ML20078A507
| ML20078A507 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 04/03/1986 |
| From: | Ramsey W GEORGIA POWER CO. |
| To: | |
| Shared Package | |
| ML20078A351 | List:
|
| References | |
| PROC-860403-01, NUDOCS 9406010271 | |
| Download: ML20078A507 (200) | |
Text
{{#Wiki_filter:- - - _ _ _ _ - _ - - . Georgia Pow 3r Company Vogtle Projec1 Readiness Review Post Office Box 282 Waynesboro, Georgia 30830 Telephone S.M 724 8114 464 554 9961 Vogtle Project April 3, 1986 Mr. D. O. Foster Vice President rN Vogtle Project Support Waynesboro, Ga. 30830 RE: Readiness Review Program Module 20 Instrumentation and Controls LOG: RR-808 FILE: I7BD102
Dear Mr. Foster:
Pursuant to your instructions I am enclosing Module 20 Of the Readiness Review Program, entitled Instrumentation and Controls. This module reports the work of the Readiness Review Team and has been prepared in order to present you with an accurate picture of the readiness for operations of the Vogtle Project, based upon a close examination of the instrumentation and controls. The Readiness Review process included an initial assessment and review of basic licensing documents in order to identify Project commitments within the scope of the module. The Readiness Review Team then verified implementation processes designed to () meet those commitments, including programs and controls relating to work within the scope of the module. The team then engaged in a process designed to verify that implementation programs were operating as described in procedures, policy statements, and other descriptive documents. () In concluding this verification process, the team then actually verified that the licensing commitments identified during the procens were being fulfilled and met. O 9406010271 940512 PDR ADOCK 05000424 ( p PDR \. .
Mr. D. O. Foster April 3, 1986 O Page 2 We are confident that the verification methodology used allowed the Readiness Review Team to properly appraise the actual O condition of the plant instrumentation and controls and provided a valid means of assessing the quality of the program, having also considered applicable past audits, inspection reports, and problems experienced by other utilities. O Based on the examinations, inspections, and evaluations of the review and the responses and corrective actions committed to by the Project, it is the conclusion of the Readiness Review Team that the design and construction programs that govern the instrumentation and controls have produced a final product that meets design requirements and licensing commitments. Additionally, none of the findings identified, either individually or collectively, are such that the adequacy of the project instrumentation and controls is called into question. Therefore, the instrumentation and controls meet the FSAR commitments. Members of the Readiness Review Team and I are prepared to discuss this module with you at your convenience. If we can O provide you with any further information or assistance regarding this matter, contact me. Very truly yours,
,.,i s i LY .{ f n [;L' '
William C. Ramsey 0 WCR/deg () cc: R. E. Conway Readiness Review Board Members Reading File Document Control O () 0045t/092-6
O-O O VOGTLE ELECTRIC GENERATING PLANT UNIT 1 READINESS REVIEW MODULE 20 - INSTRUMENTATION AND CONTROLS O O O -
READINESS REVIEW - MODULE 20 List of Effective Pages April 4, 1986 Page ReviseB Dat.e O All pages unchanged. O O O O O iii
PREFACE O 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 Program. The VEGP pilot Readiness Review Program is a systematic, O 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 called modules. There are approximately 20 modules. Each module is a predefined scope of VEGP activities. O Each module is intended to provide a brief description of the method of complying with project licensing commitments pertaining to the module scope and is not intended to make further commitments or to revise in any way prior commitments. If any differences exist between the commitments discussed in this document and the licensing documents, they are unintentional: and the licensing document 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 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 of Unit 2, since both units are being designed and constructed together under a single quality assurance program; with like management controls, procedures, etc.; and to the same specifications and criteria. Stone and Webster Engineering Corporation has been contracted to provide technical management for, and technical personnel to 0 implement, the independent design review as a part of the Readiness Review program. The VEGP Readiness Review Program is not intended to eliminate or to diminish any authorities or regulatory responsibilities now assigned to or exercised by the Nuclear. Regulatory O- Commission or GPC. Further, the Readiness Review Program is not intended to change the techniques of inspections or assurance of quality program activities. Rather, the VEGP Readiness Review Program is an added program initiated by GPC management to assess the VEGP and to provide additional feedback to management O so that they may initiate any needed corrective actions in an orderly and timely manner. v
The scope of work processes and regulatory commitment compliance covered by each module will be assessed by, and the module prepared and reviewed by, individuals collectively familiar with the design, construction, 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 g accordance with regulatory requirements. W l 1 l O O O O 0043t/092-6 vi
EXECUTIVE
SUMMARY
Introduction This module documents a review program to ascertain whether design activities and installation of Instrumentation and Controls comply with licensing commitments and whether () compliance is verifiable using existing project documentation. The scope of this module includes certain aspects of design and construction activities associated with safety-related instruments and associated instrument sensing lines for the Vogtle Electric Generating Plant. Section l.1 contains further () definition of the scope of this module. The program consisted of two separate reviews: a design program verification and a construction program verification. A technical evaluation of design activities will be included in the Independent Design Review (IDR), which will be submitted separately. In the design and construction reviews, project documents such as design criteria, specifications, data sheets, drawings, and procedures were reviewed along with the results of past audits, inspections, and recent industry problems. In addition, the Readiness Review Board's technical consultant (from Stone & Webster Engineering Corporation) provided independent technical oversight and concurrence, and Readiness Review quality assurance (QA) personnel provided QA surveillance O- of review activities. Statements from the technical consultant and QA regarding their involvement and conclusions are provided in section 8 of this module. 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 O engineering requirements with no safety concerns. Level III - Violation of project procedures with no safety concerns. A brief summary of the two reviews is provided below. (} Desion Procram Verification The design program verification consisted of a commitment implementation assessment and a design control assessment by a team of four engineers with a total of 53 years of design engineering experience. vii
The commitment implementation assessment was performed to determine whether design-related licensing commitments were included in design criteria and other appropriate design g W i documents; approximately 350 commitments were included in this review. Each commitment was confirmed as being included in l appropriate design documents. l l The design control assessment consisted of a review of design f documents such as calculations, drawings, specifications, and instrument data sheets to ascertain the effectiveness of control applied to the design activities. This evaluation resulted in six findings: one classified as Level I, one as Level II, and four as Level III. Two of the more significant findings are 20-11 and 20-14. Finding 20-11 (Level I) identified some instrument setpoint i discrepancies between two design documents, the level setting ) diagram and the instrument setpoint list. The Project has i committed to a consistency review of the setpoint list and the level setting diagrams. Identified discrepancies will be j corrected as required. I < l
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Finding 20-14 (Level III) noted the lack of a documented review i of logic diagrams by the Mechanical Group. Informal coordination did take place between the Controls Group and the Mechanical Group. However, it was not documented in accordance with project procedures. The Mechanical Group reviewed a representative sample of logic diagrams to assess the impact of the lack of formal coordination and found no discrepancies. Training has been conducted to ensure that procedures are followed in the future. The remaining four findings involved minor and/or isolated occurrences, constituting no safety concerns or impact on design. Details of the design program verification are provided in section 6.1. Construction Procram Verification The construction program verification consisted of a commitment implementation assessment and a construction assessment. The construction program verification was performed by a team composed of four members who have a combined total of 50 years of experience in construction activities. The commitment implementation assessment determined whether licensing commitments had been incorporated into the construction documents; the construction assessment determined whether instrumentation and controls installations met design requirements. . gg viii
Seven licensing commitments were identified as the responsibility of Construction for implementation. The O~ Readiness Review Construction Team identified approved project documents used by Construction that invoked, by reference or detailed directions, the requirements of each commitment. During the construction assessment, 15 hardware items and () approximately 100 records were assessed for compliance with drawing and specification requirements. The construction assessment resulted in one finding (20-17, Level II), which identified storage deficiencies that were due to storage inspection not having been performed in an () instrumentation and controls materials storage area. This resulted from a failure to assign inspection responsibilities As a result of this finding, responsibilities for this area. for the inspection of these storage areas have been appropriately identified. Details of the construction program verification are found in section 6.2. Readiness Review Conclusion Based on the results of the reviews and implementation of O effective corrective actions as committed to by the Project, Readiness Review concludes that adequate programs exist to ensure the quality of work, the documentation of that quality, and the implementation of licensing commitments within the scope of this module. ( ( O C:) 0047t/094-6 iX
i TABLE OF CONTENTS 1.0 Introduction i 1.1 Scope 1.2 Module Organization () 1.3 Vogtle Project Status 2.0 Organization and Division of Responsibility i 2.1 Design Organization O 2.1.1 Home Office Engineering 2.1.2 Project Field Engineering 2.2 Field Construction Organization 2.2.1 GPC Instrumentation and Controls Project Section 2.2.2 GPC Electrical Quality Control 2.2.3 Cleveland Consolidated 2.2.4 Pullman Power Products 2.3 Training and Qualification Design Engineers - Bechtel O 2.3.1 2.3.2 2.3.3 Construction Engineers Inspectors 3.0 Commitments 3.1 Introduction 3.2 Definitions 3.3 Sources 3.4 Commitment Matrix 3.5 Implementation Matrix 4.0 Program Description 4.1 Design 4.1.1 Design Criteria 4.1.2 Drawings and Documentation O 4.1.3 4.1.4 Design Verification Design Change Control 4.1.5 Nonconformance Control 4.2 Equipment and Material 4.2.1 Supplier Quality Surveillance Program 4.2.2 Supplier Quality Verification Documentation 4.2.3 Supplier Deviations Xi
I I TABLE OF CONTENTS : 4.3 Site Material Control 4.4 Fabrication, Installation, Inspection, and Testing 4.4.1 Pullman Power Products 4.4.2 Cleveland Consolidated 4.4.3 Georgia Power Company i 5.0 Audits and Special Investigations 5.1 Design Program Audits 5.1.1 Georgia Power Company Audits 5.1.2 Bechtel Audits 5.1.3 Nuclear Regulatory Commission Inspections 5.1.4 Self-Initiated Evaluations 5.2 Construction Audits 5.2.1 Project Audits 5.2.2 Nuclear Regulatory Commission Inspections 5.3 Past Design and Construction Problems 5.3.1 Design Problems h 5.3.2 Construction Problems 6.0 Program Verification 6.1 Design Program Verification 6.1.1 Evaluation Summary 6.1.2 Verification Scope and Plan 6.1.3 Verification Review and Results 6.1.4 Design Program Verification Findings 6.2 Construction f 6.2.1 Summary Evaluation 6.2.2 Commitment Implementation 6.2.3 Construction Assessment 7.0 Independent Design Review O G l ! xii
4 1 1 1 TABLE OF CONTENTS l O 8.0 Program Assessment / Conclusions 8.1 Summary of Open Corrective Actions Section 6.1 Engineering O 8.1.1 8.1.2 Section 6.2 Construction 8.2 Quality Assurance Statement 8.3 Technical Consultant's Certification 8.4 Readiness Review Board Acceptance () 8.5 8.6 Project Assessment Resumes 1 l 1 1 O O O 0072t/094-6 xiii
l.0 INTRODUCTION (v 1.1 SCOPE Module 20 contains a discussion and evaluation of certain aspects of the design and construction of safety-related instrumentation and controls (ISC). (% )) The design activities of Bechtel Power Corporation (BPC) and the construction activities of Georgia Power Company (GPC), Cleveland Consolidated, and Pullman Power Products (PPP) for I&C
,_s items such as instrument tubing and supports, and hydro /
pneumatic instruments are covered in this module. (c)* I&C will be addressed in several modules as indicated in Table 1.1-1. The combined modules will cover design and construction activities of control and process I&C for the reactor coolant system, steam systems, and containment and auxiliary systems. Figure 1.1-1 provides a general illustration of I&C hardware with applicable module references. The effective date of this module is January 1, 1986. Changes in the included programs, organizations, and commitments occurring after this date are not addressed. 10
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i l n/ C C) 0003t/094-6
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TABLE 1.1-1 KEY HARDWARE AND ASSOCIATED WORK ACTIVITIES FOR MODULES CONTAINING INSTRUMENTATION AND CONTROLS ASPECTS Module 4 - Mechanical Equipment and Pipinc ASME Section III components: o Valves (manual). o Pumps. o Heat exchangers. o Piping. o Etc. Module 6 - Electrical Equipment Electrical control panels Module 8 - Structural Steel o Pipe whip restraints (design only). o Project welding program. Module 11 - Pipe Stress and Supports p) ( o o Pipe supports. Stress analysis, o Piping system final design verification program. o Pipe whip restraints (construction). Module 12 - Electrical Cables and Terminations o Cable pulling. o Cable termination. Module 16 - Nuclear Steam Supply System o Primary loop components. o Primary loop and other Class 1 stress analysis 7 s) t performed by Westinghouse. o Westinghouse /Bechtel interfaces. Module 18A - Heatino. Ventilation. and Air C miitioninc
> // // II // // // //
LEGEND TUSING @ I ELEC. CABLE --- < PROCESS PIPING INSTRUMENT HE ATING, VENTILATION, ROOT VALVE N AND AIRCONDITIONING CONTROL PANEL i - J ! Figure 1.1-1 General Illustration of;Instrumentationland Controls 1 2 _ . _ _ . _ _ _ _ _ _ _ _ . _ _ __ _ _ _ . _ _ _ _ _ _ _ _ _ _ _____ _ _____.__________..____________.___1.._____...u._ _ . _ _ _ _ _ . . _ _ _ _ _ _ _ . _ _ . _ _
! 1.2 MODULE ORGANIZATION o (_) This module is divided into the following sections:
- 1. Introduction.
- 2. Organization and Division of Responsibility - A brief description of the project organizations and their
(~T) (. division of responsibilities as applicable to this module.
- 3. Commitments - Project licensing commitments pertaining to instrumentation and controls within the scope of this module and as found in the Final Safety Analysis f'
s Report, Generic Letters, and other documents. This section also lists documents that demonstrate implementation of these commitments.
- 4. Program Description - A brief description of the processes for design and construction applicable to the scope of this module.
- 5. Audits - A description of the level of audit activity by Quality Assurance (QA) or the Nuclear Regulatory Commission as it applies to this module. Also included in this section is a description of any special investigations performed on work contained in this
(~)s module and past problems identified. l 6. Program Verification - A description of the verification plan development, implementation, and results, including corrective actions.
- 7. Independent Design Review - Provided as a separate report.
- 8. Assessment - Evaluations of and conclusions on the subject work by the VEGP Readiness Review Board module expert, Readiness Review Program QA staff, Readiness I Review Board, Design Engineering management, and Construction management. In addition, this section
! (7s) contains a listing of finding items (section 6 of this module) still open and requiring project resolution. Resumes of Readiness Review Team members involved in the development of this module are also provided. l C) - 1 l 0060t/092-6
1 1 1.3 VOGTLE PROJECT STATUS
- The first instrumentation and control installation activities began in March 1984. As of January 1, 1986, the approximate project status for Unit 1 and common systems within the scope of this module is as follows:
Perc.ent Complete l Design 96 () Construction Instrument installation 85 Tubing installation 36 l l l l I (I_/) l l l I l O O O 0004t/093-6
r l 2.0 ORGANIZATION AND DIVISION OF RESPONSIBILITY () Georgia Power Company (GPC), acting on its own behalf and as agent for the Oglethorpe Power Corporation, the Municipal Electric Authority of Georgia, and the City of Dalton, is responsible for the design, procurement, and construction of the Vogtle Electric Generating Plant. The Western Power Division of gS Bechtel Power Corporation (Bechtel) is contracted by GPC to (,,) provide architect / engineering (A/E) services. , This section includes a brief description of the organization and responsibilities of GPC, Bechtel Power Corporation, Cleveland Consolidated, and Pullman Power Products, as related to the scope of this module, l i l I ( l (S) 1 l C) 0005t/084-6
2.1 DESIGN ORGANIZATION Design, specification, and installation guidelines for safety-related (Q-Class) instrumentation and controls (I&C) are the responsibility of Bechtel Power Corporation (BPC). BPC responsibility for design of I&C is divided between Home Office Engineering (HOE) and Project Field Engineering (PFE). BPC is j O, responsible for the design and specification of Q-Class I&C in j all plant areas except for the I&C furnished by Westinghouse, the supplier of the nuclear steam supply system (NSSS). Vogtle-Structural Analysis Mobile Unit (V-SAMU) is responsible for the design of Seismic Category I instrument sensing lines required for Q-Class instruments. (~ ! l 2.1.1 HOME OFFICE ENGINEERING , 1 HOE (Figure 2.1-1) is located in Norwalk, California, and is responsible for the majority of the Q-Class I&C design. The design of Q-Class I&C within HOE is the principal responsibility of the Control Systems Group, with support provided by the Equipment Qualification Group and the Miscellaneous Category I Group of the Civil / Structural Discipline. The former is responsible for ensuring the seismic and environmental qualification of all safety-related equipment and I&C; the latter is responsible for the structural design requirements for I&C installation. The Control Systems Group is divided into three subgroups under the direction of the control systems engineering group supervisor (EGS). These subgroups are Physical Design, Specifications, and NSSS. Each subgroup is responsible for various aspects of I&C design, as listed in Figure 2.1-2. 2.1.2 PROJECT FIELD ENGINEERING PFE (Figure 2.1-3) is located at the Plant Vogtle jobsite and is an extension of HOE. PFE assists construction in interpreting drawings, solving field problems, and coordinating field \- activities with HOE. Certain portions of I&C design have been transferred to PFE from HOE, including the diagrammatic routing of instrument air and branch headers, the maintenance of instrument location drawings (ILDs), the reactor vessel level indicating system, and the review and approval of () field-generated I&C drawings and stress calculations prepared by the V-SAMU. O 0037t/084-6
O O O O PROJECT E NGINE E R HOME OFFICE ' l 1 ASSISTANT AS$1ST AN T ASSISTANT ASSISTANT PROJECT ENGINEER PROJECT (- 'INEER PROJECT ENGINEER PROJECT ENGINEER SYSTEMS SYSTEks DESIGN PLANNING / CONTROL (ACTING)
- NUCLEAR / HAZARDS
- E LECTRICAL
- CIVIL / STRUCTURAL ADMINISTR ATION
- ME CH ANIC AL
- CONTROL SYSTEMS
- PL ANT DESIGN / PIPE ENGINEERING PL ANNING
- NSSS COORDIN A TION
- EQUIPMENT OUALIFICATION STRESS AND SUPPORTS OUALITY ENGINEERING
- AUDITS COORDIN ATION
- SCS ENG. COORDIN ATION
- A RCHITECTUR AL ST ARTUP COORDIN ATION
- LICENSINGIASLB SUPPORT e PROJECT FIELD ENG. PCW PROGR AM COORDIN AT RON t
- EDUCATION GROUPS (ENGINEERING DISCIPLtMEsl
- PROJECT TASMS GROUPS Figure 2.1-1 Bechtel Vogtle Home Office (Functional) Engineering Organization
O c o o ' 1 , EGS NSSS SPECIFICATIONS PHYSICAL DESIGN ENGINEERING E NGINE E RING ENGINEERING GROUP LE ADER GROUP LE ADER GROUP LE ADER EMERGENCY RESPONSE FACILITY PLANT CONTROL PANELS FIE LD COORDIN ATION ! SAFE TY MONITORING SYSTEM, PROCESS LOOPS & LOGICS INSTRUMENT INDEX CONTROL AND EFFLUENT RADI ATION MONITORING VALVES & EQUIPMENT MASTER P&lD CONTROL SYSTEM (PERMSI INSTRUMENTS INSTALL ATION DETAll POST-ACCIDENT SAMPLING SYSTEM & PROTEUS MISC. P ARTS HAZARDS FIRE PROTECTION CEBUS COORDINATION SETTING DIAGR AMS FSAR/ TECH SPEC FIELD ENGINEERING SETPOINT LIST l ' TRENDS & BUDGET CHANGE ORDER INSTRUMENT LOCATION INSE RVICE INSPECTION,OA M ATT ERS FCR.NCR,DCR.ETC. 4 PROBLEM ALERTS P&lO SYSTEMS DC & PRM
- CONTROL ROOM MODIFICATION
' PflelD SYSTEMS NSSS INTE RF ACE
, P&lD SYSTEMS
. ANNUNCIATOR SYSTEM ! CHANGE CONTROL PACK AGE COORDINATION i PROGR AM FOR COMPLETOON OF WORK COORDINATION i Figure 2.1-2 BPC Vogtle HOE Control Systems Group 1 , I
O O O 1
'O O O O e
i CONTROL SYSTEMS j ENGINEERING GROUP L i SUPERVISOR i 4 4 I V-SAMU l 4 8 4 MECHANICAL GROUP ELECTRICAL GROUP SUPPORT GROUP
- ENGINEERING ENGINEERING ENGINEERING -
GROUP LEADER GROUP LEADER GROUP LEADER i i b ! 1 i j i i d N i i t i
., Figure 2.1-3 BPC Vogtle PFE Control Systems Group ,
2.2 FIELD CONSTRUCTION ORGANIZATION Georgia Power Company (GPC) Nuclear Construction has responsibility for construction of Plant Vogtle. For direct work, Nuclear Construction employs Pullman Power Products (PPP) and Cleveland Consolidated for installation of instrumentation and controls (l&C) within the scope of this module. This () section contains descriptions of duties and responsibilities of the portions of the site construction organizations directly involved in I&C installation. 2.2.1 GPC INSTRUMENTATION AND CONTROLS PROJECT SECTION i The GPC I&C Discipline provides coordination and support for contractors installing I&C. This includes the following general responsibilities: o Providing material for the contractors by initiating purchase orders or releases as required. o Initiating and revising construction procedures as I needed to support construction activities. I o Providing schedule and budget information to various site organizations. o Interfacing with field coordination and contractors j regarding problem identification and resolution. l 2.2.2 GPC ELECTRICAL QUALITY CONTROL The Quality Control (OC) Department implements the GPC field QC program to verify quality compliance of field construction activities. The Electrical QC (EOC) Section verifies that the construction activities and installations performed by Cleveland Consolidated comply with the Vogtle Quality Assurance (QA) ! program. EQC Section personnel assist in developing forms, l checklists, and other quality verification documents necessary O to control activities and to demonstrate compliance with specified requirements. Inspection is in accordance with established QC procedures as required by the Vogtle QA program. This includes inspection of the work as it is being performed by contractor craftsmen and the completion of documentation to {} verify the results. 2.2.3 CLEVELAND CONSOLIDATED Cleveland Consolidated is the electrical contractor performing O quality-related work on the Vogtle Project. It is responsible for supplying all craft and supervisory personnel for the
1 electrical activities within the I&C scope of work, as well as for providing document control and technical assistance for its ( craft. 2.2.4 PULLMAN POWER PRODUCTS PPP is the installer (NA-certificate holder) for American Society of Mechanical Engineers (ASME), section III, division 1, I&C items. It is responsible for the field installation of all nuclear and nonnuclear instrument tubing and associated fittings, instrument piping and tubing, supporting brackets, and trays. Additionally, PPP performs the specified nondestructive examinations and performs and documents inspections to verify quality compliance for the I&C items it installs. O O 416 ; i 0010t/093-6 2.2-2
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1 l 2.3 TRAINING AND OUALIFICATION l Os This section contains a description of the project programs for l training and qualification of design engineers, Georgia Power ' j Company (GPC) construction engineers and inspectors, and i
- contractors' engineers, inspectors, and craft.
2.3.1 DESIGN ENGINEERS - BECHTEL ; i Bechtel engineering personnel assigned to the Home Office Engineering (HOE) organization and the Project Field Engineering (PFE) organization receive training to familiarize them with ,() project procedures governing their assigned responsibilities. Section 6, part A. of the Project Reference Manual (PRM) establishes the program structure and requirements for indoctrination and training of Bechtel Power Corporation (BPC) , personnel assigned to the Vogtle Project. It defines i procedures, responsibilities, documentation, and records maintenance for the BPC project training program. Participation in the program is mandatory for home office and jobsite personnel assigned to the project. The overall program includes training in the following subject areas: ^O(/ o Quality program. o Engineering indoctrination program. o PRM. o Technical and specialized training. o New arrival orientation. o Quality Concern Program. The project engineering manager or his designees are responsible O for the formulation and implementation of the training program. The control systems engineering group supervisor (EGS) is responsible for ensuring that assigned personnel attend mandatory training classes, receive training in the requirements and use of the PRM, and learn the unique technical aspects of their work. The EGS identifies the training requirements for km each individual in the Control Systems Group commensurate with assigned tasks: he also maintains training records in accordance with the PRM, section 6. The project administrator receives and stores personnel training records for persons no longer assigned to the project. .
2.3 2 CONSTRUCTION ENGINEERS This section describes training and qualification requirements for construction engineering personnel performing activities within the scope of this module. 2.3.2.1 Georcia Power Company h GPC construction engineers and other personnel who perform work related to the activities of this module report to the project section supervisor. Candidates for construction engineering positions are either degreed angineers or have construction experience. Normally, the new engineer is assigned pertinent procedures to read and works with an experienced engineer who llh provides instruction on specifications, procedures, and use of design drawings. The experienced engineer also familiarizes the new engineer with plant orientation and site organization. The project section supervisor is responsible for ensuring that personnel are capable of performing the tasks assigned to them. The supervisor trains personnel on changes and revisions to specifications and procedures and provides formalized training, as necessary, to maintain or upgrade job skills. l 2.3.2.2 Pullman Power Products l Pullman Power Products (PPP) personnel who perform activities affecting quality are indoctrinated and trained by their immediate supervisor, or others, as directed by the resident construction manager (RCM) with concurrence of the quality assurance (QA) manager (QAM). This training encompasses a thorough review of the procedures applicable to the assigned area of activity, followed by on-the-job training. Each supervisor evaluates the individuals assigned to him. Records of training and attendance are maintained by the QA Department. The responsibility for indoctrination and training of field engineers is delegated by the RCM to the chief field engineer. g Field engineers are trained in the requirements of document W' control: preparation and processing of Deviation Reports (DRs), Field Change Requests (FCR), Field Process Sheets, and Code Data Reports for American Society of Mechanical Engineers (ASME) activities; and performance and documentation of pressure tests and installation activities appropriate to their assigned areas of activity. gg 2.2.2.3 Cleveland Consolidated Cleveland Consolidated construction engineers are assigned to the GPC Electrical Project Section and are trained and qualified l l in accordance with the GPC program described above. I 2.3-2
2.3.3 INSPECTORS This section describes training requirements for construction quality contrcl (QC) inspection personnel performing activities contained within the scope of this module. () 2.3.3.1 Georgia Power Company Ouality Control GPC QC inspectors [except nondestructive examination (NDE) personnel] are qualified and certified to procedures that are in compliance with American National Standards Institute (ANSI) N45.2.6(1978) and Nuclear Regulatory Commission (NRC) Regulatory
'[)
Guide 1.58 (September 1980). The inspectors are trained in accordance with written procedures and are recertified by academic testing at intervals not exceeding 3 years. In addition, any inspector not performing an inspection activity for which he is certified for a period of 1 year requires recertification. The training and certification program for QC inspectors is developed and administered on site by the GPC Training Department. For a more detailed discussion of GPC QC inspector training, qualification, and certification, including NDE personnel, see Appendix F. Tables 2.3-1 and 2.3-2 outline the training requirements for GPC QC personnel involved with instrumentation and control (I&C) inspection. 1 l(}./ 2.3.3.2 Pullman Power Products Ouality Assurance /Ouality Control Personnel The selection, training, qualification, and certification of PPP QA/QC personnel are the responsibility of the QAM who is assisted by the training officer. Inspection and testing personnel are qualified and certified in accordance with procedures that have been prepared in accordance with ANSI N45.2.6 (1978) and NRC Regulatory Guide 1.58. Nondestructive examination (NDE) personnel are certified in accordance with procedures that have been prepared in accordance with American Society for Nondestructive Testing (ASNT) recommended practice
's_/ SNT- TC- 1 A (1975) and ASME Boiler and Pressure Vessel (B&PV)
Code, sections III and V. I For a more detailed discussion of PPP QA/QC training, qualification, and certification, see Appendix F. Tables 2.3-3 through 2.3-6 outline the training requirements for PPP QA/QC (~} N- personnel. C:) 0031t/092-6 2.3-3
i l l l TABLE 2.3-1 : i O GEORGIA POWER COMPANY TRAINING OUTLINE - INSTRUMENTATION AND CONTROL INSPECTION Certification in this activity qualifies the inspector to () perform in the following areas: o I&C installations, j o Weld inspection. () These courses are required to fulfill the academic requirements: Subject Class Hours Math I Self-study l Basic Blueprint Self-study l l l Inspection of Instrumentation (a) Mechanical I&C (25 hours) l Electrical'I&C (40 hours) lO _ l O
- a. Includes; o Installation.
o' Drawings, o Codes. o Instruments. o Supports. (- o Asscciated Piping and Tubing and Fitting / Equipment. Visual incpection certification is also required to qualify the inspector to perform the above inspection. ( 0034t/093-6/1 i [
l 4
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TABLE 2.3-2 l O. GEORGIA POWER COMPANY ! TRAINING OUTLINE - ELECTRICAL EQUIPMENT INSPECTION Certification in this activity qualifies the inspector to () perform in the following areas: o Equipment inspection. o Rigging and lifting equipment. () o Instrumentation. i l These courses are required to fulfill the academic requirements-l Subject Class Hours ) l l Math I Self-study _ l Basic Blueprint Self-study i Installation of Electrical Equipment (a) 40 hours , Instrumentation 40 hours , t f l l i I l a. Includes: i o Drawings. o Codes / standards / specifications / procedures. O o o o Grounding. Electrical instruments. Equipment. o Rigging and lifting. Inspectors required to inspect welds associated with electrical O equipment must hold a visual inspection certification and/or an American Welding Society (AWS) certification. 1 0034t/093-6/2
l I TABLE 2.3-3
. PULLMAN POWER PRODUCTS 6 TRAINING OUTLINE - RECEIVING INSPECTOR i
Self-Study i
.O Subiect and/or Class Hours (a) i QA Indoctrination 2 !
() QA Implementation A. Self-Study 20 B. Instructed Review 4 i Introduction to-ASME A. History , B. Breakdown of the 11 Sections ! C. Breakdown of the Subsections l D. Reference What Is Found ) in Each Section/ Subsection 1-1/2 Introduction to ANSI Reference to Applicable () Sections: 1.e., N45.2.2, B31.1 1 Introduction to Nuclear Power 1 Introduction to Arc Welding 2 Basic Metallurgy 3 ASME Section II A,C 4 Structural Steel Shapes and Sizes 1 4 Basic Piping Components 2 Measurement Tools 4 l () a. In addition, review of procedures pertinent to this area of certification, as well as applicable on-the-job training, is required. i l 0034t/093-6/3 l
.- , - , _ , _ . _ _ , . . _ - . . . . . . _ . . _ . _ . _ . . . , _ , . . , _ _ , . _ , , , _ , . . . . , . . _ , _ . , _ , . . , _ . , _ , . . . . ~ , . . . . . _ , . . , _ ,
TABLE 2.3-4 PULLMAN POWER PRODUCTS TRAINING OUTLINE - TOOL AND GAUGE INSPECTOR-Self-Study and/or (} Subiect Class Hours (a) QA Indoctrination 2 QA Implementation A. Self-Study 20 () B. Instructed Review 4 Introduction to ASME. I A. History and Why Started B. Breakdown of the 11 Sections C. Breakdown of the Subsections D. Reference What Materis.1 Is Found in Each Section/ Subsection 1-1/2 ; Introduction to ANSI Reference the Different Applicable Sections, as Applicable; i.e., N45.2.6, B31.1 1 Introduction to Nuclear Power 1 Introduction to Arc Welding 2 Dri.eing Interpretation 2 A. Site Building Location B. Isometric Interpretation Basic Metallurgy 3 Measurement Tools 4 Rotating Equipment 2 Post-Weld Heat Treatment 1 O
- a. In addition, review of procedures pertinent to this area of certification, as well as applicable on-the-job training, is required.
0034t/093-6/4
TABLE 2.3-5 (SHEET 1 OF 2) PULLMAN POWER PRODUCTS TRAINING OUTLINE - WELDING Subiect Class Hours (a) (3 '~# QA Orientation 4 QA Manual A. Workbook / Study Guide 4-1/2 B. Instructed Review 3-1/2 () f-s C. Exam 2 Introduction to Codes A. ASME 2
- 1. History
- 2. Breakdown of the 11 Sections
- 3. Breakdown of Subsections
- 4. Reference Material Found in Each Section/ Subsection
- 5. Section IX B. ANSI B31.1/American Water Works Association / National Fire Protection Association / Plumbing Code 2
/~ 1. History \~ 2. Applicable Sections
- 3. Reference Material Information Found in Each Section Introduction to Nuclear Power 1-1/2 Introduction to Arc Welding 3 Introduction to NDE 2 Basic Metallurgy 5 Drawing Interpretation 4 A. Building Locations B. Isometric Interpretation AWS Weld Symbols 2 rh k_) Weld Procedures and Uses/ 2 Weldor Qualification Log Measurement Tools / Inspection 5 Devices O -
0034t/093-6/5
TABLE 2.3-5 (SHEET 2 OF 2) Class Hours (a) Visual Weld Inspection 3 Weld Defects / Acceptance Criteria 3 l l 1 l 0 , I l 4 l O O O
- a. In addition, review of the procedures pertinent to this area of O certification, as well as. applicable on-the-job training, is required.
0034t/093-6/6
TABLE 2.3-6 sd PULLMAN POWER PRODUCTS TRAINING OUTLINE - LEAK TESTING INSPECTOR Self-Study and/or \ Subject Class Hours (a) Exam or Ouiz QA Indoctrination 2 No QA Implementation [,s' A. Self-Study 20 B. Instructed Review 4 Yes Introduction to ASME A. History B. Breakdown of the 11 Sections 1 C. Breakdown of the Subsections l D. Reference What Is Found I in Each Section/ Subsection 1-1/2 No l l Introduction to ANSI Reference Applicable 1 Sections; i.e., N45.2.6, B31.1 1 No I /s i k) Introduction to Nuclear Power 1 No Introduction to Arc Welding 2 Yes Drawing Interpretation A. Site Building Locations 2 Yes B. Isometric Interpretation Basic Metallurgy 3 Yes O O ("} (>
- a. In addition, review of the procedures pertinent to this area of certification, as well as on-the-job training, is required.
0034t/093-6/7
- - .~
J l l 3.0 COMMITMENTS
3.1 INTRODUCTION
This section contains, in matrix form, project commitments that affect activities described in this module and their () corresponding implementing documents. two matrixes, the commitment matrix and the implementation These are presented in matrix. A brief explanation of the development process for each matrix is also included. Additionally, the Project has a commitment to comply with O 10 CFR 50, Appendix B. Quality Assurance Criteria, and other commitments such as American National Standards Institute (ANSI) l N45.2 and N45.2.11. Although they may not be identified as specific commitments in this module, Readiness Review considered the applicable requirements of these types of commitments in i preparing and assessing the scope of work represented by'this 1 module. Any differences between the commitments discussed in this section and the VEGP Final Safety Analysis Report, if any, are l accidental, and the FSAR prevails. i l l I l i O ,C:) 0006t/092-6
3.2 DEFINITIONS O A commitment is defined as an obligation to comply with regulatory guides, industry standards, Branch Technical Positions, or owner plan of specific action. f3 An implementing document is that working-level document that (') identifies project commitments as they apply to the specific work activity. [vD A G 1 l i
/
0007t/092-6 l
l 3.3 SOURCES l Commitments covered by this report are identified from the following sources: o Final Safety Analysis Report, including responses to Nuclear Regulatory Commission questions. o Responses to Generic Letters. o Responses to Inspection and Enforcement (IE) bulletins. 4 I l l These sources are reviewed for commitments based upon guidelines developed from the definition. l Implementation of commitments stated in the commitment matrix is typically contained in: l 1 o Design criteria. l l o Equipment / material specifications. l o Construction specifications, i l o Construction procedures. j 1 l lO l l l l 'O 10 O l 0009t/092-6 l
l i j 3.4 COMMITMENT MATRIX l O Once identified by the Readiness Review Team, the commitments i are placed on the commitment matrix. Information identifying I the source, source section, and subject is also indicated on the ; matrix. Any relevant comments concerning the commitments or ! subject of the section are indicated in the remarks column. l O The commitments identified in this module are accurate as of January 1, 1986, and reflect Amendment 20 to the Final Safety Analysis Report. (:) ! j
)
O 1 O O O 0011t/092-6
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e u s e LO r b t n I C e m a o e B t u e p n I t n f s i S e e l N N N L n t . r O OG n e I PI c io a n t T SS S i t lp o a C EE D r s i i E RD L e e t r S E n u r e a p D I e q e h z o S F G t t i r T N r t n p N A F o e r a p E O R L o g a O E A r M C T R N S r e c n o e I U
/ O F i o h M O T E I
( b r i e t M N R T m e t h O S E U A t u n c t o C MT N n n e e t Y U A A e G s r B CE L m r o s O F P t o r R f d D D X i t o A n E E t S g o T R m o l e n o F i n p s O - i e d e S , t h a r e n c t e r h o e h o . t i s n c T N g t c i e R h t n e EC T E T i n s F A S d e s t r h t a I J i R s e NB P U t a A S h e u c d n r e O S n F t s u b C o i m c e f d d u t h o e n t t c n t n a e o O e s c c m e e m lp n u i j u e c f b c s r T o i u o i e N d t s d f n ENO T I h e d e h e h e X n e r T T I T T A A lmC t E - - - - - - 0S C N T O E R C U O O I T C E C E J B U E R U T Y T S S S A E I 4 6 T T T T F IL 5 N N N N / B 0 EE E E E T I .
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COMMITMRNT COMMITMENT COMMITMENT DOCUMENT / R E SI-ONS IBILITT REMARES REF NO SOURCE SECTION SUBJECT FEATURE DESIGN CONST
=e======== ====-==============e ==================== ======e==========-========== ======= ======= ==================== ========
FSAR 1. 2. 6 SAFETT FEATURES 10CFR100 X 673 i FSAR 1. 9. 11 INSTRUMENT LINES R0 1.11, 3/71. REV. 0 X SEE F8AR 6.2.4 121 PENETRATING ( CONTAINMENT FSAR 1. 9. 12 INSTRUMENT LINES FOR RG 1.12 X 678 EARTHOUAEES FSAR 1. 9. 22 PERIODIC TESTING OF RO 1.22 REV. 0 (FEB. 72) I SEE FSAR 7.1.2.6 1602 PROTECTION SF5 TEM EXCEPT AS INDICATED IN FSAR ACTUATION FUNCTIONS SECTION 1.9.22.2 AND 7.1.2.5 FSAR 1. 9. 29 SEISMIC DESIGN RG 1.29 REY. 3. 9/78 I REF. TABLE 3.2.2-1 126 CLASSIFICATION FSAR 1. 9. 30 Q.A. REQUIREMENTS RG 1.30 8/72 I I REF. 687 AND 688 686 FOR INSTALL., INSP.,
& TESTING OF INSTRUMENTATION &
ELECTRIC EQUIPMENT 1 FSAR 1. 9. 30 0.A. REQUIREMENTS ANSI N45.2.4-1972 X X REF. F8AR 3.2.2.4 687 I FOR INSTALL., INSP., LIMITED TO PIPING.
& TESTING OF TUBING. ETC FOR INSTRUMENTATION & CONSTRUCTION ELECTRIC EGUIPMENT IMPLEMENTATION.
DESIGN BASES SUBSTITUTE ASME III J l FOR ANSI B31.7 FSAR 1. 9. 30 0.A. REQUIREMENTS IEEE 336-1971 I I LIMITED TO 688 FOR INSTALL., INSP., ELECTRICAL DEVICES,
& TESTING OF CIRCUITS. ETC. FOR INSTRUMENTATION & CONSTRUCTION ELECTRIC EQUIPMENT IMPLEMENTATION FSAR 1. 9. 32 CRITERIA FOR IEEE 308-1974 I 132 SAFETT-RELATED ELECTRIC POWER ST5TEMS FOR NUCLEAR POWER PLANTS i
1 4 1
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RESPOM5 IBILITY REMARES REF NO COMMITMENT COMMITMENT COMMITMENT DOCUMENT / SECTION SUBJECT FEATURE DESIGN CONST SOURCE , so================== ========
=-== =========-========== ==================== ============================ ======= =
N0 1.32 REV. 2, 2/77 X SEE REO. GUIDE 1.6, 131 FSAR 1. 9. 32 CRITERIA FOR 1.9, 1.75, 1.81 AND SAFETY-RELATED ELECTRIC POWER 1.93. BER F8AR 8.1 SYSTEMS FOR NUCLEAR ; AND 8.3 POWER PLANTS RG 1.47 5/73 X SEE F8AR 7.5.5 & 1923 FSAR 1. 9. 47 BYPASSED AND INOPERABLE STATUS 10.4.9.5 FOR INDICATOR FOR CONFORMANCE NUCLEAR POWER PLANTS SAF' 'Y SYSTEMS IEEE 279-1971, BBCT. 4.13 X SEE FSAR 7.5.5 & 1924 FSAR 1. 9. 47 BYPASSED AND INOPERABLE STATUS 10.4.9.5 FOR INDICATOR FOR CONFORMANCE NUCLEAR POWER PLANT 5 SAFETY SYSTEMS 47 BYPASSED & 10CFR50 APP. B. CRITERIA X 8EE F5AR 7.5.5 & 1925 FSAR 1. 9. INOPERABLE STATUS XIV 10.4.9.5 FOR INDICATOR FOR CONFORMANCE NUCLEAR POWER PLANT 5 SAFETY SYSTEMS
- 1. 9. 53 APPLICATION OF RG 1.53. REY. 0, 6/73 X REF. 7.1.2.6 & 1551 FSAR SINGLE-FAILURE 15.0.8 CRITERION
- 1. 53 APPLICATION OF IEEE 379-1972 X REF. 7.1.2.6 & 1552 FSAR 9.
