ML20078A555
| ML20078A555 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 01/12/1988 |
| From: | GEORGIA POWER CO. |
| To: | |
| Shared Package | |
| ML20078A351 | List:
|
| References | |
| PROC-880112, NUDOCS 9406020213 | |
| Download: ML20078A555 (300) | |
Text
{{#Wiki_filter:O e'~g (J VOGTLE ELECTRIC GENERATING PLANT UNIT 2 READINESS REVIEW PROGRAM 6 g MODULE 4 - MECHANICAL EQUIPMENT AND PIPING n V Ol67d/356-7 9406020213 940512 PDR ADDCK 05000424 P PDR
PREFACE O Georgia Power Company (GPC), in order to gain added assurance of the operational readiness of the Vogtle Electric Generating Plant (VEGP), conducted a pilot Readiness Review Program for Unit 1. The VEGP pilot Readiness Review Program was a systematic, indepth 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 22 modules. Each module is a predefined scope of VEGP activities. Each module provides 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. Activities common to several modules are defined in General Appendixes. There are seven 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 pilot Readiness Review Program was conducted on a . schedule to provide added operational readiness assurance to GPC l gs management in support of the VEGP Unit 1 operating license. j Conclusions reached regarding programmatic and technical - adequacy through review of VEGP Unit 1 are indicative of Unit 2, i since both units are being designed and constructed together ' under a single quality assurance prograr with like management controls, procedures, specifications, and criteria. The Unit 2 Readiness Review Program extends the results of the Unit 1 review by assessing activities, hardware, and documents within the scope of selected modules and ascertaining compliance with licensing requirements. l 1 The VEGP Unit 2 Readiness Review Program is being conducted on a schedule to provide added operational readiness assurance to GPC management in support of the VEGP Unit 2 operating license. The VEGP Readiness Review Program is not intended to eliminate I or to diminish any authorities or regulatory responsibilities I now assigned to or exercised by the Nuclear Regulatory Commission or GPC. Further, the Readiness Review Program is not ; intended to change the techniques of inspections or assurance of j 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 i so that they may initiate any needed corrective actions in an orderly and timely manner. C Ol69d/005-8 iii 1
The work processes and regulatory commitment compliance covered by each module scope will be assessed by, and the module prepared and reviewed by, individuals collectively familiar with the design, construction, and preoperational processes of lh 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 findings and resulting dispositions are reviewed by the Project Quality Assurance staff and are input into the normal project process for safety significance and potential reportability evaluations in accordance with regulatory requirements. O l l l l t Ol69d/005-8
i EXECUTIVE
SUMMARY
O This module documents a review process conducted to ascertain whether the design and construction aspects of mechanical l l l equipment and piping in Unit 2 of the Vogtle Electric Generating l Plant (VEGP) comply with licensing commitments and whether compliance is verifiable using existing project documentation. The review program for Unit 2 used the results of the Unit 1 review program as a base, and focused on differences between the units. These differences included added or revised licensing commitments and program changes resulting from project development or corrective actions to Nuclear Regulatory Commission (NRC) findings, project findings, design changes, or
- hardware modifications. The review consisted of technical and programmatic evaluations of the design and construction processes and results. Project documents such as design criteria and procedures; design output such as specifications, drawings, and calculations; and construction results such as installed hardware and quality documentation were examined !
during the review. Discrepancies noted during review activities were issued to the Project as findings. Following receipt and evaluation of the response, the findings were categorized as follows to indicate their relative importance: Level 1 - Violation of licensing commitments, project procedures, or engineering requirements with indication of safety concern. I i Level II - Violation of licensing commitments or ; engineering requirements with no safety concern. Level III - Violation of project procedures with no safety concern. The Readiness Review Program mechanical equipment and piping evaluation in VEGP Unit 2 consisted of three major activities: Commitment Implementation Review Readiness Review has maintained the listing of commitments ! for design and construction developed during the Unit 1 Readiness Review through review of Final Safety Analysis Report (FSAR) amendments and letters to the NRC. The Project Engineering and Construction organizations were issued the listing of commitments applicable-to this module at the beginning of the review period; and the Project provided Readiness Review with updated imple-mentation information which is presented in Section 3.
}
v 0166d/007-8 ;
Unit 1 Finding Followup During the assessment of Unit 1, the Project committed to the performance of certain corrective actions. For Unit 2, h Readiness Review provided Project Engineering and Construction with a list of Unit 1 findings and corresponding corrective actions. The Project evaluated those applicable to Unit 2 activities and informed Readiness Review as to the action taken. The listing of Unit 1 findings and Unit 2 actions is presented in Section 5. Assessment The Unit 2 assessment of mechanical equipment and piping consisted of an evaluation of commitment implementation, Unit 1 finding followup, and an assessment of design and construction activities to ascertain project compliance to commitments. , During the assessment Readiness Review verified, by selective sampling, updated implementation and Unit 1 finding followup information provided by the Project. During the assessment of design and construction, Readiness Review chose a sample of design documents, installed piping and equipment, and quality records to verify acceptance to specified criteria and conformance to installation and procedural requirements. Thirty-five design documents, approximately 500 feet of installed piping, 7 major pieces of equipment, and those referenced project documents which support acceptance of the sample and certification of personnel were examined during the assessment. Eleven findings were issued during the assessment. None were classified as Level I two were classified as Level II; and nine were classified as Level III. The Level II and III findings were judged to be instances of procedure noncompliance or inadequate procedural requirements with no safety concern and do not indicate, either individually or collectively, programmatic concerns. Overall assessment of design and construction activities found those activities progressing in conformance with established programs and criteria. i Readiness Review Conclusion l Based on the results of the above review action, and on the j implementation of effective corrective actions as committed to I by the Project, Readiness Review concludes that adequate I programs exist to ensure that: the required quality for design and construction has been achieved, objective evidence of that ll l Ol66d/007-8
quality has been documented, and licensing commitments within the scope of this module have been implemented. O a b I E O Vii > 0166d/007-8 !
l l l MODULE 4 i MECHANICAL EQUIPMENT AND PIPING l TABLE OF CONTENTS ' Section 1 Introduction > 1.1 Scope i 1.2 Module Organization ' l.3 Project Status Section 2 Organization ' 2.1 Introduction i 2.2 Design ! 2.3 Construction 2.4 Organizational Changes l Section 3 Commitments i l 3.1 Introduction l 3.2 Commitment and Implementation Matrices Section 4 Program Description i I 4.1 Design j O 4.2 4.3 Construction Program Changes Section 5 Audits and Inspections 5.1 Introduction 5.2 Project Audits 5.3 Nuclear Regulatory Commission Inspections 5.4 Reportable and Potentially Reportable Items 5.5 Unit 1 Finding Followup ' Section 6 Program Assessment 6.1 Introduction ! 6.2 Program Description , 6.3 Summary and Conclusions 6.4 Assessment Activities and Results 6.5 Unit 2 Findings , Section 7 Assessment of Module Adequacy Project Quality Assurance : Readiness Review Board Section 8 Assessment Plan and Checklists 0168d/005-8 IX
i 1 INTRODUCTION ! C:) 1.1 SCOPE OF MODULE e Module 4 is one in a series of modules that provide an evaluation of the design, construction, and preoperational testing of the Vogtle Electric Generating Plant Unit 2. It is intended to describe the method of complying with the project' ~ commitments found in the Final Safety Analysis Report (FSAR) and is not intended to make further commitments or revise in any - way, prior commitments. If any differences exist between the , commitment description in this document and the FSAR, those differences are unintentional and the FSAR shall take precedence and shall define the project commitments. , The scope of this module encompasses the design, procurement, ; and construction activities regarding safety-related mechanical ; equipment and piping systems classified as American Society of
- Mechanical Engineera Boiler and Pressure Vessel Code, Section III, Classes 1, 2, and 3, which are included in Unit 2 1 I
piping systems that'are not a part of the nuclear steam supply system. i 1 s O 0148d/005-8 1-1 m y g g -pw, u-- -- , - - - , - - , - - - - - -e
a a + _- O O l l 9 0148d/005-8 1-2
1.2 MODULE ORGANIZATION r~ , k_N) This module is divided into the following sections:
- 1. INTRODUCTION - Includes a definition of the scope boundaries.
- 2. ORGANIZATION - A brief description of the project organizations and the division of their responsibilities as applicable to this module.
- 3. COMMITMENTS - Project licensing commitments pertaining to mechanical equipment and piping within the scope of this module as found in the Final Safety Analysis Report, responses to generic letters, and responses to Nuclear Regulatory Commission (NRC) Inspection and Enforcement Bulletins. This section also lists the documents that demonstrate implementation of these commitments.
- 4. PROGRAM DESCRIPTION - A brief description of the 1 processes for design and construction applicable to the scope of this module.
- 5. AUDITS AND INSPECTIONS - Listings of findings from )
Quality Assurance (QA) audits and NRC inspections )
/~' applicable to the scone of this module, and conducted !
I since Readiness Review's assessment of Unit 1. Readiness Review's findings, findings of the Independent Design Review, and NRC violations resulting from the Unit 1 review of this module are listed, their ; applicability to Unit 2 is indicated, and the methods i of compliance to corrective actions are presented. Descriptions of special investigations, if any, are also presented.
- 6. PROGRAM ASSESSMENT - A description of the assessment plan development, plan implementation, and results from the assessment including corrective actions.
- 7. ASSESSMENT OF MODULE ADEQUACY - The evaluations and conclusions of this module by the Project, QA, and the Readiness Review Board.
- 8. ASSESSMENT PLAN - A copy of the module assessment plan and checklists used during the assessments are included.
0148d/005-8 1-3
._2- s2 - ~ - .a +> --
0 0 0 0148d/005-8 1_4
1.3 UNIT 2 PROJECT STATUS ('s~)/
- As of July 1, 1987, the Module 4 cutoff date, the design of safety-related mechanical equipment and piping systems in the balance of plant was 98 percent complete.
As of July 1987, the construction status of Unit 2 components and systems within the scope of this module was as follows: Percent Complete o Equipment installation 58.0 o Piping installation
- Large bore 99.0
- Small bore 91.4 O
l l i
)
0148d/005-8 1-5
2 ORGANIZATION AND DIVISION OF RESPONSIBILITY O
2.1 INTRODUCTION
4 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, Georgia, is responsible for the design, procurement, and construction of the Vogtle Electric Generating Plant. The Bechtel Western Power Company (BWPC) is contracted by GPC to provide architect / engineering services. BWPC is the American Society of Mechanical Engineers (ASME) authorized N-certificate holder for piping installed by Pullman Power Products (PPP) and the GPC Nuclear Construction Team, except for those portions of the nuclear steam supply system (NSSS) for which Westinghouse Electric Corporation (Westinghouse) has the N-certificate responsibility. When BWPC acts as designee for GPC, it may perform activities assigned to GPC where specifically permitted by the ASME Boiler and Pressure Vessel (B&PV) Code, Section III, Division 1. GPC is the owner and, as an ASME-authorized NA-certificate imider, purchases and controls ASME B&PV Code items and provides ensite construction services for calibration, maintenance, documentation, document control, and nonconformance control. PPP and GPC are the installers (ASME-authorized NA-certificate holders) of ASME B&PV Code, Section III, Division 1, piping systems and are responsible for installation, field fabrication, nondestructive examinations, leak tests, and inspections. Westinghouse Electric Corporation has N-stamp responsibility for i the reactor coolant system, bottom-mounted instrument tubing, reactor vessel head vent and seal leak detection leak-off : appurtenance, pressurizer safety and relief valve assembly, l pressurizer surge line, and resistance temperature detector bypass manifold. These components and the associated Westinghouse work activities are discussed in Module 16. i Interfaces between Westinghouse and BWPC are established through project procedures and construction specifications. Nuclear Installation Services Company is an installer (ASME-authorized NA-certificate holder) for certain ASME B&PV Code, Class 1, 2, 3, NF, CS, and MC components, appurtenances, piping subassemblies, and supports furnished under the Westinghouse scope of supply. These work activities are l discussed in Module 16, NSSS. The Hartford Steam Boiler Inspection and Insurance Company is the ASME-authorized nuclear inspection agency contracted to l O i 0140d/007-8 2-1 i
perform the ASME B&PV Code-required inspections at the Vogtle Electric Generating Plant jobsite. This section includes a brief description of the organization and responsibilities of GPC, BWPC, and PPP as related to the scope of this module. O 9 0140d/007-8 2-2
2.2 DESIGN ORGANIZATION Engineering design of the facilities in Module 4 is performed
,under the direction of the Bechtel Western Power Company (BWPC) ,
project engineering manager (PEM) who takes project direction from Georgia Power Company (GPC) PEM, as shown on Figure 2-1. BWPC PEM provides project direction to the mechanical design project engineer and mechanical, nuclear, and plant design engineering group supervisors (EGSs) who combine to form the nucleus of the Design Engineering (DE) organization as shown on Figure 2-2. The EGSs receive funct.onal and technical direction from their respective discipline chief engineers. In addition, Environmental Qualification and the Westinghouse Vogtle-Structural Analysis Mobile Unit (V-SAMU) also provide technical support. Each DE discipline is supervised by an EGS, who also provides technical direction and guidance for the respective Installation Engineering (IE) discipline. The mechanical installation project engineer takes functional and administrative direction from the PEM but receives project direction from the mechanical discipline manager. The discipline work is broken down into several activities which are supervised by engineering group leaders reporting to the EGS. 2.2.1 DESIGN ORGANIZATION CHANGES SINCE THE UNIT 1 ASSESSMENT O The BWPC Vogtle engineering organization, previously known as the Home Office Engineering (HOE) and Project Field Engineering At that time, the (PFE), underwent a change in February 1987. HOE and PFE organizations were reorganized by transferring the HOE engineers-to the jobsite and establishing a DE group and an IE group as described in Section 2.2.2. 2.2.2 CURRENT DESIGN ORGANIZATION The present plan of organizations under EGSs for engineering groups involved in mechanical work and process piping are presented in the following paragraphs. 2.2.2.1 Desian Engineering Three groups in DE are responsible for the primary engineering ; design of Module 4 facilities. The Mechanical Group is ; responsible for process design, development of piping and instrumentation drawings, safe shutdown analyses, mechanical systems, feedwater and condensate systems, and steam systems. The Nuclear Group is responsible for licensing support, shielding, technical specifications support, and hazards-analyses. The Plant Design Group is responsible for piping design, including materials conformance and compliance to O 0140d/007-8 2-3
construction codes. All of these groups have the responsibility of providing technical direction to their counterparts in the IE organization. 2.2.2.2 Installation Engineering The IE organization performs the engineering work necessary to support construction by providing coordination between installation and design activities. IE consists of six groups, three of which perform work related to Module 4. The Mechanical Systems / Equipment Group is responsible for mechanical equipment, equipment installation, system installation, and valve installation. The Plant Design Group is responsible for materials and layout, reach rods, construction specifications, valve specifications, codes and standards, nozzle loads, vendor pipe, and the as-built reconciliation of certain piping. The B31.1 Design Group addresses nonsafety-related piping. Two other groups in IE, the American Society of Mechanical Engineers (ASME) Piping and Supports and the As-built Reconciliation Groups, which are parts of the Westinghouse V-SAMU organization, are responsible for piping stress analysis and pipe support design addressed in Module 11. The Instrumentation Group is addressed in Module 20. l 2.2.3 BECHTEL RESPONSIBILITIES 1 Within the scope of this module, BWPC is responsible for the overall design and the development, control, and issuance (for construction) of supporting design documentation for the ASME B&PV Code, Section III, Division 1, mechanical systems and system components. As the N-certificate holder for ASME B&PV Code, Section III, systems (excluding the Westinghouse scope), BWPC has the following responsibilities, divided between the DE ! and IE organizations according to their primary design involvement or construction support requirement: o Providing design and construction specifications for components, appurtenances, and component supports that are to be constructed in accordance with ASME B&PV Code, Section III, Division 1. The design and construction specifications, in their entirety, shall be the principal documents governing the design, fabrication, installation, examination, and testing of ASME B&PV Code, Section III, Division 1, items. o Establishing controls to verify that purchased materials, items, and services, whether by the GPC home office or field, meet the requirements of ASME B&PV Code, Section III. Division 1, and the design 0 0140d/007-8 2-4
1 l 1 specifications. These controls include the preparation, l review, approval, and issue of material requisitions: I O' evaluation and selection of suppliers' source ' surveillance inspection; and preparation, review, and approval of special handling procedures. o Reviewing installers' quality program manuals, work plan procedures / construction performance standards, welding procedures, qualification records, postweld heat treatment, and nondestructive examination procedures. o Reviewing, dispositioning, and approving Field Change Requests and Deviation Reports. o Providing project engineering records and supplier quality records and establishing with GPC the list of records to be maintained permanently. o Obtaining and maintaining an ASME certificate of authorization to apply the appropriate ASME N-symbol stamp to ASME B&PV Saction III, Division 1, items. o Obtaining the services of an authorized inspection agency to perform code inspections via GPC purchase orders. o Defining the scope and extent of ASME B&PV Code, Section () III, Division 1, items requiring application of an N-stamp. o Identifying items by line or system designator number and project classification which includes the ASME classification and requires, according to specifications, the NA- and/or NPT-stamp that shall be applied. o Reviewing required records, data, and supporting documentation for completeness and accuracy of each code item. o Certifying each N-5 Code Data Report within the BWPC scope of responsibility. o Preparing procedures related to the BWPC scope of work. o Reviewing and determining the status of the installers' hydro test procedures prior to tests. o Reviewing records generated for the pr( caration and review of code data packages maintained at the jobsite by the NA-installer and GPC. O 0140d/007-8 2-5
o Auditing ASME B&PV Code, Section III, Division 1, jobsite functions performed for BWPC by GPC (document control, documentation, receiving inspection, storage and maintenance, and GPC material supplier activities). f In addition, BWPC reviews and approves the V-SAMU initiated stress calculations on systems within the BWPC i scope of responsibility, o Reviewing field-generated drawings (piping drawings drafted by Pullman Power Products and V-SAMU). O O 0140d/007-8 2-6
l l 2.3 CONSTRUCTION ORGAN 12ATION Georgia Power Company (GPC) Nuclear Construction has the primary responsibility for the construction of Plant Vogtle. This is under the overall direction of the vice president and Vogtle project director and the inline management of the vice president-Vogtle project construction (VP-VPC) and project construction manager, as shown on Figure 2-1. They provide direction to the contractors on the schedule and budget, supply all materials, provide drawings and specifications developed by project engineering, and perform surveillance of construction activities. GPC Mechanical Project Section '4 one of four principal organizations involved in the installation of Module 4-related t facilities. The mechanical discipline manager (MDM) in this organization provides supervision of construction, as shown on Figures 2-1 and 2-3. For direct work, GPC Nuclear Construction employs Pullman Power Products (PPP) for fabrication and installation of the major portion of American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel (B&PV) Code, Section III, Division 1, piping, components and equipment. GPC has organized a Nuclear Construction Team (NCT) and has given it the responsibility of installing ASME B&PV Code, Section III, piping and equipment in and around the , auxiliary feedwater (AFW) pump house. The fourth organization, j GPC Quality Control (QC) section, under the direction of the () l ! manager of QC, is responsible for the inspection of this construction work. Additionally, Chicago Bridge and Iron (CBI) was employed for the installation of containment penetration assemblies and the field fabrication and installation of pipe racks and certain large ASME tanks. Their activities, however are not addressed in this module for the following reasons: o Work activities within the scope of this module were performed to the same programs as assessed during the Unit 1 Readiness Review program, o Project Quality Assurance (QA) conducted an extensive audit (CP01-87/10) of CBI quality documentation in . February, 1987. During the audit, one audit finding l report, AFR 1008-II, was issued which resulted in the revision of GPC Field Procedure GD-A-07 to require that quality records generated during completion of extra l work orders be transmitted to the storage vault. The ' appropriate records were transmitted to the vault and QA verification has demonstrated compliance with the revised procedure. l O 0140d/OO7-8 2-7 l l _ _ _ __ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ - _ _ _ _ _ - _ _ _ _ _ _ _ _ - - - _ . . _ _ _ _ _ . a
2.3.1 CONSTRUCTION ORGANIZATION CHANGES SINCE THE UNIT 1 ASSESSMENT The establishment of the NCT by GPC is the only significant O change in organization for the construction of Unit 2. The organization, responsibilities of the team members, and the scope of work for this group are described in detail in Section 2.3.4. 2.3.2 GEORGIA POWER COMPANY MECHANICAL DISCIPLINE GPC Mechanical Discipline has overall control of contractors and oversight of their programs in the following areas: o Development of mechanical construction procedures. o Resolution of problems. o Provision of material to contractors. o Provision of schedule and budget information, o Interface with other groups on problem identification and resolution. 2.3.3 PULLMAN POWER PRODUCTS PPP activities are all under the direction of the resident construction manager who has the overall responsibility for their quality and timely completion. Personnel reporting to him are discussed in the following paragraphs. 2.3.3.1 Chief Field Engineer The chief field engineer is responsible for the administration, coordination, training, and supervision of field engineering personnel and their activities. The following personnel assist him: o An office engineering manager who is responsible for the administration of the Engineering Department main document control center, o A field engineering supervisor who supervises process field engineers and field document control clerks. O 0140d/007-8 2-8
2.3.3.2 Construction Superintendent The construction superintendent is responsible for all PPP site fabrication, installation, testing, flushing, and system turnover. The following personnel assist him: o The assistant construction superintendent who is responsible for training of the PPP staff and craft personnel assigned to construction, fabrication, and . installation activities. , t o The flushing superintendent who is responsible for liaison and coordination between PPP and the GPC Nuclear Operations personnel for performance of flush 1 0 activities. .j o A system completion supervisor, added for Unit 2 , construction who is responsible for providing system scope documents to Construction Engineering and QA. He also monitors system status during construction. , e A welding coordinator who is responsible for technical l' implementation and operation of the automatic welding program, and provides technical assistance for other welding activities. (} 2.3.3.3 Ouality Assurance Manacer The PPP QA manager reports administratively to the resident i construction manager. He reports to the director of QA on all technical and functional matters relating to QA. He is ! responsible for effective implementation of QA and QC ; procedures. The following personnel assist him: o An assistant QA manager, who, in addition to assisting ; the QA manager, is responsible for preparation, revision and control coordination of audit responses of - site procedures, and implementation of the QA program in the absence of the QA manager. o A field QA supervisor who is responsible for training : and the qualification of QA personnel. He and his staff ! of QA engineers are responsible for review of drawings, process sheets, and code data reports, as well as control of welder qualification records, Deviation ! Reports (DRs), and storage of such QA records. o A QC supervisor who is responsible for scheduling and the performance of all QC activities. He and his staff of QC inspectors are responsible for receipt inspections of ASME B&PV Code, Section III, components, visual , 0140d/007-8 2-9
inspections, weld inspections, final inspections, welder qualifications, and test control. o A nondestructive examination (NDE) supervisor who is a Level II or III certified NDE technician and is responsible for training NDE technicians and supervising their work. He assures that NDE is performed to approved procedures. o A training officer who is responsible for the coordination and conduct of all field training and maintains records of such training. o A OA engineering supervisor, added for Unit 2 construction, who is responsible for coordination of OA activities, flushing, and work activities relating to the turnover and/or release of components and systems. 2.3.4 GEORGIA POWER COMPANi NUCLEAR CONSTRUCTION TEAM In addition to installing safety-related ASME B&PV Code, Section III, Class 3, mechanical equipment and piping in and around the Unit 2 AFW pump house, the NCT installs thrt portion of the ASME B&PV Code, Section III, Class 2, miscellaneous leak detection aystem which penetrates the containment. The NCT is under the management of the Project construction manager, as shown on Figure 2-3. He reports technically and administratively to the VP-VPC and is responsible for the performance of field construction activities and provides direction through the personnel described below. 2.3.4.1 GPC Nuclear Construction Team Superintendent The NCT superintendent acts as the craft supervisor for the construction work performed by the NCT. 2.3.4.2 Nuclear Construction Team Mechanical Discipline Manacer The NCT MDM reports technically to the VP-VPC and provides direction to the lead engineer and other supervisors of field engineering sections and services. He has overall responsibility for the following Code-related activities: o Implementation of project procedures that are in the ASME-Field Construction Procedures Manual, o Participation in processing DRs. 0140d/007-8 2-10 l i
o Field surveillance activities to ensure compliance with established procedures and mandatory hold points. [)D \._ o Initiation and maintenance of in-process documentation, and upon completion, forwarding the data to the GPC manager of QC (MQC) for review and storage. In carrying out these responsibilities, the NCT MDM is assisted by the following personnel: o The lead engineer who has field engineers under his supervision. o The project welding supervisor who is responsible for controlling welding filler material, making available welding procedure specifications, conducting weld procedure and welder qualification testing,and maintaining qualification records. He assists in processing welding-related DRs, and provides technical direction for welding and postweld heat treatment. o The Procedures Control Group issues and controls GPC field procedures and nuclear construction procedures , manuals. i o The field document control clerk who issues and controls design documents for field use. 2.3.4.3 Georgia Power Company Ouality Control Section The QC section is directed by the MQC who reports to the VP-VPC, as shown on Figure 2-3. The MQC provides project direction to the supervisors in the QC Section. This includes inspecting construction activities performed directly by GPC, including the NCT, and/or surveillance inspecting construction activities performed by subcontractors for which GPC is responsible. The MQC is responsible for maintaining the GPC ASME QA Manual and providing liaison with the ASME and Authorized Nuclear Inspection Agency in matters associated with compliance to the Code, the manual, and the control of the ASME B&PV Code symbol stamps. The mechanical QC section supervisor, who reports to the MQC, is responsible for the inspection of construction activities within i the Module 4 scope. He is assisted by QC groups assigned to . piping, hangers, instruments and controls, receiving, measuring and test eouipment, and NDE in carrying out the following responsibilities: o Administration of the QC and NDE programs. 0140d/OO7-8 2-11
A o Training, qualification, and certification of inspection personnel. o Performance and documentation of inspection activities. o Inspection of receiving, storage, handling and maintenance of safety-related non-ASME equipment (receiving inspection of ASME III materials, though the responsibility of GPC, is performed by PPP as a subcontracted service to GPC). o Administration of a nonconformance control system including validation of DRs. o Administration of a system for calibration of measuring and test equipment. o Technical direction to subcontractors and material testing laboratories. o Surveillance (by sampling-type inspections) of contractors' final inspection and NDE activities, o Review of scope of NCT Code work with the MDM and authorized nucleat inspector (ANI), including selection of hold points. o Making the ASME QA Manual available to the ANI, including approved revisions. i o Verification of completion and approval of N-5 Code Data Packages prior to ANI review. o Ensuring proper application of the NA-stamp after ANI and VP-VPC authorization. o Exercising stop work authority for activities not in accordance with the ASME QA Manual and/or the Code. Also under the MQC is the Document Review Section which has the following responsibilities: o Review of quality verification documentation and maintenance of QC records. o Review of subcontractors' and suppliers' quality verification documentation and its inclusion into the QC records system. o Operation of the quality records vault and document review section. 9 0140d/OO7-8 2-12 h
I s 2.3.5 OTHER CONSTRUCTION SUPPORT ORGANIZATIONS l C'onstruction activities are supported by other GPC groups, two of which are described below. l 2.3.5.1 Warehouse .i The warehouse is under the direction of the warehouse i supervisor, as shown on Figure 2-3. He is responsible for the
- receipt, storage, and issue of materials, components, and equipment for the project. ;
i 2.3.5.2 Drawino and Document Control Drawing and Document Control (DDC) is under the direction of the manager of administrative operations who now reports to the , VP-VPC, as shown on Figure 2-1. DDC is responsible for the { following activities: 3 o Reproduction and distribution of design documents (e.g., drawings, specifications, change documents, etc.) in accordance with a controlled distribution list. o Audit of site organizations to assure maintenance of proper handling and control of design documents. , i 1 l r .O 0140d/007-8 2-13 l o
,. . _ . , . . . . .I
,q d d,/~N LEGEND
()
* * * * * *
- P ROJE CT COOR DIN A TION VICE PRESIDENT 8, VOGTLE PROJECT DIRECTION VOGTLE PROJECT --- FUNCTION AL DIRECTION DIRECTOR --- ADMINISTR ATIVE AND FUNCTIONAL DIRECTION GENERAL E XECUTIVE SPECIAL MANAGER CONSULTANT PROJEC TS OU ALITY VOGTLE PROJECT MANAGER ASSURANCE LICE NSING OPE R ATIONS I I l ................. l i i l I I i OJECT M2 PROJECT VOGTLE PROJECT GENERAL M AN AGE p VICE PRESIDENT OWIM D MON LIC ENSING ENGINE E RING VOGTLE PROJECT VOGTLE PROJECT
" L MANAGER MANAGER SUPPORT CONSTRUC TION MANAGER MANAGER MANAGER I
PROJECT ET MANAGER MANAGER OF ENGINE E RING CONS TRUCTION MECHANICAL p OF MANAGER D I QUALITY CONTROL OPE R ATIONS B CHTE GR
'L._._._._._._._._._._._._.
