONFORMANCE IS CONTROL REQUIREMENTS FOR DISCUSSED IN SECTION DESIGN CHANGE CONTROL 1.9.64.2 OF TFE ARE CONSISTENT WITH FSAR.
POSITION OF REGULATORY GUIDE 1.64, OA REQUIREMENTS FOR THE DESIGN OF NUCLEAR
~ POWER PLANTS.
2120 FSAR 17. 2. 3 DESIGN CHANGE PROCEDURES WILL 02,07, METHODS INCLUDE CONTROL REQUIRE TRAT PERSONNEL 9A.9B PROCEDURE REVISION ARE MADE AWARE OF TRAINING, NIGHT DESIGN CRANGES OR ORDERS. AND MODIFICATIONS WHICH STRUCTURED TRAINING.
AFFECT THE PERFORMANCE OF TREIR DUTIES.
O O O O O O O
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T Page No. 99
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======================
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DOCUMENT /FRATURE TITLE MODULE REMARES NUMBER COMMITMENT COMMITMENT COMMITMENT SOURCE SECTION SUBJECT
== ========== ==============s= ==================== ====================== ================ ====== ==============
DESIGN CHANGE ANT ERRORS OR 02.05, 2842 FSAR 17. 2. 3 07,9A, CONTROL DEFICIENCIES FOUND IN THE DESIGN PROCESS OR 99 THE DESIGN ITSELF ARE DOCUMENTED AND CORRECTIVE ACTION TAREN.
PROCUREMENT DOCUMENT TO SATISFY TRE QA 05,07 SEE SECTION 17.2.4 2121 FSAR 17. 2. 4 OF THE FSAR FOR CONTROL REQUIREMENTS FOR PROCUREMENT DOCUMENT DETAILS.
CONTROL 10 SPECIFIC REQUIREMENTS SHALL BE IMPLEMENTED.
PROCUREMENT DOCUMENT RG 1.123 R/l QUALITY 05,07 CONFORMANCE IS 2123 FSAR 17. 2. 4 DISCUSSED IN SECTION CONTROL ASSURANCE REQUIREMENTS FOR 1.9.123.2 0F THE CONTROL OF FSAR.
PROCUREMENT OF ITEMS AND SERVICES FOR NUCLEAR POWER PLANTS
- 17. 4 PROCUREMENT DOCUMENT QUALITY REQUIREMENTS 05.07 CONFORMANCE IS 4 2133 FSAR 2.
DISCUSSED IN SECTION CONTROL FOR CONTROL OF DOCUMENTS FOR SAFETT 1.9.123.2 0F THE RELATED COMPONENTS, FSAR.
MATERIALS AND SERVICES ARE CONSISTENT WITR RG 1.123.
INSTRUCTIONS, RG 1.30, AUGUST 1972 QUALITY 05,07 CONFORMANCE IS 2137 FSAR 17. 2. 5 DISCUSSED IN SECTION PROCEDURES, AND ASSURANCE DRAWINGS REQUIREMENTS FOR 1.9.30.2 0F TRE TRE FSAR.
INSTALLATION, INSPECTION AND TESTING OF INSTRUMENTS AND l ELECTRICAL 2
EQUIPMENT 4
i (?
a
Page No. 100 12/02/85 COMMITMENTS FOR PLANT TABLE 3.2-1
===---========= =================_
OPERATIONS AND SUPPORT
-===-====.--=- =- =~-
TITLE MODULE REMARKS COMMITMENT COMMITMENT COMMITMENT DOCUMENT / FEATURE NUMBER SOURCE SECTION SUBJECT ====== -====s===== ========
r-==============
====== == ========== ========= === =, ===,==============,= ====== ==,== ====. =~
INSTRUCTIONS, ACTIVITIES AFFECTING 02,05, 2141 FSAR 17. 2. 5 07,9A, PROCEDURES, AND QUALITY SHALL BE PRESCRIBED BY AND 98,15 DRAWINGS ACCOMPLISHED WITH DOCUMENTED INSTRUCTIONS, PROCEDURES OR DRAWINGS.
INSTRUCTIONS, PROCEDURES SHALL 02.05, 2142 FSAR 17. 2. 5 07,9A, PROCEDURES, AND CONTAIN QUALITATIVE AND QUANTATIVE 98,15 DRAWINGS ACCEPTANCE CRITERIA FOR DETERMINING THAT IMPORTANT ACTIVITIES HAVE BREN SATISFACTORILT ACCOMPLISHED.
INSTRUCTIONS. THE REQUIREMENTS 02.05, 2145 FSAR 17. 2. 5 07,9A, PROCEDURES, AND DEALING WITH DRAWINGS INSTRUCTIONS, 98,15 PROCEDURES. OR DRAWINGS ARE CONSISTENT WITH THE
, PROVISIONS OF REG GUIDES 1.30, 1.33, AND 1.116.
INSTRUCTIONS, RG 1.33, R/2 QUALITY 02.05, CONFORMANCE IS 2844 FSAR 17. 2. 5 07,9A, DISCUSSED IN SECTION PROCEDURES, AND ASSURANCE DRAWINGS PROGRAM 98,15 1.9.33.2 OF THE REQUIREMENTS FSAR.
(OPERATION)
- 17. INSTRUCTIONS, RG 1.116 R/O-R QUALITY 05,07 CONFORMANCE IS 2845 FSAR 2. 5 DISCUSSED IN SECTION PROCEDURES, AND ASSURANCE DRAWINGS REQUIREMENTS FOR 1.9.116.2 OF THE INSTALLATION, FSAR.
INSPECTION AND TESTING OF MECHANICAL EQUIPMENT AND SYSTEMS O O O O O O O
O O O '
o o o Page No. 101 -
12/02/85 TABLE 3.2-1 COMMITMENTS FOR PLANT
===: =============r============re:
OPERATIONS AND SUPPORT
e===== =======
DOCUMENT / FEATURE TITLE MODULE REMARES NUMBER COMMITMENT COMMITMENT COMMITMENT SOURCE SECTION SUBJECT
== ========== ================ =============: ===== =e= ========e========= ==-============= ====== ==============
2135 FSAR 17. 2. 5. 1 INSTRUCTIONS. WEITTEM ADMINISTRATTVE 02.05 PROCEDURES, AND PROCEDURES WILL ENst.RE 07.9A.
DRAWINGS PROPER CONTROL OF 98.15 INSTRUCTIONS SUCH AS TEMPORART PROCEDURE CHANGES AND STANDING ORDERS. THESE INSTRUCTIONS WILL BE OF LIMITED SCOPE AND BE ISSUED FOR LIMITED TIME PERIODS.
2138 FSAR 17. 2. 5. 1 INSTRUCTIONS. CONTRACTOR QAP SHALL 05.07 PROCEDURES. AND BE REVIEWED AND DRAWINGS APPROVED IN ACCORDANCE WITH OQAP 2140 FSAR 17. 2. 5. 1 INSTRUCTIONS. PLANT DRAWING CHANGES 05.07 PROCEDURES. AND WILL BE AS A RESULT OF DRAWINGS DESIGN CHANGE OR AS-BUILTS WHICH WILL BE CONTROLLED BY WRITTEN PROCEDURES.
2148 FSAR 17. 2. 5. 1 INSTRUCTIONS. PROCEDURE MANUALS WILL 05.07 PROCEDURES. AND CONTAIN PROCEDURES 9A.98 DRAWINGS WHICH SHALL BE USED 15 FOR PERIODIC TESTS AND CALIBRATIONS, SPECIAL PROCESSPM.
MODIFICATIONS.
MAINTENANCE. AND OTHER ACTIVITIES ON SAFETY RELATED SYSTEMS.
EQUIPMENT. OR STRUCTURES.
2151 FSAR 17. 2. 6 DOCUMENT CONTROL ELEVEN CATEGORIES OF 02.05 SEE SECTION 17.2.6 DOCUMENTS ARE TO BE 07.9A. OF THE FS4R FOR CONTROLLED. 98.15 DETAILS.
(
C
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======================
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--: ===== - =,=r
TITLE MODULE REMARKS NUMBER COMMITMENT COMMITMENT COMMITMENT DOCUMENT / FEATURE SOURCE SECTION SUBJECT =====e==============
e============== =re==
:= ====e===== ================ ==================== ================
DOCUMENT CONTROL THE REQUIREMENTS FOR 02,05, 2162 FSAR 17, 2. 6 07.9A, DOCUMENT CONTROL ARE CONSISTENT WITH THE 98,15 POSITION OF REG GUIDE 1.33.
6 DOCUMENT CONTROL RG 1.33, R/2 QUALITY 02,05 CONFORMANCE IS 2163 FSAR 17. 2.
07,9A, DISCUSSED IN SECTION ASSURANCE PROGRAM 98,15 1.9.33.2 OF THE REOUIREMENTS FSAR.
(OPERATION) 6 DOCUMENT CONTROL FIVE PROVISIONS FOR 02,05, SEE SECTION 17.2.6 2164 FSAR 17. 2.
DOCUMENT CONTROL WHICH '07,9A, OF THE FSAR FOR ARE INCLUDED ARE 9B,15 DETAILS.
LISTED.
DOCUMENT CONTROL THE RESPONSIBLE 02,05 2846 FSAR 17. 2. 6 07,9A.
SUPERVISORS ARE RESPONSIBLE FOR 98.15 ENSURING THAT THE LATEST REVISION OF APPROPRIATE DOCUMENTS ARE BRING USED TO PERFORM SAFETY RELATED ACTIVITIES.
17, 6 DOCUMENT CONTROL DOCUMENTS CONTROLLED 05,07 2847 FSAR 2.
BY OFFSITE ORGANIZATIONS WILL RECEIVE CONTROL COMPARABLE TO THAT OF SITE DOCUMENTS.
2168 FSAR 17. 2. 7 CONTROL OF PURCHASED RG 1.123 R/l QUALITY 05.07 CONFORMANCE IS MATERIAL, EQUIPMENT, ASSURANCE DISCUSSED IN SECTION AND SERVICES REQUIREMENTS FOR 1.9.123.2 OF THE
' CONTROL OF FSAR.
PROCUREMENT OF
~ ITEMS AND
'C* SERVICES FOR I NUCLEAR PLANTS
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e l
ll 9 9 G O 9
7' 4 O
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Page No. 103 3 12/02/05 T A R I. E 3 . 2 1 COMMITMENTS FOR PLANT
==-==================
OPERATIONS AND SUPPORT
===================: 2= ,
COMMITMENT DOCUMENT / FEATURE TITLE MODULE REMARES NUMBER COMMITMENT COMMITMENT SOURCE SECTION SUBJECT ====== ========e===========
== ========== ================ ==================== ==================== - e=========
CONTROL OF PURCHASED RG 1.38, R/2 QUALITY 05,07 CONFORMANCE IS 2169 FSAR 17. 2. 7 ASSURANCE DISCUSSED IN SECTION MATERIAL, F.QUIPMENT, AND SERVICES REQUIREMENTS FOR 1.9.38.2 OF THE PACEAGING, FSAR.
SHIPPING, RECEIVING, STORAGE AND HANDLING OF ITEMS FOR WATER-COOLED NUCLEAR POWER PLANTS 05,07 2170 FSAR 17, 2. 7 CONTROL OF PURCHASED THE REQUIREMENTS FOR MATERIAL, EQUIPMENT, THE CONTROL OF AND SERVICES PURCHASED MATERIALS, EQUIPMENT AND SERVICES ARE CONSISTENT WITH THE POSITIONS OF REG GUIDE 1.38 AND REG GUIDE 1.123.
CONTROL OF PURCHASED PLANT PROCEDURES WILL 05,07 2177 FSAR 17. 2. 7. I MATERIAL, EQUIPMENT, REQUIRE THAT DOCUMENTS AND SERVICES SPECIFY DOCUMENTATION IDENTIFYING THE PURCHASED ITEM AND SPECIFIC PROCUREMENT REQUIREMENTS (E.G.,
CODES. STANDARDS, AND SPECIFICATIONS) MRT BY THE ITEM.
2178 FSAR 17. 2. 7. 1 CONTROL OF PURCHASED PLANT PROCEDURES 05.07 MATERIAL, EQUIPMENT, REQUIRE DOCUMENTS AND SERVICES SPECIFY DOCUMENTATION IDENTIFYING ANY PROCUREMENT REQUIREMENTS THAT HAVE
' I NOT BREN MET.
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======================
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==========
NUMBER COMMITMENT COMMITMENT COMMITMENT DOCUMENT /FEkTURE TITLE MODULE REMARES SOURCE SECTION SUBJECT
== ======e=== ==========e===== ============e======= ===e================== == ============= ====== ==============
21T9 FSAR 17. 2. 7. I CONTROL OF PURCHASED PLANT PROCEDURES 05.07 MATERIAL, EQUIPMENT. REQUIRE DOCUMENTS AND SERVICES SPECIFT A DESCRIPTION OF THOSE NONCONFORMANCES FROM THE PROCUREM?NT REQUIREMENTS DISPOSITIONED " ACCEPT AS IS" OR " REPAIR."
2183 FSAR 17. 2. 7. 3 CONTROL OF PURCHASED SOR COMMERCIAL ITEMS 05.07 MATERIAL. EQUIPMENT. WHERE SPECIFIC QA AND SERVICES CONT. APPROP. FOR NUCLEAR APPLICATIONS CANNOT BE IMPOSED IN A PRACTICAL MANNER, SPECIAL QUALITT VERIF.
REQUIRE. SRALL BE ESTAB. TO PROVIDE NECESSARY ASSURANCE OF ITEM.
21R9 FSAR 17. 2. 7. 3 CONTROL OF PURCHASED RECEIPT INSPECTION AT 05,07 MATERIAL, EQUIPMENT, VEGP IS PERFORMED IN AND SERVICES ACCORDANCE WITR WRITTEN PROCEDURE TO ENSURE TRAT MATERIALS.
EQUIPMENT. OR COMPONENTS ARE PROPERLY I?ENTIFIED AND TRACEABLE TO ASSOCIATED DOCUMENTATION.
2190 FSAR 17. 2. 7. 3 CONTROL OF PURCHASED RECEIPT INSPECTION 05,07 MATERIAL, EQUIPMENT, PROCEDURES REQUIRE AND SERVICES INSPECTIONS, TESTS, AND OTRER SPECIFIED RECORDS ATTESTING TO ACCEPTAkrs OF MATERIALS, EQUIPMENT AND COMPONENTS ARE COMPLETED AND AVAILABLE PRIOR TO INPTALLATION.
O O O O O O O
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Page No. 105 ,
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% 12/02/85 COMMITMENTS FOR PLANT TABLE 3.2-1
"* ============================== ===
OPERATIONS AND SUPPORT
r:=== e=======
DOCUMENT / FEATURE TITLa MODULE REMARES i NUMBER COMMITMENT COMMITMENT COMMITMENT SOURCE SECTION SUBJECT
==========e====e ================ ====== ==============
====== == =========e ==============e= ===================- r 2191 FSAR 17. 2. 7. 3 CONTROL OF PURCHASED RECEIPT INSPECTION 05.07 i l
MATERIAL, EQUIPMEN
T. PROCEDURE
S REQUIRE AND SERVICES MATERIALS. EQUIPMENT AND COMPJMENTS ARE INSPECTED AND JUDGED ACCEPTABLE IN ACCORDANCE WITR PREDETERMINED INSPECTION INSTRUCTIONS PRIOR TO INSTALLATION AND USE.
2192 FSAR 17. 2. 7. 3 CONTROL OF PURCRASED ITEMS ACCEPTED AND 05.07 '
MATERIAL, EQUIPMENT, RELEASED ARE AND SERVICES IDENTIFIED AS TO TREIR INSPECTION STATUS PRIOR TO SENDING TREM TO A CONTROLLED STORAGE AREA OR RELEASING TREM FOR '
INSTALLATION OR r FURTHER WORK.
+
2193 FSAR 17. 2. 7. 3 CONTROL OF PURCRASED MONCONFORMING ITEMS 05.07 MATERIAL. EQUIPMENT. ARE IDENTIFIED. !
AND SERVICES CONTROLLED AND SEGREGATED UNTIL ,
PROPER DISPOSITION IS MADE.
2197 FSAR 17. 2. 8 IDENTIFICATION AND PROCEDURES WILL 05.07 CONTROL OF MATERIAL, PROVIDE VERIFICATION .
PARTS. AND OF ITEM IDENTIFICATION COMPONENTS CONSISTANT WITH THE INVENTORY CONTROL SYSTEM AND TRACEABLE TO DOCUMENTATION WRICR IDENTIFIES THE PROPER
- USES OR APPLICATIONS OF THE ITEM.
P
Page No. 106 12/02/85 TABLF 3.2-1 COMMITMENTS FOR PLANT
========= ==== ====- ==========-
OPFRATIONS AND SUPPORT
- -==--=== === - =z=-
COMMITMENT COMMITMENT DOCUMENT /FFATURE TITLE MODULE REMARKS NUMBER COMMITMENT SOURCE SECTION SUBJECT
,= -==- - -,= --,= ==========- =- ============ =-=- --========= ====-===-- ===========~e == ====== --=-,======= ,======
==- =e 2199 FSAR 17. 2. 8 IDENTIFICATION AND MATERIALS, PARTS, AND 05.07, CONTROL OF MATENIAL, COMPONENTS WILL BE 9A,99 PARTS, AND IDENTIFIED AND COMPONENTS CONTROLLED TO PREVENT USE OF INCORRECT OR DEFECTIVE ITEMS.
LOCATION AND METHOD OF IDENTIFICATION SRALL NOT EFFECT QUALITT OR FUNCTION OF ITEM.
2200 FSAR 17. 2. 8 IDENTIFICATION AND OA REQUIREMENTS FOR 05.07 CONTROL OF MATERIAL, IDENTIFICATION AND 9A,9B PARTS, AND CONTROL OF COMPONENTS SAFETT-RELATED MATRRIALS PARTS, COMPONENTS AND SPARE PARTS ARE CONSISTENT WITH THE POSITION ON REG GUIDES 1.33 AND 1.38.
2201 FSAR IT. 2. 8 IDENT!FICATION AND RG 1.38 R/2 QUALITT 05,07 CONFORMANCE IS CONTROL OF MATERIAL, ASSURANCE DISCtfSSED IN SECTION PARTS, AND REQUIREMENTS FOR 1.9.38.2 OF THE COMPONENTS PACKAGING, FSAR.
SHIPPING, RECEIVING, STORAGE AND HANDLING OF ITEMS FOR WATER-COOLED NUCLEAR POWER PLANTS 2202 FSAR 17_ 0. 8 IDENTIFICATION AND RG 1.33 R/2 OUALITT 05,07, CONFORMANCE IS CONTROL OF MATERIAL, ASSURANCE 9A,9B DISCUSSED IN SECTION PAhTS, AND PROGRAM 1.9.33.2 OF THE COMPONENTS REQUIREMENTS FSAR.
(OPERATION)
O O O O O O O
-. . . , _ . . , _ ._ _ _ ,__m . _ _ . , _ _ , _ , , _ _ _ _
~
O O O O Page No. 107 12/02/85 TABLE 3.2-1 COMMITMENTS FOR PLANT
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DOCUMENT / FEATURE TITLE MODITLE REMARKS 4 tJM B E p enum1TMFMT COMMITMENT COMMITMENT SOURCE SECTION SUBJECT =======e============
r = = r .- == ========== ================ ==================== ====================== ================ =====
PROCEDURES FOR 05,07 2203 FSAR 17. 2. 8 IDENTIFICATION AND CONTROL OF MATERIAL. IDENTIFICATION AND PARTS, AND CONTROL OF MATERIALS, COMPONENTS CONSUMABLES, PARTS 3 AND COMPONENTS REQUIRE VERIFICATION THAT t ITEMS RECEIVEb ARE PROPERLT IDENTIFIED BT DOCUMENTATION OR MANUFACTURERS CATALOG.
2204 FSAR 17. 2. 8 IDENTIFICATION AND OC DEPARTMENT, WRICH 05.07 CONTROL OF MATERIAL, DOES RECEIPT PARTS, AND INSPECTIONS, AND COMPONENTS WAREROUSE PERSONNEL, NHO ARE RESPONSIBLE FOR STORING AND RELEASING ITEMS, ENSURE VERIFICATION AND DOCUMENTATION OF CORRECT ITEM IDENTIFICATION.
IDENTIFICATION AND ADMINISTRATIVE 05,07 2205 FSAR 17. 2. 8 9A,9B CONTROL OF MATERIAL, PROCEDURES SHALL DESCRIBE PLANT STAFF PARTS, AND COMPONENTS ACTIVITIES AND RESPONSIBILITIES FOR IDRNTIFTING AND CONTR0 LING MATERIALS, PARTS AND COMPONENTS.
ASSURANCE 3B ' DISCUSSED IN SECTION PROCESSES REQUIREMENTS FOR I.9.30'0F THE FSAR. j THE INSTALLATION, INSPECTION AND TESTING OF
' INSTRUMENTS AND
+ ELECTRICAL EQUIPMENT.
i c
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e==-===-===================
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~===== = =============
NUMBER COMMITMENT COMMITMENT COMMITMENT DOCUMENT /FEATf1RE TITLE MODULE REMARES SOURCE SECTION SURJECT
======e========- =~= ======.=----,-= ===~== ==- = === === == ====== ===================e
== === == === ==========
2207 FSAR 17. 2. 9 CONTROL or sPhtiat RG 1.37, MARCH 1973 OUALITT 05,07 CONFORMANcF IS PROCESSES ASSURANCE 98 DISCUSSED IN REQUIREMENTS FOR SECTIONS 14.2.17.1 CLEANING FLUID AND 1.9.37.2 OF THE SYSTEMS AND FSAR ASSOCIATED COMPONENTS OF WATER COOLED NUCLEAR POWER PLANTS 2208 FSAR 17. 2. 9 CONTROL OF SPECIAL PROCEDURES SHALL BE 05,07 THESE PROCEDURES PROCESSES DEVELOPED WHICH 9B WILL ENSURE DELINEATE THE RECORDING EVIDENCE REQUIREMENTS FOR OF ACCEPTABLE SPECIAL PROCESSES. ACCOMPLISHMENT USING THET WILL SPECIFY THE QUALIFIED PROCEDURES RESPONSIBILITY OF QC AND PERSONNEL AND DEPARTMENT TO ASSIGN SUITABLE AND HOLD POINTS AND CONTROLLED PERFORM NONDESTRUCTIVE EQUIPMENT.
TESTS.
2851 FSAR 17, 2. 9 CONTROL OF SPECIAL TRE REQUIREMENTS FOR 02,05, PROCESSES CONTROL OF SPECIAL 07,9B PROCESSES ARE CONSISTENT WITH THE POSITIONS OF REGULATORT GUIDES 1.30, 1.37 AND 1.5R.
2853 FSAR 17. 2. 9 CONTROL OF SPECIAL QUALIFICATION OF 05,07, PROCESSES SPECIAL PROCESSES. 98 EQUIPMENT, AND PERSONNEL IS THE RESPONSIBILITY OF THE SUPERINTENDENTS AND SUPERVISORS FOR ACTIVITIES UNDER THEIR PURVIEW.
O O O O O O O
O O i -
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====,=,==============,=====z:-=
' OPERATIONS AND SUPPORT
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COMMITMENT COMMITMENT DOCUMENT / FEATURE TITLE MODULE REMARES NUMBER COMMITMENT a SOURCE SECTION SUBJECT ee===========e=, -e=,-r====er ===--,= =rer=======--e==,=- == : ============== ====r ==================== l e-==== == e=====e===
INSPECTIONS IF SPECIFIED 05,07 IF AT TRESE 2215 FSAR 17. 2. 10 CHECEPOINTS THE i INSPECTION WITNESS POINTS REQUIRING ACTIVITT IS FOUND 70 WITNESSING OR BE UNSATISFACTORY, INSPECTING BEYOND FURT3UR PROCESSING WHICH WORE IS NOT TO OF TRE ACTIVITY IS PROCBED WITHOUT SUSPENDED UNTIL THE i INSPECTOR APPROVAL ARE PROBLEM IS RESOLVED, MECESSARY, SPECIFIC HOLD POINTS WILL BE IN WORE PROCEDURE.
- 17. TEST CONTROL TEST PROCEDURES AND 05.07, SEE SECTION 17.2.11 2230 FSAR 2. 11 9A,9B 0F THE FSAR FOR i RECORDS SHALL SATISFY THE STATED DETAILS.
REQUIREMENTS.
2231 FSAR 17. 2. 11 TEST CONTROL RG 1.30 AUGUST 1972 QUALITY 05.07 CONFORMANCE IS ASSURANCE DISCUSSED IN SECTION REQUIREMENTS FOR 1.9.30.2 0F THE THE FSAR.
INSTALLATION, INSPECTION AND
! TESTING OF I INSTRUMENTS AND j BLECTRICAL EQUIPMENT 05.07 CONFORMANCE IS I 2232 FSAR 17. 2. 11 TEST CONTROL RG 1.116, R/O-R QUALITY d ASSURANCE 9B DISCUSSED IN SECTION ,
REQUIREMENTS FOR 1.9.116.2 0F THE f INSTALLATION, FSAR.
- INSPECTION AND TESTING OF ,
t i MECHANICAL EQUIPMENT AND SYSTEMS 4
TEST CONTROL SAFETY RELATED TESTS, 02,05, l 2858 FSAR 17, 2. 11 07,9A, SURVEILLANCE TESTS, TESTING FOLLOWING 99 MODIFICATIONS, RECEIVING INSPECTION 3 TESTS, AND TESTS WITH
!f SPECIAL EQUIPMENT ARE 3
~
CONSISTENT WITH THE i j POSITIONS OF
, - REGULATORY GUIDES i 1.30, 1.33, 1.58, AND 4
. - - . . _ ---- ,, . . . - , - . . , , - . ._a,_ - ...n.~,,.w.,,- - - - , , _ . - - . . . , , _ _ - - - - - - _ _ - - - - - _ . _ _ - . _ _ _
l.16n.
Page No. 110 12/02/85 TABLE 3.2-1 COMMITMENTS FOR PLANT
==== -========= =-======== _===-r-OPEHATIONS AND SUPPOHT
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TITLE MODULE REMARKS COMMITMENT COMMITMENT DOCUMENT / FEATURE NUMBER COMMITMENT SOURCE SECTION SUBJECT
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RG 1.33, R/2 QUALITT 02,05, CONFORMANCE IS 2R59 FSAR 17. 2. Il TEST CONTROL 07.9A, DISCUSSED IN SECTION ASSURANCE PROGRAM 9B 1.9.33.2 OF THE REQU f 'IEMENTS FSAR.
(OPERATION) 05,07, 2236 FSAR 17. 2. 12 CONTROL OF MEASURING REF STDS WILL HAVE AN 9A,9B AND TEST EQUIPMENT EHROR OF NO MORE THAN ONE-FOURTH OF THE TOLERANCE OF THE M&TE BEING CALIBRATED. A GREATER UNCERTAINTY WILL BE ACCEPTABLE WR8N APPROVED BY THE R E S a'ON S I B L E SUPERINTENDENT OP HIGHER MANAGER.
CONTROL OF MEASURING COMPARISON STDS. USED 05,07, 2237 FSAR 17. 2. 12 AND TEST EQUIPMENT IN CALIB. OF REFERENCE 9A,98 STDS. WILL HAVE A TOLERANCE EQUAL TO OR SMALLER THAN THE REFERENCE STD. AND WILL BE TRACEABLE TO THE STD. MOUSED IN THE NBS AND SUPPORTED BT CERTIF. REPORTS AND DATA SREETS.
CONTROL OF MEASURING RG 1.33 R/2 QUALITY 05.07, CONFORMANCE IS 2211 FSAR 17. 2. 12 AND TEST EQUIPMENT ASSURANCE 9A,98 DISCUSSED IN SECTION PROGRAM l.9.33.2 OF THE REQUIREMENTS 6SAR.
(OPERATION)
CONTROL OF MEASURING MEASURES FOR THE 05,07, 2247 FSAR 17. 2. 12 AND TEST EQUIPMENT CONTHOL OF MEASUNINb 9A,98 AND TEST EQUIPMENT ARE CONSISTENT WITH THE POSITION OF REG. GUIDE 1.33.
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O c& Page No. 111 12/02/H5 TABLE 3.2 1 COMMITMENTS FOR PLANT
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TITLE MODULE REMARKS COMMITMFNT COMMITMENT DOCUMENT / FEATURE NUMBER COMMITMENT SOURCE SECTION SUBJECT ==-============= ===e== ====================
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05,07, 2861 FSAR 17. 2. 12 CONTROL OF MEASURING THE SUPERINTENDENT OF 9A,98 AND TEST EQUIPMENT MAINTENANCE IS RESPONSIBLE FOR DEVELOPING. APPRO"ING, AND IMPLEMENTING PROCEDURES AND INSTRUCTIONS TO ESTABLISH A CONTROL AND CALIBRATION PROGRAM. HE APPROVES CALIBRATION PROCEDURES.
05.07, 2245 FSAR 17. 2. 12.A CONTROL OF MEASURING PROCEDURES SHALL BE 9A,9B AND TEST EQUIPMENT BSTABLISHED WHICH DESCRIBE CALIB. TECH.,
CALIB. FREQ. MAINT.
AND CONTR. OF M&TB &
NDT EQPT. TO BE USED IN MEASUREMENT &
INSPECTION OF SAFETY-RELATED COMPONENTS, SYSTEMS, &
STRUCTURES.
05,07 2242 FSAR 17. 2. 12.B CONTROL OF MEASURING MEASUREMENT AND TEST 9A,98 AND TEST EQUIPMENT EQUIPMENT SHALL BE UNIQUELY IDENTIFIED AND HAVE TRACEABILITY TO CALIBRATION TEST DATA.
05,07, 2239 FSAR 17. 2. 12.C CONTROL OF MEASURIND M&TE SHALL BE CALIB. 9A,98 AND TEST EQUIPMENT AND MAINT. AT SPECIFIC INTERVALS, BASED ON THE REQUIRED ACCURACY, PURPOSE, DEGREE OF USAGE, STABILITY
- CMARACT. AND OTHER CONDITIONS AFFECTING THE MEASUREMENT.
f 1
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,== == =========, ==========
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COMMITMENT DOCUMENT / FEATURE TITLE MODULE REMARKS NUMBER COMMITMENT COMMITMENT SOURCE SECTION SUBJECT
== =====-==== =,============= ==================== ====================== ==== ==========x ====== ==============
CONTHOL OF MEASURING MEASURING AND TEST 05.07, 2244 FSAR 17. 2. 12.D 9A,9B AND TEST EQUIPMENT EQUIPMENT SHALL BE CALIBRATED ON OR BEFORE THE DESIGNATED DUE DATE OR REMOVED FROM SERVICE UNTIL CORRECTIVE ACTION IS TAEEN.
CONTROL OF MEASURING WHEN M&TE IS FOUND OUT 05,07, 2233 FSAR 17, 2. 12.E 9A,9R AND TEST EQUIPMENT OF CALIBRATION AN INVESTIGATION SHALL BE CONDUCTED AND DOCUMENTED TO DETERMINE VALIDITY OF PREVIOUS INSPECTIONS PERFORMED AND ACCEPTABILITY OF THOSE ITEMS PREV. INSPECTED.
- 17. 12.E CONTROL OF MEASURING PROCEDURES ARE 05,07, 2234 FSAR 2.
AND TEST EQUIPMENT ESTABLISHED TO INSURE 9A.98 TRAT MEASUREMENTS MADE WITH M&TE FOUND TO BE OUT OF CALIBRATION WILL BE EVALUATED TO DETERMINE THE NEED FOR REINSPECTION.
- 17. 12 F CONTROL OF ME ASURING CALIB. INST. SHALL 05,07, 2235 FSAR 2.
AND TEST EQUIPMENT HAVE KNOWN, VALID 9A.9B RELATIONSHIPS TO A NATIONAL STANDARD. IF NO MATIONAL STANDARD EXISTS. BASIS OF CALIBRATION WILL BE nOCUMENTED AND APPROVED BY RESPONSIBLE SUPER. OR A HIGHER LEVEL OF MGT.
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[3 Pete No. 113 12/02/HS TABLE 3.2-1 COMMITMENTS FOR PLANT
-====,= ==
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OPERATIONS AND SUPPORT
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CONTROL OF MEASURING SECORDS MILL BE 05,07, 2240 FSAR 17. 2. 12.G 9A,9B AND TEST EQUIPMENT MAINTAINED NHICH INDICATE THE COMPLETE STATUS OF ALL ITEMS UNDER THE CALIBRATION STSTEM.
CONTROL OF MEASURING CALIB. FAC. USED FOR 05,07, 2246 FSAR 17. 2. 12.H 9A,98 AND TEST EQUIPMENT CALIB. SENSITIVE AND
'CLOSE TOLERANCE M&TE SHALL PROVIDE AN ENVIRON. THAT IS SUFFICIENTLY -
CONTROLLED TO ALLON MEASURING DEV. TO BE EVALUATED AND CALIB.
TO ITS REQ. ACCURACT.
HANDLING. STORING, RG 1.33 R/2 QUALITT 05,07 CONFORMANCE IS 2251 FSAR 17. 2. 13 DISCUSSFD IN SECTION AND SHIPPING ASSURANCE PROGRAM 1.9.33.2 0F THE REQUIREMENTS TSAR.
(OPERATION)
HANDLING, STORING, RG 1.38, R/2 QUALITT 05,07 CONFORMANCE IS ,
2252 FSAR 17. 2. 13 DISCUSSED IN SECTION AND SHIPPING ASSURANCE REQUIREMENTS FOR 1.9.38.2 0F THE PACEAGING, FSAR.
SHIPPING, RECEIVING.
STORAGE AND HANDLING OF ITEMS FOR WATER-COOLED 1
NUCLEAR PONER PLANTS HANDLING. STORING, REQUIREMENTS FOR THE 05,07 2862 FSAR 17. 2. 13 AND SHIPPING CONTROL, HANDsING,
' STORING, SHIPPING, CLEANING. AND PRESERVATION CF MATERIALS AND EQUIPMENT ARE CONSISTENT.WITH PROVISIONS OF REGULATORT GUIDES 1.33 4
AND 1.38.
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Page No. I]4 12/02/85 TABLE 3.2-1 COMMITMENTS FOR PLANT
===== ==== ==================-
OPERATIONS AND SUPPORT
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TITLE MODULE REMARKS COMMITMENT COMMITMENT DOCUMENT / FEATURE NUMBER COMMITMENT SOURCE SECTION SUBJECT ================ ====== ============= ======
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05,07
- 17. 2. 13.A HANDLING, STONING, INSPECTION OF ITEMS BY 224R FSAR AND SHIPPING QC AND WAREHOUSE PERSONNEL WILL BE MADE PRIOR TO USE AT THE PLANT SITE. AND ROUTINE SURVEILL. WILL BE MADE DURING STORAGE.
HANDLING. STORING, FOR CRITICAL, 05,07 2249 FSAR 17. 2 13.B AND SHIPPING SENSITIVE, PERISHABLE, OR HIGH VALUE ITEMS, SPECIFIC WRITTEN PROCEDURES FOR HANDLING, STORING, PACKING, SHIPPING AND PRESERVING ARE USED.
HANDLING, STORING, SPECIAL HANDLING TOOLS 05.07 2250 FS 4R 17. 2. 13.C AND SHIPPING AND EQUIPMENT ARE INSPECTED AND TESTED IN ACCORDANCE WITH WRITTEN PROCEDURES TO VERIFT THAT THET ARE ADEQUATELT MAINTAINED.
INSPECTION, TESTING, RG 1.33 R/2 QUALITT 05,07, CONFORMANCE IS 2255 FSAR 17. 2. 14 ASSURANCE 9A,98 DISCUSSED IN SECTION AND OPERATING STATUS PROGRAM 1.9.33.2 OF THE REQUIREMENTS FSAR.