SINGLE-FAILURE 15.0.8 CRITERION FSAR 1. 9. 53 APPLICATION OF IEEE 279-1971. BBCT. 4.2 X REF. 7.1.2.6 & 1553 SINGLE-FAILURE 15.0.8 CRITERION FSAR 1. 9. 62 MANUAL ACTUATION OF RG 1.62, 10/73 X SEE FBAR 7.3.1.2.2.7 155 PROTECTIVE ACTIONS FOR DESCRIPTION O O O O O O O
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COMMITMENT COMMITHENT COMMITMENT DOCUMENT / RESPONS IBILITY REMARES REF NO SOURCE SECTION SUBJECT FEATURE DESIGN CONST
========e= =========, ========= =======e============ =======*======e============= ======= ======= ==================== ========
FSAR 1. 9. 62 MANUAL ACTUATION OF IEEE 279-1971 SECT. 4.17 E SEE F8AR 7.3.1.2.2.7 156 PROTECTIVE ACTIONS FOR CONFORMANCE F5AR 1. 9. 73 QUAL. TESTS OF IEEE 382-1972 i I REF. 158 BLECT. VALVE 3.9.B.3.2.2.8UBBBCTI OPERATORS INSTALLED ON 3.11.B.2 AND WCAP IN5IDE CONTAINMENT - 8587. SEE R.G. 1.40, 1.89 & l.100 FOR INFO. FSAR 1. 9. 75 PHYSICAL RO 1.75 REY. 2 9/78 I X SEE SECTION 7.1.2.2 180 INDEPENDENCE OF ELECTRIC SYSTEMS FSAR 1. 9. 84 DESIGN AND FAB. CODE RG 1.84 REY. 20 11/82 I REF. TABLE 1.9-1 1585 CASE ACCEPT. ASME PARA. 5.2.1.2. TABLE III. DIV. I 1.9-3 FSAR 1. 9. 85 MATERIAL CODE CASE RO 1.85. REV. 20 11/82 I REF. TABLE 1.9-2 1589 ACCEPT. ASME III. 1.9-3 PARA. 6.2.1.2 DIV. I FSAR 1. 9. 89 QUALIFICATION FOR RO 1.89 REY. O. 11/74 I BER F8AR 3.11.B. 172 CLASS IE EQUIPMENT FSAR 1. 9. 89. 1 QUALIFICATION FOR IEEE 323-1974 X WCAP-8587 IMPLEMENTS 173 CLASS IE EQUIPMENT IEEE 323-1974 FOR N888 EQUIPMENT. SEE 3.11.5 TSAR 1. 9. 92 COMBININ. MODAL RG 1.92 REY. 1. 2/76 I SEE SECTION 174 RESPONSES AND 3.7.3.2.7. 3.7.B.3.6 SPATIAL COMPONENTS & 3.7.8.3.9. IN SEISMIC RESPONSE ANALYSIS bbnR 1. 9. 95 PROTECTION OF NPP RO 1.95 RIV. 1 1/77 I 8EE 8.4.4.2 2.2.3 2020 CONTROL ROOM 8.4.2 OPERATORS AGAINST AN ACCIDENTAL CHLORINE RELEASE
Pace No. 4 04/03/86 COMMITMENTS
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RESPONS IBILITY REMARKS REF NO COMMITMENT COMMITMENT COMMITMENT DOCUMENT / SOURCE SECTION SUBJECT FEATURE DESIGN CONST e-ree===== = =====e===========e ==================== =e================e========= ======= ======= ==================== ======== INSTRUMENTATION FOR RG 1.97, REV. 2, 12/80 K SEE FSAR 7.5 178 FSAR 1. 9. 97 LIGHT-WATER-COOLED NUCLEAR PONER PLANT 8 TO ASSESS PLANT 4 CONDITIONS DURING AND FOLLOWING AN ACCIDENT. RG 1.100 REV. 1, 8/77 I SEE FSAR 3.10.B.2 175 FSAR 1. 9.100 SEISMIC QUALIFICATION OF CLASS IE ELECTRIC EQUIPMENT CONTAINMENT RG 1.141 REY. O, 4/78 X REF. 6.2.4 1595 FSAR 1. 9.141 ISOLATION PROVISIONS FOR FLUID SYSTEMS CONTAINMENT ANSI N271-1976 X REF. 6.1.4 1596 FSAR 1. 9.141 ISOLATION PROVISIONS FOR FLUID SYSTEMS
- 1. 9.141. 1 CONTAINMENT 10CFR50, APP. A. I REF. 6.2.4 1897 FSAR ISOLATION PROVISIONS FOR FLUID STSTEMS FSAR 3. 1. 1 CONFORMANCE WITH 10CFR50 APP. A, GDC 4 Y 4115 NUCLEAR REGULATORY COMMISSION GENERAL DESIGN CRITERIA.
OVERALL REQUIREMENTS. FSAR 3. 1. 1 CONFORMANCE WITH 10CFR50, APP. A, ODC 5 X 4116 NUCLEAR REGULATORY COMMISSION GENERAL DESIGN CRITERIA, OVERALL REQUIREMENTS FSAR 3. 1. 2 CONFORMANCE WITH NRC 10 CFR50, APP. A. GDC 13 I 792 GDC, PROTECTION BY MULTIPLE FUSION PRODUCT BARRIERS O O O O O O O
O Pare No. 5 O O O O O O 04/03/R6 COMMITMENTS
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COMMITMENT COMMITMENT COMMITMENT DOCUMENT / RESPONS IBILITY RBMARK5 RRF NO SOURCE SECTION SUBJECT FRATURE . DESIGN CONST
========== ==================== ==================== =======h==========c,======== ======= ======= ==================== ========
FSAR 3. 1. 2 PROTECTION BY 10CFR50, APP. A. GDC 19 I 4120 MILTIPLE FISSION PRODUCT BARRIERS 4 FSAR 3. 1. 3 CONFORMANCR WITH NRC 10CFR50, APP. A, GDC 20 X 796 GDC, PROTECTION AND REACTIVITY CONTROL SYSTEM FSAR 3. 1. 3 CONFORMANCE WITN NRC 10CFR50, APP. A. GDC 21 X 799 GDC, PROTECTION AND REACTIVITY CONTROL SYSTEMS FSAR 3. 1. 3 CONFORMANCE WITH NRC IRER 279-1971 X SEE GDC 20&21 IN 800 GDC, PROTECTION AND FSAR 3.1.3 REACTIVITY CONTROL SYSTEMS FSAR 3. 1. 3 CONFORMANCE WITN NRC IBRE 379-1972 I SEE GDC20421 IN FSAR 801 GDC, PROTECTION AND 3.1.3 REACTIVITY CONTROL SYSTEMS = FSAR 3. 1. 3 CONFORMANCR WITN NRC RG 1.22 I SEE GDC21 IN FSAR 802 ' - GDC, PROTECTION AND 3.1.3 REACTIVITY CONTROL SYSTEMS { i FSAR 3. 1. 3 CONFORMANCE WITH NRC RG 1.47 I SEE GDC21 IN F8AR 803 GDC, PROTECTION AND 3.1.3 REACTIVITY CONTROL SYSTEMS FSAR 3. 1. 3 CONFORMANCE WITH NRC 10CFR50 APP. A. GDC 22, X 804 GDC, PROTECTION AND REACTIVITY CONTROL SYSTEMS 4 i
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RESPONS IBILITT REMARES REF NO COMMITMENT COMMITMENT COMMITMENT DOCUMENT / SOURCE SECTION SUBJECT FEATURE DE8IGN CONST
=====e==
--,======= ==e===,============= ==================== ============================ ======= ======= ==================== APP. A. GDC 23 1 805 FSAR 3. 1. 3 CONFORMANCE NITR NRC 10CFR50 ODC. PROTECTION AND REACTIVITY CONTROL SYSTEMS ; APP. A. ODC 24 I B06 FSAR 3. 1. 3 CONFORMANCE WITR NRC 10CFR50 ODC PROTECTION AND REACTIVITY CONTROL SYSTEMS CONFORMANCE WITR NRC 10CFR50 APP. A. GDC 29 I 807 FSAR 3. 1. 3 ODC PROTECTION AND REACTIVITT CONTROL SYSTEMS
- 1. 3 PROTECTION AND 10CFR50 APP. A. ODC 25 I 4131 FSAR 3.
REACTIVITY CONTROL SYSTEMS
- 1. 5 CONFORMANCE WITH NRC 10CFR50 APP. A. GDC 56 X 2027 FSAR 3.
ODC. PRIMART CONTAINMENT ISOLATION FSAR 3. 1. 5 REACTOR CONTAINMENT 10CFR50 APP. A. GDC 55 1 4135 FSAR 3. 1. 6 CONFORMANCE WITH NRC 10CFR50 APP. A. GDC 63 I 819 ODC. FUEL & REACTIVITY CONTROL FSAR 3. 1. 6 FUEL AND REACTIVITT 10CFR50 APP. A. GDC 64 X 4138 CONTROL FSAR 3. 2. 2-1 CLAS8IFICATION OF NOTE (e): I&C WHICR CAN I TABLE 3.2.2-1 830 STRUCTURES. EFFECT THE COMPONENTS AND OPERATION / ACTUATION OF A SYSTEMS BAFETY-RELATED FUNCTION MUST BE QUALIFIED TO REQUIREMENTS OF PROJECT CLASS llJ. O O O O O O O
)
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COMMITMENT 5
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============e.. ======================
COMMITMENT COMMITMENT COMMITMENT DOCUMENT / RESPONS IBILITT REMARE5 REF MO SOURCE SECTION SUBJECT FEATURE DESIGN CONST we======== =======e============ =========3m========= =======-z3 ================= ======= seme=== =s=======.3sm======= nemeness FSAR 3. 2. 2-1 CLASSIFICA* ION OF NOTE (d): YEGP SAFETY CLA55 I TABLE 3.2.2-1 834 STRUCTURES. RG 1.26 COMPONENTS. SY8TEMS ( FSAR 3. 2. 2-1 CLASSIFICATION OF NOTE (c): QUALITY GROUP RG X TABLE 3.2.2-1 837 STRUCTURES. 1.26 COMPONENTS. SYSTEM 5 FSAR 3. 2. 2-1 CLASSIFICATION OF NOTE (1): MAIN CONTROL X TABLE 3.2.2-1 840 87RUCTURE5 BOARD IEEE 344 323 OUALIFIED BY COMPONENT 3 SYSTEMS NESTINGROUSE FSAR 3. 2. 2-1 CLAS5IFICATION OF NOTE (p): PAMS INSTRUMENT 5 I TABLE 3.2.2-1 842 STRUCTURES. PROJECT CLAS5. BASED ON COMPONENTS. SYSTEMS THEIR CATEGORY BY RG 1.97 REV. 2 FSAR 3. 2. 2-1 CLASSIFICATION OF NOTE (e): SEISMIC CATEGORY X TABLE 3.2.2-1 843 STRUCTURES. RG-1.29 COMPONENTS. 5757EM5 FSAR 3. 2. 2-1 PRINCIPAL CODES AND NEMA MGl 1972 (NATIONAL I 865 STANDARDS FOR ELECTRICAL MFRS. ASSOC.) T.3.2.2-1 YALVE OPERATOR 5 FSAR 3. 2. 2-1 PRINCIPAL CODES AND ASME III-3 X 5036 4 STANDARDS FOR TABLE 3.2.2-1 ORIFICES FSAR 3. 2. 2-1 PRINCIPAL CODES AND A5ME III-2 X 5037 STANDARBS FOR T3.2.2-1 PRES 5URE , 5AFETY YALVES FSAR 3. 2. 2-2 CONST. CODE 5/5fDS. A5ME III, SUB5ECTION ND. I TABLE 3.2.2-1, 00 - 889 0.G.-C FOR PRE 55URE CLA55 3 C SUB5ECTION NF FOR YESSEL5 PIPING. BUPPORTS I PUMPS. TALVES, ATM. STORAGE TANES, j 0-15pelE STORAGE a TANE5 SUPPORTS. 1 1
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========= ==================== ======e=========e=== ============================ ======= ======= ==================== ========
A5ME III, CLASS 2&3 X X 5034 FSAR 3. 2. 2. 4 FLUID CONTAINING INSTRUMENTATION COMPONENTS CONFORM TO PROCESS EQUIPMENT ; PROJECT CLASSIFICATION RG 1.61 X CONSISTENT W/R0 1.61 981 FSAR 3. 7.B. 1. 3 SEISMIC DAMPING VALUES DAMPING YALUE5 HIGHER TRAN THOSE LISTED IN T3.7.B.1-1 ALLOWED IF JUSTIFIED. ASME CODE, SECT. III. 1977 E I ADDED BY FSAR AMEND. 5026 FSAR 3. 9. B. 1. 5 WELD INSP. ACCEPT. CRITERIA ED THRU WINTER 1977 ADENDUM 20 WELD INSP. ACCEPT. ANSI B31.1 %0DE. 1977 X X ADDED BY FSAR AMEND. 3027 FSAR 3. 9. B. 1. 5 CRITERIA EDITION THRU WINTER 1977 20 ADENDA
- 1. 5 MELD INSP. ACCEPT. AWS DI.1-1976 I I REF. FSAR PARA 5028 FSAR 3. 9. B.
CRITERIA 1.9.94 FOR CLARIFICATION ADDED BY FSAR AMEND. 20 FSAR 3.10.B. 3 SEISMIC CATEGORY I ASME III I 1223 INSTRUMENT TUBING SYSTEM SUPPORTS FSAR 3.10.B. 3 SEISMIC CAT. I RG 1.48 I 1851 INSTRUMENTATION TUBING SY5 TEM SUPPORTS FSAR 5. 2. 5. I DESIGN BASIB THE AIRBORNE RADIOACTIVITY X 2339 MONITORING SYSTEM IS QUALIFIED FOR SSR l _ -_ __m_ .__ _ _ _ _ _ _ _ _
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COMMITMENT COMMITMENT COMMITMENT DOCUMENT / RESPONS IBILITT REMARES REF NO SOURCE SECTION SUBJECT FEATURE DESIGN CONST
==e======= ==================== ==e==============e== ============================ ======= ======= ==================== ========
FSAR 5. 2. 5. 3 UNIDENTIFIED LEAKAGE THE SENSITIVITY AND RESPONSE I 2340 DETECTION TIME OF THE DETECTION EQUIPMENT FOR UNIDENTIFIED LEAKAGE 15 5UCRlTHAT A LEARAGE RATE, OR ITS EQUITALENT, OF 1 GAL./ MIN. CAN BE DETECTED IN APPROXIMATELY I NOUR. FSAR 5. 2. 5. 4 SAFETY EVALUATION R0 1.45 X RADIO PARTICULATE 2162 AND RADIOGAS MONITOR 5 QUALIFIED FOR 55E FSAR 5. 4. 13. 2 PRESSURIZER SAFETT & NUREG-0737 TMI ACTION ITEMS X POSITIVE POSITION 311 RELIEF VALVE 5 II.D.3 INDICATION FSAR 6. O ENGINEERED SAFETT 10CFR100 X LIMIT 5 0F RADIATION 321 FEATURE 5 BIP05URE LEVELS FSAR 6. 1. 1. 1 E5F MATERIALS ASME III. NC-2160 & NC-3120 I FOR C55, CIS, RLTRS, 322 SELECTION & 515 & AFWS FABRICATION 3 F5AR 6. 1. 1. 1.1 SPEC 5. FOR ALL ASME III, DIY l X 323 PRESS.-RET. MATERIAL IN E5F SYSTEM < FSAR 6. 1. 1. 1.1 MATERIAL SPEC 5 FOR ASME III NC-2000, CLASS X 324 ESF COMPONENTS IN QUALITY GROUP B i FSAR 6. 1. *. 1.1 MATERIAL SPEC 5. FOR AEME III, MD-2000 CLASS 3 X 325 . E5F COMP. IN QUALITY , GROUP C FSAR 6. 1. 1. 1.1 E5F MATERIALS ASME III, NC-2000 & NE-2000 I 327 ! CONTAINMENT PENETRATION MATERIALS 1 i.
- - - - . - - - - . - - - - - - - ~ . _ - _ , - - , - - - - . - - _ - - . - - - - - - ---------.-.---._-----.__---a.--- - _ - - - _ _ _ - - - - - - - . - - - . . - - - - - - - _ - - - _ - - - - _ - - - - - _ _ _ - _ _ _ _ _ _ - - - - _ - _ - - - --__-____--.------_---__-------__---_----.---_-------.----_-__a- _ - - - - -
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COMMITMENT COMMITMENT COMMITMENT DOCUMENT / RESPONS IBILITT REMARES REF NO SOURCE SECTION SUBJECT FEATURE DESIGN CONST
-e ===e=== ==== =====e=e-ee-== ========== ========= ====e======================= ======= ======= ==================== ========
FSAR 6. 1. 1. 1.2 ESF CONSTRUCTION ASME II. PART C. SFA I 328 MATERIALS- WELD 5.1.5.2.5.5.5.17.5.18 & 5.20 MAT'L FOR JOINING FERRITIC BASE MAT'I.S ( FSAR 6. 1. 1. 1.2 ESF CONST. ASME II. PART C. SFA 5.11 & X 329 MAT'LS-WELD 5.14 MATERIALS FOR JOINING N1-CR-FE ALLOTS FSAR 6. 1. 1. 1.2 ESF CONST. MAT'LS ASME II. PART C, SFA 5.4 & I 330 FOR JOINING 5.9 AUSTENITIC 5.5 FSAR 6. 1. 1. 1.2 ESF CONST. ASME III & IX X X 331 MAT'LS-WELD MATERIAL QUALIFICATION FSTR 6. 1. 1. 1.2 ESF CONST. MAT'LS ASME II X 332 AUSTENITIC S.S. UTILIZED IN FINAL REAT TREATED COND. FSAR 6. 1. 1. 1.2 ESF CONST. MAT'L - LIMITED TO NO GREATER TRAM X 333 COLD WOREED AUST. 90.000 poi TIELD STRENGTR 8.8. FSAR 6. 1. 1. 1.2 ESF CONST. MATERIALS ASME IX X QUALIFICATION 2170 WELD MATERIAL QUAL. (S.8) FSAR 6. 1. 1. 1.3 ESF MAT'LS INTEGRITT RG 1.31 X 256 OF SAFETT-RELATED COMPONENTS FSAR 6. 1. 1. 1.3 ISF MAT'LS-INTEGRITT RG 1.37 I 258 0F SAFETT-RELATED COMPONENTS O O O O O O O
Page No. 11 04/03/86 COMMITMENTS
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FSAR 6. 1. 1. 1.3 ESF MAT'LS-INTRORITY R0 1.44 X 259 0F SAFETT-RELATED COMPONENTS i 4 FSAR 6. 1. 1. 1.3 INTEGRITY OF E8F RG 1.36 I 334 SAFETY-RELATED COMPONENTS-NONMETALL IC TRERMAL INSULATION FSAR 6. 2. 2. 1 CONTAINMENT COOLING RG 1.29 I 2398 SYSTEM SAFETY DESIGN BASES FSAR 6. 2. 2. 2 CSS SYSTEM IEEE 779 I 2405 INSTRUMENT APPLICATIONS FSAR 6. 2. 2. 2.1.1 CSS BAFETY DESIGN CSS AUTOMATICALLY PLACED IN I 2403 BASES OPERATION ON RECEIPT OF TWO OUT OF FOUR CONTAINMENT
. PRESSURE (RIGE-3) SIGNAL 5 1
FSAR 6. 2. 2. 2.5 CSS SYSTEM IEEE 279 I 2406 INSTRUMENT ! . APPLICATIONS FSAR 6. 2. 4 CONTAINMENT TMI ACTION PLAN TASE I 2409 4 180LAYION ST8 TEM II.E.4.2 l DESIGN FSAR 6. 2. 4. 1 CIS SAFETY DE5IGN DESIONED TO SEISMIC CAT. I I 2407 BA818 I FSAR 6. 2. 4. 1 CIS SAFETY DESIGN A8ME III. CLA58 2 X 2408 BASIS f FSAR 6. 2, 4. 1 CIS BAFETT DESIGN 10CFR50 APP. A. GDC 54 X 2410 BASES l 1
Page No. 12 04/03/86 COMMITMENTS
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RESPONS IBILITY REMARKS RET NC COMMITMENT COdMITMENT COMMITMENT DOCUMENT / SECTION SUBJECT FEATURE DESIGN CONST i SOURCE ======= ==================== ========
========== ==================== =========e==e======= ============================ ===e===
APP. A. GDC 57 (FOR X 2412 FSAR 6. 2. 4. I CIS SAFETY DESIGN 10CFR50 BASES LINES NEITHER PART OF RCPB NOR CONNECTED DIRECTLY TO ATMOSPHERE OF CQNTAINMENT) 10CFR50 APP. A, GDC SS AND X ISOLATION TALVES ON 2413 FSAR 6. 2. 4. 1 CIS SAFETY DESIGN BASES 66 INSTR. LINES PENET. CONTAINMENT RG 1.141 X 2414 FSAR 6. 2. 4. 1 CIS SAFETY DESIGN BASES X AMEND. 13/14 4779 FSAR 6. 2. 4. I CIS - SAFETY DESIGN DESIGNED TO WITRSTAND BASER INSTRUMENT CONTAINMENT PRESSURE & TEMP. LINES COND. FOLLOWING LOCA CIS - SAFETY DESIGN DESIGNED TO WITESTAND I AMEND. 13/14 4780 FSAR 6. 2. 4. 1 BASES INSTRUMENT DYNAMIC EFFECTS LINES
- 4. CIS SAFETY DESIGN DESIGNED TO REMAIN I AMEND. 13/14 4781 FSAR 6. 2. 1 BASES INSTRUMENT FUNCTIONAL FOLLOWING SSE LINES FSAR 6. 2. 4. 1.1 CIS SAFETY DESIGN 10CFR50, APP. A. GDC 65 & $6 I 2411
. BASES-INSTRUMENT LINES FSAR 6. 2. 4. 2 SYSTEM GENERAL BTP CSB 6-4 X TABLE 9.4.6-4 2422 DESCRIPTION - CONT.
PURGE SYSTEM FSAR 6. 2. 4. 2 DESIGN BASIS FOR RG 1.141 K SEE FSAR SECTION 1.9 2488 CONTAINMENT FOR CONFORMANCE ISOLATION FSAR 6. 2. 4. 3.D CONTAINMENT 10CFR50 APP. A. GDC 64 I PIPING PENETRATING 2418 ISOLATION SYSTEM CONTAINMENT DESIGN EVALUATION O O O O O O O
04/03/86 COMMITMENTS
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COMMITMRNT COMMITMENT COMMITMENT DOCUMENT / RESPONS IBILITT REMARE8 REF NO SOURCP SRCTION SUBJECT FEATURE , DESIGN CONST
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FSAR 6. 2. 4. 3.E VALVE ARRANGEMENTR IOCFR50, APP. A. GDC 55 & 56 I PART OF RCPE, 2491 OF LINES PENETRATING CONNECT DIRECTLY TO CONTAIMMENT CONT. ATM. OR DO NOT t MEET REGT. FOR CLOSED STSTEM l (EICIPT INSTR. LINES) FSAR 6. 2. 4. 3.1 YALVE ARRANGEMENTS 10CFR50, APP. A. GDC ST I NEITRER PART OF RCPB 2492 0F LINEM PENETRATING NOR CONNECTING TO CONTAINMENT CONT. ATM. BUT SATI5 FIRS RECT. OF CLO8ED STETEM FSAR 6. 2. 4. 3.0 DESIGN EVALUATION 10CFR50, APP. A GDC 55&56 I 2420 FSAR 6. 2. 4. 3.0 CIS ST57EM DESIGN RG 1.11 I 2429 EVALUATION FSAR 6. 2. 4. 3.R CONTAINMENT THE CONTAINMENT ISOLATION I REFERENCE TO SECTION 2437 ISOLATION VALVE ST5 TEM IS DESIGNED IN 3.2 INFORMATION ACCORDANCE WITE SEISMIC CAT. I REQUIREMENTE FSAR 6. 2. 4. 4 TESTS AND 10CFR50 APP. J I 2432
. INSPECTIONS FSAR 6. 2. 4. 5 INSTRUMENTATION ALL POWER SUPPLIES AND I 2433 APPLICATION CONTROL FUNCTIONS NECESSART FOR CONTAINMENT 180LATION ARE CLASS IE FSAR 6. 2. 5-1 DESIGN DATA FOR R2 IEEE 279 I REFER TO FSAR TABLE 2453 RECOMBINER FSAR 6. 2. 5-1 DESIGN DATA FOR R2 IEEE 308 I REFER TO FSAR TABLE 2454 RECOMBINER FSAR 6. 2. 5-1 DESIGN DATA.FOR H2 IEEE 383 I REFER 70 FSAR TABLE. 2457 RECOMBINER
Pnce No. 14 04/03/83 COMMITMENTS
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====================================s RESPONS IBILITY REMARKS REF NO COMMITMENT COMMITMENT COMMITHRNT DOCUMENT /
SRCTION SURJECT FEATURE DESIGN CONST SOURCE
========== =r==-=e==========e== ==================e= ============================ ======= ======= ==================== ========
DESIGNED AS CLASS IE, X 2066 FSAR 6. 2. 5. 1 CONTAINMRNT H/2 MONITORING SYSTEM SEISMIC CATEGORY I X 2087 FSAR 6. 2. 5. I CONTAINMENT H/2 RG 1.7 CONTROL QF HONITORING SYSTEM COMBUSTIBLE GAS CONCENTRATIONS IN CONTAINMENT FOLLOWING A LOCA POST LOCA CAVITY H/2 10CFR50 APP. A, GDC 19 X 2068 FSAR 6. 2. 5. 1 PURGE SYSTEM I 2440 FSAR 6. 2. 5. 1 CONTAINMENT HYDROGEN UNITS ARE POWERED FROM MONITORING SYSTEM INDEPENDENT CLASS lE POWER SOURCES CONTAINMENT R2 TMI ACTION PLAN TASK II.F.1 X 1336 FSAR 6. 2. 5. 2 MONITORING SYSTEM CONTAINMENT BYD. RG 1.26, QUALITY GROUP B I 2073 FSAR 6. 2. 5. 2 MONITORING SYSTEM
- 5. 2 CONTAIMMENT HYD. MONITORS DESIGNED TO X 2074 FSAR 6. 2.
MONITORING SYSTEM FUNCTION FROM -2 TO 80poit
- 5. 2 POST LOCA CAYITY EACH FAN IS POWERED FROM AN I 2447 FSAR 6. 2.
PURGE SYSTEM INDEPENDENT CLASS lE POWER SUPPLY. FSAR 6. 2. 6 CONTAINMENT LEAEAGE 10CFR50 APP. A. GDC 62,63 & I 2458 TESTING 54 FSAR 6. 3. 2. 2.16 ECCS MOTOR OPERATED BTP IC3B-18 I SEE PARA. B.3.1.1.11 2817 VALVES CONTROL - AND TABLE 6.3.2-3 POWER LOCKOUT FSAR 6. 3. 2. 2.17 24* MANUAL VALVES ON RG 1.47 I 4801 SUCTION LINE FROM RMST O O O O O O O
..E. N O 04/03/86
,5 O O O O O O COMMITMENTS
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COMMITMENT COMMITMENT COMMITMENT DOCUMENT / RESPONS IBILITY REMARES REF NO SOURCE SECTION SUBJECT FEATURE DESIGN CONST
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FSAR 6. 5. 1. 5 E5F FILTER SYSTEM R0 1.52 X 2152 INSTRUMENTATION REQUIREMENTS l FSAR 7. 1 I&C IEEE 279-1971 I 4359 INTRO. FSAR 7. 1. 2. 1 IDENTIFICATION OF MIN. DNBR SHALL NOT BE LESS X 4478 BAFETY CRITERIA TRAM 1.30 A5 A RESULT OF ANY REACTOR TRIP BTSTEM ANTICIPATED TRANSIENT OR MALFUNCTION (CONDITION II EVENTS) FSAR 7. 1. 2. 1 E!JINEERED SAFETT THE RSFAS MUST HAVE I 4479 FEATURES ACTUATION PROVISIONS IN THE CONTROL SYSTEM- MANUAL ACT. ROOM FOR MANUALLY INITIATING REQUIREMENT 5 TNB FUNCTIONS OF THE ESF SYSTEMS FSAR 7. 1. 2. 1 INSTRUMENTATION AND VITAL AC THE INVERTER SHALL I 4480 CONTROL PONER SUPPLT HAVE THE CAPACITY AND BYSTEM - RTS REGULATION REOUIRED FOR THE AC.0UTPUT FOR PROPER OPERATION OF THE EQUIPMENT SUPPLIED
^
FSAR 7. 1. 2. 1 INSTRUMENTATION AND VITAL AC RESUNDANT LOADS X 4481 CONTROL PONER SUPPLY SHALL BE ASSIGNED TO 8YSTEM -RTS DIFFERENT DISTRIBUTION PANELS WRICR ARE SUPPLIED FROM DIFFERENT INVERTERS. FSAR 7. 1. 2. 1 INTERLOCES IEEE 279-1971. BBCT. 4.11 - I 4576 (PROTECTIVE SYSTEM) 4.13
- RTS FSAR 7. 1. 2. 1 INTERLOCE5 10CFR50 APP. A. GDC 20 I 4577 (PROTECTIVE SY8 TEM)
- RTS i
4 1
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RESPONS IBILITT REMARES REF NO COMMITMENT COMMITMENT COMMITMENT DOCUMENT / SOURCE SECTION SUBJECT FEATURE DESIGN CONST
- -======== =-======,=========== ==============2===== =======e==================== ======= ======= ==================== ========
4578 FSAR 7. 1. 2. 1 INTERLOCES 10CFR50, APP. A. GDC 21 I (PROTECTIVE SYSTEMS)
- RTS 10CFR50 i
APP. A. GDC 22 X 4579 FSAR 7. 1. 2. 1 INTERLOCES (PROTECTIVE SYSTEMS)
- RTS IEEE 279-1971. SECT. 4.11 - X 4580 FSAR 7. 1. 2. I DESIGN BASES BYPASSES - RTS 4.14 IEEE 384-1974 X 4581 FSAR 7. 1. 2. I DESIGN BASES EQUIPMENT PROTECTION - RTS RG 1.75 X 4582 FSAR 7. 1. 2. I DESIGN BASES EQUIPMENT PROTECTION - RTS DESIGN BASES IEEE 279-1971 I 4583 FSAR 7. 1. 2. 1 DIVERSITT - RTS INSTRUMENTATION & VITAL AC NO SINGLE FAILURE X 4803 FSAR 7. 1. 2. 1 CONTROL PONER SUPPLT SHALL CAUSE A LOSS OF PONER STTEM - RTS SUPPLY TO MORE TRAN ONE DISTRIBUTION PANEL
- 1. DESIGN BASES: IEEE 279-1971 I 4804 FSAR 7. 2. 1 EQUIPMENT PROTECTION
-RTS FSAR 7. 1. 2. 1. 9 BI-STABLE TRIP DO NOT REQ'JIRE PROCESS X 4585 SETPOINTS, REACTOR TRANSMITTERS TO OPERATE PROTECTION AND ESF WITRIN 54 0F THE RIGH AND SYSTEM - RTS LOW END OF TREIR CALIBRATED SPAN OR FANGE FSAR 7. 1. 2. 2 INDEPENDENCE OF 10CFR 50 APP. A. GDC 22 X 4487 REDUNDANT SAFETY-RELATED SYSTEMS REACTOR PROTECTION 2
9 9 9 9 9 e e
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.......................=.....==.......
1 COMMITMENT COMMITMENT COMMITMENT DOCUMENT / RESPONS ISILITT REMARES REF NO SOURCE SECTION SU5 JECT FEATURE DESIGN CON 8T FSAR
- 7. 1. 2. 2 GENERAL R0 1.75 I 4488 PRTSICAL 5RPARATION CRITERIA FSAR 7. 1. 2. 2 GENERAL IEEE 384-1974 I 4489 NSBS EQUIPMENT FSAR 7. 1. 2. 2 GENERAL: R0 1.75. POSITION C.4 I 4586 WESTINGHOUSE CLA88 IE PROTECTION SYSTEM FSAR 7. 1. 2. 2 GENERAL: IEEE 279-1971 X 4587 WESTIN0 ROUSE CLASS 15 PROTECTION SYSTEM FSAR 7. 1. 2. 2 GENERAL WCAP-8892-A. JUNE '77 I AS-BUILT TESTS. 4588 WESTIN0 ROUSE CLASS IE PROTECTION ST5 TEM FSAR 7. 1. 2. 2 GENERAL IEEE 384-1974. SECT. 5.7 1 4589 PRTSICAL SEPARATION CRITERIA WESTIN0NOUSE M888 FSAR 7. 1. 2. 2 I&C R1 1.62 I 4590
- SPECIFIC ST87EM8 MANUAL REACTOR TRIP FCN. MAN. B8F ACT.
FSAR 7. 1. 2. 2 INDEPENDENCE OF IEEE 279-1971. SECT. 4.6 I 4805 REDUNDANT SAFETT-RELATED BYSTEMS REACTOR PROTECTION 1 FSAR 7. 1. 2. 6 WESTIN0ROU35 IEEE 379-1972 I 4593 i PROTECTION SYSTEM AND BOP E8FA8 DESIGN I I i i l ,. . .--
Page No. 10 04/03/H6 COMMITMENTS
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COMMITMENT COMMITMENT COMMITMENT DOCUMENT / RESPONS IBILITT REMARKS REF NO SOURCE SECTION SUBJECT FEATURE DESIGN CONST
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FSAR 7. 1. 2. 6 NESTINOROUSE R0 1.53 X 4594 PROTECTION SYSTEM AND BOP ESFAS DESIGN FSAR 7. 1. 2. 6 NESTINOROUSE IEEE 279-1971 ECT. 4.2 X 4595 PROTECTION SYSTEM AND BOP E5FA8 DESIGN l FSAR 7. 2. 1. 1 REACTOR TRIP 5YSTEM AUTO-INITIATE 5 WHENEVER I 4490 FUNCTION PERFORMANCE NECESSARY TO PREVENT FUEL REQUIREMENTS DAMAGE FOR AN ANTICIPATED OPER. TRANSIENT (CONDITION l II) FSAR 7. 2. 1. I REACTOR TRIP BTSTEM AUTO INTIATES TO LIMIT CORE I 4491 FUNCTIONAL DAMAGE FOR INFREQUENT FAULTS PERFORMANCE (CONDITION III) REQUIREMENTS FSAR 7. 2. 1. 1 REACTOR TRIP SYSTEM AUTO INITIATES 80 THAT TRE I 4492 FUNCTIONAL ENERGY GEN. IN THE CORE IS PERFORMANCE COMPATIBLE WITE THE DESIGN REQUIREMENTS PROV. TO PROTECT THE RCPB FOR LIMITING FAULT COND. I (CONDITION IV) l
- 1. REACTOR TRIP SYSTEMS TMI ACTION ITEM II E 3.10 X 4493 f FSAR 7. 2. 1 REACTOR TRIP ON
( TURBINE TRIP ! FSAR 7. 2. 1. 1 REACTOR TRIP SYSTEMS IEEE 279-1971 X 4494 { REACTOR TRIP ON TURRINE TRIP FSAR 7. 2. 1. I REACTOR TRIP SYSTEM RG. 1.62 X 4495 MANUAL TRIP FSAR 7. 2. 1. I REACTOR TRIP BY8 TEM 10CFR50 APP.A. 0D0 2 X 4496 BRISMIC DESIGN O O O O O O O
..E. N D19 O O O O O O 04/03/86 ,
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FSAR 7. 2. 1. 2 REACTOR TRIP SYSTEM IEEE 279-1971, 8ECT. 3 X 4596 DESIGN BASES INFO. FSAR 7. 2. 1. 2 REACTOR TRIP SYSTEM IEEE 279-1971 4 I 4597 ABNORMAL EVENTS FSAR 7. 2. 2. 2 ANALYSES 10CFR50, APP. A, ODC 10 X 4598 REACTOR TRIP EVAL. OF DESIGN LIMITS FSAR 7. 2. 2. 2 ANALYSES 10CFR50 APP. A. GDC 20 X 4599 REACTOR TRIP , EVAL. OF DESIGN
; LIMITS l FSAR 7. 2. 2. 2 ANALYSES 10CFR50, APP. A, GDC 10 X 4600 REACTOR TRIP TRIP SETPOINT DISCUSSION FSAR 7. 2. 2. 2 ANALYSB8 10CFR50 APP. A, GDC 15 I 4601 REACTOR TRIP TRIP SETPOINT DISCUSSION 4 FSAR 7. 2. 2. 2 &N A LYSIIS 10CFR50 APP. A. GDC 20 X 4602 4
. REACTOR TRIP
- .' HIP SETPOINT DICCUSSION FSAR 7, 2. 2. 2 ANALYBE5 10CFR50, APP. 4, ODC 29 I g603 REACTOR TRIP TRIP SETPOINT DISCUSSION FSAR 7, 2. 2. 2 ANALYSES BTP IC5B 12 X 4604 REACTOR TRIP TRIP SETPOINT DISCUSSION 4
Page No. 20 04/03/86 COMMITMENTS
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=e===e==-= =~====e==-==--=====e =========-========e= =====================e====== ======= ======= ==================== ========
10CFR50 APP. A. GDC 21 X 4605 FSAR 7. 2. 2. 2 ANALYSES REACTOR TRIP TRIP SETPOINT DISCUSSION ; IEEE 279-1971 SECT. 4 X 4606 FSAR 7. 2. 2. 2 ANALYSES REACTOR TRIP EVAL. OF COMPLIANCE TO CODES & STANDARDS 10CFR50, ODC 21 X 4607 FSAR 7. 2. 2. 2 ANALYSES REACTOR TRIP SINGLE FAILURE CRITERION ANALYSES 10CFR50 GDC 22 X 4608 FSAR 7. 2. 2. 2 REACTOR TRIP SINGLE FAILURE CRITERION 2 ANALYSES 10CTR50, GDC 23 X 4609 FSAR 7. 2. 2. REACTOR TRIP SINGLE FAILURE t CRITERION
- 7. 2. 2 ANALYSES 10CFR50 APP. A. GDC 4 X 4611 FSAR 2.
REACTOR TRIP EQUIPMENT QUALIFICATION 7, 2. 2. 2 ANALYSES 10CFR50 APP. 4, GDC 21 I 4612 FSAR ! REACTOR TRIP INDEPENDENCE FSAR 7. 2. 2. 2 ANALYSES 10CFR50 APP. A, GDC 22 X 4613 ' REACTOR TRIP INDEPENDENCE FSAR 7. 2. 2. 2 ANALYSES 10CFR50, APP. A, GDC 24 X 4614 REACTOR TRIP CONTROL & PROTECTION SYSTEM INTERACTION O O O O O O O
P.E. 04/03/86 D 21 O O O O O O COMMITMENT 5
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COMMITMENT COMMITMENT COMMITMENT DOCUMENT / RESPONS IBILITY REMAREs REF NO SOURCE SRCTION SUBJECT FEATURE DESIGN CCNST 3 ======== ====e=============== ==================== ==e3====e============= ===== ======= ======= ==================== ======== FSAR 7. 2. 2. 2 ANALYSES IEEE 279-1971. SECT. 4.7 I 4615 REACTOR TRIP CONTROL & PROTECTION SYSTEM t INTERACTION FSAR 7. 2. 2. 2 ANALYSES IEEE 279-1971 I 4616 REACTOR TRIP l CAPABILITY FOR TESTING SOLID-STATE LOGIC TESTING FSAR . 7. 2. 2. 2 ANALTRES IEEE 338-1975 I 4817 REACTOR TRIP , CAPABILITT FOR 4 TESTING 50 LID-87 ATE LOGIC TESTING FSAR 7. 2. 2. 2 ANALYSES 10CFR50, APP. A. GDC 21 I 4618 REACTOR TRIP , CAPABILITT FOR TESTING SOLID-STATE LOGIC 4 TESTING i FSAR 7. 2. 2. 5 ANALYSES IEEE 338-1975 I 4619 ] REACTOR TRIP j TESTS AND INSPECTIONS t FSAR 7. 3. 1. 1 M858 ANALOG RG 1.11 I 4626 I INITIATING CIRCUITRY ! FSAR 7. 3. 1. 2 BOP SYSTEMS WCAP 8760 I 4635 INTERFACING ESF . SYSTEM i a 4 k 4
Page No. 22 04/03/06 COMMITMENTS
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COMMITMENT COMMITMENT COMMITMENT DOCUMENT / RESPONS IBILITY REMARKS REF NO S otIRCE SRCTION SUBJECT FEATURE DESIGN CONST
=--e=e= =e =~===ee== ========== ==================== ============================ ======= ======= ==================== ========
FSAR 7. 3. 1. 2 COMPLIANCE WITH IEEE 279-1971 X 4636 STANDARDS AND DESIGN CRITERIA FSAR 7. 3. 1. 2 ESFAS SINGLE FAILURE 10CFR50, APP. A. GDC 21 X 4637 CRITERIA FSAR 7. 3. 1. 2 ESFAS SINGLE FAILURE 10CFR50, APP. A. GDC 23 I 4638 CRITERIA FSAR 7. 3. 1. 2 ESFAS SINGL2 FAILURE IEEE 279-1971 I 4639 CRITERIA FSAR 7. 3. 1. 2 MANUAL RESETS AND IEEE 279-1971. SECT. 4.12 X 4640 BLOCKING FEATURES FSAR 7. 3. 1. 2 MANUAL INITIATION OF RG 1.62 X 4641 PROTECTIVE ACTIONS FSAR 7. 3. 1. 2 MANUAL INITIATION OF IEEE 279-1971, BBCT. 4.12 X 4642 PROTECTIVE ACTIONS FSAR 7. 3. 3. 1 CONTAINMENT COMB. NO SINGLE FAILURE PREVENTS X 4514 GA5 CONTROL SYSTEM. THE CONTAINMENT COMBUSTIBLE GA8 CONTROL SYSTEM FROM FUNCTIONING FSAR 7. 3. 3. 2.8 CONTAINMENT RG 1.7 I 4643 COMBU8TIBLE GA8 CONTROL SYSTEM FSAR 7. 3. 3. 2.C CONTAINMENT IEEE 279-1971 X 4644 COMBUSTIBLE GAS CONTROL SYSTEM FSAR 7. 3. 4. 2.B CONTAINMENT PURGE IEEE 279-1971 I BER 7.2.3.2C FOR 4520 ISOLATION 8YSTEM CONFORMANCE FSAR 7. 3. 7. 1 ATWS - DESIGN BASES NO SINGLE FAILURE SHALL I 4516 PREVENT THIS SYSTEM FROM OPERATING O O O O O O O
i
... M 01/03/66 D ,, O O O O O O .