i L _ _ __ _ __ _ 7 l l j
\
1 PROJECT PROJECT MECHANICAL ENGINE E R - ENGINE ER - q
. DISCIPLINE HOME OFFICE FIELD MANAGER
.l
! I I
l PROJECT PROJECT D R AWING E NGIN E E R - ENGINE E R - CONST RUCTION MECHANICAL MECHANICAL SUPE RVISOR DESIGN INSTALL ATION Figure 2-1 Vogtle Project Organization (Module 4 Scope)
O LEGEND CHIEF PROJECT ENGINEER MECHANICAL MECHANICAL
- VOGTLE PROJECT DIRECTION DISCIPLINE DESIGN
- --- -== TECHNICAL DIRECTION -
- TECHNICAL & FUNCTIONAL DIRECTION l
t FIRE PROTECTION MANAGER 3 I I I MECHANICAL NUCLEAR PL ANT DESIGN ENGINEERING ENGINEERING ENGINEERING GROUP GROUP GROUP SUPERVISOR SUPERVISOR SUPERVISOR I I I PROJECT ENGINEER MECHANICAL I INSTALLATION I i i , I I : i l i I , p _ _ _ _ _ _ _ _ _ _ _I _ _ _ _ _ _ _ _ .1 _ _ _ _ _ _ _ _ J l I I , I I MECHANICAL ASME 831.1 AS BUILT SYSTEM / INSTRUMENTATION PIPING & PLANT DESIGN SUPPORTS DESIGN RECONCILIATION E.7UIPMENT i Figure 2-2 Mechanical Design and Installation Engineering Organizations
.x
~-
GENEi".AL MANAGE R PR VP - VOG TLE VOGTL E GA PROJECT VOGTLE PROJECT ENCINEERINO I 7 MANAGER SUPPOR T MANAGER LEGEND: i g I (BECHTEL) g y VOGTLE CONSTRUCTION b__ SITE MGM GE NER AL MANAGE R PROJ PROCUREME N T s OlRECTION a ggy I VOGTLE CONSTRUCTION COORDINATION og g
- l
"*- ADMINISTRATIVE AND AUDIT GROUP
! ! l*
FUNCTIONAL OtREcisON PROKCT PROJECT M AT E Ri ALS PROCUREMENT l A PERFORMS NCT WORK MANAGER MANAGER . e PE RFORMs OTHER WORK l. WAREHOUSE
- SUPE Rv:SoR O I
l l NCY MECHANICAL ROJECT l CONT O N g OMPLINE MGR MANAGER g MANAGER I l MECH A ENT A SUPERINTENDENT A MECHANICAL O REVIEW g DISCIPLINE OC SECTION PROMCT WELDING A (CR APT SUPE RVISOR) ANAGER
- MANAGER SECTION ,
g
- SUPE RVISOR a f PROCEDURE A , - P1 PING OC -
CONTROL GROUP O , FIELD DOCUMENT A HANGER OC g - O PROJECT ENGINEER CONTROL CLE RK MECHANICAL -. INSTALLATION INSTRUMENT & A FIELD S ENGINE E RING A CONTRM OC SUPE RVISOR RECEIVING A OC O M&TE A OC S FIELD ENGINEERS A DESUS
- NDE -
g ADMINIST R ATION Figure 2-3 GPC Field Organizations (Including Nuclear Construction Team)
3 COMMITMENTS
3.1 INTRODUCTION
This section contains, in matrix form, licensing and project commitments and the corresponding implementing documents. These are presented in two matrices, the commitment matrix and the implementation matrix. Commitments A commitment is an obligation to comply with the requirements of an industry standard, Regulatory Guide, Branch Technical Position, or owner plan of specific action. For the purposes of Readiness Review, commitments are identified from the following sources: o Final Safety Analysis Report (FSAR), including responses to Nuclear Regulatory Commission (NRC) questions. o Responses to Inspection and Enforcement Bulletins. o Correspondence to the NRC. These sources were reviewed and commitments were selected using the following guidelines: O o Specific design and/or construction requirement, o Specific standards of acceptance.
)
o Specific cited technical data used as a design basis i and/or unique design methodology. o Specific codes, standards, or regulatory requirements. Descriptions, detailed data and/or parameters resulting from design activities, general codes, and regulations are not generally considered licensing commitments. These include: 1 1 o Dimensions. o System operational concepts or operational descriptions. ! o Design calculation details such as strength parameters, flow rates, etc. o References to general regulations or standards such as 10 CFR 50, American Society of Mechanical Engineers (ASME). American Concrete Institute, etc. (specific requirements from such bodies, however, are commitments). Ol72d/005-8 3-1
Implementation An implementing document is a working level document, either the program control or the installation procedure, that imposes the requirements of the commitment to a specific activity. Implementation of commitments is typically found in the following: o Design Criteria. o Material Specifications. o Construction Specifications. o Project Reference Manual. o Field Procedure Manual. o Startup Manual. Additionally, the Project has a commitment to comply with 10 CFR 50, Appendix B, Quality Assurance Criteria, and industrial standards such a's American National Standards Institute ANSI /ASME N45.2 and N45.2.ll. Although they may not have been identified as specific commitments in this module, Readiness Review considered the applicable requirements of these types of commitments in preparing and assessing the scope of h work presented by this module. Differences, if any, between the commitment descriptions in this section and the FSAR are unintentional and the commitments in the FSAR take precedence. l Ol72d/005-8 3-2
. . , --- .=.. - . - _ . ._ _ . . _ _ _.. _ _ _ . _ . . 1 i 3.2 COMMITMENT AND IMPLEMENTATION MATRICES O- During the Unit 1 Readiness Review Program, the task force I i performed a systematic review of licensing documents and l identified the Project commitments. Once identified, these commitments were listed in a document called the commitment matrix. Readiness Review has maintained the matrix current for ; design and construction through review of Final Safety Analysis l Report (FSAR) Amendments and letters to the Nuclear Regulatory Commission. Additionally, during the Unit 1 Readiness Review, the task force identified project controls that implemented the commitment requirements (i.e., design criteria, specifications, construction procedures, etc.) and listed them on a document called the implementation matrix. For Unit 2, the commitment matrix and implementation matrix were transmitted to the Project for verification of the implementation matrix data to the latest documents. Upon completion, the updated matrix was returned to Readiness Review who verified the accuracy, on a sampling basis, as described in Section 6. Changes in module commitments from those presented in the Unit 1 module are identified by a vertical row of X's in the left margin of the commitment matrix. The commitment and implementation matrices are presented follouing this section. The commitments are current through Amendment 34 of the FSAR. O O Ol72d/005-8 3-3
e PLANT V0GTLE UNIT 2 READINESS REVIEW PROGRAM COMMITMENT MATRIX
=====================================s REF. COMMITMENT COMMITMENT COMMITMENT DOCUMENT / MOD DES CON FSAR REMARKS NUMBER SOURCE SECTION SUBJECT FEATURE ULE IGN ST AMEN
======= ========== ========== ========= ==================== ==================== === :== ===
. ===a s=- ;=;=:=;-=: = : : = = :.
6 EMPLANATION OF FIELOS REF. NO. - A reference neeber that corresponds to the appropriate flee entry le the geplenostettom entrlu CONNITNENT SOURCE - The documeet costeleleg the comeltment IFSAR. Generic Letter. 1.E. bulletle Response, etc I CONNITNENT SECTION - Identifies the FSAR sectles, letter number, or questlos mueber CONNITNENT SUBJECT - The subject of the FSAR section or Generic Letter DOCUMENT / FEATURE - The document discussed in the FSAR section or the pleet festore descrlbed le the FSAR section NODULE - The modele for ehich the comalteemt is implemented DESIGN / CONSTRUCTION - An X Is pieced ender the heedlag for the orgeottettom responsible for leptementottee of the commitment FSAR ANENDNENT - FSAR emeedeemt member for reelsed comaltments le aero 403 le placed In thls colume for chaeges made prior to Amendment 93 totert of Welt 1 Reedleess Reeleell NOTE: Commiteomt ebenges from those presented la the Welt I module are Identitled by a vertical roe of X*s la the left mergle.
O Page No. 1 O O 11/10/87 PLANT V0GTLE UNIT 2 READINESS REVIEW PROGRAM MODULE 04 COMMITMENT MATRIX CURRENT TRRU FSAR AMENDMENT 34
======================================
REF. COMMITMENT COMMITMENT COMMITMENT DOCUMENT / MOD DES CON FSAR REMARKS MUMBER' SOURCE SECTION SUBJECT FEATURE ULE IGN ST AMEN
======= ========== ==================== ==================== ==================== === === === ==== ====================
1509.00 FSAR 1. 9. 1. 2 NPSR FOR ECC AND RG 1.1 REY. O. 04 X 0 REF. 6.2.2.2.2.3.2 & CONTAINMENT HEAT 11/70 SECT. 6.3 REMOVAL SYSTEM PUMPS 682.0? FSAR 1. 9. 26. 2 QUAL. GROUP CLASS. RG 1.26 REV. 3 04 X 0 REF. TABLE 3.2.2-1 AND STANDARDS FOR 2/76 WATER. STEAM & RADNASTE CONTAINING COMPONENTS OF NPP 683.00 FSAR 1. 9, 27. 2 ULTIMATE HEAT SINK RG 1.27 REV 2 1/76 04 X 0 REF. FSAR 9.2.5 FOR NUCLEAR POWER PLANTS 1532.00 FSAR 1. 9. 29. 2 SEISMIC DESIGN RG 1.29 REV. 3 04 X 0 REF. TABLE 3.2.2-1 CLASSIFICATION 9/78 1855.00 FSAR 1. 9. 31. 2 CONTROL OF FERRITE RG.I.31 04 X 0 CONTENT IN STAINLESS STEEL WELD METAL 4681.00,FSAR 1. 9. 37. 2 QA REQUIREMENTS FOR ANSI M45.2.1-1973 04 X 0 CLEANING OF FLUID SYSTEMS AND ASSOCIATED COMPONENTS 1543.00'FSAR 1. 9. 46, 2 PROTECTION AGAINST BTP MBB 3-1 AND ASB 04 I O REF. TABLE 3.6.1-2 & PIPE BREAR INSIDE 3-1 SECT. 3.6 CONTAINMENT WCAP-8172-A. ANSI 20.2 DRAFT IN LIEU OF RG 1.46 1551.00 FSAR 1. 9. 53. 2 APPLICATION OF RG 1.53 REV. O. 04 X 0 REF. 7.1.2.6 & SINGLE FAILURE 6/73 15.0.8 CRITERION 154.00 FSAR 1. 9. 61. 2 DAMPING VALUES FOR RG 1.61 REV. D. 04 X 0 SEE FSAR 3.7.B.] AND SEISMIC DESIGN OF 10/73 3.7.N.1 NUCLEAR POWER PLANTS
l , Pege Ms. 2 l 11/10/87 PLANT V0GTLE UNIT 2 READINESS REVIEW PROGRAM j MODULE 04 COMMITMENT MATRIX CURRENT THRU FSAR AMENDMENT 34
======================================
REF. COMMITMENT COMMITMENT COMMITMENT DOCUMENT / MOD DES CON FSAR REMARES NUMBER SOURCE SECTION SURJECT FEATURE ULE IGN ST AMEN
======= ========== ==================== ==================== ==================== ==- === === ==== ====================
X 711.00 FSAR 1. 9. 82. 2 SUMPS FOR EMERGENCY RG 1.82, 6/74 04 X 19 SEE FSAR 6.2.2 AND X CORE COOLING AND G.3.2 X CONTAINMENT SPRAY X SYSTEMS 1565.00 FSAR 1. 9. 81. 2 DESIGN AND FAB. CODE RG 1.84, REY. 20, 04 X 0 REF. TABLE 1.9-1, CASE ACCEPT. ASME 11/82 PARA. 5.2.1.2 TABLE III, DIV. I 1.9-3 1569.00 FSAR 1. 9. 85. 2 MATERIAL CODE CASE RG 1.85, REV. 20, 04 X 0 REF. TABLE 1.9-2 ACCEPT. ASME III, 11/82 1.9-3, PARA. 5.2.1.2 DIV. I 1611.00 FSAR 1. 9.139. 2 GUIDANCE FOR RRR MODIFIED TO PROVIDE 04 X 0 AS DESCRIBED IN FSAR DESIGN SAFETY-GRADE COLD 5.4.7 SRUTDOWN IN ACCORDANCE WITR RG 1.139, REV. O. MAY 78 1595.00 FSAR 1. 9.141. 2 CONTAINMENT RG 1.141 REY. O, 04 X 0 REF. 6.2.4 ISOLATION PROVISIONS 4/78 FOR FLUID SYSTEMS 1599.00 FSAR 1. 9.148. 2 FUNCTIONAL SPEC. FOR RG 1.148, REY. O, 04 X 0 REF. TABLE ACTIVE VALVE 3/81 3.9.B.3-10 ASSEMBLIES IN SYSTEMS IMPORTANT TO SAFETY 808.00 FSAR 3. 1. 4 CONFORMANCE WITH NRC 10CFR50, APP. A. GDC 04 X 0 GDC, CONTAINMENT 41 ATMOSPRERE CLEANUP DJ9.00 FSAR 3. 1. 4 CONFORMANCE WITH NRC 10CFR50, APP. A, CDC 04 X 0 CRITERIA STATES TRAT GDC. INSPECTION OF 42 SYSTEMS SRALL BE CONTAINMENT DESIGNED FOR ATMOSPRERE CLEANUP PERIODIC INSPECTION. SYSTEM G G S
O. Iage No 1I/10/87 3 O O - PLANT V0GTLE UNIT 2 READ 1 MESS REVIEW PROGRAM , MODULE 04 COMMITMENT MATRIX CURRENT TRRU FSAR AMENDMENT 34 1
======================================
l REF. COMMITMENT COMMITMENT COMMITMENT DOCUMENT / MOD DES COM FSAR REMARKS NUMBER SOURCE SECTION SUBJECT FEATURE ULE IGN ST AMEN
======= ========== ==================== ==__================ ==================== === === === ==== ====================
1743.00 FSAR 3. 1. 5 PIPING ETSTEMS 10CFR50 APP. J 04 X 0 SEE FSAR 3.1.3 PENETRATING GDC54 CONTAINMENT 1744.00 FSAR 3. 1. 5 RCPB LINES CLOSED SYSTEM 04 X 0 SEE FSAR 3.1.5 - i PEMETRATING OUTSIDE CONTAINMENT GDC55 CONTAINMENT - RRR CONSTRUCTED TO ASME SYSTEM III CLASS 2
- 1753.00 FSAR 3. 2. 2 VEGP QUALITT GROUP RG 1.26 & RG 1.29 04 X 0 CLASSIFICATIONS 1754.00 FSAR 3. 2. 2 VEGP SEISMIC DESIGN RG 1.29 04 X .,
0 CLASSIFICATION SYSTEM , 859.00 FSAR 3. 2. 2-1 PRINCIPAL CODES AND (TEMA-C. OR TEMA-R 04 X 0 TABLE 3.2.2-1. NOTE STANDARDS FOR TUBULAR EXCR. MFR. (g) T.3.2.211 ASSOC. CLASS C OR R 880.00 FSAR 3. 2. 2-1 PRINCIPAL CODES AND ASME III. CLASS 04 X X 0 TABLE 3.2.2-1 COL. STANDARDS FOR 1.2.3 OR MC. MF. OR (g) 73.2.2-1 CS 4916.00 FSAR 3. 2. 2-1 NSCW SYSTEM DESIGN NSCW VALVES AND 04 X 0 SHEET 14 ITEM 10 PIPING OUTSIDE CONTAINMENT ARE ASME III CLASS 3. 4917.00 FSAR 3. 2. 2-1 NSCW SYSTEM DESIGN NSCW VALVES AND 04 X 0 SREET 14 ITEM 11 PIPING INSIDE CONTAINMENT ARE ASME III CLASS 2. + 4932.00 FSAR 3. 2. 2-1 BORIC ACID STORAGE BORIC ACID STORAGE 04 X 0 SREET 7 ITEM 2 TANE (BAST) TANK IS ASME CLASS 3 4933.00 FSAR 3. 2. 2-1 BORIC ACID STORAGE BORIC ACID STORAGE 04 X 0 SREET 7 ITEM 2 TANK (BAST) TANK IS SEISMIC CATEGORY l _________.__._____.-_________m-____---.m_< . _ _ . _ _ _ _ __.m - _ _2 _-_2_ r -_ _ _ _ _ _ _ _ - v-. __ ___ - - , , *
- _ _ - _ _ - ___m .a e_______m . > _ _ _- _ _ _ _ _ _ _ . - - _ - _ _ = _
7_________________. Page No. 4 11/10/87 PLANT VOCTLE UNIT 2 READINESS REVIEW PROGRAM MODULE 04 COMMITMENT MATRIX CURRENT THRU FSAR AMENDMENT 34
======================================
REF. COMMITMENT COMMITMENT COMMITMENT DOCUMENT / MOD DES CON FSAR REMARKS NUMBER SOURCE SECTION SUBJECT FEATURE ULE IGN ST AMEN
======= ========== ==================== ==================== ==================== === -== === ==== ==== ===============
924.00 FSAR 3. 5 MISSILE PROTECTION 10CFR50 APP. A. GDC 04 X 0 4 1767.00 FSAR 3. 5. 1. 2. 2 2 INCH AND LARGER HYDROSTATIC TESTING 04 X 0 VALVE DESIGN IN ACCORDANCE WITH CRITERIA TO PRECLUDE ASME III VALVE BONNET EJECTION 1764.00 FSAR 3. 5. 1. 2. 2.A 2 INCH AND LARGER ASME III 04 X 0 VALVE DESIGN CRITERIA TO PRECLUDE VALVE BONNET EJECTION 1765.00 FSAR 3. 5. 1. 2. 2.B 2 INCH AND LARGER CONTROL OF LOAD 04 X 0 VALVE DESIGN DURING BOLT CRITERIA TO PRECLUDE TIGHTENING VALVE BONNET EJECTION 941.00 FSAR 3. 6. 1 POSTULATED PIPING BTP ASB 3-1 04 X 0 CONCERNS EVALUATION FAILURES IN FLUID OF CONSEQUENCES ON SYSTEMS OUTSIDE ESSENTIAL SYSTEMS. CONTAINMENT 942.00 FSAR 3. 6. 1 POSTULATED PIPING BTP MEB 3-1 04 X 0 CONCERNS EVALUATION FAILURES IN FLUID OF CONSEQUENCES ON SYSTEMS INSIDE & ESSENTIAL SYSTEMS. OUTSIDE CONTAINMENT 947.00 FSAR 3. 6. 1. 2 SUB-COMPARTMENT BN-TOP-4, REV 1 04 X 0 PRESSURE ANALYSIS (OCTOBER 1977) 948.00 FSAR 3. 6. 1. 2 HIGH ENERGY LINE THERE ARE NO 04 X 0 LOCATIONS HIGR-ENERGY LINES IN THE PROXIMITY OF THE CONTROL ROOM O O O
O Page No. 5 O O 11/10/87 PLANT VOCTLE UNIT 2 READINESS REVIEW PROGRAM MODULE 04 COMMITMENT MATRIX CURRENT THRU FSAR AMENDMENT 34
================================e=====
REF. COMMITMENT COMMITMENT COMMITMENT DOCUMENT / MOD DES CON FSAR REMARRS NUMBER SOURCE SECTION SUBJECT FEATURE ULE IGN ST AMEN
======- ========== ==================== ==================== ==================== === === === ==== ==e=========e=======
951.00 FS AR - 3. 6. 2. 1 RIGH ENERGY PIPE BTP MEB 3-1 04 X 0 BREAK LOCATIONS BREAKS (EXCLUDING ASSUMED PER FSAR REACTOR COOLANT 3.6.2.1.1.A.2 LOOP) 952.00 FSAR 3. 6. 2. 1 HIGH ENERGY PIPE BTP MEB 3-1 04 X 0 BREAKS IN CONTAINMENT PENETRATION AREAS 954.00 FSAR 3. 6. 2. 1. l.A HIGH ENERGY PIPE BTP MEB 3-1 04 I O BREAK LOCATIONS BREAK INTERMEDIATE ASSUMED PER FSAR LOCATIONS (ASME III 3.6.2.1.1.A.1 CLASS I) 950.00 FSAR 3. 6. 2. 1. l.A. I HIGH ENERGY BREAK BTP MEB 3-1 04 I O PIPE BREAK DELETION LOCATIONS IN REACTOR BASED ON REFERENCES COOLANT LOOP (ASME NUMBERED 2, 9 AND III CLASS I) 10 0F FSAR 3.6.2 956.00 FSAR 3. 6. 2. 1. 1.B HIGH ENERGT BREAK BTP MEB 3-1 04 X 0 LOCATIONS (CLASS 2 & 3) X 5107.00 FSAR 3. 6. 2. 1. 1.B. 4 HIGH ENERGY MAIN NO WELDED 04 X 30 ALTERNATE TO BTP MEB X STEAM AND FEEDWATER ATTACHMENTS WITHIN 5 3-1 B.I.C (2) PER X SYSTEMS PIPE BREAKS NOMINAL PIPE NRC LETTER D'TD X POSTULATED AT DIAMETERS OF HIGHEST 6-28-84 (NG-84-51) INTERMEDIATE STRESS LOCATION (S) LOCATIONS X 5108.00 FSAR 3. 6. 2. 1. 1.B. 4 PIPE BREAKS NO WELDED 04 X 30 ALTERNATE TO BTP MEB X POSTULATED AT ATTACHMENTS WITHIN 3-1 B.I.C (2) PER I INTERMEDIATE 3-X SQ. ROOT OF (RT) NRC LETTER D*TD X LOCATIONS IN HIGH OF HIGREST STRESS 6-28-84 (NG-84-51) ENERGY PIPING LOCATION (S) SYSTEMS OTHER THAN MAIN STEAM AND FEEDWATER
Page No. 6 11/10/87 PLANT V0GTLE UNIT 2 READINESS REVIEW FROGRAM MODULE 04 COMMITMENT MATRIX CURRENT TRRU FSAR AMENDMENT 34
- ====================================
REF. COMMITMENT COMMITMENT COMMITMENT DOCUMENT / MOD DES CON FSAR REMARKS NUMBER SOURCE SECTION SUBJECT FEATURE ULE IGN ST AMEN
======= ========== ==================== ==================== ========- ========== === === === ==== ====================
955.00 FSAR 3, 6. 2. 1. 1.C NON-NUCLEAR (NOT BTP MEB 3-1 04 X 0 BREAK LOCATIONS ASME) PIPING BREAK ASSUMED PER FSAR LOCATIONS 3.6.2.1.1.C 961.00 FSAR 3. 6. 2. l. 2. 2.A LONGITUDINAL BREAK BTP MEB 3-1 04 X 0 SEE REF. NO. 950 FOR POSTULATION AT PIPE BREAKS IN RCL INTERMEDIATE POINTS OF HIGH ENERGY SYSTEMS OTHER THAN RCL 957.00 FSAR 3. 6. 2. 1. 2. 4 THRU WALL LEAKAGE IN BTP MEB 3-1 04 X 0 FLOODING EFFECTS MODERATE ENERGY PIPE FROM PIPE BREAKS
- FLOODING EFFECTS DETERMINED ON BASIS OF 30 MIN. OPERATOR TIME REQUIRED TO INITIATE CORRECTIVE ACTION.