(OPERATION)
INSPECTION, TESTING. THE REQUIREMENTS FOR 05.07, 2863 FSAR 17. 2. 14 9A,9B AND OPERATING STATUS IDENTIFICATION AND CONTROL OF THE INSPECTION, TESTING, AND OPERATING STATUS OF SAFETT RELATED STRUCTUR25 STSTEMS, AND COMPONENTS ARE CONSISTENT WITH THE POSITION OF REGULATORY GUIDE I.33.
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== =-:.=: c====================-= -
OPFRATIONS AND SUPPORT
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COMMITMENT DOCUMENT / FEATURE TITLE MODULE REMARES NUMBER COMMITMENT COMMITMENT SOURCE SECTION SUBJECT
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I 2253 FSAR 17. 2. 14.A INSPECTION. TESTIN
G. PROCEDURE
S SHALL BE 05.07 AND OPERATING STATUS ESTABLISHED TO CONTROL 9A.9B THE USE OF WELDING STAMPS AND INSPECTION / STATUS INDICATORS. INCLUDING THE AUTHORITY FOR APPLICATION AND REMOVAL OF TAGS.
MARKINGS. AND LABELS.
2254 FSAR 17. 2. 14.B INSPECTION. TESTING. MEASURES TO PRECLUDE 05.07 AND OPERATING STATUS BTPASSING OF REQUIRED 9A 9B INSPECTIONS. TESTS.
AND OTHER CRITICAL OPERATIONS ARE CONTROLLED THROUGH DOCUMENTED PROCEDURES.
PROCEDURES ESTABLISH ALTERATION CONTROLS OVER TESTS.
INSPECTIONS, AND OTHER OPERATIONS.
2256 FSAR 17. 2. 14.C INSPECTION. TESTIN
G. PROCEDURE
S SHALL BE 05.07 AND OPERATING STATUS ESTABLISHED AND 9A.98 DOCUMENTED TO IDENTIFT THE INSPECTION. TEST.
AND OPERATING STATUS i t
OF STRUCTURES, STSTEMS. AND COMPONENTS.
2257 FSAR 17. 2. 14.D INSPECTION. TESTING. THE STATUS OF C5.07 AND OPERATING STATUS NONCONFORMING. 9A.9B INOPERATIVE. OR MALFUNCTIONING STRUCTURES, SYSTEMS, OR COMPONENT IS IDENTIFIED TO PREVENT IMADVERTENT USE.
I
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- =====-=e=====e=======~=====
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DOCUMENT / FEATURE TITLE MODULE REMARES NUMBER COMMITMENT COMMITMENT COMMITMENT SOURCE SECTION SUBJECT
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NONCONFORMING RG 1.3H. R/2 uuAL11: 05,GT, CONFORMANCE IS 2263 FSAR 17. 2. 15 9A,9B DISCUSSED IN SECTION MATERIALS, PARTS, OR ASSURANCE COMPONENTS REQUIREMENTS FOR 1.9.38.2 OF THE PACKAGING, FSAR.
SHIPPING, RECE1VING, STORAGE AND HANDLING OF ITEMS FOR WATER-COOLED NUCLEAR PONER PLANTS NONCONTORMING RG 1.123, R/l QUALITY 05,07 CONFORMANCE IS 2269 FSAR 17. 2. 15 DISCUSSED IN SECTION MATERIALS, PARTS, OR ASSURANCE COMPONENTS REQUIREMENTS FOR 1.9.121.2 OF THF CONTROL OF FSAR.
PROCUREMENT OF ITEMS AND SERVICES FOR NUCLEAR POWER PLANTS
- 17. 2. 15 NONCONFORMING RG 1.33 R/2 QUALITY 05,07 CONFORMANCE IS 2H65 FSAR MATERIALS, PARTS, OR ASSURANCE 9A 9R DISCUSSED IN SECTION COMPONENTS PROGRAM 1,9.33.2 OF THE REQUIREMENTS FSAR.
(OPERATION)
- 17. 15 NONCONFORMING REQUIREMENTS FOR THE 05,07, 2866 FSAR 2.
9A,98 MATERIALS, PARTS, OR CONTROL OF COMPONENTS NONCONFORMING MATERIALS, PARTS, OR COMPONENTS ARE CONSISTENT WITH THE POSITIONS OF REGULATORY GUIDES 1.33, 1.38, AND 1.123.
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- O T Page No. 117 12/02/85 TABLE 3.2-1 COMMITMENTS FOR PLANT
- ==2 =========================== s OPERATIONS AND SUPPORT
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COMMITMENT DOCUMENT / FEATURE TITLE MODULE REMARES NUMBER COMMITMENT COMMITMENT SOURCE SECTION SUBJECT
== ========== ================ =======e============ ====e================= ================ ====== =e============
22C2 FSAR 17. 2. 15.A NONCONFORMING MEASURES AND PROCED. 05.07 MATERIALS. PARTS. OR SHALL BE ESTAB. TO 9A.9B COMPONENTS CONTROL IDENT..
DOCUMEN.. SEGREG.
REVIEN. DISPOSITION.
AND MOTIFICATION OF AFFECTED ORGAN. OF NONCONFOR. OF MATERIALS. PARTS.
COMPONENTS. COMPUTER CODES. OR SERVICES.
DOCUMENTATION SRALL BE 05,07 2267 FSAR 17. 2. 15.8 NONCONFORMING MATERIALS. PARTS. OR PROVIDED CLE ARLY 9A.9B COMPONENTS IDENTIFTING MONCONFORMING ITEM.
DESCRIBING MONCONFORMANCE &
1 DISPOSITION OF NONCONFORMANCE
'1 INSPECTION REQUIREMENTS. &
INCLUDES SIGNATURE APPROVAL OF DISPOSITION.
2258 FSAR 17, 2. IS.C NONCONFORMING MATERIALS. PARTS OR 05.07 MATERIALS. PARTS. OR COMPONENTS WHICH FAIL 94.98 COMPONENTS TO MEET REQUIREMENTS ARE IDENTIFIED THROUGH THE USE OF A DEFICIENCY REPORT.
I 2867 FSAR 17. 2. 15.C NONCONFORMING DEFICIENCY REPORTS. 05.07 l' MATERIALS. PARTS. OR PREPARED BY THE PERSON 9A.98 COMPONENTS IDENTIFYING THE DEFICIENCY, ARE LOGGED AND PROCESSED BT THE QC SUPERVISOR AFTER BRING REVIEWED BT 1RE SHIFT SUPERVISOR FOR r
PLANT OPERABILITY g
IMPLICATIONS AND IMMEDIATE REPCRTING REQUIREMENTS.
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4
- ._. ._ - . _ _ . _ _ _ ~ - . _ . _ _ . - _ _ _ - _ _ _ _ - _ _ - . - _ . _ _ _ _ _ _ _ _ . _ = _ _ _ _ _ _ _ - _ _ _ _ _ . . _ _ .-.--.- . _ . _ . . . - - _ _ _ . .._ _.__-_--__ -
Page No, 118 12/02/85 TABLE 3.2'l COMMITMENTS FOR PLANT
--===- =,=====-- ===- ===,=s=- -
OPERATIONS AND SUPPORT
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THESE REPORTS (DR'S) 05,07 2265 FSAR 17. 2. 15.D NONCONFORMING MATERIALS, PARTS, OR ARE REVIEWED BY COMPONENTS APPROPRIATE OPERATIONS
& ENGINEERING PERSONNEL & BY PRB FOR REGULATORY REPORTABILITY & TO ENSURE THAT APPROP.
CORRECTIVE ACTION IS BEING TAREN.
15.F NONCONFORMING NONCONFORMING ITEMS 05,07 ITEMS THAT ARE 2266 FSAR 17. 2.
9A,9B UNIQUE, IDENTIFIED, MATERIALS, PARTS, OR ARE SEGREGATED FROM OTHER ACCEPTABLE ITEMS PROPERLT MARKED, AND 4
COMPONENTS (WHERE FEASIBLE) AND HAVE THRIR OWN UNIQUELY IDENTIFIED AS SPECIFIED STORAGE NONCONFORMING UNTit LOCATION NEED NOT BE PROPERLY SEGREGATED.
DISPOSITIONED.
MONCONFORMING ITEMS REQUIRING 05,07 REWORK, ETC. AT 2261 FSAR 17. 2. 15.F MATERIALS, PARTS, OR REWORK, REPAIR, OR SUPPLIER 3*
j FACILITIES IS
- COMPONENTS REPLACEMENT ARE INSPECTED & TESTED IN PERFORMED ACCORDING i
ACCORD. WITH ORIGINAL TO DOCUMENTED INSPECTION & TESTING PROCEDURES. THE REQUIREMENTS OR DISPOSITION IS
{ DOCUMENTED, AND TBE ACCEPT. ALTERNATIVES, AS DETERMINED BY DOCUMENTS ARE SENT SUPERINTENDENT OF REG. TO THE SITE WITH THE COMP. HARDWARE.
- 17. NONCONFORMING VECP PROCED. PROVIDE 05.07, 2268 FSAR 2. 15.1 9A,9E MATERIALS, PARTS, OR ASSURANCE THAT COMPONENTS DEFICIENCIES ARE RESOLVED PRIOR TO INITIATION OF FUNCT.
TESTS. DEFICIENCIES WILL BE EVAL. TO DETERMINE WHETHER THEY WOULD ADVERSELT AFFECT FUNCT. TEST.
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NUMBER COMMITMENT COMMITMENT COMMITMENT DOCUMENT / FEATURE TITLE MODULE REMARES SOURCE SECTION SUBJECT
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05.07, i 2272 FSAR 17. 2. 16 CORRECTIVE ACTION CORRECT. ACTION IS INITIATED FOLLOWING 9A,9B l DETERM. OF CONDIT.
ADVERSE TO QUALITT.
FAILURES, MALFUNCT. t DEFIC., DEVIAT., j DEFECT. MATER. AND EQUIP. AND MONCONFORM.
ON SAFETT-RELATED SYS.-
ARE DOCUM. BY APPROP.
PROCED.
2273 FSAR 17. 2. 16 CORRECTIVE ACTION RG 1.33 R/2 QUALITY 05.07 CONFORMANCE IS ASSURANCE 9A,98 DISCUS 5ED IN SECTION j PROGRAM 1.9.33.2 0F THE :
REQUIREMENTS FSAR.
(OPERATION) 2274 FSAR 17. 2. 16 CORRECTIVE ACTION ITEMS REQUIRING PROMPT 05.07 EVALUATION AND 9A,98 CORRECTION ARE RANDLED IN A DEFICIENCY REPORT. THIS IS USED FOR NONCONFORMING l ITEMS, OPERATIONAL l
DEFICIENCIES, UNUSUAL EVENTS, AND TECH SPEC f DISCREPANCIES.
2869 FSAR 17. 2. 16 CORRECTIVE ACTION THE PROGRAM FOR 05,07*, ;
CORRECTIVE-ACTION IS 9A,98 CONSISTENT WITH TME PROVISIONS OF
' REGULATORY GUIDE 1.33.
2276 FSAR 17. 2. 17 QUALITY ASSURANCE RG 1.33 R/2 QUALITY 02,05, CONFORMANCE IS RECORDS ASSURANCE 07.9A, DISCUSSED IN SECTION l PROGRAM 98,15 1.9.33.2 0F THE 4
REQUIREMENTS FSAR.
4 (OPERATION) i i
1
, \
p (?
. - _ . _ _ _ - - - - _ - - _ _ . - _ - _ _ _ _ - . . _ . . - - - _ - - _ _ _ - _ _ _ _ . _ _ _ - . _ - - - - - - _ - - . _ _ _ _ _ _ _ - _ _ _ - - _ - _ _ - _ - _ _ - - _ - _ _ _ _ . - . - - . . _ _ - _ _ - . _ _ . - - - - _ _ . _ _ _ _ _ _ . - - _ - - - . . = _ _ - . _ - .- - _ . . _ _
Page No. 120 12/02/85 TABLE 3.2-1 COMMITMENTS FOR PLANT
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========,= =======
DOCUMENT / FEATURE TITLE MODULE REMARKS NUMBER COMMITMENT COMMITMENT COMMITMENT SOURCE SECTION SUBJECT
== ========== ================ ==================== ====== ============rr- ======== ======- ====== ==============
QUALITY ASSURANCE ACTIVITIES ASSOCIATED 02,05, 2872 FSAR 17. 2. 17 07,9A, RECORDS WITH QUALITY ASSURANCE RECORDS ARE CONSISTENT 98,15 WITH THE POSITION OF REGULATORY GUIDES 1.88 AND 1.33.
QUALITY ASSURANCE PERSONNEL AND 02,05, 2873 FSAR 17. 2. 17 RECORDS ORGANIZATIONS 07,9A, SUBMITTING RECORDS AND 98,15 DOCUMENTS TO THE DOCUMENTATION STAFF FOR STORAGE SHALL BE RESPONSIBLE FOR PROVIDING ADECUATE INFORMATION MITH THAT RECORD OR DOCUMENT TO ALLOW ITS SYSTEMATIC STORAGE AND RETRIEVAL.
2280 FSAa 18. 1. 1. I OPERATIONS CONTROL ROOM DESIGN 07 FACILITIES AND REVIEW SHALL BE EQUIPMENT CONDUCTED PRIOR TO LICENSING AS REQUIRED BY SUPPLEMENT 1 TO NUREG 0737. IT SHALL COMMENCE APPROKIMATELY ONE YEAR PRIOR TO UNIT I FUEL LOAD I 2281 FSAR 18. 1. 1 1 OPERATIONS NUREG 0737 SUPPLEMENT CLARIFICATION OF 07 FACILITIES AND 1 TMI ACTION PLAN EQUIPMENT REQUIREMENTS 2302 FSAR APP. 98, FIRE PROTECTION ADMINISTRATIVE 07 C.I.A(2) PROGRAM PROCEDURES (GENERAL FIRE PROCEDURES)
CONTROL POTENTIAL IGNITION SOURCES.
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12/02/85 TABIF 3.2-1 COMMITMENTS FOR PLANT
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N UM B Elf COMMITMENT COMMITMENT COMMITMENT DOCUMENT / FEATURE TITLE MODULE REMARKS SOURCE SECTION SUBJECT
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2292 FsAh AFP. 38 FIRE PROTECTION ONSITE RESPONSIBILITY 07 ALSO STATED IN C.I.A(3) PROGRAM FOR THE FIRE APPENDIX 98 PROTECTION PROGRAM C.I.a(4)(c).
RESTS WITH THE GENERAL MANAGER.
2288 FSAR APP. 9B. FIRE PROTECTION FIRE FIGHTING OT C.I.A(3)(A) PROGRAM PROCEDURES DELINEATE THE POTENTIAL HAZARDS OF A FIRE. THET ALSO GIVE BUILDING L A Y O UT..
22R5 FSAR APP. 9B. FIRE PROTECTION FIRE BRIGADE CONSISTS 07 THIS IS ALSO STATED C.I.A(3)(B) PROGRAM OF THREE TEAMS (ONE IN APPENDIX 98 PER SHIFT) WITH AT C.I.a(3)(e).
LEAST FIVE TEAM C.I.a(4)(f)iv, AND MEMBERS EACH. EACH HAS C.I.a(6).
A FIRE TEAM CAPTAIN.
RESPONSIBLE FOR FIRE FIGHTING ACTIVITIES AT TRE SCENE.
2294 FSAR APP. 98 FIRE PROTECTION PROGRAMS OF PREVENTIVE 07 C.I.A(3)(C) PROGRAM MAINTENANCE AND SURVEILLANCE ARE ESTABLISHED TO INSURE FIRE DETECTION AND SUPPRESSION SYSTEMS ARE OPERABLE AND THAT FIRE BARRIERS AND FIRE FIGHTING EQUIPMENT ARE IN PLACE.
2293 FSAR APP. 9B. FIRE PROTECTION FIRE FIGHTING 07 C.I.A(3)(F) PROGRAM PROCEDURES ARE USED AS PREFIRE PLANS.
2295 FSAR APP. 98 FIRE PROTECTION DESCRIBED DUTIES ARE 07 C.I.A(4)(D)I PROGRAM SHARED BT A FIRE PROTECTION ENGINEER AND THE OPERATIONS DEPARTMENT AS A PANT OF THEIR DAILT ROUNDS.
TRESE ARE DESIGNATED IN ADMINISTRATIVE FIRE PROTECTION PROCEDURES.
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TITLE MODULE REMARES NUMBER COMMITMENT COMMITMENT COMMITMENT DOCUMENT / FEATURE SOURCE SECTION SUBJECT = =====- - = ======== ====-==
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FIRE PROTECTION FIRE PROTECTION TEST 07 229D FSAR APP. 9B.
C.I.A(4)(D)II PROGRAM RESULTS ARE EVALUATED AS REQUIRED BY THE FIRE PROTECTION ENGINEER.
APP. 99, FIRE PROTECTION MAINTENANCE 07 2874 FSAR C.I.A(4)(D)II PROGRAM SUPERINTENDENT IS RESPONSIBLE FOR TESTS AND INSPECTIONS OF FIRE PROTECTION EQUIPMENT OTHER THAN DAILY OR WEEKLT SURVEILLANCES.
APP. 9B. FIRE PROTECTION FIRE PROTECTION 07 2289 FSAR C.I.4(4)(D)III PROGRAM ENGINEER WILL ASSIST IN THE CRITIQUE OF THE FIRE DRILLS FOR EFFECTIVENESS.
APP. 9B. FIRE PROTECTION THE PLANT WORK 07 2313 FSAR C.I.A(4)(D)IV PROGRAM PLANNING GROUP IS RESPONSIBLE FOR EVALUATING PROPOSED WORE ACTIVITIES TO IDENTIFY POTENTIAL TRANSIENT FIRE HAZARDS.
2297 FSAR APP. 9B, FIRE PROTECTION CONTRACT PERSONNEL 07 C.I.A(4)(D)V, VI PROGRAM WILL BE GIVEN INSTRUCTIONS ON FIRE PROTECTION PROGRAM AND PROCEDURES. PROPER HANDLING OF ACCIDENTAL SPILLS AND LEAKS OF FLAMMABLE MATERIAL WILL BE TAUGHT TO
, APPROPRIATE PERSONNEL.
I t
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NUMBER COMMITMENT COMMITMENT COMMITMENT DOCUMENT / FEATURE TITLE MODULE REMARKS SOURCE SECTION SUBJECT
= == ========== ================ ==============re==== ====================== ================ ====== ==============s
2303 FSAR APP. 98, FIRE PROTECTION AUTHORITT AND 07 C.I.A(4)(F) PROGRAM RESPONSIBILITT OF THE BRIGADE MEMBERS ARE DESCRIBED IN THE GENERAL FIRE PROCEDURES AND THE FIRE FIGRTING PROCEDURES.
2299 FSAR APP. 98 FIRE PROTECTION BRIGADE MEMBERS WILL 07 i
C.I.A(4)(F)1II PROGRAM NOT BE AMONG THOSE PEOPLE REQUIRED FOR !
OPERATIONS DURING A FIRE EMBRGENCT.
2286 FSAR APP. 9B, FIRE PROTECTION APPLICAPLE NFPA CODES. PRIVATE FIRE 07 THIS IS ALSO STATED C.I.A(4)(F)V PROGRAM INCLUDING NFPA 27 AND BRIGADES, AND IN APPENDIX 9B, NFPA 197 WILL BE INITIAL FIRE C.3.d(9)
CONSULTED WHEN ATTACK FORMULATING THE FIRE BRIGADE'S ORGANIZATION,
- TRAINING, AND DRILLS.
2296 FSAR APP. 98, FIRE PROTECTION ORGANIZATIONAL 07 C.1.A(4) A(4)(D) PROGRAM RESPONSIBILITIES AND i LINES OF COMMUNICATION ARE DEFINED IN ADMINISTRATIVE FIRE PROTECTION PROCEDURES.
2295 FSAR APP. 9B, FIRE PROTECTION ADMINISTRATIVE 07 i C.I.A(7) PROGRAM PROCEDURES DESIGNATE j THE SUPERINTENDENT OF THE OPERATING PLANT AS 1
HAVING LEAD
! RESPONSIBILITT FOR SITE FIRE PROTECTION.
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. . _ _ m Page No. 124 12/02/R5 TABLF 3.2-1 COMMITMENTS FOR PLANT
=====~==========-============ =---
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==--=r:==============-
COMMITMENT COMMITMENT DOCUMENT /FFATURE TITLE MODULE REMARES NUMBER COMMITMENT SOURCE SECTION SUBJECT
:= =- === =:-=== ====:=======r==- =====~==========-=== =-========-- =====--,= ======= ===,===- == === =================
2300 FSAR APP. 99, C.I.A.5 FIRE PROTECTION REQUIREMENTS FOR 07 PROGRAM PERSONNEL (QUALIFICATIONS) IN THE FIRE PROTECTION PROGRAM ARE DELINEATED IN THE GENERAL FIRE PROTECTION PROCEDURES.
SEE C.I.A.5 FOR REQUIREMENTS.
2305 FSAR APP. 98, C.I.B FIRE PROTECTION TRANSIENT FIRE LOADS 07 PROGRAM ARE CONTROLLED VIA ADMINISTRATIVE FIRE PROTECTION PROCEDURES.
23II FSAR APP. 99 C.I.B. FIRE PROTECTION REQUIREMENTS GOVERNING 07 C.2.C PROGRAM HANDLING OF AND LIMITING TRANSIENT FIRE LOADS IN ALL PHASES OF OPERATION ARE PROVIDED IN THE GENERAL FIRE PROCEDURES.
22R3 FSAR APP. 9B, FIRE PROTECTION UNIT I FIRE PROTECTION 03A,07 C.I.E(1), E(2) SYSTEM PROGRAM SRALL BE FULLY OPERATIONAL BEFORE INITIAL FUEL LOADING.
2310 FSAR APP. 9B, C.2.A FIRE PROTECTION FIRE PROTECTION ADMIN. 07 PROGRAM CONTROLS - COMBUSTIBLE MATERIAL STORAGE AREAS ARE CHOSEN NOT TO BE ADJACENT TO SAFETY-RELATED SYSTEMS.
2307 FSAR APP. 9R, C.2.B FIRE PROTECTION USE AND HANDLING OF 07 PROGRAM FLAMMABLE GASES, LIQUIDS, AND OTHER COMBUSTIBLES IN
, SAFETT-RELATED AREAS ARE GOVERNED BY GENERAL FIRE PROCEDURES.
O O O O O O O
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- Page No. 125 12/02/85 TABLE 3.2-1 COMMITMENTS FOR PLANT I
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TITLE MODULE REMARES COMMITMENT COMMITMENT DOCUMENT / FEATURE NL'MBER COMMITMENT SOURCE SECTION SUBJECT ====== ====================
-====r== ====================== ==e========
== ========== ================
THE FPE OR HIS 07 2334 FSAR APP. 9B, C.2.D FIRE PROTECTION PROGRAM DESIGNEE HAS THE RESPONSIBILITT TO i SPECIFY ADDITIONAL PROTECTION .
i REQUIREMENTS IN WORE ACTIVITY PROCEDURES.
THE ADMINISTRATIVE 07 ;
2R75 FSAR APP. 98, C.2.E FIRE PROTECTION PROGRAM FIRE PROTECTION PROCEDURES GOVERN TRE USE OF IGNITION SOURCES.
GENERAL FIRE 07 2314 FSAR APP. 98, C.2.F. FIRE PROTECTION r C.2.1 PROGRAM PROCEDURES REQUIRE THAT WASTE COMBUSTIBLES BE REMOVED AS SOON AS PRACTICAL.
THE ADMINISTRATIVE 07 2876 FSAR APP. 9B. C.2.G FIRE PROTECTION PROGRAM FIRE PROTECTION PROCEDURES PROHIBIT TESTING WITR AN OPEN FLAME.
ADMINISTRATIVE FIRE 07 ,
2877 FSAR APP. 98, C.2.1 FIRE PROTECTION PROGRAM PROTECTION PROCEDURES
' GOVERN THE USE OF SPECIFIC COMPUSTIBLES IN SAFETT-RELATED AREAS AND REQUIRE THAT TRANSIENT COMBUSTIBLES AND COMBUSTIBLE WASTE BE REMOVED FROM SAFETT-RELATED AREAS AS 500N AS PRACTICAL.
4 k
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- --========:-======-===-==== ==:.
OPERATIONS AND SUPPORT
=:--- ==- = =~
COMMITMENT DOCUMENT / FEATURE TITLE MODULE REMARKS NUMBER COMMITMENT COMMITMENT SOURCE SECTION SUBJECT =e=============,===
== ========== ==-============= == ========== =-===~ - = ======== ===== - - --- ===========
APP. 98 C.2.K FIRE PROTECTION PERFORMANCE AND 07 2878 FSAR PROGRAM PLANNING OF FIRE PROTECTION SURVEILLANCE TESTS IS
' THE RESPONSIBILITY OF THE MAINTENANCE SUPERINTENDENT.
ADMINISTRATIVE FIRE PROTECTION PROCEDURES DETERMINE WRICH CONTROLS ARE REQUIRED FOR PERFORMANCE OF NORK ORDERS.
APP. 98, C.2.L FIRE PROTECTION THE ADMINISTRATIVE 07 2315 FSAR PROGRAM FIRE PROTECTION PROCEDURES GIVE THE ACTIONS TO BE TAEEN BY ANYONE DISCOVERING A FIRE.
APP. 98, C.2.M FIRE PROTECTION GENERAL FIRE 07 2306 FSAR PROGRAM PROCEDURES GIVE THE ACTIONS TO BE TAKEN BY THE CONTROL ROOM WHEN A FIRE IS INDICATED.
FIRE PROTECTION SPECIFIC REQUIRFMENTS 07 2312 FSAR APP. 9B. C.2.0 PROGRAM I THROUGR 10 WILL EITHER BE A PART OF THE FIRE TRAINING PROGRAM OR WILL BE INCLUDED AS REFERENCE INFO IN THE FIRE FIGHTING PROCEDURBS.
APP. 9B, C.2.0 FIRE PROTECTION THE FIRE BRIGADE 07 2879 FSAR PROGRAM TRAINING PROGRAM WILL ENSURE TRAT THE FIRE TEAM CAPTAIN IS KNOWLEDGEABLE OF VARIOUS FIRE FIGHTING STRATEGIES FOR EACR FIRE ZONE.
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TITLE MODULE REMARKS COMMITMENT COMMITMENT DOCUMENT / FEATURE NUMBER COMMITMENT SOURCE SECTION SUBJECT ==e=== ====================
== ========== ================ =============e====== ====================== ==========
AFTER A FIRE DRILL, OT 2345 FSAR APP. 98 FIRE PROTECTION C.3.(7)(F)111 PROGRAM THE BRIGADE LEADER THROUGHNESS, ACCURACY, AND EFFECTIVENESS WILL BE ADDRESSED BY THE CRITIQUING BODY.
RG 1.101 EMERGENCY EMERGENCY OT 228T FSAR APP. 99, C.3.A FIRE PROTECTION PROGRAM PLANNING FOR NUCLEAR PLAMMING FOR POWER PLANTS, WILL BE NUCLEAR POWER CONSULTED WHEN PLANTS DEVELOPING THE FIRE BRIGADE.
i FIRE TEAM CAPTAIN WILL OT 2308 FSAR APP. 98 C.3.8 FIRE PROTECTION PROGRAM NOT BE THE SRIFT SUPERVISOR.
FIRE BRIGADE MEMBERS OT ALSO STATED IN 2347 FSAR APP. 98, C.3.8 FIRE PROTECTION APPENDIX 9B.
PROGRAM WILL UNDERGO AN ANNUAL PHYSICAL EXAMINATION. C.I.e(5)(b).
EXAM IS TO INCLUDE PERFORMANCE OF I
STREMUOUS ACTIVITY.
FIRE TEAM CAPTAIN AND OT 2880 FSAR APP. 98 C.3.B FIRE PROTECTION PROG 9AM AT LEAST TWO FIRE BRIGADE MEMBERS WILL RAVE SUFFICIENT ENOWLEDGE OF SAFETY-RELATED SYSTEMS TO UNDERSTAND THE EFFECTS OF FIRE AND FIRE SUPPRESSANTS ON SAFE SNUTDOWN CAPABILITY.
FIRE BRIGADE WILL BE 07 2304 FSAR APP. 98 C.3.C FIRE PROTECTION PROGRAM PROVIDED WITH THE MECESSARY EQUIPMENT INCLUDING AT LEAST TEM SELF-CONTAINED J I BREATRING APPARATUSES.
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Page No. 128 12/02/85 TABLE 3.2-1 COMMITMENTS FOR PLANT
_========================= =======
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========= == = ==== =-
COMMITMENT DOCUMENT /FEATURR TITLE MODULE REMARKS N t'M B E R COMMITMENT COMMITMENT SOURCE SECTION SUBJECT
==== == =-= ===== =====.========== ==-====--=======1=== ==========-========--- =============--= ====== === ========= =-=
C.3.C FIRE PROTECTION THERE WILL BE AT LEAST 07 2316 FSAR APP. 98 PROGRAM TWO EXTRA AIR BOTTLES FOR EACH OF THE REQUIRED BREATHING APPARATUS UNITS.
COMPRESSORS WILL BE USED TO REPLENISH USED AIR BOTTLES.
APP. 98, C.3.D FIRE PROTECTION INITIAL CLASSROOM 07 2348 FSAR PROGRAM INSTRUCTION WILL INCLUDE SPECIFIC ITEMS (A) TRROUGH (J) OF C.3.D.
APP. 9B. FIRE PRCTECTION INSTRUCTION OF THE 07 2318 FSAR C.3.D(2) PROGRAM FIRE BRIG ADE WILL BE PROVIDED BT QUALIFIED INDIVIDUALS TRAINED IN FIGRTING THE TTPES OF FIRES THAT COULD OCCUR IN THE PLANT, USING THE TTPES OF EQUIPMENT AVAILABLE IN THE PLANT.
2344 FSAR APP. 9B, FIRE PROTECTION INSTRUCTION WILL BE OT C.3.D(3) PROGRAM PROVIDED FOR THE BRIGADE MEMBERS AND LEADERS.
2324 FSAR AFP. 9B, FIRE PROTRCTION MEETINGS WILL BE HELD 07 C.3.D(4) PROGRAM AT LEAST EVERT 3 MONTHS FOR THE FIRE BRIGADE TO REVIEW CHANGES IN THE FIRE PROTECTION PROGRAM AND OTHER SUBJECTS AS NECESSART.
T t
O O O O O O O
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TABLE 3.2-1
== ============= =====
OPERATIONS AND SUPPORT
==== =====
TITLE MODULE REMARKS NUMBER COMMITMENT COMMITMENT COMMITMENT DOCUMENT / FEATURE SUBJECT
- SOURCE SECTION =e============== ====== ====================
== ========== ================ =========-= ======= ===============
REFRESHER CLASSROOM 07 232u ranH APP. 9B, FIRE PROTECTION t C.3.D(5) PROGRAM TRAINING COURSES WILL BE HELD FOR FIRE BRIGADE MEMBERS AT LEAST ONCE PER 2 YEARS.
PRACTICE SESSIONS WILL 07 2322 FSAR APP. 9B. FIRE PROTECTION C.3.D(6) PROGRAM BE HELD AT LEAST ONCE '
PER TEAR FOR BACH SHIFT BRIGADE ON THE PROPER METHODS OF FIGHTING POSSIBLE PLANT FIRES. BREATHING ,
APPARATUS, AND UNDER STRENUOUS CONDITIONS.
FIBE DRILLS WILL BE 07 2327 FSAR APP. 9R. FIRE PROTECTION PERFORMED WITH THE C.3.D(7)(A) PROGRAM '
FIRE BRIGADE QUARTERLY FOR EACR SHIFT'S FIRE BRIGADE.
FIRE PROTECTION EACH FIRE BRIGADE 07 2882 FSAR APP. 95 C.3.D(7)(A) PROGRAM MEMBER MUST PARTICIPATE IN AT LEAST TWO DRILLS PER TEAR. AT LEAST ONE OF THESE DRILLS EACH SHIFT WILL BE UNANNOUNCED.
9 FIRE PROTECTION 'AT LEAST ONE FIRE 07 j 2883 FSAR APP. 9B.
C.3.D(7)(B) PROGRAM DHILL PER YEAR WILL BE ON THE BACK SHIFT FOR EACH SHIFT FIRE BRIGADE.
FIRE PROTECTION FIRE DRILLS WILL BE 07 d
2323 FSAR APP. 98, C.3.D(7)(C) PROGRAM PREPLANNED AND '
CRITIQUED FOR .
- EFFECTIVENESS.
DEFICIENCIES WILL BE REMEDIED TEROUGH EXTRA TRAINING AND/OR A i
REPEAT DRILL.
i C i
Page No. 130 12/02/85 TABLF 3. 2- 1 COMMITMFNTS FOR PLANT
- - ========= =,===== = ==-======-
OPFRATIONS AND SUPPORT
-- - ----= = =-- ==-
COMMITMENT COMMITMENT DOCUMENT / FEATURE TITLE MODULE REMARKS NUMBER COMMITMENT SOURCE SECTION SUBJECT
-==t, e= = ======== ==========-=- == ==================== ==== ,==---=,==== =. ================ ===== =========== =======
2328 FSAR APP. 99 FIRE PROTECTION A GROUP OF QUALIFIED 07 C.3.D(7)(E) PROGRAM INDIVIDUALS INDEPENDENT OF GPC WILL CRITIQUE AN UNANNOUNCED FIRE DRILL AT LEAST ONCE EVERY 3 YEARS.
2319 FSAR APP. 9R, FIRE PROTECTION FIRE DRILLS WILL 07 C.3.D(7)(F)! PROGRAM INCLUDE ASSESSMENT OF ALARM EFFECTIVENESS, ASSEMBLY TIME, USE OF EQUIPMENT, AND l
STRATEGY.
j 2343 FSAR APP. 98, ilRE PROThCTION FIRE DRILLS WILL 07 C.3.D(7)(F)l1 PROGRAM INCLUDE ASSESSMENT OF EACH MEMBER'S KNOWLEDGE OF HIS/HER ROLE IN THE FIRE
- FIGHTING EFFORT.
2342 FSAR APP. 98 FIRE PROTECTION FIRE DRILLS WILL 07 C.3.p(7)(F)III PROGRAM INCLUDE SIMULATED USE OF FIRE FIGHTING EQUIPMENT REQUIRED TO COPE WITH THE SITUATION AND F*RE SELECTED FOR THE DRILL.
2329 FSAR APP. 9B. FIRE PROTECTION INDIVIDUAL RECORDS OF 07 C.3.D(8) canapau TRAINING WILL BE PROVIDED TO EACH FIRE BRIGADE MEMBER.
INCLUDING DRILL CRITIQUES. RECORDS WILL BE MAINTAINED FOR AT LEAST 3 YEARS.
l i
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Page No. 131 12/02/85 COMMITMENTS FOR PLANT TABLE 3.2-1
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==========
DOCUMENT / FEATURE TITLE MODULE REMARES NUMBER COMMITMENT COV4ITMENT COMMITMENT SOURCE SECTION SUBJECT '
e============e= ========s========e== = =========e=e=======.- ================ ====== ===================
=== == ======
APP. 98, C.4 FIRE FROTECTION FIRE PROTECTION 07 2335 FSAR QUALITT ASSURANCE PROGRAM PROGRAM WILL BE PART ,
OF OVERALL QA PROGRAM AND WILL INSURE FIRE PROTECTION PROGRAM t
CONFORMS TO REQUIRED PARTS OF OVERALL CAP AS DESCRIBED IN PARAGRAPR 9.5.1.1.4.
TESTING OF DESIGNS 07 2884 FSAR APP. 98 FIRE PROTECTION C.S.A(3)(A) PROGRAM WRICR ENVELOPE 'tHE DESIGNS FOR FINE BARRIER PENETRATION SEALS WILL BE PERFOMED IN ACCORDANCE WITH ASTM E-Il9.