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===e====== ==================== ==================== =======*==================== ======= ======= ==================== ========
FSAR 7. 3. 7. 1 AF5 AFS-TRE SYSTEM MU57 PROVIDE I 4523 DESIGN BASE 5 FULL AUXILIARY FREDWATER FLOW WITRIN 1 MINUTE. t FSAR 7. 3. 7. 2.A AF5 10CFR50, APP. A. GDC 13 1 SEE 3.1 FOR 4524 ANALYSIS OF CONFORMANCE COMPLIANCE FSAR 7. 3. 7. 2.A AF5 10CFR50 APP. A. GDC 19 I BER 3.1 FOR 4525 ANALYSIS OF CONFORMANCE COMPLIANCE FSAR 7, 3. 7. 2.A AF5 10CFR50 APP. A. GDC 34 X SEE 3.1 FOR 4526 ANALYSIS OF CONFORMANCE. COMPLIANCE FSAR 7. 3. 7. 2.B AF5 IEEE 279-1971 1 BER 7.2.2.3 AND 4527 ANALYSIS 7.3.2 FOR CONFORMANCE. FSAR 7. 3. B. 2.5 MAIN STEAM FERDNATER IEEE 279-1971 I BER 7.3.2 FOR 4528 5YSTEM ANALYSIS CONFORMANCE FSAR 7. 3. 9. 2.8 NSCW IEEE 279-1971 X 4529 ANALYSIS FSAR 7. 3. 10. 2 COMPONENT COOLING IJER 279-1971 I 4498 WATER SYSTEM FSAR 7. 4. 1. 2 SYtTEM REQUIRED FOR IEEE 279-1971. BBCT. 3 X 4645 5AFE SRUTDONN ATM05PRERIC STEAM RELIEF SYSTEM FSAR 7. 4. 1. 2 SYSTEM REQUIRED FOR 10CFR50 APP. A, GDC 13 X 4646 SAFE SEUTDOWN ANALYSIS FSAR 7. 4. 1. 2 SYSTEM REQUIRED FOR 10CFR50, APP. A. GDC 19 I 4647 i I SAFE BRUTDOWN ANALYSIS
l' age No. 24 04/03/BG COMMITMENTS
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=======rr= ===ee=============== =================e== ============================ ======= ======= ==================== ========
FSAR 7. 4. 1. 2 SYSTEM REQUIRED FOR 10CFR50 APP. A. GDC 34 X 4648 SAFE BRUTDOWN ANALYSIS FSAR 7. 4. 1. 2 SYSTEM REQUIRED FOR RC 1.29 X 4649 8AFE SHUTDOWN ANALYSIS FSAR 7. 4. 1. 2 SYSTEM REQUIRED FOR IEEE 279-1971 X 4650 SAFE SHUTDOWN ANALYSIS FSAR 7. 4. 1. 3 SYSTEM REQUIRED FOR IEEE 279-1971. SECT. 3 4651 SAFE SHUTDOWN CENTRIFUGAL CHARGING SYSTEM CONTROLS FSAR 7. 4. 1. 3 SYSTEM REQUIRED FOR 10CFR50 APP. A. GDC 13 X 4652 SAFE SHUTDOWN . CCSC ANALYSIS FSAR 7. 4. 1. 3 SYSTEMS REQUIRED FOR 10CFR50. APP. A. GDC 19 X 4653 SAFE SHUTDOWN. CCBC ANALYSIS FSAR 7. 4. 1. 3 SYSTEM REQUIRED FOR 10CFR50, APP. A. GDC 34 X 4654 SAFE SHUTDOWN CCSC ANALYSIS FSAR 7. 4. 1. 3 SYSTEM REQUIRED FOR RG 1.29 I 4655 8AFE BRUTDOWN CCSC ANALYSIS FSAR 7. 4. 1. 3 SYSTEM REQUIRED FOR IEEE 279-1971 X APPLICABLE TO MANUAL 4656 5AFE SHUTDOWN CONTROLd. CC8C ANALYSIS O O O O O O O
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=======e22 ==ee==ee========e==- =e==============-e== =====e=a==================== ======= ======= ==================== ======e=
FSAR 7. 4. 3. 1 SAFE 8RUTDOWN FROM SNUTDOWN PANELS & SAFETT X 4619 OUTSIDE CONTROL ROOM GRADE SWITCBE5 DESIGNED TO
- DESIGN BASES WITRSTAND SSE WITH NO LOSS OF ESSENTIAL FUNCTIONS FSAR 7. 4. 3. I SAFE SHUTDOWN FROM 10CFR50 APP. A. GDC 19 E 4657 OUTSIDE THE CONTROL ROOM DESIGN BASFS FSAR 7. 4. 3. I SAFE SHUTDOWN FROM IEEE 279-1971 I 4658 OUTSIDE THE CONTROL ROOM DESIGN BASES FSAR 7. 4. 3. 1 SAFE SHUTDOWN FROM 5HUTDONN PANELS ARE DESIGNED X 4660 OUTSIDE THE CONTROL TO ACRIEVE COLD 85UTDOWd POOM WHERE OFFBITE POWER IS I DESIGN BASES AVAILABLE AND WBERE OFFSITE
- POWER IS NOT AVAILABLE FOR 728.
! FSAR 7. 4. 3. I SAFE SRUTDOWN FROM SHUTDOWN PANELS DESIGNED TO X 4665 OUTSIDE CONTROL ROOM A COINCIDENT SINGLE FAILURE DESIGN BASES & SSE FSAR 7. 4. 3. 2.A SAFE SMUTDOWN FROM 10CFR50, APP. A, ODC 19 I 4661 OUT5IDE THE CONTROL ROOM ANALYSIS
, FSAR 7. 4. 3. 2.B SAFE SBUTDOWN FROM RG 1.29 I 4662 I
OUT8IDE THE CONTROL ROOM
- ANALYSI8 FSAR 7. 4. 3. 2.B SAFE SHUTDo*5 FROM RG 1.22 X 4806 00781DR int CONTROL ROON 4
ANALYSIS 4
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COMMITMRNT COMMITMENT COMMITMENT DOCUMENT / RESPONS IBILITY REMARKS REF NO SOURCE SECTION SUBJECT FEATURE DESIGN CONST
====e===== =-====e============= =e================== ============================ ======= ======= ==================== ========
FSAR 7. 4. 3. 2.C 5 ATE SRUTDOWN FROM IEEE 279-1971 X 4663 OUTSIDE THE CONTROL ROOM ANALYSIS q FSAR 7. 4. 3. 3 ALTERNATE SRUTDOWN DESIGNED TO FUNCTION DURING I 4530
. INDICATION SYSTEM AND AFTER CONTROL ROOM FIRE POWER GENERATION DESIGN BASIS FSAR 7. 4. 3. 3 ALTERNATE SRUTDOWN 10CFR50, APP. A. GDC 19 I 4532 INDICATION SYSTEM GUIDES, CRITERIA AND STANDARDS FSAR 7. 4. 3. 3 ALTERNATE SRUTDOWN IEEE 279-1971 X 4533 INDICTATION SYSTEM OUIDES, CRITERIA AND STANDARDS FSAR 7. 4. 3. 3 ALTERNATE BRUTDOWN IEEE 323-1974 X 4534 INDICATION SYSTEM GUIDES, CRITERIA AND STANDARDS FSAR 7. 4. 3. 3 ALTERNATE SRUTDOWN IEEE 344-1975 I 4535 INDICATION SYSTEM GUIDES, CRITERIA AND STANDARDS FSAR 7. 4. 3. 3 ALTERNATE 85UTDONN RG 1.22 X 4536 INDICATION SYSTEM GUIDES, CRITERIA AND STANDARD 5 FSAR 7. 4. 3. 3 ALTERNATE BRUTDOWN BTP CME 8 9.5-1 X 4537 INDICATION SYSTEM GUIDES, CRITERIA &
STANDARDS O O 9 O O O O
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====re==== ==================== ========e==========e =======+==================== ======= ======e ==================== ========
FSAR 7. 4. 3. 3 ALTERNATE BRUTDOWN BTP CMEB 9.5-I, REQ. C.S.C X 4664 INDICATION SYSTEM DESIGN BASES INFORMATION 4 FSAR 7. 5. 2-1 POST-ACCIDENT RG 1.97 REY. 2 I 4641 MONITORING INSTRUMENTATION FSAR 7. 5. 2-2 INFORMATION SYSTEMS
SUMMARY
OF DESIGN. X 4648 YARIABLE CATEGORIE5 QUALIFICATION AND INTERFACE REQUIREMENTS FSAR 7. 5. 2. 3 DESCRIPTION OF INFO. RO 1.75 I 4538 SYSTEM DESIGN CRITERIA FOR CATEGORY I FSAR 7. 5. 2. 3 DESCRIPTION OF INFO. RG 1.32 X 4539 SYSTEM DESIGN CRITERIA FOR CATEGORT I FSAR 7. 5. 2. 3 DESCRIPTION OF INFO. RG 1.105 I 4540 SYSTEM DESIGN CRITERIA FOR CATEGORY I FSAR 7. 5. 2. 3 DESCRIPTION OF INFO. RG 1.105 x 4807 575. DESIGN CRITERIA FOR CATEGORY 2 FSAR 7. 5. 4 INFO. 5T8TEMS NUREG-0737 I SEE TABLE 7.5.4-2 4542 IMPORTANT TO SAFETY FOR CONFORMANCE ADDITIONAL INFO. FSAR 7. 5. 5. I BT PASSED AND RG 1.47 I 4543 4 INOPERABLE STATUS INDIATION FOR ESF5 DESCRIPTION i i T i
- , - - , . - _ - ---------.---_-.---_- -_----------- - - - ------ - - - ~ , - --- ----- - ---e- -- -- -n,*
Page No. 28 04/03/86 COMMITMENTS l =========== '* MODULE 20 - SORTED BY SOURCE & SECTION
========e==========================*==
COMMITMENT COMMITMENT COMMITMENT DOCUMENT / RESPONS IBILITT RFMARKS REF NO SOURCE SECTION BUBJECT FEATURE DESIGN CONST
======== = ==================== ==================== =======+==================== ======= =====e= ==================== ========
FSAR 7. 5. 5. I BY PASSED AND IEEE 384 X 4544 INOPERABLE STATU5 INDICATION FOR E5F5 DESCRIPTION l FSAR 7. 5. 5. I BYPASSED AND R0 1.75 X 4545 INOPERABLE STATUS INDICATION FOR ESFB DESCRIPTION FSAR 7. 5. 5. 2 BYPASSED AND RG 1.47 I 4546 INOPERABLE STATUS INDICATION FOR ESF5 CONF. TO RG 1.47 FSAR 7. 5. 5. 3 BYPASSED AND BTP-ICSB-21. REV. 2 X 4547 IMOPERABLE STATUS INDICATION FOR ESF5 CONF. TO BTP-ICSB-21 FSAR 7. 6. 1. 2 I & C POWER SUPPLY IEEE 308-1974 X 4549 BYSTEM ANALYSIS FSAR 7. 6. 1. 2 I & C POWER SUPPLY R0 1.6 I 4808 SYSTEM ANALYSIS FSAR 7. 6. 1. 2 I & C POWER SUPPLY TITAL AC-MG SINGLE FAILURE I 4809 SYSTEM - ANALYSIS IN TBE I & C F0WER SUPPLY 8YSTEM OR ASSOCIATED PONRR SUPPLIES CAN CAU5E LO55 0F POWER TO MORE TRAM ONE OF THE REDUNDANT LOADB. FSAR 7. 6. 2. 2 RESIDUAL HEAT IEEE 279-1971 X 4550 REMOVAL ISOLATION BBCT. 4.10, 4.12, 4.15. VALVES ANALYSIS O O O O O O O
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COMMITMENT COMMITMENT COMMITMENT DOCUMENT / RESPONS IRILITY REMARES REF NO SOURCE SECTION SUBJECT FEATURE DESIGN CONST
=========- ==================== =====e============== =======e==================== e====== ======= ==================== ========
FSAR 7. 6. 2. 2 RESIDUAL REAT IEEE 384-1974 X 4551 REMOYAL ISOLATION VALVES ANALYSIS L FSAR 7. 6. 4.A INTERLOCR CIRCUITS BTP IC584 I 5035 0F MOV's IN ECC5 4 ACCUMULATOR LINES , FSAR 7. 6. 6. 7.A INTERLOCES ISOLATING RG 1.29 I 4552 , SAFETY '79 TEM FROM NO" onFETY SYSTEM 42ALYSIS FSAR 7. 6. 6. 7.A INTERLOCES ISOLATING RG 1.62 X 4553 5AFETY SYSTEM FROM NON-5AFETY SYSTEM ANALYSIS FSAR 7. 6. 6. 7.A INTERLOCE5 ISOLATING RG 1.75 I 4554 5AFETY SYSTEM FROM
- NON-5AFETY SYSTEM
, ANALYSIS FSAR 7. 6. 6. 7.A INTERLOCES 150LATING IEEE 384 I 4555 SAFETY SYSTEM FROM NON-SAFETY SYSTEM i ANALYSI5 4 FSAR 7. 6. 6. 7.8 INTERLOCES ISOLATING IEEE 279-1971 I 4556 5AFETY SY5 TEM FROM 1 MON-SAFETY SYSTEM { ANALYSIS FSAR 7. 6. 7. I INTERLOCES FOR RCS BTP R58 5-2 X 4557 PRESS. CONTROL DURING LOW-TEMP. j OPER. ANALYSIS OF - INTERLOCR i 4 l i
Pnge No. 30 04/03/86 COMMITMENTS
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COMMITMENT COMMITMENT COMMITMENT DOCUMENT / RESPONS IBILITY REMARK 8 REF NO SOURCE SECTION SUBJECT FEATURE DE8IGN CONST
==== =e================== ==================== ============================ ======= ======= ==================== ==
FSAR 7. 6. 7. 1 INTERLOCKS FOR RCS IEEE 279-1971 1 4558 PRESS. CONTROL DURING LOW-TEMP. OPER. ; ANALYSIS OF INTERLOCK. FSAR 7. 7. 2. I BEPARATION OF IERR 279-1971, BBCT. 4.7 I 4560 PROTECTION AND CONTROL SYSTEM FSAR 7. 7. 2. 2 REACTOR BRUTDOWN 10CFR50, APP. A. GDC 25 I 4561 WITH CONTROL RODS FSAR 7. 7. 2. 2 REACTOR SHUTDOWN 10CFR50, APP. A. GDC 23 I 4562 WITH CONTROL RODS FSAR 7. 7. 2. 7 CORE COOLING MONITOR NUREG 0737 ITEM II.F.2 X 4564 FSAR 7. 7. 2. 8 REACTOR VE58EL LEVEL NUREG-0737 ITEM II.F.2 X 4565 INSTRUMENTATION SYSTEM FSAR B. 3. 1. 1 DESIGN CRITERIA ALL CLASS IE MOTOR-OPERATED I EXCEPT FOR VALTES 4822 CLASS lE EQUIPMENT VALVE ACTUATORS ARE PROVIDED BT M885 SPECIFIED WITH ACC. SUPPLIER CAPABILITY AT 75% NAMEPLATE FSAR 8. 3. 1. 4 CABLE ROUTING SEPARATION - WITRIN PANELS X 32 AND CONTROL BOARDS, 6 IN. MINIMUM SPATIAL SEPARATION OR BARRIERS ARE PROVIDED BETWEEN COMPONENTS OR CABLES OF DIFF. BEPARATION GROUPS FSAR 9. 2. 1. 5 INSTRUMENTATION RADIATION DETECTOR IS I 4905 APPLICATION MOUNTED IN TER RETURN LINE TO THE TOWER 70 ENSURE RAD. NOT PRE 8ENT IN 878 TEM. O O O O O O O
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========== ==================== e============e====== ============================ ======= ======= ==================== ========
FSAR 9. 3. 2. I CONT. ISOLATION 10CFR50 APP. A.. ODC 54 I 4908 VALVE FOR PROCES5 , AND POST ACCIDENT SAMPLING SYSTEM i FSAR 9. 3. 2. 1 CONT. ISOLATION 10CRF50. APP.A. GDC 55 I 4909 VALVE FOR PROCESS AND POST ACCIDENT SAMPLING SYSTEM FSAR 9. 3. 2. 1 CONT. ISOLATION 10CFR50 APP.A. GDC66 I 4910 VALVE FOR PROCESS AND POST ACCIDENT 5AMPLING SYSTEM FSAR 9. 3. 2. 2 POST ACCIDENT NUREG-0737. TASE II. 93 I 3830 5AMPLING SYSTEM FSAR 9. 3. 2. 2 POST ACCIDENT RG. 1.97 I 3831
= SAMPLING SYSTEM FSAR 9. 3. 3. 3 LEAR DETECTION IBBB 279 I 3574 SYSTEM ON DRAIN OF E5F EQUIPMENT ROOM.
FSAR 9.8 COMPARISON OF YEGP BTP CMER 9.5-1. POSITION I 3951 UNITS 1 & 2 WITE C.T.f. GUIDELINES FOR SPEC.
- RWOUIREMENTS OF BTP PLT. ARRA8 REMOTE CMEB 9.5-1 8AFETT-RELATED PANELS FSAR 10. 3. 1. 1.C DESIGN OF SAFETT ASME III. CLASS 2 AND E SEE TABLE 10.3.2-1 1360 RELATED PORTIONS OF SEISMIC CATEGORY I MAIN STEAM BUPPLY REQUIREMENTS
! SYSTEM i FSAR 10. 3. 1. 1.C DESIGN OF THE MAIM ANSI B31.1 POWER PIPING CODE I DOWN8TREAM OF 1361 STRAM SUPPLY SYSTEM OUTBOARD MSIY RESTRAINT ASSEMBLY. n k' e
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======r=== ===================s ==================== ============================ ======= ======= ==================== ========
FSAR 10. 3. 3.F MAIM STRAM SUPPLY ASME XI 1843 SYSTEM FSAR 10. 4. 7. 1 CONDENSATE & R0 1.32 ; X 445 FERDWATER FSAR 10. 4. 8. 4.E SAFETY EVALUATION ALL POWER SUPPLIES AND I F5AR CHAPTER 7 AMD 2303 CONTROL NECESSARY FOR BAFETY 8. RELATED FUNCTIONS OF THE CONDENSATE AND FREDWATER BYSTEM ARE CLASS 1E. FSAR 10. 4. 9 AURILIARY FERD WATER NUREG-0737 II.E.1.1 I 2307 SYSTEM II.E.1.2 FSAR 10. 4. 9. I SAFETY DESIGN BASE 8. AFM CAN BE OPERATED FROM TRE X 2309 BRUTDOWN PANELS AND THE AUXILIARY FERD WATER PANEL FSAR 10. 4. 9. 5 AUXILIARY FREDWATER IEEE 279-1971 X 454 BYSTEM - INSTR. 9E0. FSAR 10. 4- 9. 5 AUXILIARY FREDWATER IEEE 308-1973 I 455 SYSTEM -INST. HEF. FSAR 10. 4. 9. 5 AUXILIARY FREDWATER RG 1.47 I 456 SYSTEM- INST. PEO. FSAR 10. 4. 9. 5 INSTRUMENTATION RG 1.62 X 2316 REQUIREMENTS FSAR 10.A. 2. ? PHYSICAL SEPARATION R.O. 1.75 I 2319 (AUI. FREDWATER SYST.) FSAR 10.A. 2. 6 PHYSICAL SEPARATION IEEE 384 I 2320 (AUI. FEEDWATER SYST.) O O O O O O O
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========== 3e================== ==e================= ============================ ======= ======= ==================== ========
FSAR 11. 3. I GWM5 DESIGN 10CFR50 APP.A.GDC 60 I SEE 11.3.3 FOR 486 CONFORMARCE FSAR 11. 3. 1 ONMS DESIGN 10CFR50. APP.A.GDC 64 I 2178 FSAR 11. 5. 1.E PERMS-DESIGN RG 1.45 I 502
- FSAR 11. 5. 1.E PERMS-DESIGN RG 1.97 I 503 i FSAR 11. 5. 1.E PERMS-DESIGN 10CFR50 APP. I I 498 FSAR 11. 5. 1.E PERMS-DESIGN RG 8.8 I 501 1
FSAR 11. 5. 1.E PERMS-DESIGN RG 1.21 I 500 i FSAR 11. 5. 1.E PERM 5-DESIGN 000 60 I 504 l } FSAR 11. 5. 1.E PERMS-DEFIGN GDC 63 I 505-t i FSAR 11. 5. 1.E PERMS-DESIGN ODC 64 I 506 4 1 FSAR . 11. 5. 1.E PERMS-DESIGN ANSI N13.1-1969 I 507 FSAR 11. 5. 2-1 PERMS - MECHANICAL ANSI B31.1 I TABLE 508
- CODES FSAR 11. 5. 2-1 PERMS - MECHANICAL ASME B&PV III, class 3 I TABLE 509
- CODE 5 i
$ FSAR 11. 5. 2-2 DETECTOR DETECTOR REQUIREMENTS I TABLE 610 i REQUIREMENTS I FSAR 11. 5. 5 PAMS DESIGN GDC 64 I 514 TSAR 11. 5. 5 PAM6 DESIGN RG 1.97 I 515 f
! FSAR 11. 5. 5-1 PAM - MECMANICAL ANSI'B31.1 I 517 j CODES i
i i i
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=====e==
========== ================ ,== ==========e==e====== ============================ ======= ======= ====================
REDUNDANCY, IEEE 344-1975 I 4872 FSAR 12. 3. 4. I DIVERSITY, INDEPENDENCE REDUNDANCY, IEEE 336-1971 X 4873 FSAR 12. 3. 4. I DIVERSITY. I N D E PE ND E.1CE IEEE 279-1971 X 4874 FSAR 12. 3. 4. I REDUNDANCY. DIVERSITY, INDEPENDENCE IEEE 308-1974 X 4875 FSAR 12. 3. 4. 1 REDUNDANCY. DIVERSITY, INDEPENDENCE IEEE 323-1974 I 4876 FSAR 12. 3. 4. I REDCWDANCY. DIVERSITY. INDEPENDENCE
- 12. 4. I REDUNDANCY, IEEE 384-1974 X 4877 l FSAR 3.
DIVERSIFY. INDEPEND5NCE FSAR 15. O. I. 5 TMI ACTION PLAN NURRO 0737 IXCEPT FOR X 2882 INAPPLICABLE II.E.2.19 (COMPLETION OF 1113.30 AND
.31 ANAIT8 NRC ACTICN)
FSAR 15. O. 8 MITIGATION OF ANSI N18.2-1973 X 2883 ACCIDENT EFFECT8 FSAR 15. O. 8 MITIGATION OF IEEE 379-1972 X 2884 ACCIDENT EFFECTS FSAR 15. O. 8 MITIGATION OF 20 1.63 X 2885 ACCIDENT EFFECTS FSAR 15. 2. 7. 1 Loss OF NORMAL ANALYSIS OF BECONDARY LINE I
SUMMARY
OF ANALYSIS 2843 FREDNATER FLON & BREAR ACCIDENT AS5UMING TO BE BUBMITfED IN CONTROL & PROT. CONTROL AND PROTECTION GRADE FUTURE F5AR SYSTEM. INTERACTION SYSTEM INTERACTION. AMENDMENT O O O O O O O
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========e= ==============,===== ==================== ======re==================== ======= ====s-== ==================== ========
FSAR 15. 6. 2 BREAK IN IMSTR. GDC 55 X 2861 LINES OR OTHER LINES FROM RCPB THAT PENETRATE i CONTAIMMENT. FSAR 17A. O INTRODUCTION ANSI M45.2.4-1972 (IEEE X RRF. F8AR 550. 2968 336-1971) 1.9.30 REF. 9687 AND 688 FSAR 17A. 1 QUALITY ASSURANCE RG 1.30 8/11/72 X REF. F8AR 1.9.30 754 REO. FOR INST. AND INSP. OF P '. ROUIP. FSAR 18. 1. 2.12.8 PLASMA D1 .AY RG 1.97 REY. 2 X 3432 MODULES GENERIC C-83/04/14 EMERGENC' ,ESPONSE A BACRUP EMERGENCT I RESPON8E TO NUREG 4503 LETTER FACILITI'_s OPERATION 8 FACILITT (ROF) 0737. SUPPLEMENT 1. WILL BE PROVIDED. (GENERIC LETTER NO. 82-33) GN 83-3 I.E.B. C-78/04/21 VALVE LIMIT 8WITCHE8 8WITCHE8 WILL BE PROPERLT I RE8PONSE TO IRB 4667 CORRES. QUALIFIED OR CONTROL 78-04 CIRCU178 WILL BE REDESIGNED. I.E.B. C-80/08/05 POSSIBLE MALFUNCTION REPAIR VALVE 8 WITH NAMCO EA I GPC RESPON8E TO NRC. 4673 CORRES. OF NAMCO MODEL EA180 190 POSITION SWITCNE8 WITH DTD 12-17-80. REF.: LIMIT 8WITCNES SWITCH ROUSING 9'8 BETWEEN JP0 50-424 50-425
# ELEVATED 01-79 AND 08-79 PLACING RESPON8E TO 19B TEMPERATURES VALTE8 ON WOLD UNTIL REPAIR 79-28 (8AFETY-RELATED IS COMPLETE.
- EQUIPMENT)
CRC QUEST. 0210. 45B COMPONENT SUPPORTS FRICTION LOAD CONSIDRRED IF I RESPONSE TO QUESTION 4253 CORRES. FRICTION LOAD THERMAL IVEMENT LARGER TBAN l 1/16 INCA. t 1
PoGe No. 36 04/03/86 COMMITMENTS
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RESPONS IBILITY REMARES REF NO COMMITMENT COMMITMENT COMMITMENT DOCUMENT / SOURCE SECTION SUBJECT FEATURE DESIGN CONST rre-==== = =e===r======eer=-=== =========-ee--==e-== e--==e===============e====== ======= ======= ==================== ======== NUREO 0737. CLARIFICATION I RESPONSE TO QUESTION 4155 NRC QUEST. Q281. 10 POST-ACCIDENT CORRES. SAMPLING SYSTEM (9) IN ITEM II.B.3 RG 1.97 REY. 2; I RESPON5E TO 4314 NRC QUEST. 0420. 8 RELIEF AND SAFETY VALVE POSITION QUESTION. REFERENCE CORHRS. TO FSAR TABLE INDICATION 7.5.2-1. PROVIDES QUALIFIED DISPLAY I RERPON5E TO 4315 NRC QUEST. 0420. 13 PLANT SAFETY MONITORING SYSTEM OF RG 1.97 KEV. 2. CAT. 1 QUESTION. CORRES. VARIABLES STEAM GEN. LEVEL IEEE 279-1971 SECT. 4.7 I RESPONSE TO QUESTION 4318 NRC QUEST. 0420. 18 CORRES. INSTRUMENTATION (TWO OUT OF FOUR LOGIC FOR LEVEL) REACTOR VESSEL READ MUREG-0737 II.B.I. ITEM I RE8PONSE TO QUESTION 4903 NRC QUEST. Q420. 40 CORRES. VENT SYSTEM DESIGN A(8) BALANCE OF PLANT WCAP 8760 X RESPOMBE TO QUESTION 4319 NRC QUEST. 0420. 46 CORRES. INTERFACE NITH WESTINGROUSE DE5IGN NRC QUEST. 0420. 51 PHY5ICAL SEPARATION BEPARATION BARRIERS ARE I RESPONSE TO QUESTION 4316 CORRE5. GF MAIN CONTROL PROVIDED OR CIRCUITS BOARD NIRING SEPARATED BY A DISTANCE OF AT LEAST 6 INCRES LUBE OIL PRESS. IEEE 323-1974 X AMEND. 13 4789 NRC QUEST. Q430. 33 CORRES. 8BN50R5 ENVIRONMENTAL QUALIFICATION 8 NRC QUEST. 0430, 75 SEPARATION OF CLASS IEEE 384-1974 I RESPONSE TO QUESTION 4328 CORRES. IE CIRCUITS WITRIN THE MAIN CONTROL BOARD NRC QUEST. 0440. 26 QUALIFICATIONS OF THE ATMOSPRERIC DUMP YALVES. I RESPON5E TO QUESTION 4262 CORRES. ADV'8 PER THEIR OPERATIONS AND TREIR "BTP-RSB5-1" PONER SUPPLIES ARE REQUIREMENTS SAFETY-RELATED AND ARE DESIGNED TO SAFETT-GRADE STANDARDS. O O O O O O O
O O O Page No. 04/03/86 37 O O O COMMITMENTS
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==e======e ================= == ==e==========e====== ====cere=========e========== ======= ======= e==========e======== ========
NRC QUEST. 0140. 29 COMP., EQUIP., AND RO 1.139 I RESPONSE TO QUESTION 4161 CORRES. CONTROLS IN SAFETY-0RADE COLD SRUTDOWN SYSTEM 8 % NRC QUEST. 0440. 39 QUALIFICATION CCWS IEEE 279 I RESPONSE 4263
- CORRES. PUMP DISCRARGE PT.
i NRC QUEST. 0440. 47 RVMYS VALVE 8 THE CONTROL SYSTEM FOR THE I RE8PONSE TO 4266 CORRES. RYRV8 YALVB5 IS SAFETY ORADE QUESTION. , AND MEETS CLASS IE REQUIREMENT 8. 4 NRC QUEST. Q440. 47 RVRV8 VALVES THE CONTROL SY8'7EM FOR THE I RESPONSE TO QUESTION 4270 CORRES. RTRV8 YALVEB IS SAFETY ORADE AND MEET 8 CLASS IG REQUIREMENTS. , NRC QUEST. Q460. 02 DESIGN, TESTING AND RG 1.52. REY. E. 3/T8 I RESPONSE TO QUESTION 4156 l CORRES. MAINTENANCE OF E8F. , ATM. CLEANUP SYSTEM. AIR FILTER AND AD8ORPTION UNIT 8.
- NRC QUEST. Q460. 08 MOBLE GA8 SYSTEM NUREG-0737 I RESPONSE TO QUESTION 4896 4
CORRRS. . NRC QUEST. Q471. 11 PORTABLE MONITOR RG 1.32, REY. 2. TABLE 2 I RESPONSE TO QUESTION 4167 CORFES. INSTR. FOR HIGN RANGE AREA MONITORS (UP 70 10.000 R/N) NRC QUEST. Q480. 23 PENETRATIONS FOR RG 1.141 I RESPON85 TO QUESTION 4321 ! CORRES. INSTRUMENT LINES AMEND. 14 l (CRANGED) NRC QUEST. Q480. 24 PENETRATIONS FOR RG 1.11 I RESPON83 TO 4322 CORRES. INSTRUMENT LINES QUESTION. I i _ _ - . . _ . . . _ _ . _ _ _ _ _ _ . _.______.__m.-.__________.___ __._ _ _ ____ms. _ _ _ - _-_.___.____.___4_______.____.___________m_ - - -
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RESPONS IBILITY REMARE8 RET NO COMMITHRNT COMMITMRNT COMMITMENT DOCUMENT / SUBJECT FEATURE DESIGN CON 8T SOURCR SRCTION ==================== ========
===-====== =====e===========e== =e================== ============================ ======= ====e==
QUALITY OROUP B, RG 1.26 X RESPONSE TO QUESTION 4323 NRC QURST. 0480. 28 CONTAINMENT CR4NGED BY AMEND. CORRES. COMBUSTION GAS 14 CONTAINMENT SYSTEM VALVRS. PIPING OTHRR t TRAN PRESS. BOUND. O O O O e
3.5 IMPLEMENTATION MATRIX O After the commitments are identified, each team reviews the l documents controlling its areas of responsibility to verify l compliance with commitment requirements. O O I l l l O O O O 0013t/092-6
O O O IFLEENTATION SORTED BY REFERENCE NUfeER DOCUMENT / FEATURE SECTION DESIGN LAST DESIGN FIRST CONST LAST CONST FIRST REMARKS E F NO. 1 i EXPLANATION OF FIELDS 4 DOCUMENT /IEA1URE - lim document discussed in the FSAR section or the plant feature described in the FSAR section. (See Connilment Matrix.) , SECTION - The section of the document / feature that is being discussed I UESIGN LAS1, CONST LAST - Last"
" indicates the project document currently containing the information found in the conunitment
! DESIGN FIRST, [ CONST FIRST - "First" indicates the project document that contained the information found in the cranitment when the a , etivities governed by the document first began. REF NO. - A reference number that corresponds to the appropriate line entry in the connitment matrix. - i J t 5 i. ( 0040t/4/0564 i i 1 ___m._m______._____._______.____.___ ______m _ . _ _ - _ - - - - . - - . - , .-u .. ,- _ _ . - - - - , :. m . ,, ..sw---
. , ~ - - , r . - - . . _ , , . , , _ . _ _ _ _ _ ,
O O O I i 1 l O l l l O O e
O O Pnge Co. 04/03/86 O 1 C IMPLEME*JT ATION
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DOCUMRNT/ FEATURE SECTION DESIGN LAST DESIGN FIRST CONST LAST CONST FIRST REMARKS REF NO l
==-=======e==-============ ============ ================ ================ ================ ================ ============= ========
l SEPARATION - WITHIN PANELS DC-1601 REY. 1 DC-Idol, REY. O, 82.00 AND CONTROL BOARDS, 6 IN. 5-10-83 7-7-77 ! MINIdUM SPATIAL SEPARATION I OR BARRIERS ARE PROVIDED i BETWEEN COMPONENTS OR CABLES OF DIFF. SEPARATION GROUPS (FSAR 8.3.1.4) RG 1.29 REV. 3 9/78 (FSAR DC-1000-J. REV. DC-1000-J. REV. 126.00 1.9.29) 4, 4-4-85, 2, 11-15-77, DC-1005 REV. 1 LC-1905 REV. O, 4-4-83 3-10-80 RG 1.32 (FSAR 1.9.32) IEEE-308-1974 132.00 ACCEPTABLE TO NRC , R0 1.62, 10/73 (FSAR DC-16al, REY. 1.-DC-1601, REY. O, 155.00 l.9.62) 6-10-83, 7-7-77. DC-1620 DC-1620 REY. 2 REY. 2, 3-29-83 3-29-83
,i 5 IEEE 279-1971 SECT. 4.17 DC-1000-J REV. DC-1000-J. REY. 156.00 i (FSAR 1.9.62) 4, 4-4-85, 2, 11-15-77 DC-1601, REV. 1. DC-1601, REY. O,
- 5-10-83, 7-7-77 DC-1605, i DC-1605, RET. 1. REY. 0, 8-8-77,
- 3-29-83 DC-1820, REV. O.
DC-1820. REY. 2, 7-1-77. DC-1624,
- 3-29-83, REY. O, 4-28-78 DC-1624 REY. 2
; 6-13-83 I
4 a _ _ . _ - - _ . - _ . _ _ _ . . - _ _ . _ . _ . _ _ _ .a___.__.___---...-____._-____-_._-________---..__.-.________-___--_-._---__.-_____.__-___________.--__-._.---__.____.___--_______.._____..____._._.__----._.-_a .
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DOCUMENT / FEATURE SECTION DESIGN LAST DESIGN FIRST CONST LAST CONST FIRST REMARIS REF NO
========================== =====-=-==== ================ ===s============ ================ ================ ============= ========
RG 1.73 (FSAR 1.9.73) DC-1000-J. REV. DC-1000-J. REY. IEEE-382-1972 158.00 4, 4-4-05, 2, 11-15-77 GENERALLY DC-2415 REV. 1 DC-2415, REV. O ACCEPTABLE 5-16-83 i RG 1.75 (FSAR 1.9.75) DC-1601, REY. 1 DC-1601, REY. 1, 160.00 5-10-83, 5-10-83 DC-1605, REV. 1 DC-1605, REV. 1, 3-29-83 3-29-83 RG 1.89 REV. O 11/74 (FSAR DC-1007 REV. 4 DC-1007 REV. O. 172.00 1.9.89). 4-30-85 6-6-79 IEEE 323-1974 (FSAR DC-1000-J. REY. DC-1000-J. REV. 173.00 1.9.89.1) 4, 4-4-85 2, 11-15-77, DC-1601 REY. 1 DC-1601, REY. O, 5-10-83, 7-7-77 DC-1605, DC-1605, REY. 1 REV. O, 8-8-77, 3-29-83 DC-1620 RET. O. DC-1620 REY. 2. 7-1-77, DC-1624, 3-29-83 REV. O, 4-28-78 DC-1624 REV. 2 6-13-83 RG 1.92, REV. I 12/76 DC-1005 REY. 1. DC-1005, REY. O, 174.00 (FSAR 1.9.9.2) 4-4-83 3-10-80 RG 1.100, REV. I 8/77 DC-1000-J, REY. DC-1000-J, REV. 175.00 (FSAR 1.9.100) 4 4-4-85 2, 11-15-77, i DC-1005, REV. 1. DC-1005 REV. O, i 4-4-83 3-10-80 1 O O O O O O O
. ..m.. .. _
,... . C,O 04/03/86 O O O O O IMPLEMENTATION
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DOCUMENT / FEATURE BBCTION DESIGN LAST DESIGN FIRST CONST LAST CON 5T FIRST REMARES REF NO ,
========================== ============ ===e============ ================ ================ ================ =========== = ========
RG 1.97 REY. 2 12/78 DC-1000-J. REY. DC-1000-J. REV. 178.00 (FSAR 1.9.97) 4 4-4-85 2 11-15-77 DC-1601 REV. 1. DC-1601 REV. 1, 5-10-83 5-10-83 ; DC-1623 REV. 1. DC-1623 REY. 1 5-23-83 5-23-83 DC-2701. REY. O. DC-2701 RET. O. 5-4-80 5-4-80 RG 1.31 (FSAR 6.].l.1.3) X4AQ37-5.0A. X4A037-5.0A. 256.00 REV. 11 RET. O. 3-24-90, 12-20-84 X4AZ01. DIV. Pl. X4AZOI. DIV. Pl. REY. O REY. 14 10-9-85 RG i.37 (FSAR 6.1.1.1.3) X4A037-5.0A. X4A037-5.0A. 258.00 RET. 11 REV. O. 3-24-80 12-20-84 RG 1.44 (FSAR 6.1.1.1.3) X4AZ01. DIV. Pl. X4A201. DIV. Pl. 259.00 REY. 14, 10-9-85 RET. 0 , NUREG-0737 TMI ACTION DC-1623. REY. 1. DC-1623. RET. 1 311.00 ITEMS II.D.3 (F5AR 5-23-83 5-23-83 5.4.13.2) IX4DBil2 REY. IX4DBil2, REV. 18 12-31-85 15 1-21-85 10CFR100 (FSAR 6.0) DC-1000-J. REV. DC-1000-J. REY. 321.00
- 4. 4-4-85 2. 11-15-77 I
l 4 I l I _ _ _ _ , _ _. ___________-_____________-__-___--_-_____-___________---___--___----_--__--__--_-_--_-_________
Page No. 4 04/03/86 IMPLEMENTATION
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========================,3============
DOCUMENT / FEATURE SECTION DESIGN ' *L? DESIGN FIRST CONST LAST CONST FIRST REMARES REF NO
- -=====y================== ============ ====-r3 ,=,===== ================ ================ ================ ============= ========
ASME III. NC-21GO & DC-1204, REY. 2 DC-1204-4, RT 322.00 NC-3120 (FSAR 6.1.1.1.1) 2-11-83, 0, 3-13-78, DC-1205, REV. 2 DC-1205-4, REV. 3-17-83, 0, 12-13-77^, DC-1206, REY. 2, DC-1206-4, REV. 4-28-83, 0, 1-6-78, DC-2415 REV. 1 DC-2415 REV. O, 5-16-83, 3-23-78, X5A015-4, REY. X5A015-4, REY. II, 11-15-85, 0, X4P0003-C.4, X4P0003-C.4 REY. O REY. 2 ASME III, DIV. 1 (FSAR SEE REMARE8 SEE REF. NO. 323.00 6.1.1.1) 322 FOR DESIGN IMPLEMENTATIO N ASME III, NC-2000, CLASS 2 SEE REMARKS SEE REF. NO. 324.00 (FSAR 6.1.1.1.1) 322 FOR DESIGN IMPLEMENTATIO N ASME III, ND-2000, CLASS 3 SEE REMARKS SEE REF. NO. 325.00 (FSAR 6.1.1.1.1) 322 FOR DESIGN IMPLEMENTATIO N 4 O O O O O O O
- . - - .. - _-.-.~ . . . . - - . . . . . . - . . - - . ~ . - - ~ ~ ~ . . . .