958.00 FSAR 3. 6. 2. 1. 2. 4.A THROUGH-WALL LEAKAGE BTP MEB 3-1 04 X 0 CRACKS POSTULATED IN MODERATE ENERGY PIPING UNLESS EXEMPTED BY BTP MEB 3-1 959.00 FSAR 3. 6. 2. 1. 2. POSTULATION OF PIPE BTP MBB 3-1 04 X 0 TRERE ARE NO CLASS 1 4.C(l) BREAKS AND TRRU WALL MODERATE ENERGY LEAKAGE IN ASME III LINES CLASS I PIPING, MODERATE ENERGY 960.00 FSAR 3. 6. 2. 1. 2. POSTULATION OF PIPE BTP MEB 3-1 04 X 0 4.C(2) BREAKS AND THRU WALL LEAKAGE IN ASME III CLASS 2 AND 3 & NON-NUCLEAR PIPING. MODERATE ENERGY O O O
O Page No. T O O ll/10/R7 ' PLANT VOCTLE UNIT 2 READINESS REVIEW PROGRAM MODULE 04 COMMITMENT MATRIX CURRENT THRU FSAR AMENDHENT 34
======================================
REF. COMMITMENT COMMITMENT COMMITMENT DOCUMENT / MOD DES CON FSAR REMARKS ' NUMBER SOURCE SECTION SUBJECT FEATURE ULE IGN ST AMEN
======= ========== ==================== =============,======= ==================== === === === ==== ====================
5099.00 FSAR 3. 6. 2. 3. 2. l.A INTEGRITY OF MINIMUM PERFORMANCE 04 X 0 ESSENTIAL COMPONENTS CAPABILITIES NOT AND ESF SYSTEMS REDUCED BELOW THAT REQUIRED TO PROTECT AGAINST THE POSTULATED BREAR S100.00 FSAR 3. 6. 2. 3. 2. 1.8 INTEGRITY OF CONTAINMENT LEAK 04 X 0 ESSENTIAL COMPONENTS TIGHTNESS IS NOT
. AND ESF SYSTEMS DECREASED BELOW
' DESIGN VALUE IF ^ ' BREAK LEADS TO A LOCA 5101.00 FSAR 3. 6. 2. 3. 2. 1.C INTEGRITY OF PROPAGATION OF 04 X 0 ESSENTIAL COMPONENTS DAMAGE LIMITED TO AND ESF SYSTEMS EXTENT THAT A PIPE BREAK WRICR IS NOT LOCA WILL NOT CAUSE A LOCA OR STEAM OR FREDWATER LINE BREAK 1841.00'FSAR 3. 6. 2. 3. 2. 2.A RESTRAINT OF LARGE PROPAGATION OF BREAK 04 X 0 RCL BRANCR LINES TO UNAFFECTED LOOPS PREVENTED 1842.00 FSAR 3. 6. 2. 3. 2. 2.B RESTRAINT OF LARGE PROPAGATION OF BREAK 04 X 0 3.6.2.3.2.2.B RCL BRANCR LINES IN AFFECTED LOOP DOES NOT EXCEED 20% OF FLOW AREA 0F RUPTURED LINE 966.00 FSAR 3. 6. 2. 4. I PROTECTIVE ASSEMBLY BN-TOP-2 SECT. 3.0 04 X 0 DESIGN CRITERIA. BARRIER AND SHIELD DESIGN 4370.00 FSAR 3. T.B. 1-1 DAMPING VALUES FOR PERCENT OF CRITICAL 04 X 0
-FIXED BASE DAMPING FER MODE STRUCTURES AND COMPONENTS 4 y-9 w-9y s-y-mn- -f 'a +Prr- pg- +te-- m ye 5-ret /P hM-* ='-e-, -w-- -- e- A c - ' +- w - - ---- - - -
l l Page No. 8 11/10/87 PLANT V0GTLE UNIT 2 READINESS REVIEW PROGRAM MODULE 04 COMMITMENT MATRIX CURRENT TRRU FSAR AMENDMENT 34
======================================
REF. COMMITMENT COMMITMENT COMMITMENT DOCUMENT / MOD DES CON FSAR REMARKS NUMBER SOURCE SECTION SUBJECT FEATURE ULE IGN ST AMEN t ======= ========== ==================== ==================== ==================== === === === ==== ==================== 1778.00 FSAR 3. 8. 2. 1 PIPE ATTACRED TO ASME III, CLASS 2 04 X 0 CONTAINMENT WALL PENETRATION SLEEVES 1779.00 FSAR 3. 8. 2. 1. 4 ISOLATION VALVE ASME III, CLASS MC 04 X 0 ENCAPSULATION VESSELS AND BELLOWS EXPANSION JOINTS 1786.00 FSAR 3. 8. 2. 1. 5 PROCESS PIPE MAXIMUM OPERATING 04 I O PENETRATION TEMPERATURE RANGE ASSEMBLIES (RIGR 445 DEGREES F - 557 TEMP. PIPING) DEGREES F , m 1787.00 FSAR 3. 8. 2. 1. 5 PROCESS PIPE DESIGNED TO LIMIT 04
~
X 0 PENETRATION CONCRETE MAXIMUM ASSEMBLIES (RIGR TEMPERATURE TO 200 TEMP. PIPING) DEGREES T 1989.00 FSAR 3. 8. 2. 4. 4 STEEL CONTAINMENT. ASME III. ART 04 X 0 ISOLATION VALVE NE3000, 1974 TRRU ENCAPSULATION VESSEL SUMMER 1976 ADDENDA ASSEMBLIES, DESIGN 1781.00 FSAR 3. 8. 2. 4. 5 DESIGN OF FLUED READ ASME III, ARTICLE 04 I O OF PROCESS PIPING NC-3000 1977 THRU PENETRATION SUMMER 1978 ADDENDA ASSEMBLIES 1788.00 FSAR 3. 8. 2. 5 STRUCTURAL ASME III SUBSECTIONS 04 X 0 ACCEPTANCE CRITERIA NC (CLASS 2 PIPING) FOR STEEL ITEMS AND NE (CLASS MC OTRER TRAN LINER COMPONENTS) PLATE AND SLEEVE ASSEMBLIES 1789.00 FSAR 3. 8. 2. 6.A MATERIALS, O.C. & ASME III CLASS 2 04 X 0 SPECIAL CONSTRUCTION PIPING COMPLIES WITR TECHNIQUES SUB. NC, ART. NC-2000 9 - 9 9
O Page No. 9 O O " i 11/10/87 PLANT V0GTLE UNIT 2 READINESS REVIEW PROGRAM MODULE 04 COMMITMENT MATRIX CURRENT THRU FSAR AMENDMENT 34 .
====================================== !
REF. COMMITMENT COMMITMENT COMMITMENT DOCUMENT / MOD DES CON FSAR REMARKS t NUMRER SOURCE SECTION SUBJECT FEATURE ULE IGN ST AMEN
======= ========== ==================== ==================== =========e========== === === === ==== =================*==
1782.00 FSAR 3. 8. 2. 7 TESTING OF CLASS 2 ASME III. NC-6000 04 X X 0 FOR CONSTRUCTION
. PIPING ASSEMBLIES IMPLEMENTATION SEE FORMING PRESS. BDR. NUMBER 880.10 WITRIN CONTAINMENT 1790.00 FSAR 3. 8. 2. 7 TESTING /ISI CLASS 2 CONTAINMENT 04 X 0 STRUCTURAL INTEGRITT TEST USES 1.15 TIMES DESIGN PRESSURR X 5026.00 FSAR 3. 9.B. 1. 5. I WELD INSPECTION ASME III 1977 04 X X 20 ADDED BY FSAR AMEND.
I ACCEPTANCE CRITERIA EDITION THRU WINTER 20 X 1977 ADENDA X X 5027.00 FSAR 3. 9.B. 1. 5. 1 WELD INSPECTION ANSI B31.1 CODE 1977 04 X X 20 ADDED BY FSAR AMEND. X ACCEPTANCE CRITERIA EDITION THRU WINTER 20 X 1977 ADENDA i X X 5348.00 FSAR 3. 9.B. 3 ASME III. CLASS 1 2 DESIGN OF CLASS I 04 X 34 ADDED BY FSAR AMEND. X & 3 COMPONENTS. PIPING IS IN 34 , I X COMPONENT SUPPORTS. ACCORDANCE WITR X AND CORE SUPPORT SUBSECTION NB 0F STRUCTURES 1977 EDITION THRU SUMMER 1979 WITH STATED EXCEPTION X 5349.00 FSAR 3. 9.B. 3 ASME III. CLASS 1, 2 DESIGN OF CLASS 2& 04 X 34 ADDED BY FSAR AMEND. X & 3 COMPONENTS.- -3 PIPING IS IN 34 X COMPONENT SUPPORTS. ACCORDANCE WITH X AND CORE SUPPORT SUBSECTIONS NC & ND STRUCTURES 1974 EDITION TRRU SUMMER 1975 WITH STATED EXCEPTIONS 1676.00 FSAR 3. 9.B. 3. 2. I BOP SAFETY-RELATED IN SROP RYDROTEST OF 04 X 0 ACTIVE PUMPS CASING TO 150% OF DESIGN PRESSURE a _ . - . . . . , - - . . . . ~ , ~ ~ _ . . - .. . ,. - n.. .- .- ,, , . .. -, --. . ..- ,.-. _ --- - . _ _ - -
Page No. 10 11/10/87 PLANT V0GTLE UNIT 2 READINESS REVIEW PROGRAM MODULE 04 COMMITMENT MATRIX CURRENT THRU FSAR AMENDMENT 34
======================================
REF. COMMITMENT COMMITMENT COMMITMENT DOCUMENT / MOD DES CON FSAR REMARES NUMBER SOURCE SECTION SUBJECT FEATURE ULE IGN ST AMEN
======= ========== ==================== ==================== ==================== === === === ==== ====================
IS79.00 FSAR 3. 9.B. 3. 2. 2 BOP SAFETY-RELATED HYDROTEST - ASME III 04 X 0 ACTIVE VALVES 1707.00 FSAR 3. 9.B. 3. 2. 2 BOP SAFETY-RELATED TO VERIFY OPENING & 04 X 0 ACTIVE VALVES CLOSING TIMES WITHIN FUNCTIONAL TEST SPECIFIED LIMITS 1688.00 FSAR 3. 9.B. 3. 3. I MAXIMUM ALLOWABLE 110% OF STEAM 04 X 0 INTERNAL PRESSURE OF GENERATOR SRELL MAIN STEAM PIPING OR DESIGN PRESSURE AS HEADER AT SAFETT PER ASME III, VALVE INLET N0ZZLB NC-7411 1687.00 FSAR 3. 9.B. 3. 3. 1 OPEN SYSTEM (PRESS. ASME III, CODE CASE 04 X 0 RELIEF) 1569 (N-40) 5102.00 FSAR 3. 9.B. 3. 3. 1 RELIEF VALVE SPACED ON READER SO 04 X 0 CONNECTIONS TRERE IS NO LOCAL INTERACTION 5103.00 FSAR 3. 9.B. 3. 3. 1 REACTION FORCES AND BLOWDOWN LOAD 04 X 0 MOMENT EFFECTS OF CARRIED BY STRUCTURE BLOWING VALVES USING PISTON TYPE DESIGN 5104.00 FSAR 3. 9.B. 3. 3. I VALVE MANUFACTURER'S VERIFIED BY TOTAL 04 X 0 REACTION FORCE HYDRAULIC REACTION FORCE ANALYSIS 5105.00 FSAR 3. 9.B. 3. 3. I STRESS ANALYSIS OF STRESS CATEGORIZED 04 X 0 SAFETY AND RELIEF ACCORDING TO VALVE SYSTEM APPROPRIATE CODE 510G.00 FSAR 3. 9.B. 3. 3. I MATERIAL THICENESSES MAINTAIN STRESSES 04 X 0 0F COMPONENTS IN THE WITHIN ALLOWABLE SAFETY AND RELIEF LIMITS V A LVF 9'St h:* l O O O
O O O
~
Page No. 11 11/10/87 PLANT V0GTLE UNIT 2 READINESS REVIEW PROGRAM MODULE 04 COMMITMENT MATRIX CURRENT TRRU FSAR AMENDMENT 34 q ====================================== i REF. COMMITMENT COMMITMENT COMMITMENT DOCUMENT / MOD DES CON FSAR REMARES NUMBER SOURCE SECTION SUBJECT FEATURE ULE IGN ST AMEN
======= ========== ==================== ==================== ==================== === === === ==== ====================
X 5091.00 FSAR 3.11.8 I ENVIRONMENTAL DESIGN DESIGNED TO BREAK 04 X 25 I - MAIN STEAM PIPING EXCLUSION I IN MSIV COMPARTMENTS (SUPERPIPE) CRITERIA X OF BTP MBB 3-1 FOR ' FORTIONS PASSING THRU CONTAINMENT & " EXTENDING TO 5-WAT RESTRAINT PAST MSIV'S , i 1302.00 FSAR 3F. 4. 2. I HAZARDS EVALUATION STRUCTURE DESIGNED 04 X 0 MSIV & MFIV FOR ENVIRONMENTAL i COMPARTMENT CONDITIONS FROM L BREAR EQUAL TO ONE CROSS SECTION AREA L OF MAINSTEAM LINE OR MAIN FREDWATER LINE 2294.00 FSAR 3F. 4. 2. 3 MASS AND ENERGY ANSI M176 APP. E 04 X 0 BLOWDOWN CALCULATION RELEASE FOR MAIN STRAM LINE BREAR < X 2295.00*FSAR 3F. 4. 4 POSTULATED BREAR IN PROPAGATION OF FLOOD 04 X 16 X 96-INCR CIRCULATING WATERS INTO I X WATER PIPING TO SAFETT-RELATED X CONDENSERS IN STRUCTURES PRECLUDED TURBINE BLDG. BT DESIGN r 2346.00 FSAR 5. 4. 7. 2. 5 APPLICABLE CODES AND THE ENTIRE RRRS IS 04 X 0 CLASSIFICATION DESIGNED AS NUCLEAR l SAFETT CLASS 2 WITH l THE EXCEPTION OF THE I SUCTION ISOLATION 7ALVES. WHICR ARE SAFETT CLASS I. 313.00 FSAR 5. 4. 13. 3 PRESSURIZER SAFETT ASME III 04 X 0 1104 SYST. DESIGN i VALVES DESIGN PRESS. EVALUATION , i t I f
< -..wn -.- - + c , ~ - . ,. + , ~ . >~n -+- r - - .e',, ~~a + +-w- . . + - - - 'nna-
. A n- - - + - + ~ - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - , - - -
Page No. 12 11/10/87 PLANT V0GTLE UNIT 2 READINESS REVIEW PROGRAM MODULE 04 COMMITMENT MATRIX CURRENT TRRU FSAR AMENDMENT 34
====================_:============_===
i REF. COMMITMENT COMMITMENT COMMITMENT DOCUMENT / HOD DES CON FSAR REMARES NUMBER SOURCE SECTION SUBJECT FEATURE ULE IGN ST AMEN
======= ========== =============_==_:== ==================== ====_=============== ==2 === === ==== ===================.