FIRE BRIGADE LEADER 07 2337 FSAR APP. 95 FIRE PROTECTION ,
C.5.A(5) PROGRAM WILL RAVE ACCESS TO EETS FOR LOCEED FIRE DOORS. ,
FIRE PROTECTION ONE OF TRE SPECIFIED 07 2340 FSAR APP. 98 C.S.A(5) PROGRAM MEASURES (C.5.e.5)
WILL BE USED TO PROTECT DOOR OPENINGS.
k FIRE PROTECTION EXIT SIGNS WILL BE 07 !
2341 FSAR APP. 98 f C.S.A(7) PROGD M PLACED ALONG EGRESS ROUTES.
l'
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+a PeBe No. 132 12/02/85 TABLE 3.2-1 COMMITMENTS FOH PLANT
===== =========e=======e = ====x
OPERATIONS AND SUPPORT
=========-
NUMBER COMMITMENT COMMITMENT COMMITMENT DOCUMENT / FEATURE TITLE MODULE REMARKS I l
SOURCE SECTION SUBJECT
e=== ====== ============,====
e== == ========== ============== . ==================== ====================== = ==
l 2332 FSAA APP. 9B. FIRE PROTFCTION FLAMMABLE LIQUIDS WILL 07 l i
C.5.D(4) PROGRAM BR STORED IN ACCORDANCE WITH NFPA 30 EXCEPT FOR ,
EMERGENCY DIESEL FUEL OIL.
2350 FSAR APP. 9B. FIRE PROTECTION ALL EXTERIOR POST 07 C.6.C(2) PROGRAM INDICATOR AND FIRE PUMP HOUSE VALVES ARE LOCKED IN THEIR NORMAL OPERATING POSITION IN LIEU OF BEING ELECTRICALLY SUPERVISED.
2321 FSAR APP. 9B, FIRE PROTECTICN ALL VEGP FIRE HOSES 07 C.G.C(6) PROGRAM ARE HYDROSTATICALLY l l
TESTED ANNUALLY.
2325 FSAR APP. 98, C.6.D FIRE PROTECTION USE OF HALON FIRE 07 PROGRAM EXTINGUISHING AGENTS AND SYSTEMS ARE GUIDED BY THE REQUIREMENTS OF NFPA 12A, ONLY UL OR FM APPROVED AGENTS AND
_ SYSTEMS ARE USED.
2326 FSAR APP. 9B. C.6.D FIRE PROTRCTION IN ADDITION TO THE 07 PROGRAM GUIDELINES OF NFPA NO.
12A. PREVENTATIVE MAINTENANCE AND TESTING OF THE SYSTEMS, INCLUDING WEIGHING OF THE HALON CYLINDERS IS DONE IN l ACCORDANCE WITH TRE TECHNICAL SPECIFICATIONS.
l l
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Page No. 133 12/02/R5 TABLE 3.2 1- COMMITMENTS FOR PLANT e:- ==e==========-== ====== =====,
OPERATIONS AND SUPPORT
-=============
TITLE MODULE REMARKS NUMBER COMMITMENT COMMITMENT COMMITMENT DOCUMENT / FEATURE SOURCE SECTION SUBJECT
== ==e======= ==========s==-=e ====x=============== ==-===========.======- ================ ====== ==============
95, FIRE PROTECTION CPC TIRE PROTECTION 07 2317 FSAR 4: P.
C.7.A(2) PROGRAM PROGRAM DOCUMENTS WILL ADDRESS THE MANAGEMENT PROCEDURES AND CONTROLS NECESSARY TO ENSURE ADEQUATE FIRE PROTECTION FOR TRANSIENT FIRE LOADS.
APP. 98, FIRE PROTECTION SELF CONTAINED 07 2330 FSAR C.7.A(2) PROGRAM BREATHING APPERATUS ARE STORED NEAR THE PERSONNEL ACCESS HATCH OF THE CONTAINMENT.
APP. 98 C.7.8 FIRE PROTECTION MANUAL FIREFIGRTING 07 2331 FSAR PROGRAM CAPABILITY IS PROVIDED FOR FIRE ORIGINATING WITHIN A CONTROL ROOM CABINET, CONSOLE, OR CONNECTING CABLES. OR EXPOSURE FIRES INVOLVING COMBUSTIBLES IN GENERAL ROOM AREA.
i APP. 98, FIRE PROTECTION IN THE CONTROL ROOM. 07 2333 FSAR C.7.B(2) PROGRAM BREATHING APPARATUS WILL BE AVAILABLE FOR NECESSARY PERSONNEL.
APP. 98 C.8.A FIRE PROTECTION A PERMIT WILL BE 07 2338 FSAR PROGRAM EMPLOYED TO LIMIT
. TEMPORARY STORAGE OF.
AND TO CONTROL USE OF ACETYLENE OR OXYGEN CYLINDERS IN SAFE d
SRUTDOWN AREAS.
i APP. 9B, C.8.B FIRE PROTECTION UNUSED ION EXCHANGE 07 l 2887 FSAR f
PROGRAM RESINS WILL NOT BE STORED IN AREAS THAT CONTAIN OR EXPOSE SAFE SHUTDOWN, EQUIPMENT.
I
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O P F it AT IONS AND SUPPORT
=--====:----====
DOCUMENT / FEATURE TITLE MODULE REMARES NUMBER COMMITMENT COMMITMENT COMMITMENT SOURCE SECTION SUBJECT
= == ========== =============: , =========== ======== =.==============-===== = ========~== == ====== ==============
FIRE PROTECTION HAZARDOUS CHEMICALS 07 2339 FSAR APP. 98. C.8.C PROGRAM WILL NOT BE STORED IN AREAS THAT CONTAIN OR EXPOSE SAFE SHUTDOWN EQUIPMENT.
C-83/06/16 RCP TRIP CRITERIA RCP TRIP CRITERIA WILL GN-236, D.O. 07 GL 83-10C.
2353 GENERIC LETTER BE ADDRESSED DURING FOSTER TO E.G.
DEVELCPMENT OF ADENSAM, JUNE CORRE EMERGENCT OPERATING 16, 1983 PROCEDURES. THE PROCEDURES WILL BE BASED ON REVISION 1 TO THE OWNERS GROUP EMERGENCT RESPONSE GUIDELINES.
2354 GENERIC C-83/ll/08 ACTIONS BASED ON 1.1 Tile POST-TRIP GN-276 D.O. 07 GL 83-28.
LETTER IMPLICATIONS OF REVIEW PROCEDURE WILL FOSTER TO E.G.
CORRE SALEM ATWS EVENTS ADDRESS REQUIREMENTS ADENSAM, EXPRESSED IN GENERIC NOVEMBER 8, 1983 LETTER 83-28 AND USE INFORMATION AND DATA PROVIDED AS A RESULT OF THE CAPABILITT REVIEW.
2355 GENERIC C-83/ll/08 ACTIONS BASED ON 4.2 REACTOR TRIP GN-276 D.C. 07 GL 83-28.
LETTER IMPLICATIONS OF SYSTEM PREVENTIVE FOSTER TO E.G.
CORRE SALEM ATWS EVENTS MAINTENANCE AND ADENSAM, SURVEILLANCE NOVEMBER 8, 1983 PROCEDURES WILL ADDRESS THE REQUIREMENTS EXPRESSED IN GENERIC LETTER 83-28.
2357 GENERIC C-84/05/01 EMERGENCT OPERATING EMERGENCY OPERATING GN-348 D.O. 07 GL 82-33. DETAILS LETTER PROCEDURE GENERATION PROCEDURES WILL BE FOSTER TO E.G. ARE IN TRE PROCEDURE J CORRE PACEAGE DEVELOPED IN ADENSAM, MAT 1 GENERATION PACEAGE.
" ACCORDANCE WITH THE 1984 TRE PACKAGE WAS PROCEDURE GENFRATION REVISED IN MARCH PACEAGE 1985.
O O O O O O O
,m._. _. ___.m _ _ _ . - ._..m_ - _..__..-.,m..- ._~m________.m. . . . .m. m_. .. . __ . ___.m . -m....._._.m._ . .~..m
'25 O O : -
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===========s
s NUMBER COMMITMENT COMMITMENT COMMITMENT DOCUMENT / FEATURE TITLE MODULE REMARES !
SOURCE SECTION SUBJECT
==== == ========e- =========e====== : ====== =======e=e= ====== ==-============ ==============e= ====== ===================
r 2358 GENER!C C-84/09/14 CONTROL ROOM DESIGN CRDH - THE CONTROL GN-416, D.O. 07 GL 82-33. DETAILS LETTER REVIEW PROGHAM PLAN ROOM DESIGN REVIEW FOSTER TO H.R. ARE IN THE CONTROL CORRE WILL BE CONDUCTED IN DENTON, ROOM DESIGN REVIEW ACCORDANCE WITH THE SEPTEMBER 14 PROGRAM PLAN.
PROGRAM PLAN. 1984 2369 IEB C-74/06/2G TECHNICAL SUPPORT GPC RAS DETERMINED R.W. SCHERER TO 07 IEB 74-09 CORRES. ORGANIZATION AND THAT NO SUCR CIRCUIT N.C. MOSELEY, ADMINISTRATION BREAKERS DESCRIBED IN AUGUST 26, 1974 REG. OPS. BULLETIN 74-9 EXIST, AND ARE NOT EXPECTED TO EXIST.
AT VEGP.
2370 IEB C-76/05/17 TECRNICAL SUPPORT EQUIPMENT FOR VEGP R.W. STAFFA TO 07 IEB 76-03 CORRES. PROCEDURES AND INCORPORATING THE GE N.C. MOSELEY, DOCUMENTATION TYPE HFA, RGA, AND STD MAY 17, 1976
- RELAYS RAS NOT BREN MANUFACTURED. HKA AND HMA RELAYS ARE NOT INCLUDED IN THE V0GTLE DESIGN.
2371 IEB C-76/06s03 TECHNICAL SUPPORT NO ITE TIME DELAY R.W. STAFFA 70 07 IRB 76-05 CORRES. PROCEDURES AND RELAYS RAVE BREN. N.C. MOSELEY, DOCUMENTATION PURCRASED OR SPECIFIED-JUNE 3, 1976 FOR OUR V0GTLE UNITS.
SUPPLIERS FOR ELECTRICAL EQUIPMENT (FUTURE) WILL BE INSTRUCTED NOT TO USE ITE IMPERIAL PNEUMATIC TIME DELAY RELAYS.
a 2372 IEB C-76/06/03 TECHNICAL SUPPORT NO MESTINGROUSE BFD R.W. STAFFA TO 07 IRB 76-05 CORRES. PROCEDURES AND RELAYS ARE USED AND NO N.C. MOSELEY, DOCUMENTATION PLANS BRIST FOR THEIR JUNE 3, 1976 USE ON UNITS 1 AND 2 j OF VEGP.
5(
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=========-===-= == =======,= ===r OPERATIONS AND SUPPORT
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========e- -===== ==-===== ===
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TECHNICAL SUPPORT NO WESTINGHOUSE BF N.W. STAFFA TO 07 IEB 76-02 2373 IEB C-76/ll/lO COHRES. PROCEDURES AND (AC) OR BFD (DC) N.C. MOSELEY, DOCUMENTATION RELAYS ARE USED AND NO NOVEMBER 10 PLANS EXIST FOR 1976 THEIRUSE ON UNITS 1 AND 2.
TECHNICAL SUPPORT VOGTLE UNITS WILL USE R.W. STAFFA TO 07 IRB 77-01 2374 IEB C-77/06/27 CORRES. PROCEDURES AND EITHER SOLID STATE N.C. MOSELEY, DOCUMENTATION TIME DELAY RELAYS OR JUNE 27, 1977 PNEUMATIC TIME DELAY RELAYS WITH A REPEAT ACCURACY RANGF. BETTER THAN + OR - 15 PERCENT.
2375 IRB C -77/ ll/09 MAINTENANCE SOLID STATE PROTECTION R.W. STAFFA TO 07 IEB 77-03 CORRES. PROCEDURES AND SYSTEM TESTING J.P. O'REILLY, DOCUMENTATION PROCEDURES WILL NOVEMBER 9, 1977 CONTAIN INFORMATION PROVIDED IN WESTINGHOUSE TECHNICAL BULLETIN NSD TB-77-II.
2376 IEB C-77/11/11 TECHNICAL SUPPORT NO WESTINGHOUSE AR R.W. STAFFA TO 07 IEB 77-02 CORRES. PROCEDURES AND RELAYS WILL BE USED IN J.P. O'REILLY, DOCUMENTATION BALANCE OF PLANT NOVEMBER 11 SAFETY CIRCUITS AT 1977 PLANT VOGTLE.
2377 IEB C-78/01/09 TECHNICAL SUPPORT VEGP WILL BE USING R.W. STAFFA TO 07 IEB 77-05 CORRES. PROCEDURES AND CONNECTORS OF PIN AND J.P. O'REILLY, DOCUurgtaTION SOCKET TYPE, WITH JANUARY 9, 1978 METAL SHELL AND CREW COUPLINGS FOR PENETRATION ASSEMBLIES IN THE CONTAINMENT.
2378 IEB C-78/Ol/09 TECHNICAL SUPPORT OUR SPECIFICATION WILL R.W. STAFFA TO 07 IRB 77-05 CORRES. PROCEDURES AND INDICATE THAT TRE J.P. O'REILLY, DOCI! MENTATION CONNECTOR ASSEMBLY JANUARY 9, 197R SHALL BE QUALIFIED TO SURVIVE ACCIDENT CONDITIONS IF THEY CARRY ANY CLASS lE CIRCUIT.
O O O O O O O
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. . .. m - . . .m . _ _ . _ , ~- . ._ . . _ _ _ - - - -__. ..
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SOURCE ===================e== ================ ======
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R.W. STAFFA TO 07 IEB 77-07 TECHNICAL SUPPORT TO AVOID ANY PROBLEMS 2379 IEB c-78/01/24 ARISING OUT OF USING J.P. O'REILLY, CORRES. PROCEDURES AND JANUARY 24, 1978 DOCUMENTATION EPOKY SEALANT, GPC SPECIFICATION WILL PRORIBIT USE OF EPOXY SEALANT IN CONTAINMENT ELECTRICAL PENETRATIONS.
ELECTRICAL PENETRATION R.W. STAFFA TO 07 IBB C-78/Ol/24 TECHNICAL SUPPORT 2380 PROCEDURES AND ASSEMBLIES SRALL MEET J.P. O'REILLY.
~
CORRES. REQUIREMENTS OF IEEE JANUARY 24, 1978 DOCUMENTATION STANDARDS 317-1976 AND 323-1974.
PLANT VOGTLE WILL NOT R.W. STAFFA TO 07 IEB 78-02 2381 IEB C-78/02/28 TECHNICAL SUPPORT J.P. O'REILLY, PROCEDURES AND USE ANY UNPROTECTCD CORhES. FEBRUARY 28 DOCUMENTATION TERMINAL BLOCES IN SYSTEMS WRICR MUST 1978 FUNCTION IN THE POST-ACCIDENT ENVIRONMENT.
NO GENERAL ELECTRIC R.W. STAFFA TO 07 IRB 78-01 2382 IEB C-78/03/13 TECHNICAL SUPPORT J.P. O'REILLY, 4 CORRES. PROCEDURES AND TYPE CR 120 A RELAYS DOCUMENTATION WILL BE USED AT PLANT MARCH 13, 1978 VOGTLE.
NO CUTLER-RAMMER' R.W. STAFFA TO. 07 IEB 78-06 2888 IEB C-78/06/06 DEFECTIVE J.P. O'REILLY, CORRES. CUTLER-RAMMER TYPE M D23MRD TYPE M RELAYS RELAYS WITH D-C COIL PRODUCED JULY 24, 1978 4
BETWEEN 1971 AND 1976 WILL BE USED AT PLANT VOGTLE.
NO GENERAL ELECTRIC R.W. STAFFA TO 07 IEB 78-15 2383 IRB C-78/06/07 TECHNICAL SUPPORT PROCEDURES AND TYPE CR IO5X AURILIARY J.P. O'RE1LLY, CORRES. CONTACT MECHANISM WILL JUNE 7, 1978 DOCUMENTATION BE USED AT PLANT VOGTLE.
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- - _ _ _ _ . - - - - _ - - - _ . . . . - _ _ _ _ _ - - _ _ _ _ _ - - - - - - . _ _ _ _ . - - - _ _ - _ _ - - - - - - _ ,____-.-__r___v u ,-e - - - -,
Page No. 138 12/02/85 TABLE 3.2 1 COMMITMENTS FOR PLANT
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= == =====-==== ================ ================== = - =========e ==-= ===- =======-===== = ====== ================
BERGEN-PATERSON NO BERGEN-PATERSON R.W. STAFFA TO 07 IED 78-10 2889 IEB C-78/08/ll HYDRAULIC SHOCE HYDRAULIC SHOCE J.P. O'REILLY, COHRES.
SUPPRESSORS SUPPRESSORS WILL BE AUGUST 11, 1978 l' SED AT PLANT VOGTLE.
TECHNICAL SUPPORT GPC IS NOT USING VELAN GM-475 R.W. 07 IER 79-04 2384 IEB C-79/05/25 COHNES. PROCEDURES AND SWING CHECE VALVES AT STAFFA TO J.P.
DOCUMENTATION PLANT VOGTLE. O'REILLY, MAY 25, 1979 TECHNICAL SUPPORT GPC IS NOT USING GM-459 R.W. 07 IRB 79-04 2385 IEB C-79/05/29 CORRES. PROCEDURES AND GENERAL ELECTRIC TYPE STAFFA TO J.P.
DOCUMENTATION AK-2 CIRCUIT BREAEERS O'REILLY, MAY IN ANY SAFETY RELATED 29, 1979 SYSTEM AT PLANT VOGTLE.
2890 IED C-79/07/06 PIPE SUPPORT BASE ALL PIPE SUPPORT BASE R.W. STAFFA TO 07 IEB 79-02 CORRES. PLATES USING PLATES USING EXPANSION J.P. O'REILLY, CONCRETE EXPANSION ANCHOR BOLTS WILL BE JULY 6, 1979 ANCHORS ANALTZED TO ACCOUNT FOR PIATE FLEXIBILITY, SHEAR-TENSION INTERACTION, MINIMUM EDGE DISTANCE AND PROPER BOLT SPACING.
2891 IRB C-79/07/06 BASE PLATE DESIGNS FACTORS OF R.W. STAFFA TO 07 IEB 79-02 CORRES. USING CONCRETE SAFETY (I.E., RATIO OF J.P. O'REILLY, EXPANSION ANCHORS BOLT ULTIMATE CAPACITY JULY 6, 1979 TO DESIGN LOAD) OF OUR FOR WEDGE TYPE AND FivF Fnp 9 R F i t- TYPE ACNHOR BOLTS WILL BE USED.
2892 IEB C-79/07/CS BASE PLATE DESIGNS TO THE EXTENT THAT R.W. STAFFA TO 07 IEB 79-02 CORRES. USING CONCRETE LOADS INCLUDE CYCLIC J.P. O'REILLY, EXPANSION ANCHORS CONSIDERATIONS. THESE JULY 6, 1979 EFFECTS WILL BE N INCLUDED IN THE DESIGN OF RANGERS. BASE PLATES AND ANCHORAGES.
O O O O O O O
-- - . ~ - - . .. -. -. . . . - . - . - . . . . . . = . . - . . . - . . . . .
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2833 IEB C-79/07/06 BASE plt.TE DESYGw? A PROCEDURE FOR R.W. STAFFA TO 07 IRB 79-02 CORRES. USING CONCRETE INSPECTION OF J.P. O'REILLY.
EXPANSION ANCHORS INSTALLATION OF BOLTS JULY 6 1979 ON RANGERS WILL INCLUDE TORQUE OF 1 BOLT ON BACR PLATE OR ALL IF ONE FAILS PLUS RANDOM SURVEILLANCE OF BOLT INSTALLATION.
2386 IEB C-79/07/30 TECRNICAL SUPPORT GPC IS NOT USING GM-479 D. 07 IBB 79-11 CORRES. PROCEDURES AND WESTINGROUSE TYPE DUTTON TO J.P.
DOCUMENTATION DB-75 OR DB-50 0'REILLY. JULY BREAKERS WITH END CAPS 30 1979 IN ANY SAFETT RELATED SYSTEMS AT PLANT V0GTLE.
2387 IEB C-79/12/28 TECHNICAL SUPPORT NO RELAYS OF THE TYPE GM-542 D. 07 IRB 79-25 CORRES. PROCEDURES AND DISCUSSED IN I.E. DUTTON TO J.P.
DOCUMENTATION BULLETIN 79-25 NAVE 0'REILLT.
BREN USED IN ANT CLASS DECEMBER 28 I EQUIPMENT TO DATE. 1979 MEASURES WILL BE TAKEN TO ENSURE TRAT TNE DEFECTIVE RELAYS ARE NOT USED.
2388 IRB C-80/03/20 TECRNICAL SUPPORT PLANT V0GTLE WILL NOT 'CM-592 D. 07 IRB 80-03 CORRES. PROCEDURES AND USE THE STANDARD TYPE DUTTON TO J.P.
-- DOCUMENTATION II. TRAY OR DRAWER O'REILLY. MARCH ABSORBER CELL. 20 1980 ABSORBER CELLS ARE OF gi THE VERTICAL FILL TYPE AND USE PERFORATED g METAL SREETS WELDED.
NOT RIVETED. TO THE FILTER CASINGS.
C 4
cs
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OPERATIONS AND SUPPORT
==== =====
DOCUMENT / FEATURE TITLE MODULE REMARES NUMBER COMMITMENT COMMITMENT COMMITMENT SOURCE SECTION SUBJECT
== ========== ================ ==================== ======= ===r========== ============= == -===== ==============
TECHNICAL SUPPORT GPC HAS NOT UTILIZED GN-333 D.O. 07 IEB 83-08 2389 IEB C-80/03/27 FOSTER TO J.P.
CORRES. PROCEDURES AND ELECTRICAL CIRCUIT DOCUMENTATION BREAEERS WITH O'REILLY, MARCH UNDERVOLTAGE TRIP 27, 1984 FEATURES IN ANY SAFETY-RELATED APPLICATIONS OTHER THAN THE REACTOR TRIP SYSTEM.
IRB C-80/06/16 TECHNICAL SUPPORT GPC DOES NOT USE AH-90 GM-636, D. 07 IEB B0-09 2390 CORRES. PROCEDURES AND OR NH-90 SERIES DUTTON TO J.P.
DOCUMENTATION HYDRAMOTOR ACTUATORS O'REILLY, JUNE MANUFACTURED BY ITT 16, 1980 GENERAL CONTROLS FOR ANY SAFETY RELATED SYSTEMS OR COMPONENTS IN PLANT VOGTLE.
IEB C-80/09/02 TECHNICAL SUPPORT GPC DOES NOT USE GM-687, D. 07 IEB 80-16 2391 CORRES. PROCEDURES AND ROSEMOUNT MODELS 1151 DUTTON TO J.P.
DOCUMENTATION OR 1152 PRESSURE O'REILLT, TRANSMITTERS, OR SEPTEMBER 2 ROSEMOUNT MODEL 510DU 1980 TRIP UNITS, FOR ANY SAFETY RELATEC SYSTEMS OR COMPONENTS IN PLANT VOGTLE.
IRB C-80/09/16 TECHNICAL SUPPORT GPC DOES NOT USE GM-693 D. 07 IRB 80-20 2392 CORRES. PROCEDURES AND WESTINGHOUSE TYPE W-2 DUTTON TO J.P.
DOCUMENTATION CONTROL SWITCHES WITH O'REILLT, SPRING RETURN TO SEPTEMBER 16, NEUTRAL FOR SAFETY 1980 RELATED APPLICATIONS AT PLANT VOGTLE.
2393 IEB C-80/12/30 TECHNICAL SUPPORT GPC DOES NOT HAVE ANY GN-lO7, D. 07 IRB 80-21 CORRES. PROCEDURES AND VALVES IN DUTTON TO J.P.
DOCUMENTATION SAFETY-RELATED SYSTEMS O'REILLY, WITH VALVE PARTS CAST DECEMBTR 30, BY MALCOM FOUNDRY 1980 COMPANY. INC.
O O O O O O O
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=---=====: =.=========e===-- 4
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===============e
COMMITMENT DOCUMENT / FEATURE TITLE MODULE REMARKS NUMBER COMMITMENT COMMITMENT SOURCE SECTION SUBJECT
====e===== ============-===-=== ===m======== ==-===-== =======r===e==== ====== ==============
= ====
TECHNICAL SUPPORT GPC DOES NOT HAVE ANY GN-106 D. 07 IRB RO-23 2394 IEB C-80/12/30 CORRES. PROCEDURES AND VALCOR SOLENOID VALVES DUTTON TO J.P.
DOCUMENTATION WITH PART NUMBERS O'REILLY, V70900-21-1 OR 3 FOR DECEMBER 30 SAFETY RELATED 1980 FUNCTIONS.
TECHNICAL SUPPORT GPC WILL CONDUCT GN-438 D.O. 07 IRB 84-02 2395 IRB C-84/II/13 CORRES. PROCEDURES AND PERIODIC SURVEILLANCE FOSTER TO J.P.
DOCUMENTATION TESTS OF WESTINGROUSE 0'REILLY.
RELAYS USED IN REACTOR NOVEMBER 13 PROTECTION SYSTEM TO 1984 INSURE MALFUNCTIONING RELAYS WILL BE DETECTED AND REPAIRED OR REPLACED.
SURVEILLANCE TESTING PRESERVICE EXAMINATION 07 SEE GL 84-13.
2405 NRC QUEST. Q210 47 CORRES. PROGRAMS WILL BE PERFORMED ON SNUBBERS INSTALLED IN SAFETY RELATED SYSTEMS. AND SNUBBERS WHOSE FAILURE WOULD AFFECT A SAFETY SYSTEM.
INSERVICE INSPECTION THE IST PROGRAMS WILL 07 2897 NRC QUEST. Q210. 49 CORRES. PROGRAMS DESCRIBE THE PUMPS AND VALVES TO BE TESTED.
TESTING FREQUENCIES.
AND RELIEF REQUESTS ALONG WITH JUSTIFICATION FOR
- RELIEF REQUESTS.
2406 NRC QUEST. Q241, 19 SETTLEMENT THE SETTLEMENT 05.07 g
CORRES. MONITORING PROGRAM MONITORING PROGRAM WILL BE A SEPARATE PROGRAM CONTROLLED BY PLANT PROCEDURBS.
1 C
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===-===-== ======
TITLE MODULE REMARKS COMMITMENT COMMITMENT COMMITMENT DOCUMENT / FEATURE NUMBER SOURCE SECTION SUBJECT
=======e========= ===m.================= ===== ========= ===-== =================
== == = ===== ====-======
07 2407 NRC QUEST. Q250. I SURVEILLANCE TESTING PRESERVICE EXAMINATION CORRES. PROGRAMS OF THE FULL LENGTH OF EACH TUBE IN EACH STEAM GENERATOR USING EDDY-CURRENT TECHNIQUE TO ESTABLISH THE BASE LINE CONDITION IS DONE IN ACCORDANCE WITH TECH SPECS add RG 1.83.
SURVEILLANCE TESTING ULTRASONIC EXAMINATION 07 2408 NRC QUEST. Q250. 2 CORRES. PROGRAMS OF REACTOR PRESSURE VESSEL WELDS WILL BE PERFORMED PER REG GUIDE I.150 AND APPENDIX A.
EXAMINATIONS WILL SPECIFICALLY INCLUDE THE BELTLINE REGION WELDS ONLY.
INSERVICE INSPECTION PROCEDURES WILL BE 07 2900 NRC QUEST. Q250. 3 CORRES. PROGRAMS DEVELOPED AND DEMONSTRATED TO ACCURATELT DETECT FLAWS ORIGINATIPG IN WELD AND ADJACENT BASE MATERIAL FOR CAST STAINLESS STEEL WELDMENTS IN REACTOR COOLANT PIPING.
SURVEILLANCE TESTING APPENDIX III WILL BE OT 2409 NRC QUEST. Q250. 4 CORRES. PROGRAMS USED FOR EXAMINATION OF AUSTENITIC PIPING WELDS. WREN EXAMINATION CAN ONLY BE CONDUCTED FROM ONE SIDE OF THE WELD.
OTHER ANGLES MAY BE USED TO ENSURE ADEQUATE EXAMINATION.
O O O O O O O
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===:-:=========~========-====,=-
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========e============= 1 NUMBER COMMITMENT COMMITMENT COMMITMENT DOCUMENT / FEATURE TITLE MODULE REMARKS SOURCE SECTION SUBJECT
== ======,=== =-============== =============,====== ====================== =====e========== ====== ==============
INSERVICE INSPECTION ANY CRACKLIKF 07 2901 NRC QUEST. 0250. 4 CORRES. PROGRAMS INDICATION. REGARDLESS OF AMPLITUDE. WILL BE INVESTIGATED AND RECORDED BY A LEVEL II OR III EXAMINER TO ACCURATELY IDENTIFY AND LOCATE THE INDICATION.
ENGINEERING- IF CP PURCRASES SPENT 07 2906 NRC QUEST. Q281. 3 '
CORRES. PROCEDURES AND FUEL STORAGE RACES DOCUMENTATION CONTAINING POISONOUS MATERIALS, AN INSERVICE INSPECTION PROGRAM WILL BE DEVELOPED TO ENSURE TREIR INTEGRITY.
NRC QUEST. Q410. 25 CONDUCT OF WATERTIGHT DOOR 07 SEE ALSO FSAR 2455 12.3.1.2.
CORRES. OPERATIONS POSITIONS WILL BE CONTROLLED BY ADMINISTRATIVE PROCEDURES.
NRC QUEST. 0410. 25 MAINTENANCE WATERTIGHT DOOR 07 THIS APPLIES ONLY TO 2456 THOSE WATERTIGRT CORRES. PROCEDURES AND GASKETS AND SEALS WILL DOCUMENTATION BE INSPECTED EVERY 18 DOORS NOT ADDRESSED MONTRS. BY TECHNICAL SPEC NRC QUEST. 0410. 52 MAINTENANCE GPC PREVENTIVE 07 2457 CORRES. PROCEDURES AND MAINTENANCE PROCEDURES DOCUMENTATION CONTAIN STEPS WHICH ARE TAKEN TO ENSURE TRE EMERGENCY DIESEL GENERATOR BLECTRICAL CABINETS ARE CLEANED PERIODICALLY.
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T Page No. 144 12/02/85 TABLE 3. 2- 1 COMMITMENTS FOR PLANT
====================1 === ==
OPERATIONS AND SUPPORT
= == = == =~ =====-.-
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OPERATIONS OPhkAT10N FROM REMOTE 07 2458 NRC QUEST. Q410. 57 CORRES. PROCEDURES AND SHUTDOWN PANEL DOCUMENTATION PROCEDURES WILL ADDRESS MANPOWER REQUIREMENTS AND MANUAL ACTIONS TO ACCOMPLISR REMOTE SHUTDOWN.
NRC QUEST. Q420. 2 OPERATIONS LOSS OF INSTRUMENT 07 2460 CORRES. PROCEDURES AND POWER PROCEDURE WILL DOCUMENTATION ADDRESS ITEM 2 OF IE BULLETIN 79-27 AND WILL IDENTIFY VARIOUS COMPONENTS AFFECTED BY POWER FAILURES.
MAINTENANCE PROCEDURES ADDRESSING 07 2464 NRC QUEST. Q420. 16 CORRES. PROCEDURES AND RESPONSE TIME TESTING DOCUMENTATION OF BOP & MSSS PROTECTION SYSTEMS WILL CONFORM TO REG GUIDE 1.118 POSITION C.5 (SEE FSAR PARAGRAPH 1.9.118),
AND IEEE 338, SECTION 6.3.4.
NRC QUEST. Q420. 16 CONDUCT OF VEGP WILL USE 07 2466 CORRES. MAINTENANCE INSTALLED INSTRUMENTS FOR PRESSURE AND TEMPERATURE SENSORS FOR RESPONCE TIME TESTING OF BOP AND NSSS PROTECTION SYSTEMS.
OPERATIONS REACTOR TRIP ON 07 2467 NRC QUEST. Q420. 20 CORRES. PROCEDURES AND TURBINE TRIP CIRCUITRY a DOCUMENTATION WILL BE TESTED DURING INITIAL PLANT STARTUP.
O O O O O O O
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Page No. 145 .
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TITLE MODULE REMARES COMMITMENT COMMITMENT COMMITMENT DOCUMENT / FEATURE NUMBER SOURCE SECTION SUBJECT
====== == ===-====== -=============== =e================== ==================== = ================ ====== ====================.
1 REACTOR TRIP ON 07 2908 NRC QUEST. Q420. 40 REACTOR PROTECTION CORRES. TURBINE TRIP CIRCUITRY WILL BE TESTED DURING INITIAL PLANT STARTUP AS DISCUSSED IN SECTION 14.2.
NORMALLY LOCKED OPEN 07 2909 NRC QUEST. 0420. 32 OPERATIONS CORRES. PROCEDURES AND VALVES WILL NOT BE DOCUMENTATION MANUALLY CLOSED DURING SYSTEM TESTING OF THE AUEILIARY TEEDWATER SYSTEM.
REACTOR COOLANT PUMP 07 2910 N2C QUEST. 0420. 36 SURVEILLANCE CORRES. PROGRAMS AUEILIARY COMPONENT COOLING WATER SUPPLY AND RETURN ISOLATION VALVES WILL BE TESTED DURING REFUELING OUTAGES.
TWO MAINTENANCE CREWS 07 2472 NRC QUEST. 0430. 1 MAINTENANCE CORRES. ORGANIZATION AND WILL BE ASSIGNED TO ADMINISTRATION THE DIEdEL GENERATORS AS THEIR SYSTEM RESPONSIBILITY. SEE ENTIRE SECTION FOR DETAILS OF RESPONSIBILITIES AND AVAILABILITY OF ASSISTANCE.
CONDUCT OF ONE OPERATOR WILL BE 07 2473 NRC QUEST. 0430. I CORRES. OPERATIONS IMMEDIATELY AVAILABLE FOR DIESEL GENERATOR OPERATIONS. TWO OTHER OPERATORS ARE AVAILABLE AS NEEDED.
WITH OTHERS REASSIGNED a
FROM OTHER SHIFTS.
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OPERATIONS AND SUPPORT
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TITLE MODULE REMARKS NUMBER COMMITMENT COMMITMENT COMMITMENT DOCUMENT /FEATUHE SOURCE SECTION SUBJECT
===== == ===e====,= ============,=== ==================== ================~===== ====== ==-====== ===== ========= ===~====~
OPERATIONS PROCEDURES WILL 07 2474 NRC QUEST. Q430. 2 CORRES. PROCEDURES AND SPECIFY THAT PERIODIC DOCUMENTATION SURVEILLANCE TESTING OF DIESEL GENERATORS SHALL BE INITIATED ONLY FROM THE CONTROL ROOM.
2 OPERATIONS OPERATORS WILL BE MADE 07 2475 NRC QUEST. 0430.
CORRES. PROCEDURES AND AWARE OF BUILT IN 90 DOCUMENTATION SECOND TIME DELAY IN THE DIESEL GENERATOR AND WILL BE INSTRUCTED NOT TO INITIATE MANUAL STARTING OF DIESEL ENGINE DURING THAT PERIOD.
CONDUCT _OF PROCEDURES TO CONTROL 07 2477 NRC QUEST. 0430. 3 CORRES. OPERATIONS DIESEL GEN.
RESTORATION UPON COMPLETION OF MAINTENANCE AND TESTING INCLUDE A CHECKLIST COMPLETED BY MAINTENANCE AND OPS PERSONNE
L. PROCEDURE
S REQUIRE INDEPENDENT VERIFICATION.
NRC QUEST. Q430. SURVEILLANCE TESTING DIESEL GENERATOR TEST 07 2478 3 CORRES. PROGRAMS PROCEDURES WILL REQUIRE THE nTPSEL GENERATORS TO BE TESTED TO A MINIMUM OF 304 OF RATED LOAD DURING SURVEILLANCE TESTING.