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[ h 1 Page M6. 5 04/03/86 IMPLEMENTATION
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SECTION DESIGN LAST DESIGN FIR 8T CON 8T LART CON 57 FIRST REMARES REF NO DOCUMENT / FEATURE
========================== ============ ================ ================ ================ =rs============= =========s..-= ========
X4A010 REV. 5 X4AQ10 REY. 3 3?7.00 ASME III. NC-2000 ME-2000 (FSAR 6.1.1.1) 12-17-84 SPEC. 11-8-82 SPEC. X5AGl9 REV. 2 X5AGl9 REY. 2 7-16-84 7-16-84 ; ASME 11 PART C. SFA X44037-8.0A, X4AQ37-5.04 E8F SYSTEM 8 328.00 8 5.1.5.2 5.5 5.17 5.18 REY. 11 REY. 0. 3-24-80, i AND 5.20 (F5AR 6.1.1.1.2) 12-20-84 YMP VNP SPEC FOR
- SPEC FOR NVAC NTAC OA5 GAS ANALYSIS ANALY818 y
EQUIPMENT SPEC. EQUIPMENT SPEC. 4 X5AA04 REY. 4 X5AA04 REY. 4 PAGE 2, ATM0 87M PAGE 2 ATM0 BTM DUMP VALVE SPEC DUMP YALVE SPEC i X5ACl3 ATT. 6 X5ACl3 ATT. 6 i 6-4 6-4 SFA 5.11 AND 5.14 (F5AR SEE REMARES est , F. NO. 329.00 6.1.1.1.2) 328 boR i DESIGN ! IMPLEMENTATIO I SFA 5.4 AND 5.9 (F8AR 8EE REMARES SEE REF. NO. 330.00 6.1.1.1.2) 328 FOR l DESIGN i IMPLEMENTATIO 1 N l i i I e 3 f I i 1 3 i 1
Pnte No. 6 04/03/06 IMPLEMENTATION
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DOC'fMENT/ FE ATURE SECTION DESIGN LAST DESIGN FIRST CONST LAST CON 8T FIRST REMARE8 REF NO
========-=============e=== -===-=====-- ==============e- ================ ================ ================ ============= .s======
ASMR III AND IX PPP GW5 III/I PPP GWS III/I 331.00 REY. 07/29/85 REY. 09/07/83 ASME III AND IX (FSAR X4A037-5.0A. X4A037-6.0Ai PPP GW5 III/I PPP GWS III/I 331.00 6.1.1.1.2) REV. 11 REY. O. 3-24-80 REY. 07/29/85 REV. 09/07/83 12-20-84 A S,4 E II (FSAR 6.1.1.1.2) SEE REMARKS SER REF. NC. 332.00 328 FOR DESIGN IMPLEMENTATIO N LIMITED TO NO GREATER TRAN DC-1204-4.0L. DC-1204-4.0L. 333.00 90.000 PSI YIELD STRENGTR REY. 2 NRC BRP REV. 1, 3-30-79 (FSAR 6.1.1.1.2) 6.1.1 11/24/75 DC-1206-4.ON. PAGE 6.1.1-4 REY. 1 1-25-79 DC-1206-4.0N. REV. 2, 4-28-83 RG 1.36 (FSAR 6.1.1.1.3) SEE REMARES SEE RET. NO. 334.00 256 FOR DESIGN IMPLEMENTATIO N RG 1.32 (FSAR 10.4.7.1) DC-1305. REY. 4 DC-1305, REY. 4 445.00 3-22-83 3-22-83 O O O O O O O
__._______o_m . . . _ . _ m - __..m._.__. .- _ , ____ -_ . . .._ - . -_- _ ._ _ _ _._..._m . . . . _ _ _ _ _ - . - - . - . O C O Page No. 7 C 01/03/86 IMPLEMENTATION
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DOCUMENT /FRATURE SECTION DRSIGN LAST DESIGN FIRST CONST LAST CON 5T FIPST REMARES REF NO ,
========================== =====e====== ================ ==e============= ================ ================ ============= ========
IEEE 279-1971 (FSAR DC-1000-J. REV. DC-1000-J. REY. 454.00 10.4.9.5) 4, 4-4-85, 0, 11-15-77, DC-1625, REV. 1 DC-1625 RET. O, 8-2-83 2-5-79 ; IERE 308-1973 (FSAR SER REMARES SER REF. NO. 455.00 i 10.4.9.5) 454 FOR DESIGN IMPLEMENTATIO N .i RG 1.47 (FSAR 10.4.9.5) DC-1625. REV. 1 DC-1625 REV. O, 456.00 4 8-2-83 2-5-79 10CFRSO, APP. A, GDC 60 DC-1609 RET. 1 DC-1609 REV. O, 486.00 (FSAR 11.3.1) 4-21-83 3-17-78 10CFR50 APP. I (FSAR DC-1609, REY. 1. 9C-1609 RET. O, 498.00 , ll.5.1.E) 4-21-83 3-17-78 RG 1.21 (FSAR 11.5.1.5) SER REMARES 8BE REF. NO. 500.00 498 FOR i DESIGN - IMPLEMENTATIO i N ! RG 8.8 (FSAR 11.5.1.E) SEE REMARES SER REF. NO. 501.00 j 498 FOR DESIGN IMPLEMENTATIO N 4 s 4 W i i
l Page No. G 04/03/86 IMPLEMENTATION i ============== MODULE 20 - SORTED BT REFERENCE NUMBER [ =====================.================ i DOCUMENT /FRATURE SECTION DRSION LAST DESIGN FIRST CONST LAST CONST FIRST REMARKS REF NO
========================== ============ ==========e*==== ================ ================ ================ ============= ========
RG 1.45 (FSAR 11.5.1.E) DC-1809 REV. 1 DC-1609 REY. 1 802.00 4-21-83 4-21-83 RG 1.97 (FSAR 11.5.1.E) SEE REMAKES ( SEE REF. No. 503.00 602 FOR DESIGN IMPLEMENTATIO N GDC 60 (F8AR 11.5.1.5) BEE REMARES SEE REF. NO. 504.00 498 FOR DESIGN IMPLEMENTATIO N GDC 63 (FSAR 11.5.1.5) SEE REMARES SEE REF. NO. 505.00 498 FOR DESIGN IMPLEMENTATIO N 8EE REMARES BER REF. NO. 506.00 GDC 64 (F5AR ll.5.1.E) 498 FOR DESIGN IMPLEMENTATIO N ANSI N13.1-1969 (F8AR SEE REMARES BER REF. No. 507.00 11.5.1.5) 498 FOR DESIGN IMPLEMENTATIO N i 0 0 0 0 0 9 9 O
,.E. D0 04/03/86 O O O O O O IMPLEMENTATION
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DOCUMENT /FRATURR SECTION DESIGN LAST DESIGN FIRST CONST LAST CONST FIRST REMARES REF NO
==================== ============ ================ ================ ================ ================ ============= ==
PERMS - MECR. CODES (FSAR SEE REMARES SEE REF. NO. 508.00 11.5.2-1) 509 FOR DESIGN
; IMPLEMENTATIO N
ASME BAPV III. CLASS 3 DC-1609 REY. 1. DC-1609 REY. 1, 509.00 (FSAR 11.5.2-1) 4-21-83 4-21-83 DC-2702 REY. O. DC-2702. REY. O. 1-21-82 1-21-82 DETECTOR REQUIREMENTS DC-1609-3.0 DC-1609-3.0, 510.00 (FSAR TABLE 11.5.2-2) REV. 1 4-21-83 REY. 1. 4-21-83 GDC 64 (FSAR 11.5.5) DC-1623 REY. 1 DC-1823 RET. O. 514.00 5-23-83 7-7-77 RG 1.97 (FSAR 11.5.5) SEE REMARES 8EE REF. NO. 515.00 514 FOR DESIGN IMPLEMENTATIO N PAMS - MECR. CODES (FSAR SEE REMARES SEE REF. NO. 517.00 11.5.5-1) 509 FOR DESIGN IMPLEMENTATIO N P
Page No. 10 04/03/86 IMPLEMENTATION
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DOCUMENT /FRATURE SECTION DESIGN LAST DESIGN FIRST CONST LAST CONST FIRST REMARES REF NO
========ce================ ============ ================ ================ ================ s=============== ============= ========
10CFR100 (FSAR 1.2.6) SEE REMARKS SEE REF. NO. 673.00 321 FOR DESIGN ( IMPLEMENTATIO N R.G. 1.12 (FSAR 1.9.12) DC-2414 REY. 1 DC-2414, REV. 1, 678.00 6-29-81 6-29-81 RG 1.30, 8/72 (FSAR DC-1000-J, REY. DC-1000-J. REY. DESIGNATED 686.00 1.9.30) 4, 4-4-85 2, 11-16-77 IEEE 336 GENERALLY ACCEPTABLE, REFER TO 687 AND 688 FOR CONSTRUCTION IMPLEMENTATIO N ANSI 45.2.4 1972 C.1 PPP YOGTLE QA PPP YOOTLE QA ASME B&PT 687.01 MANUAL, REV. MANUAL, REY. SECTION III 10/21/85 PPP 11/21/83 PPP PIPING. II-40 REY. IX-40 REY. TUBING, ETC. 09/09/85 01/12/84 ANSI 45.2.4 1972 C.2 PPP YOGTLE QA PPP V0GTLE 04 DESIGN BASR8 687.02 MANUAL, RET. MANUAL, RET. SUBSTITUTE 10/21/95 PP 11/21/83, 15-40, ASME R&P?, 11-40 REY. REY. 01/12/84 SECTION III 09/09/85 FOR ANSI B31.7 i O O O O O O O
Page N 11 04/03/86 IMPLEMENTATION
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SECTION DESIGN LAST DESIGN FIRST CONST LAST CONST FIRST REMARES REF NO DOCUMENT / FEATURE ............e == .....
=======================... ============ .===............ ==.........ta=== ===...===.....== ===... 3== .....
DC-1000-J. REY. DC-1000-J. REV. 687.03 ANSI N45.2.4-1972 (FSAR 1.9.30) 4 4-4-85 2 11-15-77 IEEE 336-1971 (FSAR 2.3.4.5.6 ; GD-A-04 REY. 11. GD-A-04 REY. O. LIMITED TO 688.01 1.9.30) GD-A-08 REY. 15 GD-A-08 REY. O. ELECTRICAL GD-A-30 REY. 10. GD-A-30 REV. O. BBVICES, GD-T-01 REV. 13. 00-T-01 REY. O. CIRCUITS. GD-T-09 REY. 8 GD-7-09 REV. O. ETC. FOR GD-T-20 REY. 1 GD-T-20 REY. O. CONSTRUCTION GD-T-22 REY. 2 GD-T-22 REY. O. IMPLEMENTATIO BD-T-02 REY. B. ED-T-02 REY. O. N ED-T-04 REY. 8 ED-T-04 REY. O. ED-T-08 REY. 8 ED-T-08 REY. O. DC-A-09 REV. 4 DC-A-09 REV. 3 OC-A-01 REY. 3 OC-A-01 NEV. 1 IEEE 336-1971 (FSAR DC-1000-J. REY. DC-1000-J. REY. 688.02 1.9.30) 4 4-4-85 2 11-15-77 RG 1.30 8/11/72 (FSAR SEE REMARES 8EE REF. NO. 754.00 17.A.1) 686 FOR DESIGN IMPLEMENTATIO N 10CFR50 APP.A. GDC 13 DC-1621. REY. 1. DC-1621. REY. O. 792.00 (FSAR 3.1.2) 6-2-83 DC-1612, 10-13-77 REY. O. 9-8-77 DC-1612. REY. O. 9-8-77 i i i 1 i
Page No. 12 04/03/86 IMPLEMENTATION
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MODULR 20 - SORTED BT REFERENCE NUMBER
..=e ...=...=....= ...................
DOCUMRNT/FRATURR SRCTION DRSIGN LAST DESIGN FIRST CONST LAST CONST FIRST REMARES REF NO e.........= ==..-...-..= . .--,........ == -=........... .....=.......... ................ ................ ............. ........ 10CFR50 APP. A. GDC 20 DC-1604, REY. 1 DC-1604 REY. O, 796.00 (FSAR 3.1.3) 6-31-83 10-3-77
. DC-1605 REV. 1, DC-1605 REV. O.
3-29-83 8-8-77 4 10CFR50, APP. A. GDC 21 SEE REMARES BER REF. NO. 799.00 (FSAR 3.1.3) 796 FOR DESIGN IMPLEMENTATIO N IRRR 279-1971 (FSAR 3.1.3) DC-1000-J. REV. DC-1000-J. REY. 800.00 4, 4-4-85, 2 11-15-77 DC-1604, REY. 1 DC-1604, REY. O, 6-31-83, 10-3-77, DC-1605, REV. 1. DC-1605, REV. O, 3-29-83, 8-8-77 DC-1620, DC-1620, REV. 2. REY. O. 7-1-77 3-29-83 IEEE 379-1972 (FSAR 3.1.3) SEE REMARES SEE REF. NO. 801.00 800 FOR DESIGN IMPLEMENTATIO N RG 1.22 (FSAR 3.1.3) SEE REMARES SEE REF. NO. 802.00 800 FOR DESIGN IMPLEMENTATIO N i 1 O 9 9 O O O O
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SECTION DESIGN LAST DESIGN FIRST CONST LAST CONST FIRST REMARES REF NO DOCUMENT / FR Attf RE
==================e======= ============ ================ ================ ================ ================ ============= ========
l RG 1.47 (FSAR 3.1.3) SEE REMARES SEE REF. NO. 803.00 456 FOR i DESIGN IMPLEMENTATIO N 10CFR50 APP. A. ODC 22 SEE REMARES 8EE REF. NO. 804.00 800 FOR I (FSAR 3.1.3) DESIGN IMPLEMENTATIO N 10CFR50 APP. A. GDC 23 DC-1605 REY. 1. DC-1605. REV. O. 805.00 (FSAR 3.1.3) 3-29-83 B-8-77 DC-1620 DC-1620 REV. 2 REV. O. 7-1-77 ' 3-29-83 10CFR50 APP. A. GDC 24 SEE REMARKS SEE REF. NO. 806.00 l i (FSAR 3.1.3) 805 FOR DESIGN d IMPLEMENTATIO N 10CFR50 APP. A. GDC 29 SEE REMARKS SEE REF. NO. 807.00 l 796 FOR i (FSAR 3.1.3) DESIGN IMPLEMENTATIO N i 3 4 s i J s 1 l I J 9
PoEe No. ' 14 04/03/06 IMPLEMENTATION
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CONST LAST CONST FIRST REMARES REF NO DOCUMENT / FEATURE SECTION DESIGN LAST DESIGN FIRST
==================== ======-===== =====e========== ============e=== ================ ================ ============= ==
819.00 10CFR50 APP. A. ODC 63 DC-1000-J. REY. DC-1000-J. REV. (FSAR 3.1.6) 4 4-4-85 2 11-15-77 DC-1609 REV. 1. DC-1609 REY. O. 4-21-83 3-17-78 ; REY. 1 DC-1604. REY. O. 830.00 NOTE (S): I&C WRICR CAN DC-1604 EFFECT THE 5-31-83, 10-3-77 OPERATION / ACTUATION OF A DC-1010 REV. 4 DC-1010 RET. O. SAFETT-RELATED FUNCTION 6-29-83 8-4-78 MUST BE QUALIFIED TO REQUIREMENT OF PROJECT CLASS llJ (FSAR 3.2.2-1) DC-1000-J. REY. DC-1000-J. REY. 834.00 R.G. 1.26 (FSAR 3.2.2-1) NOTE (d) 4 4-4-85, 2 11-15-77 DC-1010 REV. 5 DC-10lO. REV. O. 2-7-86 8-4-78 SEE REMARKS SEE REF. NO. 837.00 NOTE (c): QUALITT OROUP RO 834 FOR 1.26 (FSAR 3.2.2-1) DESIGN IMPLEMENTATIO N DC-1000-J. REY. DC-1000-J. REY. 840.00 MAIN CONTROL BOARD IEEE-344 & 323 (FSAR 4 4-4-85, 2 11-15-77 3.2.2-1) DC-1601 REV. 1. DC-1601. REY. 0, 5-10-83 7-7-77 O O O O O O O
.... N ,.
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SRCTION DESIGN LAST DESIGN FIRST CONST LAST CONST FIRST REMARES REF NO DOCUMENT /FRATURE ================ ================ ================ ============= =====; =
========================== ======e===== ==-======s======
NOTE (p): PAMS INSTR. SEE REMARES SEE REF. No. 842.00 PROJ. CLASS BASED ON 178 FOR CATEGORY BT RG 1.97 REV. DESIGN
; IMPLEMENTATIO 2 (FSAR 3.2.2-1) N NOTE (e): SEISMIC SEE REMARES 8EE REF. NO. 843.00 CATEGORY RG 1.29 (FSAR 126 FOR 3.2.2-1) DESIGN IMPLEMENTATIO N
MEMA Mal 1972 (FSAR DC-1010 REY. 5 DC-1010 REY. O. 865.00 3.2.2-1) 2-7-86 8-4-78 ASME III. SUBSECTION ND. SEE REMARE5 SEE REF. NO. 889.00 CLASS 3 (FSAR 3.2.2-2) 322 FOR DESIGN IMPLEMENTATIO N RG 1.61 (FSAR 3.7.B.1.3) DC-1005 REY. 1 DC-1005 REY. O. 981.00 4-4-83 3-10-80 ASME III (FSAR 3.10.B.3) DC-1017 REY. 4. DC-1017 REV. O. 1223.00 8-9-85, 1-19-78 DC-1000-J. REY. DC-1000-J. REY. 4 4-4-85 2 11-15-77 ! DC-1005 REV. 1. DC-1005. REY. O. 4-4-83 3-10-80 I i. i l
Pags No. 16 04/03/86 IMPLEMENTATION
=====...= ==..
MODULE 20 - SORTED BY REFERENCE NUMBER
=====-..====...=..........===..=====..
DOCUMENT /FRATURR SECTION DRSIGN LAST DESIGN FIRST CONST LAST CONST FIRST REMARKS REF NO 3,== ==..=.=.. ==-3--- === 3. - =.-==.. . . . = = . = . . . . . . . - . . . . . . . . . . . - . . . . . . . . . . = . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . TMI ACTION PLAN TASK SPRC. FOR SPEC. FOR 1336.00 II.F.I (FSAR 6.2.5.2) HYDROGEN HYDROGEN MONITORING MONITORING EQUIPMENT, SPEC. EQUIPMENT, $PEC. NO. X5AA05 REV. NO. X5AA05 REV. 5, 5-31-84 0 ASMR III, CLASS 2 AND DC-1005, REY. 1 DC-1005, REV. O, 1360.00 SRISMIC CAT. 1 4-4-83, 3-10-80 REQUIRRMENTS (FSAR DC-1000-J. REY. DC-1000-J. REY. 10.3.1.1.C) 4, 4-4-85, 2 11-15-77 DC-1301 REY. 5 DC-1301, REY. 3, 3-29-83 12-6-79 ANSI B31.1 PONER PIPING SEE REMARK 5 SEE REF. NO. 1361.00 CODE (FSAR 10.3.1.1.C) 1360 FOR DESIGN IMPLEMENTATIO N HG 1,53 REY. 0 6/73 (F5AR DC-1000-J. REY. DC-1000-J. REY. 1551.00 1.9.53) 4, 4-4-85, 2, 11-15-77 DC-1601, REY. 1. DC-1601 REY. O, 5-10-83, 7-7-77 DC-1605 DC-1605. REV. 1 RET. O, 8-8-77, 3-29-83, DC-1620, REV. O, DC-1620 REV. 2, 7-1-77 3-29-83 J O O O O O O O
.. ..._.m__ . . _ ._.___m...
_ _ ..mm.._m..._ .-_.._._m-_...m.-_._ _ . _ _ _ _ _ _ _ . . _ _ _ _ . . . . . . . . . . . . - . . . . _ . . - ..m__ . . .m_. . _ . . _ _ m I'a g e % 17 04/03/86 IMPLEMENTATION
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DOCUMENT / FEATURE SECTION DESIGN LAST DESIGN FIRST CONST LAST CONST FIRST REMARES REF NO
============nn============ ==-========= ================ ================ ================ ================ ============= ========
I IREE 379-1972 (FSAR SEE REMARES SEE REF. NO. 1552.00 1.9.53)~ 1551 FOR DESIGN
; IMPLEMENTATIO N
IEEE 279-1971 SECT. 4.2 DC-1009 REV. 2 DC-1009, REY. 1, 1553.00 (FSAR 1.9.53) 6-3-83 3-12-81 RG 1.84, REY. 20, 11/82 DC-1000-J. PARA. DC-1000-J, PARA 1585.00 (FSAR 1.9.84) IB, REV. 4, IB, REV. 2, 4-4-85 11-15-77 RG 1.85, NEV. 20, 11/82 DC-1000-J. PARA. DC-1000-J. PARA. 1569.00 (FSAR 1.9.85) IB, REY. 4 18 REV. 2, l 4-4-85 11-15-77 i ANSI N45.2.8-1975 (F8AR SEE REMARKS SEE REF. NO. 1579.00 1.9.116.1) 887.02 FOR DESIGN IMPLEMENTATIO N RG 1.141 REY. O, 4/78 DC-2415 REY. 1 DC-2415 REY. 1, 1595.00 . (FSAR 1.9.141) 5-16-83 6-18-83 i ] ANSI N271-1976 (FSAR DC-2415, REV. 1 DC-2415 REY. O, 1596.00 1 1.9.141) 6-16-83 3-23-78 4 4 ? I ] i i t T 1 1
)
4
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DOCUMENT / FEATURE SECTION DESIGN LAST DESIGN FIRST CONST LAST CONST FIRST REMARES REF NO
-========================= =ee===-=-=== ================ ================ ================ ================ ============= ========
10CFR50 APP. A (FSAR SEE REMARES SEE REF. No. 1597.00 1.9.141.1) 1596 FOR DESIGN ( IMPLEMENTATIO N R.G. 1.22. REV. 0 (FSAR DC-1000-J. REV. DC-1000-J. REV. 1602.00 1 9.22) 4 4-4-85, 2 11-15-77 DC-1605 REV. 1 DC-1605 REV. O. 3-29-83 8-8-77 DC-1620 0C-1620 REY. 2 REY. O. 7-1-77 3-29-83 DC-1625 REY. O. DC-1625, REY. 1 2-5-79 8-2-83 ASME XI (FSAR 10.3.3.F) DC-1000-M. REY. DC-1000-M. REV. 1843.00 2, 4-12-78 0, 6-1-73 R0 1.48 (FSAR 3.10.B.3) DC-1017 REV. 4 DC-1017 REV. 0 1851.00 0-9-85 RG 1.47, 5/73 (FSAR SEE REMARES SEE REF. NO. 1923.00 1.9.47) 4543 FOR DESIGN IMPLEMENTATIO N IEEE 279-1971. SECT. 4.13 DC-1000-J. REY. DC-1000-J. REY. 1924.00 (FSAR 1.9.47) 4 4-4-85, 2 11-15-77 DC-1625 REY. 1 DC-1625. REY. O. 8-2-83 2-5-79
)
i l l O O O O O O O i
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Pace M & #' 19 04/03/86 IMPLEMENTATION
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SECTION DESIGN LAST DESIGN FIRST CONST LAST CONST FIRST REMARE8 REF NO DOCUMENT /FRATURE
=======e3================= ============ ================ ================ ================ ================ ============= ========
10 CFR 50 APP. R CRITERIA SEE REMARES SEE REF. NO. 1925.00 XIV (FSAR 1.9.47) 1924 FOR DESIGN
; IMPLEMENTATIO N
RG 1.95, REY. I 1/77 (FSAR DC-1531 REV. 3 DC-1531 REV. O, 2020.00 1.9.95) 8-9-83 6-27-74 10CFR50 APP. A. GDC 56 DC-2415. REY. 1 DC-2415 REY. O, 2027.00 (FSAR 3.1.5) 6-16-83 3-23-78 DESIGNED AS CLASS IR, DC-1513 REV. O. DC-1513. REY. O, 2066.00 SEISMIC CAT. 1 (FSAR 6-3-83 6-3-83 6.2.5.1) R.G. 1.7 - CONTROL OF SEE REMAR25 855 REF. NO. 2067.00 COMBUSTIBLE GAS CONC. IN 2066 FOR CONTA. FOLLONING A LOCA DESIGN (FSAR 6.2.5.1) IMPLEMENTATIO N 10CFR50, APP. A, ODC 19 SEE REMARE8 SEE REF. No. 2068.00 (FSAR 6.2.5.1) 2066 FOR DESIGN IMPLEMENTATIO N RG 1.26 QUALITT GROUP 5 855 hdMARES SEE REF. NO. 2073.00 (FSAR 6.2.5.2) 2066 FOR DESIGN IMPLEMENTATIO i i J d 5 __ __.___m______._______._ _ _ _ _ _ _ _ _ _ _ _ __
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SECTION DRSIGN LAST DESIGN FIRST CONST LAST CONST FIRST REMARES REF NO DOCUMENT /FRATURR 2-========-==e============ =====-====== ================ ===e============ ================ ================ ============= ====== = MONITORS DESIGNED TO SEE REMARES SEE REF. NO. 2074.00 FUNCTION FROM 2 TO 60 PSI 2068 FOR 0 (FSAR 6.2.5.2) DESIGN ( IMPLEMENTATIO N 4 RG 1.45 (FSAR 5.2.5.4) DC-1000-J. REY. DC-1000-J. REV. 2162.00 4, 4-4-85, 3, 6-29-83, 0C-1609 REY. 1. DC-1609 REV. 1, 4 4-21-83 4-21-83 ASME IX & III (FSAR DC-1000-J. REY. DC-1000-J. REV. 2170.00 6.1.1.1.2) 4, 4-4-85, SPEC. 2, 11-15-77, X5AC01, REY. 6 8PEC. E5AC01, REV. 0 10CFR50 APP. A. GDC 64 DC-1609. REV. 1. DC-1609. REY. O, 2178.00 (FSAR 11.3.1) 4-21-83 3-17-78 ALL POWER SUPPLIES AND DC-2415 REY. 1. DC-2415. REY. 1, 2303.00 CONTROL NECESSARY FOR 5-16-83 5-16-83 SAFETV RELATED FUNCTIONS OF THE CONDENSATE AND FDWR SYSTEM ARE CLASS IE (FSAR 10.4.8.4.E) NUREG-0737 II.E.1.1, DC-1604, REY. 1. DC-1604 REV. O, 2307.00 II.E.1.2 (FSAR 10.4.9) 5-31-83 10-3-77 i f O O O O O O O
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DOCUMENT / FEATURE SECTION DESIGN LAST DESIGN FIR 5T CONST LAST CONST FIRST REMARES REF NO
=== =.=========........... ..==........ ................ ................ =............... ................ ............. ......-.
. AFW CAN BE OPERATED FROM DC-1302 REY. 5 DC-1302, REV. 2, 2309.00 ! THE SHUTDOWN PNL5 AND THE 8-1-84 8-28-74 AUX. FDWR PNL (FSAR 10.4.9.1) ; R0 1,62 (FSAR 10.4.9.5) DC-1601. REY. 1. DC-1601, REY. O. 2316.00 5-10-83, 7-7-77 DC-1620, 4 DC-1620 REY. 2, REY. O. 7-1-77, 3-29-83 DC-1624 REY. O. DC-1624 REY. 2, 4-28-78 6-14-83 RG 1.75 (FSAR 10.A.2.6) DC-1302 REV. 5. DC-1302, REY. O, 2319.00 4-18-83, 7-9-74 DC-1001 DC-1001 REY. 1. REV. 1, 8-30-83 8-30-83 l IEEE 384 (F5AR 10.A.2.6) SEE REMARK 5 855 REF. NO. 2320.00 2319 FOR , DESIGN
~
IMPLEMENTATIO , N THE AIRBORNE RADIOACTIVITT DC-1609 REY. 1, DC-1609 REY. O, 2339.00 i MONITORING SYSTEM IS 4-21-83 3-17-78 . QUALIFIED FOR SSE (F8AR 5.2.5.1) THE SENSITIVITT & RE5P. DC-1220 REY. 1. DC-1220. REY. 1, 2340.00 i TIME OF THE DETECTION 9-5-80 9-5-80 } EQUIPMENT FOR UNIDENTIFIED - LEAEAGE IS SUCR THAT A i LEAEAGE RATE, OR 175 EQUIVALENT OF 1 OAL/ MIN. CAN BE DETECTED IN APPRO. 1 HOUR (F5AR 5.2.5.3) i i 4 i i i
Page Eo. 22 04/03/86 IMPLEMENTATION
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DOCUMENT / FEATURE SECTION DESIGN LAST DESIGN FIR 5T COMBT LAST CONST FIRST REMARE5 REF NO se======================e= ============ ================ ================ ================ ================ ============= =====e-= BTP ICSB-21 (FSAR 8.1-1) SAME A8 ITEM 2382.00 e 4474. 4 RO 1.29 (FSAR 6.2.2.1) DC-1005, REY. 1 DC-1005, REF. O, 2398.00 4-3-83, DC-1010, 3-10-P0, REY. 4, 6-29-83 DC-1010 REY. O, 8-4-78 CSS AUTO. PLACED IN DC-2415 REY. 1 DC-2415. REY. O. El-El IN DCM, 2403.00 OPERATION ON RECEIPT OF 5-16-83 3-23-78 81-3 IN FSAR TWO OUT OF FOUR CONTA. PRESSURE (RI-3) SIGNALS (rSAR 6.2.2.2.1.1) IEEE 279 ( FSAR 6.2.2.2) SEE REMARE8 SEE REF. NO. 2405.00 1491 FOR DEBIGN IMPLEMENTATIO N 4 IEEE 279 (FSAR 6.2.2.2.5) 8EE REMARK 8 SAME A8 ITEM 2408.00
# 1491 FOR i
DESIGN IMPLEMENTATIO N DESIGNED TO SEIBMIC CAT. 1 DC-2415 REY. 1 DC-2415 REY. O, 2407.00 (FSAR 6.2.4.1) 6-18-83, 3-23-78 DC-1005 REY. 1. DC-1005 REY. O, 4-3-83 3-10-80 9 9 O O O O O
..E.
04/03/86 O 23 O O O O ' IMPLEMENTATION
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MODULE 20 - SORTED BT REFERENCE NUMBER
==.==.=.. .......=.......=..=..=...=.e r
DOCUMENT / FEATURE SECTION DESIGN LAST DESIGN FIR 8T CON 5T LAST CONST FIRST REMARES REF NO
=..==..................=.. ............ ................ ................ ................ ..........=..... ............. ........
ASMR III. CLASS 2 (FSAR SEE REMARKS SEE REF. NO. 2408.00 6.2.4.1) 965 FOR DESIGN
; IMPLEMENTATIO N
i TMI ACTION PLAN TASK DC-1604 REY. 1. DC-1604 REV. 1 2409.00 II.E.4.2 (FSAR 6.2.4) 5-31-83 D-31-83 , DC-1000-J. REY. DC-1000-J. REY. 4 4-4-85 4. 4-4-85 , 10CFRSO. APP. A. GDC 54 DC-2415 REY. 1. DC-2415. REV. O. 2410.00 (FSAR 6.2.4.1) 5-16-83 3-23-78 10CFR50 APP. A, GDC 55 & DC-2415. REY. 1. DC-2415. RET. O. 2411.00 ' 56 (FSAR 6.2.4.1.1) 6-16-83 3-23-78 10CFR50 APP. A. GDC 57 SEE REMARKS SEE REF. NO. 2412.00 (FSAR 6.2.4.1) 2410 FOR
- DESIGN IMPLEMENTATIO N
1 10CFR50 APP. A. ODC 55 & 8BE REMARES 8EE REF. NO. 2413.00 i 56 (FSAR 6.2.4.1) 2410 FOR I DESIGN ' IMPLEMENTATIO 4 N 1 ) 1 r 1 i I
PsCe No. 24 04/03/86 IMPLEMENTATION
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DOCUMENT / FEATURE SECTION DESIGN LAST DESIGN FIRST CONST LAST CONST FIRST REMARES REF NO er======================== ======-===== ================ ===we=========== ================ ================ ============= ======== R.O. 1.141 (FSAR 6.2.4.1) SEE REMARK 5 SEE REF. NO. 2414.00 2410 FOR DESIGN ( IMPLEMENTATIO N 10CFR50 APP. A. GDC 64 SEE REMARK 8 SEE REF. NO. 2418.00 (FSAR 6.2.4.3D) 2410 FOR DESIGN IMPLEMENTATIO N 10CFR50 APP. A. GDC 56 BBE REMARKS SEE REF. NO. 2420.00 (FSAR 6.2.4.30) 2410 FOR DESIGN IMPLEMENTATIO F BTP CSB 6-4 (FSAR 6.2.4.2) SEE REMARKS SEE REF. NC. 2422.00 2410 FOR DESIGN IMPLEMENTATIO N R0 1.11 (F8AR 6.2.4.30) SEE REMARES SEE REF. NO. 2429.00 2410 FOR DESIGN IMPLEMENTATIO N P O O O O O O O
,.E. R 01/03/86 O 2, O c O O O IMPLEMENTATION
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DOCUMRNT/FRATURE SECTION DESIGN LAST DESIGN FIRST CONST LAST CONST FIRST REMARES REF NO
===,==========- ========== ===========, ================ ================ ================ ================ ============= ========
10CFR50, APP. J (FSAR SRE REMARES 8EE REF. No. 2432.00 6.2.4.4) 2410 FOR DESIGN
; IMPLEMENTATIO N
ALL POWER SUPPLIE5 AND SEE REMARK 5 SEE REF. NO. 2433.00 CONTROL FCTS NECESSART FOR 2410 FOR CONTA. ISOLATION ARE CLASS DESIGN IR (FSAR 6.2.4.6) IMPLEMENTATIO N 1 THE CONTA. ISOL. SYSTEM 15 SEE REMARK 5 SEE REF. NO. 2437.00 DESIGNED IN ACCORDANCE 2410 FOR I WITH SEIBMIC CAT. I DESIGN REQUIREMENT (FSAR IMPLEMENTATIO 6.2.4.3.R) N UNITS ARE POWERED FROM DC-1513, REY. O DC-1513, REY. O, 2440.00 INDEPENDENT CLASS IE POWER 6-3-83 6-3-83 SOURCES (FSAR 6.2.5.1) HA. FAN IS POWRRED FROM AM DC-1516 REY. 1, DC-1516. REY. O, 2447.00 INDEPENDENT CLA85 IE POWER 9-6-83 11-21-78 SUPPLT (FSAR 6.2.5.2) IEEE 279 ( FSAR 6.2.5-1) VNP SPEC. FOR R2 VNP SPEC. FOR R2 2453.00 RECOMBINER RECOMBINER X6AB01-18-3, ISAB01-18-3, PAGE 5 PAGE 5 t r
. _ . _ _ . _ . _ _ . _ _ _ . _ - _ . _ . _ _ _ _ _ _ . _ _ _ _ _ _ _ . . _ _ . . . _ _.____-..._.__.__._________._________.__.___.____m.- _ _ _ _ _ _ . _ _ _ . _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ . _ _ . _ _ _ _ _ _ _ _ _
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DRSIGN LAST DESIGN FIRST CONST LAST CONST FIRST REMARE5 REF NO DOCUMENT /FRATilRR SECTION
==========r =e============ ========-=== ================ =========s====== ================ ================ ============= ========
SEE REMARKS SEE REF. NO. 2454.00 IEER 308-1974 (FSAR 2453 FOR 6.2.5-l) DESIGN 4 IMPLEMENTATIO N SEE REMARK 8 SEE REF. No. 2457.00 IEEE-383 (FSAR 6.2.5-1) 2453 FOR DESIGN IMPLEMENTATIO N 10CFR50, APP. A. GDC 54 DC-2415. REV. 1 DC-2415. REY. O. 2458.00 (FSAR 6.2.6) 5-16-83 3-23-78 \' RG 1.141 (FSAR 6.2.4.2) SEE REMARK 5 SEE REF. NO. 2488.00 2410 FOR DESIGN IMPLEMENTATIO N 10CFR50 APP. A, ODC 56 SEE REMARKS 5EE REF. NO. 2491.00 (FSAR 6.2.4.3E) 2410 FOR DESIGN IMPLEMENTATIO N 10CFR50, APP. A, ODC 57 BER REMARK 8 SEE REF. No. 2492.00 (FSAR 6.2.4.3F) 2410 FOR DESIGN IMPLEMENTATIO N j i O O O O O O O
._ . . ....___ m _ _ _ _m_. m . . _ . . . _ _ . . __ _ _ _ _ .. . _ m .. ,.E.
04/03/86 O 2, O O O O O IMPLEMENTATION j
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==..=====..we========================.
SECTION DESIGN LAST DE' ION TIRST CONST LAST CON 8T FIRST REMARES REF NO DOCUMENT / FEATURE
==e-===-======...=.3=.==.. =====....... .==....=........ .==......=...... ......==........ .....==......... ............. .=......
BTP ICSB-18 (FSAR DC-1009. REY. 2 DC-1009 REY. 1, 2817.00 6.3.2.2.16) 6-3-83 3-12-81 ANALYSIS OF SECONDARY LINE DC-1302, REY. 5 DC-1302, rey. 3, 2843.00 BREAK ACCIDENT A55UMING 4-19-83 2-11-77 CONTROL AND PROTECTION GRADE SYSTEM INTERACTION (FSAR 15.2.7.1) GDC 55 (FEAR 15.6.2) SEE REMARES SEE REF. NO. 2861.00 2410 FOR DESIGN IMPLEMENTATIO N NUREG-0737 EXCEPT FOR DC-1007 REY. 3. DC-1007. REY. 1, 2882.00 INAPPLICABLE II.K.2.19 4-6-84 12-7-82 (FSAR 15.0.1.5) ANSI N18.2-1973 (FSAR DC-1009 REY. 2, DC-1009, REY. 2, 2883.00 15.0.8) 6-3-83, 6-3-83 DC-1000-J. REY. DC-1000-J, REY. 4, 4-4-85 IEEE 379-1972 (FSAR SEE REMARES SEE REF. NO. 2884.00 15.0.8) , 2883 FOR DESIGN IMPLEMENTATIO N
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DESIGN FIRST CON 5T LAST COMET FIRST REMARE5 REF NO DOCUMENT / FEATURE SECTION DESIGN LAST
===-===========-========== ============ ================ ================ =====u========== ================ ============= ========
SEE REF. NO. 2885.00 RG 1.53 (FSAR 15.0.8) SEE REMARES 2883 FOR DESIGN ( IMPLEMENTATIO N SEE REMARE8 SEE REF. NO. 2988.00 ANSI M45.2.4-1972 (!EEE 687.02 FOR 336 1971) (FSAR 17A.0) DESIGN IMPLEMENTATIO N DC-1623. REV. 1. DC-1623. REY. 1 3432.00 RG 1.97 REV. 2 (FSAR 18.1.2.12.8) 5-23-83 5-23-83 REV. O. 3574.00 IEEE 279 (FBAR 9.3.3.3) DC-1609. REY. 1 DC-1809 4-21-83 3-17-78 VNP P.A.S.8. TNP P.A.S.8. 3830.00 NUREG-0737 TA5E II. B.3 (FSAR 9.3.2.2) SPEC. E5AA08 SPEC. E5AA08 REY. 3. DC-1211. REV. 3. DC-1702 REV. 2. 3-17-83 REV. O. 1-20-82, DC-2702, REY. O. DC-1211. RET. 2 1-70-82 3-17-83 SEE REMARES SEE REF. NO. 3831.00 RG 1.97 (FSAR 9.3.2.2) 3830 FOR DESIGN IMPLEMENTATIO N l 9 O O O O O O
. _ . . . . . . .. . . .. .. . . . . _ _ . _ . . . _ . - , _ . .m _ _ . _._m _ . .m__ . _ .. _ _ _ _ . _ _
O O O
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- MODULE 20 - SORTED BT REIERENCE NUMBER < ======_=========_===================== i DOCUMENT / FEATURE SECTION DESIGN LAST DESIGN FIRST CONST LAST CONST FIRST REMARES REF NO 1
========================== ============ ================ ================ ================ ================ ============= ========
BTP CMEB 9.5-1 POSITION SEE REMARES EEE REF. No. 3951.00 C.7.f. GUIDELINES FOR 4537 FOR , . SPEC. PLT. ARRAS. REMOTE DESION S/R PNLS. (FSAR 9.B) ( IMPLEMENTATIO N i
- 10CFR50 APP. A. GDC 8 DC-1006 REV. 2 DC-1006 REY. O. 4115.00 I
(FSAR 3.1.1) 7-13-83, 12-19-77 DC-1007 REV. 4 DC-1007. REY. 1, 4 4-30-85 12-7-82 10CFR50 APP. A. ODC 5 DC-1001. REY. 1. DC-1001 REY. 1 4116.00 (FSAR 3.1.1) 8-30-83 8-30-83 l 10CFR50 APP. A. GDC 19 DC-1601 REV. 1 DC-1601 REY. O. 4120.00 (FSAR 3.1.2) 6-10-83 7-7-77 10CFR50 APP. A. GDC 25 DC-1602 REY. 1. DC-1607. REY. O. 4131.00 (FSAR 3.1.3) 4-15-83 10-11-77 DC-1605 REY. 1 DU-1605 REY. D. 3-29-83 8-8-77 ! 10CFR50 APP. A. GDC 55 DC- 1000-J. REY. DC-1000-J. REY. 4135.00 (FSAR 3.1.5) 4 4-4-85 3. 6-29-83 DC-2415. REY. 1. DG-1415. REY. O. 5-16-83 3-23-78 I i 10CFR50 APP. A. GDC 64 DC-1609. REY. 1. DC-1609 REY. O. 4138.00
- (FSAR 3.1.6) 4-21-83 3-17-78 I
i k i
PmQe No. 30 04/03/86 IMPLEMENTATION
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=======================,=====,========
DOCUMRNT/FEATURR SECTION DESIGN LAST DESIGN FIRST CONST LAST CONST FIRST REMARK 5 REF NO
=============-============ ===========- ====e=== ======= ===*============ ================ ================ ============= ===== en NUREG-0737 CLARIFICATION SEE REMARES SEE REF. NO. 4155.00 (9) IN ITEM II.B.3 (NRC 3830 FOR OURST. CORRES. 0281.10) DESIGN 4 IMPLEMENTATIO N
RG 1.52 REY. 2 3/78 (NRC DC-1531 REV. 3 DC-1531 REY. O. 4156.00 QURT. CORRES. 0460.02) 8-9-83 DC-1620 6-27-74 REV. 2, 3-29-83 DC-1620 REY. 2 3-29-83 RG 1.139 (NRC QUEST. DC-1205 REV. 2 DC-1205 REY. O. 4161.00 CORRES. Q440.29) 3-17-83, 12-13-77 DC-1624 REY. 2 DC-1624 REV. 2, 6-13-83 6-13-83 RG 1.92 REV. 2 TABLE 2 oc-1609 REY. 1 DC-1609 REY. O. 4167.00 (NRC QUEST. CORRES. 4-21-83. SPEC. 3-17-78 8PEC. 0471.11) I6AZ01. REY. 4 I6AE01 REY. O. PROCESS EFFUENT PEKMS RADIATION MONITORING SYSTEM (PERMS) FRICTION LOAD CONSIDERED DESIGN 4253.00 IF THERMAL MOVEMENT LARGER- STATEMENT. THAN 1/16 INCH (NRC QUEST. NOT A CORRES. Q210.458) COMMITMENT 9 9 9 9 9 9 e -
O % - Pete Mk. 31 V %' ') 04/03/86 IMPLEMENTATION
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SECTION DESIGN LAST DESIGN TIRST CONST LA8T CONST FIRST REMARE8 REF NO i DOCUMENT / FEATURE
=================...=..=== =====.. ==== =====.....====== ==....===..===== ==..=...===..... ................ ............. ==......