322.00 FSAR 6. 1. 1. 1 ESF MATERIALS ASME III, NC-2160 & 04 X 0 FOR CSS. CIS, RRRS, SELECTION & NC-3120 SIS & AFWS FABRICATION 2386.00 FSAR 6. 1. 1. 1 ESF MATERIAL COMPATIBILITY WITR 04 X 0 COMPATIBILITY WITR SELECTION AND RCS AND CONTAINMENT RCS & CONT. SPRAY FABRICATION SPRAY SOLUTIONS SOLUTIONS 323.00 FSAR 6. 1. 1. 1. 1 SPECS. FOR ALL ASME III 04 X 0 PRINCIPAL PRESSURE PRESSURE RETAINING RETAINING MATERIALS MATERIAL IN ESF INDICATED IN TABLE SYSTEM 6.1.1-1 324.00 FSAR 6. 1. 1. 1. 1 MATERIAL SPECS FOR ASME III. NC-2000, 04 X 0 ESF COMPONENTS IN CLASS 2 QUALITY GROUP B, CLASS 2 325.00 FSAR 6. 1. 1. 1. 1 MATERIAL SPECS. FOR ASME III, ND-2000, 04 X 0 ESF COMP. IN QUALITY CLASS 3 GROUP C, CLASS 3 326.00'FSAR 6. 1. 1. 1. 1 ESF MATERIALS SPEC. ASTM /ASME COMPLIANCE 04 X 0 FOR CSS, CIS, RRRS, REQUIREMENTS - NA/NCA-1220 SIS, & AFWS 327.00 FSAR 6. 1. 1. 1. 1 ESF MATERIALS ASME III. NC-2000 & 04 X 0 CONTAINMENT NE-2000 PENETRATION MATERIALS 328.00 FSAR 6. 1. 1. 1. 2 ESF CONSTRUCTION ASME II, SFA 5.1, 04 X 0 MATERIALS- WELD 5.2, 5.5, 5.17, 5.18 MAT'L FOR JOINING & 5.20 FERRITIC BASE MAT'LS 329.00 FSAR 6. 1. 1. 1. 2 ESF CONST. ASME II SFA 5.11 & 04 X 0 MAT'LS-WELD 5.14 MATERIALS FOR JOINING N1-CR-FE ALLOYS O O O
s
)
bite No. 11/10/87 13 Q PLANT V0GTLE UNIT 2 READINESS REVIEW PROGRAM MODULE 04 COMMITMENT MATRIX CURRENT TRRU FSAR AMENDMENT 34
======================================
REF. COMMITMENT COMMITMENT COMMITMENT DOCUMENT / MOD DES CON FSAR REMARKS NUMBER SOURCE SECTION SUBJECT FEATURE ULE IGN ST AMEN
======= ========== ==================== ==================== ==================== === === === ==== ====================-
330.00 FSAR 6. 1. 1. 1. 2 ESF CONST. MAT *LS ASME II SFA S.4 & 04 X 0 FOR JOINING 5.9 AUSTENITIC S.S 331.00 FSAR 6. 1. 1. 1. 2 ESF CONST. ASME III 04 X 0 ESF SYSTEMS MAT *LS-WELD MATERIAL QUALIFICATION 333.00 FSAR 6. 1. 1. 1. 2 ESF CONST. MAT *L - LIMITED TO NO 04 X 0 COLD WORRED GREATER TRAN AUSTENITIC 5.S. 90,000 psi YIELD STRENGTR 2030.00 FSAR 6. 1. 1. 1. 2 ESF CONSTRUCTION COMPONENTS IN 04' X 0 MATERIALS CONTACT WITH BORATED ,. WATER ARE FABRICATED OF OR CLAD WITH AUSTENITIC STAINLESS STEEL OR EQUIV. CORROSION-RESISTANT-MATERIAL 2170.00'FSAR 6. 1. 1. 1. 2 ESF CONST. MATERIALS ASME IX 04 X X 0 WELD MATERIAL QUALIFICATION 256.00 FSAR 6. 1. 1. 1. 3 ESF MAT'LS INTEGRITY RG 1.31 04 X 0 FOR CSS, CIS, RRRS, OF SAFETY-RELATED SIS & AFWS COMPONENTS 259.00 FSAR 6. 1. 1. 1. 3 ESF MAT'LS-INTEGRITY RG 1.44 04 X 0 FOR CSS. CIS, RRRS OF SAFETY-RELATED SIS, AFWS COMPONENTS 258.00 FSAR 6. 1. 1. 1. 3.C ESF . RG 1.37 04 X 0 MATERIALS-INTEGRITY OF SAFETY-RELATED COMPONENTS - QA REQUIREMENTS FOR CLEANING _ _ _ _ _ _ _ - _ - . . ~ . _ . _ . - _ . . - - - . ~ .- - _ - _ _ _ _ _ _ _ -
Page No. 14 11/10/87 PLANT VOGTLE UNIT 2 READINESS REVIEW PROGRAM MODULE 04 COMMITMENT MATRIX CURRENT THRU FSAR AMENDMENT 34
==============================e ======
REF. COMMITMENT COMMITMENT COMMITMENT DOCUMENT / MOD DES CON FSAR REMARKS NUMBER SOURCE SECTION SUBJECT FEATURE ULE IGN ST AMEN
======= =======a== ==================== ==================== ======e-====e======e === === === ==== = ==e===============
l 2471.00 FSAR 6. 2. 1. 2. 3. I ANALYTICAL MODEL FOR BN-TOP-4 (REV. 1) 04 X 0 COMPUTER PROGRAM FOR CONTAINMENT PRESSURE TRANSIENT SUB-COMPARTMENT ANALYSIS ANALYSIS 1326.00 FSAR 6. 2. 2. 1. 1. 1.D CONTAINMENT COOLING ASME XI 04 X 0 SYSTEM, SAFETY DESION BASIS IN-StWVICE INSPE; TION 2397.00 FSAR 6. 2. 2. 1. 1. l.G CONTAINMENT COOLING DESIGNED AND 04 X 0 SEE FSAR TABLE SYSTEM SAFETY DESIGN FABRICATED TG CODES 3.2.2-1 FOR QUALITY BASES CONSISTENT WITR RG GROUP CLASS 1.26 2398.00 FSAR 6. 2. 2. 1. 1. 1.0 CONTAINMENT COOLING RG 1.29 04 X 0 SEE FSAR TABLE SYSTEM SAFETY DESIGN 3.2.2-1 FOR SEISMIC BASES CATEGORY 2479.00 FSAR 6. 2. 2. 2. 1. 1.C CONTAINMENT SPRAY SINGLE ACTIVE 04 X 0 SYSTEM SAFETY DESIGN FAILURE PLUS LOOP BASES (INJECTION FHASE) AND SINGLE ACTIVE OR PASSIVE FAILURE PLU. LOOP (RECIRCULATION PRASE) CANNOT IMPAIR SAFETY FUNCTION 2482.00 FSAR 6. 2. 2. 2. 1. 1.0 CONTAINMENT SPRAY ASME III, CLASS MC 04 X 0 FSAR 3.2.2-1 (SH. 6) SYSTEM CODE AND STANDARDS 2480.00 FSAR 6. 2. 2. 2. 1. l.G CONTAINMENT SPRAY ASME III, CLASS 2 04 X 0 FSAR 3.2.2-1 (SH. 6) SYSTEM CODE AND STANDARDS i 2481.00 FSAR 6. 2. 2. 2. 1. l.G CONTAINMENT SPRAY ASME III, CLASS 3 04 X 0 FSAR 3.2.2-1 (SH. S) SYSTEM CODE AND STANDARDS O O O
~
Fage No. 15 11/10/87 PLANT YOGTLE UNIT 2' READINESS REVIEW PROGRAM MODULE 04 COMMITMENT MATRIX CURRENT THRU FSAR AMENDMENT 34
======================================
REF. COMMYTMENT COMMITMENT COMMITMENT DOCUMENT / MOD DES CON FSAR REM 4RES NUMBER SOURCE SECTION SUBJECT FEATURE ULE IGN ST AMEN
======= ========== ==================== ==================== ==================== === === === ==== ====================
2483.00 FSAR 6. 2. 2. 2. 1. l.G CONTAINMENT SPRAY NEMA-MGl 04 1 0 FSAR 3.2.2-1 (SR. 6) SYSTEM CODE AND STANDARDS 2484.00 FSAR 6. 2. 2. 2. 2. 2 ALLOWED TIME FOR 20 MINUTES 04 X 0 OPERATOR TO INITIATE MANUAL SWITCROVER TO RECIRCULATION UPON RECEIPT OF A LOW LEVEL ALARM IN RWST 2485.00 FSAR 6. 2. 2. 2. 2. 2 CONTAINMENT SUMP MINIMUM pH OF 8.5 04 X 0 FLUID pH AT END OF INJECTION PRASE 2512.00 FSAR 6. 2. 2. 2. 2. 3. NPSR AVAILABLE TO RG 1.1 04 X 0 2 CONTAINMENT SPRAY PUMPS 2515.00 FSAR 6. 2. 2. 2. 2. 3. DESIGN OF THE RG 1.82 04 X 0 6 CONTAINMENT EMERGENCY CORE COOLING SYSTEM SUMPS 2486.00 FSAR 6. 2. 2. 2. 2. 3. MATERIAL THAT CAN AUSTENITIC 5.5. 04 X 0 6 COME IN CONTACT WITH RECIRCULATION FLUID 2409.00 FSAR 6. 2. 4 CONTAINMENT TMI ACTION PLAN TASE 04 X 0 ISOLATION SYSTEM II.E.4.2 DESIGN 2407.00 FSAR 6. 2. 4. 1. 1. F. 2 CIS SAFETT DESIGN DESIGNED TO SEISMIC 04 X 0 BASES CAT. I 2408.00 FSAR 6. 2. 4. 1. 1.F. 3 CONTAINMENT ASME III. CLASS 2 04 X 0 ISOLATION SYSTEM. SAFETY DESIGN BASIS l s m__________ _ ___ _ . _ - _ _ ~ _ _ _ _
Page No. 16 11/10/87 PLANT 70GTLE UNIT 2 READINESS REVIEW PROGRAM MODULE 04 COMMITMENT MATRIX CURRENT TRRU FSAR AMENDMENT 34
======================================
REF. COMMITMENT COMMITMENT COMMITMENT DOCUMENT / MOD DES CON FSAR REMARKS MUMBER SOURCE SECTION SUBJECT FEATURE ULE IGN ST AMEN
===~=== ========== ==================== ==================== ==================== === === === ==== ====================
2048.00 FSAR 6. 2. 4. I. l.R CONTAINMENT DESIGNED TO REMAIN 04 X 0 ISOLATION SYSTEM, FUNCTIONAL FOLLOWING SAFETY DESIGN BASIS A SSE 2422.00 FSAR 6. 2. 4. 2. I SYSTEM GENERAL BTP CSB 6-4 04 X 0 TABLE 9.4.6-4 DESCRIPTION - CONTAINMENT PURGE SYSTEM 2519.00 FSAR 6. 2. 4. 2. 1 LOCATION OF THE ABOVE MAXIMUM 04 X 0 ACTUATORS FOR ANTICIPATED CONTAINMENT CONTAINMENT WATER ISOLATION VALVES LEVEL 2055.00 FSAR 6. 2. 4. 3.D CONTAINMENT 10CFR50, APP. A. GDC 04 X 0 ISOLATION SYSTEM, 54, PIPING SYSTEMS DESIGN EVALUATION PENETRATING CONTAINMENT 2056.00 FSAR 6. 2, 4. 3.B CONTAINMENT 10CFR50, APP. A, GDC 04 X 0 ISOLATION SYSTEM, 55 & 56 PRIMARY DESIGN EVALUATION CONTAINMENT ISOLATION 2057.00 FSAR 6. 2. 4. 3.F CONTAINMENT 10CFR50, APP. A. GDe 04 X 0 ISOLATION STSTEM, S7 CLOSED SYSTEM DESIGN EVALUATION ISOLATION VALVES 2059.00 FSAR 6. 2. 4. 4 CONTAINMENT ASME XI 04 R 0 SEE FSAR 6.2.6 ISOLATION SYSTEM, TESTS AND INSPECTIONS 2432.00 FSAR 6. 2. 4. 4 CONTAINMENT 10CFR50, APP. J 04 X 0 ISOLATION SYSTEM - TESTS AND INSPECTIONS O O O
O Vage No. 11/10/87 17 O o PLANT V0GTLE UNIT 2 READINESS REVIEW PROGRAM d MODULE 04 COMMITMENT MATRIX CURRENT THRU FSAR AMENDMENT 34
================================-= ===
REF. COMMITMENT CCMMITMENT COP'M I TME NT DOCUMENT / MOD DES CON FSAR REMARES MUMBER SOURCE SECTION SUBJECT FEATURE ULE IGN ST AMEN
=e===== =====e==== ==================== ==================== ==================== === === === ==== ===================e 2450.00 FSAR 6. 2. 5-1 DESIGN DATA FOR H2 ASME IX 04 X 0 RECOMBINER 2455.00 FSAR 6. 2. 5-1 DESIGN DATA FOR H2 IEEE 323 04 X 0 RECOMBINER 2456.00 FSAR 6. 2. 5-1 DESIGN DATA FOR H2 IEEE 344 04 -X 0 RECOMBINER 2063.00 FSAR 6. 2. 5. 1. 1.D COMBUSTIBLE CAS CAPACITY IS SUCH 04 X 0 CONTROL IN THAT CONTAINMENT H2 CONTAINMENT CONC. WILL NOT ELEC. HYDROGEN EXCEED 4% BASED ON RECOMBINERS NRC TID RELEASE MODEL AS INDICATED IN RG 1.7.
2444.00 FSAR 6. 2. S. 2. 1 ELECTRIC HYDROGEN 2 RECOMBINERS ARE 04 X 0 RECOMBINER PROVIDED TO MEET THE REQUIREMENTS FOR REDUNDANCY AND INDEPENDENCE. 2808.00 FSAR 6. 2. 7. 2.D FLURD HEADS - ASME III, DIV. 1, 04 X 0 FRACTURE TOUGHNESS SUBSECTION NC, 1977 , TESTS THRU SUMMER 1978 ADDENDA. 2809.00 FSAR 6. 2. 7. 2.8 PRESSURE BOUNDARY ASME III. DIV. 1 04 X 0 MSIV. MFIV DESIGNED PIPING - MAIN STEAM SUBSECTION NC. 1974 PER 1974 ED. THRU AND FERDWATER TRRU SUMMER 1975 SUMMER 1975 ADDENDA I SYSTEMS - FRACTURE ADDENDA. W/O FRACTURE TOUGHNESS TESTED TOUCHNESS TESTS. 2812.00 FSAR 6. 2. 7. 2.E REMAINING ASME III, 1974 THRU 04 I O CONTAINMENT PRESSURE SUMMER 1975 ADDENDA. BOUNDARY PIPING DESIGNED WITHOUT FRACTURE TOUGHNESS TESTING _: _ _ . _ . _ . . _ . _ . ~ . _ . . _ _. _ . . _ _ _ _ . _ _- _. ._. - . ~_ __ _ _ __ _ . . _ _
Page No. 18 I1/10/87 PLANT V0GTLE UNIT 2 READINESS REVIEW PROGRAM MODULE 04 COMMITMENT MATRIX CURRENT THRU FSAR AMENDMENT 34
======================= ==============
REF. COMMITMENT COMMITMENT COMMITMENT DOCUMENT / MOD DES CON FSAR REMARKS NUMBER SOURCE SECTION SUBJECT FEATURE ULE IGN ST AMEN
======= ========== ==================== ==================== ==================== === === === ==== ====================
2810.00 FSAR 6. 2. 7. 2.F FRACTURE TOUGHNESS ASME III. DIV. 1 04 X 0 VALVES WITHIN NSSS TEST FOR PRESSURE SUBSECTION NC. NEED NOT BE FRACTURE BOUNDARY MATERIAL OF FUB-ARTICLE NC-2300 TOUGHNESS TESTED. , MAIN STEAM AND 1977 EDITION. SINCE MATERIAL USED l FEEDWATER ISOLATION IS EITHER AUSTENITIC VAF"ES S.S. OR C.S.
- 2813.00 FSAR 6. 2. 7. 2.F CONTAINMENT PRESSURE ASME III. DIV. 1, 04 X 0 i BOUNDARY VALVES SUBSECTION NC. 1974 OTHER THAN MAIN THRU SUMMER 1975 STEAM AND FEEDWATER ADDENDA.
l ARE PROCURED WITHOUT FRACTURE TOUGRNESS
- TESTING 281I.00 FSAR 6. 2. 7. 4 SAFETY EVALUATION - MINIMUM REQUIREMENTS 04 X 0 DID NOT REQUIRE CONTAINMENT OF ASME III, 74 IMPACT TESTING.
ISOLATION BOUNDARY EDITION THRU SUMMER PIPING AND BOP 75 ADDENDA. CONTAINMENT ISOLATION BOUNDARY VALVES 4930.00 FSAR 6. 3. 1 EMERGENCY CORE ELEVATED TEMPERATURE 04 X 0 COOLING SYSTEM OF SUMP SOLUTION IS (ECCS) WELL WITHIN DESIGN TEMPERATURES OF ECCS COMPONENTS DURING RECIRCULATION. X 2816.00 FSAR 6. 3. 2. 2. 9 REFUELING WATER DESIGNED TO SEISMIC 04 X 17 X STORAGE TANE CATEGORY I X REQUIREMENTS. X HEATER PROVIDED TO MAINTAIN MIN. WATER i TEMP. OF SO DEGREES l F. l l O O O
O Page No. 19 O O 11/10/87
- PLANT V0GTLE UNIT 2 READINESS REVIEW PROGRAM MODULE 04 COMMITMENT MATRIX CURRENT THRU FSAR AMENDMENT 34
======================================
REF. COMMITMENT COMMITMENT COMMITMENT DOCUMENT / MOD DES CON FSAR REMARKS NUMBER SOURCE SECTION SUBJECT FEATURE ULE IGN ST AMEN
======~ ========== ==================== ==================== ==================== === === === ==== ====================
2503.00 FSAR 6. 3. 2. 2.17 ECCS MANUAL VALVES NO SINGLE VALVE CAN 04 X 0 ISOLATE BOTR TRAINS OF ECCS EQUIPMENT 2084.00 FSAR 6. 3. 2. 4.A EMERGENCY LORE ALL PARTS / COMPONENTS 04 X 0 COOLING SYSTEM IN CONTACT WITH MATERIAL SPECS & BORATED WATER ARE COMPATIBILITY FABRICATED OF OR CLAD WITH AUSTENITIC STAINLESS STEEL OR EQUI. CORROSION RESISTANT MATERIAL 4929.00 FSAR 6. 3. 2. 5. 2.B. 1 EMERGENCY CORE PIPING IS ANSI 04 X 0 COOLING SYSTEM SAFETY CLASS 2 AND ASME CLASS 2 QA PROGRAM 4928.00 FSAR 6. 3. 2. 5. 2.B. 5 EMERGENCY CORE PIPING IS AUSTENITIC 04 X 0 COOLING SYSTEM STAINLESS STEEL. 2821.00 FSAR 6. 3. 4. 2 INSERVICE INSPECTION ASME XI. 04 X 0 0F ECCS COMPONENTS i AND SYSTEMS i l 4516.00 FSAR 7. 3. 7. 1, 2 AFWS - DESIGN BASES NO SINGLE FAILURE 04 X 0 SRALL PREVENT THIS SYSTEM FROM OPERATING 4523.00 FSAR 7. 3. 7. 1. 2 AFS AFS-THE SYSTEM MUST 04 X 0 DESIGN EASES PROVIDE FULL AUXILIARY FEEDWATER FLOW WITRIN 1 MINUTE. 4526.00 FSAR 7. 3. 7. 2.A. 3 AFS 10CFR50 APP. A. GDC 04 X 0 SEE 3.1 FOR ANALYSIS OF 34 CONFORMANCE. COMPLIANCE tm .. _ _ _ _ _ _ _ _ _ ..-.- . ..- . . . . . - - - . - . . . . . . . .
Page No. 20 11/10/87 PLANT VOGTLE UNIT 2 READINESS REVIEW PROGRAM MODULE 04 COMMITMENT MATRIX CURRENT THRU FSAR AMENDMENT 34
=============_========_-======_========
REF. COMMITMENT COMMITMENT COMMITMENT DOCUMENT / MOD DES CON FSAR REMARES NUMBER SOURCE SECTION SUBJECT FEATURE ULE IGN ST AMEN
======= e========= ==================== ==================== ==================== === === === ==== ====================
5119.00 FSAR 8. 3. 2. 2 EYEWASR FACILITIES DESIGNED TO PRECLUDE 04 X 0 UENERIC LETTER PROVIDED IN ALL SPILLING OF WATER ON GN-1218 DIRECTS TRAT BATTERY ROOMS BATTERIES AN INSULATOR WRAP AND 2 LAYERS OF METALLIC SREATR COVER PIPING 3721.00 FSAR 9. 1. 2. 2 SPENT FUEL STORAGE ALL INTERVENING 04 X 0 FACILITY DESCRIPTION PIPING DESIGNED TO SEISMIC CAT. I REQUIREMENTS 3723.00 FSAR 9. 1. 3. 1.B SFPCPS DESIGN BASIS SYSTEM PIPING 04 X 0 ARRANGED SO TRAT FAILURE OF ANY PIPELINE CANNOT DRAIN SFP BELOW WATER LEVEL REQUIREMENT FOR RADIATION SRIELDING 421.00,FSAR 9. 1. 3. 5.B SFPCPS DESIGN RG 1.13 04 X 0 4913.00 FSAR 9. 2. 1-1 NSCW SYSTEM DESIGN MARIMUM TOTAL NSCW 04 X 0 TABLE REAT LOAD DURING ACCIDENT CONDITIONS IS 349.8 MILLION BTU /ROUR 4914.00 FSAR 9. 2. 1-1 NSCW SYSTEM DESIGN MINIMUM NSCW FLOW 04 X 0 TABLE PER TRAIN REQUIRED FOR ACCIDENT CONDITIONS IS 15,733 GPM. 384.00 FSAR 9. 2. 1-3 NSCW SYSTEM NSCW PUMP AND 04 X 0 TABLE EQUIPMENT DESIGN TRANSFER PUMP ASME III CLASS 3 l O O O
OPage No. 21 O O 11/10/87 PLANT V0GTLE UNIT 2 READINESS REVIEW PROGRAM MODULE 04 COMMITMENT MATRIX CURRENT TRRU FSAR AMENDMENT 34
======================================
REF. COMMITMENT COMMITMENT COMMITMENT DOCUMENT / MOD DES CON FSAR REMARES NUMBER SOURCE SECTION SUBJECT FEATURE ULE IGN ST AMEN
======= ========== ==================== ==================== ==================== === === === ==== ====================
3 3525.00 FSAR 9. 2. 1. 1. 1.C NSCW SYSTEM SAFETY THE NSCW SYSTEM 04 X 0 DESIGN BASES. DESIGNED TO MEET SEISMIC CAT. I i REQUIREMENTS 3749.00 FSAR 9. 2. 1. 1. l.G NSCW SYSTEM SAFETY DESIGNED TO PERFORM 04 X 0 DESIGN BASIS ITS COOLING FUNCTION FOLLOWING LOCA. AUTOMATICALLY. ASSUMING SINGLE FAILURE COINCIDENT WITH A L.0.0.P. 4912.00 FSAR 9. 2. 1. 1. l.R NSCW SYSTEM SAFETY NSCW DESIGNED TO 04 X 0 4 DESIGN BASES PREVENT BOILING IN CONTAINMENT COOLERS DURING LOCA CONDITIONS. 3750.00 FSAR 9. 2. 1. 1. 1.1 NSCW SYSTEM SAFETT DESIGNED SUCR THAT 04 X 0 TO PRECLUDE LEAEAGE DESIGN BASIS SYSTEM PRESSURE IS TO ENVIRONMENT GREATER TRAN CONTAINMENT BUILDING MAXIMUM DESIGN PRESSURE 4915.00 FSAR 9. 2. 1. 2. 3 NSCW SYSTEM NSCW SUPPLIES WATER 04 X 0 OPERATION AT A RIGRER PRESSURE TRAN FLUID IN THE COOLED SAFETY RELATED COMPONENT. 393.00 FSAR 9. 2. 2-1 CCW SYSTEM EQUIPMENT EQUIPMENT CODES AND 04 X 0 ANSI B31.1 ASME Ill DESIGN PARAMETERS STANDARDS CLASS 3 NEMA. TEMA R 388.00 FSAR 9. 2. 2. 1 CCW SYSTEM DESIGN ASME III, CL. 3 04 X 0 (EXCEPT CCW CHEM. ADD. TANK AND ASSOCIATE PIPE) l
Page No. 22 11/10/87 PLANT V0GTLE UNIT 2 READINESS REVIEW PROGRAM MODULE 04 COMMITMENT MATRIX
- CURRENT THRU FSAR AMENDMENT 34
======================================
REF. COMMITMENT COMMITMENT COMMITMENT DOCUMENT / MOD DES CON FSAR REMARKS NUMBER SOURCE SECTION SUBJECT FEATURE ULE IGN ST AMEN
======= ========== ==================== ==================== ==================== === === === ==== ====================
4918.00 FSAR 9. 2. 2. 1. l.A CCW SYSTEM SAFETY DESIGNED TO TRANSFER 04 X 0 DESIGN BASES REAT FROM RRR SYSTEM TO NSCW SYSTEM AT A SUFFICIENT RATE TO AVOID FUEL OR CORE DAMAGE FOLLOWING A LOCA. IN ACCORDANCE WITH 10CFR50 APP. A. GDC 44 i 4921.00 FSAR 9. 2. 2. 1. 1.C CCW SYSTEM SAFETY DESIGNED SO TRAT A 04 X 0 DESIGN BASES SINGLE FAILURE OF ANY COMPONENT i ASSUMING L.0.0.P. l CANNOT IMPAIR SYSTEM CAPABILITY TO COMPLY WITH TRE SAFETY-RELATED REAT REMOVAL FUNCTION. l 3752.00 FSAR 9. 2. 2. 1. 1.D CCWS - SAFETY DESIGN DESIGNED TO REMAIN 04 X 0 l BASIS FUNCTIONAL DURING l AND AFTER SSE 2174.00 FSAR 9. 2. 2. 1. 1.E CCW SYSTEM SAFETY 10CFR50 APP. A. GDC 04 X 0 DESIGN BASES 45 2175.00 FSAR 9. 2. 2. 1. 1.E CCW SYSTEM SAFETY 10CFR50, APP. A. GDC 04 X 0 DESIGN BASES
- 46 4919.00 FSAR 9. 2. 2. 1. 1.F. CCW SYSTEM SAFETY DESIGNED TO REMOVE 04 X 0 1.E DESIGN BASES REACTOR DECAY REAT SUFFICIENT TO BRING REACTOR TO COLD SRUTDOWN CONDITION IN 36 ROURS WITR LOSS OF 0FFSITE POWER AND ASSUMING MOST LIMITING SINGLE FAILURE IN ACCORD.