O O O O O O O
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O O ~1 o Page No. 147 12/02/85 TABLE 3.2-1 COMMITMENTS FOR PLANT
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COMMITMENT DOCUMENT / FEATURE TITLE MODULE REMARKS NUMBER COMMITMENT COMMITMENT SOURCE SECTION SUBJECT
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TECHNICAL SUPPORT DIESEL GENERATOR - OT 2479 NRC QUEST. Q430. 3 CORRES. PROCEDURES AND PROCEDURES WILL ENSURE DOCUMENTATION THAT IF PROLONGED OPERATION BELOW 30%
LOAD OCCURS. THE DIESEL WILL BE SUBSTANTIALLY LOADED FOR 1 HOUR FOR EVERY 24 ROURS OF OPERATION BELOW 30 %.
MAINTENANCE VEGP IS DEVELOPING 07 2480 NRC QUEST. 0430. 3 CORRES. PROCEDURES AND DIESEL GENERATOR DOCUMENTATION PROCEDURES FOR POST MAINTENANCE / REPAIR TESTING, OPERATION DURING
' TROUBLESROOTING. AND OPERATION DURING A LOSS OF COOLANT ACCIDENT (LOCA).
MAINTENANCE PROJECT MANAGEMENT 07 2491 NRC QUEST. Q430. 3 CORRES. PROCEDURES AND WILL REVIEW DIESEL DOCUMENTATION GENERATOR COMPONENT FAILURE RISTORY FOR TRENDS.
MAINTENANCE PROJECT MANAGEMENT 07 2482 NRC QUEST. 0430. 3 CORRES. PROCEDURES AND WILL REVIEW TDI DOCUMENTATION RECOMMENDATIONS FOR j
DIESEL GENERATOR PREVENTIVE MAINTENANCE FOR APPLICABILITY AT VEGP.
MAINTENANCE MINIMUM FREQUENCY FOR 07
$ 2484 NRC QUEST. 0430. 8 CORRES. PROCEDURES AND TESTING AND DOCUMENTATION CALIBRATING DIESEL g' GENERATOR INSTRUMENTATION WILL BE ANNUALLY.
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COMMITMENT DOCUMENT / FEATURE TITLE MODULE REMARMS NUMBER COMMITMENT COMMITMENT SOURCE SECTION SUBJECT
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OPERATIONS PROLONGhD DIESEL CT 24R5 NRC QUEST. 0430. II CORRES. PROCEDURES AND GENERATOR OPERATION.
DOCUMENTATION VEGP WILL MAKE PROVISIONS BY THE STH DAY OF OPERATION FOR THE DELIVERY OF FUEL OIL.
OPERATIONS DIESEL GENERATOR 07 2486 NRC QUEST. Q430. 11 CORRES. PROCEDURES AND OPERATING PROCEDURES DOCUMENTATION WILL OUTLINE STEPS NECESSARY TO FILL THE STORAGE TANK USING THE MANWAY.
OPERATIONS OPERATING PROCEDURES 07 2487 NRC QUEST. 0430. 12 CORRES. PROCEDURES AND ARE BEING DEVELOPED DOCUMENTATION FOR EMERGENCY VENTING OF THE DIESEL FUEL OIL TANK.
2488 NRC QUEST. Q430. 17 OPERATIONS IF TRAIN A STORAGE 07 CORRES. PROCEDURES AND TANK IS BEING DOCUMENTATION REFILLED. OPERATING PROCEDURES DIRECT TRAIN A DAT TANK TO BE MANUALLY FILLED FROM TRAIN B STORAGE.
2494 NRC QUEST. 0430, 26 OPERATIONS IN THE EVENT TEMP. IN 07 CORRES. PROCEDURES AND THE DIESEL GEN. ROOM DOCUMENTATION DROPS BELOW 50 DEG.,
THE D.G. WILL BE RUN TO PREVENT LOW TEMP.
IN THE COOLING WATER AND LUBE OIL SYSTEMS 2495 NRC QUEST. Q430. 26 OPERATIONS EOP'S DIRECTS THE 07 CORRES. PROCEDURES AND OPERATORS TO STOP THE DOCUMENTATION UNLOADED DIESEL 1' GENERATORS TRAT ARE RUNNING AFTER S.I. AND OFFSITE POWER IS AVAILABLE O O O O O O O
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COMMITMENT DOCUMENT / FEATURE TITLE MODULE REMARKS NUMBER COMMITMENT COMMITMENT SOURCE SECTION SUBJECT
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malNIENANCE PERIODIC INSPECTION OF 07 2496 NRC QUEST. 0430. 28 CORRES. PROCEDURES AND DIESEL GENERATOR DOCUMENTATION JACKET WATER AND LUBE OIL WILL BE PERFORMED TO DETECT JACKET WATER LEAKING INTO LUBE OIL OR LUBE OIL LEAKING INTO JACERT WATER.
CONDUCT OF OPERATIONS SUPERVISOR 07 2498 NRC QUEST. Q430. 35 CORRES. OPERATIONS ON SHIFT WILL HAVE A KET TO INSURE ACCESS TO DIESEL LUBE OIL STORED IN THE WAREHOUSE.
OPERATIONS DIESEL GENERATOR LUBE 07 2499 NRC QUEST. 0430. 35 c0RRFS. PROCEDURES AND OIL ADDITION DOCUMENTATION PROCEDURES WILL INCLUDE VERIFICATION THAT REPECTED CHANGE IN LUBE OIL LEVEL OCCURS FOR VOLUME ADDED.
MATERIALS MANAGEMENT GPC WILL MAINTAIN AN 07 2500 NRC QUEST. Q430. 35 CORRES. ONSITE SUPPLY OF OIL TO ACCOMMODATE A COMPLETE LUBE OIL CHANGE FOR ONE DIESEL GENERATOR. LUBE OIL WILL BE STORED IN TRE' ONSITE WAREHOUSE MANNED AROUND THE CLOCK.
OPERATIONS OPERATING PROCEDURES OT 2501 NRC QUEST. Q430. 35 .
CORRES. PROCEDURES AND WILL INCLUDE DOCUMENTATION PROVISIONS FOR
'i PERIODICALLT CHECKING THE LUBE OIL LEVEL.
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NUMBER COMMITMENT COMMITMENT COMMITMENT DOCUMENT / FEATURE TITLE MODULE REMARKS SOURCE SECTION SUBJECT
=e ====e===== ================ =================- = ====================== ======r ======== ====== =============t
2502 NRC QUEST. Q430. 35 OPERATIONS PHOCEDURES rok OT CORRES. PROCEDURES AND OPERATING THE DEISEL, DOCUMENTATION I.E. PRELUBE. BARRING OVEN AND SHUTDONN WILL PE AVAILABLE LOC A LI.Y IN THE D.G. ROOM.
2503 NRC QUEST. 0430. 36 OPERATIONS GPC WILL ADD MARKINGS 07 CORRES. PORCBDURES AND ON THE DIESEL DOCUMENTATION GENERATOR, ESPECIALLY LUBE OIL LINES. TO ENSURE OIL IS ADDED AT CORRECT LOCATIONS.
PROCEDURES WILL PRECLUDE ENTRY OF DELETERIOUS MATERIALS INTO LUBE OIL BY ERROR.
2505 NRC QUEST. Q430. 44 OPERATIONS OPERATING PRCCEDURES 07 CORRES. PORCEDURES AND WILL ENSURE DG DOCUMENTATION LOUVERED / SCREENED OPENING IS CLEAR OF ANY OBSTRUCTIONS ESPECIALLY DURING ABNORMAL CLIMATIC CONDITIONS, SUCH AS FREEZING RAIN, DUST STORMS, ICE, AND SNOW.
2506 NRC QUEST. 0430. 44 MAINTENANCE MAINTENANCE PROCEDURES 07 CORRES. PROCEDURES AND ARF BEING DEVELOPED TO DOCUMENTATION ENSURE THAT TRE DIESEL INTARE AIR FILTER IS PROPE.1LT MAINTAINED IN ACCORDANCE WITH MANUFACTURER'S RECOMMENDATIONS.
4 4
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O Page No. 151 O 3 o 12/02/85 TABLE 3.2-1 COMMITMENTS FOR PLANT
===-===.==,,,=r=================:-
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NUMBER COMMITMENT COMMITMENT COMMITMENT DOCUMENT / FEATURE TITLE MODULE REMARKS SOURCE SECTION SUBJECT
== ========== ==============e= ======== =========== ====================== ================ ====== ==============
2507 NRC QUEST. 0430. 45 PLAhi MATERIAL ANY Lhai ACCbMULATION OT CORRES. CONDITION INSIDE DIESEL GENERATOR CONTROL CABINETS WILL BE CLEANED OFF PRIOR TO PLANT STARTUP.
2508 NRC QUEST. 0430. 45 PLANT MATERIAL GENERAL HOUSECLEANING 07 CORRES. CONDITION AND MAINTENANCE AT REGULAR INTERVALS WILL BE PERFORMED TO PREVENT ACCUMULATION OF DUST ON DIESEL GENERATOR ELECTRICAL COMPONENTS.
2509 NRC QUEST. Q430. 57 MAINTENANCE THE SWITCHTARD BATTERY 07 SEE ALSO SECTION l 1.9.129. I CORRES. PROCEDURES AND PERIODIC MAINTENANCE DOCUMENTATION WILL COMPLY WITH IEEE 450-1975 AS STATED IN FSAR SECTION 8.2.2.5.
2510 NRC QUEST. 0430. 59 OPERATIONS WHEN BOTH CLASS lE - 07 CORRES. PROCEDURES AND ELECTRICAL DIST.
DOCUMENTATION TRAINS MUST BE SUPPLIED FROM THE SAME RESERVE AURILIARY TRANSFORMER, NON lE ELECTRICAL LOADS WILL BE ADMINISTRATIVELY SRED.
2411 NRC QUEST. 0430. 59 OPERATIONS DURING PREOPERATIONAL 03A,07 CORRES. PROCEDURES AND AND STARTUP PHASES AT DOCUMENTATION VEGP. EACH RAT WILL BE TESTED TO EVALUATE ITS LOADING CAPABILITY.
2511 NRC QUEST. 0430. 60 OPERATIONS OPERATORS WILL BE 07 CORRES. PROCEDURES AND PROVIDED THE MAXIMUM DOCUMENTAION ELECTRICAL LOAD WRICH CAN BE DRAWN FROM THE RESERVE AURILIART TRANSFORMERS AND THE EMERGENCT DIESEL GENERATORS.
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TITLE MODULE REMARKS NUMBER COMMITMENT COMMITMENT COMMITMENT DOCUMENT / FEATURE SOURCE SECTION SUBJECT
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OPERATIONS THE AC INPUT TO IHE 03A,07 2912 NRC QUEST. Q430. 61 CORRES. PROCEDURES AND 10-KVA INVERTERS IS DOCUMENTATION REQUIRED FOR INITIAL STARTUP OF THE INVERTER. THESE BREAEERS ARE TO BE OPENED AFTER THIS IS ACCOMPLISHED TO ISOLATE THE AC SOURCE.
SURVEILLANCE TESTING TWO CIRCUIT BREAKERS 07 2512 NRC QUEST. 0430. 62 CORRES. WHICH PROVIDE ISOLATION BETWEEN 480-V BUS AND 12 0- V HEATER CIRCUITS Will BE TESTED PhR10DICALLY TO CRITERIA FOR PROTECTIVE DEVICES USED FOR CONTAINMENT ELECTRICAL PENETRATIONS.
MAINTENANCE CIRCUIT BREAKERS AND 07 2513 NRC QUEST. Q430. 62 CORRES. PROCEDURES AND FUSES LOCATED IN DOCUMENTATION PRIMARY AND SECONDARY OF THE 120/24-V TRANSFORMERS FOR NON-CLASS lE MONITOR LIGHT BOXES WILL BE TESTED PERIODICALLY.
OPERATIONS VALVES HV-8803A & B 07 VALVES ARE 2515 NRC QUEST. 0430. 73 IDENTIFIED IN FSAR CORRES. PROCEDURES AND WILL HAVE POWER DOCUMENTATION LOCKOUT USING LOCKED SECT. 8.3.1.1.11.
OPEN BREAKERS. CIRCUIT
( BREAKERS FOR THESE l VALVES WILL BE I
l PADLOCKED IN OPEN I
DURING REACTOR POWER OPERATION, AFTER ALIGNING VALVES AS REQUIRED.
I l
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O O O > c Page No. 153 12/02/85 TABLE 3.2 I COMMITMENTS FOR PLANT
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4 TITLE MODULE REMARES NUMBER COMMITMENT COMMITMENT COMMITMENT DOCUMENT / FEATURE SOURCE SECTION SUBJECT =,==e=========== ====== ====================
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ACCbMu6ATOR ISOLATION 07 2516 NRC QUEST. 4430. 73 OPERATIONS CORRES. PROCEDURES AND VALVE CIRCUIT BREARERS DOCUMENTATION WILL BE PADLOCEED OPEN DURING REACTOR PONER OPERATION.
MAINTENANCE VERIFICATION OF TRE 07 2519 NRC QUEST. Q440. 10 CORRES. PROCEDURES AND ACCURACT OF DOCUMENTATION INSTRUMENTATION IS ACCOMPLISHED BT CALIBRATION OF THE INSTRUMENTATION.
OPERATIONS PRESSURIZER SAFETT AND 07 ,
2520 NRC QUEST. Q440. II CORRES. PORCEDURES AND RELIEF VALVE SETPOINTS DOCUMENTATION WILL BE VERIFIED DURING INITIAL STARTUP PROCEDURES.
OPERATIONS LOSS OF INSTRUMENT AIR 07 2522 NRC QUEST. Q440. 28 CORRES. PROCEDURES AND IS ADDRESSED IN i
DOCUMENTAION ABMORMAL OPERATING PROCEDURES. STEPS WILL DIRECT OPERATOR
' TO TARE MANUAL ACTIONS TO CONTROL COOLDONN RATE.
OPERATIONS RESIDUAL HEAT REMOVAL 07 2523 NRC QUEST. 0440. 32 CORRES. PROCEDURES AND STSTEM SHALL BE DOCUMENTATION COMPLETELY VENTED FOLLOWING MAINTENANCE AND IS OPERATED IN A MANNER WHICH WILL PRECLUDE WATER RAMMER OCCURANCES.
OPERATIONS INTERRUPTION OF 07 2524 NRC QUEST. Q440.. 44 CORRES. PROCEDURES AND SHUTDOWN COOLING - IF DOCUMENTAION OPERATOR CANNOT RESTORE ALTERNATE RER LOOP TO OPERATION.
PROCEDURES WILL DIRECT USE OF ALTERNATE LONG-TERM HEAT REMOVAL
(. PATR.
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r====-====-=== ===== ==================
== ====c===== ===============- ===============-==== = ==============
NRC QUEST. 0440. 50 SURVEILLANCE TESTING FOR PUMPS USED FOR 07 252G CORHES. PROGRAMS LONG TERM CORE COOLING FOLLOWING A LOCA, PERFORMANCE IS CHECKED AT THE PLANT SITE PERIODICALLY IN ACCORDANCE WITH ASME SECTION RI.
NRC QUEST. 0440. 54 OPERATIONS PROCEDURES REQUIRE 07 2527 CORRES. PROCEDURES AND INSPECTION OF DOCUMENTATION CONTAINMENT SUMP COMPONENTS (TRAF'l RACKS, SCREENF, SUCTION INLEis) FOR VISUAL EVIDENCE OF STRUCTURAL DISTRESS OR CORROSION AFTER REFUBLING OR EXTENDED OUTAGE.
NRC QUEST. 0440. 70 OPERATIONS ALL EMERGENCT CORE 07 2913 CORRES. PROCEDURES AND COOLING SYSTEM DOCUMENTATION COMPONENTS ARE EITHER TESTABLE ONLINE OR HAVE POWER LOCKED OUT.
2529 NRC QUEST. Q440. 98 HEACTOR ENGINEERING CORE DELTA T AND A 07 CORRES. CALCULATED CALORIMETRIC FLOW AT A LOW POWER LEVEL TO BE OBTAINED FROM THE NATURAL CIRCULATION TEST.
2530 NRC QUEST. Q440.116 CONDUCT OF REMOVAL OF POWER TO 07 THESE FOUR VALVES 15 CORRES. OPERATIONS NOT APPLICABLE SINCE THEY ARE RAND VALVES.
THESE VALVES WILL BE PLACED IN A VALVE LINE-UP PROCEDURE PRIOR TO ENTRY INTO MODE G.
O O O O O O O
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DOCUMENT / FEATURE TITLE MODULE REMARKS NUMBER COMMITMENT COMMITMENT COMMITMENT SOURCE SECTION SUBJECT
e== == ========== ================ ==================== ====================== ================ ====== =================
OPERATIONS THE RECOMMRNDATIONS 07
- 2915 NRC QUEST. Q440.131 CORRES. PROCEDURES AND AND CONCLUSIONS OF THE DOCUMENTATION GENERIC STUDY FOR i RESPONSE TO RADIOLOGICAL CONSEQUENCES OF A STEAM GENERATOR TUBE RUPTURE AND RESPONSE TO STEAM OENERATOR OVERFILL WILL BE IMPLEMENTED.
4 PRESSURIZER VALVE PRESSURIZER PORV AND 02,07 253I NRC QUEST. 0440.142 CORRES. INDICATION SAFETY VALVE INDICATION IS ON THE MAIN CONTROL BOARD. IT WILL BE INCLUDED IN OPERATING PROCEDURES AND TRAINING.
MAINTENANCE GPC WILL IMPLEMENT A 07 2535 NRC QUEST. Q460. 4 CORRES. PROCEDURES AND MAINTENANCE AND 4
DOCUMENTATION SURVEILLANCE PROGRAM-COMENSURATE WITH QA CRITERIA FOR DESIGN .
AND INSTALLATION OF MAIN CONDENSER EVACUATION SYSTEM AND TURBINE GLAND SEALING SYSTEM.
WASTE PROCESSING SPECIFIC MEANS OF 07,9A 2541 NRC QUEST. 0460. IO CORRES. WASTE CLASSIFICATION WILL BE DEVELOPED AS A PART OF PLANT PROCEDURES.
WASTE PROCESSING RECORD EEEPING AND 07 2542 NRC QUEST. 0460. 10 CORRES. ADMINISTRATIVE CONTROLS FOR STORAGE AND UTILIZATION OF POLYMER, CATALYST, AND
' PROMOTOR WILL BE DEVELOPED AS A PART OF PROGRAM FOR DRY
! #g, ~
PRODUCT SOLIDIFICATION d- STSTEM.
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OPERATIONS AND SUPPORT
,============ ==
COMMITMENT DOCUMENT / FEATURE TITLE MODULE REMARES NUMBER COMMITMENT COMMITMENT SOURCE SECTION SUBJECT
== ========== ===,============ =====: ============= = = = = = = = = = = = = = = = = = = = = - - ================ ====== =============
WASTE PROCESSING BASED ON AMOUNT OF DHY 07 2543 NRC QUEST. Q460. 14 CORRES. PRODUCT TO BE SOLIDIFIED, PROCESS CONTROL PROGRAM WILL DETERMINE AMOUNT OF CATALYST TO BE ADDED TO DRUM SUCH THAT DRl!M SURFACE TEMPERATURE WILL PEAK AT APPROXIMATELY 230F.
NRC QUEST. Q460. 14 MATERIAL MANAGEMENT GPC PLANT PROCEDURES 07 2544 CORRES. ADDRESS THE RECEIPT OF FLAMMABLE MATERIALS ONSITE.
NRC QUEST. Q471. 7 CRITICALITY MONITORS THE SPECIAL NUCLEAR 07 2546 CORRES. MATERIALS LICENSE APPLICATION WILL CONTAIN THE REQUIRED EXEMPTION TO 10CFR70.24 (b).
NRC QUEST. Q480. 5 OPERATIONS CONTAINMENT INSPECTION 07 2553 CORRES. PROCEDURES AND - OPERATING PROCEDURES DOCUMENTATION REQUIRE AN INSPECTION OF CONTAINMENT (SUMP AREA IN PARTICULAR) TO IDENTIFY MATERIALS CAPABLE OF BLOCEING THE SUMP DURING RECIRCULATION.
NRC QUEST. Q480. 24 INSERVICE INSPECTION CONTAINMENT PRESSURE 07 2916 CORRES. PROGRAMS AND REACTOR VESSEL LEVEL INSTRUME%TATION PENETRATIONS ARE VERIFIED DURING PERIODIC TYPE A TESTS.
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TITLE MODULE REMARKS NUMBER COMMITMENT COMMITMENT COMMITMENT DOCUMENT / FEATURE SOURCE SECTION SUBJECT
==e= ====e=========== ============e== r=== ===============r===e== ================ ====== ==============
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MAINTehaNCE CONTAINMENT HATCHES 07 25b9 NHC QUEST. u480. 34 CORRES. PROCEDURFS AND ARE TYPE B TESTED AT DOCUMENTATION INTERVALS SPECIFIED IN TECH. SPECS. INTERVALS ARE IN ACCORDANCE WITH 10CFR50, APP. J.
EXCEPT FOR MULTIPLE OPENINGS OF AIRLOCKS, WHICH ARE TESTED EVERY 3 DAYS.
MAINTENANCE CONTAINMENT AIR LOCKS 07 2560 NRC QUEST. 0480. 34 CORRES. PROCEDURES AND WILL BE TESTED PRIOR DOCUMENTATION TO ESTABLISHING CONTAINMENT INTEGRITY ONLY IF MAINTENANCE HAS BEEN PERFORMED ON TRE AIR LOCK WHICH COULD AFFECT THE AIR LOCK SEALING CAPABILITY.
MAINTENANCE LOOSE PARTS MONITORING 07 2564 NRC QUEST. 0492. 1 CORRES. PROCEDURES AND SYSTEM CALIBRATION DOCUMENTATION PROCEDURES WILL BE PREPARED IN ACCORDANCE WITH MANUFACTURER'S RECOMMENDATIONS.
MAINTENANCE LOOSE PARTS MONITORING 07 2565 NRC QUEST. Q492. 1 CORRES. PROCEDURES AND SYSTEM CALIBRATION AND DOCUMENTATION IMPLEMENTATION-PROCEDURES WILL BE COVERED IN DIGITAL METAL IMPACT MONITORING SYSTEM BASELINE REPORT PLANT PERFORMANCE RCS FLOWRATE WILL BE 07 2567 NRC QUEST. Q492. 5 CORRES. MONITORING MEASURED PRIOR TO INITIAL CRITICALITY, AT 50 PERCENT POWER.
' AND AT LEAST ONCE PER 18 MONTHS USING THE SAME METHOD OF C' MEASUREMENT.
s C
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COMMITMENT DOCUMENT / FEATURE TITLE MODULE REMARKS NUMBER COMMITMENT COMMITMENT SOURCE SECTION SUBJECT
,,==== == ========== ================ =================-== = ==================== ================ =-==== ===================
2568 NRC QUEST. Q630. 8 FIRE PROTECTION PERSONNEL ALLOWED 07 SEE ALSO Q630.17.
CORRES. PROGRAM UNESCORTED ACCESS IN PROTECTED AREA WILL RECEIVE TRAINING IN:
FIRE PROTECTION ADMIN CONTROLS, FIRE BARRIERS AND SEALS, RESPONSE TO FIRE ALARMS, ACTIONS UPON DISCOVERT OF FIRES.
NRC QUEST. 0630. 8 FIRE PROTECTION PERSONNEL RESPONSIBLE 07 2569 CORRES. PROGRAM FOR PERFORMING MAINTENANCE AND INSPECTION OF FIRE PROTECTION EQUIPMENT WILL RECEIVE TRAINING IN CODES. STANDARDS, PROCEDURES. AND SPECIFICATIONS NECESSART TO PERFORM JOB.
2570 NRC QUEST. 0630. Il FIRE PROTECTION FIRE BRICADE TRAINING 07 CORRES. PROGRAM WILL BE TAUCRT BT OUALIFIED PERSONNEL.
QUALIFICATION OF FIRE BRIGADE TRAINING PERSONNEL IS DISCUSSED IN SUBSECTION 9.5.1 AND APPENDIX 98 SECTION C.3.
2571 NRC QUEST. 0630. 12 FIRE PROTECTION PRACTICE SESSIONS ON 07 SEE ALSO APPENDIX CORRES. PROGRAM THE PROPER METROD OF 98, C.3.d(2)
FIGHTING VARIOUS TTPES OF FIRES THAT COULD OCCUR IN A NUCLEAR POWER PLANT SRALL BE 4 i HELD FOR RACH SHIFT BRICADE.
r a
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OPERATIONS AND SDPPORT
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COMMITMENT COMMITMENT DOCLNENT/ FEATURE TITLE MODULE HEMARES NUMBER COMMITMENT SOURCE SECTION SUBJECT '
== ========== ================ ==-====e============ ====================== ================ ====== ==============
NRC QUEST. 0630. 14 FIRE PROTECTION FIRE DRILLS WILL DE 07 MRR APPENDIX 98, 2572 CORRES. PROGRAM PERFORMED QUARTERLY C.3.d(T)(a).
FOR EACH SHIFT'S FIRE BRIGADE.
NRC QUEST. 0630. 15 FIRE PROTECTION A GROUP OF QUALIFIED 07 SEE APPENDIX 98, 2573 CORRES. PROGRAM INDIVIDUALS C.3.d(T)(e).
INDEPENDENT OF GEORGIA POWER COMPANY WILL ,
- CRITIQUE AN UNANNOUNCED FIRE DRILL AT LEAST ONCE EVERY 3 YEARS.
NRC QUEST. 0630. 16 FIRE PROTECTION INDIVIDUAL TRAINING 07 SEE APPENDIX 98, 2574 CnRRES. PROGRAM RECORDS FOR RACH FIRE C.3.d(8).
BRIGADE MEMBER, INCLUDING DRILL CRITIQUES. WILL BE MAINTAINED FOR AT LEAST 3 TEARS.
2580 NRC QUEST. 0640. 6 CONDUCT OF TEST EXCEPTIONS OPEN 07 CORRES. OPERATIONS AT FUEL LOADING EVALUATED PRIOR TO FUEL LOAD TO DETERMINE IMPACT. EVALUATION WILL INCLUDE A TECHNICAL JUSTIFICATION FOR TEST DELAY AND SCHEDULE FOR COMPLETION.
2583 NRC QUEST. 0640. 12 EMBRGENCT PARTIAL LOADS ON ESF 03A,07 CORRES. VENTILATION SYSTEMS EQUIPMENT ROOM COOLERS WILL BE USED TO VERIFY FULL LOAD CAPABILITIES BY DEMONSTRATING THAT
. COOLERS HAVE THE HEAT
! ' TRANSFER CAPABILITY REQUIRED BY DESIGN.
, (0640.12)
C
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== ========== ================ =================e== ====================== == ============= =====- ==============
PLANT PERFORMANCE SHOULD THE 03A,07 2585 NRC QUEST. 0640. 12 CORRES. MONITORING MEASURED / CALCULATED UA FOR A PARTICULAR ESFAS EQUIPMENT ROOM COOLER FALL SRORT OF DESIGN, FAN FLOW AND WATER FLOW ADJUSTMENTS WILL BE MADE TO BRING THE COIL UP TO DESIGN REQUIREMENTS.
PRIMARY AND CHEMISTRY REQUIREMENTS 03A 07 BORIC ACID BLENDER, 2596 NRC QUEST. 0640. 23 SECONDARY CREMISTRY OF REG GUIDE 1.68 9B NUCLEAR CORRES.
TEST ABSTRACT APPENDIX A.4.h. ARE SAMPLING REACTOR SATISFIED BY COOLANT SYSTEM FOR PERFORMING THE RCS AND THE BOP PREOPERATIONAL TESTS. SAMPLING, CONDENSATE DEMIN, AND CONDENSATE CREMICAL INJECTION FOR THE SECONDART SYSTEMS.
2600 NRC QUEF, 0640, 30 OPERATIONS VERIFICATION OF THE 07 CORRES. PROCEDURES AND CAPACITY OF TRE DOCUMENTATION PRESSURIZER PORV'S WILL BE DEMONSTRATED IN THE LARGE LOAD REDUCTION TEST.
NRC QUEST. Q730. STATION BLACEOUT STATION BLACEOUT EVENT 02,07 2607 1 CORRES. REVIEW AND TRAINING REVIEW AND TRAINING WILL BE COMPLETED PRIOR TO FUEL LOAD DATE. VEGP NILL UTILIZE THE WESTINGHOUSE OWNERS GROUP ERGS FOR DEVELOPMENT OF EMERGENCY OPERATING 1 PROCEDURES.
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Page No. 161 12/02/85 TABLE 3.2-1 COMMITMENTS FOR PLANT
-====--===e==-====================
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DOCUMENT / FEATURE TITLE MODULE REMARKS NUMBER COMMITMENT COMMITMENT COMMITMENT SOURCE SECTION SUBJECT
==== == ========-= ================ ==-==-============ = ====e================= ================ ====== ===================
NRC QUEST. 0730. SURVEILLA*CE TESTING INSERVICE INSPFCTTON 07 2608 I CORRES. PROGRAMS AND TECH SPEC REQUIREMENTS WILL ENSURE THAT GEORGIA POWER STAFF AND N3C STAFF ARE ALERTED TO TUBE DEGRADATION SHOULD IT OCCUR.
OPERATIONS PROCEDURES WILL 07 2609 NRC QUEST. 0730. 1 CORRES. PROCEDURES AND REQUIRE INSPECTIONS DOCUMENTATION FOR DEBRIS CAPABLE OF CONTAINMENT SUMP BLOCKAGE.
2612 S E I. F INIT. C-82/DH/10 OPERATIONS AFTER DIAGNOSING THE 07 10CTR50.55(E) REPORT PROCEDURES AND INITIATING EVENT AND ON CRARGING PUMP CORRES.
DOCUMENTATION ASSURING TRAT OPERATION.
REQUIREMENTS FOR g
TERMINATION OF SAFETT INJECTION HAVE BEEN MET. THE CHARGING PUMP SUBSTSTEM CAN BE REALIGNED FOR NORMAL OPERATION.
GPC WILL INCORPORATE GN-254. D.O. 07 WESTINGROUSE LETTER 2614 SELF INIT. C-83/09/06 MAINTENANCE MS-EPR-2744 TO MRC CORRES. PROCEDURES AND WESTINGROUSE BULLETIN FOSTER TO J.P.
DOCUMENTATION NSD-TB-83-03 ON O'RRILLT. DATED MARCH 31 TESTING PROCEDURES FOR SEPTEMBER 6 1983.
MECHANISMS FOR MODEL BD AND DS CIRCUIT BREAEER SHUNTS AND UV COILS INTO PLANT MAINTNEANCE PROCEDURES l
WATERRAMMER IN GN-352,.D.O. OT 2615 SELF INIT. C-84/04/26 OPERATIONS CORRES. PROCEDURES AND AUXILIART FREDWATER - FOSTER TO H.R.
DOCUMENTATION THERM 0 WELLS ALLOW DENTON. APRIL TEMPERATURE INCREASES 26 1984 TO BE DETECTED AND PROPER OPERATING PROCEDURES TO BE IMPLEMENTED.
p 4
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OPERATIONS AND SUPPORT
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261G SELF INIT. C-84/04/26 OPERATIONS WATEHHAMMER IN RCS GN 352, 0.0. 07 CORRES. PROCEDURES AND IF ANY PROBLEMS ARE FOSTER TO H.R.
DOCUMENTATION EXPERIENCED DURING DENTON, APRIL PREOPERATIONAL TEST 5, 26, 1984 THEY WILL BE ELIMINATED BY MODIFYING OPERATING PROCEDURES.
MINIM 1 ZING WATER AND WATERRAMMER IN MAIN GN-352, D.O. 07 2617 SELF INIT. C-84/04/2G CORRES. STEAM HAMMER EFFECTS FEEDWATER - FOSTER TO H.R.
TEMPERATURE DENTON, APRIL MONITORING, ALARM, AND 26, 1984 OPERATIONAL PROCEDURES MINIMIZE OR ELIMINATE WATERHAMMER.
DIESEL GENERATOR TRANSAMERICA DELAVAL, GN 441 D.O. 07 2619 SELF INIT. C-84/ll/12 CORRES. PROGRAM INC (TDI) INTENDS TO FOSTER TO J.P.
PERFORM A PLANT UNIQUE O'REILLY, ANALYSIS OF LUBE OIL NOVEMBER 12, PIPING TO TURBOCRARGER 1984 THRUST BEARING AFTER ENGINE AND ASSOCIATFD EQUIPMENT HAS BEEN INSTALLED.
?620 SELF INIT. C-84/ll/12 DIESEL GENER ATOR TDI WILL INSTALL GN-441, D.O. 07 CORRES. PROGRAM TEMPORARY DRIP LUBE FOSTER TO J.P.
OIL PIPING FOR THE 0'REILLY, TURBO-CHARGER TRRUST NOVEMBER 12 BEARING TO DETERMINE 1984 ACTUAL SIZE AND ARRANGEMENT OF PERMANENT PIPING.
2621 SELF INIT. C-84/12/06 BETTIS DAMPER AND BETTIS DAMPER AND GN-491, D.O. 07 10CFR50.55(E) REPORT CORRES. VALVE ACTUATORS VALVE ACTUATORS IN FOSTER TO J.P. ON BETTIS DAMPER AND ATTACRMENTS A AND C OF O'REILLY, VALVE AC Tf' ATORS .
TRIS CORRESPONDENCE DECEMBER 6, 1984 WILL BE SERVICED WITH NEW SEALS AND DOW CORNING MOLYEOTE 44 LUBRICANT PRIOR TO FUEL LOAD.
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BETTIS DAMPER AND BETTIS DAMPER AND GN-491, 07 10CFR90 99fR) REPORT J 2622 SELF INIT. C-84/12/06 VALVE ACTUATORS IN D.O. FOSTER TO ON BETTIS DAMPER AND CORRES. VALVE ACTUATORS ATTACHMENT B 0F THIS J.P 0'REILLT, VALVE ACTUATORS.
LETTER WILL BE DECEMBER 6, 1984 RECONDITIONED UNLESS VENDOR TEST
- INFORMATION INDICATES ACTUATORS WILL CLOSE WITHIN THE REQUIRED TIME INTERVAL.
OPEN ITEMS - VOGTLE SETTLEMENT M9NITORING GN-623 J.A. 07 2921 SELF INIT. C-85/05/21 CORRES. SETTLEMENT FOR BOTH UNITS WILL BE BAILEY TO H.R.
CONTINUED FOR DENTON, MAT 21, IMPORTANT MAREERS 1985 THROUGH THE FIRST YEAR FOLLOWING ISSUANCE OF OPERATING LICENSE FOR ,
UNIT 2 AT A FREQUENCT INTERVAL NOT TO EXCEED 90 DATS.
OPEN ITEMS - VOGTLE AT THE END OF THE GN-623, J.A. 07 2922 SELF INIT. C-85/05/2I SETTLEMENT MONITORING BAILET TO R.R.
CORRES. SETTLEMENT PERIOD, THE LICENS$E DENTON, MAT 21 WILL PROVIDE A BREIF 1985 TECHNICAL REPORT WITH SUPPORTING SETTLEMENT DATA AND GRAPHICAL PLOTS.
OPEN ITEMS - V0GTLE SETTLEMENT MONITORING GN-623 J.A. 07 2923 SELF INIT. C-85/05/2I WILL BE PERFORMED BAILET TO H.R.
CoRRRs. SETTLEMENT IMMEDIATELT AFTER ANY DENTON, MAT 21 EARTRQ9AEE EVENT EQUAL 1985 TO OR EXCEEDING A FREE-FIELD ACCELEkATION OF I/2 OBE ( 06G).
. I 1
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Page No- 164 12/02/R5 TABLE 3.2-1 COMMITMENTS FOR PLANT
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2924 SELF INIT. C-85/05/21 OPEN ITEMS - V0GTLE A SETTLEMENT SURVEY GN-623 J.A. 07 CORRES. SETTLEMENT WILL BE PEHFORMED IF DAILEY TO H.R.