THE ATMOSPRERIC DUMP ADV's SPEC. ADV's SPEC. 4262.00 VALVES. THEIR OPERATIONS X5Acl3. REY. 2 X5AC13 REV. O. AND THEIR POWER SUPPLIES 12-23-83 ARE SAFETY-RELATED AND ARE ; DESIONED TO SAFETY-ORADE STDS. (NRC QUEST. CORRES. ! 0440.26) IEEE 279 (NRC QUEST. DC-1203. REY. 6 DC-1203, REY. 6 4263.00 l 1 CORRES. 0440.39) 11-2-83, 11-2-83 DC-1601. RET. 1. DC-1801. REY. O. 5-10-83 7-7-77 THE CONTROL SYSTEM FOR TRE DC-1000-J. REY. DC-1000-J. REY. 4266.00 RVHYS VALVES IS SAFETY 4 4-4-85 2 11-15-77 3 l GRADE AND MEETS CLASS IE DC-1201. REY. 2 DC-1201. REY. 1 REQUIREMENTS (MRC QUEST. 3-9-84 DC-1010 4-21-83
- CORRES. 0440.47) REY. 4. 6-29-83. DC-1010 REY. O.
- FILE I6AA01 8-4-78 FILE
' I6AA01 , RO 1.97 REY. 2 (NRC SEE REMARE5 SEE REF. NO. 4314.00 ' QUEST. CORRES. 0420.8) 178 FOR DESION I IMPLEMENTATIO
- N 1 PROVIDES QUALIFIED DISPLAY 8EE REMARE8 SEE REF. NO. 4315.00 0F RO 1.97 REY. 2 CAT. I 178 FOR VARIABLE (NRC QUEST. DESIGN CORRES. 0420.13) IMPLEMENTATIO
' N i e t
PsGe No. 32 04/03/06 IMPLEMENTATION
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DOCUMENT / FEATURE SECTION DRSIGN LAST DESIGN FIRST CONST LA8T CONST FIRST REMARES REF NO e=-=====--================ ======~ee=== ================ ===*============ ========n======= ================ ============= ======== SRPARATION BARRIERS ARE DC-1601 REV. 1 DC-1601 REV. 1 4316.00 PROVIDED OR CIRCUITS 5-10-83 5-10-83 SEPARATED BY A DISTANCE OF AT LEAST 6 INCRES (NRC % QUEST. CORRES. 0420.51) IEEE 279-1971 SECTION 4.T DC-1000-J. REY. DC-1000-J. REV. 4318.00 (NRC QUEST. CORRES. Q 4 4-4-85 2 11-15-77 420.18) DC-2415, REY. 1 DC-2415 REY. O. 5-16-83, 3-23-78 DC-1320 REY. 2 DC-1320 REV. O. 5-31-83 12-6-79 WCAP 8760 (NRC QUEST. DC-1009 REY. 2. DC-1009 REV. 2 BER REFERENCE 4319.00 CORRES. 0420.46) 6-3-83 6-3-83 0F DC-LOOP TN DC-1825 RG 1.141 (NRC QUEST. DC-2415 REY. 1. DC-2415. REY. 1 4321.00 CORRES. 0480.23) 6-16-83 5-18-83 RG 1.11 (NRC QUEST. BER REMARES SEE REF. NO. 4322.00 CORRES. 0480.24) 4321 FOR DESION IMPLFMENTATIO N QUALITT GR B R.G. 1.26 DC-1000-J. REY. DC-1000-J. RRV. 4323.00 , (NRC QUEST. CORRE5. 4 4-4-85, 2 11-15-77 0480.28) 0C-1010 REY. 5 DC-1010 REY. O. 2-7-86 8-4-78 O O O O O O O
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DOCUMENT / FEATURE SECTION DESIGN LA5T DESIGN FIRST CONST LAST CONST FIRST REMARES REF NO , --.==....-- =.===-......-e e--e-...-... ......-.......= ................ =...==.......... ................ .....= ...... ........
~
IEEE 384-1974 (NRC QUEST. DC-1000-J. REY. DC-1000-J, REY. 4328.00 CORRES. 0430.75) 4 4-4-85, 2 11-15-77 DC-1601 REV. 1. DC-1601 REV. O. 5-10-83 7-7-77. DC-1620 DC-1620 REV. 2 REY. O. 7-1 1 77 3-29-83 IEEE 279-1971 (FSAR 7.1) DC-1620 REV. 2. DC-1620 REY. O. 4359.00 3-29-83 7-1-77 90-1624 DC-1624 REY. 2, REY. O. 4-28-78 6-13-83 MIN. DNBR SHALL NOT BE DC-1605. REY. 1. DC-1605-1. REV. 4478.00 LESS TRAN 1.30 AS A RESULT 3-29-83 0. 8-8-77 0F ANY ANTICIPATED TRAN5IENT OR MALFUNCTION (F5AR 7.1.2.1) E5FA5 MUST HAVE PROVISIONS DC-1605. REY. 1. DC-1605-1. REV. 4479.00 IN THE CONTROL ROOM FOR 3-29-83 O. 8-8-77 MANUALLY INITIATINO THE DC-1620 REY. 2. DC-1620 REV. O. PUNCTICN5 0F THE ESF 3-29-83 7-1-77 SYSTEM (FSAR 7.1.2.1) VITAL AC THE INVERTER DC-1605. REY. 1. 90-1605-1. REY. 4480.00 SRALL BAVE THE CAPACITY , 3-29-83 0, 8-8-77 AND REOULATION REQUIRED FOR THE AC OUTPUT FOR PROPER OPERATION OF THE EQUIPMENT SUPPLIED (FSAR 7.1.2.1) d j 4 i 4
PnRe Not 34 04/03/86 IMPLEMENTATION
==============
MODULE 20 - SORTED BT REFERENCE NUMBER
==er=====,============================
DOCUMENT / FEATURE SECTION DESIGN LAST DERIGN FIRST CONST LAST CON 5T FIRST REMARE8 REF NO
=--==============-==e===== ====-=--===e ====-=========== ===-============ ================ ================ ============= ========
VITAL AC - REDUNDANT LOADS DC-1605 REV. 1 DC-1605 REY. O, 4481.00 SRALL BR ASSIGNED TO DIFF. 3-29-83 8-8-77 DISTRIBUTION PNLS NRICR ARE SUPPLIED FROM DIFF. 4 INVERTERS (FSAR 7.1.2.1) IEEE 279-1971 (FSAR DC-1605, REY. 1. DC-1805, REY. O, 4487.00 7.1.2.2) 3-29-83, 8-8-77, DC-1620 DC-1620, REY. 2, REV. O, 7-1-77 3-29-83 CCAP-8892-A, JUNE '77 BER REMARES 5BE REF. NO. 4488.00 (FSAR 7.1.2.2) 4487 FOR 7ESION IMPLEMENTATIO N IEEE 384-1974 SECT. 5.7 SEE REMARES SER REF. NO. 4489.00 (FSAR 7.1.2.2) 4487 FOR DESION IMPLEMENTATIO N AUTO INITIATES NRENEVER DC-1605, REY. 1. DC-1605, REV. O, 4490.00 NECESSARY TO PREVENT FUEL 3-29-83 8-8-77 bAMAGE FOR AN ANTICIPATED OPER. TRANSIENT (CONDITION II) (FSAR 7.2.1.1) O O O O O O O
.. . ___ - . . . . _ . _ _ _ . - _ _ . . . _ . ._ . - _ . . . . . . . . - _ m . . _ . . _ . . . _ . . _ _ _ . _ ._ . . _ .
Pase No. 35 01/03/R6 IMPLEMENTATION
==== .========
MODULE 20 - SORTED BT REFERENCE NUMBER
=============..=..====================
DESIGN FIRST CONST LAST CONST FIRST REMARE8 REF NO DOCUM2NT/FRATIIRE SECTION DRSIGN LART ========
==e== s=e==== e========= . .e=====,==== ............ .. ......... ... == =======......... =s======........ .......=3====
SEE REMARK 5 BER REF. NO. 4491.00 AUTO INITIATES TO LIMIT 4490 FOR , CORE DAMAGE FOR INFREQUENT DESIGN FAULTS (CONDITION III) IMPLEMENTATIO (FSAR 7.2.1.1) ( N SEE REMARES BEE REF. NO. 4492.00 AUTO IMITIATES 50 TRAT THE 4490 FOR ENERGT GEN. IN THE CORE IS BBSIGN COMPATIBLE WITH THE DESIGN IMPLEMENTATIO PHOV. TO PROTECT THE RCPB N FOR LIMITING FAULT COND. i (CONDITION IV)(FSAR , 7.2.1.1) SEE REF. No. 4493.00 TMI ACTION ITEM II.K.3.10 5EE REMARKS 4490 FOR (FSAR 7.2.1.1) DESIGN IMPLEMENTATIO N 4494.00 IEEE 279-1971 (FSAR DC-1000-J. RET. DC-1000-J. RET. 7.2.1.1) 4 4-4-45, 2 11-16-77 DC-1613. REY. 9 90-1613. RET. O. 10-19-77 10-19-77 SEE REMARE8 SEE REF. MO. 4496.07 RG 1.82 (F5AR 7.2.1.1) 4490 FOR DESIGN IMPLEMENTATIO N I I 4
Page No. 36 04/03/8G IMPLEMENTATION
==============
MODULE 20 - SORTED BY REFERENCE NUMBER eree-e=-e-==-============-=ee===e===== DOCUMENT /FRATURE SECTION DESIGN LAST DESIGN FIRST CONST LAST CONST FIRST REMARES REF NO
=====-====e=ee=== =====-e, -==--===-=== ====e=========== =,-============= ================ ================ ============= =======e 10CFR50 APP. A. ODC 2 DC-1005 REY. 1 DC-1005 REV. O. 4496.00 (FSAR 7.2.1.1) 4-4-83 DC-1605 3-10-80 REV. 1 3-29-83 DC-1605 RET. O.
8-8-77 i IEEE 279-1971 (FSAR DC-1203 REV. 6 DC-1203 REY. 6 4498.00 7.3.10.2) 11-2-83, 11-2-83 DC-1000-J. REV. DC-1000-J. REY. 4 4-4-85 2 11-15-77 A BACEUP EMBRGENCY DC-2701 REV. O. DC-2701. REV. O. 4503.00 OPERATIONS FACILITY (BOF) 5-4-82 5-4-82 WILL PE PROVIDED (GENERIC LTR CORRES. C-83/04/14) NO SINGLE FAILURE PRRVENTS DC-1513 REY. O. DC-1513 REY. O. 4514.00 THE CONTA. COMBUSTIBLE GAS 6-3-83 6-3-83 CONTROL SYSTEM *~ ROM FUNCTIONING (FSAR 7,3.3.1) NO SINGLE FAILURE SHALL DC-1302. REY. 5. DC-1302. REY. 3 4516.00 PREVENT THIS SYSTEM FROM 4-18-83 2-11-77 OPERATING (FSAR 7.3.7.1) SHUTDOWN PNLS AND SAFETY DC-1624 REY. 2. DC-1624. REY. 1 4519.00 GRADE SW DESIGNED TO 6-13-83 9-16-84 WITHSTAND SSE WITR MO LOSS OF ESSENTIAL FUNCTIONS i (FSAR 7.4.3.1) 9 9 9 9 9 9 9
Page Nb 37 -
\
04/03/86 IMPLEMENTATION
==============
MODULE 20 - SORTED BT REFERENCE NUMBER
===================.======.========.==
DOCUMENT /FEATURR SECTION DESIGN LAST DESIGN FIRST CONST LAST CONST FIRST RBMARES RRF NO
,=e- ====-=--=-.========-= ====-=-=..=- e-====.... ===== .=====.......... ......= =====... ==........=..... ===.....=..=. =.......
IEEE 279-1971 (FSAR DC-1000-J. RRY. DC-1000-J. REY. 4520.00 7.3.4.2.8) 4, 4-4-85, 2 11-15-77 DC-1620 REV. 2 DC-1620 REV. O, 3-29-83, 7-1-77. DC-{415 DC-1505 REY. 5 REY. O, 3-23-78, 7-26-83 DC-1505 REY. 2 DC-2415. REY. 1. 6-27-74 5-16-83 AFS - TRK SYSTEM MUST DC-1302 RRV. 5. DC-1302, REY. 3, 4523.00 PROVIDE FULL AUX. 4-19-83 2-11-77 FERDWATER FLOW WITRIN 1 MIN. (FSAR 7.3.7.1) 10CFR50, APP. A, GDC 13 DC-1302, REY. 5 DC-1302. REY. 5, 4524.00 i (FSAR 7.3.7.2.A) 4-19-83 4-18-83 DC-1601, REY. 1. DC-1601. REY. 1 5-10-83, 5-10-83, ' DC-1624 REY. 2 DC-1624. REV. 2 , l 6-13-83 6-13-83 1 10CFR50 APP. A. GDC 19 DC-1801, REY. 1. DC-1801, REY. O, 4525.00 I (FSAR 7.3.7.2.A) 5-10-83, 7-7-77, DC-1834, DC-1624 REY. 2 REV. O. 4-28-78 6-13-83 10CFR50, APP. A, GDC 34 DC-1302 REY. 5. DC-1302, REY. O, 4526.00 i (FSAR 7.3.7.2.A) 4-18-83, 7-9-74. 9C-1620 i DC-1620 REY. E. REY. 2, 3-29-83 3-29-83 4 i i 4 4 l
Pore No. 38 04/03/R6 IMPLEMENTATION
==============
MODULE 20 - 50RTED BY REFERENCE NUMBER
======ne==============================
CONST LAST CONST FIRST REMARKS REF NO SECTION DESIGN LAST DESIGN FIRST DOCUMENT / FEATURE ================ ================ ================ ============= ========
=========e========== ====e======= ==========
4527.00 IEEE 279-1971 (F5AR DC-1000-J REV. DC-1000-J. REV. 4, 4-4-85, 2, 11-15-77 7.3.7.2.8) DC-1302, REV. 3, DC-1302, REY. 5 4-18-83 2-11-77 ( 4528.00 IRER 279-1971 (FSAR DC-1000-J. REY. DC-1000-J. REY. 4, 4-4-85, 2, 11-15-77 7.3.8.2.5) REY. O, DC-1820, REV. 2 DC-1620 3-29-83, 7-1-77, DC-1305, DC-1305 REV. 4 REY. 4, 3-22-83 3-22-83 SEE REMARES SEE REF. NO. 4529.00 IREE 279-1971 (FSAR 4528 FOR 7.3.9.2.8) DESIGN IMPLEMENTATIO N REY. 2, 4530.00 DESIONED TO FUNCTION DC-1624 REY. 2. DC-1624 DURING AND AFTER CONTROL 6-13-83 6-13-83 ROOM FIRE (FSAR 7.4.3.3) DC-1824 REV. 2. DC-1624. REV. O, 4532.00 10CFR50, APP. A, ODC 19 (FSAR 7.4.3.3) 6-13-83, BER 4-28-78 REMARKS SEE REMARE8 SEE REF. No. 4533.00 IBBE 279-1971 (FSAR 4532 FOR 7.4.3.3) DESIGN IMPLEMENTATIO N O O O O O O O
Page N- 39 04/03/86 IMPLEMEETATION
==============
MODULE 20 - 50RTED BT REFERENCE NUMBER
======================================
DOCUMENT / FEATURE SECTION DESIGN LAST DESIGN FIRST CONST LAST CON 8T FIRST REMARES REF NO
========================== ============ ================ ================ ================ ================ ============= ========
IEER 323-1974 (FSAR SEE REMARKS SEE REF. NO. 4534.00 7.4.3.3) 4332 FOR DESIGN
; IMPLEMENTATIO N
IEEE 344-1975 (FSAR SEE REMARK 8 BER REF. NO. 4535.00 l 7.4.3.3) 4532 FOR DESIGN IMPLEMENTATIO N RO 1.22 (FSAR 7.4.3.3) DC-1624 REY. 2, DC-1624 REY. 1, 4536.00 6-13-83 9-16-81 BTP CMED 9.5-1 (FSAR SEE REMARK 8 SEE REF. NO. 4537.00 7.4.3.3) 4536 FOR DESIGN IMPLEMENTATIO N RG 1.75 (FSAR 7.5.2.3) DC-1623. REY. 1. DC-1623, RET. 1 4538.00 5-23-83 6-23-83 RG 1.32 (FSAR 7.5.2.3) SEE REMARKS BER REF. No. 4539.00 4538 FOR DESIGN IMPLEMENTATIO 1 N I. 1 J i e a 1 4 I
PnEe No. 40 01/03/86 IMPLEMENTATION
==============
HODULE 20 - SORTED BY REFERENCE NUMBER
======================================
SECTION DESIGN LAST DESIGN FIRST CONST LAST CONST FIRST REMARK 8 REF NO DOCUMENT / FEATURE
========================== =======-==== ==e============, ================ ================ ================ ============= ========
SEE REMARES SEE REF. No. 4540.00 RG 1.105 (FSAR 7.5.2.3) 4538 FOR DESIGN t IMPLEMENTATIO N RG l.97, REY. 2 (FSAR BEE REMARKS 8EE REF. NO. 4541.00 7.5.2-1) 178 FOR DESIGN IMPLEMENTATIO N NUREG-0737 (FSAR 7.5.4) SEE REMARKS SEE REF. KO. 4542.00 4338 FOR DESIGN IMPLEMENTATIO N RG 1.47 (FSAR 7.5.5.1) DC-1625, REY. 1. DC-1625 REY. 0, 4543.00 8-2-83 2-5-79 IEEE 384 (FSAR 7.5.5.1) BER REMARKS SEE REF. NO. 4544.00 4543 FOR DESIGN IMPLEMENTATIO N RG 1.75 (FSAR 7.5.5.1) 8EE REMARE8 SEE REF. No. 4545.00 4543 FOR DESIGN IMPLEMENTATIO ' N O O O O O O O
.___._m_ . . _ . m . _ _ . , _ _ _ _ .-m.. - . . . .
. _ . _ _ . . _ _ . _m- .. _. .
. . .. . _ . . . . -_. _ m__- .
Page N 41 04/03/86 IMPLEMENTATION
==============
MODULE 20 - SORTED BT REFERENCE NUMBER
================,======================
DOCUMENT /FRATUEE SECTION DESIGN LAST DESIGN FIRST CONST LAST CONST FIRST REMARES REF NO
========================= ============ ================ ==== ========== ================ ================ ============= ========
RG l.47 (FSAR 7.5.5.2) SEE REMARKS SEE REF. NO. 4546.00 4543 FOR DESIGN
; IMPLEMENTATIO N
BTP ICSB-21 REY. 2 (F8AR SEE REMARKS SEE REF. NO. 4547.00 7.5.5.3) 4543 FOR DESIGN IMPLEMENTATIO N SUMMART OF DESIGN, SEE REMARES SEE REF. No. 4548.00 QUALIFICATION AND 4538 FOR INTERFACE REQUIREMENTS DESIGN (FSAR 7.5.2-2) IMPLEMENTATIO N IEEE 308-1974 (FSAR DC-1000-J. REY. DC-1000-J. RET. 4549.00 7.6.1.2) 4, 4-4-85 2, 11-15-77 IEEE 279-1971, SECT. 4.10, DC-1000-J REY. DC-1000-J. REY. 4550.00 4.12 AND 4.15 (FSAR 4, 4-4-85, 2 11-15-77, 7.6.2.2) DC-1605, NET. 1. DC-1605 REY. O, 3-29-85 8-8-77 IRRE 384-1974 (FSAR DC-1000-J. REY. DC-1000-J REY. 4551.00 7.6.2.2) 4, 4-4-85, 2 11-15-77, DC-1604, RET. 1. DC-1604, REY. O, 5-31-83, 10-3-77, DC-1605 REY. 1, DC-1605 RET. O, 3-29-85 8-8-77 I t 4 t
Pnge No. 42 04/03/06 IMPLEMENTATION
======-=======
MODULE 20 - SORTED BT REFERENCE NUMBER
======================================
CONST LAST CONST FIRST REMARKS REF No DOCUMENT /FRATURE SECTION DRSION LAST DRSION FIRST =====r-= r=========e ============== ==e=-=-===== =e============== ====w=========== ================ ================ ============= SEE REF. NO. 4552.00 RG 1.29 (FSAR 7.6.6.7.A) SEE REMARKS 4551 FOR DESIGN ( IMPLEMENTATIO N SEE REMARKS SEE REF. NO. 4553.00 RG 1.62 (FSAR 7.6.6.7.A) 4551 FOR DESIGN IMPLEMENTATIO N SEE REMARKS 8EE REF. NO. 4554.00 RG 1.75 (FSAR 7.6.6.7.A) 4551 FOR DESIGN IMPLEMENTATIO N SEE REMARKS SEE REF. NO. 4555.00 IEEE 384 (FSAR 7.6.6.7.A) 4551 FOR DESIGN IMPLEMENTATIO N SEE REMARKS SEE REF. NO. 4556.00 IEEE 279-1971 (FSAR 4550 FOR 7.6.6.7.8) DESIGN IMPLEMENTATIO N l l
,.E f 04/03/06 4, O O O O O O IMPLEMENTATION
==============
MODULE 20 - SORTED BY REFERENCE NUMBER
======================================
DOCUMENT /FRATURR SECTION DRSION LAST DESIGN FIRST CONST LAST CONST FIRST REMARES REF NO
=========-================ ====e===-=-= =-============== ==============*= ================ ================ ============= ========
BTP PSB 5-2 (FSAR 7.6.7.1) DC-1201 REY. 2. DC-1201 REY. 2 4557.00 3-9-84 3-9-84 IRRR 279-1971 (FSAR SEE REMARES ; SEE REF. No. 4558.00 7.6.7.1) 4557 FOR DESIGN IMPLEMENTATIO N IEEE 279-1971. SECT 4.7 8EE REMARES SEE REF. NO. 4560.00 (FSAR 7.7.2.1) 4550 FOR DESIGN IMPLEMENTATIO N 10CFR50 APP. A. GDC 25 DC-1605 REY. 1. DC-1605. REY. O. 4561.00 1 (FSAR 7.7.2.2) 3-29-83 8-8-77 10CFR50 APP. A. 000 23 BEE REMARES SEE REF. NO. 4562.00 (FSAR 7.7.2.2) 4561 FOR l DESIGN
! IMPLEMENTATIO 4
N NUREG-0737 ITEM II. F.2 DC-1601. REY. 1. DC-1601. RRY. 1 4564.00 (FSAR 7.7.2.7) 5-10-83 6-10-83 1 NUREG-0737 ITEM II. F.2 855 REMARES SEE REF. NO. 4565.00 (FSAR 7.7.2.8) 4564 FOR DESIGN IMPLEMENTATIO N a 1 4 i 1 . l
Page No. 44 04/03/86 IMPLEMENTATION
==============
MODULE 20 - SORTED BT REFERENCE NUMBER
======================================
DOCUMENT / FEATURE SECTION DESIGN LAST DESIGN FIRST CONST LAST CONST FIRST RBMARKS REF MO
========================== =====-=====- ================ ================ ====-=========== ================ ============= ======-=
IEEE 279-1971 SECT. 4.11 - DC-1000-J. REV. DC-1000-J. REY. 4576.00 4.13 (FSAR 7.1.2.1) 4 4-4-85 2. 11-15-77 DC-1605 REV. 1 DC-1605 REV. O. 3-29-83 8-8-77 ( 10CFR50 APP. A. ODC 20 SEE REMARES SEE REF. No. 4577.00 (FSAR 7.1.2.1) 4576 FOR DESIGN IMPLEMENTATIO N 10CFR50 APP. A. GDC 21 SEE REMARKS SEE REF. NO. 4578.00 (FSAR 7.1.2.1) 4576 TOR DESIGN IMPLEMENTATIO N 10CFR50 APP. A. ODC 22 SEE REMARKS SEE REF. No. 4579.00 (FSAR 7.1.2.1) 4576 TOR DESIGN IMPLEMENTATIO N IEEE 279-1971. SECT. 4.11 DC-1000-J. REY. DC-1000-J. REY. 4580.00
- 4.14 (FSAR 7.1.2.1) 4 4-4-85 2 11-15-77 DC-1625 REY. 1 DC-1625 REY. O.
B-2-83 2-5-79 IEEE 384-1971 (F8AR SEE REMARE8 SEE REF. No. 4581.00 7.1.2.1) 4580 FOR DESIGN IMPLEMENTATIO N O O O O O O O
Page No.O 45 O O O O O 04/03/86 IMPLEMENTATION
==============
MODULE 20 - SORTED BT REFERENCE NUMBER
======================================
DOCUMENT /FRATURE SECTION DESIGN LAST DESIGN FIRST CONST LAST CONST FIRST REMARR8 REF NO
==e=======e=======e======= ee==ee====== ================ ================ ================ ================ ============= ========
R0 1.75 (FSAR 7.1.2.1) SER REMARES 8BR REF. NO. 4582.00 4580 FOR DESIGN
; IMPLEMENTATIO N
IRRE 279-1971 (FSAR SER REMARRR 5BB REF. NO. 4583.00 7.1.2.1) 4580 FOR DB5 ION IMPLEMENTATIO N DO NOT REQUIRE PROCESS SPEC, X5AD05 8PRC. ISAD05 4585.00 TRANSMITTERS TO OPERATR REV. 5 5-31-84 REY. O WITRIN 5% OF THE RIGH AND LOW RND OF THEIR CALIBRATED SPAN OR RANGE (FSAR 7.1.2.1.9) R0 1.75 POSITION C.4 SER REMARES 8BB REF. NO. 4586.00 (FSAR 7.1.2.2) 4580 FOR DESIGN IMPLBMENTATIO N I 1885 279-1971 (FSAR SER REMARR8 BBB REF. NO. 4587.00
- 7.1.2.2) 4580 FOR
- DB5 ION IMPLEMENTATIO
! N t i i i 4 1
Pete No. 46 04/03/86 IMPLEMENTATION
==============
MODULE 20 - SORTED BT REFRRENCE NUMBER e===== =============================== CONST FIRST REMARES REF NO SECTION DESIGN LAST DESIGN FIRST CONST LAST DOCUHRNT/FRATURR
= ======-2-===========-=== ======-===== ================ ================ ================ ================ ===========_= =====--=
SEE REF. No. 4588.00 WCAP-8R92-A. J tlN R '77 SEE REMARES 4580 FOR (FSAR 7.1.2.2) DESIGN ( IMPLEMENTATIO N SEE REMARES SEE REF. NO. 4589.00 1RRE 384-1974 SECT. 5.7 4580 FOR (FSAR 7.1.2.2) DESIGN IMPLEMENTATIO N i 4590.00 RG 1.62 (FSAR 7.1.2.2) DC-1605. REY. 1. DC-1605. REY. O. 3-29-83 8-8-77 DC-1620 DC-1620 REV. 2 REV. 2 3-29-83 3-29-83 SEE REF. NO. 4593.00 IRER 379-1972 (F5AR SEE REMARE5 4590 FOR 7.1.2.6) DESIGN IMPLEMENTATIO N BEE REMARES SEE REF. NO. 4594.00 RO 1.53 (FSAR 7.1.2.6) 4590 FOR DESIGN IMPLEMENTATIO N O 9 9 O O O O
Page N 47
- 04/03/86 IMPLEMENTATION
==============
MODULE 20 - SORTED BT REFERENCE NUMBER
==============-=======================
DOCUMENT /FRATURE SECTION DRSIGN LAST DESIGN TIRST CONST LAST CONST FIRST REMARR5 REF NO
-e===,=====e============ ======-===== ===============- ================ ================ ================ ============= =====
IRRE 279-1971. SECT. 4.2 SER REMARES SER REF. NO. 4595.00 (FSAR 7.1.2.6) 4590 FOR BRSION
; IMPLEMRMTATIO N
IRRE 279-1971 SECT. 3 DC-1000-J. REV. DC-1000-J. REV. 4596.00 (FSAR 7.2.1.2) 4 4-4-85 2 11-15-77 DC-1605 REY. 1 DC-1605. REV. O. 3-29-85 8-8-77 IRER 279-1971 ( FS t.R SER REMAREB SER REF. No. 4597.00 7.2.1.2) 4596 FOR DR5 ION IMPLEMENTATIO N 10CFR50 APP. A. GDC 10 SER REMARES SER REF. NO. 4598.00 (FSAR 7.2.2.2) 4596 FOR DRsION
- IMPLEMENTATIO N
10CFR50, APP. A. GDC 20 SER REMARR8 SRB REF. NO. 4599.00 (FSAR 7.2.2.2) 4596 FOR DESIGN IMPLEMENTATIO N
Pnde No. 48 04/03/86 IMPLEMENTATION
==============
MODULE 20 - SORTED BT REFERENCE NUMBER
======================================
DOCUMENT /FRATURE SECTION DRSIGN LAST DESIGN FIRST CONST LAST CONST FIRST REMARK 8 REF NO
===============e========== =======-e==, ================ ================ ================ ================ ============= ====r--=
10CFR50 APP. A. GDC 10 SEE REMARKS SIR REF. NO. 4600.00 (FSAR 7.2.2.2) 4598 FOR DESIGN l IMPLEMENTATIO N 10CFRSO. APP. A. GDC 15 SEE REMARK 8 SEE REF. NO. 4601.00 (FSAR 7.2.2.2) 4596 FOR DESIGN IMPLEMENTATIO N 10CFRSO. APP. A. GDC 20 SEE REMARK 8 SEE REF. NO. 4602.00 (FSAR 7.2.2.2) 4596 FOR DESIGN IMPLEMENTATIO N 10CFR50 APP. A. GDC 29 SEE REMARK 5 BER REF. NO. 4803.00 (FSAR 7.2.2.2) 4596 FOR DESIGN IMPLEMENTATIO N BTP ICSB 12 (FBAR 7.2.2.2) SEE REMARK 8 SEE REF. No. 4604.00 4596 FOR DESIGN IMPLEMENTATIO N O O O O O O O
. _ _ _ . .. . _ _ , _ 4 _ . _ . . ._ .. --..--_m. . . _ . - . . _ . _ . . - _ - - _ _ _ _ _ . _ . .._ _ _ . _
PnBe N h-. 49 - 04/03/86 IMPLEMENTATION
==============
MODULE 20 - SORTED BT REFERENCE NUMBER
======================================
DOCUMENT /FRATURR SECTION DRSION LAST DESIGN TIRST CONST LAST CONST FIRST REMARES REF NO
========================== ============ ================ ================ ================ ================ ============= ========
10CFR50 APP. A. GDC 21 SEE REMARKS 55E REF. NO. 4805.00 (FSAR 7.2.2.2) 4596 FOR DESIGN
; IMPLEMENTATIO N
IEEE 279'-1971 SECT. 4 SEE REMARK 5 SEE REF. NO. 4606.00 (FSAR 7.2.2.2) 4596 FOR DESIGN IMPLEMENTATIO 4 10CFR50 GDC 21 (FSAR SEE REMARKS SEE REF. NO. 4607.00 7.2.2.2) 4596 FOR DESIGN IMPLEMENTATIO N] 10CFR50 APP. A. GDC 22 BER REMARES SEE REF. NO. 4608.00 (FSAR 7.2.2.2) 4596 FOR DESION IMPLEMENTATIO N 10CFR50 APP. A. GDC 23 16AA02-225. REY. X6AA02-225. REY. 4809.00 (FSAR 7.2.2.2) 9 0 10CFR50 APP. A. GDC 4 BEE REMAREB SEE REF. No. 4611.00 (F5AR T.2.2.2) 4596 FOR DESIGN IMPLEMENTATIO N 1 I i 1 i
PnBe No. 50 04/03/86 IMPLEMENTATION
==============
MODULE 20 - SORTED BT REFERENCE MUMBER
=================.....===...======....
DOCUMENT / FEATURE SECTION DRSION LART DESIGN FIRST CONST LAST CONST FIRST REMARK 5 REF NO ====-====-===============- .=-====,=-== .-===-====-=-=== ................ =======......... ................ ====...==.... ..=..... 10 C F R 50.. APP. A. GDC 21 SEE REMARKS SEE REF. NO. 4612.00 (FSAR 7.2.2.2) 4596 FOR DESIGN L IMPLEMENTATIO N 10CFR50, APP. A. GDC 22 SEE REMARK 5 SEE REF. NO. 4613.00 (FSAR 7.2.2.2) 4596 FOR DESIGN IMPLEMENTATIO N 10CFR50 APP. A, GDC 24 SEE REMARKS BEE REF. NO. 4614.00 (FSAR 7.2.2.2) 4596 FOR DESIGN IMPLEMENTATIO N IEEE 279-1971 SECT. 4.7 SEE REMARK 8 SEE REF. NO. 4615.00 (FSAR 7.2.2.2) 4596 FOR DESIGN IMPLEMENTATIO N IEEE 279-1971 (FSAR SEE REMARKB SEE REF. NO. 4616.00 7.2.2.2) 4596 FOR DESIGN IMPLEMENTATIO N O O O O O O O
. ._..m. .
Pege N o- 51 01/03/86 IMPLEMENTATION
. ==============
MODULR 20 - SORTED BT REFERENCE NUMBER
-===== =============== ===============
DOCUMENT / FEATURE SECTION DESIGN LAST DESIGN FIRST CONST LAST CONST FIR 57 REMARES REF NO .-=====e=-===============, ============ e==============- ================ ================ ================ ============= ===- --= IEER 338-1975 (FSAR SEE REMARES SER REF. NO. 4617.00 7.2.2.2) 4596 FOR DESIGN q IMPLEMENTATIO. N 10CFR$0, APP. A. GDC 21 SEE REMARES SEE REF. NO. 4618.00 (FSAR 7.2.2.2) 4596 FOR DESIGN IMPLEMENTATIO N IEEE 33d-1975 (FSAR DC-1000-J. REY. DC-1000-J. REV. 4619.00 7.2.2.5) 4, 4-4-85, 2, 11-lF-77 DC-1605, REV. 1 DC-1605 REY. O, 3-29-85 R-8-77 RG 1.11 (FSAR 7.3.1.1) DC-2415. REY. 1. DC-2415 REV. O, 4626.00 5-16-83 3-23-78 i WCAP 8760 (FSAR 7.3.1.2) SEE REMARES BEE REF. NO. 4635.00 4319 FOR DESIGN IMPLEMENTATIO N IEEE 279-1971 (FSAR DC-1000-J, REY. DC-1000-J REY. 4636.00 7.3.1.2) 4, 4-4-85, 2, 11-15-77, DC-1620 REV. 2. DC-1620, REY. O, 3-29-83 7-1-77
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DOCUMENT / FEATURE SECTION DESIGN LANT DESIGN FIR 5T CONST LAST CONST FIRST REMARES REF NO eer==eseeeee=eeze-====:e erre-=ee=e== - e-e-====e=reee ==============e= ================ ================ ============= ======== 10CFR50 APP. A. GDC 21 SEE REMARES SEE REF. NO. 4637.00 (FSAR 7.3.1.2) 4636 FOR DESIGN t IMPLEMENTATIO N 10CFR50, APP. A. GDC 23 SEE REMARES BEE REF. NO. 4638.00 (FSAR 7.3.1.2) 4636 FOR DESIGN IMPLEMENTATIO N IEEE 279-1971 (FSAR SER REMARES SEE REF. NO. 4619.00 7.3.1.2) 4636 FOR DESIGN IMPLEMENTATIO N IEEE 279-1971 SECT. 4.12 SEE REMARE8 SEE REF. NO. 4640.00 (FSAR 7.3.1.2) 4636 FOR DESIGN IMPLEMENTATIO N RG 1.62 (FSAR 7.3.1.2) BER REMARK 5 SEE REF. NO. 4641.00 4636 FOR DESIGN IMPLEMENTATIO N O O O O O O O
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DOCUMENT /FRATURR SNCTION DRSIGN LAST DESIGN FIR 8T CONST LAST CONST FIR 87 REMARES REF NO
==========-==-me=======e== ==e========= ====== ========= ================ ================ ================ ============= ==== --.