WITH RG 1.139 O O O
a=. .w- .-- , O Page No. 23 O O 11/10/87 PLANT VOGTLE UNIT 2 READINESS REVIEW PROGRAM MODULE 04 COMMITMENT MATRIX CURRENT THRU FSAR AMENDMENT 34
======================================
REF. COMMITMENT COMMITMENT. COMMITMENT DOCUMENT / MOD DES CON FSAR REMARKS NUMBER SOURCE SECTION SUBJECT FEATURE ULE IGN ST AMEN
======= ========== ==================== ==================== ==================== === === === ==== ====================
3753.00 FSAR 9. 2. 2. 1. 2.5 CCWS - POWER DESIGNED WITH LOWER 04 X 0 GENERATION DESIGN PRESSURE THAN MSCW BASIS SYSTEM TO PREVENT POTENTIAL RADIATION LEAKAGE INTO NSCW SYSTEM. X 4923.00 FSAR 9. 2, 2. 3.A CCW SYSTEM 5AFETY DURING ONE TRAIN 04 X 20 X EVALUATION COOLDOWN, TRE PEAK X LOAD IS X APPROXIMATELT 189 I 10 TO THE 6TR ' " BTU / HOUR AND COLD SHUTDOWN IS ACHIEVED IN 34 HOURS. # 390.00 FSAR 9. 2. 2. 3.A CCW SYSTEM COLD BTP R5B 5-1 04 X 0 SHUTDOWN REQUIREMENTS 3539.00 FSAR 9. 2. 2. 3.C CCW SYSTEM SAFETY THE SAFETT RELATED 04 X 0 EVALUATION PORTION DESIGNED AND CONSTRUCTED AS SEISMIC CATEGORY l 400.00 FSAR 9. 2. 5 ULTIMATE REAT SINK RG 1.27 04 X 0 SYSTEM DESIGN - STORAGE CAPACITY OF-- TWO M5C TOWER BASINS 401.00 FSAR 9. 2. 5. I ULTIMATE HEAT SINK SEISMIC CAT. I 04 X 0 TOWERS AND BASINS DESIGN 3755.00 FSAR 9. 2. 5. 1. l.A ULTIMATE NEAT SINK - DESIGNED 50 THAT 04 X 0 SAFETY DESIGN BASES SINGLE FAILURE WITH L.O.O.P. DOES NOT RESULT IN INADEQUATE CORE COOLING OR PREVENT A SAFE SHUTDOWN. A_._ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ . , _ . , ._ . _ . _ . .__ _ . _. ~ _ __
Page No. 24 11/10/87 PLANT V0GTLE UNIT 2 READINESS REVIEW PROGRAM MODULE 04 COMMITMENT MATRIX CURRENT THRU FSAR AMENDMENT 34
======================================
REF. COMMITMENT COMMITMENT COMMITMENT DOCUMENT / MOD DES CON FSAR REMARKS NUMBER SOURCE SECTION SUBJECT FEATURE ULE IGN ST AMEN
======= ========== ==================== ==================== ==================== ,== === === =-== ====================
3542.00 FSAR 9. 2. 5. 1. l.A ULTIMATE HEAT SINK SINGLE FAILURE PLUS 04 X 0 NS COOLING TOWFRS (URS) SAFETY DESIGN L.0.0.P. WILL NOT , BASES IMPAIR SYSTEM CAPABILITY 418.00 FSAR 9. 2. 5. 1. 1.8 ULTIMATE HEAT SINK RG 1.27 04 X 0 COOLING FOR 30 DAYS SAFETY DESIGN BASES 3541.00 FSAR 9. 2. 5. 2. 2 ULTIMATE HEAT SINK FAN MOTORS PONERED 04 X 0 (UHS) COMPONENT BY CLASS IE POWER DESCRIPTION SUPPLY. 402.00 FSAR 9. 2. 5. 2. 4 ULTIMATE HEAT SINK BTP ASB 9-2 04 X 0 SYSTEM PERFORMANCE (RESIDUAL HEAT DECAY) 403.00 FSAR 9. 2. 5. 2. 4 ULTIMATE HEAT SINK RG 1.27 04 X 0 SYSTEM PERFORMANCE (BASIN SIZING) 4777.00 FSAR 9. 2. 5. 2. 4 ULTIMATE REAT SINK BTP RSB 5-1 SECTION 04 X 13 AMEND. 13/14 SYSTEM PERFORMANCE A.4 3543.00 FSAR 9. 2. 6. 1. l.A CONDENSATE STORAGE SINGLE FAILURE PLUS 04 X 0 CONDENSATE STORAGE FACILITY L.0.0.P. WILL NOT TANK IMPAIR SYSTEM 3758.00 FSAR 9. 2. 6. 1. 1.C CONDENSATE STORAGE FAILURE OF NON-CAT. 04 X 0 FACILITY - SAFETY I LINES ATTACHED TO DESIGN BASES CST'S CANNOT CAUSE LOSS OF RESERVE CAPACITY REQUIRED FOR SAFE SHUTDOWN. 37F9 00 FSAR 9. 2. 6. 1. 3 CODES / STANDARDS STORAGE TANKS & 04 X 0 SAFETY-RELATED PIPING DESIGNED AND CONSTRUCTED AS SEISMIC CAT. I. O O O
9 O Page No. 25 O 1 11/10/87 2 PLANT V0GTLE UNIT 2 READINESS REVIEW PROGRAM MODULE 04 COMMITMENT MATRIX CURRENT THRU FSAR AMENDMENT 34
======================================
P REF. COMMITMENT COMMITMENT COMMITMENT DOCUMENT / MOD DES CON FSAR REMARKS '} NUMBER SOURCE SECTION SUBJECT FEATURE ULE IGN ST AMEN t
======= ========== ==================== ==================== ==================== === === === ==== =================___ j 3544.00 FSAR 9. 2. 6. 4.C SAFETY EVALUATION CST'S AND ASSOCIATED 04 X 0 CONDENSATE STORAGE SAFETY RELATED TANKS (CST'S) PIPING AND VALVES ARE DESIGNED AS ,
SEISMIC CAT 1. ' 406.00 FSAR 9. 2. 7. 2. 2 REACTOR MAKEUP WATER SEISMIC CAT. I 04 X 0 STORAGE TANK DESIGN 3760.00 FSAR 9. 2. 7. 3 REACTOR MAKEUP WATER PORTIONS OF RMWS 04 X 0 FACILITY SAFETY REQUIRED TO SERVE AS EVALUATION BACKUP MAKEUP WATER SOURCE FOR SPENT ! FUEL POOL IS DESIGNED / BUILT TO CAT. I REQUIREMENTS. 411.00 FSAR 9. 2. 8-2 ACCW SYSTEM DESIGN EQUIPMENT CODES AND 04 X 0 ANSI B31.1 ASME III ! PARAMETERS STANDARDS CLASS 3 ASME VIII. NEMA, TEMA R 3549.00 FSAR 9. 3. 2. 2. 5 POST ACCIDENT ESSENTIAL PORTIONS 04 X 0 PORTIONS WITRIN SAMPLING SYSTEM DESIGNED FOR SEISMIC CONTAINMENT AND CATEGORY I INCLUDING THE OUTER CONTAINMENT ISOLATION VALVES X 3575.00 FSAR 9. 3. 3. 4.A TEST AND INSPECTIONS PRESSURIZED PORTIONS 04 X 19 I DURING CONSTRUCTION HYDROSTATICALLT X WASTE COLLECTION TESTED AT 1 1/2 X SYSTEM. TIMES DESIGN PRESSURE. X 3834.00 FSAR 9. 3. 3. 4.A WASTE COLLECTION NON PRESSURIZED 04 X 19 I SYSTEMS - TESTS AND PORTIONS X INSPECTIONS DURING H YD ROS't AT IC A L LY X CONSTRUCTION TESTED (UNDER' ATMOSFHERIC PRESSURE)
)
, <w, ~mm ~,- , , ,
Page No. 26 11/10/87 PLANT VOGTLE UNIT 2 READINESS REVIEW PROGRAM MODULE 04 COMMITMENT MATRIX CURRENT THRU FSAR AMENDMENT 34
======================================
REF. COMMITMENT COMMITMENT COMMITMENT DOCUMENT / MOD DES CON FSAR REMARES NUMBER SOURCE SECTION SUBJECT FEATURE ULE IGN ST AMEN
======= ========== ==================== ==================== ==================== === === === ==== ====================
4931.00 FSAR 9. 3. 4. 1. 2. BORIC ACID STORAGE BORIC CID STORAGE 04 X 0 (MOST REACTIVE 5.12 TANK (BAST) TANE IS SIZED TO CONTROL ROD NOT STORE SUFFICIENT INSERTED) SOLUTION FOR ONE WESTINGHOUSE REFUELING SHUTDOWN CALCULATED THE PLUS ENOUGH FOR ONE CAPACITY AS COLD SHUTDOWN FROM DOCUMENTED IN GP1649 FULL-POWER OPERATION AND GP2033 IMMEDIATELY FOLLOWING REFUELING WITH (SEE REMARKS) . 3555.00 FSAR 9. 3. 4. 1. 3. I SAFETY EVALUATION - SINGLE FAILURE OF 1 04 X 0 i REACTIVITY CONTROL OF 2 FLOWPATHS DOES l BORATION FLOWPATHS NOT RESULT IN l INABILITY TO BORATE RCS. 3455.00 FSAR 9. 3. 4. 1. 3. 5 LEAKAGE PROVISIONS VALVES & PIPING 04 X 0 l FOR CVCS COMPONENTS WHICH SEE RADIOACTIVE SERVICE ARE DESIGNED TO LIMIT LEAKAGE TO THE ATMOSPHERE. 1352.00 FSAR 10. 1. 2.B SPRING LOADED SAFETY ASME III. 04 X 0 VALVES 1360.00 FSAR 10. 3. 1. 1.C DESIGN OF SAFETY ASME III, CLASS 2 04 X 0 SEE TABLE 10.3.2-1 RELATED PORTIONS OF AND SEISMIC CATEGORY MAIN STEAM SUPPLY l REQUIREMENTS SYSTEM 1359.00 FSAR 10. 3. 1. 1.C. I MAIN STEAM DESIGN BTP MEB 3-1 04 X 0 PIPING / VALVES FROM BASIS S/G TO AND INCLUDING PIPE RESTRAINT DOWNSTREAM OF EACH MSIV. O O O
' No. 27 11/10/87 PLANT V0GTLE UNIT 2 READINESS REVIEW PROGRAM MODULE 04 COMMITMENT MATRIX
- CURRENT THRU FSAR AMENDMENT 34
==s===========================e=======
REF. COMMITMENT COMMITMENT COMMITMENT DOCUMENT / MOD DES CON FSAR REMARES NUMBER SOURCE SECTION SUBJECT FEATURE ULE IGN ST AMEN
======= ========== ==================== ==================== ==================== === === === ==== ====================
1363.00 FSAR 10. 3. 1. 1.F INSERVICE INSPECTION ASME II 04 X 0 ACCESS TO NELDS AND REMOVEABLE INSULATION 1369.00 FSAR 10. 3. 6. 2 MAIN STEAM SUP. SYS. ANSI B36.19 FOR S.S. 04 X 0 MATLS SELECTION & PIPE FABR. FOR PIPING. FLANGES FITTI NGS. VALVES & OTHER PIPING MATLS-1370.00 FSAR 10. 3. 6. 2 MAIN STEAM SUPPLT ANSI B36.10 FOR C.S. 04 0 SYSTEM MATLS. PIPE SELECTION & FABR. FOR PIFING, FLANGES, FITTINGS, VALVES & OTHER PIPING MATERIALS 1371.00 FSAR 10. 3. 6. 2 MAIN STEAM SUPPLT ANSI B16.9, B16.11 04 X 0 SYSTEM MATERIALS OR B16.28 FOR S.S. SELECTION & FABR. FITTINGS AND C.S. FOR PIPING. FLANGES, FITTINGS. FITTINGS, VALVES & OTHER PIPING MATERIALS 1372.00 FSAR 10. 3. 6. 2 MAIN STEAM SUP. SYS. ANSI B16.5 FOR S.S. 04 X 0 MATLS SELECTION & & C.S. FLANGES FABR. FOR PIPING, FLANGES, FITTINGS, VALVES & OTHER PIPING MATL. 1374.00 FSAR 10. 3. 6. 2 MAIN STEAM SUP. SYS. ASdB MATERIAL 04 X 0 MATLS SELECTION & SPECIFICATIONS FABR. FOR PIPING, FLANGES, FITTINGS, VALVES & OTHER PIPING MATL.
Page No. 28 11/10/87 PLANT VOGTLE UNIT 2 READINESS REVIEW PROGRAM MODULE 04 COMMITMENT MATRIX CURRENT TRRU FSAR AMENDMENT 34
====================================a=
REF. COMMITMENT COMMITMENT COMMITMENT DOCUMENT / MOD DES CON FSAR REMARES NUMBER SOURCE SECTION SUBJECT FEATURE ULE IGN ST AMEN
======= ==== ===== ==================== ==================== ==================== === === === ==== ====================
441.00 FSAR 10. 4. 7. 1. I FEEDWATER SYS. FROM ASME III. CLASS 2 04 X 0 STM. GEN. MAIN AND BYPASS FERDWATER INLETS TO THE FIRST SEISMIC RESTRAINT UPSTREAM OF THE CONTAINMENT ISOLATION VALVES 442.00 FSAR 10. 4. 7. 1. 1.D MAIN FEELMATER ASME XI 04 X 0 SYSTEM 443.00 FSAR 10. 4. 7. 1. 1.E CONDENSATE & RG 1.26 04 X 0 FEEDWATER 444.00 FSAR 10. 4. 7. 1. 1.E CONDENSATE & RG 1.29 04 X 0 FERDWATER 2301.00 FSAR 10. 4. 7. 3.C CONDENSATE AND SINGLE ACTIVE 04 X 0 FSAR CHAPTER 8 FEEDWATER SYSTEM COMPONENT FAILURE OF SAFETY EVALUATION SAFETY-RELATED OR . NONESSENTIAL PORTIONS WILL NOT COMPROMISE THE SYSTEM'S SAFETY FUNCTION. 457.00 FSAR 10. 4. 9-1 AUXILIARY FREDWATER ASME III. CLASS 2 04 X 0 TABLE SYSTEM. DESIGN CODE AND 3 2309.00 FSAR 10. 4. 9. 1. 1 AFW SYSTEM SAFETY AFW CAN BE OPERATED 04 X 0 DESIGN BASES. FROM THE SRUTDOWN PANELS AND THE AUXILIARY FEED WATER PANEL 2310.00 FSAR 10. 4. 9. 1. 3 AFW SYSTEM CODES AND DESIGNED AND 04 X 0 STANDARDS CONSTRUCTED IN ACCORDANCE WITH SAFETY CLASS 3 TO CONTAINMENT ISOLATION VALVES AND THE REMAINING SYSTEM IS SAFETY CLASS 2. O O O
Mo. 29 11/10/87 , PLANT V0GTLE UNIT 2 READINESS REVIEW PROGRAM MODULE 04 COMMITMENT MATRIX CURRENT THRU FSAR AMENDMENT 34
======================================
REF. COMMITMENT COMMITMENT COMMITMENT DOCUMENT / MOD DES CON FSAR REMARES NUMBER SOURCE SECTION SUBJECT FEATURE ULE IGN ST AMEN ,
======= ========== ==================== ==================== ==================== === === === ==== ====================
2311.00 FSAR 10. 4, 9. 2. 1 AUX. FERDWATER ATW MIN. FLOW TO AT 04 X 0 , SYSTEM GENERAL LEAST 2 S/G'S IS DESCRIPTION DELIVERED WITRIN 1 MIN. OF RECEIPT OF SIGNAL 4924.00 FSAR 10. 4. 9. 2. 1 AFW SYSTEM DESIGN CONDENSATE STORAGE 04 X 0 TANE PROVIDES FOR COLD SRUTDOWN FOR A PERIOD OF 9 ROURS i 4 NOURS AT NOT ! STANDBY FOLLOWED BY A 5 ROUR C00LDOWN. ! 451.00 FSAR 10. 4. 9. 3 AUXILIARY FEEDWATER BTP ASB 10-1 04 X 0 SYSTEM 1 2313.00 FSAR 10. 4. 9. 3 AUX FREDWATER SYSTEM EQUIPMENT OR 04 X 0 SAFETY EVALUATION STRUCTURES NOT SEISMIC CATEGORY I AND WROSE COLLAPSE COULD RESULT IN LOSS OF AFW FUNCTION ARE CRECRED TO DETERMINE THEY WILL NOT COLLAPSE UNDER A SSE OR ARE UPGRADED TO i CATEGORY I i 2314.00 FSAR 10. 4. 9. 3 AUI. FREDWATER NUREG-0737, II.E.1.1 04 X 0 RELIABILITY ANALYSIS SYSTEM SAFETY & II.E.1.2 EVALUATION 4925.00 FSAR 10. 4. 9. 3 AFW SYSTEM DESIGN AFW SYSTEM IS ROUSED 04 X 0 IN SEISMIC CATEGORY I STRUCTURES 4926.00 FSAR 10. 4. 9. 4 AFW PUMPS BACH AUXILIARY 04 X 0 FERDWATER PUMP IS HYDR 0 STATICALLY TESTED IN ACCORDANCE l WITN ASME III. CLASS 3. I l l
.2.-_.--...~..-.-.----...--.-...-...----..-..-- - - . . . - . - . . . - - . - . - . - . . - . . - - _ _ _ _ _ - - _
Page No. 30 ll/10/H7 PLANT V0GTLE UNIT 2 READINESS REVIEW PROGRAM MODULE 04 COMMITMENT MATRIX CURRENT TRRU FSAR AMENDMENT 34
======================================
REF. COMMITMENT COMMITMENT COMMITMENT DOCUMENT / MOD DES CON FSAR REMARKS NUMBER SOURCE SECTION SUBJECT FEATURE ULE IGN ST AMEN
======e ========== ==================== ==================== ==================== === === ==- ==== ====================
4927.00 FSAR 10. 4. 9. 4 AFW PUMPS TURBINE-DRIVER IS 04 X 0 TESTED IN ACCORDANCE GIVEN A RYDROSTATIC WITH API-STANDARD TEST. MECRANICAL GIS RUNNING TEST AND AN OVERSPEED TRIP TEST PRIOR TO SRIPMENT. 2321.00 FSAR 10A. 3. I AFW SYSTEM NUREG-0611 APP. III 04 X 0 METHODOLOGY- & ANN 1 0F APP. X RELIABILITY EVALUATION 2882.00 FSAR 15. O. 1. 5 TMI ACTION PLAN NUREG 0737 EXCEPT 04 X 0 FOR INAPPLICABLE II.K.2.19 (COMPLETION OF IIK3.30 AND .31 AWAITS NRC ACTION) 2883.00 FSAR 15. O. 8 MITIGATION OF ANSI Ni8.2-1973 04 X 0 ACCIDENT EFFECTS 2884.00*FSAR 15. O. 8 MITIGATION OF IEEE 379-1972 04 X 0 ACCIDENT EFFECTS 2885.00 FSAR 15. O. 8 MITIGATION OF PG 1.53 04 X 0 ACCIDENT EFFECTS 3361.00 FSAR IT. 1. 2 GPC Q.A. PROGRAM RG. 1.37 OA REQMNT. 04 X 0 1 REQUIREMENTS: FOR CLEANING OF
- CLEANING OF FLUID FLUID SYSTEMS AND SYSTEMS AND COMPONENTS COMPONENTS l 4506.00 GENERIC C-85/01/14 ADDITIONAL INFO. ON ASME III. SUBARTICLE 04 X 0 IEB 83-06.
l LETTER NON-CONFORMING NX-2600 MATERIALS SUPPLIED 1977 EDITION BY TUBE LINE CORP. - TWO INCR AND SMALLER FITTINGS I O O O
O page No. 31 O O 11/10/87 PLANT V0GTLE UNIT 2 READINESS REVIEW PROGRAM MODULE 04 COMMITMENT MATRIX e CURRENT THRU FSAR AMENDMENT 34
=====================================,
REF. COMMITMENT COMMITMENT COMMITMENT DOCUMENT / MOD DES CON FSAR REMARES NUMBER SOURCE SECTION SUBJECT FEATURE ULE IGN ST AMEN
======= ========== ==================== ==================== ==================== === === === ==== ==e=================
4507.00 GENERIC C-85/01/14 ADDITIONAL INFO. ON ASME III, SUBARTICLE 04 X 0 IRB 83-06 LETTER NON-CONFORMING NA 3767.4 CORR. MATERIALS SUPPLIED 1977 EDITION BY TUBE LINE CORP. - TWO INCR AND SMALLER FITTINGS 4892.00 IRB 79-03A C-81/04/02 SA-312 OR A-312 TYPE DESIGN STRESSES IN 04 X 0 300 SERIES FUSION SAFETY-RELATED WELDED PIPE COMPONENTS LIMITED TO 85% MAN. ALLOWABLE STRESS AT DESIGN TEMPERATURE 4679.00 IRB 79-24 C-79/ll/01 FROZEN LINES ALL SAFETY-RELATED 04 X 0 RESPONSE TO IRB PROCESS INSTR. & 79-24 SAMPLING LINES THAT ARE PHYSICALLY ROUTED IN AN AREA EXPOSED TO EXTREMELY COLD WEATHER SRALL BE PROVIDED WITH ADEQUATE REAT TRACING. 4673.00 IRB 79-28 C-80/08/05 POSSIBLE MALFUNCTION REPAIR VALVES WITH 04 X 0 GPC RESPONSE TO NRC. OF NAMCO MODEL BA180 NAMCO BA 180 DTD 12-17-80. REF.: LIMIT SWITCHES POSITION SWITCHES JPO 50-424, 50-425
# ELEVATED WITH SWITCH ROUSING RESPONSE TO IER TEMPERATURES #'S BETWEEN 01-79 79-28 (SAFETY-RELATED AND 08-79 PLACING EQUIPMENT) VALVES ON ROLD UNTIL REPAIR IS COMPLETE.