THE GROUNDWATER LEVEL DENTON, MAY 21, IN THE POWER BLOCK 1985 AREA DROPS MORE THAN 10 FEET BELOW REFERENCE GROUNDWATER LEVEL IN MORE THAN ONE OBSERVATION WELL MONITORING THE BACKFILL.
2925 SELF INIT. C-85/05/21 OPEN ITEMS - VOGTLE REFERENCE GROUNDWATER GN-623 J.A. 07 CORRES. SETTLEMENT LEVEL WILL BE VERIFIED BAILEY TO H.R.
THROUGH MONITORING THE DENTON, MAY 21, OBSERV4lldN WELLS IN 1985 THE POWER BLOCK BACKF?LL FOR A TWO YEAR PERIOD (JUNE 1987).
2926 SELF INIT. C-85/05/21 OPEN ITEMS - VOGTLE THROUGROUT THE LIFE OF GN-623, J.A. 07 CORRES. SETTLEMENT THE PLANT IMPORTANT BAILEY TO R.R.
SETTLEMENT MAREERS DENTON, MAY 21 WHICH ARE DESTROYED OR 1985 BECOME INACCESSIBLE WILL BE REPLACED WITH MARKERS a5 NEAR AS POSSf3LE TO THEIR ORIGINAL LOCATIONS.
2623 TECH. 6. 1. 2 CONDUCT OF OPERATIONS SUPERVISOR 07 SPEC. OPERATIONS OR A DR31GNATED INDIVIDUAL SHALL BE RESPONSIBLE FOR THE CONTROL ROOM COMMAND FUNCTION.
2625 TECH. 6. 2-1 CONDUCT OF CONTROL ROOM COMMAND 07 SPEC. OPERATIONS SHALL BE ASSUMED BY A LICEWSED SRO WHEN c
EITHER UNIT IS IN MODE 1, 2, 3, OR 4 AND THE OPERATIONS SUPERVISOR IS ABSBNT.
O O O O O O O
=
0 0 -O O i O O Page No. 165 12/02/R5 T A B l.E ** . 2 - 1 COMMITMENTS FOR PLANT
=============.-=============== ===-
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-e= ==========-=======
NUMBER COMMITMENT COMMITMENT COMMITMENT DOCUMENT / FEATURE TITLE MODULE REMARKS SOURCE SECTION SUBJECT
== ========== ============== = = ===========-====== ===========e========== ================ ====== =========.e====
262b TECH. O. 2-1 CONDUCT OF CONTROL E66M COMMAND 07 SPEC. OPERATIONS SHALL BE ASSUMED BT EITHER A LICENSED RO OR SRO WHEN BOTH UNITS ARE IN MODE 5 OR 6 AND THE OPERATIONS SUPERVISOR IS ABSBNT.
2627 TECH. 6. 2-1 CONDUCT OF SHIFT CREW COMPOSITION 07 THIS DOES NOT PERMIT SPEC. OPERATIONS MAT BE ONE LESS THAN ANT POSITION TO BE THAT LISTED IN TABLE UNMANNED UPON SHIFT 6.2-1 (EXCFPT FOR THE CHANGE.
OPERATIONS SUPERVISOR)
FOR UP TO 4 HOURS IN ORDER TO ACCDMODATE UNEXPECTED ABSENCES OF -
ON-DUTY CREW MEMBERS.
2624 TECH. 6. 2. 2.A CONDUCT OF EACH ON DUTT SHIFT 07 DETAILS ARE IN TABLE SPEC. OPERATIONS SHALL BE COMPOSED OF 6.2-1 OF THE AT LEAST THE MINIMUM TECHNICAL SHIFT CREW COMPOSITION SPECIFICATIONS.
SHOWN IN TABLE 6.2-1.
2628 TECH. 6. 2. 2.8 CONDUCT OF AT LEAST ONE LICENSED DT SPEC. OPERATIONS RO SHALL BE IN THE CONTROL ROOM WHEN FUEL IS IN EITHER REACTOR.
IN ADDITION, WRILE 51THER REACTOR IS IN MODE 1, 2 3, OR 4 ONE LICENSED SRO SHALL ALSO BE PRESENT, 2629 TECH. 6. 2. 2.D CONDUCT OF CORE ALTERATIONS SHALL 07 SPEC. OPERATIONS BE OBSERVED AND SUPERVISED BT A i LICENSED SRO OR SRO
, (FUEL MANDLING) WHO IS IN THE CONTAINMENT BUILDING AND HAS NO
, OTHER CONCURRENT RESPONSIBILITIES.
C
(
Page No. 166 12/02/85 TABLE 3.2 l COMMITMENTS FOR PLANT
-e=======- _==_ =====-e=== =- .--=-
OPERATIONS AND SUPPORT
= ===,=: :==.- ==
TITLE MODULE REMARES COMMITMENT COMMITMENT COMMITMENT DOCUMENT / FEATURE NUMBER SOURCE SECTION SUBJECT
-======= === === =-===e============-- =====- .- ============= :.====-,=-====== ====== ===== == ======= ===
= = == ==.===e
FIRE BRIGADE OF AT 07 2630 TECH. 6. 2. 2.E CONDUCT OF SPEC. OPERATIONS LEAST 5 MEMBERS SHALL BE M41MTAINED. IT SHALL NOT INCLUDE THE OPERATIONS SUPERVISOR AND 2 OTHER MEMBERS OF THE MINIMUM CREW NECESSARY FOR SAFE SHUTDOWN.
CONDUCT OF WORKING HOURS FOR 05,07 DETAILS ARE IN 263] TECH. 6. 2. 2.F 9A,9B SECTION 0.2.2.F OF SPEC. OPERATIONS THOSE WHO PERFORM SAFETY RELATED THE TECHNICAL FUNCTIONS SHALL BE SPECIFICATIONS.
LIMITED.
4 CONDUCT OF STA SHALL SERVE IN AN 07 2632 TECH. 6. 2.
ADVISORY CAPACITY TO SPEC. OPERATIONS THE OPERATIONS SUPERVISOR ON MATTERS PERTAINING TO THE ENGINEERING ASPECTS OF ASSURING SAFE OPERATION OF REACTORS.
CONDUCT OF SAFTEY LIMIT VIOLATION 05,07 2640 TECH. 6. 7. l.A SPEC. OPERATIONS - NRC OPERATIONS CENTER SHALL BE NOTIFIED AS SOON AS POSSIBLE (WITHIN ONE HOUR). MANAGEMENT AND SRB SHALL BE NOTIFIED WITHIN 24 HOURS.
2642 TECR. 6. 7. 1.B CONDUCT OF IF A SAFETY L l"41 T IS 05.07 SPEC. OPERATIONS VIOLATED, A SAFETY LIMIT VIOLATION REPORT SHALL BE PREPARED AND REVIEWED BY THE PRB.
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4 Page No. 167 12/02/85 TABLE 3.2-1 COMMITMENTS FOR PLANT
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== ========== ================ ==================== =====================e ================ ====== ==============
A SAFETY LIMIT 05,07 2643 TECH. 6. 7. 1.B CONDUCT OF SPEC. OPERATIONS VIOLATION REPORT SHALL DESCRIBE (1)
APPLICABLE CIRCUMSTANCES PRECEEDING THE VIOLATION, (2) EFFECTS OF VIOLATION UPON FACILITY COMPONENTS OR SYSTEMS, AND (3)
CORRECTIVE ACTION TAEEN.
CONDUCT OF SAFETY LIMIT VIOLATION 05,07 2646 TECH. 6. 7. 1.D SPEC. OPERATIONS - CRITICAL OPERATION OF THE UNIT SHALL NOT BE RESUMED UNTIL AUTHORIZED BY THE COMMISSION.
PROCEDURES AND WRITTEN PROCEDURES 05.07, 2648 TECH. 6. 8. l.A SHALL BE ESTABLISHED, 9A 95, SPEC DOCUMENTATION IMPLEMENTED AND 15 MAINTAINED COVERING THE APPLICABLE PROCEDURES RECOMMENDED IN APPENDIX A OF RG
' I.33 R/2.
PROCEDURES AND RG 1. 33, R/2, QUALITY . 05.07 CONFORMANCE IS 2649 TECH. 6. 8. l.A ASSURANCE 9A,95, DISCUSSED IN SECTION SPEC. DOCUMENTATION APPENDIX A PROGRAM 15 1.9.33.2 0F THE REQUIREMENTS FSAR.
(OPERATION)
WRITTEN PROCEDURES 05,07, 2650 TECH. 6, 8. l.B PROCEDURES AND 95 DOCUMENTATION SHALL BE ESTABLISHED, SPEC.
IMPLEMENTED AND MAINTAINED COVERING REFUELING OPERATIONS.
(
i C lC 1
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====---========== = =========-=-
OPERATIONS AND SUPPORT
--========== ,=,=-===
l TITLE MODULE REMARES COMMITMENT COMMITMENT DOCUMENT / FEATURE NUMBER COMMITMENT SOURCE SECTION SUBJECT
==e= == ========== =============-== ===============e === ===========.====== =- ====== ========= ====== =============-=====
WRITTEN PROCEDURES 05.07, 2651 TECH. 6. 8. 1.C PROCEDURES AND 9A,9B DOCUMENTATION SHALL BE ESTABLISHED, SPEC.
IMPLEMENTED AND MAINTAINED COVERING SURVEILLANCE AND TEST ACTIVITIES OF SAFETY RELATED EQUIPMENT.
WRITTEN PROCEDURES 05,07 2652 TECH. 6. 8. 1.F PROCEDURES AND DOCUMENTATION SHALL BE ESTABLISHFD, SPEC.
IMPLEMENTED AND MAINTAINED COVERING THE FIRE PROTECTION PROGRAM IMPLEMENTATION.
WRITTEN PROCEDURES 05,07, 2955 TECH. 6. 8. l.G PROCEDURES AND SHALL BE ESTABLISHED, 9B SPEC. DOCUMENTATION IMPLEMENTED AND NAINTAINED COVERING PROCESS CONTROL PROGRAM IMPLEMENTATION.
8, PROCEDURES AND BACH PROCEDURE WRITTEN 05,07, 2653 TECH. 6. 2 DOCUMENTATION TO FULFILL TECH SPEC 9A,98, SPEC. 15 6.8.1 AND CHANGES THERETO, SHALL BE APPROVED BY EITRER THE GENERAL MANAGER -
I VOGTLE NUCLE AR OPERATIONS, OR TRE MANAGER Of THE RESPONSIBLE DEPARTMENT.
PROCEDURES AND BACH PROCEDURE WRITTEN 05,07, 2654 TECH. 6. 8. 2 DOCUMENTATION TO FULFILL TECR SPEC 9A,9R, SPEC.
6.8.1 WILL BE REVIEWED 15 4 PERIODICALLY AS SET
I FORTH IN ADMINISTRATIVE
, g PROCEDURES.
(!
- ; \
9 O O O O O O
. -. . .-_~~ --- -~ ~ . - _ . . . . . . ~ _ . . - - ._ - . ._ . . .
O O O O Page No. 169 12/02/85 TABLE 3.2-1 COMMITMENTS FOR PLANT
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OPERATIONS AND SUPPORT
==========
COMMITMEPT COMMITMENT DOCUMENT / FEATURE TITLE MODULE REMARES NUMBER COMMITMENT SOURCE SECTION SUBJECT ==----= =====
e ==
r ====
T 3.A PROCEDURES AND TEMPORARY CHANGES TO' 05.07, 2657 TECH. 6. 8.
SPEC. DOCUMENTATION PROCEDURES MAT BE MADE 9A.98.
PROVIDED THE INTENT OF 15 THE ORIGINAL PROCEDURE IS NO ALTERED.
2658 TECH. 6. 8. 3.B PROCEDURES AND TEMPORARY CHANGES TO 05.07 SPEC. DOCUMENTATION PROCEDURES MUST BE :9A 9B.
APPROVED BY TWO 15
" MEMBERS OF THE PLANT MANAGEMENT STAFF. AT LEAST ONE OF WHOM HOLDS A SRO LICENSE.
2659 TECH. 6. B. 3.C PROCEDURES AND TEMPORARY CRANGES TO 05.07 SPEC. DOCUMENTATION PROCEDURES SHALL BE 9A 98 DOCUMENTED. REVIEWED.' 15 AND APPROVED IN ACCORDANCE WITH TECH ,
SPEC 6.8.2 WITHIN 14 DAYS OF IMPLEMENTATION.
4.A PROCEDURES AND A PROGRAM TO REDUCE 07 2660 TECH, 6. 8.
SPEC. DOCUMENTATION LEAEAGE FROM THOSE PORTIONS OF SYSTEMS OUTSIDE CONTAIMENT THAT COULD CONTAIN HIGHLY RADICACTIVE FLUIDS DURING A SERIOUS TRANSIENT OR ACCIDENT TO AS LOW AS 1
PRACTICAL LEVELS.
TECH. 4.A PROCEDURES AND LEAEAGE REDUCTION 07 2661 6. 8.
SPEC. DOCUMENTATION- PROGRAM INCLUDES APPLICABLE PORTIONS OF CONTAINMENT 4 RECIRCULATION SPRAY, SAFETY INJECTION, CHEMICAL AND VOLUME CONTROL. AND RESIDUAL REAT REMOVAL SYSTEM.
1 i C ,
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======= =--===================ce-OPERATIONS AND SUPPORT
=================-
TITLE MODULE REMARKS COMMITMENT COMMITMENT COMMITMENT DOCUMENT / FEATURE NUMBER SOURCE SECTION SURJECT
== ==r======= ================ ======= ============ ==== ================= =======-======== ====== ==============
PROCEDURES AND A PROGRAM SHALL BE 07 2662 TECH. 6. 8. 4.A. I DOCUMENTATION ESTABLISHED, SPEC.
IMPLEMENTED AND MAINTAINED TO PROVIDE PREVENTIVE MAINTENANCE AND PERIODIC VISUAL INSPECTION IfEQUIREMENTS FOR THE PROGRAM TO REDUCE LEAKAGE OUTSIDE CONTAINMNENT.
PROCEDURES AND A PHOGRAM SHALL BE 07 2663 TECH. 6. 8. 4.A.II DOCUMENTATION ESTA- .ISHED, SPFC.
IMPLEMENTED AND MAINTAINED TO PROVIDE LEAK TEST REQUIREMENTS FOR EACH SYSTEM AT REFUELING CYCLE INTERVALS IN THE PROGRAM TO REDUCE LEAKAGE OUTSIDE CONTAINMENT.
A
SUMMARY
RCPORT OF 07 2666 TECH. 6. 9. 1. 1(1) REPORTS TO THE NRC SPEC. PLANT STARTUP AND POWER ESCALATION TESTING SHALL BE SUBMITTED FO! LOWING REChlPT OF AN I OPERATING LICENSE.
- 1. I(2) REPORTS TO THE NRC A
SUMMARY
REPORT OF 07 2667 TECH. 6. 9.
SPEC. PLANT STARTUP AND POWER ESCALATION TESTIKJ SHALL BE SUBMITTED FOLLOWING AN AMENDMENT TO THE LICENSE INVOLVING A PLANNED INCREASE IN POWER LEVEL.
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COMMITMENT COMMITMENT DOCUMENT / FEATURE TITLE MODULE REMARKS NUMBER CCMMITMENT SOURCE SECTION SUBJECT
--= -= e========= ================ ============ ======= ====e====-============ =-============== ====== =================
1(3) REPORTS TO THE NRC A SUMMART REPORT OF 07 C668 TECH. 6. 9. I.
SPEC. PLANT STARTUP AND PONER ESCALATION TESTING SHALL BE SUBMITTED FOLLONING INSTALLATION OF FUEL THAT HAS A DIFFERENT DESIGN OR HAS BEEN MANUFACTURED BY A DIFFERENT FUEL SUPPLIER.
- 1. 1(4) REPORTS TO THE NRC A
SUMMARY
REPORT OF 07 2669 TECH. 6. 9.
SPEC. PLANT STARTUP AND PONER ESCALATION TESTING SHALL BE SUBMITTED FOLLONING MODIFICATIONS THAT MAY HAVE SIGNIFICANTLT ALTERED THE NUCLEAR.
THERMAL. OR HYDRAULIC PLANT PERFORMANCE.
- 1. 2 REPORTS TO THE NRC THE STARTUP RRPORT 07 2670 TECH. 6. 9.
SPEC. SHALL ADDRESS ANY CORRECTIVE ACTIONS TRAT WERE REQUIRED TO OBTAIN SATISFACTORY OPERATION.
- 1. 2 REPORTS TO THE NRC THE STARTUP REPORT 07 2G7I TRCR. 6. 9.
SPEC. SHALL ADDRESS ANT ADDITIONAL SPECIFIC DETAILS REQUIRED IN LICENSE CONDITIONS BASED ON OTHER COMMITMENTS.
TECR. 6 REPORTS TO THE NRC ROUTINE REPORTS OF 05,07
, 2673 6. 9. I.
SPEC. OPERATING STAT?.3 TICS AND SHUTDOWN EXPERIENCE. INCLUDING DOCUMENTATION OF ALL CHALLENGES TO THE PORV'S OR SAFETY I VALVES, SHALL BE SUBMITTED ON A MONTHLY BASIS.
('
_ - - _ - _ _ _ - _ _ _ _ - _ - _ _ .- - .= . -_ .. --
Page No. [Tg 12/02/85 TABLE 3.2-1 COMMITMENTS FOR PLANT
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OPERATIONS AND SUPPORT
==========
DOCUMENT / FEATURE TITLE MODULE REMARKS NUMBER COMMITMENT COMMITMENT COMMITMENT SOURCE SECTION SUBJECT
= == ========== ================ ==================== =================== = ===== ==========
THE HADIAL PEAKING 07 2674 TECR. 6. 9. 1. 7 REPORTS TO THE NHC SPEC.
FACTOR LIMIT REPORT SHALL BE PROVIDED FOR ALL PLANES CONTAINING BANK "D" CONTROL RODS AND ALL UNRODDED CORE PLANES AT LEAST 60 DAYS PRIOR TO CYCLE INITIAL CNITICALITY.
REPORTS TO THE NRC IF THE RADIAL PEAKING 07 2675 TECH. 6. 9. 1. 7 SPEC. FACTOR LIMIT REPORT WOULD BE SUBMITTED AT SOME OTHER TIME DURING CORE LIFE. IT WILL BE SUBMITTED 60 DAYS PRIOR TO THE DATE THE LIMIT WOULD BECOME RFFECTIVE UNLESS EXEMPTED.
1.10 REPORTS TO THE NRC THE ANNUAL RCS 07.9B 2677 TECH. 6. 9.
SPEC. SPECIFIC ACTIVITY REPORT IS REQUIRED WHEN RESULTS OF SPECIFIC ACTIVITY ANALYSES OF THE PRIMARY COOLANT HAVE EXCEEDED THE LIMITS OF SPECIFICATION 3.4.8 DURING THE TEAR.
REPORTS TO THE NRC THE RCS SPECIFIC 07,98 2679 TECH. 6. 9. 1.10(1)
SPEC. ACTIVITY REPORT SHOULD INCLUDE REACTOR POWER HISTORT STARTING 48 HOURS PRIOR TO THE FIRST SAMPLE IN WHICH THE LIMIT WAS EXCEEDED.
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== =====================-====s
OPERATIONS AND SUPPORT
' ======================
COMMITMENT COMMITMENT DOCUMENT / FEATURE TITLE MODULE REMARKS NUMBER COMMITMENT SOURCE SECTION SURJECT f' ,
====== == ========== ==========e===== ==================== ====================== ================ ====== 2c= =u..===a#__ _ . . _
2680 TECH. 6. 9. 1.10(2) REPORTS TO THE NRC THE RCS SPECIFIC 07,9B SPEC. ACTIVITY HEPORT SHOULD.
INCLUDE FUEL BURNUP BY CORE REGION.
2681 TECH. 6. 9. 1.10(3) REPORTS TO THE NRC THE RCS SPECIFIC 07,98 SPEC. ACTIVITY REPORT.SHOULD INCLUDE CLEANUP' FLOW HISTORY STARTING 48 HOURS PRIOR TO THE-FIRST SAMPLE IN WHICH THE LIMIT WAS EXCEEDED.
TECH. 1.10(4) REPORTS TO THE NRC THE RCS SPECIFIC 07,9B 2682 6. 9.
SPEC. ACTIVITY REPORT SHOULD INCLUDE HISTORY OF DE-GASSING OPERATIONS, IF ANY. STARTING 48 HOURS PRIOR TO THE FIRST SAMPLE IN WHICH THE LIMIT WAS EXCEEDED.
2683 TECH. 6. 9. 1.10(5) REPORTS TO THE NRC THE RCS SPECIFIC- 07.9B SPEC. ACTIVITY REPORT SHOULD INCLUDE THE TIME
. DURATION WHEN THE SPECIFIT ACTIVITY OF THE PRIMART COOLANT EXCEEDED 1.0 MICROCURIE PER GRAM DOSE EQUIVALENT I-131.
2684 TECH. 6. 9. 1.12.A REPORTS TO THE NRC ANNUAL DATA REPORT ON 07
, SPEC. DIESEL GENERATOR RELIABILITY WILL INCLUDE A
SUMMARY
OF ALL TESTS (VALID AND 45 INVALID) THAT OCCURRED WITHIN THE TIME PERIOD OVER WHICH THE LAST 1 ([ 20/100 VALID TESTS WERE PERFORMED.
- Ce i C)
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== == ========== ================ ==================== ====================== ================
ANNUAL DATA REPORT ON 07 2685 TECH. 6. 9. 1.12.B REPORTS TO THE NRC DIESEL GENERATOR SPEC. RELIABILITY WILL INCLUDE ANALYSIS OF FAILURES AND DETERMINATION OF ROOT CAUSES OF FAILURES.
ANNUAL DATA REPORT ON 07 2686 TECH. 6. 9. 1.12.C REPORTS TO THE NRC DIESEL GENERATOR SPEC.
RELIABILITT WILL INCLUDE IDENTIFICATION OF ACTIONS TAKEN TO CORRECT ROOT CAUSES OF FAILURES AND TO ACHIEVE A GENERAL IMPROVEMENT OF DIESEL GENERATOR RELIABILITT.
REPORTS TO THE NRC ANNUAL DATA REPORT ON 07 2961 TECR. 6. 9. 1.12.D SPEC.
DIESEL GENERATOR RELIABILITT WILL INCLUDE AN ASSESSMENT OF TRE EXISTING RELIABILITY OF ELECTRIC POWER TO EST EQUIPMENT.
6.10. I.A RECORD RETENTION RECORDS AND LOGS OF 05.07 2690 TECH.
REACTOR OPERATION SPEC.
COVERING TIME INTERVAL AT EACH POWER LEVEL SRALL BE RETAINED FOR AT LEAST FIVE TEARS.
RECORD RETENTION RECORDS AND LOGS OF 05,07 2691 TECR. 6.10. 1.B PRINCIPAL MAINTENANCE SPEC.
ACTIVITIES, INSPECTIONS, REPAIR
- 4 AND REPLACEMENT OF
'4 PRINCIPAL ITEMS OF
,l EQUIPMENT RELATED TO 4
' NUCLEAR SAFETT SHALL BE RETAINED AT LEAST j , FIVE TEARS.
e 1
4c G G e G G G
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COMMITMENT DOCUMENT / FEATURE TITLE MODULE REMARKS NUMBER COMMITMENT COMMITMENT SOURCE SECTION SUBJECT ===========s========
===e======
== ========== ================ ========-==== ====== =========e======
2692 TECH. 6.10. 1.D RECORD RETENTION RECORDS OF . 05.07 SURVEILLANCE 9A,99 SPEC.
ACTIVITIES:
INSPECTIONS AND CALIBRATIONS REQUIRED BY TECHNICAL SPECIFICATIONS SHALL BE RETAINED FOR AT LEAST FIVE YEARS.
RECORD RETENTION RECORDS OF CRANGES 05,07, 2693 TECH. 6.10. 1.E 9A,98, SPEC. MADE TO PROCEDURES REQUIRED BY TECH SPEC 15 6.8.1 SRALL BE RETAINED AT LEAST FIVE YEARS.
2695 TECH. 6.10. 2.A RECORD HETENTION RECORDS AND DRAWING 05.07 SPEC. CHANGES REFLECTING PLANT DESIGN MODIFICATIONS MADE TO SYSTEMS AND EQUIPMENT DESCRIBED IN THE FSAR SHALL BE RETAINED FOR THE DURATION OF THE PLANT OPERATING LICENSE.
RECORD RETENTION RECORDS OF NEW AND 05,07 2696 TECH. 6.10. 2.8 SPEC. IRRADIATED FUEL INVENTORT, FUEL TRANSFERS AND ASSEMBLY BURNUP HISTORIES SRALL BE RETAINED FOR THE DURATION OF THE PLANT OPERATING LICENSE.
2697 TECH. 6.10. 2.E RECORD RETENTION RECORDS OF TRANSIENT 05.07 SPEC. OR OPERATIONAL CTCLES
,' FOR THOSE PLANT
' COMPONENTS IDENTIFIED IN TECR SPEC TABLE
( 5.7-1 SHALL BE RETAINED FOR THk DURATION OF THE
() OPERATING LICENSE.
~1 I
Q
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====,=:=====-==-====e===========-
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==~=======
DOCUMENT / FEATURE TITLE MODULE REMARES NUMBER COMMITMENT COMMITMENT COMMITMENT
< SOURCE SECTION SUBJECT
-== == ========== == ============= ==================== ====================== ================ ====== ========= ========
TECR. 6.10. 2.F RECORD RETENTION RECORDS OF REACTOR 05.07 2698 SPEC. TESTS AND EXPERIMENTS SHALL BE RETAINED FOR THE DURATION OF THE PLANT OPERATING LICENSE.
TECH. 6.10. 2.H RECORD HETENTION RECORDS OF IN-SERVICE 05.07 2699 SPEC. INSPECTIONS PERFORMED PURSUANT TO THESE T E C!!N I C A L SPECIFICATIONS SHALL BE RETAINED FOR THE DURATION OF THE PLANT OPERATING LICENSE.
HECORD RETENTION RECORDS OF REVIENS 05,07, 2700 TECH. 6.10. 2.J PERFORMED FOR CHANGES 9A,9B, SPFC. 15 MADE TO PROCEDURES OR EQUIPMENT OR REVIEWS OF TESTS AND EXPERIMENTS PURSUANT TO 10CFR50.59 SMALL BE RETAINED FOR THE DURATION OF THE OPERATING LICENSE.
RECORD RETENTION RECORDS OF SERVICE 05,07 270) TECH. 6.10. 2.L SPEC. LIVES OF ALL SNUEBERS REQUIRED BY SPEC 3.7.8, INCLUDING DATE THE SERVICE LIFE COMMENCES AND ASSOCIATED INSTALLATION AND MAINTENANCE RECORDS SHALL BE RETAINED FOR DURATION OF LICENSE t
9 9 e G G e e
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-- =-=-- -== =====
NUMBER COMMITMENT COMMITMENT COMMITMENT DOCUMENT / FEATURE TITLE MODULE REMARES SOURCE SECTION SUDJECT
-= =========- = ============ =_ == ---===--_. ==== - ============u====-==== ======= ======== =====- ============ =
HIGH RADIATION AREA FOR AREAS WHERE DOSE 07,9A WHERE NO ENCLOSURE 2972 TECH. 6.12. 2 EXITS, AREAF SHALL SPEC. RATE IS GHEATER THAN 1000 MREM /HR, LOCKED BE ROPED OFF, DOORS SHALL BE CONSPICUOUSLY PROVIDED. THE KEYS POSTED, AND A SHALL BE UNDER CONTROL FLASHINO LIGHT OF THE ON SHIFT ACTIVATED.
OPERATIONS SUPERVISOR AND/OR THE HEALTII PHYSICIST.
PROCESS CONTROL LICENSEE INITIATED 07,9B 2702 TECH. 6.13 SPEC. PROGRAM CHANGES TO THE PCP SHALL BE SUDMITTED TO THE NRC IN THr SEMI ANNUAL RAD EFFLUENT RELEASE REPORT FOR THE PRRIOD THAT THE CHANGKS WERE MADE.
l 1
(
j i .i 4 O C
4 l
C - . -
t
.___.m.__ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ . . _ _ _ . _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ . _ _ _ _ . . _ _ _ _ _ _ . . _ . . _ _ _ _ _ _ _ _ . _ _ _ . _ _ _ . _ _ _ _ _ _ . _ _
i i
- () 3.3 IMPLEMENTATION MATRIX 1
The implementation matrix was developed from the commitment matrix by tabulating approved documents which incorporated each commitment, by identifying proposed documents in which Nuclear Operations planned to incorporate each commitment, or by O locating each commitment in the Nuclear Operations commitment tracking system. This process began in June 1985 and continued I
through December 1985. It was performed for each of the 1266 commitments in Table 3.3-1. During the development process, the commitment matrix was revised to reflect review of source )
documents and to reflect amendment 18 to the FSAR. Each revised j O commitment was reviewed for impact on the implementation matrix. The development process was repeated for those
~
commitments which required it.
Instances of the same document appearing in more than one status (i.e., as a different version, or as both draft and approved) are caused by the dynamic nature of commitment implementation.
Documents for implementing commitments typically are contained in:
o Operations Department procedures.
o Maintenance Department procedures.
o Plant Engineering and Services Department procedures.
1 o Plant administrative procedures.
o Startup Manual procedures.
o Startup test procedures o Plans Procedures Manual.
o Nuclear Procurement Policy Manual.
() o VEGP Design Manual.
Many implementing documents that contain or will contain commitments are not yet approved. Unapproved implementing documents are listed in the draft document column of the implementation matrix and have not been verified to have been
() written or to contain the listed commitment. These documents were identified for implementation by the Nuclear Operations l Department and the Readiness Review Team.
Commitments may be implemented in documents other than those listed in the implementation matrix. When this occurs, the
() commitment tracking system will determine whether implementation has been made and identify the actual implementing document.
For more detailed information on the commitment tracking system, see Module 5. !
The implementation matrix is presented as Table 3.3-1.
O O
i I
i O
l l
I i
Oi O ,
I i
1 00429/1-2-6 3 . 3 -- 2 l
O C IPFLEENTATION SORTED BY SOURCE AM) SECTION 00PMITENT CDPMlTENT DOCUMENT / REMARKS / APPROVED DOCUENT DRAFT
~
NupeER SOURCE SECTION FEATURE 95FFCT10N NLDEER E DATE SECTION 00CIDENT EXPUMATION OF FIELDS NUMBER - A reference number that corresponds to the line entry in the comitment matrix ,
COPelTENT SOURCE - The document containing the comitment ,
CopWITENT SECTION - The section of the comitment source containing the comitment DOCUENT/ FEATURE - The document discussed in the FSAR section or the plant feature described in the FSAR section. (See 4
%itmnt Matriv.)
REMARKS / SUBSECTION - Any further subdivision of the comihnent document, along with explanatory notes I
APPROVED DOCUENT - The number, revision, date, and section of the implementing docunmt DRAFT DOCUENT - A document under development that implements a comitment ,
s i
I 4
s 1
l J
Page N 1 12/06/85 TABLE 3.3-1 ' IMPLEMENTING DOCUMENTS FOR PLANT
=================================
OPERATIONS AND SUPPORT
==========
APPROVED DOCUMENT DRAFT NUMBER COMMITMENT COMMITMENT DOCUMENT / FEATURE REMARKS /SUBSECTinN DOCUMENT NUMBER REV DATE SECTICN SOURCE SECTION ==========........================== ========
= ========== ================ ===......=========== ==============
1-500-01 O 07/11/85 5.20 93320-C 2706.00 FSAR 1. 2. 2.B PRIOR TO START OF UNIT 1 OPERATION, ELECTRICAL.
VENTILATION, AND PROCESS SYSTEMS IN CONSTRUCTION AREA OF UNIT 1 ARE SEGREGATED PROM SIMILAR SYSTEMS IN THE CONSTRUCTION AREA OF UNIT 2.
OOO63-C O 08/15/85 ALL 2707.00 FSAR 1. 2. 2.C ACCESS BETWEEN THE ALL UNIT UNDER 90112-C 0 07/18/85 CONSTRUCTION AND THE OPERATING UNIT IS CONTROLLED.
11701-C O 03/12/85 PAGE 6
??R 00 F?AR 1. 7. 2.E SHARED SYSTEMS AND PAGE 30 INTERFACES BETWEEN 11743-C O 04/19/85 i 11743-C O 04/19/85 PAGE 21 UNITS WILL BE PAGE 24 ISOLATED FROM UNIT 2 PAGE 26 AND/OR COMPLETED AND PAGE 30 CHECKED OUT FOR UNIT PAGE 34 1 PRIOR TO START OF PAGE 35 OPERATION OF UNIT 1. PAGE 36 i
CONFORMANCE IS 13427-1 0 10/17/84 4.4.1 729.00 FSAR 1. 9. 6 RG 1.6 MARCH 1971 DISCUSSED IN SECTION 4.4.2 1.9.6.2 OF THE FSAR.
' C.2. APPROPRIATE 13130-1 730.01 FSAR 1. 9. 7 RG 1.7. R/2 19010-1 DESIGN AND 19222-1 PROCEDURAL 19242-1 PROVISIONS SHOULD BE 19251-1 MADE FOR USE OF COMBUSTIBLE GAS CONTROL EQUIPMENT.
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- TABLE 3.3-1 IMPLEMENTING DOCUMENTS FOP PLANT OPERATIONS AND SUPPORT APPROVED DOCUMENT DRAFT DOCUMENT / FEATURE REMARKS / SUBSECTION DATE SECTION DOCUMENT NUMBER COMMITMENT COMMITMENT NUMBER REV ........
SECTION ....................................
SOURCE
................ .................... .................... t 1-300-07 RG 1.20 R/2 CONFORMANCE IS 743.00 FSAR 1. 9. 20 DISCUSSED IN SECTION i 3.9.N.2.4 OF THE FSAR.
23100-C O 04/03/84 14225-1 RG 1.23. FEBRUARY C.S. METEOROLOGICAL 24499-C 746.01 FSAR 1. 9. 23 23101-C 0 04/19/84 1972 INSTRUMENT SERVICING AND CALIBRATION 23110-C 0 04/03/84 '
24681-C 0 02/04/85 FREQUENCY.
24682-C 0 05/25/85 24683-C 0 02/04/85 24684-C 1 12/04/84 24685-C 1 11/08/84 24686-C 1 11/20/84 4 24687-C 0 11/20/84 s 24688-C 1 11/08/84 24689-C 1 11/05/84
(
PC 1 10 AUGUST '072 CONFORMANCE IS SEE ANSI N45.2.4-1972 753.00 FSAh 4 . s. 3C SECTION OF MATRIX DISCUSSED IN SECTION <
1.9.30.2 OF THE FSAR.
OO350-C O 03/19/85 3 00400-C (
- 9. 30 ANSI N45.2.4-1972 1.3. RESPONSIBILITY
-754.01 FSAR 1.
OF ORGANIZATION RESPONSISLE FOR (
ESTABLISMING REQUIREMENTS OF THIS STANDARD SHALL BE 6 IDENTIFIED AND DOCUMENTED.
00050-C 2 07/29/84 00400-C ANSI M45.2.4-1972 2.0. MEASURES SHALL
( ,754.02 FSAR 1. 9. 30 BE ESTABLISNED FOR OOO54-C 20407-C 0
1 10/13/84 07/25/85 6.2 DOCUMENTING INSTALLATION,
( INSPECTION, AND TESTING TO VERITY CONFORMANCE TO C- REQUIREMENTS.
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Tt Faga No. 3 12/06/85
- TABLE 3.3-1 IMPLEMENTING DOCUMENTS FOR PLANT
........................==..-=.....==
OPERATIONS AND SUPPORT
================..
APPROVED DOCUMENT DRAFT COMMITMENT DOCUMENT / FEATURE REMARKS / SUBSECTION SECTION DOCUMENT NUMBER COMMITMENT NUMBER REV DATE SOURCE SECTION ==================================== ========
.... = ========== =====.========== ==========..=======. =======.......=====
00350-C 0 03/19/85 4.8 00400-C
- 9. 30 ANSI N45.2.4-1972 2.1. ACTIVITIES 5.0
'754.03 FSAR 1.