IEER 279-1971 SECT. 4.12 SEE REMARKS SEE REF. NO. 4642.00 (FSAR 7.3.1.2) 4636 FOR DB8 ION i
; IMPLEMENTATIO N i RG 1.7 (FSAR 7.3.3.2.5) DC-1513 REY. O. DC-1513. REY. O. 4843.00 6-3-83 6-3-83 -
IEER 279-1971 (F8AR DC-1000-J, REY. DC-1000-J. REY. d644.00 7.3.3.2.C) 4, 4-4-85 2 11-15-77 DC-1513. REY. O. DC-1513. REY. O. 6-3-83 6-3-83 IEEE 279-1971 SECT. 3 DC-1000-J. REY. DC-1000-J. REY. 4645.00 (FSAR 7.4.1.2) 4, DC-1301. REY. 2 11-15-77
- 5. 3-29-83 DC-1301, REY. 5 3-29-83 10CFR50 APP. A. GDC 13 DC-1624 REY. 2 DC-1624. REY. 2 4646.00 (FSAR 7.4.1.2) 6-13-83 6-13-83 10CFR50, APP. A, ODC 19 SEE REMARES SEE REF. NO. 4647.00 (FSAR 7.4.1.2) 4646 FOR DESIGN IMPLEMENTATIO N
10CFR50 APP. A. GDC 34 BER REMARE8 SEE REF. No. 4648.00 (FSAR 7.4.1.2) 4646 FOR DESIGN IMPLEMENTATIO
- N 4
_ _ _ _ _ _ _ . _ _ _ _ _ _ _ ._ _ _ . _-~ _ _ _ _ _ _ . ._. ~ - _ _ _ _ _ _ _ _ _ _ _ _ . . _ _ _ _ _ _ _ _ _ _ _ _
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DOCUMENT / FEATURE SECTION DESIGN LAST DESIGN FIRST CONST LAST CONST FIRST REMARES REF NO
=====-================-== ,--==-e==== ================ ===e============ ================ ============e=== ============= ==== --
RG 1.29 (FSAR 7.4.1.2) SEE REMARES SEE REF. No. 4649.00 4646 FOR DESIGN
; IMPLEMENTATIO N
IEEE 279-1971 (FSAR SEE REMARES BEE REF. NO. 4650.00 7.4.1.2) 4646 FOR DESIGN iMPLEMENTATIO N IEEE 279-1971 SECT. 3 DC-1000-J. REV. DC-1000-J. REY. 4651.00 (FSAR 7.4.1.3) 4 4-4-65, 2 11-15-77 DC-1601. REY. 1. DC-1801. REY. O. 5-10-83 7-7-77 DC-1624 DC-1624 REY. 2 REV. O. 4-28-78 6-13-83 10CFR50 APP. A. GDC 13 DC-1624 REV. 2. DC-1624 REY. 2 4652.00 (FSAR 7.4.1.3) 6-13-83 6-13-93 10CFR50 APP. A. ODC 19 SEE REMARES BER REF. NO. 4653.00 (FSAR 7.4.1.3) 4652 FOR DESIGN IMPLEMENTATIO N 10CFR50 APP. A. GDC 34 SEE REMARES SEE REF. No. 4654.00 (FSAR 7.4.1.3) 4651 FOR DESIGN IMPLEMENTATIO N O O O O O O O
m -m-- _ ..-.m.. , - __. _ m.._ _ ._
,_ D SS 04/03/86 O O O O O IMPLEMENTATION
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MODULE 20 - SORTED BT REFERENCE NUMBER r===================================== SECTION DESIGN LAST DESIGN FIRST CONST LAST CONST FIRST REMARES REF NO DOCUMENT /FRATURE
========================== ============ ================ === ============ ================ ================ ============= === -==
' SEE REF. No. 4655.00 RG 1.29 (FSAR 7.4.1.3) SEE REMARES 4651 FOR DESIGN
; IMPLEMENTATIO N
1RRE 279-1971 (FSAR BEE REMARES SEE REF. No. 4656.00 7.4.1.3) 4651 FOR DESIGN IMPLEMENTATIO N 10CFR50 APP. A, GDC 19 DC-1624 REY. 2 DC-1624 REY. O. 4657.00 (FSAR 7.4.3.1) 6-13-83 4-28-78 IERE 279-1971 (FSAR SEE REMARES SER REF. No. 4658.00 7.4.3.1) 4657 FOR DESIGN IMPLEMENTATIO N SHUTDOWN PNL8 ARE DESIGNED SER REMARES REE REF. NO. 4680.00 TO ACHIEVE COLD SHUTDOWN 4657 FOR WHERE OFF8ITE POWER IS DESIGN AVAILABLE AND WHERE IMPLEMENTATIO OFFSITE POWER 15 NOT N f, ' AVAILABLE FOR 72 N (FSAR i 7.4.3.1) l j f l 1 i i _ . - - _ _ _ - _ _ . - _ - - . . - _ _ _ _ . - _ _ _ - - . _ _ _ - - - _ _ _ - - - v- _ _ - _ - - _ - - _ - _ - . _ _ - - - - - - _ _ - _
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========e====================== ======
DOCUMENT / FEATURE SECTION DESIGN LAST DESIGN FIRST CONST LAST CONST FIRST REMARES REF NO
== ======-===-=========e=e ====-==-==== ========--====== ================ ================ ================ ============= ====== =
10CFR50, APP. A. GDC 19 SEE REMARKS SEE REF. NO. 4661.00 (FSAR 7.4.3.2.A) 4657 FOR DESIGN t IMPLEMENTATIO N R0 1.29 (FSAR 7.4.3.2.8) DC-1624 REY. 2 DC-1624 REY. O, 4602.0C 6-13-83, 4-28-78 DC-1005, REV. 1 DC-1005, REY. O, 4-4-85 3-10-80 IEEE 279-1971 (FSAR SEE REMARK 5 SEE REF. No. 4663.00 7.4.3.2.C) 4651 FOR DESIGN IMPLEMENTATIO N BTP CME 8 9.5-1 REQ.C.5.C SEE REMARK 5 8EE REF. NO. 4664.00 (FSAR 7.4.3.3) 4657 FOR DE8IGN IMPLEMENTATIO N SHUTDOWN PNLS DESIGNED TO SEE REMARK 5 SEE REF. No. 4665.00 A COINCIDENT SINGLE 4651 FOR FAILURE & SSR (FSAR DESIGN 7.4.3.1) IMPLEMENTATIO N O O O O O O O
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SECTION DESIGN LAST DESIGN TIRST CONST LAST CONST FIRST REMARKS REF NO DOCUMENT / FEATURE
====================== === ============ ================ ================ ================ ================ ============= =====- =
SWITCHES WILL BE PROPERLT LETTER BO-10245 LETTER B0-10245, 4667.00 QUALIFIED OR CONTROL CRTS 7-7-80 7-7-80 WILL BE REDESIGNED (I.E.B. CORRES. C-78/04/21) ; REPAIR VALVES WITH NAMCO FILE X7BC24, FILE 17BC24, 4673.00 EA180 POS. SW WITH SW BO-10254, 7-7-80 M-1032, 2-19-80 HOUSING NUMBERS BETWEEN 01-79 AND 08-79 PLACING VALVES ON HOLD UNTIL REPAIR Is COMPLETE (I.E.B. i CORRES. C-80/08/05) DESIGNED TO WITHSTAND DC-2415 REV. 1, DC-2415. REY. I. 4779.00 CONTA. PRESSURE & 5-16-83 5-16-83 TEMPERATURE COND. FOLLOWING LOCA (FSAR 6.2.4.1) i DESIGNED TO WITHSTAND SEE REMARES 8EE REF. NO. 4780.00 DYNAMIC EFFECTS (FSAR 4779 FOR 6.2.4.1) DERIGN 4 IMPLEMENTATIO N i, DESIGNED TO REMAIN SER REMARE8 SER REF. NO. 4781.00 j FUNCTIONAL FOLLOWING SSE 4779 FOR DESIGN IMPLEMENTATIO N ? g 8 I 1 I
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SECTION DESIGN LAST DESIGN FIRST CONST LAST CONST FIRST REMARES REF NO DOCUMENT / FEATURE
========================== =======-==== =====e=======-== ================ ================ ======== ======= ============= =====- =
SPEC. X4AE01, SPEC. I4AE01, 4789.00 NRC QUEST. CORRES. (Q 430.33) REV. 7 DC-2403, REV. 7 DC-2403, REV. 3, 5-2-79 REV. 3, 5-2-79 i DC-1625 REV. 1 DC-1625 RET. O, 4801.00 RG 1.47 (FSAR 6.3.2.2.17) 8-2-83 2-5-79 VITAL AC - NO SINGLE DC-1605, REY. 1 DC-1605, REY. O, 4803.00 FAILURE SHALL CAUSE A LOSS 3-29-83 8-8-77 0F PONER SUPPLY TO MORE THAN ONE DISTRIBUTION PNL (FSAR 7.1.2.1) DC-1000-J. REY. DC-1000-J. REV. 4804.00 IRRE 279-1971 (FSAR 7.1.2.1) 4, 4-4-85, 2, 11-15-77, DC-1605, REY. 1 DC-1605, REV. O, 3-29-83 8-8-77 DC-1000-J. REY. DC-1000-J. REY. 4805.00 IEEE 279-1971 SECT. 4.6 (FSAR 7.1.2.2) 4, 4-4-85, 2, 11-15-77 DC-1601, REY. 1 DC-1601, REY. O, 5-10-83 7-7-77 DC-1624 REY. 2. DC-1624. REV. O, 4806.00 RG 1.22 (FSAR 7.4.3.2.B) 6-13-83 4-28-78 DC-1623. REV. 1. DC-1623. REV. 1, 4807.00 RG 1.105 (FSAR 7.5.2.3) 5-23-83 6-23-83 O O O O O O O
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DOCUMENT [ FEATURE SECTION DESIGN LAST DESIGN FIRST CONST LAST CONST FIRST REMARES REF NO
-========-e=============== ============ ================ ================ ================ ================ ============= ====r =
RG 1.6 (FSAR 7.6.1.2) DC-1000-E, REV. DC-1000-E, REY. 4808.00 6, 8-29-85 2, 12-13-77 . VITAL AC - NO SINGLE DC-1605, REV. 1 DC-1605, R E,V . O. 4809.00 FAILURE IN THE I&C POWER 3-29-83 8-8-77
- SUPPLT SYSTEM OR ASSOCIATED POWER SUPPLIES 3
CAN CAUSE LOSS OF POWER TO MORE TRAN ONE OF THE l REDUNDANT LOADS (FSAR j 7.6.1.2) ALL CLASS IE MOTOR SPEC. X5AC01 SPEC. X5AC01, 4822.00 O PE RI. f E D VALVE ACTUATORS APP. AD-5, REY. APP. AD-5, REY. ARE SPECIFIED WITH ACCES. 2, 5-4-79 0 CAPABILITY AT 754 NAMEPLATE (FSAR 8.3.1.1) IEEE 344-1975 (FSAR DC-1000-J. REV. DC-1000-J. REY. 4872.00 s 12.3.4.1) 4, 4-4-85, 2, 11-15-77, j DC-1609 REY. 1 DC-1609, REY. 1. i 4-21-83 4-21-83 IEEE 336-1971 (FSAR DC-1623 REY. 1. DC-1623. REY. O, 4873.00 , 12.3.4.1) 6-23-83 7-7-77 IEEE 279-1971 (FSAR SEE REMARES SEE REF. NO. 4874.00 l 4872 FOR
- 12.3.4.1)
BREIGN IMPLEMENTATIO l N 1 i l 4 5 i 1
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DOCUMENT /FRATURE SECTION DRSION LA87 DESIGN FIRST COMBT LAST CONST FIRST REMARE5 REF NO
-=-====-====-=======....== === ........ ===== .=== ... . ........=====,.= ..............== ===..=== ....... ............= ====r--.
IERE 308-1974 (FSAR SEE REMARES 8EE REF. NO. 4875.00 12.3.4.1) 4872 FOR DESIGN t IMPLEMENTATIO N IEEE 323-1974 (FSAR BER REMARK 5 BER REF. PS. 4876.00 12.3.4.1) 4872 FOR DESIGN IMPLEMENTATIO N IEEE 384-1974 (FSAR SEE REMARK 8 SEE REF. NO. 4877.00 12.3.4.1) 4872 FOR DESIGN IMPLEMENTATIO N NUREG-0737 (NRC QUEST. DC-1609 REY. 1. DC-1609. REY. O, 4896.00 CORRES. 0460.08) 4-21-83, 3-17-78, DC-2702, REY. O. DC-2702, REY. O, 1-20-82 1-20-82 NUREG-0737, II.B.1, ITEM 8 DC-1201, REY. 2. DC-1201, REY. 2, 4903.00 (NRC QUEST. 0420.40 3-9-84 3-9-84 CORRES.) RADIATION DETECTOR IS MTD DC-1609 REY. 1. DC-1609 REY. O, 4905.00 IN THE RETURN LINE TO THE 4-21-83 3-17-78 TOWER TO ENSURE RADIATION NOT PRESENT IN SYSTEM (FSAR 9.2.1.5) O O O O O O O
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DOCUMENT /FRATURE SECTION DESIGN LAST DESIGN FIRST CON 57 LAST CONST FIRST REMARR5 RRF NO
========================== ============ me============== ================ ================ ================ ============= ========
10CFR50, APP. A. GDC 54 DC-24t5 REV. 1 DC-2415 REY. O, 4908.00 (FSAR 9.3.2.1) 5-lC -83 3-23-78 10CFR50, APP. A, ODC 55 SER REMARES ; SER REF. NO. 4909.00 (FSAR 9.3.2.1) 4908 FOR BR5IGN IMPLEMENTATIO N 10CFR50, APP. A, ODC 56 SER REMARE8 SER REF. NO. 4910.00 (FSAR 9.3.2.1) 4908 FOR DESIGN IMPLEMENTATIO N 10CFR50, APP. A. GDC 15 DC-1000-J. REV. DC-lOOO-J. REY. 4959.00 (FSAR 7.1.1-1) 4, 4-4-85, 8-29-83 DC-1201, REV. " '"1201. RET. O, 3-9-84, DC-160L_ 11-78 REV. 1, 3-29-83 DC-1605. REY. 1, 8-8-77 ASMR CODR, SECT. III, 1977 FPP II-40, REV. PPP IX-40, REY. 5028.00 ED THRU WINTER 1977 09/69/85 X-18, 01/12/84 I-18, ADDENDA REV. 11/15/85 REY. 02/02/84 ANSI B31.1 CODR, 1977 PPP II-40, REY. PPP II-40. REY. 5027.00 EDITION THRU WINTER 1977 09/09/85, X-18, 01/12/84, 1-18 ADDENDA REY. 11/15/85 REY. 02/02/84
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DOCUMENT /FRATURR SRCTION DRSIGN LAST DESIGN FIRST CONST LAST CONST FIRST REMARES REF NO
=e- = == se=============-= ====ee,===== ================ ===e============ ================ ================ ============= ========
AWS DI.1-1975 PPP II-40 REY. PPP IX-40, REY. 5028.00
- 09/09/85, R-18, 01/12/84, X-18 REY. 11/15/85 REY. 02/02/84
( ASME III, CLASS 2& 3 SEE REMARES SEE REF. NO. 5034.00 (FSAR 3.2.2.4) 322 FOR DESIGN IMPLEMENTATIO N
)
BTP ICSB 4 (FSAR 7.6.4A) X6AA02-230-7 I6AA02-230-7 5035.00 ASMR III-3 (FSAR 3.2.2-1) SEE REMARES SEE REF. No. 5036.00 865 FOR DESIGN IMPLEMENTATIO N ASME III-2 (FSAR 3.2.2.-1) SEE REMARES SEE REF. NO. 5037.00 865 FOR DESIGN IMPLEMENTATIO i N O O O O O O O
4.0 PROGRAM DESCRIPTION iO: i This section describes the work processes for the design and )' construction of instrumentation and controls (I&C). It describes the control mechanisms that ensure the quality and
- integrity of the I&C design and construction program.
The programs for design, procurement, and construction are described in the following sections: 4.1 - Design. 4.2 - Equipment and Material. 4.3 - Site Material Control. 4.4 - Fabrication, Installation, Inspection, and Testing. I O ~
.i O
1
. O O
0076t/092-6
4.1 DESIGN This section describes the preparation, control, review, and change control of safety-related (Q-Class) instrumentation and control (I&C) design documents. The preparation and revision of the design criteria, I () specifications, data sheets, drawings, and other design documents are illustrated in a simplified flow diagram Design criteria were prepared to provide the j (Figure 4.1-1). i bases from which the I&C design is controlled. The Regulatory Guides, codes, standards, calculations, and operating plant experiences were utilized to determing I&C requirements. ' l () Drawings, specifications, data sheets. and reports were prepared to facilitate construction, procurement, and licensing l activities, as well as subordinate engineering design functions. 4.1.1 DESIGN CRITERIA This section covers the criteria documents that govern the Vogtle Project design of safety-related I&C. Design criteria were initially provided in the Preliminary Safety Analysis Report (PSAR), which was prepared by the Vogtle Project and submitted to the Nuclear Regulatory Commission (NRC) in August 1972. Subsequently, detailed design criteria were developed and issued as part of Vogtle Project Design Manual. ( The criteria contained in the Design Manual are organized into sections as follows: j A. General Plant Criteria l The general plant criteria were issued as the Physical Plant Design Criteria on December 12, 1974. This l document provides the overall plant physical protection, as well as maintenance and serviceability, criteria. l The protection criteria provide acceptable design bases for the protection of systems and equipment important to safeguard against postulated events or hazards. The maintenance and serviceability criteria define the design bases pertinent to the development of the (")T
\- general plant arrangement.
i
I B. Interdiscipline Design Criteria The interdiscipline design criteria provide design bases having multidiscipline applicability. Table 4.1-1 lists the interdiscipline design criteria applicable to this module and the initial issuance date. C. Discipline General Design Criteria The General Control System and Civil / Structural Design Criteria (DC-lOOO-J and DC-1000-C) were first issued on May 10, 1973, and February 28, 1974. The control system criteria summarize the principal functions and safety design bases pertaining to the functional and g physical parameters of I&C design. The civil / structural criteria provide bases for the structural design of safety-related instrument installation details. D. System Design Critoria The system design criteria provide detailed criteria (e.g., principal function, safety design bases, etc.) for each plant system. Table 4.1-2 lists the system design criteria applicable to this module, the material covered, and the initial issuance date. The design criteria control and review process is performed in accordance with the procedures established in preface sections 1, 2, and 3 of the Design Manual. The Project Administration Group retains (files) and publishes the design criteria. 4.1.2 DRAWINGS AND DOCUMENTATION Based on the established design criteria and Bechtel Power Corporation (BPC) design guides / standards, drawings, and documentation were prepared to describe the design in detail sufficient to facilitate engineering, fabrication, and installation functions. This section describes the drawings and documentation specifically prepared for the control systems covered by this module. Design control and review of these documents are also addressed. 4.1.2.1 Calculations O Calculations for installation of safety-related instruments and associated sensing lines were prepared to determine allowable instrument weight on stand or plate and unsupported span of g i instrument sensing lines. The design calculations were W prepared based on actual conditions (where known; otherwise, 4.1-2
i l I
)
conservative conditions were assume-d), actual design drawings, (' and licensing requirements. Input data for the calculations were obtained from plant material suppliers, industry i standards, and BPC design guides / standards. Calculations pertaining to this module are summarized in Table 4.1-3. The BPC Home Office Engineering (HOE) Control Systems Group has : O principal responsibility for the preparation and control of the I&C design calculations listed in Table 4.1-3. The calculations are controlled and reviewed in accordance with the procedures established in the VEGP PRM, part C, section 9. 1 () 4.1.2.2 Drawings I&C drawings diagramatically describe the design of the plant 1 1&C system as stated in section 7.0 of DC-1000-J. Drawings l applicable to the safety-related I&C include instrument data sheets, logic diagrams, loop diagrams, instrument location l drawings, instrument installation details drawings, and level 1 setting diagrams. Design drawings are prepared, reviewed, and controlled in accordance with the procedures established in the VEGP Project Reference Manual (PRM), part C, section 4. (The design drawing review and control process is illustrated in Figure 4.1-2.) O 4.1.2.2.1 Data Sheets Instrument data sheets are standard forms prepared to define the design requirements for control valves and process instruments. Instrument data sheets are developed and maintained by the HOE Control Systems Group. 4.1.2.2.2 Logic Diagrams Logic diagrams provide functional logic for the operation of the equipment to meet design requirements. Subsequently, logic s ,j diagrams are used by the Electrical Group to develop the elementary diagrams. Logic diagrams are developed and maintained by the HOE Control Systems Group and have primary interfaces with the Electrical, Mechanical, and Nuclear l Groups. O 4.1.2.2.3 Loop Diagrams Loop diagrams show how I&C is physically interconnected (wiring or tubing). They generally involve analog systems. However, digital inputs and outputs are shown when required to clarify O system functions and to delineate interfaces with other systems. Their content may be pneumatic, electrical, or a 4.1-3 l _ _
combination. Loop diagrams are developed and maintained by the HOE Control Systems Group. The primary interface is with the Electrical Group, which uses these drawings to develop wiring diagrams for the instruments and controls. 4.1.2.2.4 Instrument Location Drawings Instrument location drawings show the physical location of the instruments. These include independently mounted instruments, local panel-mounted instruments, and main control board-mounted instruments. As applicable, instrument sensing lines are approximately shown and instrument services (electrical, pneumatic, etc.) are indicated on the drawings. The g responsibilities for the instrument location drawings have been W transferred to Project Field Engineering (PFE), which maintains and updates these drawings. These drawings are interfaced with those of Vogtle-Structural Analysis Mobile Unit (V-SAMU) and Pullman Power Products (PPP), which provide isometric drawings for installation of tubing and instrumentation. 4.1.2.2.5 Instrument Installation Detail Drawings Instrument installation detail (IID) drawings show in detail the installation of instruments based on their types, such as pressure, differential pressure, level, etc. On each drawing, a table of the instrument tag numbers applicable to the drawing is included. The IID drawings are developed and maintained by the HOE Control Systems Group. The purpose of these drawings is to provide diagrammatic routing for instrument sensing lines. These drawings are used by the PFE Control Systems Group, V-SAMU, and PPP for development of isometric drawings in the field. 4.1.2.2.6 Level Setting Diagrams Level setting diagrams are used to record: o The elevations and ranges of instruments used to llh measure and control level. o The elevations of associated vessel parts. Level setting diagrams are developed for each vessel (i.e., i storage tank, heat exchanger, etc.) depicting the level i settings for all level instrumentation associated with that vessel. Level setting diagrams are developed and maintained by the HOE Control Systems Group. These diagrams are used for development of isometric drawings by V-SAMU for installation of instruments and instrument setpoint calibration after installation. 4.1-4
l l 4.1.2.3 Procurement Specifications l O I&C procurement specifications define the technical requirements, special instructions, data, and other information describing the items or services procured, along with l requirements for installation. The BPC HOE Control Systems Group is responsible for preparing and controlling I&C procurement specifications in accordance with the PRM, part C, O section 8. The procurement specifications applicable to this module are listed in Table 4.1-4. 4.1.2.4 Construction Specifications () Construction specifications are generated to give specific instructions for field construction activities. As shown in Table 4.1-5, construction specifications applicable to this module are X4AZ01-P1 (General Requirements) and X4AZ01-P2 (Instrument Installation). Construction specification control and review were performed in accordance with the procedures established in the VEGP PRM, l part C, section 26. l l 4.1.2.5 Desion Specifications IvO Design specifications provide the complete basis for the l construction of components as required by the American Society l of Mechanical Engineers (ASME) Boiler and Pressure Vessel (B&PV) Code, section III. Design specifications for all ASME B&PV Code, section III, components, parts, appurtenances, and piping systems are listed in the ASME design specification matrix (document No. X4P0005). Design specifications are prepared in accordance with the PRM, part C, section 29. Table 4.1-5 lists the design , specifications applicable to this module. l 4.1.2.6 Tubino Isometrics and Support Drawinos There are two types of isometric drawings developed for installation o-f instrument sensing lines: A. A type A isometric drawing is developed by PPP based l upon BPC standard drawings. This isometric drawing covers installation from the instrument isolation valve to the instrument. B. A type B isometric drawing is developed by V-SAMU O based upon information provided by BPC. This drawing 4.1-5
covers installation from the root valve (process pipe) to the instrument isolation valve. This drawing includes the location of tube clamps for tubing support. lh V-SAMU has provided standard support drawings to support the instrument tube clamps and the instrument tube clamps and the instrument mounting plates or stands. The standard support drawings are utilized by PPP and are identified on the two isometric drawings discussed above. The calculations required for the instrument sensing lines (type B) are performed by V-SAMU. Before installation, V-SAMU provides flexibility analysis verifying proposed routing of sensing lines. After as-installed isometric drawings are g i issued, V-SAMU provides final calculation for the instrument W sensing line installation. Appendix 2, section 9, of the PRM provides the program description for organization and maintenance of piping, pipe supports, and instrument tubing drawings. 4.1.3. DESIGN VERIFICATION REVIEWS Design verification reviews were systematically performed'to ensure that equipment, systems, and structures were properly ! designed and that the designs were properly coordinated. Design verification reviews were performed by BPC in accordance with the criteria established in the Design Manual, preface, section 4. These criteria provide guidance supplemental to the VEGP PRM, part C, section 20, Design Review Procedure. The Design Manual criteria define the review procedures, including requirements establishing the division of responsibility for preparing and reviewing design verification review packages, requirements for design review meetings, and requirements for the report documenting the design review. to the Design Manual, preface, section 4, tabulates the division of responsibility for all disciplines, including the Controls Discipline. O 4.1.4 DESIGN CHANGE CONTROL Design changes for I&C documents and drawings are realized by , issuing Document Change Notices or Interim Design Change l Notices (IDCNs), or by approving Field Change Requests (FCRs). lh l Changes may be initiated by Engineering or Construction, or they may be the result of a Nonconformance (Deviation) Report. Changes may be approved only by the design engineering organization having responsibility for the document. 4.1-6
._ . -_- - - .. - _ . . . _ _ _ - - ~_- -
l l I i 4.1.4.1 Encineerino-Initiated Chances 4.1.4.1.1 Design Document Revision The procedures for design document revisions are essentially identical to the procedures followed for their initial () issuance, which are described in section 4.1.3. The major differences are that a different review process may have been i followed due to the limited scope of a minor revision or (in l the case of incorporating change notices) that the change may l a.1 ready have been reviewed. ' l t O 4.1.4.1.2 Design Manual (Design Criteria) Change Notices Changes to project design criteria are controlled through the l issuance of Design Manual Change Notices (DMCNs). DMCNs are controlled in accordance with the procedures established in the preface, section 3.7, of the Design Manual. 4.1.4.1.3 Drawing Change Notices Changes to drawings are controlled through the issuance of Drawing Change Notices (DCNs). DCNs are controlled in O accordance with the procedures established in the VEGP PRM, part C, section 4.8. 4.1.4.1.4 Specification Change Notices Changes to procurement specifications or construction specifications are controlled through the issuance of Material Specification Change Notices (MSCNs) or Construction Specification Change Notices (CSCNs) in accordance with the PRM, part C, sections 8 and 76, respectively. 4.1.4.2 Field-Initiated Chances FCRs afford a means for Construction to obtain changes to design drawings or specifications as conditions warrant. The change may be requested due to interferences, drawing discrepancies, changes in arrangements required by job O conditions, etc. Within the design organization, FCRs are controlled in accordance with the procedures established in the PRM, part C, section 17. 1 In addition to FCRs, greenlining is used to make changes to V-SAMU-routed ASME instrumentation tubing. Greenlining is not O permitted for changes that deviate from code, specification, or instrument installation detail drawing requirements. 4.1-7 I- _a
I l Greenlining is also not permitted for changes to instrument ' locations or instrumentation standard supports. l l This greenlining procedures is described in the PRM, Appendix 2, section 19. i 4.1.5 NONCONFORMANCE CONTROL 1 l l Deviation Reports (DRs) are prepared by GPC Engineering Quality l Control, or contractors, to report deficiencies in material, documentation, or procedures identified during the construction phase of the project. Within the design organization, DRs are controlled in accordance with the procedures established in the PRM, part C, section 18. l i O O O 0062t/093-6 4.1-8
TABLE 4.1-1 INTERDISCIPLINE DESIGN CRITERIA . s ) Designation initial Principal j Number issue Title and Description Responsibility i DC-1001 01-24-78 Separation - This document provides design bases to ensure that systems, Plant Design
- components, a.d structures important to safety are adequately separated.
l 2 DC-1003 01-12-78 riooping - This documnnt provides design bases to ensure that safety- Nuclear
- related systems and structures are protected against flooding caused by i fastulated pipe breaks or activation of the fire protection system.
} DC-1005 03-10-80 Seismic - This document provides bases for designing systems, structures, Civil / l and equipment having safety impact to withstand seismic events. Structural I DC-1006 12-19-77 Missiles - This documord presents the criteria for analysis of internally Nuclear
- generated missile hazards.
4 i DC-1007 06-06-79 Environmental - This document provides design bases for environnentally Nuclear j qualifying safety-related equipment to ensure that it will perform its j required safety functions during normal, abnortnal, test, accident, and i post-aceIdent conditions. DC-1010 08-04-78 Project Classification List - This document lists significant structures, Nuclear i components, and systems. . 4 , DC-1018 01-25-79 Pipe Break Effects Criteria - This document defines the criteria to be Nuclear I used for determining the assumed pipe break locations and the types of [ failures and their effects. 1 t t i } , 0003t/084-6/2
m . . . . . _ _ . . ._ .__ _ ._..... m.~ . _ .. - . . . - - ...._. . .___. - m.. . _ . . _ _ . _ _ _ _ . _ . _ _ _ _ . . _ . . _ . O . o > o TABLE 4.1-2 (SilEET I Or 2) SYSTEM DESIGN CR11ERIA Designation Initial Principal Material Number issue Title and Function Responsibility Covered i DC-1620 07-01-71 Engineered Safety features Actuation System - This system (ESFAS) BPC - Control Sensing devices, , is provided to sense an accident situation and to initiate System panels, cabinets, operation of the necessary equipment to mitigate the accident. modules, etc. DC-1621 10-13-77 Reactor Instrumentation - This system interfaces with other systems BPC - Control flux measurement, to provide reactor control and reactor power level during startup, System (M) source range shutdown, and power operation. detectors, reactivity monifors, etc. DC-1622 10-11-77 Reactor Control System - This system provides the operator with the BPC - Control DNBR ratio, ability to bring the reactor critical and provide reactor control System (y) temperature from low power to 15-percent power output. deviation, turbine first stage pressure, turbine runback, etc. DC-1623 07-07-77 Post-Accident Monitorina System - This system provides information BPC - Control Q-Class and non-regarding the plant variables required by control room operating System Q-Class plant personnel during normal, abnormal, and accident situations, for instruments. safe reactor operation. DC-1624 04-28-78 Plant Auxiliary Control Boards - These boards are used to provide BPC - Control Auxiliary control plant with system control or duplicate certain main control board Systems boards, functions to permit operators to control plant systems from various locations. i 0063t/084-4 3 ; __...-_--_m .__ _ _ _ _o_m.____..__.___m.m__--. .._.._m _.L:-_ _ _ _ ____._t__ _ _ _ . . _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ - . -- _ _ _ . _ _ - _ . _ _ _ _ _ _ . _ . .
- _ m___.._e.__-___ m ._-_..___ ___.___.. .___ ____.w____ .____.u_____._m..__._____u__.2-__--.___._____-__mm___ ._____._.....-_ .__m
O TABLE 4.1-2 (SilEET 2 0F 2) Designation initial Principal Material Number issuo Title and function Responsibility Covered , DC-1625 02-05-79 Safoty-Related Systems Dypass/ Inoperable Status and Trip /Monitorina BPC - Control Bypass / inoperable Indicatina Lights - This display system provides the trip status, Systems. status panel. ESF monitoring, and system status indication of safety syst m to the control room operator. DC-1601 07-07-77 Main Control Board - The main control board houses instruments BPC - Control Display, control, which are used for operating the plant and displaying Systems alarm, and important parameiers. computer functions. DC-1602 10-1l-77 Nuclear instrumentation System - The neutron flux is monitored for BPC - Control Source, interme-safe operation of reactor over the whole range of reactor Systems diate, and power operation. (idestinghouse signals necessary (M) ] for reactor over-power protection. DC-1604 10-03-77 Process Control System - Process instrumentation which measures BPC - Control Process measuring process variables, consists of measuring devices, power supplies, System (M) Instruments, Indicators, controllers, signal conditioning devices, etc. Indicators, controllers, etc. DC-1605 08-06-77 Protection System NSSS - The protection system encompasses all BPC - Control Reactor, electrical and mechanical devices and circuitry involved in System (M) generator, and generating the protective function. pressurizer instrumentation and controls. DC-1609 03-17-78 Radiation Monitorina System - This system monitors radiation BPC - Control Plant area, level in certain process fiulds, effluent paths, or areas. The System (M) ef fluent, and system also provides indications, records, alarms and controls. process radiation. DC-2415 03-23-78 Containment Isolation System - This system allows the normal or BPC - Control Valves, closed emergency passage of fluids through the containment boundary System piping system, while preserving the ability of the boundary to prevent or limit ' blind flanges. 0063t/004-6/4 escape of fission products from postulated accident-s.
I l TABLE 4.1-3 O INSTRUMENTATION AND CONTROLS CALCULATIONS Date of Calculation Initial Project No. Issue Calculation Title Classification l O X5CP8102-1 6/22/82 Maximum unsupported tubing span 212 l X5CP8203 12/16/81 Floor-mounted instrument support 212 . and baseplate l X5CP8205 12/16/81 Design of structural members to 212 support instrument mounting plate assembly X5CP8212 2/15/83 Instrument mounting plate 212 attachment X5CP8303 12/15/81 Transmitter mounting assembly 212 1 X5CP8305 5/11/83 Barton pressure transmitter 212 l mounting X5CP0005 12/4/81 Instrument tubing support 212 i .O I O ! lO ,O 0065t/092-6/1
l( ) TABLE 4.1-4 PROCUREMENT SPECIFICATIONS Specification Specification Title
-( ) No.
X5AF02 Level - Float Switches X5AB01 Miscellaneous Control Panels X5AC05 Safety Valves and Relief Valves X5ACl3 Atmospheric Steam Dump Valves i X5AA05 Containment Hydrogen Monitoring l Equipment i X5AA06 Post Accident Sampling System X5AC01 Nuclear Service Control Valves X5AC07 Nuclear and Non-Nuclear Solenoid Valves X5AC08 General Service Control Valves X5AD04 Pressure Transmitters X5AD05 Differential Pressure Transmitters X5AD07 Level and Pressure Transmitters X5AE06 Thermometers, Thermal Elements and Thermowells X5AG02 Orifice Plates and Flow Assemblies () X5AG00 Instrument Valves ! X5AG15 Instrument Tubing and Fittings X5AG16 Flexible Metal' Hoses and Hose Assemblies F O O - . 0065t/092-6/3
I TABLE 4.1-5 (~'\
'" CONSTRUCTION / DESIGN SPECIFICATIONS Date of Specification Initial Constr/ Design Specs Project No. Issue Title and Description Classification ,-]
X4AZ01-P1 9/3/74 General Requirements N/A X4AZ01-P2 9/3/74 Instrumentation - Installation 212 of Instrument Piping, Tubing j
,e 3 and Instrument Hookup l
U X4AP0003 4/30/80 Instrumentation Sensing Line 212 I l l 1 I l I (s 1 n V tr,) , 0065t/092-6/2
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i l l l 4.2 EQUIPMENT AND MATERIAL Safety-related instrumentation and controls (I&C) are procured or are fabricated from material procured in compliance with specifications written and controlled by Bechtel Power Corporation (BPC). These specifications are prepared in accordance with the design criteria prepared by BPC and (} contained in the VEGP Project Design Manual. Georgia Power Company (GPC) is the purchasing agent for I&C and l material discussed in this module and supplies them to the i contractors for installation. I Detailed descriptions of the procurement process and receipt and i k -) document review are contained in Appendixes C and E. respectively. Vendor requests for approval to deviate from the requirements of i an equipment or material specification were submitted on a l Supplier Deviation Disposition Request (SDDR) form. These l requests were reviewed and approved (or rejected) by the BPC control systems group supervisor [ engineering group supervisor (EGS)]. In addition, the SDDRs approved by the EGS were i reviewed and approved by BPC Quality Engineering, the BPC project engineer, and BPC Quality Assurance (QA). The approval disposition of each request was categorized as one of the following: Accept As Is, Repair, or Modify Buyer's Requirement. O s/ : l l l l OO70t/092-6 i l l 1
l 4.3 SITE MATERIAL CONTROL () Georgia Power Company (GPC) purchases, receives, inspects, and stores instruments, equipment, and materials, including welding material required for construction at Plant Vogtle. GPC is also l designated as the material supplier for American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel (B&PV) , Code, section III, division 1, ma terial.
)
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The contractors performing instrumentation and controls I
)
installation activities within the scope of this module are Pullman Power Products (PPP) and Cleveland Consolidated. PPP requisitions and temporarily stores material required for {'j} s construction, using the guidelines of procedure VII-2. PPP also j performs receipt inspection on requisitioned ASME material as l l required by the ASME B&PV Code. The process for PPP material l l control is described in section 4. 3 of Module 4 and Module ll, i l l Material required for construction by Cleveland Consolidated is l controlled in accordance with the general site receipt inspection program. This program is described in Readiness Review Appendix E and covers receipt, receipt inspection, document review and acceptance, release for issue, storage, and I storage inspection of warehouse-controlled ma terial. l lC) lC) l 'C:) 0038t/084-6 l l
i 4.4 FABRICATION, INSTALLATION, INSPECTION, AND TESTING
) The installation and inspection of instrumentation and controls i (I&C) within the scope of this module have been delegated to two primary contractors, Pullman Power Products (PPP) and Cleveland Consolidated, with certain inspection activities performed by Georgia Power Company (GPC).
This section presents a brief description of these organizations and the applicable specifications, procedures and construction codes pertinent to I&C systems at VEGP. 4.4.1 PULLMAN POWER PRODUCTS PPP performs installation activities for instruments, sensing lines, sample lines, and associated supports, and control valves for hydro / pneumatic systems. The construction activities are governed by construction specification X4AZOl, Division P1, General Requirements, and Division P2, Instrumentation-Installation of Instrument Piping, Tubing, and Instrument Hookup. The specification includes requirements of American National Standards Institute (ANSI) B31.1, Power Piping Code, 1977, including addenda through winter 1977, and American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code, section III, division 1, 1977, including addenda p) (, through winter 1977, and section IX. A description of the PPP program for installation activities is provided in Module 4, Mechanical Equipment and Piping, and Module ll, Pipe Stress and l Supports. These activities are supplemented by PPP procedure IX-40, Instrumentation. Installation, Inspection, and Testing. 4.4.2 CLEVELAND CONSOLIDATED Cleveland Consolidated performs installation activities for control panels and electrical instruments. These activities are governed by construction specification X3AR01, section E12, Installation Procedure for Electrical Equipment, which includes requirements of ANSI N45.2-4-1972 [ Institute of Electrical and () Electrical Engineers (IEEE) 336-1971), Installation, Inspection and Testing Requirements for Instrumentation and Electrical Equipment During Construction of Nuclear Power Generating Stations. Cleveland Consolidated construction activities for I&C are !O controlled in accordance with the following GPC procedures: o GD-T-22 Installation of Instrumentation. o ED-T-04, Installation of Major Electrical Equipment. () ' A description of the Cleveland Consolidated program for installation work activities is provided in Module 6, Electrical Equipment, and is supplemented by the procedures referenced above.
l 4.4.3 GEORGIA POWER COMPANY GPC provides construction management for the installation of I&C. In addition, GPC QC is responsible for primary inspection and acceptance of work performed by Cleveland Consolidated in ! accordance with the VEGP Quality Assurance Manual and the VEGP Field Procedures Manual. A description of the GPC program is i provided in Module 6, Electrical Equipment, and in Module 12, Electrical Cables and Terminations. 1 0 1 O l O 0 0039t/093-6 4.4-2
5.0 Audits This module section contains a discussion of the Quality Assurance (QA) audit process, Nuclear Regulatory Commission (NRC) inspections, and special evaluations addressing instrumentation. (~' Throughout the Plant Vogtle construction program, onsite audits ,\ - have been performed by Georgia Power Company (GPC) QA. In addition to regularly scheduled and periodic inspections and investigations, the NRC has conducted a Systematic Assessment of Licensee Performance (SALP) evaluation and a special
~
investigation performed by the Regional Construction Assessment Team (CAT). Plant Vogtle was the first of 22 utility sites that (s)h initially participated in onsite investigations and evaluations performed by the Institute of Nuclear Power Operations (INPO). As a result of the pilot INPO program and the subsequent followup onsite investigation, the GPC Self-Initiated Evaluation (SIE) program was formed. ~ This section is divided as follows: 5.1 Design Program Audits 5.1.1 Georgia Power Company Audits 5.1.2 Bechtel Audits r- 5.1.3 Nuclear Regulatory Commission Inspections 5.1.4 Self-Initiated Evaluations 5.2 Construction Audits 5.2.1 Project Audits 5.2.2 Nuclear Regulatory Commission Inspections 5.3 Past Design and Construction Problems 5.3.1 Design Problems 5.3.2 Construction Problems The Readiness Review Team used the results of the audits. () inspections, and evaluations as an aid in developing the assessment program described in section 6.0. l 0027t/093-6 l l I
5.1 DESIGN PROGRAM AUDITS 7_ Design-related findings may result from audits of specific design activities or from audits of construction activities. If a finding er deficiency occurred in construction because the construction specification requirements were not met, it constituted a finding in construction and not design. However, (~h if the construction specification requirements did not \-) accurately reflect codes or standards or if it required clarification through revision, the finding was considered a design finding, even if the deficiency was originally discovere3 during a review of construction activities. The design program audits and the category of each finding are O' summarized in the design audit matrix at the end of this section. 5.1.1 GEORGIA POWER COMPANY AUDITS Regularly scheduled audits are conducted by GPC Quality Assurance to verify compliance with project requirements. This section describes audits addressing design-related problems and the associated findings. There were two audits with two findings applicable to ISC design activities. Audit CP01-85/29, conducted on April 19, 1985, ("' \ reviewed instrumentation but did not result in any findings. Audit GDll-81/61, performed September 11, 1981, resulted in Findings 250 and 251. Finding 250 was issued because preliminary drawings had been issued in series CX5DP002 and CX5DP005. Bechtel was requested to issue completed, signed-off drawings for construction; and the finding was satisfactorily closed. Finding 251 was issued, during the same audit, because Nonconformance Reports had not been approved by the design organization. Approval was obtained, and the finding was satisfactorily closed. 5.1.2 BECHTEL AUDITS Bechtel Power Corporation (BPC) conducts scheduled audits to verify compliance with project procedures: American National Standards Institute (ANSI) Standards, as they apply to the Project; and 10 CFR 50, Appendix B. There were eight BPC audits related to I&C design activities. The audits resulted in seven findings, categorized as follows: C:)
Category No of Findings Specifications 2 Training 2 Bid packages 1 Document Review Notice (DRN) 1 review Supplier programs 1 g These findings were minor in nature, and corrective actions were completed promptly. The Readiness Review Team considered these findings to be of minor importance and not indicative of any potential programmatic deficiencies. The findings were adequately resolved by the Project. 5.1.3 NRC INSPECTIONS The NRC conducted several inspections relating to installation of I&C. However, no design-related I&C findings were identified. 5.1.4 SELF-INITIATED EVALUATIONS In September and October of 1982, the Self-Initiated Evaluation (SIE) program was conducted for an indepth review of design and construction activities, using criteria developed by the Institute of Nuclear Power Operations (INPO). The SIE identified one design-related finding applicable to this module. Finding DC 2-08 identified failure to establish a document to identify instrument setpoints. This finding was satisfactorily resolved. In response to that finding, the Project developed and issued an instrument setpoint document. This document was included in the decign program verification activities as presented in section 6.1. O O O 0050t/093-6 5.1-2
O O O O O O O DESIGN AUDITS SORTED BY INITI ATING ORGANIZATION AND AUDIT NUPEER EDIT INIT AUDIT DESIGN CALCU- DRAW- SUPPLR DEVIAT. TRAIN DESIGN DESIGN DESIGN WEST. NO. ORGAN NUPBER DATE CRIT LATIONS INGS SPEC DATA REPORTS PRGM REVIEW DOC CNT CHANGES MISC SCOPE i EXPLANATION OF FIELDS for convenience, categories were combined where appropriate. The following is a listing of combinations and explanations: , EDIT NO. - Used for complete entry / corrections INIT ORGAN ~ Initiating or responsible organization: BPC, GPC, NRC, SCS AUDIT NUFOLR - Number applicable to specific audit DATE - Date of audit, finding, or report DESIGP. CRIT - Design Criteria, FSAR CALCitAT IONS - Calculations, Failure Modes and Ef fects Analyses (FMEAs), engineering studies DRAWING" - (Self-explanatory) SPEC - Design specifications, procurement specs, construction specs, bid evaluations SUPPLR DATA - Supplier data includes expediting, inspections, Supplier Deviation Disposition Pq uests (SDDRs)
- Supptier data package problems DEVIAT. REPORTS - Deviation Reports, Nonconformance Reports, reportable items t
TRAIN PRGM - Training progran for design personnel DESIGN REVIEW - Design reviews of engineering documents, Design Review Notices (DRNs), and interface between engineering disciplines DESIGN DOC CNT - Document Control - records, correspondence, design control (of design documents), manual control Project ' Reference Manual (PRM) DESIGN CllANGES - Field Change Requests (FCRs), Design Change Notices (DCNs), greenlining, Field Engineering Change Orders (IECOs) , MISC - Licensing deviation disposition requests procedures, miscellaneous design audits WEST. SCOPE - NSSS and activities specific to Module 16 0040t/2/056-6
Page No. 1 l 04/02/R6 DESIGN AUDITS
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7 MODULE 20 - 5ORTED BY INIT. ORoxt?!Z ATION & AUDIT NUMBER
.. .=......====.....=====.==.=. ..... .e===.=..=====....
EDIT INIT AUDIT DATR DESIGN CALCUL DRAW- SPEC' SUPPLN DEVIAT. TRAIN DESIGN DESIGN DESIGN MISC WEST. NO ORGAN NUMBER CRIT ATION5 INGS DATA REPONT5 PROM REVIEW DOC CNT CHANGE 5 SCOPE e- , ...--..=== ........== ........ ....-.. ... ... ....... ....... ...... ....... ....... ....... ....... .....== ....... ......- l 951 BPC-QA 77-001 04-31-77 I ; i 953 BPC-04 VM-II-I-3 03-28-79 78-12 L j 952 MPC-GA VM-II/I 03-24-78 78-o5 t l 950 BPC-QA VM-III-3 05-23-77 77-27 955 BPC-0A VM-III-3 07-31-79 79-42 949 BPC-QA VM-VII-2 03-08-77 77-10 I 954 BPC-OA VM-VII-2 04-25-79 79-18 ) 346 GPC-QA CP01-85/29 04-19-85 I 198 GPC-QA 0D11-81/61 09-11-81 250 251 753 NRC-INS 83-19 10-27-83 83-19-0 1
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+
- - . _ _ _ - . . . _ _ _ _ - . . . _ _ . - . - - - - - - . . . - . . - . - _ . . - - . -_-,_<--.-a.., , . _ . nn.-,,~- - . ,. -~,-r, m ..mv. .ne.,s
5.2 CONSTRUCTION AUDITS 1 O The project audits discussed in this section represent broad, indepth reviews of construction activities related to instrumentation and controls (I&C) installation. These audits principally addressed work activities as they progressed. including control of design documents, installation activities, O and quality assurance (QA) documentation. The construction audit matrix at the end of this section identifies audit subject areas and frequency of audit subject consideration.