4674.00 IRB 80-05 C-80/08/05 VACUUM CONDITION LOW PRESSURF PROCESS 04 X 0 RESPONSE TO IBB RESULTING IN DAMAGE OR ROLDUP TANAS THAT 80-05 TO PROCESS OR ROLDUP CAN CONTAIN TAMES. RADIOACTIVE MATERIAL l ARE DESIGNED WITH FEATURES TO PRECLUDE l VACUUM CONDITIONS I 4 - .
Page No. 32 11/10/87 PLANT VOGTLE UNIT 2 READINESS REVIEW PROGRAM MODULE 04 COMMITMENT MATRIX CURRENT THRU FSAR AMENDMENT 34
======================================
REF. COMMITMENT COMMITMENT COMMITMENT DOCUMENT / MOD DES CON FSAR REMARES NUMBER SOURCE SECTION SUBJECT FEATURE ULE IGN ST AMEN
======= ========== ==================== ===========-======== ==================== === === === ==== ===================-
1832.00 IEB B0-08 C-80/bS/26 EXAMINATION OF SLEEVE INTO FLUED 04 X 0 RESPONSE OF 6-26-80 PENETRATION SLEEVE BEAD WELD, AT VENDOR TO I.E.B 80-08 TO FLUED READ (OR SHOP, SUBJECT TO IMMEDIATE SLEEVE FOR 100% RADIOGRAPHY FLUED READS EQUIPPED 1.A.W. NC-5200, & WITH INTERMEDIATE ACCEPTANCE CRITERIA SLEEVE) IAW NC-5320 5023.00 IRB 81-02 GEN. LTR. C-81/07/02 WESTINGHOUSE 3-INCH MODIFY WESTINGHOUSE 04 X 0 FOR DETAILS ALSO SEE CORRESP. AND 4-INCH GATE 3-INCR AND 4-INCH WESTINGROUSE FCN VALVE CLOSURE VALVES TO CORRECT GAEM-10549 PROBLEM CLOSURE PROBLEM 46T5.00 IEB 83-06 C-83/II/23 NONCONFORMING INV0EE SUBARTICLE 04 1 0 LETTERS GN-287 MATERIALS SUPPLIED NX-2600 ASME III, 11-23-83, GN-331 BT TUBE-LINE CORP. 1977 WHICH EXEMPTS 3-22-84, GN-507 2-INCH & SMALLER l-14-85, ADVISED NRC FITTINGS FROM OF CORRECTIVE ACTION NA-3700/NCA-3800 TO IEB 83-06 EXCEPT FOR
- REQUIREMENTS OF NA-3767.4 l 4219.00 NRC QUEST. 0210. 09 TUBE AND SHELL SIDE ASME III, CLASS 2 04 X 0 RESPONSE TO QUESTION CORRES. (ACCW) 0F SEAL WATER AND 3 RESPECTIVELY HEAT EXCHANGER OF CVC SYSTEM 4220.00 NRC QUEST. Q210. 10 CENTRIFUGAL CHARGING ASME I'I I , CLASS 3 04 X 0 Pr
- p;N3d TO QUESTION CORRES. PUMP LUBE OIL COOLERS:
CONSTRUCTION REQUIREMENTS . 4221.00 NRC QUEST. 0210. 11 NSCW SYSTEM COOLING ASME SECTION III, 04 X 0 RESPONSE TO QUESTION l CORRES. MATER SUPPLT AND CLASS 3 QUALITY RETURN PIPING FOR GROUP C PUMP MOTOR COOLERS l 0 0 0
s
)
~#
Page No. 33 11/10/87 PLANT V0GTLE UNIT 2 READINESS REVIEW PROGRAM MODULE 04 COMMITMENT MATRIX
- CURRENT THRU FSAR AMENDMENT 34
======================================
REF. COMMITMENT COMMITMENT COMMITMENT DOCUMENT / MOD DES CON FSAR REMARKS NUMBER SOURCE SECTION SUBJECT FEATURE ULE IGN ST AMEN
======= ===*====== ======e============= ==================== ==================== === === === ==== ====================
4223.00 NRC QUEST. 0210. 13 AUXILIARY FRED WATER ASME III. CLASS 3 04 X 0 0210.12 COMPONENTS CORRES. TURBINE LUBE OIL LISTED IN A.B.C. COOLERS RESPONSE TO QUESTION 4226.00 NRC QUEST. 0210. IT RYDROGEN RECOMBIN8RS ASME III. CLASS 2 04 X 0 0210.12 COMPONENTS CORRES. LISTED IN A.B.C. RESPONSE TO QUESTION 4194.00 NRC QUEST. Q410. 05 INTERNALLY GENERATED 10CFR50 APP. A. GDC 04 X 0 RESPONSE TO QUESTION CORRES. MISSILE SOURCE BY 4 NON-SAFETY-RELATED SYSTEM OR COMPONENT. j 4195.00 NRC QUEST. Q410. 06 SEISMIC INDUCED SEISMIC 2-OVER-1 04' I O RESPONSE To QUESTION CORRES. FAILURE OF SEISMIC ANALYSIS f CAT. 2 COMPONENT (WILL NOT RESULT IN FAILURE OF ESSENTIAL EQUIPMENT) 4230.00 NRC QUEST. 0410. 13 CRITERIA FOR FLOOD SINGLE ACTIVE 04 I O RESPONSE TO QUESTION CORRES. ANALYSIS FAILURE COINCIDENT WITE POSTULATED PIPING FAILURE EXCEPT FOR DUAL PURPOSE MODERATE ENER07 SYSTEM 4197.00 NRC QUEST. Q410. IT FLOODING ANALYSIS BTP MEB 3-1. PARA. 04 X 0 RESPONSE TO QUESTION CORRES. B.2.C(2) 4202.00 NRC QUEST. 0410. 39 AUXILIARY FRED WATER RG 1,139 POS. C.6 04 X 0 RESPONSE TO QUESTION CORRES. SYSTEM: CST CAPACITY 4203.00 NRC QUEST. 0410. 39 AUXILIARY FERD WATER BTP RSB 5-1. PARA. G 04 X 0 RESPONSE TO QUESTION CORRES. SYSTEM: CST CAPACITY _ b .__ m.m.._ _ _ _ . . _ _ _ _ _ _ _ . _ _ . _ _ . _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ . _ _ . _ ._ _. . - , . r - _--e..- _- -. . __ ,_. _-
Page No. 34 11/10/87 PLANT V0GTLE UNIT 2 READINESS REVIEW PROGRAM l MODULE 04 COMMITMENT MATRIX CURRENT TRRU FSAR AMENDMENT 34
======================================
REF. COMMITMENT COMMITMENT COMMITMENT DOCUMENT / MOD DES CON FSAR REMARKS NUMBER SOURCE SECTION SUBJECT FEATURE ULE IGN ST AMEN
====e== ========== ==================== =====e============== ==================== === === === ==== ====================
4262.00 NRC QUEST. Q440. 26 BTP RSB 5-1 ATMOSPRERIC DUMP 04 X 0 RESPONSE TO QUESTION CORRES. REQUIREMENT FOR VALVES DESIGNED TO STEAM GENERATOR FAFETT-GRADE ATMOSPRERIC DUMP STANDARDS. VALVES 4169.00 NRC QUEST. 0730. 01 SRUTDOWN DECAT REAT NUREG 0737 ITEM 04 X 0 RESPONSE TO QUESTION CORRES. REMOVAL REQUIREMENTS IIE.1.1 AND 118.1.2 - ALSO GENERIC ISSUE (A-45) A-45 0F MUREG 0636 4901.00 NRC QUEST. Q730. 01 FREDWATER SYSTEM BTP ASB 10-2 04 X 0 GENERIC ISSUE (A-1) CORRES. DESIGN AGAINST WATER OF NUREG 0606 RAMMER (A-1) RESPONSE TO QUESTION. l l I I l O O O -
a . Pl. ANT VOGTIE UNIT 2 READINESS REVIEW PROGRAM IMi'LEMENTATION MATHIX .
======_================_======e=====
DESIGN CONST REF. SOURCE AND DES CON CURRENT DESIGN CURRENT CONSTRUCTION NtNBER SECTION SUBJECT DoctMENT/ FEATURE IGN ST. AS OF: IMPLEMENTATION AS OF: IMPLEMENTATION REMARKS
======= =============== ===========;======== ==================== === === ======== ====================== ======== ===============e====== ====e====== = = = = = --
l EXPLANATION OF FRELDS REF NO. - A reference member that corresponds to the appropriate line entry In the comaltment metrix. SOURCE AND SECTION - The commItsent source and section to be implemented SUBJECT - The subj ect of the comeltment peregraph 00CUMENT/ FEATURE - The document discussed le the FSAR sectice or the pleet feetore descrlbed la the FSAR settles. ISee Commitment Matrix.) DESIGN / CONSTRUCTION - Ao X le placed ender the heading for the orgentretles responsible for leptementetles of the comeltment DESIGN CURRENT - The date that commitment Implementatles ses vertfled AS oft CONST CURRENT AS OF DESIGN - The Project decomestist that more revlemed te verify commItseet INPLEMENTATION Implementation CONSTRUCTION SNPLEMENTATlON
...-m .
Page No. I 11/10/87 PLANT V0GTLE UNIT 2 READINESS REVIEW PROGRAM t 4 IMPLEMENTATION MATRIX a MODULE 04
===e==================================
DESIGN CONST REF. SOURCE AND DoctMENT DES CON CURRENT DESIGN CURRENT CONSTRUCTION NUMBER MODULE SECTION SUBJECT DoctDEtNT/ FEATURE SECTION IGN ST. AS OF: IMPLEMENTATION AS OF: . IPFLEMENTATION REMARKS
======= ====== =============== ==================== ==================== ============ === === ======== =============== ======== =============== =============
1 154.00 04 FSAR DAprING VALUES ft)R RG 1.61 OC1t)eER, X 07-13-87 DC-1005-3.6.2 SEE FSAR SEISMIC DESIGN OF 17I3 REY. 1, 4-4-83 3.7.B.1 AND ,
- 1. 9. 61. 2 NUCLEAR PUNER PLANTS 3.7.N.1 256.00 04 FSAR ESF MAT *IS INTEGRITT RG 1.31 X 07-13-87 DC-1206-1.0 FOR CSS, CIS, OF SAFETT-RELATED REV. 2, 4-28-83 RHRS. SIS &
- 6. 1. 1. 1. 3 C0Pf0NENTS AfWS
! 258.00 04 FSAR ESF MAT'LS-INTEGRITT RG 1.37 ALL X 07-13-87 X4AZ01-Pl.ll.0. OF SAFETT-RELATED A. REV. 18,
- 6. 1. 1. 1. 00Pe0NENTS - QA 5-11-87 3.C REQUIREMENTS FOR X4A001-12.1, CLEAMING REY. 16, 7-20-84 259.00 04 FSAR ESF MAT'LS-INTEGRITT RG 1.44 X 07-13-87 DC-1206-1.0, FOR CSS CIS, ,
OF SAFETT-RELATED REY. 2, 4-28-83 RHRS SIS &
- 6. 1. 1. 1. 3 COPFONENTS AfWS 313.00 04 FSAR PRESSURIZER SAFETT ASPEt III X 07-13-87 DC-1201-2.0, VALVES DESIGN REY. 2, 3-9-84 '
5.'4. 13. 3 EVALUATION 322.00 04 FSAR ESF MATERIALS ASpet III, NC-2160 & X 09-11-87 DC-1206-2.0 B. FOR CSS CIS, 8 ELECTION & NC-3120 REV 2, 4-28-83, RRRS. SIS & l 6. 1. 1. I FABRICATION DC-1205-2.0.B.1 AFWS i
,REV. 2, 3-17-83 DC-1204-2.0.C.1 i
~ , REY. 2 2-11-83, DC-1302-2.2, REV. 5, 4-18-83, DC-2415-2.0, > REV. 1, 5-16-83
Parge Co. 2 11/10/87 PLANT V0GTLE UNIT 2 READINESS REVIEW PROGRAM IMPLEMENTATION MATRIX MODULE 04
===_==================================
DESIGN CONST REF. SOURCE AND DoctNENT DES CON CURRENT DES MN CURRENT CONSTRUCTION NINBER MODUIR SECTION SUBJECT DOCINENT/ FEATURE SECTION IGN ST. AS OF: IMPLEMENTATION AS OF: IMPLEMENTATION REMARES
=== === ====== =============== ==================== ==================== ============ === === ======== =============== ======== =============== =============
323.00 04 FSAR SPECS FOR ALL ASME III E 07-13-87 DC-1204-2.0C.I. PRINCIPAL PRESSURE RETAINING REY. 2. 2-11-83 PRESSURE
- 6. 1. 1. 1. 1 MATERIAL IN ESF RETAINING SYSTEM COMIVNENTS DC-1205-2.08.1 MATERIALS REV. 2. 3-17-83 INDICATED IN DC-1206-2.08 TABLE 6.1.1-1 REY. 2, 4-2& 83 DC-1302-2.2, REY. 5, 4-18-83 324.00 04 FSAR MATERIAL SPECS EVR ASMK III. DIV 1 x 07-13-87 DC-1206-2.0B, IVR CSS, RNR.
EST COMPONENTS IN NC-2000-CROUP B REV. 2 SIS, CIS &
- 6. 1. 1. 1. I CUALITY GROUP B, 4-28-83, AFWS CLASS 2 DC-1205-2.05.1 REV. 2, 3-17-83 DC-1204-2.0C.I.
REY. 2, 2-11-83, DC-2415-2.0, REV. 1, 5-16-83 325.00 04 FSAR MATERIAL SPECS. FOR ASMK III, DIV. 1, X 08-11-87 DC-1206- 2.0.B. IVR CSS, RHR, ESF COMP. IN QUALITT ND-2000 - CROUP C REV. 2 SIS, CIS &
- 6. 1. 1. 1. I GROUP C, CLASS 3 4-28-83, AFWS DC-1205-2.0.B.1
, REV. 2, 3-17-83, DC-1302-2.2, REY. 5, 4-18-83 DC-2415. 52.0, REY. 1, 6-16-83 326.00 04 FSAR ESF MATERIAIS SPEC. ASME MATERIAL SPEC. K 07-13-87 X4A037-6.lD. FVR CSS, RHR, REQUIREMENTS COMPLIANCE - SUBART. REV. 14, 5-3-87 SIS. CIS &
- 6. 1. 1. 1. I NA/NCA - 1220 AFWS s
e G G
s % j Pete No. 3 11/10/87 PLANT V0GTLE UNIT 2 READINES$ REVImf PROGRAM IMPLRMENTATION MATRIX MODUIA 04
======================================
4 DESIGN CONST REF. SOUNCE AND DOCl#ENT DES CON CURRENT DESIGN CURRENT CONSTRUCTION NINHER MDDULE SECTION SUBJECT DOCINENT/FEA111RE SECTION IGN ST. AS OF: IMPLEMENTATION AS OF: IMPID ENTATION RIMARKS
======= ====== =============== ==================== ==================== ============ === === ======== =============== ======== =============== =============
327.00 04 FSAR ESF MATERIALS ASPE III, NC-2000 & X 07-13-87 X4AQ10-4.lA, CONTAlfMENT NE-2000 MATERIAL REV. 6,
- 6. 1. 1. 1. 1 PENETRATION SPECS. 11-15-85 MATERIALS 328.00 04 FSAR ESF (X)MSTRUCTION ASME II SFA 5.1, X 07-13-87 X4AQ37-6.0A, ESF SYSTEMS MATERIAIS- WELD 5.2, 5.5, 5.17, 5.18 REV. 14, 6-3-87
- 6. 1. 1. 1. 2 MAT'L IVR JOINING & 5.20 FERRITIC BASE MAT'LS 329.00 04 FSAR ESF CONST. ASPE II SFA 5.11 & X 07-13-87 X4AQ37-5.0A, MAT'LS-WELD 5.14 REY. 14, 6-3-87
- 6. 1. 1. 1. 2 MATERIALS FVR JOINING N1-CR-fi ALIDTS 330.00 04 FSAR ESF CONST. MAT'LS ASPE II SFA 5.4 & X 07-13-87 X4AQ37-5.04, IVR JOININO 5.9 REY. 14, 5-3-M
- 6. 1. 1. 1. 2 AUSTENITIC S.S 331.00 04 FSAR
~
ESF CCNST. ASME III X 07-13-87 I4AQ37-5.0A, ESF SYSTEMS MAT'LS-WELD MATERIAL REV. 14, 5-3-tr1
- 6. 1. 1. 1. 2 QUALIFICATION 333.00 04 FSAR ESF CONST. MAT'L - LIMITED TO NO X 07-13-87 DC-1204-4.0L, COLD WORRED GREATER THAN 90,000 REY. 2,
- 6. 1. 1. 1. 2 AUSTENITIC S.S. pel TIEla STRENGTH 2-11-83 DC-1206-4.ON, REV. 2, 4-28-83, IX4DR004, REV.
22, 2-13-87 AX4DR001 REV. 19, 7-24-86 384.00 04 FSAR MSCN SYSTEM NSCW PtNP AND X 07-13-87 DC-1202-2.C. EQUII?WtNT DESIGN TRANSFER PIMP ASME REY. 5,
- 9. 2. 1-3 III, CLASS 3 4-19-83, DMCN-3, 5-15-15, DC-1010-TI-P.19
, REV. 5, 2-7-86 I
______ ______ _______ ___________z_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
Page No. 4 11/10/87 PLANT V0GTLE UNIT 2 READINESS REVIEW PROGRAM IMPLEMENTATION MATRIX MODULE 04
==========u ====== ===================
DESIGN CONST REF. SOURCE AND DOCINENT DES CON CURRENT DESIGN CURRENT CONSTRUCTION MlNBER MODULE SECTION SUBJECT PoctNENT/IEATURE SECTION IGN ST. AS OF: IMPLEMENTATION AS OF: IMPLEMENTATION RIMARKS
===~=== === == =============== ==================== = ================= =====-====== === === =====-== =============== ======== =============== =============
388.00 04 FSAR CCW SYSTEM DESIGN ASME III, CL. 3 X 07-13-87 DC-1203-3.lF. (EXCEPT CHEM AUD. REV. 6. 11-2-83
- 9. 2. 2. 1 TANK AND ASSOCIATED PIPING) 390.00 04 FSAR CCW SYSTEM COLD BTP RSB 5-1 X 08-11-87 DC-1205-1.0, SITUTDOWN REV. 2,
- 9. 2. 2. 3.4 REQUIREMENTS 3-17-83, DC-1203-3.lK.
REY. 6, 11-2-83, DMCN-4,- w 12-29-8G' 1 393.00 04 FSAR CCW SYSTEM EQUIINENT EQUIINENT CODES AND I 07-13-87 DC-1203-2.0, DESIGN PARAMETERS STANDARDS REY. 6, 11-2-83
- 9. 2. 2-1 400.00 04 FSAR ULTIMATE REAT SINK RG 1.27 X 07-13-87 DC-1202A-1.0, SYSTEM DESIGN - REY. 5, 4-19-83
- 9. 2. 5 SMRAGE CAPACITY OF DIO NSC TOWER BASINS 401.00 04 FSAR ULTIMATE REAT SINK SEISMIC CAT. I X 07-13-87 DC-1202A-3 lA.
WWERS AND BASINS REY. 5, 4-19-83
- 9. 2. 5. 1 DESIGN 402.00 04 FSAR ULTIMATE HEAT SINK BTP ASB 9-2 X 07-13-87 DC-1202A-1.0, SYSTEM PERmfMANCE REV. 5, 4-19-83
- 9. 2. 5. 2. 4 (RESIDUAL HEAT DECAY) 403.00 04 FSAR ULTIMATE HEAT SINK RG 1.27 X 07-13-87 DC-1202-A-1.0A, SYSTEM PERmfMANCE REY. 5, 4-19-83
- 9. 2. 5. 2. 4 (BASIN SIZING) 406.00 04 FSAR REACMR MAKEUP WATER SEISMIC CAT. I X 07-13-87 DC-2128-1.0, S M RAGE TANK DESIGN REV. 2, 8-19-83
- 9. 2. 7. 2. 2 s
S 9 9
q ,m Page No. r
)5 (v) )
1I/10/87 PLANT V0GTLE UNIT 2 READINESS REVIEW Pfl0 GRAM IMPLEMENTATION MATRIN MODULE 04
======================================
DESIGN CONST REF. SOURCE AND DOCtNENT DES COM CURRENT DESIGN CUWENT CONSTRUCTION NINBER EDULE SECTION SUBJECT DoctMENT/ FEATURE SECTION IGN ST. AS OF: IMPLEMENTATION AS OF: IMPLEMENTATION REMARKS
======= ====== =============== ==================== =======e=== ======== ============ === === ======== =============== ======== =============== =============
411.00 04 FSAR ACCW SYSTEM DESIGN EQUlFNENT CODES AND I 07-13-87 DC-1217-2.0, ANSI B31.1, PARAMETERS STANDARDS REY. 1, 3-9-83 ASME III
- 9. 2. 8-2 CLASS 3. ASME DC-1010-TI-P.21 VIII NEMA
, REV. 5 W I, TEMA R 2-7-86 418.00 04 FSAR ULTIMATE REAT SINE RG 1.27 X 07-13-87 DC-1202-A-1.0A, SA RTY DESIGN BASES REY. 5,
- 9. 2. 5. 1. 4-19-83, l.B DMCN-2, 6-7-85 421.00 04 FSAR SFPCPS DESIGN RG 1.13 X 07-13-87 DC-1213-1.0, REY. 2 5-31-83
- 9. 1. 3. 5.B 441.00 04 FSAR FEEDWATER STS. FROM ASME III, CLASS 2 X 07-13-87 DC-1305-3.18,RE STM. GEN. MAIN AND V. 4, 3-22-83
- 10. 4. 7. 1. 1 BYPASS REDWATER INLETS TO THE FIRST SEISMIC RESTRAINT .