SHALL BE PLANNED AND OUTLINED TO DEFINE ,
THE OPERATIONS AND SEQUENCE.
00800-C 0 08/14/84 00400-C 30 ANSI N45.2.4-1972 2.2. PREREQUISITES i "754.04 FSAR 1. 9.
SHALL HAVE BERN MET 00850-C 2 03/17/85 PER OTHER STANDARDS 00851-C 0 08/14/84 INCLUDING: PERSONNEL 00853-C 0 08/24/84 QUALIFICATION, SYSTEM DESIGN, MATERIAL' SELECTION AND FABRICATION, SHIPPING AND RANDLING, AND ACCEPTABLE DOCUMENTATION. i PROCEDURES AND 00350-C 0 03/19/85 5.1.6 00400-C "754.05 FSAR 1. 9. 30 ANSI M45.2.4-1972 2.3.
INSTRUCTIONS SMALL BE PREPARED AND DOCUMENTED.
00050-C 2 07/29/84 3.4.7 00400-C ANSI N45.2.4-1972 2.4. RESULTS OF
-754.06 FSAR 1. 9. 30 20407-C 1 07/25/85 6.2.2 INSPECTIONS AND TESTS SHALL BE DOCUMENTED IN A TEST REPORT OR DATA SNEET.
00208-C 0 08/14/84 4.4 00400-C
- 9. 30 ANSI N45.2.4-2972 2.5. MEASURING AND "7?4.07 FSAR 1. 20405-C 1 09/14/84 4.0 TEST EQUIPMENT WITH 4.0 ACCEPTABLE ACCURACY 20230-C 2 08/24/84 SHALL BE SELECTED, ADJUSTED AND CALIBRATED AT PRESCRIBED INTERVALS.
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Page No. 4 12/06/85 TABLE 3.3-1 IMPLEMENTING DOCUMENTS FOR PLANT
...................................========
OPERATIONS AND SUPPORT
( ..................=...
APPROVED DOCUMENT DRAFT COMMITMENT DOCUMENT / FEATURE REMARKS / SUBSECTION DOCUMENT NUMBER COMMITMENT NUMBER REV DATE SECTION
- SOURCE SECTION .................................... ........
....... .......... ................ .................... ...................=
r OO150-C NONCONFORMING 20407-C 1 07/25/05 7.3
+754.08 FSAR 1. 9. 30 (NSI N45.2.4-1972 2.6.
OO400-C ITEMS SHALL BE 80014-C I RESOLVED IN 853OO-C ACCORDANCE WITH 4Q ~l' ESTABLISHED G PROCEDURES. A O 3.0. 00350-C 0 03/19/85 5.1.4 OO400-C
'754.09 FSAR 1. 9. 30 ANSI N45.2.4-1972 5.1.24.5 PRECONSTRUCTION VERIFICATION SHALL 00857-C 0 08/14/84 INCLUDE VERIFICATION OOB53-C 0 08/14/84 OF EQUIPMENT 00101-C 0 12/02/84 4.0 IDENTITY, APPROVED 00103-C O 08/14/84 4.0 PROCEDURES 00108-C 0 09/29/84 5.11 AVAILABLE, STORAGE PROTECTION RECORDS, EQUIPMENT PHYSICAL INTEGRITY.
4.0. EQUIPMENT 20407-C 0 05/31/85 6.2 OO400-C
--754.10 PSAR 1. 9. 30 ANSI N45.2.4-1972 SRALL BE LOCATED. OO350-C 0 03/19/85 5.0 INSTALLED, ASSEMBLED OOO54-C O 10/13/84 AND/OR CONNECTED PER APPROVED DRAttINGS, MANUFACTURER'S INSTRUCTIONS.
INSTALLATION SPECIFICATIONS AND PROCEDURES.
~
ANSI N45.2.4-1972 5.1. INSPECTIONS OF OO350-C O 03/19/85 5.1.3 00400-C
-754.11 FSAR 1. 9. 30 NORE AREAS AND 5.1.4 PROGRESS SKALL 5.1.6.1 4
INCLUDE VERIFICATION OO254-C 0 12/04/84 0F CORRECT 20407-C 0 05/31/85 7.0 INSTALLATION, 20427-C 0 12/04/84 4.0 e
ADEQUACY OF HOUSEKEEPING AND PROTECTIVE MEASURES r
INCLUDING CONTROL OF 7-h TEMPORARY CONDITIONS.
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- =..........== ...............................
OPERATIONS AND SUPPORT COMMITMENT DOCUMENT / FEATURE REMARKS / SUBSECTION APPROVED DOCUMENT DRAFT NUMBER COMMITMENT NUMBER REV DATE SECTION DOCUMENT SOURCE SECTION ........
....... .......... ==.............. .................... .................... ....................................
ANSI N45.2.4-1972 5.2. CONSTRUCTION 00350-C 0 03/19/85 5.1 OO400-C 454.12 PSAR 1. 9. 30 TESTS SHALL BE 00050-C 2 07/29/84 PERFORMED IN 00054-C 0 10/13/84 ACCORDANCE WITH 20407-C 1 07/25/85 6.2 WRITTEN PROCEDURES TO VERITY COMPLIANCE WITH QYUALITY AND PERFORMANCE REQUIREMENTS.
30 ANSI N45.2.4-1972 5.2.1. CONSTRUCTION 00350-C 0 03/19/85 5.1.6.1 00400-C 454.13 FSAR 1. 9.
TESTS SMALL INCLUDE 5.1.6.2 SPECIFIED ELECTRICAL 5.1.21 TESTS. 5.1.22 30 ANSI N45.2.4-1972 5.2.2. MECHANICAL OO350-C 0 03/19/85 5.1.6.1 00400-C 754.14 FSAR 1. 9.
5.1.25.6 TESTS SKALL BE PERFORMED TO ASCERTAIN THAT COMPONENTS OR SYSTEMS CAN WITHSTAND SYSTEM PRESSURE RATINGS.
5.2.3. PHYSICAL AND OO350-C 0 03/19/85 5.4.7 OO400-C
-754.15 FSAR 1. 9. 30 ANSI N45.2.4-1972 CHEMICAL TESTS SHALL 5.1.6.2 INCLUDE AS 5.1.9 APPROPRIATE ANALYZING FOR OXYGEN OR MOISTURE CONTENT AND PURITY AND RADIATION SENSITIVITY TESTING.
6.1. 00350-C O 03/19/85 5.1.6.1 OO400-C "754.16 FSAR 1. 9. 30 ANSI N45.2.4-1972 POSTCONSTRUCTION INSPECTIONS SHALL BE PERFORMED TO VERIFY ACCEPTABILITY OF THE INSTALLATION.
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9 Page No. 6 12/06/85 f TABLE 3.3-1 IMPLEMENTING DOCUMENTS FOR PLANT
...................................=.========
OPERATIONS AND SUPPORT
/ ......................
NUMBER COMMITMENT COMMITMENT DOCUMENT / FEATURE REMARKS / SUBSECTION APPROVED DOCUMENT DRAFT SOURCE SECTION NUMBER REV DATE SECTION DOCUMENT l ....... .......... ................ .................... .................... .................................... ........
'754.17 FSAR 1. 9. 30 ANSI N45.2.4-1972 7.0. PROCEDURES 20407-C 0 05/31/85 11 OO400-C SHALL BE ESTABLISHED
/ FOR PROCESSING
- INSPECTION AND TEST DATA AND THEIR ANALYSIS AND EVALUATION.
s754.18 FSAR 1. 9. 30 ANSI N45.2.4-1972 8.0. RECORD COPIES 20407-C 0 05/31/85 6.2.2 OO400-C OF COMPLETED OO100-C 2 06/26/85 4.0 PROCEDURES, REPORTS, S.O PERSONNEL 6.0 QUALIFICATIONS, TEST EQUIPMENT CALIB RATONS , TEST DEVIATIONS OR EXCEPTIONS, AND INSPECTIONS SHALL BE PREPARED AND SAVED.
755.00 FSAR 1. 9. 31 RG 1.31. R/3 CONFORMANCE IS 20406-C 1 11/30/84 DISCUSSED IN SECTION 1.9.31.2 OF THE FSAR.
764.01 FSAR 1. 9. 33 RG 1.33, R/2 C.3. INDEPENDENT OO402-C O 04/10/85 4.1.2.2 REVIEW OF TECHNICAL 4.1.4 SPECIFICATION 4.1.4.4 CHANGES OR LICENSE 4.1.13 AMENDMENTS PRIOR TO SUBMITTAL TO COMMISSION FUR APPROVAL.
765.01 FSAR 1. 9. 33 ANSI N18.7-1976 3.4.2. DESIGNATE 10003-C O 08/22/84 TABLE 1 POSITIONS REQUIRING 10010-C 2 03/01/85 SECT. 4.0 RO AND SRO LICENSES.
765.02 FSAR 1. 9. 33 ANSI N18.7-1976 3.4.2. MINIMUM 10003-C O 08/22/84 TABLE I NUMBER OF PERSONNEL WITH RO AND SRO LICENSES.
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12/06/85 ,
TABLE 3.3-1 IMPLEMENTING DOCUMENTS FOR PLANT
=================================
OPERATIONS AND SUPPORT
=============== ......
REMARKS / SUBSECTION APPROVED DOCUMENT DRAFT NUMBER COMMITMENT COMMITMENT DOCUMENT / FEATURE DOCUMENT NUMBER REV DATE SECTION SOURCE SECTION
= ========== ================ ==================== ==========,========= ==================================== ==
gN765.03 3.4.2. OOOO1-C FSAR 1. 9. 33 ANSI N18.7-1976 RESPONSIBILITY OF PLANT MANAGER 4.4. MONITOR- OOOO1-C y 765.04 FSAR 1. 9. 33 ANSI N18.7-1976 DAY-TO-DAY OPERATING ACTIVITIES TO ENSURE SAFETY AND IN ACCORDANCE WITH ADMINISTRATIVE CONTROLS. { PLANT MANAGER)
ANSI N18.7-1976 5.1. IDENTIFY 24000-1
<765.05 FSAR 1. 9. 33 SERIES STRUCTURES. SYSTEMS AND COMPONENTS COVERED BY PROGRAM AND MAJOR ORGANIZATIONAL UNITS AND RESPONSIBILITIES.
765.06 FSAR 1. 9. 33 ANSI N18.7-1976 5.2. -RULES ARE 20020-C O 11/28/84 ESTABLISHED OOOOS-C. O 09/10/84 PERTAINING TO COOO6-C 0 01/20/85 PERSONEL CONDUCT 00003-C 0 10/13/84
- WHICH INFLUENCE OO209-C 0 11/11/84 EFFECTIVENESS OF 00251-C O 09/20/83 OPERATING AND OO253-C 0 01/20/85 MAINTENANCE 00259-C 0 10/14/84 PERSONNEL, HOURS AT DUTY STATICM, AND AVAILABILITY ON CALL OF SUPERVISORS.
765.07 PSAR 1. 9. 33 ANSI N18.7-1976' 5.2. RULES FOR 00301-C 0 08/08/84 4.0 PERSONNEL CONDUCT -' OOOO5-C 0 09/10/84 3.0 HOURS AT DUTY 10003-C 0 08/22/84 TABLE 1 I STATION. 00050-C 2 07/29/84 ALL <
AVAILABILITY OF 00051-C 1 09/20/84 ALL'
- PROFESSIONALS, 10010-C' 3 04/18/85 ALL CONDUCT OF 10012-C 2 02/07/85 ALL
! OPERATIONS, 10013-C 1 02/07/85 ALL
'i PREPARING DOCUMENTS. 10000/C 0 06/05/84 3.3.1
~
(SEE FSAR'3ECT.
13.5.1.1.G.
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Psge No. 8 12/06/85 IMPLEMENTING DOCUMENTS FOR PLANT TABLE 3.3-1
.....=== ..==.................=..............
OPERATIONS AND SUPPORT
......=...............
r APPROVED DOCUMENT DRAFT COMMITMENT DOCUMENT / FEATURE REMARKS / SUBSECTION SECTION DOCUMENT NUMBER COMMITMENT NUMBER REV DATE SECTION ........
SOURCE 10000-C 6 06/05/84 3.3.1.4 ANSI N18.7-1976 5.2.1(1). RO 765.08 FSAR 1. 9. 33 RESPONSIBILITY TO SHUT DOWN FEACTOR.
10006-C O 04/24/84 765.09 FSAR 1. 9. 33 ANSI N18.7-1976 5.2.1(2).
RESPONSIBILITY TO ANALYZE CAUSE BEFORE RETURNING TO PeWER AFTER TRIP OR REDUCTION. SEE ALSO ANSI 18.7 SECT.
5.3.4.1.
SRO 10000-C 0 06/05/84 2.5 765.10 FSAR 1. 9. 33 ANSI N18.7-1976 5.2.1(3).
2.6 RESPONSIBILITY TO BE PRESENT DURING RETURN TO POWER.
10000-C 0 06/05/84 3.3.2 765.11 FSAR 1. 9. 33 ANSI N18.7-1976 5.2.1(4).
r2SPONSIBILITY TO RESPOND CONSERVATIVELY TO INSTRUMENT INDICATIONS.
5.2.1(5). 10000-C 0 06/05/84 2.5 765.12 FSAR 1. 9. 33 ANSI N18.7-1376 2.6.A RESPONSIBILITY TO ADHERE TO TECHNICAL SPECIFICATIONS.
10000-C O 06/05/84 4.5.1.3 V 'E/.7 ,X/
I 33 ANSI N18.7-1976 5.1.1(6).
765.13 FSAR 1. 9.
10C01-C O 04/19/94 3.1.B RESPONSIBILITY TO REVIEW ROUTINE 3.2.B OPERATING DATA. 3.3.C ANSI N18.7-1976 5.2.2. APPROVAL OF OOO52-C 0 03/15/85 5.0 gt(" #785.14 FSAR 1. 9. 33 6.0
' TEMPORARY PROCEDURE CHANGES c:d t~
r
- 9 9 9 O O O
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k Page w . 9 .
12/06/85 -
TABLE 3.3-1 IMPLEMENTING DOCUMENTS FOR PLANT
.=.......................=........=.......... [
OPERATIONS AND SUPPORT
.....................= ,
APPROVED DOCUMENT DRAFT NUMBER COMMITMENT COMMITMENT DOCUMENT / FEATURE REMARKS / SUBSECTION NUMBER REV DATE SECTION DOCUMENT SOURCE SECTION =..=====
......= .......... .....==........= ==.................= =................... .............====....=======.. .==..
4 765.15 FSAR 1. 9. 33 ANSI N18.7-1976 5.2.2 AND 5.2.15. 00054-C 0 10/13/84 0 4.0 ,
REQUIREMENTS TO USE 10000-C 06/05/84 AND FOLLOW PROCEDURES 765.16 FSAR 1. 9. 33 ANSI N18.7-1976 5.2.2. AVAILABILITY 00103-C 0 08/15/84 4.0 OF 6'?OCEDURE COPIES 00051-C 1 08/20/84 4.2.2.2 ;
ANSI N18.7-1976 5.2.2. 00052-C 0 03/15/85 ALL !
33 h</W '765.17 FSAR 1. 9.
DOCUMENTATION AND INCORPORATION OF TWIPORARY PROCEDURE CHANGES. SEE FSAR SECT. 13.5.1.1.B.
I ANSI N18.7-1976 5.2.7 EMERGENCY 10000-C 0 06/05/84 4.0 765.18 FSAR 1. 9. 33 ACTIONS MNEN NO PROCEDURE COVERS.
33 ANSI N18.7-1976 5.2.2. TEMPORARY 00052-C 0 03/15/85 .
3765.19 FSAR 1. 9. I PROCEDURE CHANGES.
SEE FSAR SECT.
13.5.1.1.B.
33 ANSI N18.7-1976 5.2.2. MEMORIZE 10000-C 0 06/05/84 4.2.1 l' 765.20 FSAR 1. 9.
IMMEDIATE ACTIONS TO 00054-C 0 10/13/84 3.3 E0PS 33 ANSI N18.7-1976 5.2.2. RECORDING OF 10011-C 3 04/18/85 3.2.3 765.21 FSAR 1. 9. .
DATA
- 9. 33 ANSI N18.7-1976 5.2.3. OPERATING 10000-C 0 06/05/84 2.0 ,
765.22 FSAR 1.
3.0 ORDERS - GENERAL 10004-C 0 08/15/84 INSTRUCTIONS: SHIFT 10001-C 0 04/19/84 3.0 RELIEF, CONFINES OF 4.0 CONTROL ROOM, DEFINITION OF INDIVIDUAL DUTIES.
TRANSMITTAL AND FILING OF OPERATING DATA. ACCESS TO EQUIPMENT.(SEE 13.5.1.1.F)
?" -g 1 .
N,c
Psge No. 10 12/06/85 I TABLE 3.3 . IMPLEMENTING DOCUMENTS FOR PLANT OPERATIONS AND SUPPORT
' ........i.............
APPROVED DOCUMENT DRAFT NUMBER COMMITMENT COMMITMENT DOCUMENT / FEATURE REMARKS / SUBSECTION DOCUMENT NUMBER REV DATE SECTION SOURCE SECTION .................................... ........
.......... ................ ....e............... ....................
SPECIAL 10002-C 1 10/31'84 3.2 765.23 FSAR 1. 9. 33 ANSI N18.7-1976 5.2.4.
ORDERS - SRORT TERN
, MANAGEMENT INSTRUCTIONS:
SPECIAL OPERATIONS, MOUSEKEEPING, DATA TAKING, PUBLICATIONS.
PLOTTING PARAMETERS, PERSONNNEL ACTIONS.
5.2.5. TEMPORARY 00052-C O 05/19/85 ALL 765.24 FSAR 1. 9. 33 ANSI N18.7-1976 PROCEDURES -
DESIGNATION OF TIME PERIOD TEMPORARY 00053-C O 05/19/85 5.0 765.25 FSAR 1. 9. 33 ANSI N18.7-1976 5.2.5.
PROCEDURES - REVIEW AND APPROVAL ANSI N18.7-1916 5.2.6. RELEASE OF OO350-C 0 03/19/95 4.5 765.26 FSAR 1. 9. 33 EQUIPMENT OR SYSTEMS 4.15 FOR MAINTENANCE 4.18.2 AFTER ASSESSING 4.20 POTENTIALLLY 5.1.18 DEGRADED DEGREE OF 5.5.1 PROTECTION ANSI N18.7-1976 5.2.6. MEASURES TO OO304-C 3 12/30/84 ALL d 765.27 FSAR 3. 9. 33 PROVIDE FOR PROTECTION OF EQUIPMENT AND WORKERS AND MEASURES TO ENFORCE SCCH CONTROLS 33 ANSI N18.7-1976 5.2.6. 00304-C 3 12/30/84 4.1.2 h765.28 FSAR 1. 9.
CONSIDERATIONS IN PREPARING EQUIPMENT FOR MAINTENANCE INCLUDE SHUTDOWN MARGIN, DECAY HEAT REMOVAL, SYSTEM TEMP. AND PRESS, J
- VALVES BETWEEN WORK r' AND RAZARDOUS MATERIAL, VENTING AND DRAINING.
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Page . 11 12/06/85 TABLE 3.3-1 IMPLEMENTING DOCUMENTS FOR PLANT OPERATIONS AND SUPPORT REMARKS / SUBSECTION APPROVED DOCUMENT DRAFT NUMBER COMMITMENT COMMITMENT DOCUMENT / FEATURE NUMBER REV DATE SECTION DOCUMENT 1 SOURCE SECTION ........
.=..... .......... ................ .......... 2........ .................... ...........e..................=====.
33 ANSI N18.7-1976 5.2.6. PROCEDURES 00304-C 3 12/30/84 4.2 765.29 FSAR 1. 9.
FOR LOCKING OR 00308-C O 05/11/85 '
J TAGGING TO SECURE AND IDENTIFY EQUIPMENT IN CONTROLLED STATUS.
INDEPENDENT VERIFICATION TO ENSURE CORRECT ISOLATION AND TAGGING.
1 5.2.6. TEMPORARY 00306-C 0 08/14/84 ALL 4765.30 FSAR 1. 9. 33 ANSI N18.7-1976 12/15/84 ALL ELECTRICAL JUMPERS, 00307-C O LIFTED LEADS, AND 20429-C 0 09/24/85 3.3 TEMPORARY TRIP SETTINGS SHALL BE CONTROLLED BY APPROVED PROCEDURES WHICH REQUIRE i IMDFP!NDEF*
VERIFICATION.
33 ANSI N18.7-1976 5.2.6. A LOG SHALL OO307-C 0 12/15/84 3.2.3 765.31 FSAR 1. 9.
' BE MAINTAINED OF STATUS OF TEMPORARY MODIFICATIONS i
e765.32 FSAR 1. 9. 33 ANSI N18.7-1976 5.2.6. TEMPORARY OO307-C O 12/15/84 ALL ELECTRICAL OR MECMANICAL MODIFICATIONS SHALL RE CONTROLLED BY PROCEDURES WHICH REQUIRE INDEPENDENT VERIFICATION.
J 765.33 33 ANSI N18.7-1976 5.2.7. MAINTENANCE 10000-C 0 06/05/84 3.10
- FSAR 1. 9.
AND MODIFICATION OF
$ SAFETY RELATED i
STRUCTURES, SYSTEMS
' OR COMPONENTS SHALL BE FOLLOWED BY in APPROPRIATE t' INSPECTION AND
- PERFORMANCE TESTING.
C i<
-.. - -., .-_,-___.__._ _._._ _ _ _ _ _ _ _ . . - . . .__m_-__a . _. _ _ __ _ - - . - - - _ - _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _
Pcge No. 12 12/06/85 TABLE 3.3-1 IMPLEMENTING DOCUMENTS FOR PLANT
......=. 3..===.e==........==....======
OPERATIONS AND SUPPORT
.=.......-= ..........
APPROVED DOCUMENT DRAFT COMMITMENT COMMITMENT DOCUMENT / FEATURE REMARKS / SUBSECTION DOCUMENT NUMBER NUMBER REV DATE SECTION SOURCE SECTION ......=............................. ========
....... .......... == ............. .................... ===......====== ....
MAINTENANCE OO350-C 0 03/19/85 5 PSAR 1. 9. 33 ANSI N18.7-1976 5.2.7.
765.34 OR MODIFICATION OF EQUIPMENT SHALL BE PPEPLANNED AND PERFORMED IN ACCORDANCE WITH WRITTEN PROCEDURES
- 9. 33 ANSI N18.7-1976 5.2.7.1. OO350-C 0 03/19/85 765.35 FSAR 1.
MAINTENANCE PROGRAMS TO MAINTAIN SAFETY RELATED STRUCTURES, SYSTEMS AND COMPONENTS AT QUALITY REQUIRED TO PERFORM THEIR INTENDED FUNCTIONS SHALL BE DEVELOPED.
ANSI N18.7-1976 5.2.7.1. OO350-C 0 03/19/85 5.0 THRU 765.36 FSAR 1. 9. 33 MAINTENANCE SHALL BE 5.11 SCHEDULED AND 2.1 PLANNED SO AS NOT TO COMPROMISE PLANT SAFETY.
- 9. 33 ANSI N18.7-1976 5.2.7.1. OO350-C 0 03/19/85 5 765.37 FSAR 1.
MAINTENANCE PLANNING SHALL CONSIDER POSSIBLE SAFETY CONSEQUENCES OF CONCURRENT OR SEQUENTIAL MAINTENANCE. TESTING OR OPERATING ACTIVITIES.
FSAR 1. 9. 33 ANSI N18.7-1976 5.2.7.1. OO350-C 0 03/19/85 5 765.38 MAINTENANCE PLANNING SHALL INCLUDE EVALUATION OF USE OF SPECIAL PROCESSES.
EQUIPMENT AND MATERIALS IN PERFORMANCE OF THE TASK, INCLUDING ASSESSMENT OF POTENTIAL HAZARDS TO PERSONS AND EQUIP. ~
O O O O O O O
Page 13 12/06/85 TABLE 3.3-1 IMPLEMENTING DOCUMENTS FOR PLANT
e==================================
OPERATIONS AND SUPPORT
==========
NUMBER COMMITMENT COMMITMENT DOCUMENT / FEATURE REMARKS / SUBSECTION APPROVED DOCUMENT DRAFT SOURCE SECTION NUMBER REV DATE SECTION DOCUMENT
= ========== ================ ==ee================ ==================== ==================================== ==
d765.39 FSAR 1. 9. 33 ANSI N18.7-1976 5.2.0. SURVEILLANCE 80012-C TESTING AND INSPECTION SCNEDULE FOR SAFETY RELATED STRUCTURES, SYSTEMS.
AND COMPONENTS SHALL BE PRESCRIBED.
'765.40 FSAR 1. 9. 33 ANSI N18.7-1976 5.2.8. SURVEILLANCE 14000 TEST PROGRAM SHALL SERIES BE PRESCRIBED TO ENSURE SAFETY SYSTEMS WILL ACT.
765.41 FSAR 1. 9. 33 ANSI N18.7-1976 5.2.8. MASTER 80012-C SURVEILLANCE SCHEDULE - SEE ALSO ANSI N18.7, SECT 5.2.19.3.
'765.42 FSAR 1. 9. 33 ANSI N18.7-1976 5.2.8. SURVEILLANCE 80012-C TESTS - ADDITIONAL CONTROLS TO ASSURE TIMELY CONDUCT.
'765.43 FSAR 1. 9. 33 ANSI N18.7-1976 5.2.10. OO254-C 1 06/14/85 HOUSEKEEPING AND CLEANLINESS CONTROL.
- 765.44 FSAR 1. 9. 33 ANSI N18.7-1976 5.2.13. PROCUREMENT OO800-C 3 03/08/85 AND MATERIALS OO853-C 2 05/05/85 CONTROL
<765.45 FSAR 1. 9. 33 ANSI N18.7-1976 5.2.13. PROCUREMENT OO203-C 2 03/08/85 ALL DOCUMENT CONTROL
/765.46 FSAR 1. 9. 33 ANSI N18.7-1976 5.2.13.2. CONTROL OO853-C 2 05/05/85 6.1 l OF PURCHASED MATERIAL
(^
C
Page No. 14 12/06/85 TABLE 3.3-1 IMPLEMENTING DOCUMENTS FOR PLANT
.......= ,e.....=.........=... .......=......
OPERATIONS AND SUPPORT
........= ........=...
APPROVED DOCUMENT DRAFT COMMITMENT DOCUMENT / FEATURE REMARKS / SUBSECTION SECTION DOCUMENT NUMSER COMMITMENT NUMBER REV DATE SOURCE SECTION ........
== .................................
==..... .......... .............- . .... ............... . . . . . . . . . . . . . . . . . . . .
5.2.13.3. OO853-C 2 05/05/85 6.0
=765.47 FSAR 1. 9. 33 ANSI N18.7-1976 IDENTIFICATION AND CONTROL OF MATERIALS AND PARTS.
5.2.13.4. HANDLING, OO951-C 0 05/04/84 (765.40 FSAR 1. 9. 33 ANSI N18.7-1976 STORAGE AND SHIPPING.
PROCEDURES OO850-C 2 03/17/85 8
/765.49 FSAR 1. 9. 33 ANSI N18.7-1976 5.2.14.
9 FOR NONCONFORMING ITEMS, SERVICES AND 10 ACTIVITIES SHALL INCLUDE INSTRUCTIONS FOR IDENTIFICATION, DOCUMENTATION.
SEGREGATION, DISPOSITION AND NOTIFICATION TO AFFECTED ORGANIZATIONS.
OO850-C 2 03/17/85 10 SOO11-C
'765.50 FSAR 1. 9. 33 ANSI N18.7-1976 5.2.14.
NONCONFORMING ITEMS SHALL BE REVIEWED AND ACCEPTED, REJECTED, REPAIRED OR REWORKED IN ACCORDANCE WITH DOCUMENTED PROCEDURES.
5.2.14. MEASURES OO950-C 2 03/17/85 10 e765.51 P'SAR 1. 9. 33 ANSI N18.7-1976 WHICH CONTROL FURTHER PROCESSING, DELIVERY OR INSTALLATION OF A NONCONFORMING ITEM REQUIRE DOCUMENTATION VERIFYING ACCEPTABILITY OF ITEMS WITH DISPOSITION OF
O O O O O O O
h Page'r4 . 15 V[ '\
12/06/85 TADLE 3.3-1 IMPLEMENTING DOCUMENTS FOR PLANT
....=.e===.....=.............=...=..=====
OPERATIONS AND SUPPORT I
DOCUMENT /FEATUPE REMARKS / SUBSECTION APPROVED DOCUMENT DRAFT NUMBER COMMITMENT COMMITMENT NUMBER REV DATE SECTION DOCUMENT SOURCE SECTION ........
.e===== .......... ................ .................... ....e............... ....................................
ANSI N18.7-1976 5.2.15. A OO414-C 0 08/06/84 2.3
<765.52 FSAR 1. 9. 33 SYSTEMATIC REVIEW AND FEEDBACK OF ,
INFORMATION BASED ON USE OF PROCEDURES IS REQUIRED. (SEE FSAR 13.5.1.1.C).
- 1. 9. 33 ANSI N18.7-1976 5.2.15. CONTROLS OOO51-C 1 08/20/84 4.2
'765.53 FSAR FOR THE APPROVAL AND OOOS2-C O 03/15/84 ALL ISSUANCE OF DOCUMENTS, INCLUDING REVISIONS SHALL BE PROVIDED. (SEE FSAR SECT. 13.5.1.1).
-765.54 FSAR 1. 9. 33 ANSI N18.7-1976 5.2.15. REVIEW, OOO50-C 2 07/29/84 APPROVAL AND CONTROL OOO51-C 1 08/29/84 OF PROCEDURES AND 00052-C 0 03/15/85 wsild'0E0 TIiZEr.! .
FSAR 9. 33 ANSI N18.7-1976 5.2.15. CONTROLS OO103-C 0 08/15/84 ALL 765.55 1.
ENSURE AGAINST MISUSE OF OUTDATED OR INAPPROPRIATE DOCUMENTS. (SEE FSAR SECT. 13.5.1.1.A).
<765.56 FSAR 1. 9. 33 ANSI N18.7-1976 5.2.15. DOCUMENTS, 10011-C 3 04/18/85 2.2 INCLUDING REVISIONS 50004-C O 08/01/85 OR CHANGES, MUST BE REVIEWED AND APPROVED BY QUALIFIED OR AUTHORIZED PERSONNEL PRIOR TO INITIAL USE. (SEE FSAR SECT.
13.5.1.1.A).
4 i
d 1
l (
Page No. 16 12/06/05 IMPLEMENTING DOCUMENTS FOR PLANT TABLE 3. $-1
==================================-
OPERATIONS AND SUPPORT nen===================
APPROVED DOCUMENT DRAFT COMMITMENT DOCUMENT / FEATURE REMARKS / SUBSECTION SECTION DOCUMENT NUMBER COMMITMENT NUMBER REV DATE SOURCE SECTION ==============,-===== ====e=============================== ========
= ========== ================ ==============
PROCEDURES OO103-C 0 08/15/84 ALL
'765.57 FSAR 1. 9. 33 ANSI N18.7-1976 5.2.15.
MUST BE DISTRIBUTED IN ACCORDANCE WITH CURRENT DISTRIBUTION LISTS.
COO 51-C 1 08/20/84 4.3
'765.58 FSAR 1. 9. 33 ANSI N18.7-1970 5.2.15. FREQUENCY OF REVIENS SUBSEQUENT TO PROCEDURE ISSUANCE SHALL BE SPECIFIED NO LONGER THAN TWO YEARS. (SEE FSAR SECT. 13.5.1.1.A).
PROCEDURES OO414-C 0 08/06/84 2.3 765.59 FSAR 1. 9. 33 ANSI N18.7-1976 5.2.15.
4.4 SHALL BE REVIEWED 10000-C 0 06/05/84 FOLLOWING AN INCIDENT.
5.2.15. CHANGES OOO51-C 1 08/20/04 4.0 e765.60 FSAR 1. 9. 33 ANSI N18.7-1976 REVIEWED BY SAME ORGANIZATION AS ORIGINAL UNLESS OTHERWISE DESIGNATED.
5.2.15. PROCEDURE 10011-C 3 04/18/85 5.1 4765.61 FSAR I. 9. 33 ANSI N18.7-1976 4.2.6 REVIEW MUST BE OOO51-C 1 08/20/84 CONDUCTED BY PERSONNEL OTHER THAN ORIGINATOR.
5.2.15. ACCESS TO 10011-C 3 04/18/85 FIGURE 1
- 765.62 FSAR 1. 9. 33 ANSI N18.7-1976 BACKGROUND INFORMATION FOR REVIEW OF PROCEDURES.
O O O O O O O
~
Page k 17 12/06/85 TABLE 3.3-1 IMPLEMENTING DOCUMENTS FOR PLANT l t
OPERATIONS AND SUPPORT APPROVED DOCUMENT DRAFT ;
NUMBER COMMITMENT COMMITMENT DOCUMENT / FEATURE REMARKS / SUBSECTION NUMBER REV DATE SECTION DOCUMENT SOURCE SECTION ======..
....... .......... .....=.......... .................... =................... .........=.......................=..
5.2.15. PROCEDURES 10000-C 0 06/05/84 4.4 OO400-C 765.63 _FSAR 1. 9. 33 ANSI N18.7-1976 SHALL BE REVIEWED ,
FOLLOWING A i MODIFICATION.
ANSI N18.7-1976 5.2.15(1). DOCUMENT 00050-C 2 07/29/84 2.0
<765.64 FSAR 1. 9. 33 CONTROL - 3.0 >
IDENTIFICATION OF ORGANIZATIONS RESPONSIBLE FOR PROCEDURES.
ANSI N18.7-1976 5.2.15(2) AND (4). 00054-C 0- 10/13/84 3.0
<765.65 FSAR 1. 9. 33 DOCUMENT CONTROL -
IDENTIFY PROPER DOCUMENTS TO BE USED IN THE PERFORMING ACTIVITY.
5.2.15(3). DOCUMENT 00108-C 09/29/84 OOOO2-C
-765.66 FSAR 1. 9. 33 ANSI N18.7-1976 '
Cubihuu - CONTROL OF INTERFACE DOCUMENTS-
'765.67 FSAR 1. 9. 33 ANSI N18.7-1976 5.2.15(5). DOCUMENT 00103-C 0 08/15/84 l
CONTROL -
ESTABLISNING DISTRIBUTION LISTS.
i <765.68 FSAR 1. 9. 33 ANSI 18.7-1976 5.2.16. MEASUREMENT 00208-C O 08/14/84
. AND TEST EQUIPMENT i CALIBRATION AND CONTROLS.
l 765.69 FSAR 1. 9. 33 ANSI N18.7-1976 5.2.17. INSPECTION 00201-C 1 03/17/85 ,
l
' PROGRAM FOR ACTIVITIES AFFECTING ,
f SAFETY
+
FSAR 1. 9. 33 ANSI N18.7-1976 5.2.18. CONTROL OF 00204-C 0 08/04/84 ALL i j '765.70 SPECIAL PROCESSES ;
j 4
r C
C' 1
I l
Page No. 18 12/06/85 t
! TABLE 3.3-1 IMPLEMENTING DOCUMENTS FOR PLANT
...........= ............................=...
OPERATIONS AND SUPPORT f ......................
I DOCUMENT / FEATURE REMARKS / SUBSECTION APPROVED DOCUMENT DRAFT NUMBER LMMITMENT COMMITMENT
' NUMBER REV DATE SECTION DOCUMENT SOURCE SECTION e.... .......... =====........... .................... ...........--....... ..--....................=........... ........