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5.2.1 PROJECT AUDITS The Readiness Review Teat has identified 15 Georgia Power Company (GPC) QA audits addressing construction activities within the scope of Module 20. The 15 audits resulted in the identification of 27 findings or deficiencies related to construction activities. As part of the Readiness Review Program, the findings were reviewed and categorized by subject in the audit matrix. The results are summarized in the table J below. . l Subiect Frequency (a) Findinc(b) l Materials 9 5 Training and qualification 2 Ct Fabrication 11 1 8 inspection 13 8 l Testing 1 O Measuring and test equipment 1 0 ) Document control 7 4 1 QA records 2 1 Totals 46 27 The QA evaluation of the audit findings included a determination of impact on safety-related work, if any: corrective measures; and assessment of the proposed actions to minimize the potential {} for recurrence. l
- a. The Frequency column includes findings, deficiencies, observations, and other references to the subject areas within audit reports.
l l b. The Findings column includes findings and deficiencies and l () reflects multiple listings of the same finding if more than one category is affected.
The Mechanical Construction Team reviewed the audit findings to establish the level of potential importance in meeting design , requirements or having an adverse effect on programmatic l considerations related to construction activities. The team concluded that all of the findings were of moderate importance. The assessment activities for this module included these finding subjects. The results of the assessment activities of this module are OIj described in section 6.2. i 5.2.2 NUCLEAR REGULATORY COMMISSION INSPECTIONS Instrumentation activities have been addressed in nine Nuclear 9I Regulatory Commission (NRC) inspections. During these inspections, the NRC identified two severity Level IV violations. These inspection reports addressing the construction activities included in the scope of Module 20 were reviewed and categorized into one or more of eight subject areas as shown below: Subiect Frequency Violations Materials 6 1 Training and qualification 1 0 Fabrication 1 1 g Inspection 4 0 W Testing 0 0 Measuring and test equipment 0 0 Document control 0 0 QA records 0 0 Total 12 2 The audit matrix at the end of this section identifies the subject categories assigned to each of the violations. For convenience, each violation has been boxed on the matrix for ready identification. GPC has submitted responses to these two , violations and, as of January 3, 1986, is awaiting response from the URC. The NRC comments, inspector followup item, and observations noted in the reference reports were considered when preforming the assessment activities described in section 6.0 of this j module. l l llI 0028t/092-6 5.2-2
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O O O O O O' O Page No. 1 03/25/86 CONSTRUCTION AUDITS
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MODULE 20 - SORTED BT INIT. ORGANIZATION & AUDIT NUMBER
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EDIT INITIATING AUDIT DATE MATERIAL TRAIN / FABRIC- INSPECT- TESTING MEASURE DOCUMENT QA RENARE5 NO ORGANIZATION NUMBER QUAL ATION ION & TEST EQ CONTROL RECORD 5
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1766 BPC NONE 11-19-85 V8-85/17 4 1767 OPC-QA CD07-85/22 03-29-85 773 157 GPC-04 CP01-85/29 04-19-85 787 I 1768 GPC-QA CP02/5P01-85/77 10-31-85 857 1548 GPC-QA CP08-85/61 08-08-85 I 1566 GPC-G A CP21-85/65 08-30-85 I I I I I I 1719 GPC-QA CP21-85/90 12-22-85 I I 227 GPC-GA E303-84/15 03-15-84 580 230 GPC-GA ED04-82/118 12-13-82 376,377 376.377 390 GPC-QA 9D11-81/61 08-31-81 248.249 I 250 249 392 GPC-0A 0011-82/20 03-04-82 I I I 393 GPC-GA 9911-83/05 02-09-83 I I I 390 394 GPC-GA 0911-83/86 09-26-83 I I 395 GPC-GA G311-84/21 04-02-84 608.611 607,608 607 812 809,610, 611 398 OPC-GA G811-84/72 09-12-84 706 705.707 725 GPC-GA 8701-82/96 08-09-82 021-DEP 854 NBC-IN8 78-03 03-21-78 I I
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j i MODULE 20 - 80RTED ST INIT. ORGANIZATION & AUDIT NUMBER
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EDIT INITIATING AUDIT DATE MATERIAL TRAIN / FABRIC- IN8PECT- TESTING MEASURE DOCUMENT OA REMARES NO ORGANIZATION NUMBER QUAL ATION ION & TEST EQ CONTROL RECORDS
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857 NRC-IN8 78-04 08-20-78 I 948 NEC-INS 80-12 10-09-60 I 1037 NBC-IN8 82-10 06-21-82 I 1064 NBC-INS 82-15 08-21-82 I I 1106 NRC-IN8 82-27 12-07-82 82-27-01 1120 NBC-INS 83-02 02-18-83 I 1235 NNC-IN8 84-11 07-11-84 I 84-11-0 1 1374 NRC-INS 85-08 04-11-85l85-08-02l O O O O O O O
i l 5.3 PAST DESIGN AND CONSTRUCTION PROBLEMS f ([) 5.3.1 DESIGN PROBLEMS Seven problems related to instrumentation and controls (I&C) design were identified during the course of VEGP design. In l each case the Nuclear Regulatory Commission (NRC) was informed l O of the potential reportability of the deficiency and was subsequently informed that the identified deficiencies constituted a reportable condition pursuant to the criteria of 10 CFR 21 and 10 CFR 50.55(e). These seven problems are described in cases A through F below: A. Hydrogen Recombiner Power Supply - Non-Class lE Power l Supply On December 30, 1980, Georgia Power Company (GPC) notified the NRC of a reportable concern involving a non-Class lE transformer that was employed in the hydrogen recombiner power supply unit.
- To resolve this concern, the hydrogen recombiner was l returned to Westinghouse, the subvendor, for i replacement of the transformer.
,() B. Reactor Coolant System Wide-Range Pressure Transmitter Inaccuracy On April 27, 1082, GPC notified the NRC of a reportable concern regarding possible inaccuracies of the reactor coolant system (RCS) wide-range pressure transmitters if used during post-accident applications. To resolve this concern, two pressure-sensing lines
- from the RCS hot legs were established. Each line l contains two transmitters, of an increased range, l located outside containment. The four transmitters l provide indication on the main control board in the control room.
C. Undetectable Failure - Solid-State Protection System On August 6, 1982, Westinghouse notified the NRC of a reportable condition involving a potential undetectable , O failure in online testing circuits for relays in the solid-state protection system. The condition was resolved by corrective action to testing procedures to ensure that no failures would occur in the circuits after completion of testing. \ l
D. Defective Printed Circuit Cards On January 11, 1984, GPC notified the NRC of a reportable condition involving defective heat sink assemblies on printed circuit cards for the nuclear loop power supply. The condition was resolved by returning the detective circuit cards to the vendor, Westinghouse, for repair. E. Isolation Valves and Damper Actuators - Defective Seals On March 26, 1985, GPC reported a deficiency involving l l rubber seals used in rotary actuators for valves and dampers that swell when in contact with Mobil 28 lubricant or flatten if not exercised. Four valves and a number of dampers were identified to be affected by the defective actuators. To resolve the deficiency, each installed actuator was repaired with new seals and lubricant. Deficient actuators in storage have been identified and will be serviced with the new seals and lubricant prior to installation. F. Undetectable Failure - Engineered Safety Features Actuation System On March 26, 1985, GPC notified the NRC of a reportable condition concerning an undetectable failure involving an interlock used to input the status (open or closed) of the reactor trip breakers to the engineered safety features actuation system. To resolve the condition, the Project has revised the system testing procedure to identify this type of failure as prescribed by Institute of Electrical and Electronic Engineers (IEEE) 379, Application of the Single railure Criterion to Nuclear Power Generating Station Protection Systems. 5.3.2 CONSTRUCTION There have been no significant past construction problems O identified within the scope of the instrumentation module. O 0032t/100-6 l 5.3-2 _________-__-______2_ _ _ _ - _ _ .
)
, 6.0 PROGRAM VERIFICATION l O This section describes the activities undertaken to ascertain the degree of control applied to the design and construction work processes with respect to the implementation of licensing commitments, project procedures, and design requirements.
) This section is divided into two parts: section 6.1 describes activitier relcted to design program verification and section 6.2 addresses construction program verification. l l
Resultant findings have been classified into three levels of importance relating to plant safety: 1 0 1 - Violation of licensing commitments, project i procedures, or engineering requirements with l indication of safety concern.
; II - Violation of licensing commitments or engineering requirements with no safety concerns.
III - Violation of project procedures with no safety concerns. Listings of the identified findings, along with their assigned level of inportance, are included in this section. O 1 l O , 0075t/092-6 l i l
q fg 6.1 DESIGN PROGRAM VERIFICATION b The following sections describe the design program verification and resultant findings and corrective actions. This evaluation was performed by the Readiness Review Design Team consisting of four engineers with a cumulative experience of 53 years in power plant design engineering. Approximately 800 manhours were p), (, expended performing this verification. The verification concentrated on the programmatic aspects of design. This evaluation was a systematic review of design documents to determine whether the design activities associated with instrumentation and controls (I&C) comply with licensing ( commitments. This section has been divided into the following subsections: Section 6.1.1: Evaluation Summary Section 6.1.2: Verification Scope and Plan Section 6.1.3: Verification Review and Results Section 6.1.4: Design Program Verification Findings 6.1.1 EVALUATION
SUMMARY
The design program verification includes instruments (Table () 6.1-1) selected from three systems: primary coolant system, main stean system, and component cooling water system. The review of 106 documents resulted in five findings: one Level I, one Level II, and three Level III. The one Level I finding (20-11) identified an inconsistency between the setpoint on a level setting diagram and the setpoint list. An expanded review of additional level setting diagrams identified additional discrepancies with the setpoint document. This item is currently being reviewed for reportability by the Project. Also, the Project is taking action to resolve all discrepancies between the two documents and to preclude recurrence. (See section 6.1.4.) One Level III finding (20-14) identified a lack of design coordination review of logic diagrams between the Control Systems Group and the Mechanical and Nuclear Groups. Expanded review of the logic diagrams by the Mechanical and Nuclear Groups did not disclose any deeign problems. O Two findings (20-9, Level I '.1, and 20-10, Level II) identified deficiencies related to inoccuracies or omission of the project quality class designator <sn I&C drawings. Both findings were determined to be isolated instances of minor importance. i
i i One Level III finding (20-13) identified a deficiency on an instrument location drawing. The finding was determined to be a i unique instance of minor importance. In summary, the Design Team assessed pertinent design activities related to instrumentation and controls. Although programmatic deficiencies have been revealed, as evidenced by the findings, none resulted in a technical deficiency or a potential safety concern except for Finding 20-11, which is being evaluated by the Project for potential reportability. With proposed project improvements, the Design Team finds the Module 20 design program l to be satisfactory and to meet project licensing commitments and l quality requirements. O 6.1.2 VERIFICATION SCOPE AND PLAN l l 6.1.2.1 Verification Scope The scope of this verification considered the design documents l described in section 4.1. Documents included in the verification scope are as follows: l o Design Documents i l - Design criteria (DC).
- Calculations.
- Drawings.
- Procurement specifications.
- Supplier data and drawing documents.
- Construction specifications.
o Design Change and Nonconformance Documents l
- Design Change Notices (DCNs).
- Construction Specification Change Notices (CSCNs).
- Field Change Requests (FCRs).
- Supplier Deviation Disposition Requests (SDDRs).
- Deviation Reports (DRs).
6.1.2.2 Verification Plan The design program verific3Llon included an assessment of licensing commitment implementation and an assessment of the design control program. Design-related licensing commitments that apply to this module were reviewed to determine whether they were included in appropriate design criteria or other appropriate design documerits; e.g., specifications or drawings. O 6.1-2
l l l
- The design control program assessment involved a review of
(_,s) design documents associated with a selected sample of instruments. This review included documents such as drawings, specifications, and change documents to determine compliance with licensing commitments and project procedures. i () 6.1.3 VERIFICATION REVIEW AND RESULTS l The review methodology and results for each part of verification review are described in the subsections that follow. () 6.1.3.1 Commitment Implementation Assessment ) i The commitment implementation review consisted of two parts. In l 1 part 1, a review was made to ensure that each commitment was included in the appropriate design basis document; e.g., design criteria. In part 2, a review of commitments was made to determine whether subordinate design documents such as calculations, drawings, procurement specifications, and construction specifications adequately implemented the commitments during the development of the detailed design. Parts 1 and 2 of the commitment implementation assessment were accomplished as described in sections 6.1.3.1.1 and 6.1.3.1.2. 6.1.3.1.1 Part 1, Commitments in Design Criteria Commitments were identified by review of the source documents [i.e., the Final Safety Analysis Report (FSAR), Regulatory Guides, industry codes, etc.], as applicable. The appropriate design criteria were then reviewed to determine whether the subject commitment was included. The implementing documents resulting from this assessment are presented in section 3.5 of this module. The described steps ascertained that commitments were recognized by the Design Engineering Group as requirements for detailed (} design or design-related activities, as appropriate. 6.1.3.1.2 Part 2, Implementation in Detailed Design In part 2, selected commitments from a variety of source () documents were reviewed (using the checklist in Figure 6.1-1) to ascertain whether they were correctly applied during the design process. The verification was accomplished by reviewing affected detailed design documents (e.g., specifications, drawings, etc.) to determine whether selected commitment details were incorporated. The selected commitments and the associated implementing documents are provided in the commitment [) verification matrix (Table 6.1-2). 6.1-3
The review results indicated that the Project had incorporated the selected commitments into the second-order design documents (Table 6.1-2). g 6.1.3.2 Desion Control Assessment Project design documents were reviewed for conformance to the design program requirements. The emphasis of the review was to verify that the design process was controlled in accordance with the quality program licensing commitments. This was accomplished by verifying that the design process complied with project procedures and other documents governing design control [e.g., American National Standards Institute (ANSI) N45.2.ll). llh Checklists to provide review guidelines were developed for each type of document. Documents that were reviewed included design criteria, design change documents, drawings, specifications, procurement and vendor documents, and calculations. The design documents reviewed (Table 6.1-3) primarily pertain to the selected I&C sample. 6.1.3.3 Desicn Criteria A procedural review of one design criteria (DC-1000-J) was performed to determine whether this design document was appropriately reviewed, updated in a timely manner, and approved by the affected disciplines. The checklist shown in Figure 6.1-2 was used to review specific attributes of the design criteria. It was observed that an interdisciplinary review had been conducted. The group supervisors from the Controls. Licensing, Mechanical, and Electrical Plant Design Groups and the project engineer had approved the design criteria. Changes to the design criteria had been properly incorporated. There were no findings in this area. 6.1.3.4 Calculations Verification was performed to determine whether the design calculations comply with project procedures, design criteria, industry standards, and the FSAR. In addition, selected design requirements from the calculations were compared to pertinent design drawings. One set of design calculations (X5CP0005), listed in Table 6.1-3, was reviewed using a checklist (Figure 6.1-3). It was observed that the calculations met the requirements of Project Reference Manual (PRM), part C, section 9. Both the original 6.1-4
and subsequent revisions had appropriate approvals. The review O included verification that the calculations conformed to I pertinent project commitments, that the output data was incorporated into affected documents, and that the input data was consistent with referenced documents. There were no findings in this area. O 6.1.3.5 Piping and Instrumentation Diagrams A procedural review of six piping and instrumentation diagrams J (P& ids) focused attention on conformance to project design ' ! (T (_) criteria and licensing requirements, project coordination with l other disciplines, and conformance to PRM, part C, section 4, l requirements. A checklist (Figure 6.1-4) was used as a guide to . verify the compliance of the instruments with the requirements l identified on the checklist. l 1 There were no findings associated with the review of P& ids. 6.1.3.6 Loop Diagrams One loop diagram was reviewed using the checklist shown in i Figure 6.1-5 as a guide. The review focused on conformance to j 7si project procedures, selected design criteria, licensing ' requirements, coordination with other disciplines, and appropriate approvals. The loop diagrams were also reviewed for consistency with the applicable P& ids. Vendor hardware drawings were reviewed to determine input signal compatibility with the receiver unit, and output signal compatibility with the receiving device. No findings were identified by review of the loop diagrams. 6.1.3.7 Logic Diagrams O ' A procedural review of logic diagrams focused on conformance to project design criteria, licensing requirements, and coordination with other disciplines and verified that diagrams had received appropriate approvals.
/~T Six logic diagrams were reviewed using the checklist shown in
() Figure 6.1-6 as a guide. Logic diagrams were reviewed to confirm compliance with Design Criteria DC-1000-J: Component Cooling Water System, DC-1203: Main Steam Line and Feedwater Line Isolation Systems, DC-1320; and Steam Generator Blowdown System, DC-1407. Applicable safeguards actuation signals were () reviewed to verify consistency of design -iteria, the FSAR, and logic diagrams. 6.1-5
One programmatic finding (20-14) was identified. There is no documented coordination between the Control Systems Group and the Mechanical and Nuclear Groups regarding review of logic diagrams. Findings details and project corrective action are provided in section 6.1.4. 6.1.3.8 Data Sheets Three instrument data sheets were reviewed using the checklist shown in Figure 6.1-7 as a guide. The review included assessments of project conformance to licensing requirements, design and process information: response to seismic and environmental qualification requirements and confirmation of interdiscipline coordination. No deficiencies were identified during this review. 6.1.3.9 Instrument Location Drawinos Eleven instrument location drawings were reviewed using the checklist shown in Figure 6.1-8 as a guide. The drawings were checked for appropriate approvals, selected features from design requirements, and interdiscipline coordination. Three instruments located in containment were reviewed to determine whether they had been assessed for hazard effects. Two " instruments (FT-0512 and PT-405) are located within a jet impingement impact zone, but the hazards analyses had been performed and the acceptability of this location had been documented. On one of the location drawings, an electrical supply to position switches for valve PSV-8010A was not identified. The Readiness Review Team initiated a Finding (20-13) to note this discrepancy. Details of the finding and the project corrective action are provided in section 6.1.4. No other discrepancies were identified. 6.1.3.10 Installation Details llh Five instrument installation detail drawings were reviewed using the checklist shown in Figure 6.1-9 as a guide. The drawings were reviewed for required approvals, conformance to applicable licensing commitments / design criteria, and interdiscipline coordination. One finding (20-10) was identified during the review of level setting diagrams. One diagram that should have had a 0-classification did not. Details of this finding are presented in section 6.1.4. No other discrepancies were identified. 6.1-6
l 6.1.3.11 Setpoint Lists Five setpoint lists were reviewed using the checklist shown in Figure 6.1-9 as a guide. Setpoint lists were reviewed for required approvals, conformance to applicable licensing commitments / design criteria, and interdiscipline coordination. I One finding (20-11) was identified. Setpoints on one list did not agree with setpoints stated on the level setting diagram. Details of this finding are presented in section 6.1.4. No other discrepancies were identified. 6.1.3.12 Procurement Specifications Two procurement specifications were reviewed using the checklist shown in Figure 6.1-10. Procurement specifications were reviewed for compliance with applicable licensing commitments and for compliance with codes, standards, and design criteria requirements. The review also checked whether SDDRs were issued affecting any licensing commitments and specification requirements, whether multidiscipline reviews were carried out where applicable, and whether specification revisions were controlled. No findings were identified during the review of the procurement (} specifications. 6.1.3.13 Construction Specification The construction specification X4AZOl, division P2, was reviewed using the checklist shown in Figure 6.1-11 as a guide. The specification was reviewed for implementation of design criteria, interdisciplinary reviews, proper incorporation of change notices, incorporation of vendor information, and conformance to applicable codes and licensing requirements. No finding was identified by review of the construction specifications. (')T 6.1.3.14 Vendor Documents Twelve vendor drawings were reviewed using the checklist shown on Figure 6.1-12 as a guide. Vendor documents were reviewed to
- ['s~>} confirm compliance with the corresponding procurement specifications. In addition, selected details from the vendor documents were reviewed for proper inclusion into design documents.
(} No findings were identified by review of vendor drawings. 6.1-7
..~
6.1.3.15 Field Chance Requests Five FCRs were evaluated using the checklist shown in Figure 6.1-13. The evaluation included reviews to determine compliance with design requirements; correlation with appropriate calculations; and compliance with procedural requirements, such as appropriate reviews and approvals, documentation of rationale for disposition, and proper incorporation into applicable g drawings. W No findings were identified during the review. 6.1.3.16 Deviation Reports Six DRs were reviewed using the checklist shown in Figure 6.1-14 as a guide. The DRs were reviewed for attributes such as adequate technical justification, appropriate reviews and approvals, and any impact on applicable licensing commitments. No findings were identified by review of DRs. 6.1.3.17 Construction Specification Change Notices Five CSCNs were reviewed using the checklist shown in Figure 6.1-15. The selected CSCNs were reviewed for attributes such as compliance with project procedures, licensing commitments, and design criteria requirements, and for interdiscipline coordination and review. No findings were identified by review of the selected CSCNs. 6.1.3.18 Drawino Chance Notices Five DCNs were reviewed using the checklist shown in Figure 6.1-4. The DCNs were reviewed for attributes such as compliance with project procedures, licensing commitments, and design criteria, and interdiscipline coordination and review. No findings were identified by reviewing the selected DCNs. O 6.1.3.19 Supplier Deviation Disposition Requests Two SDDRs were reviewed using the checklist shown in Figure 6.1-16. The SDDRs were reviewed for attributes such as interdisciplinary review, conformance with licensing commitments, and adequate rationale of disposition. No findings were identified by review of SDDRs. 6.1-8
6.1.3.20 Instrument Index r i
\. Fourteen instruments in the instrument index were reviewed using the checklist shown in Figure 6.1.17 as a guide. The data for each instrument were reviewed for correct tag number, vendor identification, project classification, reference drawings, process information, and environmental designation.
One finding (20-9) was identified during the review of the instrument index. The finding noted that two level switches were identified in the instrument index as a higher classification than required. Details of this finding are provided in section 6.1.4. No other discrepancies were noted. 6.1.3.21 Industry Problems Three industry concerns, three Inspection and Enforcement (IE) Notices, seven IE Bulletins, one Institute for Nuclear Power l Operations (INPO) Significant Event Report (SER), and one 7.NPO l Significant Operating Experience Report (SOER) were reviewed using the checklist shown in Figure 6.1-18 as a guide. Project I documentation was reviewed for proper interpretation of the scope of work and technical considerati.ons, adequate ! justification of resolution, consideration of inputs from vendors and/or other disciplines, consistency of problem resolution with design criteria, and implementation of ((~N-) solution. There were no findings identified by the review of industry problems. 6.1.4 DESIGN PROGRAM VERIFICATION FINDINGS During the performance of the verification activities described in section 6.1.3, identified discrepancies were issued, on a Readiness Review Finding Form, to the Project for review and resolution. During the verification process for this module, five findings were identified. Table 6.1-4 provides a summary of those findings. () A detailed description of these findings and the corrective actions follows: o Finding 20-9 (Level III) l
Description:
Level instruments LSH-1850 and LSL-1850 l (/^%) _ were furnished as safety-related (Project Quality Class llJ) instruments. The instrument index also lists these instruments as safety related (Project Class llJ). Contrary to this, the data sheets identify these instruments and the wiring connected to level switches as Project Quality Class 61J. l l 6.1-9
l Project Response: Level switches LSH-1850 and LSL-1850 were specified in data sheet CX5DC503, specification X5AF02, as Project Class 61J per process requirement. ) The vendor, however, supplied these switches with a higher qualification level as Project Class 11J. Although the switches are manufactured and qualified to Project Class llJ, their intended services are for Project Class 61J and should be shown as such in the g instrument index. The instrument index, in its latest W version, lists the subject switches as Project Class llJ in conformance with the quality of instruments supplied by the vendor. In an effort to determine the extent of this g observation, all level switches procured under W specification X5AF02 (a total of 445 switches for Unit 1, common, and Unit 2) were checked against the instrument index with respect to project class. As a result, four additional level switches (LSH-1851, LSL-1851, LSH-1955, and LSL-1955) were found to have the same problem. These four switches were specified as 61J. supplied as llJ. and listed as llJ in the instrument index. Since no other vendors provided qualifications beyond those actually required under any other control specification, Home Office Engineering (HOE) believes that the discrepancy described in the observation is unique to this one specification, X5AF02. Although the instrument index showed the as-supplied quality class, the proper project classification should have been used to reflect design requirements. Specification X5AF02 is a unique case, where the vendor supplied some instruments that exceed the project qualification requirement. When entering the project class in the index, the controls engineer failed to recognize that the required project class for the intended service should have been entered in lieu of the actual qualification of the hardware supplied. lll Change documents to the instrument index have been written to show the correct project classification for the six aforementioned level switches for incorporation in the next appropriate revision. o Finding 20-10 (Level II)
Description:
Level setting diagrams (LSDs) 1X5DTOO31, Revision 0, for pressurizer, and 1X5DT0077, Revision 0, for steam generator (SG) 1 should be designated as l Q-drawings, since the instruments on these two diagrams 6.1-10
I are Project Quality Class llJ. Current issues of these (} two diagrams are not designated as Q-drawings. Proiect Response: The Project agrees that the LSDs for l pressurizer 1X5DT0031 and for steam generator 1X5DT0077 do not show Q-designators. l () A review of LSDs (198 diagrams for Unit 1 Unit 2, and common) revealed that the following LSDs do not have Q-designators. LSD Equipment () 2X5DT0031 2X4DT0077 Pressurizer, Unit 2 SG No. 1, Unit 2 ; 1X5DT0071 SG No. 3, Unit 1 1 2X5DT0071 SG No. 3, Unit 2 1X5DT0072 SG No. 4, Unit 1 2X5DT0072 SG No. 2, Unit 2 1X5DT0078 SG No. 2, Unit 1 2X5DT0078 SG No. 2, Unit 2 DCNs to add Q-designators to Unit 1 drawings were issued on January 28. 1986. These particular LSDs are based on Westinghouse documents which do not provide Q-designation. This O situation is assessed as unique, since only the steam generators and pressurizers were involved. All LSDs for Unit 1 have been reviewed and corrected for missing Q-designators. l To further prevent similar deficiencies or any other I&C l drawings issued in the future, a desk memorandum to the l Controls Systems Group has been issued to require a more complete review to determine Q-status for the drawings. l o Finding 20-11 (Level I)
Description:
The setpoint values for three level instruments have the following discrepancies: Instrument Setpoint Level Setting List Diagram m Tac No. CX5DT101-96. Rev. 3 1X5DTOO22. Rev. 0 1LSLL-1852 el 252 ft 9 in. el 252 ft 7-1/4 in. lLSLL-1854 el 252 ft 9 in. el 252 ft 7-1/4 in. 1LSLL-1856 el 252 ft 9 in, el 252 ft 7-1/4 in. O 6.1-11
Proiect Response: Following is a brief history of the ~ latest changes to the two drawings in question:
- l. LSD 1X5DT0022: Document Review Notice (DRN) J-169 was initiated by Mechanical on December 20, 1985, requesting changes to the settings. DCN 1 was issued on January 20, 1986, to document this change. The LSD was revised on January 27, 1986, to ,
incorporate the change described by the DCN.
- 2. Setpoint list 1X5DT101-96: a DCN to this drawing was issued on February 7, 1986, to document the changes created by the LSD 1X5DT0022.
To determine the extent of this observation, a review of 18 randomly selected level instruments was conducted. Results of this review revealed six additional cases where the instrument setpoints shown in the LSDs differ from those in the setpoint list. The discrepancies are classified into two categories as follows: i o Tag Nos. LSH-7883. LSHL-7893: Unit 2 drawings were changed, but Unit 1 drawings were not. o Tag Nos. LSHL-7875, LSH-5178. LSH-10455, and LSH-1955: The change in the setpoints of the instrument was initiated by an interoffice memorandum g from the Mechanical Group. The interoffice W memorandum was routed to the engineering group supervisor (EGS), engineering group leader (EGL), and responsible engineers (REs) for action. For the above four instruments, the RE for the setpoint list did not issue the setpoint list change at the same time as the LSD change. The format of the LSD will be changed to eliminate the duplication of information on two documents; i.e., all level information will be placed on the LSD only. The setpoint list will be revised to refer to the appropriate LSD for all data relevant to a level device. list. All LSDs will be compared against the setpoint Any discrepancies in the two documents will be lh ; identified by the Project (HOE) to Nuclear Operations. The change to the setpoint list, the revision to the LSDs, and changes in the two documents will be completed by April 30, 1986. o Finding 20-13 (Level III) i
Description:
Instrument location drawing 1X5DS4D,10, g l Revision 3, does not show electric service to PSV-8010A, W ' 6.1-12
even though the P&ID indicates that position switches are required. r~~ k_) Proiect Response: PSV-0010A is a spring-loaded safety relief valve supplied with special position switches to provide electrical signals for the post-accident monitoring system (PAMS). The Project agrees that location drawing 1X5DB4D18 should show electrical
/~T service for this valve.
O This is a unique case, because spring-loaded pressure relief valves typically do not require position switches. Out of 308 balance-of-plant pressure relief valves in the plant, only three were backfitted with position switches [due to Three Mile Island (TMI) f~)'
'- requirements] and therefore required electrical service. Although the engineer correctly implemented the TMI requirements, he did not show the power requirement on the location drawings. Any instrumentation device requiring electrical service is required to be shown on location drawings. Sixty other randomly elected instrumentation devices requiring electrical service were reviewed, and all were shown on location drawings.
o Finding 20-14 (Level III) Ik
Description:
VEGP PRM Table C4-2 requires design review I by the Electrical, Mechanical, and Nuclear Groups (radwaste only). This requirement implies that the control diagrams should be reviewed by the Electrical, Mechanical, and Nuclear Groups (radwaste only) and that the review should be documented. There is no coordination of design review of logic diagrams by the Mechanical Group, except that the control engineer consults with the Mechanical Group on an informal basis. There is no record of design coordination. The Electrical Group and the Control Systems Group sign the logic diagrams. Proiect Response: Project requirements for coordination of drawings among disciplines are given in the PRM, sections 4.7.2 and 4.7.5 and Table C4-2. As noted in section 4.7.5, Table C4-7 applies to drawings issued for fabrication / construction to accomplish interdiscipline O coordination of design changes not accomplished by a DCN. While informal coordination has occurred, the formal requirement for Mechanical and Nuclear review and signature of logic diagrams has not been implemented.
/~'N
' (_) .d 6.1-13
Present project procedure requires that all design changes to any drawing be done by DCN. In accordance with requirements, for any design change a DCN will be routed to the Mechanical and/or Nuclear Groups. lh ! In order to ensure appropriate cognizance of logics by the Mechanical and Nuclear Groups, a review has been made of a sample of the logics (60 drawings) to ascertain the correctness of the design. The review by the Mechanical Group and the Nuclear Group has confirmed h the correctness of the logic drawings. , Readiness Review
Conclusion:
The Readiness Review Design Team is in agreement with the above-stated project corrective actions. O O O 0051t/100-6 ll 6.1-14
.. I
t TABLE 6.1-1 SELECTED INSTRUMENTS AND CONTROLS Instrument No. Instrument l PT-0405 Reactor coolant loop 4 hot-leg pressure transmitter l ! PSV-8010A Pressurizer relief valve l (} .ZS-8010A TE-0413A Pressurizer relief valve position switch Reactor loop 1 wide-range hot HS-1852A Component cooling water (CCW) pump P4001 control switch LSLL-1854 CCW surge tank T4001 makeup level switch l HV-7603C SG B600C blowdown isolation valve ! HY-7603M SG B6004 blowdown isolation solenoid valve HV-3026A Main steam isolation valve 'O PV-3020 -Atmospheric dump valve FT-0512 SG loop 1 steam flow transmitter l LT-0517 SG loop 1 level transmitter l LI-0517 SG' loop 1 level indicator PDI-9085 Diesel generator G4002 fuel filter ) pressure differential indicator I ! 1451E70 Main control board front view section O O 0067t/2/092-6
O O O O O O O TABLE 6.I-2 (SilEET I 0F el) 00fMilf1LNI VERIF ICATION MAIRIX Criteria Design FSAR Design Document Itcm Subject Description Section Comi tment No. _Section Type - No. 1 Design and fabrication codo 1.9.04 1%5 DC-1000-J X5ACO3, Rev. 12 case acceptabiiity (RG l.84, X4POOO5 ASME I11) 2 Reactor trip system 7.l.2.1 4583 DC-1000-J X6AU01-278-3 (IEEE-279) DC-1625 3 Containment 112 monitoring 6.2.5.1 2%7 DC-1513 X5AA05, Rev. 6 system (RG 1.7) Delphi drawing 080929, 08093I 4 Manual initiation of 7.3.1.2.2.7 464I DC-1000-J IX5DN149-l protective actions (RG l.62) DC-1620 5 Class IE MOVs specified 8.3.1.l.8 4822 X5AC01, Rev. 12 with accelerating capability 75% nameplate voltage 0064t/094-6/I
O O O O O O O 1ABLE 6.1-2 (SilEET 2 OF 4) Criteria Design ISAR Design Document llem Subject Description Section Comitment No. Section Type - No. 6 Cablo routing panels and 8.3.l.4 82 DC-1601 Shutdown panel boards internal wiring Train A: j IX5AB01-54-7 IX5AB01-57-6 IX5ABOI-55-7 IX5AB01-58-6 IX5ABOI-Il2-6 IX5ABOI-I l 3-5 IX5ABOI-II4-5 IX5ABOI-il54 1 IX5AB01-I l64 IX5AB01-i l74 IX5AB01-i l84 IX5AB01-il9-7 IX5AB01-120-5 IX5AB01-122-5 Train B: t IX5AB01-60-7 Main Control Board {' Front View Section IBit IX6AV02-49-9 Termination Cabinet No. IACPT03,
] ! Train A: ! IX6AV02-95-3 Termination Cabinet No. IBCPT04 Train B IX6AV02-96 3 l
t 7 Controlled use of sensitized 6.l.1.l.3 259 DC-1201 X5AG00, Rev. 8 I DC-1206 stainless steel (RG 1.44) I 0064t/094-6/2 i
O t O TABLE 6.1-2 (SilEET 3 0F 4) , Criteria Design FSAR Design Document i lim Subject Description Section Comitment No. Section Type - No. 0 Bypassed and inoperable 7.5.5.3 4547 DC-1625 Control logic ] status indication for diagram system ' engineered safety feature status monitor ! (EST) systems (BIP-lCSB-2i) IX5Dh070-5, Rev. 2 IX5DN070-6, Rev. 2 3 IX5DN070-7, Rev. 2 j IX5DN070-8, Rev. 2 j IX5DN070-9, Rev. 6 IX5DN070-10, Rev. 4 i IX5DN070-il, Rev. 4 IX5DN070-12, Rev. 3 f 1 l 9 Containment isolation I.9.141 1595 DC-2415 Functional diagram
- provisions for fluid safeguard actuation
- systems (RG l.141) system: I/2X6AA02-232-10 I Control logic { diagram, steam j generator blowdown j and sample system: i IX5DNil7-1, Rev. 4 IX50 Nil 7-2,' Rev. 3 IX50 Nil 7-5, Rev. 3 IX5DNil7-4, Rev. 1 IX5DNil7-5, Rev. 0 I 1 1 i 4 ! 0064t/094-6/3 l l i I
O O O O O O O TABLE 6.1-2 (SilEET 4 OF 4) Criterla Design ISAR Design Document item Sub_jo:7 Description Section Comitment No. Section Type - No. 10 interlocks for RCS 7.6.7.I 4557 DC-1701 Solid-state 3r,ssure control protection system (BIP-PSB-5-2) schematic diagram Westinghouse 12961101, sheet 17 W process control block diagram V2X6AV01-669-3 l P&lO reactor coolant system , sy: tem No. 1201 IX4DBil2 i i i 4 t i i l 0064 t/094-6/4 i
- ?
i l . I TABLE 6.1-3 (SHEET 1 OF 5)
- O j
SUMMARY
OF DOCUMENTS REVIEWED 4 i Calculations (1) Title X5CP0005 Instrument Tubing and Tubing Supports i' i Piping and Instrumentation Diagrams (6) 1X4DBill Reactor Coolant System 1X4DBil2 Reactor Coolant System , 1X4DB136 Component Cooling Water System ' 2 ^ 1X4DB137 Component Cooling Water System i 1X4DB159 Main Steam System , ] 1X4DB170 Dissel Generator Loop Diagrams (1) Instruments ; i j 1X5DV043 PV-3020 l i Logic Diagrams (6) Instruments , i 1X5DN125-1 PV-3020 1
, 1X5DN092-1 LSH-1850, LSL-1850 ..
l 1X5DN117-1 HV-7603C, NY-7603M, HY-7603L, HY-7603G j 1X5DN149-1 HV-3026A, HS-3026A 1X5DN152-1 HS-15212C
- 1X5DN091-1 HS-1852A, LSLL-1852, LSLL-1854, LSLL-1856 4
j Data Sheets (3) Instruments- ,' CX5DC501 LSL-1852, LSLL-1854, LSLL-1856 j CX5D0003 PV-3020 ) CX5DU004 PSV-3004 !O O O - 0053t/094-6/2 4 1
TABLE 6.1-3 (SHEET 2 OF 5) (D U Location Drawings (11) Instruments 1X5DS4D07 PT-0405 1X5DSPD002 HS-1852A, LI-517 O 1X5DS4D06 LT-0461. TE-0443B 1X5DS4D18 PSV-8010A, ZS-8010A 1X5DS4A06 TE-0413A 1X5DS3H01 LSLL-1856, LSH-1850, LSL-1850, LSLL-1852, LSLL-1854 1X5DS3G06 HV-7603C O 1X5DSP148 1X5Db2E02 HV-7603M HV-3026A, PV-3020 FT-0512, LT-0517 1X5DS4A02 1X5DS5D02 PDI-9085 Installation Details (5) Instruments CX5DP3008 PT-0405 CX5DP4018 TE-0413A, TE-0443B CX5DP2026 LSH-1850, LSL-1850, LSLL-1852, LSLL-1854, LSLL-1856 1X5DP6010 FT-0512, LT-0517 CX5DP6009 LT-0461 Setpoint Lists (5) Instruments CX5DT101-95 LSH-1850, LSL-1850 CX5DT101-196 PSV-8010A CX5DT101-96 LSLL-1852, LSLL-1854, LSLL-1856 CX5DT101-3 PSV-1872-CX5DT101-78 PSV-3004 Procurement Specifications (2) Equipment X5AF02 LSH-1850 X5Acl3 PV-3020 O O 0053t/094-6/3
TABLE 6.1-3 (SHEET 3 OF 5) l Construction Specification (1) Title X4AZ01-P2 Instrument Installation Vendor Drawings (12) Instruments ! 1/2X6AA02-302 PT-405 1/2X6AA06-167 PSV-8010A, Z9-8010A 1/2X6AA02-315 TE-0413A ! () lx5AF02-001 1/2X6AA06-0595 LSH-1850 HV-7603C, NY-7603M 1X4AR17-102 HV-3026A 1X5AC13-033 PV-3020 1/2X6AA02-306 FT-0512 1X4AK01-458 PDI-9085 1X6AA02-408 TI-0443B 1X6AV02-46 HS-1852A 1/2X6AA06-574, 575 ZS-8010A 4 Field Change Requests (5) Drawings O Y-FCRB-1652 Y-FCRB-2043 Y-FCRB-2110 1X5DS4D07 1X5DS4D06 1X5DS3G06' l j Y-FCRB-2229 1X5DS2E02 Y-FCRB-2231 CX5DP7020 l l Deviation Reports (6) Drawings l DR-ID-lll7, DR-ID-ll33 X5AD04 DR-MD-2772, DR-MD-2773 X5ACl3 DR-ID-0717, DR-MD-2575 X5AF02 () Construction Specification Change Notices (5) Instrument Installation Specification CSCNs-373, 374, 375, 388, 404 X4AZ01, Division P2 4 O 0053t/094-6/4 l
- ~. - . - _ . . . - _ . - _ _ - _ _ . - _ _ . -
TABLE 6.1-3 (SHEET 4 OF 5) O Drawing Change Notice (5) Drawings DCN No. 19 1X4DBlll 1 DCN No. 51 1X4DBil2-O DCN No. 41 DCN No. 21 1X4DB136 1X4DB137 1X4DB159-2 DCN No. 51 l Supplier Deviation (2) Drawings Disposition Requests ( )- SDDR No. 71; SDDR No. 29 X4AR17 Instrument Index (1) Instruments (14) i Report No. FT-0512 NM-111-50RX3 HS-1852A l HV-3026A HV-7603C l HY-7603M LI-0517 O LT-0517 LSLL-1854 PT-0405 PSV-8010A ZS-8010A PV-3020 PDI-9085 TE-413A Industry Concerns (3) Instrument Air System - Corrosion-Resistant Piping O Anchor Darling Bypass Valves [ Main Steam Isolation Valves (MSIVs)] Valcor Solenoid Valves - Coil and Switch Failures O O 0053t/094-6/5
TABLE 6.1-3 (SHEET 5 OF 5) (I IE Notices and Bulletins (10) Title IEB 78-14 Deterioration of Buna-N in ASCO SOVs IEB 79-01 Environmental Qualification of Class I Equipment IEB 79-28 Possible Malfunction of Namco EA180 Limit C,]/ Switches at Elevated Temperature IEB 80-06 ESF Reset Controls IEB 80-09 Hydromotor Actuator Deficiencies IEB 80-16 Potential Misapplication of Rosemount 1151 and 1152 Press. Transmitters with A or D Output Codes IEB 80-23 Failure of Solenoid Valves Manufactured by Valcor Eng. Corp. IEN 85-02 Improper Installation and Testing of Differential Pressure Transmitters IEN 85-47 Potential Effects of Line Induced Vibration on Target Rock SOVs IEN 85-73 Discrepancies between As-Built construction Drawings and Equipment Installations l INPO SERs and SOERs (2) Title l l SER 71-83 Inability to Shut Down Diesel Generator f-'g SOER 81-01 Possible Failures of GE Type HFA Relays O Design Manual (1) Section General Design Criteria DC-1000-J O O O - - 0053t/094-6/6
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( 4 Module 20 Checklist Corumitment Matrix checklist Reviewer Commitment Wumber Date PSAR Section Subject
Description:
4 4 4 Applicable Documents: i ITEM YES NO N/A
- 1. Has the intent of the requirements for the j commitment been met?