UPSTREAM OF THE CONTAINMENT ISOLATION VALVES 442.00 04 FSAR MAIN FFEDWATER ASME XI X 07-13-87 DC-1305-3.lF, SYSTEM REV. 4, 3-22-83
- 10. 4. 7. 1.
1.D 443.00 04 FSAR CONDENSATE & RG 1.26 X 07-13-87 DC-1305-1.0, FEEDWATER REV. 4, 3-22-83
- 10. 4. 7. 1.
1.E 444.00 04 FSAR CONDENSATE & RG 1.29 X 08-11-87 DC-1305-1.0, FEEDWATER REY. 4, 3-22-83
- 10. 4. 7. 1.
1.E
Page No. 6 11/1C/87 PLANT V0GTLE UNIT 2 READINESS REVIEW PHOGRAM IMPLEMENTATION MATRIX PODULE 04
===========_==================== =====
DESIGN CONST REF. SOURCE AND DOCtNENT DES CON CURRENT DESIGN CURRENT CONSTRUCTION NUMBER MODULE SECTION SUBJECT DOCINENT/ FEATURE SECTION IGN ST. AS OF: IMPLEMENTATION AS OF: IMPLEMENTATION REMARKS
======= ==_=== =============== ========_=========_= =========_========== ============ === === =====_-== =====_========= ===_==== =============== =============
l 451.00 04 FSAR AUX 1LIART FEEDWATER BTP ASB 10-1 X 07-13-87 DC-1302-1.0, SYSTEM REY. 5, 4-18-83
- 10. 4. 9. 3 457.00 04 FSAR AUXILIART FEEDWATER ASME III, CLASS 2 X 07-13-87 DC-1302-3.1.IW, SYSTEM, DESIGN CODE AND 3 REY. 5, 4-18-83
- 10. 4. 9-1 682.00 04 FSAR QUAL. CROUP CLASS. RG 1.26. REV. 3, X 07-13-E7 DC-1010-TI-P.2, REF. 73AR AND STANDARDS MR 2/76 REY. 5, 2-7-86 TABLE 3.2.2-1
- 1. 9. 26, 2 WATER. STEAM &
RADWASTE CONTAINING COMPONENTS OF NPP 683.00 04 FSAR ULTIMATE REAT SINK RG 1.27, REV 2, 1/76 I 07-13-87 DC-1202-A-1.0, REF. TABLE mR NUCLEAR F0WER REV. 5, 4-19-83 9.2.5
- 1. 9. 27. 2 PLANTS I 711.00 04 FSAR SLNPS mR EMERGENCT RG 1.82, 6/74 X 07-13-87 DC-1204-3.lJ. SEE FSAR CORE COOLING AND REV.2, 2-11-83 6.2.2 AND
- 1. 9. 82. 2 CONTAINMENT SPRAY 6.3.2 SYSTEMS 808.00 04 FSAR CONMENANCE WITR NRC 10CFR50 APP. A, X 08-11-87 DC-1206-1.0, CDC, CONTAIPNENT GDC-41 REY. 2,
- 3. 1. 4 ATNOSPRERE CLEANUP 4-28-83, DC-1206-3.lB.
REV. 2, 4-28-83, DMCN-1, 5-31-83, DC-1513-1.0 & 3.1.IE. REY. O, 6-3-83 809.00 04 f3AR CONMfMANCE WITR NRC 10CFR50, APP. A, X 08-11-87 DC-1206-1.0, GDC. INSPECTION OF GDC-42 REV. 2,
- 3. 1. 4 CONTAINMENT 4-28-83 ATMOSPRERE CLEANUP DC-1513-3.1.10 SYSTEM REV. O, 6-3-83 O O O
Pop Ne il/10/fF PLANT V0GTLE UNIT 2 READINESS REVIEW f?0 GRAM ipa'LEPE!NTATION MATRIX MODUIE 04
==============================-=======
DESIGN CONST REF. SOURCE AND DOCt#EINT DES CON CURRENT DESIGN WRRENT CONSTRUCTION NtPSER MODUIE SECTION SUBJECT DoctNENT/ FEATURE SECTION IGN ST. AS OF: IT LEMENTATION AS OF: IWLEPECNTATION REMARES
======= ====== =============== ==================== ==================== =___________ === === ======== =============== ======== =============== =============
859.00 04 FSAR PRINCIPAL CODES AND (TEMA C R) TUBULAR X 07-13-87 DC-1010-T1, TABLE 3.2.2-1 STANDARDS FOR EXCH. MTW. ASSOC. REY. 5, 2-7-06 NOTE (g),
- 3. 2. 2-1 T.3.2.2-1 CLASS C OR R TABIE 3.2.2-2 830.00 04 FSAR PRINCIPAL CODES AND ASME III, CLASS X 07-13-87 DC-1010-T2, TABLE 3.2.2-1 STANDARDS PVR 1,2,3 OR MC, NF, OR REY. 5, 2-7-06 COL (g)
- 3. 2. 2-1 T3.2.2-1 CS 880.01 04 FSAR PRINCIPAL CODES AND ASME III (1977-4rT7) NB/NC/ND X 05-13-87 PPP PROCEDURES ADDED MORE STANDARDS IVR GENERAL REQUIREPEtNTS 4100 VI-5 7-3-86, DETAILED
- 3. 2. 2-1 T3.2.2-1 VII-2 6-27-06, CRITERIA IVR VIII-l 8-27-86, ARC STRIEE VIII-3 7-6-86, REMOVAL IX-3 6-15-86 II-14 8-15-86, 11-52 6-20-86 880.02 04 FSAR PRINCIPAL CODES AND ASPE III (IW7-trT7) NB/NC/ND X 05-13-87 ITP PROCEDURES NO NOT STANDARDS IVR PU8 MING, FITTING, 4200 IX-3 6-15-86, BENDING
- 3. 2. 2-1 T3.2.2-1 AND ALIGNING IX-16 6-19-86, PERftMEID IX-19 12-3-86 ON-SITE IX-43 12-16-86, IX-44 4-4-83, X-18 2-7-87, GNS III/I 5-28-86 880.03 04 FSAR PRINCIPAL CODFS AND ASME III (1977-W77) NB/NC/ND X 05-13-M ITf' PROCEDLRES STANDARDS PVR WELDING 4300 GWS III/I
- 3. 2. 2-1 T3.2.2-1 QUALIFICATIONS 5-28-86, 11-8 6-12-86 880.04 04 FSAR PRINCIPAL C Q ,AND ASPE SECTION III NB/NC/ND X 05-13-EFT PPP PROFEDURES REQUIREPEINT STANDARDS i C (1977-W77) RULES 4400 VII-2 8-27-86, 1U GRIND
- 3. 2. 2-1 T3.2.2-1 00VERNING MARING, VIII-l 8-27-86, EXfDSED EXAMINING, AND VIII-3 7-6-86, THREADS PRIOR REPAIRING NELDS IX-3 6-15-86 TO SEAL ;
IX-14 8-15-86 WELDING ADDED ' II-19 12-3-86, 4/24/81 10 IX-43 12-16-86, X-18. NO , IX-44 4-4-83, PERMING j X-18 2-7-87 ALIDWED AT IIII-4 2-20-87, PLANT V0GTLE. OWS III/I 5-28-86
Page No. H 11/10/R7 PLANT V0GTLE UNIT 2 READINESS REVIEN PROGRN4 IMPLEMENTATION MATRIX m DULE 04
=========================e============
DESIGN CONST REF. SotHCR AND DOCtNENT DES COG CtHRENT DESIGN CimRENT CONSTRUCTION NIMP5R MODULE SECTION St% JECT DOCINENT/FEATtME SECTION IGN ST. AS OF: IMPLEMENTATION AS OF: IMPIJNENTATION REMARKS
=- = ==-=== ======= ==-==== ==================== === =====_========== ============ === === ======== =============== ======== =====-========= ===========_= %% ' S 04 FSAR PRIPK'IPAL CODES AND ASME III (1977-W 7) NB/NC/ND X 05-13-87 ITP PROCFDURES NO ASME STANDARDS MR BRAZING 4500 BI-P107-F102-R1 BRAZING
- 3. 2. 2-1 73.2.2-1 01 8--11-80 PFRIVRMED AT PLANT V0GTLE.
8R0.06 01 FSAR PRINCIPAL CODES AND ASME III (1977-W77) NB/NC/NU X 05-13-87 ITP PROCEDimES STANDARDS FVR POS1 WEIR HEAT 4600 IX-3 6-15-86,
- 3. 2. 2-1 T3.2.2-1 TREA1 MENT IX-43 12-16-86, X-18 2-7-87, GWS III/I 5-28-06 880.07 04 FSAR PRINCIPAL CODES AND ASME III (lW7-W77) NB/NC/ND4700 X 05-13-87 ITP PROCEDLTES STANDARDS FUR K'*3tANICAL JOINTS IX-5 2-12-87
- 3. 2. 2-1 T3.2.2-1 RRO.08 J4 FSAR PRINCIPAL CODES AND ASME III (1977-W77) NC/ND4800 X 05-13-87 FIT PROCEDlmES STANDARDS FUR EXPANSION JOINTS IX-3 6-15-86,
- 3. 2. 2-1 T3.2.2-1 IX 19 12-3-86 180.09 04 FSAR PRINCIPAL CODES AND ASME III (l W7-W77) NB/NC/ND X 05-13-87 ITP PROCEDURES STANDARDS FUR EXAMINATION 5000 IX-3 6-15-86,
- 3. 2. 2-1 T3.2.2-1 X-18 2-7-87 11-2 8-15-86, II-3 8-19-81
, BRO.10 04 FSAR PRINCIPAL CODE AND ASME SECTION IIT NB/NC/ND6000 X 05-13-87 FIT PROCEDLPES ! STANDARDS FVR (1977-W77) TESTING XI-l 6-15-86, l 3. 2. 2-1 T3.2.2-1 X-19 12-3-86 l j 924.00 04 FSAR MISSILE FPOTECTION 10CFR50, AIT. A. GDC I 07-13-87 DC-1006-1.0, 4 REV. 2, 7-13-83 l 3. 5 941.00 04 FSAR IVSTULATED PIPING BTP ASB 3-1 X 08-11-87 DC-1018-1.0, FAILURES IN FLUID REV. 2,
- 3. 6. I SYSTEMS OUTSIDE 10-11-83 CONTAINMENT l
l l O O 9
.l
- 5~
E g l: !3 : ( IE :!al
! 445g"*
Eun
.322, E ll E p i;
~ < , ,
W il ,, ll k- ,i:, ; t .. !l E 8 llo 8 El J " " -
- 5 lll . .
- - = a E a ll
* ~ E >
9 a a E g ., - o e . . . . . . r? m . s"a saa sa .Edg sea?f 4 .E a .8 s .8 . 4"EJE ..ae"E. 4"E ! 5 Ell :: 5"a ssa*JE Ts-a s44 E 5 '?-E T .: 7 E TE.ETM-EEE BES saabk E3254 ETETE,TE~EEEE" g g ll T4" T ** T ? >* T .
.l EMS .2 E 2 E .E !
i E g !l E E E E E E f !! El!E ll st E f! h n8 h E h E h 8 h h 8 E ll . , , E- !: $ t;; . , E~ !l m ,, ! g (( E w w w w w w ; E g E ;l
~ l 4 !
~ !
l S ~.
. g ll, ,
E ':, .. E u g l~l lll ~
- 9A A ll E. ;lll .
~
. ~. ~.
~
EI!!
"1 ll ll Eg i
m t; ll El - Et , 2 12 ll
>R s g.
ll - EB E EK - - - t E " E l:l A .- gB E R A A A i e r: -s < . . EE I kg g"E E E I . U 8 ., :: E. A8
.- E.E5 h. -b b
4 ll t ll E2 2 g 5$ g E g a
! EEE5g "! 3
*- ER til t B ll EmEElb5 * *~h"f "
gWg 5 g EEE ll l g, E gp g ll gg E RE .- fSt3 EE l ka
~
Yn =4 gt5u g 3gt gE* .
! ll!! EEEEHE SM ssBE sEEM m!E t ll u 1
- u u ; - - !
E,U - A a a a a l "2l . . . .~ . . t E 5
- 5
- 5
- 5 *4 5* 5
- 8mg "ll E 4 l
2 4 E d E W: E d E 4 ,
- 5 ll
*l
$ ll 5 E E E E E ,
ik i/ E ll 8 8 8 8 8 8 s2 E t ll a a i & a c V5 c- Ej E E E 8 E 8 t
- a ll E@ 9 i
E U ~ hg8 go$2= t E 855
$o 2 ~
-" u g .-2* 7 e.
!E!~w$Et ou Em = o r
E.:: :l g s"
. ucsg .s
. : sues 5eg"g geregist-w=c=.Ena8g <
r ll x 2 :l 2 4 ll D E :: S !,! B B, k !,! 91 E .. ll eao Ep ll B d u !l
" * " g m: -
t E 2 ll * " E "! 4 nu n n n a n ob n* n
$ ll! A.. A" a . .e . .a . 46 A. a 4"BJE sgE e"B.48.Ee"B 6"E e .8 El B 5 l,
~ scaTa EEa Esa??s?assa n .
8" ssa - -". 4 5
., = - - n - g- -. -g-E t_ ,,:
- o. -g&$n 8' .- A - 8' s. a gA 8' .- -A A 8' .A 8'*E 8' .s
*s B'E-
[ 8 g ll B B B s B B [ !! ll =ce 5 $ u l: s !l s s 6
?
s
?
a E ll .. C= ll 8 ts ll mE!! gg ::
=
o-o5 l: - = = = x W g E ll ll 4
~
l E E" $ 0 lll E x ll E ta 2 ll u 4 o o
" g E ll: g :l n a : 6 4 t :3 ll w: 4 4 4 4 4 Ek- ,,ll o o = ll :
E ll 3 :: 9 :: c ll c li E !! s e n vn n n n 3 m m .,;; . . . . . f l,l E E E E E H, : l,, b b b b t
- - a se s .
ll $0 4 g: gEQ = E E! 3=g h ll o EEg m$u mE Eg~ won sgt
=g=
a
*fn-5dE ll Egm W-50 nrgt E
E5u. a WEE E ag"3-
# N "s 5 lll l "gcm "U o C "De *E
- GEE 12 ll E E.g$o*3
$"w -
m l: h S$IF
- EEu5*3 E$i 85EEEA b<EE
!! d d ll ; : a ; :
k , ll 4 4 4 4 N
" 2 ll .- . .
5 *.4,
$ t; ll
- 5 *< 5 *d 5 *. 5 .
8 n ll c4: E 4; E da c c es 2 5 ll 0 ,,
$ ,,ll 3 E E E E ik 65" 8 8 8 8 8 is E f t: s s e g e 2D u E ,,
$ $ $ 8 8
Pega No, il 11/10/87 PLANT V0GTIE UNIT 2 READINESS RRVIEW PROGRAM IPW'LEMENTATION MATRIX MODULE 04
=-=-===-====================--=====e==
DESIGN CONST REF. SOURCE AND DOCtMINT DES COM CURRENT DESIGN CURRENT CONSTRtCTION NtNBER MODULE SECTION SUBJECT DOC 1 MENT /ITATURE SECTION IGN ST. AS OF: IMPLEMENTATION AS OF: IMPLFMENTATION RPNARKS
======= ====== =============== ===================e ===============-==== ============ === === ==-===== ============ == ======== =============== ========= ===
959.00 04 FSAR FUS1ULATION OF PIPE B11' MEB 3-1 B.2.c I 07-13-87 DC-1018-TI, 115tRE ARE NO BREAKS AND THRU-NALL REV. 2 CLASS I M00.
- 3. 6. 2. 1. 2. LEAKAGE IN ASME 10-11-83 ENERGY LINES 4 SECTION III CLASS 1 DMCN-4, 9-30-85 PIPING MODERATE ENERGY 900.00 04 FSAR IVSTULATION OF PIPE BTP MEB 3-1 B.2.c I 07-13-87 DC-1018-3.38.7n BREAKS AND THRU--NALL , REV. 2,
- 3. 6. 2. 1. 2. LEAKAGE IN ASME 10-11-83 4.c(2) SECTION III CLASS 2 l AND 3 & NON-NUCLEAR PIPING MODERATE ENERGY 961.00 04 FSAR IDMGITUDINAL BREAK BTP MtB 3-1 B.3.b X 07-13-87 DC-1018-TI, SEE REF. NO.
IVSTULATION AT REY. 2, 950 FUR PIPE
- 3. 6. 2. - 1. 2. INTEIMIDI A11t FUINTS 10-11-83 BREAKS IN RCL 2.A OF HIGH ENERGY l SYSTEPE OTHER TRAN RCL FEG.00 01 FSAR PROTECTIVE ASSEMBLY BN-1DP-2 SECT. 3.0 X 07-13-87 DC-1018-2.0, DESIGN CRITERIA, REY. 2,
- 3. 6. 2. 4. 'l BARRIER AND SHIELD 10-11-83 DESIGN 1302.00 04 FSAR MAZARDS EVALUATION STRUCTURE DESIGNED X 07-13-87 DC-1018-APP.B.
PEIV & MFIV FOR ENVIR0!WWINTAL REY. 2, 3F. 4. 2. I COMPARTMENT CONDITIONS FROM 10-11-83 BREAK BOUAL 10 ONE DMCN-15, 1-2-87 C90SS SECTION AREA OF MAINSTRAM LINE OR MAIN FYEDNATER LINE 1 1326.00 04 FSAR CONTAlfeetNT COOLING ASPEt XI X 08-11-87 DC-10ll-2.0, SYSTEM, SAf1 TTY REY. 1, 12-9-80
- 6. 2. 2. 1. 1. DESIGN BASES 1.D INSERVICE INSPECTION
_ ______.___m_.. ._m_.____m_. .___._.mm . - - - - - - _ _ - _ . --. _ . _ _ - - - - - - _ - - - _ _ . -
Paga Co. 12 11/10/87 PLANT V0GTIE UNIT 2 READINESS REVIEW FTOGRAM IMPLEMENTATION MATRIX MODUIR 04
======================================
l l DESIGN CONST ( REF. SOURCE AND DoctNENT DES CON CURRENT DESIGN C1'RRENT CONSTRUCTION l NtNBER MODULE SECTION SUBJECT DoctNENT/ FEATURE SECTION IGN ST. AS OF: IMPIDENTATION AS OF: IMPLEMENTATION REMARKS
------= ====-= ======e======== ==================== ==================== ============ === === ======== =============== =-====== = ============= =============
1352.00 04 FSAR SPRING LOADED SAFTTY ASME III X 07-13-87 DC-1301-2.0, & VALVES 3.10. REV.5, l
- 10. 1. 2.B 3-29-83 1359.00 04 FSAR MAIN STEAM DESIGN RTP MEB 3-1 X 08-11-87 DC-1018-1.0, FIPIPG/ VALVES I
BASIS REV. 2 I1KN S/G 7t>
- 10. 3. 1. 1.C. 10-11-83 AND 1NCLUDING 1 Pird RESTRAINT DOWNSTEAM OF EACH MSiv 1360.00 04 FSAR DESIGN OF SAFETY ASME III CLASS II X 07-13-87 DC-1301-3.lA, SEE TABI.E RELATED FORTIONS OF AND SEISMIC CAT. I REV. 6, 3-29-83 10.3.2-1
} 10. 3. 1. 1.C MAIN STEAM SUPPLY EEQUIREMENTS. I STSTEM l 1363.00 04 FSAR INSERVICE INSPECTION ASME II X 07-13-87 DC-1301-2.0, ACCESS 10 WELDS AND REY. 5, 3-29-83 [ 10. 3. 1. 1.F RINOVABLE INSULATION i 1369.00 04 FSAR MAIN STEAM SUP. SYS. ANSI B36.19 M R 5.5. X 07-13-87 AX4DR001-GN-2,R MATIS SELRCTION & PIPE EV. 16, 4-12-85
- 10. 3. 6. 2 FABR. MR PIPING, FLANGES.FITTI NGS, VALVES & OTIER PIPING MATLS 1370.00 04 FSAR MAIN STEAM SUPPLY ANSI B36.10 WR C.S. X 07-13-87 AX4DR001-CN-2 SYSTEM MATLS. PIPE REV. 16,
- 10. 3. 6. 2 SELECTION & FABR. 4-12-85 MR PIPING, FLANGES, FITTINGS, VALVES &
OTHER PIPING MATERIALS 1371.00 04 FSAR MAIN STEAM SUITLY ANSI B16.9, B16.11 E 07-13-87 AX4DR001-CN-2, SYSTEM MATERIALS OR B16.28 mR S.5. REY. 16,
- 10. 3. 6. 2 SELECTION & FABR. FITTINGS AND C.S. 4-12-85 MR PIPING, FLANGES, FITTINGS FITTINGS, VALVES &
OTRER PIPING MATERIALS O O O
'f'ege No. 13 11/10/87 PLANT YOGTLE IMIT 2 READINESS REVIEN PROGRAM I T LEMENTATION MA1RIX MODULE 04
======================================
DESIGN CONST REF. SOURCE AND DoctMINT DES COM CURRENT DESIGN CURRENT CONSTRUCTION NtNBER MODUIE SECTION SUBJECT DOCINENT/ FEATURE SECTION IGN ST. AS OF: IPFLEMENTATION AS OF: IMPlJU1RNTATION REMARKS
======= ===-== =============== ==================== ==================== ============ === === ======== ===== ========= ======== ======== ====== =============
1372.00 04 FSAR MAIM STEAM SUP. STS. ANSI B16.5 FVR S.S. X 07-13-M AX4DR001-GN-2, MATIS SELECTION & & C.S FLANGES REV. 16,
- 10. 3. 6. 2 FABR. PVR PIPING, 4-12-85 FLANGES, FITTINGS, VALVES & OTRER PIPING MATL.
1374.00 04 FSAR MAIN STEAM SUP. SYS. ASPE MATTRIAL X 07-13-87 AX4DR001, REV. MATLS SELECTION & SPECIFICATIONS 16, 4-12-85
- 10. 3. 6. 2 FABR. FVR PIPING, FLANGES, FITTINGS, VALVES & OTHER PIPING MATL.
1509.00 04 FSAR NPSR IVR ECC AND NG 1.1, REV. 0 (NOV. X 07-13-87 DC-1204-3.lc, REF. CONTAlfMINT REAT 70) REV. 2, 6.2.2.2.2.3.2
- 1. 9. 1. 2 REMOVAL SYS111M PtPFS 2-11-83, . & SECT. 6.3 DC-1206-3.lF.