RG 1.33. REV 2, 5.2.19(2). SUM-20 2 02/28/85 6.5.2 765.71 FSAR 1 9. 33 SECTION 5.F - SUITABILITY OF PLANT MODIFIES ANSI OPERATING PROCEDURES N18.7-1976 SHALL BE CHECKED DURING PREOP AND INITIAL STARTUP PROGRAMS.
FSAR 1, 33 ANSI N18.7-1976 5.2.19.3. TESTS OO350-C 0 03/19/85 3.2.6 765.72 9.
ASSOCIATED WITH 4.18.3 PLANT MAINTENANCE, 4.20 MODIFICATIONS OR 5.1.6.1 PROCEDURE CHANGES 33 ANSI N18.7-1976 5.3. SAFETY RELATED OOO54-C 0 10/13/84
'765.73 FSAR 1. 9.
ACTIVITIES MUST BE COVERED BY PROCEDURE.
- 9. 33 ANSI N18.7-1976 5.3.1. PROCEDURE 10011-C 3 04/18/85 3.1.2
,765.74 FSAR 1.
SCOPE - SUFFICIENT TO PERFORM WITHOUT DIRECT SUPERVISION.
FSAR 9. 33 RG 1.33, REV 2, 5.3.2(1). EACH OOO50-C 2 07/29/84
/765.75- 1.
SECTION 5.H - PROCEDURE SHALL MODIFIES ANSI CONTAIN A N18.7-1976 DESCRIPTIVE TITLE, REV NUMBER, DATE AND APPROVAL STATUS.
FSAR 1. 9. 33 RG 1.33, REV 2, 5.3.2(2). OOO50-C O 07/29/84 3.4.1
/765.76 3.4.2 SECTION 5.H - APPLICABILITY - IF MODIFIES ANSI PURPOSE NOT CLEAR 10011-C 3 04/18/85 3.5.2 N18.7-1976 FROM TITLE FSAR 1. 9. 33 RG 1.33, REV 2, 5.3.2(4). 10011-C 3 04/18/84 3.1.2
-765.77 SECTION 5.H - PREREQUISITES SHALL MODIFIES ANSI IDENTIFY ACTIONS TO N18.7-1976 BE COMPLETED BEFORE USE.
I c
O O O O O O e
Page N 19 12/06/85 TABLE 3.3-1 IMPLEMENTING DOCUMENTS FOR PLANT
.....===...............................======
OPERATIONS AND SUPPORT APPROVED DOCUMENT DRAFT NUMBER COMMITMENT COMMITMENT DOCUMENT / FEATURE REMARKSfSUBSECTION DOCUMENT NUMBER REV DATE SECTION
- SOURCE SECTION .................................... ........
.....== ...== .... ................ ...............e.... ....................
0 RG 1.33. REV 2, 5.3.2(5). 10011-C 3 04/18/85 3.1.2.2
-765.78 FSAR 1 33 SECTION 5.H - PRECAUTIONS SHALL BE MODIFIES ANSI ESTABLISHED N18.7-1976 RG 1.33, REV 2. 5.3.2(6). 10011-C 3 04/18/85 3.1.2.2 765.79 FSAR 1. 9. 33 SECTION 5.H - LIMITATIONS SHALL BE MODIFIES ANSI SPECIFIED N18.7-1976 RG 1.33, REV 2, 5.3.2(7). MAIN BODY 10011-C 3 04/18/85 3.1.2.4
-765.80 FSAR 1. 9. 33 SECTION 5.H - SHALL CONTAIN MODIFIES ANSI STEP-BY-STEP N18.7-1976 INSTRUCTIONS.
RG 1.33, REV 2, 5.3.2(8). TEST 10011-C 3 04/18/05 3.2
'765.01 FSAR 1. 9. 33 SECTION 5.H - PROCEDURES SHALL MODIFIES ANSI CONTAIN CHECKOFF N18.7-1976 LISTS.
RG 1.JJ, REV 2, 5.3.2(9) AND 0.0.3. 200*' C ? ^4'*97R5 3.2.3 765.82 FSAR 1. 9. 33 SECTION 5.H - COMPLEX PROCEDURES MODIFIES ANSI SHALL HAVE CHECKOFF N18.7-1976 LISTS. SYSTEM PROCEDURES SHALL HAVE CHECKOFF LISTS WHERE APPROPRIATE.
5.3.3. REQUIREMENTS OOO50-C 2 07/29/84 2.2.2 765.83 FSAR 1. 9. 33 ANSI N18.7-1976 3.4 FOR SYSTEM OPERATING 10011-C 3 04/18/85 PROCEDURES 5.3.3. REQUIREMENT OOO50-C 2 07/29/84 2.2.5 765.84 FSAR 1. 9. 33 ANSI N18.7-1976 FOR OFF-NORMAL PROCEDURES 5.3.4.1. RECOVERY 10006-C O 04/24/84 3.3.5 765.85 FSAR 1. 9. 33 ANSI N18.7-1976 FROM TRIP MUST BE IN ACCORDANCE WITH THE STARTUP PROCEDURE.
-)
e l'
Page No. 2C 12/06/05 TABLE 3.3-1 IMPLEMENTING DOCUMENTS FOR PLANT
==..... .....................................
OPERATIONS AND SUPPORT
, ====.........=======..
APPROVED DOCUMENT DRAFT COMMITMENT COMMITMENT DCCUMENT/ FEATURE REMARKS / SUBSECTION SECTION DOCUMENT NUMBER NUMBER REV DATE SOURCE SECTION .................................... ........
-...... .......... ................ .... ............... ..... .co...........
00050-C 2 07/29/84 2.2.1 765.86 FSAR 1. 9. 33 ANSI N18.7-1976 5.3.4.1.
04/18/85 3.3 REQUIREMENT FOR 10011-C 3 START-UP PROCEDURES 5.3.4.1(1). 10001-C O 04/19/85 3.0 765.87 FSAR 1. 9. 33 ANSI N18.7-1976 START-UP PROCEDURES SHALL HAVE PREREQUISITES.
06/16/85 3.3.2 12000 765.88 FSAR 1. 9. 33 ANSI N18.7-1976 5.3.4.1(2). MAIN 10011-C 4 SERIES BODY OF START-UP PROCEDURES SHALL INCLUDE MAJOR STEPS AND REFERENCE TO SYSTEM PROCEDURES.
5.3.4.2. 20011-C 4 06/16/85 3.3.2 12000 765.89 FSAR 1. 9. 33 ANSI N18.7-1976 SERIES REQUIREMENT FOR SHUTDOWN PROCEDURES
- MUST INCLUDE INSTRUCTIONS FOR MAINTAINING HOT STANDBY OR COLD SHUTDOWN.
ANSI N18.7 1976 S.3.4.3. OPERATION 10011-C 4 06/16/35 3.3.2 12000 765.90 FSAR 1. 9. 33 SERIES AND LOAD CHANGING PROCEDURES SHALL INCLUDE MAKING DELIBERATE LOAD CHANGES, RESPONDING TO UNANTICIPATED LOAD CHANGES AND ADJUSTING OPERATING PARAMETERS.
ANSI N18. 7- 1976 5.3.4.4. PROCESS 10001-C 0 04/19/84 5.2.3 12000 765.91 FSAR 1. 9. 33 MONITORING SERIES PROCEDURES SHALL CONTAIN MAXIMUM AND MINIMUM LIMITS I
i O O O O O O O
..- . ._ . _ . - - , _ . . . . . .. , - ~ . . . . . . - - . . . . . _ . . . .
O 21 O 3 c o ~
o)
Page No.
12/06/85 TABLE 3.3-1 IMPLEMENTING DOCUMENT 3 FOR PLANT
e==-=e=====================n=============
OPERATIONS AND SUPPCFT
=======-==
APPROVED DOCUMENT DRAFT NUMBER COMMITMENT COMMITMENT DOCUMENT, FEATURE REMARV: SUBSECTION SECTION DOCUMENT NUMBER REV DATE SOURCE SECTION ==================================== ========
========== ==================== ==3===========
= ====
10001-C 0 04/19/84 ALL 11880-C FSAP 9. 11 ANSI N18.7-1976 5.3.4.4. NATURE AND 11881-C 765.92 1 FREQUENCY OF PROCESS 11882-C MONITORING 11883-C PROCEDURES SHALL BE COVERED BY OPERATING PROCEDURES 10001-C 0 04/19/84 765.93 FSAR 1. 9. 33 ANSI N18.7-1976 5.3.4.4.
REQUIREMENT FOR PROCESS MONITORINC PROCEDURES 5.3.4.5(2), 18006-1 765.94 FSAR 1. 9. 33 ANSI N18.7-1976 CONTAINMENT EVACUATION PLAN SHALL BE CONTAINED IN REFUELING PROCEDURES.
MAINTENANCE OOO50-C 2 03/19/85 ALL 765.95 FSAR 1. 9. 33 ANSI N18.7-1976 5.3.5.
PROCEDURE PREPARATION 5.3.5(3). POST 10000-C O 06/05/84 3.10 765.96 FSAR 1. 9. 33 ANSI N18.7-1976 MAINTENANCE CHECK OUT AND RETURN TO SERVICE 5.3.10. TEST AND OOO50-C 0 03/19/85 3.4 765.97 FSAR 1. 9. 33 ANSI N18.7-1976 INSPECTION PROCEDURES CONTENT.
28325-C
INSPECTION OF TENDONS SHOULD BE PERFORMEND 1.3 AND 5 YEARS AFTER INITIAL STRUCTURAL INTEGRITY TEST AND EVERY 5 YEARS THEREAFTER.
t C
l Page No. 22 12/06?B5 TABLE 3.3-I IMPLEMENTING DOCUMENTS FOR PLANT ee===== =====.e.......===. ==.... ==re...eee.
OPERATIONS AND SUPPORT
......====. ===== ===
APPROVED DOCUMENT DRAFI NUMBER CCMMITMENT COMMITMENT DOCUMENT / FEATURE REMARKS / SUBSECTION SECTION DOCUMENT NUMDER REV DATE SOURCE SECTION .m=====.............====.......=2... ........
===... .......... ==.............. ............==...... .....- =....=......
26325-C 35 RG 1.35. R/2 C.2. TENDON SAMPLES 768.02 FSAR 1. 9.
FOR INSPECTION I SHOULD BE SELECTED AS DESCRIBED IN THIS SECTION.
C.3. VISUAL 28325-C 35 HG 1.35, R 2 768 03 FSAF 1 9. i INSPECTION OF TENDON ASSEMBLY HARDWARE AND SURROUNDING CONCPETE.
TENDON LOSS OF 2???5-C
- 9. 35 RG 1.35, R/2 C.4.
768.04 FSAR I.
PRESTRESS MONITORING TESTS FG I.35, C.5. TENDON 28325-C I 768.05 FSAR 1. 9. 35 R/2 MATERIAL TESTS AND INSPECTIONS I N SPEC 1 P ro vt ~c'2=
- 9. 35 RG 1.35. M/2 t .o.
768.06 FSAR 1.
TENDON SHEATHING t FILLER GREASE a
C.7. TENDON 28325-C 768.07 FSAR 1. 9. 35 RG 1.35. F/2 INSPECTION AND -
! ( ACCEPTANCE CRITERIA RG 1.35, R/2 C.8. REPORTING TO 28325-C i 768.08 FSAR 1. 9. 35 I THE COMMISSION IF INSPECTION CRITERIA ARE NOT MET.
RG 1.36, FEBRUARY CONFORMANCE IS OO400-C 769.00 FSAR 1. 9. 36 1973 DISCUSSED IN SECTION SCO21-C 1.9.36.2 OF THE FSAR.
FSAR 1. 9. 37 RG 1.37, MARCH 1973 CONFORMANCE IS SEE ANSI N45.2.1 SECTION 4774.00 OF MATRIX DISCUSSED IN SECTIONS 14.2.17.1 AND 1.9.37.2 OF THE FSAR.
O O O O O O O
O Page Rc. 23 O O '
g od 12/06/85 TABLE 3 . 3 -- 1 IMPLJMENTING DOCUMENTG FOR PLANT
=================================
OPERATIONS AND SUPPORT
==========
APPROVED DOCUMENT DRAFT NUMBER COMMITMENT COMMITMENT DOCUMENT / FEATURE REMARKS / SUBSECTION NIMB ER REV DATE SECTION DOCUMENT SOURCE SECTION ==;.=s-...============================ ========
= ========== ================ ==================== ==============
1.3 RESPONSIBILITY 00350-C 0 03/19/85 3.1.5 775.01 FSAR 1. 9. 37 ANSI N45.2.1-1973 3.1 20408-C 0 07/22/85 20427-C 0 12/04/84 4.4.4 775.02 FSAR 1. 9. 37 ANSI N45.2.1-1973 2.1 PLANNING 2.2 PROCEDURES AND 20427-C 0 12/04/84 ALL 775.03 FSAR 1. 9. 37 ANSI N45.2.1-1973 INSTRUCTIONS 20427-C 0 12/04/84 SHEET 1 775.04 FSAR 1. 9. 37 ANSI N45.2.1-1973 2.3 RESULTS 2.4 PERSONNEL 20427-C 0 12/04/84 4.4.2 775.05 PSAR 1. 9. 37 ANSI N45.2.1-1973 QUALIFICATIONS 775.06 FSAR 1. 9. 37 ANSI N45.2.1-1973 2.5 TEST EQUIPMENT ANSI N45.2.1-1973 3.1 CLEANNESS 20427-C 0 12/04/84 4.3.1 775.07 FSAR 1. 9. 37 CLASSIFICATIONS 4.3.2 4.3.3 4.3.4 TABLE 1 FSAR 1. 9. 37 ANSI N45.2.1-1973 3.2 WATER QUALITY 775.09 REQUIREMENTS 4.0 20004-C 0 05/14/85 4.2 775.09 FSAR 1. 9. 37 ANSI N45.2.1-1973 PRE-INSTALLATION 20527-C 0 12/04/84 4.2 CLEANNESS 37 ANSI N45.2.1-1973 5.0 INSTALLATION 20408-C 0 07/22/05 2.5
, 775.10 FSAR 1. 9.
4.1.1 CLEANING I 20427-C 0 12/04/84 4.2 TABLE 1 FSAR 1. 9. 37 ANSI N45.2.1-1973 6.0 MAINTENANCE OF 775.11 4
INSTALLATION CLEANNESS 4
e 9
._m. .m__..__ . - _ _ - _ _ . _ _ . . . _ _ _ _ _ _ _ . - . . _ _ _ . _ _ . _ _ _ _ _ _ . _ . _ - _ - _ _ _ _ _ _ _ _ _ _ . _ _ . _ _ _ _ _ _ _ _ .
s Page No. 24 12/06/85 TABLE 3.3-3 IMPLEMENTING DOCUMENTS FOR PLANT
==,======e=======================
OPERATIONS AND SUPPORT
-=========
COMMITMENT DOCUMENT / FEATURE REMARKS / SUBSECTION APPROVED DOCUMENT DRAFT NUMBER COMMITMENT SECTION NUMBER REV DATE SECTION DOCUMENT SOURCE ========
= -========= ================ ==============e===== =================n== ==============================
37 ANSI N45.2.1-1973 7.1 PREPARATIONS 20427-C 0 12/04/04 4.2 775.12 FSAR 1. 9.
FOR PRE-OPERATIONAL CLEANING 775.13 FSAR 1. 9. 37 ANSI N45.2.1-1973 7.2 FLUSHING AND CLEANING METHODS 775.14 FSAR 1. 9. 37 ANSI N45.2.1-1973 7.3 CLEANING PRECAUTIONS 775.15 FSAR 1. 9. 37 ANSI N45.2.1-1973 7.4 CONTROL OF CLEANING SOLUTIONS t
FSAR 37 ANSI N45.2.1-1973 8.0 LAYUP AND 20427-C 0 12/04/84 775.16 1. 9.
POST-LAYUP CLEANING 37 ANSI N45.2.1-1973 9.0 RECORDS 20427-C 0 12/04/84 4.4.2 775.17 FSAR 1. 9.
'779.00 FSAR 1. o 1R RG 1.38 R/2 CONFORMANCE IS OO850-C 2 03/17/85 DISCUSSED IN SECTION 00851-C 0 08/04/84 l
1.9.38.2 OF THE 85307-1 1 05/07/84
[
FSAR.
l
~
$ vit
- /7 .01 FSAR 1. 9. 38 ANSI N45.2.2-1972 2. MEASURES SHALL OO850-C 2 03/17/85 BE IMPLEMENTED FOR OO851-C O 08/04/84 PACKAGING, SHIPPING, RECEIVING. STORAGE AND RANDLING OF ITEMS TO BE INSTALLED IN THE NUCLEAR POWER PLANT h 8 02 FSAR 1. 9. 38 ANSI N45.2.2-1972 2.1. PLANNING TO OO851-C 0 08/04/84 TAKE INTO ACCOUNT THE NEED FOR PREPAPATION AND CONTROL OF WORK INSTRUCTIONS f-i O O O O O O O
7 u-Page 25 12/06/85 TABLE 3.3-1 IMPLEMENTING DOCUMENTS FOR PLANT
-====--== =========================
OPERATIONS AND SUPPORT
==========
APPROVED DOCUMENT DRAFT COMMITMENT DOCUMENT / FEATURE REMAPKS/ SUBSECTION DOCUMENT NUMBER COMMITMENT NUMBER REV DATE SECTION SOURCE SECTION ====......========================r== ========
= ========== ================ ====...============= ==============
PROCEDURES AND OO851-C 0 08/04/84 780.03 FSAR 1. 9. 38 ANSI N45.2.2-1972 2.2.
INSTRUCTIONS FOR PACKAGING.
RECEIVING. SHIPPING AND STORAGE.
DOCUMENTATION 00850-C 2 03/17/05 7 ANSI N45.2.2-1972 2.3.
C( 780b .04 FSAR 1. 9. 38 OF INSPECTION AND 8
TEST RESULTS MEASURING AND OO208-C O 08/14/84 ANSI N45.2.2-1972 2.5.
d'd 780.05 Alb FSAR 1. 9. 38 TEST EQUIPMENT
- gs</L FSAR 1. 9. 38 ANSI N45.2.2-1972 2.6. HOUSEKEEPING OO951-C O 08/04/04 7.4.4 v 780.06 IN JOB-SITE AREAS, OO254-C 1 06/14/85 SHIPPING, RECEIVING, STORAGE, HANDLING
,g ,
CLASSIFICATION OO851-C 0 08/04/84 7.2.4
( 780.07 FSAR 1. 9. 38 ANSI N45.2.2-1972 2.7.
OF ITEMS INTO LEVELS WITH RESPECT TO PROTECTIVE MEASURES TO PREVENT DAMAGE, DETERIORATION OR CONTAMINATION.
PACKAGING - 00851-C 0 08/04/84 7.2.4 7AO.08 FSAR 1. 9. 38 ANSI N45.2.2-1972 3.
GENERAL REQUIREMENTS 3.2. LEVELS OF OO851-C 0 08/04/84 7.2.4 780.09 FSAR 1. 9. 38 ANSI N45.2.2-1972 PACKAGING TO PROVIDE VARYING DEGREES OF .
PROTECTION Ib by180.10 FSAR 1. 9. 38 ANSI N45.2.2-1972 3.3. CLEANING IN OO851-C 0 08/04/84 7.3.4 PREPARATION FOR PRESERVATION OR PACKAGING.
e
. . _ . . ..- _ _ _ _ _ _ m_.__. . _ _ _ - . . _ . . ......m. .m_.._ _ m . _ _ _ .___m. _ _.______-_m.mm._ .___._._m. _ . . _ . _ . _ . . . . _ . _ . _ _ . .
Page No. 26 12/06'85 TABLE 3.3-1 IMPLEMENTING DOCUMENTS FOR PLANT e======.wese.================ ....,==========
OPERATIONS AND SUPPORT
=========ew...=====,
APPROVED DOCUMENT DRAFT COMMITMENT DOCUMENT / FEATURE REMARKS SUBSECTION DATE SECTION DOCUMENT NUMBER COMMITMENT NUMBER REV ........
a SOURCE SECTION ,,=.................. ......--................. =.........
.......,=..r=,,, ,-...... = r........
==...e. ==ere.....
00851-C 0 08/04/84 7.3.1 l'J ANSI N45.2.2-1972 3.4. METHODS OF FSAR 1. 9. 38 7.3.2 Q 780.11 PRESERVATION OP ITEMS SUBJECT TO DELETERIOUS CORROSION
,\. PLUGS, CAPS, 00851-C 0 08/04/04 7.4.4 FSAR 1. 9. 38 ANSI N45.2.2-1972 3.5.
' 762.12 TAPES, ADHEASI'IES TO SEAL OPENINGS.
PROTECT TNREADS, END PREPARATIONS AND OTNER SENSITIVE SURFACES.
g BARRIER AND OO851-C 0 08/04/84 7.3.3 FSAR 1. 9. 3d ANSI N45.2.2-1972 3.6.
7.4.4 t 780.13 WRAP MATERIALS AND 1
DESICCANTS r
D 7.5 CONTAINERS 00851-C O 08/04/84 780.14 FSAR 1. 9. 36 ANSI N45.2.2-1972 3.7.
CRATING AND SKIDS g6 <lb FSAR 1. 9. 38 ANSI N45.2.2-1972 3.8. CUSHIONING, 00851-C 0 08/04/84 7.5 7 0.15 BLOCKING, BRACING AND ANCHORING
$ IV MARKING TO OO851-C O 08/04/84 7.4.4.E T80.16 PSAR 1. 9. 38 ANSI N45.2.2-1972 3.9.
00853-C 2 05/05/85 4.1.1 MAINTAIN PROPER 4.1.2 IDENTIFICATION 6 4.1. GENERAL 00851-C O 08/04/84 7.5
[ 780.17 FSAR 1. 9. 38 ANSI N45.2.2-1972 SHIPPING REQUIREMENTS 4.2. TRANSPORTATION OO851-C 0 08/04/84 7.5.5 780.18 FSAR 1. 9. 38 ANSI N45.2.2-1972 REQUIREMENTS PRECAUTIONS OO851-C C 08/04/04 7.5 780.19 FSAR 1. 9 38 ANSI N45.2.2-1972 4.3.
CURING LOADING AND TRANSIT (SEE FSAR SECT. 1.9.38.2-4)
I
- # 9 9 e e e ,
/O h / -
\
P&ge No 27 Y
12/06/85 TABLE 3.3-1 IMPLEMENTING DOCUMENTS FOR PLANT mee================.==========..=============
OPERATIONS AND SUPPORT o.....=====..........=
APPROVED DOCUMENT DR4FT NUMBER COMMITMENT COMMITMENT DOCUMENT / FEATURE PEMARKS/ SUBSECTION SECTION DOCUMENT NUMBER REV DATE SOURCE SECTION
... ..-==. ................ ==.....=,.. n== .... .. ....=e........... ===========..............========... ====..==
=
IDENTIFICATION OOB51-C 0 08/04/84 7.4.4 780.20 FSAR 1. 9. 38 ANSI N45.2.2-1972 4.4.
OO853-C 2 05/05/05 4.1.1 AND MARKING (SEE 4.1.2 FSAR 1.9.38.,2-4) 6 SHIPMENTS FROM OO851-C O 08/04/84 7.5 780.21 FSAR 1. 9. 38 ANSI N45.2.2-1972 4.5.
COUNTRIES OUTSIDE OF U.S. (SEE FSAR 1.9.38.2-4).
GENERAL OO150-C 2 03/17/85 7 b 780.22 FSAR 1. 9. 38 ANSI N45.2.2-1972 5.1.
RECEIVING Sib REQUIREMENTS ANSI N45.2.2-1972 5.2. RECEIVING OO850-C 2 03/17/85 S
'A 780.23 FSAR 1. 9. 38 N INSPECTION REQUIREMENTS h /b 780.24 FSAR 1. 9. 39 ANSI N45.2.2-1972 5.2. DISPOSITION OF """** " 03/17/85 8 9
IVED ITEMS 10 h ANSI N45.2.2-1972 5.3.1. RECEIPT OF OO850-C 2 03/17/85 8.3.E 780.25 FSAR 1. 9. 38 ITEMS FOUND TO BE ACCEPTABLE 5.3.2. RECEIPT OF 00050-C 2 03/17/85 8.3.D D 780.26 FSAR 1. 9. 38 ANSI N45.2.2-1972 ITEMS NOT CONFORMING TO SPECIFIED REQUIREMENTS.
RECEIPT OF OOB50-C 2 03/17/85 10 FSAF 1. 9. 38 ANSI N45.2.2-1972 5.3.3.
[780.27 ITEMS WHOSE ACCEPTABILITY IS QUESTIONABLE OR UNACCEPTABLE CONDITION IS QUESTIONABLE.
Poge No. 26 12/06/85 TABLE 3.3-1 IMPLEMENTING DOCUMENTS FOR PLANT
=================================
OPERATIONS AND SUPPORT
==========
APPROVED DOCUMENT DRAFT COMMITMENT DOCUMENT / FEATURE REMARKS / SUBSECTION DATE SECTION DOCUMENT NUMBER COMMITMENT NUMBER REV ========
SOURCE SECTION ====================================
= ========== ================ ==================== ==============
OO850-C 2 03/17/80 8.3.D ANSI N45.2.2-1972 5.4. STATUS 780.28 FSAR 1. 9. 38 INDICATING SYSTEM, 8.3.E WHICH IDENTIFIES ITEMS AS ACCEPTABLE OR UNACCEPTABLE FOR INSTALLATION.
OO850-C 2 03/17/80 10.3 ANSI N45.2.2-1972 5.5. CORRECTION OF 780.29 FSAR 1. 9. 38 NONCONFORMANCES OO851-C O 08/04/84 7.4.4.E ANIS N45.2.2-1972 5.6. MARKING TO 780.30 FSAR 1. 9. 38 PROVIDE POSITIVE IDENTIFICATION DURING RECEIVING.
STORAGE, AND INSTALLATION.
O OO850-C 2 03/17/85 7 ANSI N45.2.2-1972 5.7. DOCUMENTATION 780.31 FSAR 1. 9. 38 8 (SEE FSAR 9 1.9.38.2-7) 44 ANSI N45.2.2-1972 6.1. GENERAL 00851-C 0 08/04/84 7.4 780.32 FSAR 1. 9. 38 STORAGE REQUIREMENTS AND LEVELS OF STORAGE (W STORAGE AREAS OO851-C O 08/04/84 7.4.1 780.33 FSAR 1. 9. 38 ANSI N45.2.2-1972 6.2.
(SEE FSAR _
1.9.38.2-8) iNL 1. 9. 38 ANSI N45.2.2-1972 6.3. STORAGE OO851-C O 08/04/84 .4.4 4780.34 FSAR -
METHODS (SEE FSAR 1.9.38.2-9)
CONTROL OF OO851-C O 08/04/84 7.4.4 t,Y3780.35 FSAR 1. 9. 38 ANSI N45.2.2-1972 6.4.
OO853-C 2 05/05/85 6.1 ITEMS IN STORAGE C
6.5. REMOVAL OF OO853-C 2 05/05/85 6.2 780.36 FSAR 1. 9. 30 ANSI N45.2.2-1972 ITEMS FROM STORAGE
' C r
9 ay .
- # 9 G G e e
a C O m O 3 (
(',f O v
Page No. 29 (V U t%
(
)
(v) 12/06/85 TABLE 3.3-1 IMPLEMENTING DOCUMENTS FOR PLANT
====e============================
OPERATIONS AND SUPPORT
e,=========ne======e APPROVED DOCUMENT DRAFT NUMBER COMMITMENT COMMITMENT DOCUMENT / FEATURE REMAPKS/ SUBSECTION SECTION DOCUMENT NUMBER REV DATE SOURCE SECTION ==,-================================ ======
= ========== ================ ==================== ==============
OO853-C 2 05/05/85 6.5
- 9. 38 ANIS N45.2.2-1972 6.6. STORAGE '
780.37 FSAR 1.
RECORDS OC851-C O 08/04/84 7.1
- 9. 38 ANSI N45.2.2-1972 7.1. GENERAL 780.38 FSAR 1.
HANDLING REQUIREMENTS METHODS AND OO851-C 0 08/04/84 7.1 780.39 FSAR 1. 9. 38 ANSI N45.2.2-1972 7.2.
PROCEDURES FOR ITEMS WHICH REQUIRE SPECIAL HANDLING.
HOISTING 20426-C
- f 0.40 FSAR 1. 9. 38 ANSI N45.2.2-1972 7.3.
EQUIPMENT (SEE FSAR j
M h 1.9.38.2-11).
W INSPECTION OF 25040-C 0 08/15/84 20426-C 780.41 FSAR 1. 9. 38 ANSI N45.2.2-1972 7.4.
25045-C 0 12/20/84 LIFTING EQUIPMENT AND RIGGING. OO851-C 0 08/04/84 PERSONNEL 20426-C 780.42 FSAR 1. 9. 38 ANSI N45.2.2-1972 7.5.
QUALIFICATION FOR OPERATION OF LIFTING EQUIPMENT.
RECORDS OF OOB50-C 2 03/17/85 3 O.43 FSAR 1. 9 38 ANSI N45.2.2-1972 8.
OO100-C 2 06/26/85 COMPLETED PROCEDURES, SUPPORTING PERSONNEL QUALIFICATION RECORDS, TEST EQUIPMENT CALIBRATION RECORDS, ECT.
- 9. 39 RG 1.39, R/2 SEE ANSI N45.2.3 SECTION 784.00 FSAR 1.
OF MATRIK
+
(
C i
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PGge No. 30 12/06/85
' TABLE 3.3-1 IMPLEMENTING DOCUMf:NTS FOR PLANT
================== ..====2=======
OPERATIONS AND SUPPORT
' ======================
APPROVED DOCUMENT DRAFT COMMITMENT COMMITMENT DOCUMENT / FEATURE REMARKS / SUBSECTION SECTION DOCUMENT NUMBER NUMBER REV DATE SOURCE SECTION ==================================== ========
========e========= ==================-
= ========== ==========
RESPONSIBILITY 00254-C 1 06/14/85 3.0 FSA* 9. 39 ANSI N45.2.3-1973 1.3 785.01 1.
OO350-C 0 03/19/85 3.1.5 5.1.3 PLANNING 00254-C 1 06/14/85 4.0 785.02 FSAR 1. 9. 39 ANSI N45.2.3-1973 2.1 0 12/04/84 4.1.5 20427-C 25266-C 0 09/04/84 4.0 2.2 PFOCEDURES AND OO254-C 1 06/14/85 ALL 785.03 FSAR 1. 9. 39 ANSI N45.2.3-1973 INSTRUCTIONS RESULTS 00254-C 1 06/14/85 6.2.4 785.04 FSAR 1. 9. 39 ANSI N45.2.3-1973 2.3 SHEET 1 SHEET 2 PERSONNEL 00254-C 1 06/14/85 3.14.2 795.05 FSAR 1. 9. 39 ANSI N45.2.3-1973 2.4 0 4.1.6.I QUALIFICATIONS 00700-C 03/10/85 CONTROL OF SITE 00253-C 0 01/20/85 4.0 785.06 FSAR 1. 9. 39 ANSI N45.2.3-1973 3.1 4.0 AREA 00254-C 1 06/14/05 OO653-C 0 08/15/85 ALL i
3.2 CONTROL OF 00254-C 1 06/14/85 5.3.3 785.07 FSAR 1 9. 39 ANSI N45.2.3-1973 FACILITIES 5.5.6 5.5.7 25266-C 0 09/04/84 4.0 f
3.2.1 CLEANNESS OO254-C 1 06/14/85 5.1 785.08 FSAR 1. 9. 39 ANSI N45.2.3-1973 00260-C O 05/27/85 ALL ANSI N45.2.3-1973 3.2.2 ENVIRONMENT 20427-C 0 12/04/84 4.3.5 785.09 FSAR 1. 9. 39 s
(
- # 9 9 9 e e
-. . . - - -.- . ., . . ~ - - - - . . - . . ~ . . . - . . - . . . - - - - . ~ . . ~ . _ ~ - - - - - - - . - - . - ~ . . ~ ~ ._ . ~ ~ .
Page.No. 31 12/06/95 i TABLE 3.3-1 IMPLEMENTING DOCUMENTS FOR PLANT
..= .e==...e.................................
OPERATIONS AND SUPPORT REMARKS / SUBSECTION APPROVED DOCUMENT DRAFT NUMBER COMMITMFNT COMMITMENT DOCUMENT / FEATURE NUMBER REV DATE SECTION- DOCUMENT SOURCE SECTIOff ........
==..... .......... ................ ...................= .................... .................................... 5 39 ANSI N45.2.3-1973 3.3 MATERIALS AND OO254-C 1 06/14/85 5.7 785.10 FSAR 1. 9.
EQUIPMENT 20427-C 0 12/04/84 4.3.5 785.11 FSAR 1. 9. 39 ANSI N45.2.3-1973 3.4 CONSTRUCTION 20427-C 0 12/04/84 4.3.5 TOOLS. SUPPLIES, AND EQUIPMENT ,
I 785.12 FSAR 1. 9. 39 ANSI N45.2.3-1973 3.5 SURVEILLANCE, OO254-C 1 06/14/85 3.0 INSPECTIONS. AND 6.2 EXAMINATIONS 39 ANSI N45.2.3-1973 4.0 RECORDS OO254-C 1 06/14/85 8.0 785.13 FSAR 1. 9. !
40 RG 1.40, MARCH 1973 CONFORMANCE IS OO420-C 0 06/20/85 OO400-C 787.00 FSAR 1. 9.
DISCUSSED IN SECTION SOO20-C' ;
1.9.40.2 OF THE 55002-C FSAR.
789.01 FSAR 1, 9. 45 RG 1.45. MAY 1973 C.7. PROCEDURES FOR 14905-1 O 08/15/84 COhVERTING VARIOUS 14910-1 1 12/15/84 INDICATIONS TO A COMMON LEAKAGE EQUIVALENT SHOULD BE AVAILABLE TO THE OPERATORS.
790.00 FSAR 1. 9. 47 RG 1.47, MAY 1973 CONFORMANCE IS 10005-C 0 06/19/84 DISCUSSED IN SECTIONS 7.5.5 AND 10.4.9.5 OF THE FSAR.
793.01 FSAR 1. 9. 52 RG 1.52. R/2 C.4.D. EACH 14510-1 1 12/04/84 .6.2 ATMOSPHERE CLEANUP 14514-C 1 12/13/84 6.2 TRAIN SHOULD BE 14515-1 1 12/13/84 6.2 OPERATED AT LEAST 10 14516-1 1 12/20/84 6.2 HOURS PER MONTH WITH HEATERS ON TO REDUCE MOISTURE ON ADSORBERS AND HEPA FILTERS.
t' l
I 1 k.
Page No. 32 12/06/05 l
TABLE 3.3-1 IMPLEMENTING DOCUMENTS FOR PLANT
=================================
I OPEPATIONS AND SUPPORT l ======================
l APPROVED DOCUMENT DRAFT COMMITMENT DOCUMENT / FEATURE REMARKS / SUBSECTION SECTION DOCUMENT NUMBER COMMITMENT NUMBER REV DATE SECTION ========
l SOURCE ==================== ===e-ev=============================
===== ========== ================ =================-
C.5.A. VISUAL 27420-C 0 06/13/85 793.02 FSAR 1. 9. 52 FG 1.52. R/2 INSPECTION OF ESF ATMOSPHERE CLEANUP SYSTEM IN ACCORDANCE WITH SECTION 5 OF ANSI N510-1980.
54051-1 O 09/29/85 1.0 54052-1 52 PG 1.52. Re 2 C.S.B. AIRFLOW 793.03 FSAR 1. 9. 4.3 DISTRIBUTION TEST TO 5.2 HEPA FILTERS AND ADSORBERS AFTER 54053-1 O 09/29/85 1.0 MAINTENANCE 4.3 AFFECTING FLOW 5.2 DISTRIBUTION IN ACCORDANCE WITH SECTION 9 OF
" INDUSTRIAL VENTILLATION" AND SECTION 8 OF ANSI N510-1960.