- 2. Have the requirements been implemented in second order documents Remarks:
a t J Checked by Date 0061t/2/079-6 Figure 6.1-1 Commitment Matrix Checklist a
MODULE 20 CHECKLIST Design Criteria Checklist Reviewer Date Drawing No. Rev. Title IIE! IES.! H.Q Elh
- 1. If design criteria involved more than one discipline, was interdisciplinary review performed and documented? ,,,,,,_ _ .,,,,,_
- 2. Were Design Manual Change Notices (DMCWs) incorporated in Design Criteria? ,,,,,_ _ _
Ex. DPK3r No. _ _ _
- 3. Has DMCW received all required signatures? _ _ _
originator /EGS _ _ _ Licensing Engineer _ _ _ Project Engineer _ _ _
- 4. Was the DMCW incorporated into the appropriate design documents within the required time of days? _ _ _
- 5. Was a Change Control Package initiated if necessary, or were the physical changes mandated by the DMCN performed? _ _ _
REMARKS: C061t/079-6/22 Figure 6.1-2 Design Criteria Checklist
i I MODULE 20
,; OtECKLIST Calculation Checklist Reviewer Instrument Tag No.
s Date Calc. No. Rev. Title 4 CALC.
; pG.
g NUMBER M NO N/A + 1. Does cale. conform to commitment / design criteria? _ _ _ i t 2. Does it identify quality class? _ _ _
- 3. Are the assumptions / engineering judgments clearly noted? _ _
- 4. Is input identified and consistent with criteria? _ _ _
j t 5. Is computer program identified by name and version? _ _ _
- 6. Is output incorporated in drawing or other calc.? _ _ _
drawing No./ calc. No.
- 7. Is calculation checked? _ _ _
- 8. Is cale. reviewed / approved by EGS, chief, etc.? _ _ _
l < 9 Are revisions identified and approved? _ _ _ REMARKS: a 0061t/3/0?9-6 4 Figure 6.1-3 Calculation Checklist
MODULE 20 CHECKLIST P&ID Checklist Reviewer Instrument Tag Wo. Date Drawing No. Rev. Title
- m . m
- 1. Has drawing received all required signatures? _ _
originating Engineer checkers (Cont & Mech.) _ _ Engineering Group Leader (EGL) _ _ Engineering GroLp Supervisor (EGS) _ _ Professional Ent,ineering Stamp _ _ Chief controls Engineer _ _ Project Engineer _ _
- 2. Is the drawing in conformance with ISA standards? _ _
- 3. Does this drawing conform to applicable licensing concitments/ design criteria requirements? _ _
- 4. Was drawing provided for interdiscipline design coordination? _ _
Identify discipline (s) REMARKS: 0061t/4/079-6 1 - Figure 6.1-4 P&ID Checklist
I i l MODULE 20 CHECKLIST Loop Diagram Checklist Reviewer Instrument Tag No. Date Drawing No. Rev. Title O _ m e m
- 1. Has drawing received all required signatures? _ _ _
originating Engineer checkers (cont. & Mech.) _ _.,,,,. _ Engineering Group Leader (BGL) _ _ Engineering Group Supervisor (EGS) _ _ Chief Controls Engineer _ ._._ .___ Project Engineer __ _
- 2. Is the drawing in conformance with selected features from the design requirements:
I/O Signal Compatibility ,_ ,__ Viring diagrams _ ,_ _ Receiver _ __. _ vendor information _ _
- 3. Does this drawing conform to applicable licensing commitments / design criteria requirements? , , , , , .,__. _
- 4. Was drawing provided for interdiscipline design coordination? _.,,_ _ __,
Identify discipline (s)
- 5. Was interdiscipline input / output coordinated properly? ___ ,,__
REMARKS:
)
0061t/5/079-6 O O . . Figure 6.1-5 Loop Diagram Checklist
- =
i l l 1
~
MODULE 20 y CHECKLIST Logic Diagram Checklist Reviewer Instrument Tag No. Date Drawing No. Rev. Title j IIlin ll;s_ Eg lLa
- 1. Has drawing received all required signatures? _ _ _
Originating Engineer Checkers (Cont, & Mech.) _ _ _ Engineering Group Leader (EGL) _ _ _ Engineering Group Supervisor (EOS) _ _ _ Chief Control Engineer _ _ _ Project Engineer _ ,,_ _
- 2. Is the drawing in conformance with selected features from the design requirements:
i
- Vendor Documents _ _ _
System Description _ _ _ Set points _ _ _
- 3. Does this drawing conform to applicable licensing commitments / design criteria requirements? _ _ __
- 4. was drawing provided for interdiscipline design coordination? _ _ _ l Identify discipline (s) l
- 5. Was interdiscipline input / output coordinated properly? _ _ _
REMARKS: 0061t/6/079-6 Figure 6.1-6 Logic Diagram Checklist
I l 1 4 ( j O MODULE 20 CHECKLIST j Data Sheet Checklist Reviewer Instrument Tag No. 1 a
, Date % Drawing Wo. Rev. Title g 135 NO W/A
- 1. Has drawing received all required signatures? _ _ _
originating Engineer Checkers (Cont. & Mech.) _ _ _ Engineering Group Leader (EGL) _ _ _ i Engineering Group Supervisor (EGS) _ _ _ Chief Controls Engineer _ _ _ Project Engineer _ _ _ s 2. Is the drawing in conformance with selected process and design information? _ _ _ Process Data _ _ _ Electrical Requirements _ _ _ Environmental / Seismic Requirements _ _ _ installation Requirements _ _ _ J s
- 3. Was mechanical process calculation performed prior to issue of the drawing? _ _ _
Calc. No.
- 4. Does this drawing conform to applicable licensing l conritments/ design criteria requirements? _ _ _
- 5. was drawing provided for interdiscipline design coordination? _ _ _
- 6. was interdiscipline input / output coordinated 4 .
properly? _ _ _ REPARKS : 0061t/7/079-6 Figure 6.1-7 Data Sheet Checklist
i l l % 1 IODULE 20 CHECKLIST i Piping Area Drawino checklist 4 Reviewer Instrument Tag No. f j { Date }\ Drawing No. , Rev. Title 1 IIE1 XFa N2 IL.h i
- 1. Has drawing received all required signatures? _ _ _
- Originating Engineer Checker _ _ _
Engineering Group Leader (EGL) _ _ _ Engineering Group Supervisor (BGS) ,_ j Professional Engineering Stamp _ _ j Chief controls Engineer _ _ _ lI Project Engineer _ _ _ 1 2. Is the drawing in conformance with selected features from the design requirements: Tap orientation _ _ _ Instrument Location _ _ _ Environmental condition _ _ _ Hazard - - - Flooding _ _ _
- 3. Does this drawing conform to applicable licensing couaitments/ design criteria requirements? _ _
(
- 4. Was drawing provided for interdiscipline design coordination? _ _ _
Identify discipline (s)
- 5. Was interdiscipline input / output coordinated properly? Drawing Rev. _ _
REMARKS: a 0061t/8/079-6 S Figure 6.1-8 Piping Area Drawing Checklist
)
i O MODULE 20 CHECKLIST Installation Drawing Checklist Reviewer Instrument Tag No. Date Drawing No. Rev. Title M M G A N
- 1. Mas drawing received all required signatures? _ _ _
Originating Engineer Checker _ , _ Engineering Group Leader (BGL) _ _ _ Engineering Group Supervisor (EGS) ._,, _ Professional Engineering Stamp _ _ Chief Controls Engineer _ _ _ Project Engineer _ _
- 2. Is the drawing in conformance with selected features from the design calculations-Allowable weight ,,,_ ,__ ,.
Bolt Site & Torque Value _ _ _ Supt Type Calc. No. _ _ _,
- 3. was calculation approved prior to issue of the Drawing? Calc. No. _ ___. _
- 4. Does this drawing conform to applicable licensing cocnitments/ design criteria requirements? _,,,,,. _ _
- 5. Was drawing provided for interdiscipline design coordination? _ _ _
Identify discipline (s)
- 6. Was interdiscipline input / output coordinated properly? Drawing Rev. _ _ _
REMARKS: 0061t/9/079-6 Figure 6.1-9 Installation Drawing Checklist
l
% 1 i
i l MODULE 20 OtECKLIST Procurement Specification Checklist Reviewer Instrument Tag Wo. Date Specification No. Rev. Title ) IIE1 X]lsi M9 H!A
- 1. Did this specification receive required approval signatures on the DRW7 _ _ _
I
- 2. Was interdiscipline review accottplished and DRW signed? _ _ _,
g 3. Did the proposal form contain the quality verification documentation list for Q-class items or require a certificate of empliance? _ _ _
- 4. l Were tests required to verify the specified I performance and, if so, were the tests results documented and accepted by Bechtel? _ _ _
n
- 5. Were SDDRs issued and approved by Bechtel against this specification Ex. SDDR Wo.
Sa. If SDDRs were issued, were design changes required? Ex. SDDR Wo. Page 1 of 2 0061t/10/079-6 Figure 6.1-10 Procurement Specification Checklist (Sheet 1 of 2)
l O 1 ^ 4 J PODULE 20 CHECKLIST Procurement Specification Checklist IE5 ygg J N Q
- O Sb. Did the SDDR adversely affect licensing commitments; if so, was a licensing document deviation issued?
Ex. SDDR Wo. _ _ _
- 6. Were MSCNs incorporated into this specification?
Ex. MSCW Wo. _ _ _ ( 7. Do the requirements of this specification impose the requirements of *esign criteria and licensing 4 commitments documented in the PSAR? _ _ _ 4
- 8. Were CA requirements included in specification? _ _ _
i 1
- 9. Has the supplier QA program required by the specification, been reviewed and approved by Bechtel prior to any fabrication? _ _ _
~~
O 9 a . O 4 i Page 2 of 2 0061t/11/079-6 ( Figure 6.1-10 Procurement Specification Checklist (Sheet 2 of-2)
i l l l l l O MODULE 20 CHECKLIST Construction Specification Checklist Reviewer Instrument Tag No. Date O ' Specification No. Rev. Title IIBM IEE M9 N/.6.
- 1. If specification involved more than one discipline was interdisciplinary review performed and documented? _ _ _
- 2. If specification is identified in the DCCL, was it reviewed and approved by the chief engineer on DPM7 _ _ _
('.
- 3. Were CSCNs incorporated in the construction specification?
Ex. CSCW Wo. _ _ _
- 4. Were incorporated CSCNs noted in the revision block?
Ex. CSCW Wo. _ _ _
- 5. Are design / vendor requirements incorporated?
Ex. Torque value _ _ _ Bolting Hardware _ _ _
- 6. If specification defines safety-related systems or components, were applicable NRC Regulatory
( ouldes and Codes specified? _ _ _ REMARKS: 0061t/079-6/12 e Figure 6.1-11 Construction Specification Checklist
A \ ICDULE 20 CHECKLIST Vendor Document Checklist Reviewer Instrument Tag No. Date Vendor Document Wo. Rev. Title IIBM XEft E2 MA
- 1. Mas this document been properly statused by the responsible engineer? _ _ _
- 2. was vendor data reviewed by affected discipline to satisfy interface requirements? _ _ _
- 3. Are selected data and materials on the vendor document in compliance with the procurement specification? _ _ _
- 4. For Bechtel-reviewed supplier drawings, have the required signatures (responsible EOS and APE or PE) been obtained for revisions to drawings? _ _ _
- 5. Does the supplier's design conform to the licensing coramitments as outlined by the specification? _ _ _
- 6. Was selected data submitted by the supplier properly used in the BPC design documents (i.e.,
calculations)? _ _ _
- 7. Does the Codes and Standards list submitted by the supplier include the applicable revision date of each document?
REMARKS 1 0061t/13/079-6 Figure 6.1-12 Vendor Document Checklist
1 f
.i 1
1 i 2Oj MODULE 20 CHECKLIST
.! Pield Chance Recuests (PCRS) Checklist I 4
- Reviewer Instrument Tag Wo. i
. Date PCR No. Rev. Title M M E O I ; 1. Was PCR dispositioned by PPE? _ _ _
la If document affected was not transferred to field, was HOB concurrence obtained? _ _ _
- 2. Is PCR in compliance with current Design l
Criteria? ._ _ _
- 3. was FCR consistent with assQciated IW requirement (s)?
I i 3a. Does current calculation reflect PCR? _ _ _ Calculation No. 4 Revision i
- 4. For PCRs approved with design change was PCR converted to DCW/DCN-R?CSCW/MSCW?
4 4a. Has the PCR converted DCW/DCW-R or CSCW/MSCW e been incorporated into applicable drawing or
\ specification? _ _ _
i 5. was interdiscipline review performed when required? _ _ _ Sa. Are appropriate signatures on PCR7 _ _ _ Page 1 of 2 0061t/14/079-6 4 4 Figure 6.1-13 Field Change Requests (FCRs) Checklist (Sheet 1 of 2)
1 1 1 1 l i I I l l MODULE 20 l i CHECKLIST Field Chance Recuests (FCRs) Checklist g ygS, S NO W/A Sb. Were other affected documents revised? 4 (List documents reviewed) l
]
- 6. If PCR applies to the specification for Q-class equipment, fire protection or radwaste, was it signed off by Quality Assurance? ,_, _ _ l 1
- 7. Are ' Hazards and Equipment Qualification" attributes j
$ adequately addressed? _ _ _ 1 1
; 8. If PCR was initiated as Authorization to Conplete
! work (ATOW) and disapproved or approved with revision and affected work had already begun, j was a DR written? _ _ _ i
- 9. Are EGS and PFE signatures present? _ _ _
- 10. Has rationale for disposition been documented? _ _ _,_
l
- 11. Were licensing connitments affected? ,,_ _ _
1 ~\ lla. If commitments were affected, was a Licensing Document Deviation initiated? _ _ _ 1 REMARKS: Page 2 of 2 2 0061t/15/079-6 Figure 6.1-13 Field Change Requests (FCRs) Checklist (Sheet 2 of 2)
l [
\ l MODULE 20 CHECKLIST Deviation Report (DR) Check 11g1 j Reviewer Instrument Tag Wo.
Date DR wo. Rev. Title IIE5 XIE! E2 N!h
- 1. Is the deficiency clearly identified? _
I l
- 2. Is the cause of the deficiency clearly identified? ,_, _ _
- 3. Is the. approved disposition clear? , _ , ._
- 4. If item was dispositioned ' Repair,* 'Use-As-Is,*
" Void," and ' Acceptable" was justification prepared? ,_
4a. Did justification require a calculation? ._,.,,_ _, , If so, is calculation checked, approved as required by calculation procedure? ,,,,. _ _ i
- 5. was interface review required / accomplished (interdiscipline. CPC, etc.)? _ ,,,_ _
- 6. Have all required approvals been obtained (BGS, pE. QA)? _ .,, __
- 7. was a licensing commitment affected? ,.,, _ _
If so, has LDD been initiated? _ _ _ 1 1
- 8. Has the deviation been reviewed to determine if the nonconformance contains potential conditions O
U reportable under provisions of 10 CPR 50.55(e) or 10 CFR 217 ,., ,_ RF# ARKS: 0061t/16/079-6 O Figure 6.1-14 Deviation Report (DR) Checklist
MODULE 20 CHECKLIST CSCW Checklist Reviewer Instrument Tag Wo. Date CSCW Wo. Rev. Title N l 4 jig 5 M F.!2 N.l.A
- 1. Did this CSCW receive required approval signatures (responsible EOS, nuelear, EOS, PE, and pQAE)? _ _ ,,,_, !
- 2. Has the EOS provided for the interface coordination of the CSCW: ,
1
- a. _ _ - l (Identify other disciplines)
- b. _ _ _
(HOE) (pre)
- 3. Were design documents revised if necessary (drawings, etc., analys!.s, calculations)? _ _ _
Did the CSCW impact design criteria? _ _ _ 3a. If so, were other design documents revised (e.g., calculations, drawings, etc.)? ,,,,,, _ _
- 4. Does this CSCW conflict with FSAR (lic?nsing) commitments, and, if so, has a licensing document deviation (1.DD) form been initiated by the responsible EGS? ,_,,, _ _
- 5. Are specification change notices being incorporated within time frames required by procedure? _ _ _
page 1 of 2 0061t/17/079-6 Figure 6.1-15 CSCN Checklist (Sheet 1 of 2)
O O MODULE 20 CSCW Checklist IM IES- F.2 F./.h
- 6. Did this change impose spore stringent requirements, and, if so, was a retrofit required of work already in place? - - _,,,_
REMARKS: O O O Page 2 of 2 0061t/079-6/18 Figure 6.1-15 CSCN Checklist (Sheet 2 of 2)
l i $ l d
'O MDDULE 20 CHECKLIST Supplier Deviation Disposition Requests (SDDRs) Checklist f Reviewer Instrument Tag Wo.
I Date SDDR No. Rev. Title ID2! IlEE E9 8
- 1. Did SDDR receive required (QE, PE, QAE) signature? _ _ _
t
- 2. Did SDDR receive required interdisciplinary reviews?
(Identify disciplines.) _ _ _
- 3. Does deviation affect or also apply to previously shipped items?
O If so, has discipline or supplier evaluated for i 10 CFR 50.55(e) or 10 CFR 217 _ _ _ Has the deviation been revised to determine if the ] nonconformance contains potential contitions reportable under the provisions of 10 CFR 50.55(e) or 10 CFR 21? _ _ _
- 4. Does the SDDR conflict with licensing commitments? _ _ _
If so. has a licensing document deviation been submitted? _ _ _
- 5. Has the deviation described in the SDDR been resolved i by revising the affected design documents? _ _ _
- 6. Does BPC approve SDDR contain adequate rationale for Use-As-Is? or
- Repair
- disposition? _ _ _
REMARKS: 0061t/079-6/19 Figure 6.1-16 Supplier Deviation Disposition Requests 1 (SDDRs) Checklist
IODULE 20 CHECKLIST Instrumentatton Index CheckIist , Reviewer Instrument Tag No. Date I i Drawing No. Rev. Title ITE XIS. H2 E/E
- 1. Has document received all required signatures? _ _ _
Originating Engineer Checker _ _ _ Engineering Group Leader (EGL) _,_ ,,,,,,,, Engineering Group Supervisor (EGS) , _ Project Engineer _ _ _
- 2. Is the document in conformance with selected design information? .,_
Y Tag No. ,_ _ _, vendor identification correct _ _ _ , , Classification of the instrument .,_., __ _ Reference drawings _,_, _ _ Process Information _ _ Environmental Designation _ ,, REMARKS: O 0061t/20/079-6 E'igure 6.1-17 Instrumentation Index Checklist
4 l j 1 i l l l
/
a MODULE 20 i CHECKLIST Industry problem Checklist {i Reviewer i Date Drawing No. Rev. Title i M IEE !!9 O
- 1. Is the problem properly interpreted as to scope of work, and with regard to technical considerations? _ _ _
j
- 2. Is the problem reviewed for generic implications? _ _ _
- 3. Is there adequate documentation or technical j justification for resolution of the problem? _ _ _
; 4. Were other disciplines and/or vendors contacted i ! for input into the problem resolution, if required? _ _ _
i I l S. Are the problem and solution reviewed by appropriate project personnel and is the review documented appropriately?' _ _ _ 4 6. Is the resolution of the problem consistent with design criteria? _ _ _ l 1
- 7. Is the solution properly implemented through an acceptable program? _ _
i REMARKS: 1 0061t/21/079-6 4 4 Figure 6.1-18 Industry Problem Checklist
6.2 CONSTRUCTION O Program assessment of the construction section of this module was performed to provide an evaluation of instrumentation and control (I&C) installation at Plant Vogtle. The assessment activities were intended to satisfy the following objectives: () A. Commitment implementation (section 6.2): assessment of incorporation of licensing commitments into the implementing documents. B. Construction assessment (section 6.2.3): assessment of installed I&C equipment to ascertain conformance with O design drawings and specifications and an assessment of quality verification documentation to ascertain implementation of the quality program. The Readiness Review Construction Team for Module 20 consisted of four team members with a combined total of 50 years of construction experience. Assessment activities were performed by team members that have been qualified and certified at other projects to Level 11 capabilities in accordance with American National Standards Institute (ANSI) N45.2.6. Program assessment represents approximately 700 manhours expended by the Construction Team. This included manhours spent familiarizing personnel with the current installation program, the development of the assessment plan, the performance of assessment activities, and the resolution of Readiness Review Findings. 6.2.1
SUMMARY
EVALUATION l The Construction Team assessed 15 hardware items and approximately 100 records during program assessment. The installed hardware was determined to be in conformance with design requirements, and the review of records found that both completed and in-process records adequately reflect an acceptable program for I&C installation. Program assessment resulted in the initiation of one Level II O* finding (20-17) involving discrepancies identified at an I&C material storage area. The Project has completed remedial action and has taken measures, using periodic inspections of storage areas, to preclude recurrence. The finding does not indicate that an inadequate storage program exists or that the (} discrepancies affected the acceptability of installed hardware. The overall conclusion of the Construction Team is that ar acceptable program for installation and inspection of I&C has been established and is resulting in acceptable I&C installation. i
I
\
)
6.2.2 COMMITMENT IMPLEMENTATION Section 3.4 contains the matrix for the commitments identified O1 by the Final Safety Analysis Report (FSAR), responses to Inspection and Enforcement (IE) Bulletins, and Generic Letters that are applicable to Module 20. After identification of the commitments, the Readiness Review Construction Team reviewed each construction commitment and identified the project document
- .4 a t currently implements each commitment. Additionally, review g
was performed to identify the project document that initially implemented the commitment. The commitment matrix identifies seven construction ecmmitments. The commitments were appropriately traced to the implementing documents from the time of initial implementation to current status. 6.2.3 CONSTRUCTION ASSESSMENT The assessment involved a walkdown of the 15 I&C hardware items identified by the Design Team (Table 6.1-1) and an I&C material storage area. The I&C sample was selected to include installed, safety-related I&C that represents the major types of I&C and includes items installed by the principal I&C contractors at Plant Vogtle. The sample was assessed to ascertain conformance to the applicable design drawings, construction specifications, and procedures. Assessment activities were performed using the checklists illustrated in Figures 6.2-1 through 6.2-4. The & checklists identify the specific attributes assessed and W include, as appropriate, the following: o Location / configuration. o Makeup of connections. o Routing of sensing lines. o Welding. o Identification, o Clearances and tolerances. h o Storage requirements. Two of the items in the sample (PSV-8010A and ZS-8010) were not installed and were not assessed. The remaining items were g surveyed and found to be in various stages of construction. The W completed items were found to be in conformance with design requirem ats: for the items in process, the Construction Team concluded that the construction program would ensure acceptable installation. l l The Construction Team also performed a visual assessment of an l I&C material storage area using the checklist illustrated in l 6.2-2
i Figure 6.2-5. As a result of the assessment, the Construction Team issued Readiness Review Finding 20-17, described below: 'I) o Readiness Review Finding 20-17 (Level II)
Description:
Various storage discrepancies, such as segregation of material and cleanliness of storage areas, were identified during a survey of a Pullman ( satellite warehouse (Troy IV). proiect Response: The finding as stated is correct. The areas noted as not meeting storage requirements have been reinspected, corrected, and documented. The Project issued a site instruction that established specific responsibilities and instructions for implementation and documentation of periodic storage and housekeeping inspection requirements in accordance with ANSI N45.2.2 and N45.2.3. Hardware has not been affected by the conditions identified; the above action will preclude recurrence and improve storage conditions. Readiness Review
Conclusion:
.The Construction Team noted that the findings indicated are considered minor problems that can occur occasionally at a construction site but are not-indicative of an inadequate program.
() The Construction Team verified that the storage inadequacies were corrected. Construction assessment also involved a review of the quality verification documents associated with the installation, testing, and inspection of the instruments listed in Table 6.1-1. Approximately 100 documents and records, including the following, were reviewed to evaluate the implementation of construction program requirements: o Inspection checklists. o Hydrotest records. o Tubing / restraint inspection reports. o Weld records. o Material requisitions. The review was performed to assess the specific attributes identified on the checklist illustrated in Figure 6.2-6. The attributes were selected to include the following: o Legibility and retrievability. O o Qualification of special processes / procedures. 6.2-3
Performance of required tests / inspection. l o o Completion of hold points. o Attachment or reference of supplemental documents. o Certification of personnel, equipment, and material. The documents requested by the Construction Team were readily retrievable from the Pullman Power Products and Georgia Power Company vaults. The Construction Team determined that the quality verification documentation was adequate to demonstrate acceptability of the hardware. O O O O O 0049t/093-6 6.2-4
l l MODULE 20 CHECKLIST Instrument Sensina tine Checklist ! i Reviewer Date Instrument lag ho. 150 No. Rev. IllM 1[} NO N/A
- 1. Has drawing received all required signatures?
(Responsible EGS, PE)
- 2. Does installation conf orm to requirements of the ;
construction specification? i
- 3. Has proper alope of sensing lines been maintained? I
- 4. Does unsupported span meet specification requirements?
l
- 5. Have proper tube clamps been used? j
- 6. Does the make-up of tubing connections appear visually acceptable?
i
- 7. Are high/ low points properly vented / drained?
REMARKS: m f i>g I SHEET 1 OF I } 0019t/2/064-6 l , I i l Figure 6.2-1 Instrument Sensing Line Checklist 1 _- -- -- y,<v e gen,_, em---m- m-m, - w-- e+ - - - <w-*g-c >m, q
j 4 l u ! l r l ! 1 l i l i 1
- MODULE 20 CHECKt151 1
l Instrument and Control Eauipment Checklist Date Reviewer j Instrument lag No. ] Drawing No. -Rev. JB YES N3 N/A
- 1. Has installation drawing received all required signatures? __
- 2. Have any vendor recommendations for installation been followed?
- 3. Is orientation of equipment correct per drawing or vendor requirements? (vendor Drawing Number )
- 4. Is weight of equipment within allowable limits for field _
fabricated supports?
- 5. Are mounting bolts tight?
- 6. Is tag /model number correct pe' data sheet?
- 7. Does installation provide f or calibration / venting / maintenance?
- 8. Are any unapproved attachments made to instrument supports?
- 9. 15 equipment protected from adjacent construction activity?
SHEET 1 0F 2 0019t/3/064-6 Figure 6.2-2 Instrument and Control Equipment Checklist (Sheet 1 of 2)
l 5 a ,
- l 1
1 4 4 i ) i i 1 , l l
! l I MODULE 20 CHECKLIST l
1 Instrument and Control Eauipment Checklist i Eeviewer Date Instrument lag No. Drawing ho. Rev. 3 A 3
))JEM YES NO N/A
- Has proper insertion f or thermowells been achieved?
- 10. ,
l i j 11. Is continuity of tubing from root valve to instrument
} acceptable?
i I 4 . . l ] ! REMA MS: 1 I i t 4 i I l i i i 1 1 e 1 I i SHEET 2 0F 2 l 0019t/4/064-6 i 1 ] Figure 6.2-2 Instrument and Control Equipment Checklist (Sheet 2 of 2) l l j
l l MDDULE 20 CHECKtlST Cpntrol Valve Checklist ; Reviewer Date Valve No. I 150 ho. Rev. Vendor Drawings 1. Rev. 4. Rev.
- 2. Rev. 5. Rev.
- 3. Rev. 6. Rev.
lllM M E9 h/l
- 1. Have drawings received required approval /statusing? :
1
- 2. Is tag /model number correct per data sheet? __
- 3. Is flow orientation correct?
- 4. !s orientation of valve and operator correct per vendor /
design requirements?
- 5. Is any associated appurtenances (solenoid, limit switches, relays, etc..) properly installed?
i l REMARKS: SHEET 1 0F 1 0019t/5/064-6 Figure 6.2-3 Control Valve Checklist
l I 1 i 4 MODULE 20 l l CHECKLIST l l Panel Checklist Reviewer Dat; l a Louipment lag No. Dwg. No. Rev. Title l y YES NO N/A l
- 1. Has vendor drawing received proper status?
j (Status 1) I l i l 2. Is equipment tag number correct per specification? l l I i b, 3. Is panel f ront layout correct per approved vendor drawing?
- l. 4. Have panel changes been properly implemented?
(CCPs, FECOs, etc.) i-
] 5. Has proper separation between qualified (IE) instruments been ,
maintained? i
! 6. Does any visible damage to panel exist?
I
! 1. Does panel have light / ventilation? i i
l
! REMARKS:
1 1 t , SHEET 1 0F 1 00191/6/064-6
- 4) .
Figure 6.2-4 Panel Checklist _ . - - ._ _ _ . _ _ _ _ _ . . _ . - - _ . . . . ~ . . . - ._
l MODULE 20 CHECKLIST ILC Material Storace Area Checklist , [ Reviewer Date: ! Location: j lits Xea E9 E!A i l
- 1. Access controls (doors, gates, fences, etc.) evident? .
r
't
- 2. Item in storage adequately identified (tag no., M aass, ;
I material type, etc.)? 3 ASME/Non-ASME materia) ' s i ' .19
. d?
4 Tubing stored in dot tdequately supported and capped? ,
)
i
$. Stainless steel material adequately protected from carbon f atee1 contamination?
1
- 6. housekeeping acceptable (no loose parts, trash, scrap, material)?
1 1 6
- Sheet 1 of 1 0048t/1/064-6
.l , [ f a i Figure 6.2-5 I&C Material Storage Area Checklist
l MODULE 20 CHECKilST Ouality verification Document Checklist Reviewer Date Record No. Title YES NO N/A IT[M
- 1. 15 the record retrievable and legible? _____
- 2. Does the record adequately identify the item to which it applies?
- 3. Are the appropriate design requirements identified?
(drawings, DCNs, FCRs, etc.)
- 4. Is there evidence that any required prerequisite activities were completed?
- 5. Were the required tests / inspections performed per the requirement?
- 6. Are all 00/ANI hold points signed?
- 7. Are referenced welding /hDE procedures appropriately qualified?
SHEET 1 0F 2 0019t/7/064-6 Figure 6.2-6 Quality Verification Document Checklist (Sheet 1 of 2)
l l l l l MODULE 20 CHECKLIST quality verification Document Checklist Reviewer Date Record No, lille i llLM LE,5 !iQ !L.6 j l 8. Are the QC/ Welding personnel appropriately certified?
- 9. are any noted exceptions documented on deviation reports as __ __.
applicable? l l l l REMARKS: I I SHEET 2 0F 2 0019t/8/064-6 Figure 6.2-6 Quality Verification Document Checklist (Sheet 2 of 2) r---w -,m - , , - , , _-, -- _ _ . , _ _ _ . _ _ - _ _ . _ - - _ _ _
. - - - ~ , . .- . .. .- . . _ - . . . = . . .- - - - . . -
7.0' INDEPENDENT DESIGN REVIEW-3 The Readiness Review process includes an independent review of
~O design documents, such as system design criteria, calculations, specifications, and drawings, to ascertain whether proper design requirements were considered and whether design documents -
cor rectly implement l'icensing commitments . This review'is being conducted by Stone & Webster Engineering Corporation and . includes a team of technical and professional experts to assess I the technical adequacy of the design of the work . covered 'by this a nd o th e r mo dule s. - This Independent Design Review (IDR) ensures that the design technically meets commitments and that .the instrumentation and controls within the scope of this module are in fact adequate. The results of the IDR will be provided as~a < separate report. . l () I O 0097p/084-6 i
l l i 1 8.0 PROGRAM ASSESSMENT / CONCLUSIONS 8.1
SUMMARY
OF OPEN CORRECTIVE ACTIONS 8.1.1 SECTION 6.1 ENGINEERING () o Finding 20-11 l Action: Review all level setting diagrams and compare to setpoint list. Notify Georgia Power Company Nuclear Operations of any discrepancies. Revise setpoint list, and level setting diagrams as required, to refer to O level setting diagrams for all data relevant to-level devices. Completion Date: i April 30, 1986. Responsible Orcanization: BPC. 8 .1. 2' SECTION 6.2 CONSTRUCTION There are no open corrective actions. 1 1 O O () 0056t/100-6
1 1 8.2 OUALITY ASSURANCE STATEMENT The process for the development of Module 20 was monitored by the Readiness Review Quality Assurance (QA) staff for general adequacy. The primary focus of the monitoring effort was the identification, documentation, analy;is, and resolution of Readiness Review l O Findings. The finding reports issued by the Readiness Review Team and their responses were reviewed, individually and collectively, for root causes and generic issues; i.e., trends. Based upon review of the responses and commitments to individual finding reports and generic concerns, the resolutions were determined to be adequate. All findings were initially distributed to project QA for review for reportability [10 CFR 21, 10 CFR 50.55(e)] in [) k accordance with existing QA procedures. In addition, findings ) were screened by Readiness Review to determine whether any i required additional evaluation by the project for reportability. j Finding 20-11 was so identified, and is under evaluation as of l April 1, 1986. Other monitoring activities consisted of reviewing personnel qualification and training records for the team members, reviewing the verification plan, and reviewing completed checklists to assure adequate identification of findings. Additionally, an independent reverification was performed on a sampling basis under Readiness Review QA overview to determine the adequacy of the (~ CommitmE't/ Implementation matrixes and the Design / Construction ()} verification efforts. Based upon these monitoring efforts, this module and the Readiness Review Team conclusions are judged to be acceptable. t / N-
%~ h< km.t
,3ohn H. Draggs //
' Readiness Review Team Quality Assurance Representative 0077t/092-6
TECHNICAL CONSULTANT'S CERTIFICATION O On the basis of review of selected Module 20 documentation on instrumentation and controls, the Project Engineering Organization, and appropriate project documents.such as construction specifications, design reports, design criteria, O and selected drawings, I certify that, to the best of my belief and knowledge, the information and conclusions contained herein are factually and technically correct. Under the program described in section 4 of this report and on the basis of corrective actions described in section 6, it is concluded that the commitments of the Vogtle Electric Generating Plant Final () Safety Analysis Report are being implemented and that the design and construction programs that relate to instrumentation and controls have resulted in a final product that meets design requirements and licensing commitments. l O l (:) l EsA , . iA (} Frank J.CnezsWdis, P.E. l l l C:) 0060t/093-6 _ - . _ _ _ _ . , . _ _ _ , _ . . . _ . - . _ - . . _ . _ _ _._ _ _ __ ._ . - _ . . . _ _ _ ~ . . . , . . . . . _ . . ~_
Instrumentation and Controls - Module 20 Readiness Review Board Acceptance The Readiness Review Board has been apprised of the scope and content of Module 20, Instrumentation and Controls. The Board'has reviewed the program verification, as well as corrective actions, both proposed and implemented, by the Vogtle Project. Based upon this review and based upon the collective experience and professional judgement of the members, the Readiness Review Board is of the opinion that the corrective actions proposed are acceptable, and that the instrumentation and controls system at Plant Vogtle is sound and complies with commitments set forth in the FSAR and acceptable practices.
~
L ; _ APPROVED: DATE: 3~ ~ Doug Duttonj Chairman, Rehdiness Review Board Vogtle Electric Generating Plant O O o O 0044t/064-6
Georgia Pow:r Company Proget M:nagimsnt Post Offica Box 282 Waynisboro, Georgia 30830 Telephone 404 724-8114 404 554 9961 p) i Southern Company Services. Inc. Post Office Box 2625 Birmingham, Alabama 35202 b Telephone 205 870-6011 VOnlle U Project /~5 Date: April 2,1986 A Re: Plant Vogtle - Units 1 & 2 Cl Readiness Review Module 20 File: X7BD102 Log: SS-5527 From: 0. Batum To: W. C. Ramsey Engineering has reviewed Module 20, Instruments and Controls, for general accuracy and completeness. To the best of our knowledge and belief, the module is a complete and accurate representation of the Instruments and Controls, and the engineering process and commitments related (q,/ thereto. 1 l i r ,. - f [] Ozen Setum Devdty to Vice President Project Engineering xc: Project File (3 LJ
intsroffica Correspondanco GeorgiaPower d ! April 2,1986 MEM0 T0: W.C. Ramsey ,
SUBJECT:
Plant Vogtle - Units 1 & 2 Readiness Review Module 20 FILE N0: X7BS102 CORRESPONDENCE NO: TSG - 032 ; l SECURITY CODE: NC , i ONuclet.r construction has reviewed Module To the best20. of our knowledge and belief, the Module is a complete and accurate representation of the site Instrumentation and Controls program and commitments related thereto.
- t. 4%
M.H. G00GE Project Construction Manager MSG /GB/rp O - 0 4 l O O 4 I I i O . . t i v.
8.6 RESUMES l The resumes which follow precent a breif professional history of those personnel involved in the development of Module 20. l l MING CHANG, Engineer, Design Team Member
- Mr. Chang has been employed by Bechtel Power Corporation since 1973 and has over 12 years of experience in the nuclear power plant industry. Currently, he reviews field changes and resolves startup field problems for the San Onofre Nuclear Generating Station Units 1, 2, and 3. Previously, he was
('h
'/
responsible for installation details and location drawings of instruments and controls for the Maanshan Nuclear Power Station in Taiwan. Prior to the Maanshan Project, Mr. Chang was assigned to the San Onofre Nuclear Generating Station Units 2 and 3 as a control systems engineer. He has also worked at the San Onofre Nuclear Generating Station Unit 1. Education: Northeastern University B.S., Electrical Engineering M.S., Electrical Engineering P.E., State of California HENRY E. GILBERT, Quality Control Engineer, Construction Team Member Mr. Gilbert began his employment with Bechtel Construction, Inc., in 1974. He has over 22 years experience in the construction, installation, and documentation of HVAC systems for nuclear power plants. Also, he has extensive experience in the inspection and surveillance of various HVAC system components. Mr. Gilbert was previously assigned to Hope Creek Project, where his duties included assisting in the preparation g- of instructions and procedures for the implementation of the plant betterment and modification program. Education: U.S. Navy Machine Mate A School O (_) U.S. Navy Nuclear Power School Drexal University
LEO P. HYDRICK, JR., Instrumentation Quality Control Engineer, Construction Team Member Mr. Hydrick has 7 years of nuclear experience in quality control (QC) engineering with Bechtel Power Corporation. His responsibilities have included supervision of inspection activities required to complete construction of Diablo Canyon Nuclear Units 1 and 2, performing software review activities associated with quality assurance (QA) records completion for Limerick Nuclear Units 1 and 2, developing the QC program and procedures required for the completion of construction at Zimmer Nuclear Unit 1, and supervising inspection activities associated with the construction of Susquehanna Steam Electric Station Nuclear Units 1 and 2. Education: Pennsylvania State University Nuclear Engineering Technology CHARLES H. MULLEN, Engineer, Team Member Mr. Mullen; began his employment with Stone & Webster Engineering Corporation in 1971 and has 15 years experience in nuclear power plant engineering. Currently, he is responsible for preparation of- logic ' diagrams , system descriptions for logic diagrams, instrumentation sections for system descriptions, and preparation of the instrument and control sections for the Millstone Nuclear Power Plant Unit 3 Final Safety Analysis heport. His past experience includes assignments to the Beaver Valley Power Station and the James A. Fitzpatrick Nuclear Power Plant. Education: Mitchell College A.S., Engineering FRANK J. REZENDES, Supervisor of Control Logic, Technical Consultant lh M r '. Rezendes began his employment with Stone & Webster Engineering Corporation in 1970 and has 14 years of experience in the nuclear power plant industry. He has served as a principal and a lead control engineer at various nuclear projects, including the Nine Mile Point Nuclear Station Unit 2, the Beaver Valley Nuclear Plant Unit 2, and the Haddam Neck Nuclear Station. He has also served as a lead control engineer on design verifications and cost estimate g studies of non-Stone & Webster Engineering Corporation projects. W 8.6-2
He is currently on the staff of the". Control.. System D,ivision. (} serving as the supervisor of the Control Logic Group.- ; Education: . .. fc , e n .
. i N '
Massachusetts Ma :itime Academy . ., r .r .u , B.S., Marine Engineering #. - O Southeaster Massachusetts Universi.tyn; a> B.S., Electrical Engineering ,., ,, Masters in Business Administration i 3 , e e P.E., State of Massachusetts . ROBERT C. SOMMERFELD, Supervising Construction Engineer. _ ~_, Construction Team Member Mr. Sommerfeld has over 20 years of experience in the nuclear power industry. His responsibilities have included design assistance; material selection and performance; corrosion control: preparation of technical specifications; review and approval of vendor and contractor special process procedures and quality programs; preparation of project QA manuals; interface with regulatory agencies: participation in code writing bodyg, activities: and control of welding operations,.. forging, heaty O treatment, and QA/QC activities related to the. manufacture of' pipe, pipe fittings, extruded headers, vessels, and piping _ subassemblies. Education: University of Wisconsin B.S., Mechanical Engineering JAMES B. STEELE, Senior Electrical Quality Control Engineer, Construction Team Member Mr. Steele has 5 years of nuclear experience as an electrical O inspector and QC engineer at several nuclear construction projects. His responsibilities have included QC activities, as I well as QA surveillance of contractors' QA programs and i supervision of QC departments. His most recent assignment was l supervisor of the Electrical QC Department at Diablo Canyon. ' O Education: Western Illinois University , O 8.6-3 _ _ . ~ . - _ . _ _ . . . _ _.___________..__._._._.)
i i RAJINDER S. WALIA, Engineering Supervisor, Design Team Leader Mr. Walia has been employed by-Bechtel Power Corporation since 1970 and has 15 years experience in the nuclear power plant industry. He is presently working as a member of the control systems engineering staff, where his responsibilities include providing technical support to inhouse nuclear and fossil-fired power plant projects. From 1982 to 1984, he worked as deputy engineering group supervisor (EGS) at the Vogtle Electric Generating Plant. From 1972 to 1982, Mr. Walia worked as an EGS at San Onofre Nuclear Generating Station Units 2 and 3. He has also worked as a control systems engineer on the design and construction of Lake Hubbard Power Plant Unit 1. Education: B.I.T. Ranchi B.S., Mechanical Engineering C.S.U., Los Angeles M.S., Electrical Engineering P.E., State of California O l l l O til OOO74t/093-2 8.6-4}}