C.S.C. IN PLACE DOP 54051-C 793.04 FSAR 1. 9. 52 RG 1.52. R/2 54052-C TEST FOR HEPA FILTERS ONCE PER 54053-C 54056-1 18 MONTHS AND FOLLOWING PAINTING, 54058-1 54057-1 FIRE. CHEMICAL RELEASE. OR FILTER REPLACEMENT IN ACCORDANCE WITH SECTION 10 OF ANSI N510-1980, ADSORBER 54051-C FSAR 1. 9. 52 RG 1.52, R/2 C.5.D.
793.05 SECTION LEAK TESTING 54052-C FOR CONDITIONS AND 54053-C INTERVALS DESCRIBED 54062-I IN ACCORDANCE WITH 54063-1 ANSI N510-1980, 54064-1 SECTION 12.
O O O O O O O
. - - . -- . - - . . . .- . _~ . _ . - . . - - _ - - , ~ . . .
~' -x Pa-e 33 12/06/05 TABLE 3.3-1 IMPLEMENTINn DOCUMENTS FOR PLANT
=-===============================
OPERATIONS AND SUPPORT
==========
REMARKScSUBSECTION APPROVED DOCUMENT DRAFT NUMBER COMMITMENT COMMITMENT DOCUMENT / FEATURE SECTION DOCUMENT NUMBER REV DATE SOURCE SECTION ==================================== ========
= ===== w=== ================ -========,==-======e ==============
54050-C 793.06 FSAR 1. 9. 52 RG 1.52. R/2 C.6.B. EFFICIENCY OF ACTIVATED CARBON ADSORBER BY LABORATORY TESTING OF SAMPLES OF ACTIVATED CARBON AS INDICATED BY TABLE 2 OF THIS REG GUIDE.
THE 54050-C 793.07 FSAR 1. 9. 52 RG 1.52. R/2 C.6.8.
ACTIVATED CARBON ADSORBER SECTION SHOULD BE REPLACED WHEN CONDITIONS DESCRIBED IN THIS SECTION OCCUR.
794.01 FSAR 1. 9. 52 ANSI N509-1980 TABLE 5.1 DESCRIBES PHYSICAL PROPERTY SPECIFICATIONS FOR NEW, UNUSED ACTIVATED CARBON ADSORBER MATERIAL VISUAL 27420-C O 06/13/85 4 795.01 FSAR 1. 9. 52 ANSI N510-19BO 5.
INSPECTION
- 8. AIRFLOW CAPACITY 54054-C 795.02 FSAR 1. 9. 52 ANSI N510-1980 54057-1 AND DISTRIBUTION 54059-1 TESTS 54060-1 54051-C
' 54052-C 54053-C
- 9. AIRFLOW 1-GK-09 795.03 FSAR 1. 9. 52 ANSI N510-1980 1-GG-04 DISTRIBUTION TESTS PER AMERICAN 1-GL-06 CONFERENCE OF GOVERNMENTAL 1
INDUSTRIAL HYGENISTS ON INDUSTRIAL VENTILLATION, 1976.
(
m ,
Page No. 34 12/06/85 IMPLEMENTING DOCUMENTS FOR PLANT TABLE 3.3-1
-======================================
OPERATIONS AND SUPPORT
=================e
APPROVED DOCUMENT DRAFT COMMITMENT COMMITMENT DOCUMENT / FEATURE REMARKS / SUBSECTION SECTION DOCUMENT NUMBER NUMBER REV DATE SOURCE SECTION ===============.. ================== ........
,s ====...... ================ ==================== ==============
54051-C
- 9. 52 ANSI N510-1980 10. IN PLACE IEAK 54052-C 795.04 FSAR 1.
TESTS, HEPA FILTER 54053-C BANKS 54056-1 54057-1 54058-1 54062-1
- 9. 52 ANSI N510-1980 12. IN PLACE LEAK 54063-1 795.05 FSAR 1 TEST, ADSORBER STAGE 54064-1 54051-C 54052-C 54053-C A
/ 796 .00 9. 54 RG 1.54, R/I CONFORMANCE IS FSAR 1.
DISCUSSED IN SECTION 1.9.54.2 OF THE FSAR.
FSAR 1. 9. 54 ANSI N101.4-1972 CONFORMANCE IS J797.00 DISCUSSED IN SECTIONS 1.9.54.2 AND 6.1.2.1 OF THE FSAR. ~~.
RG 1.64, R/2 CONFORMANCE IS OO400-C 1 804.00 FSAR 1. 9. 64 t
DISCUSSED IN SECTION 1.9.64.2 OF THE FSAR.
CONFORMANCE IS OO400-C 805.00 FSAR 1. 9. 64 ANSI N45.2.11-1974 DISCUSSED IN SECTION 1.9.64.2 OF THE I FSAR.
RG 1.65, OCTOBER CONFORMANCE IS OO400-C J 806.00 FSAR 1. 9. 65 50020-C 1973 DISCUSSED IN SECTION 1.9.65.2 CF THE FSAR.
i~
O O O O O O O
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=================================
OPERATIONS AND SUPPORT
==========
APPROVED DOCUMENT DRAFT NUMBER COMMITMENT COMMITMENT DOCUMENT / FEATURE REMARKS / SUBSECTION DOCUMENT NUMBER REV DATE SECTION SOURCE SECTION ==================================== ========
= ========== ================ ==================== ==============
RG 1.68, R/2 C.4. PROCEDURES TO SUM-20 2 03/06/85 6.1.8.2 808.01 FSAR 1. 9. 68 5.3 ENSURE THAT 00306-C 0 08/14/84 TEMPORARY CABLES AND TEST LEADS USED IN STARTUP TEST PHASE ARE ROUTED NOT TO COMPROMISE ELECTRICAL SEPARATION CRITERIA.
1-600-13 808.02 FSAR 1. 9. 68 RG 1.68, R/2 C.8. MILESTONES AND POWER NOLD POINTS RG 1.68 R/2 C.9. STARTUP REPORT 51002-C 0 10/12/84 808.03 FSAR 1. 9. 68 REQUIREMENTS INITIAL 1-500-04 0 06/09/85 5.0 1-500-01 808.04 FSAR 1. 9. 68 RG 1.68 R/2 APP.A.2.
1-600-04 FUEL LOADING -
ESTABLISH REQUIREMENTS FOR OPERABILITY OF PLANT SYSTEMS AND COMPONENTS TO ENSURE PERSONNEL SAFETY IN THE E7ENT OF ERRORS OR MALFUNCTIONS.
INITIAL 1-500-01 808.05 FSAR 1. 9. 68 RG 1.68 R/2 APP.A.2.
FUEL LOADING -
INITIAL CORE LOADING SHOULD BE DIRECTLY SUPERVISED BY A SRO HAVING NO OTHER CONCURRENT DUTIES.
APP.A.2. INITIAL 1-500-04 0 03/28/85 ALL 1-500-01 808.06 FSAR 1. 9. 68 RG 1.69, R/2 FUEL LOADING - THE LOADING OPERATIONS SHOULD BE CONDUCTED IN STRICT ACCORDANCE ,
WITH DETAILED APPROVED PROCEDURES.
2 t
l'
Pcge No. 36 12/06/85 TABLE 3.3-1 IMPLEMENTING DOCUMENTS FOR PLANT
.---==-===,============e============ ==-=====
OPERATIONS AND SUPPOPT
=_-=================-=.-
DOCUMENT / FEATURE REM /RKS/ SUBSECTION APPROVED DOCUMENT DRAFT NUMBER COMMITMENT COMMITMENT NUMBER REV DATE SECTION DOCU'fENT SOURCE SECTION
= ========== -= ==e=======c== = = = = = = = = = = = = = . - = = = = = ===================- -==-================================ ==
RG 1.68, R/2 APP.A.2. INIT. FUEL I-500-04 O 03/28/85 4.0 808.07 FSAR 1. 9. 68 LOADING - ESTABLISH CRITERIA AND REQUIREMENTS FOR REQUIRED ACTIONS SHOULD MEASURED RESULTS DEVIATE FROM EXPECTED VALUES.
68 PG 1.68. R/2 APP.A.2. INITIAL I-500-01 808.08 FSAR 1. 9.
FUEL LOADING -
ESTJ ? ..-I S H RECL i:MENTS FOR CON % <JOUS MONiiORING OF NEUTRON FLUX THROUGHOUT CORE LOADING FSAR 9. 68 RG 1.68. R/2 APP.A.2. INITIAL 1-500-01 808.09 1.
FUEL LOADING -
ESTABLISH REQUIREMENTS FOR PERIODIC DATA-TAKING FSAR 1. 9. 68 FG 1.68, R/2 APP.A._, INITIAL I-500-01 808.10 FUEL LOADING - 93370-C INDEPENDENTLY VERIFY THAT THE FUEL AND CONTROL COMPONENTS HAVE BEEN PROPERLY INSTALLED.
808.11 FSAR 1. 9. 68 RG 1.68, R/2 APP.A.2. INITIAL 1-500-01 FUEL LOADING -
PREDICTIONS OF CORE REACTIVITY SROULD BE PREPARED IN ADVANCE.
J t
O O O O O O O
.. . , - __ ._ . . _ . . _ . . = . . . -__ . _ m --- ...__._.-m.- . __m.._...._4 m <
l r
Page No. 37 12/06/85 TABLE 3.3-1 IMPLEMENTING DOCUMENTS FOR ?LANT ,
.......=.....=............==..==......e.....
4 OPERATIONS AND SUPPORT ;
APPROVED DOCUMENT DRAFT NUMBER COMMITMENT COMMITMENT DOCUMENT / FEATURE REMARKS / SUBSECTION i NUMBER REV DATE SECTION DOCUMENT SOURCE SECTION ...........,........................ ........
[
=...... ...,...... ................ .................... ...=...... .........
1 RG 1.68, R/2 APP.A.2. INITIAL I-500-04 0 03/28/85 5.16 i 808.12 FSAR 1. 9. 68 FUEL LOADING -
ENSURE THAT ALL I APPL. TECH. SPEC. ,
AND OTHER ,
l PREREQUISITES HAVE BEEN SATISFIED.
RG 1.68, R/2 APP.A.2.a. .
1-500-01 808.13 FSAR 1. 9. 68 ;
PRECRITICAL TEST -
SHUT DOWN MARGIN i VERIFICATION FSAR 1. 9. 68 RG 1.68, R/2 APP.A.2.b. 1-5SF-02 0 04/15/95 'ALL !
808.14 1-5SF-03 0 12/12/84 ALL PRECRITICAL TEST - ,
COMPLETE TESTING OF 1-5SF-04 0 11/03/84 ALL CONTROL ROD SYSTEMS 1-SSF 05 0 03/16/85 ALL R/2 APP.A.2.c. 1-5SB-01 0 03/19/85 ALL !
I 808.15 FSAR 1. 9. 68 RG 1.68 ;
PRECRITICAL TEST -
R/2 APP.A.2.d. 1-5BB-01 0 06/01/85 ALL 808.16 FSAR 1. 9. 68 RG 1.68 PRECRTICAL TEST - l RCS LEAK RATE VERIFICATION APP.A.2.e. 1-SSJ-01 0 03/22/85 1-600-12 '
808.17 FSAR 1. 9. 60 RG 1.68, R/2 l
' PRECRITICAL TEST -
WATER QUALITY AND
' BORON CONCENTRATION MEASUREMENT OF RCS.
i i
RG 1.68, R/2 APP.A.2.f. 1-5BB-04 0 02/13/85 ALL ,
! 808.18 FSAR 1. 9. 68
' PRECRITICAL TEST - 1-5BB-05 0 02/22/85 ALL ,
" RCS FLOW TEST FOR 1-5BB-06 0 12/12/85 ALL
-VIBRATION LEVELS !
CORE AND COMPONENT i 1
4 DIFFERENTIAL i i
I PRESSURES LOSS OF
)' FLOW TO VERIFY COASTDOWN t ,
j f
h h
. _ _ _ _ - - _ _ _ _ . - _ . _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ - _ . . _ _ _ _ -m___ _ _ _ _ ______m +<__ _.m____.,__._________ . + - - - < - - - - _ _ . . - -.
. -- - - . _ _ = .
Page No. 38 12/06/85 IMPLEMENTING DOCUMENTS FOR PLANT TABLE 3.3-1
=================================
OPERATIONS AND SUPPORT r ======================
APPROVED DOCUMENT D RAFT COMMITMENT DOCUMENT / FEATURE REMARKS / SUBSECTION SECTION DOCUMENT NUMBER COMMITMENT NUMBER REV DATE SOURCE SECTION ==================================== ========
= ========== ================ ==================== ==============
1-5SE-02 RG 1,68 R/2 APP.A.2.g.
608.19 FSAR 1. 9. 68 PRECRITICAL TEST -
SOURCE AND INTERMEDIATE RANGE MONITORS APP.A.2.h. 1 ~=SE-01 0 02/16/85 ALL I 9. 6e RG 1.68, R .' 2 808.20 FSAR PRECRITICAL TEST-MECHANICAL 1ND ELECTRICAL TEST OF INCORE MONITORS INCLUDING TRAVERSING INCORE MONITORS 1-600-02 0 03/22/95 4.6 1-600-04
CRITICALITY PREDICTIONS FOR BORON CONC. SHOULD BE PROVIDED AND ACTIONS TO BE TAKEN ESTABLISHED IF PLANT PERFORMANCE DEVIATES.
APP.A.3. INITIAL I-500-04 0 03/28/85 5.16 FSAR 1. 9. 68 RG 1.68, R/2 808.22 CRITICALITY - ALL 1-600-02 0 03/22/85 4.0 SYSTEMS REQUIRED FOR STARTUP OR PLANT PPOTECTION SHOULD BE OPERABLE AND IN STATE OF READINESS RG 1.68, R/2 APP.A.3. INITIAL 1-600-02 0 03/22/05 4.0 808.23 TSAR 1. 9. 68 4.3.1 CRITICALITY - 1-600-02 0 03/22/05 NEUTRON FLUX LEVELS SHOULD BE CONTINUOUSLY MONITORED AND PERIODICALLY EVALUATED.
1
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4 Page 39 12/06/85 TABLF 2.3-1 IMPLEMENTING DOCUMENTS FOR PLANT
====... .. ......==========,=======e,=...=...
. OPERATIONS AND SUPPORT
..... 3=e.............
APPROVED DOCUMENT DRAFT NUMBER COMMITMENT COMMITMENT DOCUMENT / FEATURE REMARKS / SUBSECTION DOCUMENT NUMBER REV DATE SECTION SOURCE SECTION ......==................=====..===== ========
- , = = = = = = .......... ==== .= .===..=. ........ ....==...== === ....===.........
APP.A.3. INITIAL I-600-02 0 03/22/85 4.3.1 808.24 FSAR 1. 9. 68 RG 1.68. R/2 6.0 CRITICALITY - 1-600-02 0 03/22/85 REACTIVITY ADDITION SEQUENCE SNOULD BE PRESCRIBED AND REQUIRE ACHIEVING CRITICALITY AT LESS THAN ONE DECADE PER MINUTE.
68 RG 1.68 R/2 APP.A.3. INITIAL 1-600-02 0 03/22/85 5.5 808.25 FSAR 1. 9.
CRITICALITY -
SIGNAL-TO-NOISE RATIO TO BE GREATER THAN TWO.
R/2 APP.A.3. INITIAL 1-600-02 0 03/22/85 6.4.4 808.26 FSAR 1. 9. 68 PG 1.68 CRITICALITY - 6.4.5 CONTROL ROD 6.4.6 INSERTION LIMITS IN 6.4.7 THE TECH. SPECS. 6.4.8 SHOULD BE COMPLIED 6.5.10 WITH. 6.5.14 6.5.20 6.5.22 APP.A.3. INITIAL 1-600-02 O 03/22/85 ALL 808.27 FSAR 1. 9. 68 RG 1.68. R/2 CRITICALITY -
CONTROL ROD OR POISON REMOVAL SEQUENCE SHOULD BE ACCOMPLISHED BY DETAILED, APPROVED PROCEDURES FSAR 1. 9. 68 RG 1.68. R/2 APP.A.3. INITIAL 1-600-02 O 03/22/85 6.6.1 808.28 CRITICALITY -
CONTROL RODS SHOULD BE WITHDRANN BEFORE BORON DILUTION BEGINS
.. I t'
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Page No. 40 12/06 85 TABLE 3. 3- 1 IMPLEMENTING DOCUMENTS FOR PLANT
====e.c===... were.====,.e=======ew. ewe
OPERATIONS AND SUPPORT
, ========ee, e ,===== c APPROVED DOCUMENT DRAFT COMMITMENT COMMITMENT DOCUMENT / FEATURE REMARKS /SUBSECTICN DOCUMENT NUMBER NUMBER REV DATE SECTION SOURCE SECTION ..= ..,= =................................... ........
=e.......,,=... .e .c=.. ..-......., ....e...n.
==...== ..=ew..- .
INITIAL 1-600-02 O 03/22/85 5.2 FSAR 1. 9. 68 RG 1.68, R/2 APP.A.3.
808.29 CRITICALITY -
NEUTRON COUNT RATE OF AT LEAST 1/2 CPS ON STARTUP CHANNELS BEFORE STARTUP BEGINS APP.A.3. INITIAL 1-600-02 0 03/22/85 0.0 800.30 FSAR 1, 9. Se RG 1.68. R/2 CRITICALITY - USE SAME ROD WITHDRAWAL SEQUENCES AND PATTERNS THAT WILL BE USED DURING SUBSEQUENT STARTUPS.
APP.A.4.a. LOW 1-6SF-09 0 02/13/85 ALL 1-6SC-01 FSAR 9, 6R PG 1.68, R/2 808.31 1 POWER TESTING - 1-600-03 DETERMINATION OF BORON AND MODERATOR TEMPERATURE REACTIVITY COEFFICIENT OVER RANGES WHICH REACTOR MAY BE TAKEN CRITICAL APP.A.4.b. LOW 1-6SF-06 0 12/12/85 ALL 808.32 FSAR 1. 9. 68 RG 1.68. R/2 POWER TESTING -
MEASUREMENTS OF CONTROL ROD AND CONTROL ROD BANK REACTIVITY WORTHS.
APP.A.4.c. LOW 1-6SF-04 808.33 FSAR 1. 9. 68 RG 1.68. R/2 POWER TESTING-PSEUDO-ROD-E JECTION TESTS I
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Page No.
~
41 3 O 12/06 85 TABLE 3.3-1 IMPLEMENTING DOCUMENTS FOR FLANT
==== ============================
OPERATIONS AND SUPPORT
==========
APPROVED DOCUMENT DRAFT COMMITMENT DOCUMENT / FEATURE REMARKS / SUBSECTION SECTION DOCUMENT NUMBER COMMITMENT NUMBER REV DATE SECTION ========
SOURCE ====================================
= ========== ================ ==================== ==========ee==
RG 1.68, R/2 APP,A.4.d. LOW 1-600-02 O 03/22/85 6.6.14 808.34 FSAR 1. 9. 68 1-600-02 O 03/22/85 4.5 POWER TESTING -
DETERMINATION THAT ADEQUATE OVERLAP OF
' SOURCE AND INTERMEDIATE NEUTRON ,
INSTRUMENTATION EXISTS.
1-600-02 O 03/22/85 6.0
POWER TESTING - I VERIFICATION THAT PROPER OPERATIONS OF ;
PROTECTIVE FUNCTIONS AND ALARMS PROVIDE PLANT PROTECTION IN i
LOW POWER RANGE.
1-6SE-02 0 12/12/84 ALL
POWER TESTING -
DETERMINATION OF '
FLUX DISTRIBUTION i
1-600-05
808.37 FSAR 1.
POWER TESTING - l NEUTRON AND GAMMA RADIATION SURVEYS. i 1-6SD-01 i
POWER TESTING -
DETERMINATION OF ,
PROPER RESPONSE OF PROCESS AND EFFLUENT i RADIATION MONITORS.
4 1-600-04
CHEMICAL AND i RADIOCHEMISTRY TEST a AND DEMONSTRATE DESIGN CAPABLITY OF CHEMICAL CONTROL SYSTEM TO MAINTAIN WATER QUALITY IN THE REACTOR COOLANT AND
' SECONDARY COOLANT SYST
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Page No. 42 12:06165 TABLE 3.3-1 IMPLEMENTING DOCUMENTS FOR PLANT
========================================-we
OPERATIONS AND SUPPORT e=====e===============
APPROVED DOCUMENT DRAFT NUMBEH COMMITMENT COMMITMENT DOCUMENT / FEATURE REMARKS / SUBSECTION DOCUMENT NUMBER REV DATE SECTION SOURCE SECTION =========-e,====,=================== ========
==== ==========e===== ==========e========= ==============
e==-===
RG 1.68, R/2 APP.A.4.1. EOW 1-5SF-02 O 04/15/85 808.40 FSAR 1. 9. 68 POWER TESTING -
DEMONSTRATION OF THE OPERABILITY OF CONTROL ROD WITHDRAWAL AND INSERTION SEQUENCES AND CONTROL ROD WITHDRAWAL INHIBIT OR BLOCK FUNCTIONS.
1a600-14 808.41 FSAR 1. 9. 69 RG 1.68, R/2 APP.A.4.J. LOW POWER TESTING -
DEMONSTRATION OF THE CAPABILITY OF PRIMARY CONTAINMENT VENTILATION SYSTEM APP.A.4.k. LOW 1-600-13 808.42 FSAR I. 9. 68 RG _.68. R/2 POWER TEST'NG -
DEMONSTRATION OF THE OPERABILITY OF STEAM-DRIVEN ESF AND STEAM-DRIVEN PLANT AUX. AND POWER CONVERSION EQUIPMENT.
RG 1.68, R/2 APP.A.4.o. LOW 1-5SF-04 0 11/15/84 1-7SF-01 808.43 FSAR 1. 9, 68 POWER TESTING -
CONTROL ROD SCRAM TIME TESTING AT RATED TEMPERATURE.
POWER TESTING -
DEMONSTRATION OF THE OPERABILITY OF RHRS, INCLUDING ATMOSPHERIC STEAM DUMP VALVES AND TURBINE BYPASS VALVES.
9 O O O O O e
^ -
Page No. 43 12/06/85 TABLE 3.3-1 IMPLEMENTING DOCUMENTS FOR PLANT
--===========================================
OPERATIONS AND SUPPORT
==========
APPROVED DOCUMENT DRAFT COMMITMENT COMMITMFNT DOCUMENT / FEATURE REMARKS / SUBSECTION DOCUMENT NUMBER NUMBER REV DATE SECTION SOURCE SECTION ==================================== ========
======= ========== ==========e===== ==================== ==================== 1 i
LOW 1-600-10 FSAR 9, 68 RG 1.68, R/2 APP.A.4.t.
808.45 1.
POWER TESTING -
PERFORMANCE AND NATURAL CIRCULATION TESTS.
1-600-06 FSAR 1. 9. 68 RG 1.68. R/2 APP.A.4.u. LOW 1-6AE-01 808.46 POWER TESTING -
DEMONSTRATION OF THE 1-6SF-01 OPERABILITY OF MAJOR OR PRINCIPAL PLANT CONTROL SYSTEMS.
1-600-13 808.47 FSAR 1. 9. 68 RG 1.68, R/2 APP.A.S. POWER ASCENSION TEST- THE PREDICTED RESPONSES SHOULD BE DEVELOPED USING REAL OR EXPECTED 7ALUES AND i NOT THOSE ASSUMED FOR CONSERVATIVE EVALUATIONS OF
' POSTULATED ACCIDENTS 1-600-13
ASCENSION TESTS-EVALUATE AND APPROVE THE LOW POWER TEST RESULTS PRIOR TO BEGINNING POWER a
ASCENSION TEST.
1-600-13
ASCENSION TEST -
TEST SHOULD ESTABLISH THAT MEASURED RESPONSES ARE IN ACCORDANCE WITH PREDICTED RESPONSES t
1 n
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Page No. 44 12/06/85 IMPLEMENTING DOCUMENTS FOR PLANT TABLE 3.3-1
=== .===....,====================
OPERATIONS AND SUPPORT w...======= ..========
APPROVED DOCUMENT DRAFT COMMITMENT COMMITMENT DOCUMENT / FEATURE REMARKS / SUBSECTION SECTION DOCUMENT NUMBER NUMBER REV DATE SOURCE SECTION ======.......=====...==.........== ========
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1-600-13
TESTING SHOULD BE SUFFICIENTLY COMPREHENSIVE TO ESTABLISH THAT THE FACILITY CAN OPERATE IN ALL OPERATING MODES FOR WHICH THE FACILITY HAS BEEN DESIGNED TO OPERATE.
APP.A.S.a. POWER 1-600-13
ASCENSION TEST -
DETERMINE THAT POWER REACTIVITY COEFFICIENTS ARE IN ACCORDANCE WITH DESIGN VALUES (25%,
50%, 75%, 100%)
APP.A.S.b. 1-600-06 FSAE 1. 9. 68 RG 1.68, R/2 808.52 1-800-01 POWER-ASCENSION TEST- DETERMINE THAT STEADY-STATE CORE PERFORMANCE IS IN ACCORDANCE WITH DESIGN THROUGHOUT THE PERMISSIPLE RANGE OF POWER-TO-FLOW.
RG 1.68, R/2 APP.A.5.d. POWER 1-600-06 808.53 FSAR 1. 9. 68 ASCENSION TEST -
DEMONSTRATE THE CAPABILITIES OF PROCEDURES FOR CONTROLLING CORE XENON TRANSIENTS.
r
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I D 5 .
Page\n . 45 12/06/85 TABLE 3.?-1 IMPLEMENTING DOCUMENTS FOR PLANT
=================a===============
1 OPERATIONS AND SUPPORT
==========
APPROVED DOCUMENT D RAFT NUMBER COMMITMENT COMMITMENT DOCUMENT / FEATURE REMARKS / SUBSECTION NUMBER REV DATE SECTION DOCUMENT SOURCE SECTION ==================================== ========
= ========== ================ ==================== ==============
APP.A.S.e. POWER 1-6SF-04 808.54 FSAR 1. 9. 68 RG 1.68, R/2 ASCENSION TEST -
PSEUDO-ROD-EJECTION TEST.
APP.A.S.f. POWER 1-6SF-06 0 12/12/84 ALL 1-600-13 808.55 FSAR 1. 9. 68 RG 1,68 R/2 1-6SF-02 ASCENSION TEST -
DEMONSTRATE THE CORE THERMAL AND NUCLEAR PARAMETERS WITH A SINGLE NIGH NORTH ROD FULLY INSERTED AND DURING AND FOLLOWING RETURN OF THE ROD TO ITS BANK POSITION (50%)
RG 1.68, R/2 APP.A.S.g. POWER 1-5SF-02 0 04/15/85 ALL 808.56 FSAR 1. 9. 68 ASCENSION TEST-DEMONSTRATE THAT CONTROL ROD SEQUENCERS, CONTROL ROD WORTH MINIMIZERS ,
AND ROD WITHDRAWAL BLOCK FUNCTIONS OPERATE IN ACCORDANCE WITH DESIGN (25%)
68 RG 1.68. R/2 APP.A.S.h. POWER 1-SSF-03 0 12/12/84 ALL 808.57 FSAR 1. 9.
ASCENSION TEST -- 1-5SF-04 0 11/03/84 ALL DETERMINE THAT THE 1-SSB-01 O 03/05/85 ALL SCRAM TIMES REMAIN WITHIN ALLOWABLE LIMITS.
~
RG 1.68, R/2 APP.A.5.1. POWER 18003-1 _O 11/05/84 ALL 1-600-01 808.58 FSAR 1. 9. -38 ASCENSION TEST -
DEMONSTRATE CAPABILITY OF INCORE
' AND ERCORE NEUTRON FLUX INSTRUMENTATION, TO 2
DETECT A CONTROL ROD F MISALIGNMENT (50%,100%) .
, F 2
s r
_ ._ .. _ _m .
Page No. 46 12/06/85 TABLE 3. 3- 1 IMPLEMENTING DOCUMENTS FOR PLANT
.=== .======= .....==,...====......= ..==
OPERATIONS AND SUPPORT
......== .............
APPROVED DOCUMENT DRAFT COMMITMENT DOCUMENT / FEATURE REMARKS / SUBSECTION SECTION DOCUMENT NUMBER CCMMITMENT NUMBER REV DATE SECTION ........
SOURCE .................... .... =.....................==.......
....... == ....... ................ ....=.......=.......
1-600-13 800.59 FSAR 1. 9. 68 RG 1.68. R/2 APP.A.S.J. POWER ASCENSION TEST -
' VERIFY THAT PLANT PERFORMANCE IS AS EXPECTED FOR POD RUN BACK AND PARTIAL SCRAM POWER 1-600-13
- 9. 68 RG 1.68. P/2 APP.A.S.k.
808.60 FSAR 1.
ASCENSION TEST -
DEMONSTRATE THAT ECCS NIGN-PRESSURE COOLANT INJECTION SYSTEMS CAN START UNDER SIMULATED ACCIDENT CONDITIONS AND INJECT INTO THE PEACTOR COOLANT SYSTEM AS DESIGNED.
1-600-09 FSAR 1. 9. GB RG 1.68 R/2 APP.A.5.1. POWER 1-600-10 008.61 ASCENSION TEST -
I-600-13 DEMONSTRATE DESIGN CAPABILITY OF ALL SYSTEMS AND COMPONENTS PROVIDED TO REMOVE RESIDUAL HEAT FROM THE RCS (PRIOR TO EXCEEDING 25% POWER)
APP.A.S.m. POWER 1-600-13 FSAR 1. 9. 68 RG 1.68, R/2 808.62 ASCENSION TEST -
DEMONSTRATE THAT THE
- RCS OPERATES IN ACCORDANCE TO DESIGN.
ASCENSION TEST -
i ODTAIN BASELINE DATA FOR REACTOR COOLANT SYSTEM LOOSE PARTS MONITORING SYSTEM f
9 O O O O O O
Page No.
12/06/85 O 47 O_ _ - - - ' \ - o )
TABLE 3.3-1 IMPLEMENTING DOCUMENTS FOR PLANT
...=...=...==..........................=.....
OPERATIONS AND SUPPORT
.. ...=.........==....
APPROVED DOCUMENT DRAFT [
NUMBER COMMITMENT COMMITMENT DOCUMENTfFEATURE REMARKS / SUBSECTION DOCUMENT '
NUMBER REV DATE SECTION SOURCE SECTION .................................... ........ ;
APP.A.S.o. POWER 1-5BB-01 808.64 FSAR 1. 9. 68 RG 1.68. R/2 l ASCENSION TEST -
DEMONSTRATE THE PROPER RESPONSE OF REACTOR COOLANT LEAK DETECTION SYSTEM POWER I-6SD-OI
- 9. 68 RG 1.68. R/2 APP.A.S.q.
808.65 FSAR 1.
ASCENSION TEST - >
VERIFY THE PROPER OPERATION OF FAILED j
FUEL DETECTION SYSTEM. (25%.1004) 1-6RJ-01 808.66 FSAR 1. 9. 68 RG 1.68, R/2 APP.A.S.r. ' POWER ASCENSION TEST -
VERIFY CONTROL ROOM OR CCMPUTER IS i RECEIVING CORRECT INPUTS FROM PROCESS VARIABLES AND PERFORMANCE CALCULATIONS PERFORMED BY COMPUTER ARE CORRECT (25%,50%,754.100%;.
1-600-13 FSAR 9. 68 RG 1.68 R/2 APP.A.5.s. POWER 808.67 1 ASCENSION TEST -
VERIFY THE PERFORMANCE OF MAJOR OR PRINCIPAL PLANT CONTROL SYSTEM (25%,50%,75%.100%)
APP.A.S.t. POWER 1-600-13 808.68 FSAR 1. 9. 68 RG 1.68 R/2 ASCENSION TEST -
VERIFY OPERABILITY RESPONSE TIMES, RELIEVING CAPACITIES, SETPOINTS AND RESET PRESSURES FOR LISTED VALVES. (25%) i I (
I r
7
Page No. 48 12/06/85 IMPLEMENTING DOCUMENTS FOR PLANT TABLE 3.3-1
.-=======-===========================-=e=====
OPERATIONS AND SUPPORT
==================....
APPROVED DOCUMENT DRAFT COMMITMENT COMMITMENT DOCUMENT / FEATURE REMARKS / SUBSECTION SECTION DOCUMENT NUMBER NUMBER REV DATE SOURCE SECTION ....= ========..............====.......... == .....
==...==-,= =======.===....e =======..=========== .....--======u
=
1-600-13 FSAR 1. 9. 68 RG 1.68. R/2 APP.A.5.u. VERIFY 808.69 OPERABILITY AND RESPONSE TIMES OF MAIN STEAM LINE ISOLATION VALVES.
POWER 1-600-13
ASCENSION TEST - 1-800-01 VERIFY THAT THE MAIN STEAM SYSTEM AND FEEDWATER SYSTEM OPERATE IN ACCORDANCE WITH DESIGN PERFORMANCE REQUIREMENTS (25%.50%,75%,1004)
RG 1.68, R/2 APP.A.S.w. POWER 1-600-05 808.71 FSAR 1. 9. 68 1-600-13 ASCENSION TEST -
DEMONSTRATE ADEQUATE 1-600-14 BOL PERFORMANCE MARGINS FOR SHIELDING AND PENETRATION COOLING SYSTEM (100%)
APP.A.5,x. POWER 1-600-14 808.72 PSAR 1. 9. 68 RG 1.68. R/2 ASCENSION TEST -
DEMONSTRATE ADEQUATE BEGINNING-OF-LIFE PERFORMANCE MARGINS FOR AUX. SYSTEMS REQUIRED TO SUPPORT TNE OPERATION OF ESF OR TO MAINTAIN THE ESF ENVIRONMENT.
(50%,1004)
RG 1.68, R/2 APP.A.5.y. POWER 1-5SC-02 808.73 FSAR 1. 9. 68 ASCENSION TEST - 1-5SE-02 VERIFY THE FROPER 1-5SF-06 OPERATION OF 2-5SF-07
(
l IMPORTANT 4 INSTRUMENTATION l
SYSTEMS
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I l
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(25%,50%,75%,100%)
(
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. _ __ . _ .. - m. ... .._. . . . - . _ - . - - - m-. -s .- ._ mm_.- _ . - . . _ _ . . . . --- . m._ -- - ..
[)
- ~' -
lL:
3 s . . . -
Poww ov. 44 12/06/85 TABLE 3.3-1 IMPLEMENTING DOCUMENTS FOR PLANT
.........=..............=..................==
OPERATIONS AND SUPPORT APPROVED DOCUMENT DRAFT COMMITMENT DOCUMENT / FEATURE REMARKS / SUBSECTION DOCUMENT NUMBER COMMITMENT NUMBER REV DATE SECTION SOURCE SECTION .................................... . .....
==..... .......... ................ ..................== ....................
1-6SD-01
ASCENSION TEST -
DEMONSTRATE THAT PROCESS AND EFFLUENT RADIATION MONITORING SYSTEMS ARE RESPONDING CORRECTLY.
POWER 1-600-12 FSAR 9. 68 RG 1.68, R/2 APP.A.S.aa. 1 C00-13 808.75 1.
ASCENSION TEST -
DEMONSTRATE CHEM.
AND RADIOCHEMICAL CONTROL SYSTEM FUNCTION PER DESIGN AND SAffLE TO ESTABLISH REACTOR AND SECONDARY COOLANT LIMITS ARE NOT EXCEEDED (25%,50%,75%,10 1-600-05 808.76 FSAR 1. 9. 68 RG 1.68, R/2 APP.A.S.bb. POWER ASCENSION TEST-CONDUCT NEUTRON AND Gale 4A-RADIATION SURVEYS (50%,100%)
I-600-08 808.77 FSAR 1. 9. 68 RG 1.68 R/2 APP.A.S.dd. POWER 1-600-13 ASCENSION TEST - 28038-1 DEMONSTRATE THE CAPABILITY TO SHUTDOWN AND MAINTAIN THE REACTOR IN A HOT STANDBY CONDITION FROM OUTSIDE THE CONTROL
! ROOM.
F' P
f
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