REY. 2, 4-28-83, DC-1205-1.0, REY. 2, 3-17-83 1532.00 04 FSAR SEISMIC DESIGN RG 1.29,_ REY. 3 X 07-13-87 DC-1010-71, REF. TABLE CLASSIFICATION REPT., 1978 REV. 5, 2-7-86 3.2.2-1 1
- 1. 9. 29. 2 1543.00 04 ISAR PROTdCTION AGAINST BTP PEB 3-1 AND ASB X 08-II-M DC-1018-1.0, REF. TABlJ[
PIPE BREAR INSIDE 3-1 REY. 2, 3.6.1-2 &
- l. 9. 46. 2 CONTAINMENT 10-11-83 SECT. 3.6, NCAP-8172A, ANSI 20.2 DRAFT IN LIEU OF RG 1.46 1551.00 04 FSAR Af?LICATION OF NG 1.53, REV. 0 X 07-13-87 DC-1009-1.0, SEE FSAR SINGLE FAILINER (JUNE 73) REV. 2, 6-3-83 REF. 7.1.2.6
- 1. 9. 53. 2 CRITERION & 15.0.8
Page No. 14 11/10/87 PLANT YOGTLE UNIT 2 liEADINESS REVIEW I'ROGRAM IMPLEMENTATION MATRIX MODUIR 04
======================================
DESIGN CONST REF. SOURCE AND DOCINENT DES CON CURRENT DESIGN CURRENT CONSTRUCTION NtNBER PODULE SECTION SUBJECT DOCtNENT/ FEATURE SECTION IGN ST. AS OF: IMPLEMENTATION AS OF: IMPIRMENTATION REMARKS
=== === ====== =============== ===== ============== ==================== ============ === === ======== ============ == ==== === =====-========= =============
1565.00 04 FSAR DESIGN AND FAB. CODE RG 1.81. REY. 20 X 07-13-87 11P+{29.9 REY. REF. TABLE CASE ACCEPT. ASME (NOV. 82) 4, 8-8-84 1.9-1 PARA.
- 1. 9. 81. 2 III, DIV. 1 5.2.1.2 TABLE 1.9-3 1569.00 04 FSAR MATERIAL CODE CASE RG 1.85, REY. 20 X 07-13-87 PHPt{29.9, REY. REF. TABLE ACCEPT ASME III. (NOV. 82) 4. B-8-84 1.9-2, 1.9-3
- 1. 9. 85. 2 DIV. I PARA. 5.2.1.2 1595.00 04 FSAR CUNTAIPNENT RG 1.141. REV. O, X 07-13-87 DC-2415-1.0, REF. 6.2.4 ISOLATION PROVISIONS (APRIL 78) REY. 1, 5-16-83
- 1. 9.141. 2 FVR FLUID SYSTEMS ' '
1599.00 04 FSAR FUNCTIONAL SPEC. FVR RG 1.148. REY. 0 X 07-13-87 DC-101FTI, REF. TABLE ACTIVE VALVE (MARCH 81) REY. 5, 2-7-86, 3.9.B.3-10
- 1. 9.148. 2 ASSEMBLIES IN X4AR01 ATT. 85, SYSTDG IMrURTANT TO REV. 14, 1-2'-87 SAFETY 1611.00 04 FSAR GUIDANCE FUR RHR MODIFIED 10 PROVIDE X 07-13-87 DC-1205-1.0D, AS DESCRIBED DESIGN SAFETT-GRADE COLD REY. 2, 3-17-83 IN FSAR 5.4.7
- 1. 9.139. 2 SilUTDOWN IN ACCORDANCE WITH RG 1.139 REV. O, MAT 78 1676.00 04 FSAR BOP SAFETT-RELATED INSHOP HYDROTEST OF X 07-13-87 X4AFV3-5.3.1.4, ACTIVE PUMP 3 CASING to 150% OF REV. 12,
- 3. 9.B. 3. 2 DESIGN PRESSURE 12-2-86 1679.00 94 FSAR BOP SAFETY-RELATED HYDROTEST - ASME III X 07-13-87 X5AC01-ATT.ll.
ACTIVE VALVES REV. 3, 9-27-79
- 3. 9.B. 3. 2. 2 l 1687.00 04 FSAR OPEN SYSTEM (PRESS. ASME III CODE CASE I 08-11-87 DC-1017-2.3.2, I
RELIEF) 1569 (i-40) REY. 5,
- 3. 9.B. 3. 3. 1 3-19-86, DMCN-3, 5-8-86, X4P0005. REV.
7, 12-18-8G, DC-1017-3.2A, REV. 5, 3-19-86 i O O O
Page No. 15 O O 11/10/87 PLANT 90GTIE UNIT 2 READINESS REVIEN PROGRAM IN LEMENTATION MATRIX MODULE 04
==============================-=======
DESIGN CONST RE F. SOURCE AND DOCUMENT DES COM CURRENT DESIGN CURRENT CONSTRUCTION NtNBER MODULE SECTION St'BJECT DOCLMENT/ITATURE SECTION IGN ST. AS OF: IMPLE N NTATION AS OF: IMPIJMNTATION REMARKS s====== =====r =============== ==================== ==================== ============ === === ======== ==========-==== ======== =======e======= =========e=== 1688.00 04 FSAR MAllIMlN ALIDNABLE 110% OF SHAM NC-7411 X 07-13-87 DC-1301-3.1G & INTERNAL PRESSURE CENERA1DR SHELL 3.1R. REY. 5, '
- 3. 9.E. 3. 3. 1 MAIN STEAM PIPE OR DESIGN PRESSURE AS 3-29-83 READER AT SAFETY PER ASME III VALVE INLET N0ZZIE 1707.00 04 FSAR BOP SAFETT-RELATED TO VERIFT OPENING & I 07-13-87 X5AC01-ATT-1A, ACTIVE VALVES CIDSING TIMES NITRIN REV. 4, 7-22-80
- 3. 9.B. 3. 2. 2 FUNCTIONAL TESTS SPECIFIED LIMITS 1743.00 04 FSAR PIPING SYSTEMS 10CFR50, APP. J X 07-13-87 DC-2415-2.0, SEE FSAR PENETRATING REV. 1, 5-16-83 3.1.3 00C 54
- 3. 1. 5 CONTAlfMENT 1744.00 04 FSAR RCPB LINES CIDSED SYSTEM X 07-13-87 DC-1205-2.08.1, SEE FSAR PENETRATING OUTSIDE CONTAllMENT REV. 2, 3-21-85 3.1.5 CDC 55
- 3. 1. 5 CONTAINMENT-RRR CONSDUCTED 10 ASM SYSTEM III CLASS 2 1753.00 04 FSAR VEGP 00ALITY GROUP RG 1.26 I 07-13-87 DC-1010-T1, CLASSIFICATIONS REV. 5, 2-7-86
- 3. 2. 2-1754.00 04 FSAR VEGP SEISMIC DESIGN RG 1.29 X 07-13-87 DC-1010-71 CLASSIFICATION REV. 5, 2-7-86
- 3. 2. 2 SYSTEM 1764.00 04 FSAR 2 INCR AND LARGER ASME III X 07-13-87 DC-1006-3.3.D.2 VALVE DESIGN , REY. 2,
- 3. 5. 1. 2. CRITERI A TO PRECLUDE 7-13-83 2.A VALYE BONNET EJECTION 1765.00 04 FSAR 2 INCR AND LARGER CONTROL OF IDAD I 07-13-87 DC-1006-3.3.D.2 VALVE DESIGN DURING BOLT , REY. 2,
- 3. 5. 1. 2. CRITERIA 10 PRECLUDE TIGHTENING 7-13-83 2.B VALVE BONNET EJECTION
< - - - - -= - - e.n m . % = . . . = - .- w, -t < - - _ <r
Pcge No. 16 11/10/87 PLANT V0GTLE UNIT 2 READINESS REVIEW PROGRAM IMPLEMEPrTATION MATRIX MODULE 04
====================_=================
DESIGN CONST REF. SOURCE AND DOCUMENT DES CON CURRENT DESIGN CURRENT CONSTRtCTION NtNBER MODULE SECTION SUBJECT DOCUMENT /fTATURE SECTION IGN ST. AS OF: IMPLEMENTATION AS OF: IMPLEMENTATION REMARM
======= ====== =============== ==================== ==================== ======e===== === === ======== =============== ======== ===========-=== =============
1767.00 04 MAR 2 INCH AND LARGER HTDROSTATIC TESTING X 07-13-87 X4AR01-13.9 VALVE DESIGN IN ACCORDANCE WITH REV. 14,
- 3. 5. 1. 2. 2 CRITERIA 1V PRECLUDE ASME III l-2-87 VALVE BONNET X4AR06-13.7 EJECTION REV. 11, 5-28-86, X4AR34-13.7 REV. 10, 5-19-86 1778.00 04 F3AR PIPE ATTACHED TO ASME III, CLASS 2 X 07-13-87 X4AQ10-4.lA, CONTAINMENT WALL REY. 6,
- 3. 8. 2. 1 PENETRATION SLEEVES 11-15-85 1779.00 04 FSAR ISOLATION VALVE ASME III, CLASS MC I 07-13-87 DC-1010-T1-P.ll ENCAPSULATION VESSEL , REV. 5,
- 3. 8. 2. 1. 4 AND BELIOWS 2-7-86 EXPANSION JOINTS 1781.00 04 FSAR DESIGN OF FLUED READ ASME III. NC-3000 X 07-13-87 X4A010-2.lc, OF PROCESS PIPING 1977 THRU StMER REY. 6
- 3. 8. 2. 4. 5 PENETRATION 1978 ADDENDA 11-15-85 ASSEMBLIES 1782.00 04 FSAR TESTING OF CLASS 2 NC-6000 OF ASME SEC. X X 07-13-87 X4AQlO-8.2, FUR PIPING ASSEMBLIES III REV. 6 CONSTRUCTION
- 3. 8. 2. 7 IURMING PRESS. BDR. 11-15-85 IMPIJNENTATIO WI111IN CONTAIPMENT N SEE 880.10 1786.00 04 FSAR PROCESS PIPE MAX. OITRATING 1TMP. X 07-13-87 I4AQ10. ATTACH.
PENETRATION RANGE 445 F TO 557 F 2 REV. 6,
- 3. 8. 2. 1. 5 ASSEMBLIES (HIGH 11-15-85 TEMP. PIPING) 1787.00 04 FSAR PROCESS PIPE DESIGNED 10 LIMIT X 07-13-87 X4AQ10-4.1.4.5, PENETRATION CONCRETE MAXIMtN REY. 6,
- 3. 8. 2. 1. 5 ASSEMBLIES (HICR TEMPERATURE to 200 11-15-85 TEMP. PIPING) DEGREES T O O O
j
'\
V Pate No. 17 11/10/87 PLANT V0GTLE UNIT 2 READINESS REVIEW PROGRAM IMPLEMENTATION MATRIX MODUIR 04
==-==============================_====
DESIGN CONST REF. SOURCE AND DOCUMENT DES COM CURRENT DESIGN C 4 RENT CONSTRtCTION NtPEER MODUIR SRCTION SUBJECT DoctNENT/FEATL'RE SECTION IGN ST. AS OF: IW LE N NTATION AS OF: IW LEMENTATION REMARKS
======= ====== =============== ========_e========== ==================== ============ = = === ======== =:.==.========== ======== =============== =============
1788.00 04 FSAR STRUCTL1tAL ASput III, X 07-13-87 %Q10-4.1.4.7A ACCEPTANCE CRITERIA SUBSECTIONS MC , REY. 6,
- 3. 8. 2. 5 IUR 51TEL ITEPG (CLASS 2 PIPING) AND 11-15-85, OTHER THAN LINER NE (CLASS MC X4AH04-2.0, PLATE AND SLEEVE COPMfhMTS) REY. 13, i ASSEMBLIES 10-14-86 1789.00 04 FSAR MATERIALS, O.C. & ASMI III CLASS 2 X 07-13-87 X4AQ10-5.1, SPECIAL CONSTRLCTION PIPING C0WLIES WITH REV. 6,
- 3. 8. 2. 6.A TECHNIQUES SUB. NC, ART. 11-15-85 NC-2000 1790.00 04 FSAR TESTING /ISI CIASS 2 CONTAllMENT X 07-13-87 DC-2101-4.1, STRUCTURAL INTEGRITT REY. 2, 8-16-83
- 3. 8. 2. 7 TEST USES 1.15 TIMES DESIGN PRESSURE 1832.00 04 IEB 80-08 EXAMINATION OF SLEEVE INM FLUED X 07-13-87 X4A010-4.lA &
PENETRATION SLEEVE HEAD WELD, AT VENDOR 6.6C, REY. 6 C-80/06/26 10 FLUED HEAD (OR SHOP, SUBJECT To 11-15-85, IP9EDIATE SLEEVE FOR 1008 RADIOGRAPHY X4AZ01-P3.9.3.1 FLUED HEADS EQUIPPED 1.A.W. NC-5200, & .A. REV. 19 WITH INTEIMtDIATE ACCEPTAPCR CRITERI A 6-16-87 SLEEVE) IAW NC-5320 i 1811.00 04 FSAR RESTRAINT OF LARGE PROPOGATION OF BREAK X 07-13-87 DC-1018-APP.D. GN LTR TO RCL BRANCH LINES 10 UNAFFEC11tD IDOPS REY. 2, NRC GN-1364,
- 3. 6. 2. 3. 2. PREVENTED 10-11-83 4-29-87 2.A 1842.00 04 FSAR RESTRAINT OF LARGE PRONGATION OF BREAR X 07-13-87 DC-1018- APP. D.
RCL BRANCH LINES IN AFFECTED IDOP REY. 2,
- 3. 6. 2. 3. 2. DOES NOT EXCEED 208 10-11-83 2.B OF FLOW AREA 0F RUPTURED LINE 1855.00 04 FSAR CONTROL OF FEPRITE RG 1.31 X 07-13-87 X4AZOI-Pl.7.5, CONTENT IN STAINLESS REY. 18,
- 1. 9. 31. 2 STEEL WELD METAL 5-11-87
Pnge No. 18 11/10/87 PLANT V0GTLE UNIT 2 READINESS REVIEW PROGRAM IMPLEMENTATION MATRIX MDDULE 04
========================= ============
DESIGN CONST REF. SOURCE AND DOC M NT DES CON CUFRENT DESIGN CURRENT CONSTRUCTION NtNBER MODULE SECTION SUBJECT DOCINENT/FRARTRE SECTION IGN ST. AS OF: IMPLEMENTATION AS OF: IMPIEMENTATION REMARKS
======= ====== =============== ==================== =================e=e ============ === = = ======== = ==== ======== ======= ============= = ====== ======
1989.00 04 FSAR STEEL CONTAINMENT, ASME III, ART. NE X 07-13-87 DC-1010-TI-P.12 ISOLATION VALVE 3000, 1974 THRU , REY. 5,
- 3. 8. 2. 4. 4 ENCAPSULATION VESSEL StPNER 1976 ADDENDA 2-7-86 ASSEMBLIES, DESIGN 2030.00 04 FSAR ESF CONSTRUCTION COMPONENTS IN X 07-13-87 DC-1204-4.0D, MATERIAIS CONTACT WITH BORATED REY. 2,
- 6. 1. 1. 1. 2 WATER ARE FABRICATED 02-11-83 0F, OR CLAD WITR, DC-1205-4.0A, AUSTENITIC STAINLESS REV. 2, STEEL OR EQUIVELANT 03-17-83 CORROSION RESISTANT DC-1206-4.0A, MATERIAL REV. 2, 04-28-83 DC-1208-3.3.C.
REV. 1, 03-09-83 2048.00 04 FSAR CONTAIPNENT DESIONED *IU REMAIN X 08-11-87 DC-1010-TI-P.19 ISOLATION SYSTEM, FUNCTIONAL IVLIDWIPRI , REY. 5,
- 6. 2. 4. 1. SAITTY DESIGN BASIS A SSE 2-7-86, l.R' DC-2415-3.1K.
REV. 1, 5-16-83 2055.00 04 FSAR CONTAI!NENT 10CFR50 APP.A. GDC X 07-13-87 DC-2415-1.0, ISOLATION SYSTEM, 54, PIPING SYSTEMS, REV. 1, 5-16-83
- 6. 2. 4. 3.D DESIGN EVALUATION PENETRATING CONTAlfMENT 2056.00 04 FSAR CONTAINMENT 10CFR50, AI'P. A., X 07-13-87 DC-2415-1.0, ISOLATION SYSTEM, CDC 56. PRIMART REV. 1, 5-16-83
- 6. 2. 4. 3.E DESIGN EVALUATION CONTAINMENT ISOLATION 2057.00 04 FSAR CONTAllMtNT 10CTR50, APP.A., GDC X 07-13-87 DC-2415-1.0, ISOLATION SYSTEM, 57 CIDSED SYSTEM REV. 1, 5-16-83
- 6. 2. 4. 3.F DESIGN EVALUATION ISOLATION VALVES O O O
Ptge No. 19 11/10/87 PLANT V0GTLE UNIT 2 READINESS REVIEW PROGRAM , IPG'lJIMENTATION MAlltIX MODULE 04
======================================
DESIGN CONST REF. SOURCE AND DOCtMENT DES CON CURRENT DESIGN CURRENT CONSTRUCTION Nt995R MODUIE SECTION SUBJECT DoctSEINT/ FEATURE SECTION IGN ST. AS OF: IPE'IJMINTATION AS OF: IWIJIPetNTATION RMMARES
======= ====== =============== ==================== =__________========= ============ === === ======== =============== ======== =============== =============
2059.00 04 FSAR CONTAIIDEINT ASMr II X 08-11-87 DC-10ll-4.0, SEE FSAR ISOLATION SYSTEM. REY. 1. 12-9-80 6.2.6
- 6. 2. 4. 4 TESTS AND INSPECTIONS 2063.00 04 FSAR CUPWUSTIBIE CAS CAPACITY IS SUCR X 07-13-P7 DC-1513-3.1.lE.
C0fr!ROL IN THAT CONTAINP9ffrr R2 SEC. 3.1.1.E.
- 6. 2. 5. 1. 00NTAll#EINT (XNIC. WILL NOT REY. O 6-3-83 1.D RIRC. RTDROGEN EXCERD 44 BASED ON RE00Pe!NERS NRC TID REIRASE MODEL AS INDICATED IN RG 1.7. -
2084.00 04 FSAR EPetRGENCY CORE ALL PARTS /C0ffutRNTS X 07-13-87 DC-120 H .0D. COOLING STSTEM IN CONTACT WITH REY. 2
- 6. 3. 2. 4.A MATERIAL SPECS & BORATED WA11tR ARE 2-11-83 COPW'ATIBILITY FABRICA11rD OF OR DC-1205-4.0A.
CLAD WITH AUSTENITIC REY. 2 STAINLESS STEEL OR 12-14-84 BOUI. CORROSION DC-1206-4.0A. RESISTANT MATERIAL REY. 2. 4-28-83 2170.00 04 FSAR ESF CONST. MATERIALS ASMt IX X X 07-13-87 X4A037-5.0A. 05-13-87 GNS III/I WELD MATERIAL REY. 14. 5-3-87 5-24-86
- 6. 1. 1. 1. 2 QUALIFICATION 2174.00 04 FSAR CCW SYS111M SAFETY 10CHl50. APP. A, GDC X 07-13-87 DC-1203-1.0 DESIGN BASES 45 REY. 6. 11-2-83
- 9. 2. 2. 1.
1.E 2175.00 04 FSAR CCW STS111M SAFETT 10Cf1t50. APP. A. 0D0 X 08-11-07 DC-1203-1.0 & DESIGN BASES 46 3.10. REY. 6,
- 9. 2. 2. 1. 11-2-83 1.E 2294.00 04 73AR MASS AND ENERGY ANSI N176 APP. E I 07-13-87 DC-1018-2.0, BIDMDONN RELEASE FOR MAIN REY. 2 CAlfULATION 3F. 4. 2. 3 STEAM LINE BREAR 10-11-83 l
1
.',,,.- __.~. , - - - - . ...m -- -
PeEe No. 20 11/10/87 PLANT V0GTLE UNIT 2 READINESS REVIEW PHOGRAM IMPLEMENTATION MATRIX FODULE 04
======================================
DESIGN CONST REF. SOtPCE AND DoctNENT DES CON CURRENT DESIGN CL'RRENT CONSTRtCTION NIMUER MODULE SECTION SUBJECT DOCtMENT/ FEATURE SECTION IGN ST. AS OF: IMPLEMENTATION AS OF: IMPLEMENTATION REPt4RKS
=====-= == === =============== ==================== ===~================ ============ === === ======== =============== ======== =========== === =============
2295.00 04 FSAR POSTUIATED BREAR IN PROPAGATION OF FLOOD X 07-13-87 DC-1003-3.2, 96-INCH CIRCULATING WATERS INM REV. 2, 3F. 4. 4 WATER PIPING 10 SAFETY-RELATED G-29-83, CONDENSERS IN STRUCTURES PRECLUDED DMcN-2, 7-10-85 TURBINE BLDG. BY DESIGN 2301.00 04 FSAR CONDENSATE AND SINGLE ACTIVE X 07-13-87 DC-1305-3.lB, FEEDWATER SYSTEM COMPONENT FAILURE OF REV. 4, 3-22-83
- 10. 4. 7. 3.C SAFETY EVALUATION SAFETY-RELATED OR NON-ESSENTIAL PORTION WILL NOT COMPROMISE THE SYSTEM'S SAFETY IUNCTION.
~ 2309.00 04 FSAR AFW SYSTEM SAf1TT AFW CAN BE OPERATED X 08-11-87 DC-1302-3.1.lG, DESIGN BASES. IPOM THE SHUTDOWN REY. 5, 4-18-83
- 10. 4. 9. 1. 1 PANELS AND THE AUXILIARY fYEDWATER PANEL 2310.00 04 FSAfl AfW SYSTEM CODES AND DESIGNED AND X P7-13-Ir1 DC-1302-3.1.1.W STANDARDS CONSTRUCTED IN , REY. 5,
- 10. 4. 9. 1. 3 ACCORDANCE WITH 4-18-83 SAFETT CLASS 3 TO CONTAIPNENT ISOLATION VALVES AND THE REMAINING SYSTEM IS SAFETT CLASS 2.
2311.00 04 FSAR AUX. FEEDWATER AfW MIN. Flow TO AT X 07-13-87 DC-1302-3.1.1.B SYSTEM GENERAL LEAST 2 S/G'S IS , REV. 5,
- 10. 4. 9. 2. I DESCRIPTION DELIVERED WITHIN 1 4-18-83 MIN. OF RECEIPT OF SIGNAL 2313.00 04 FSAR AUX. FEEDWATER EQUlfHENT OR X 08-11-87 DC-1017-3.3.5, SYSTEM SAFETY STRUCTURES WillCH ARE REY. 5,
- 10. 4. 9. 3 EVALUATION NOT SEISMIC CAGETURY 3-19-86, 1 AND WHOSE COLLAPSE DMCN-12 COULD RESULT IN LOSS 5-28-87 0F AfW IUNCTION ARE CHECKED TO DETEININE DC-1302-3.1.1.0 THEY WILL NOT , REY. 5 COLLAPSE UNDER SSE 4-18-83, OR ARE UfURADED TO DC-1005-3.58, SEISMIC CAT. I. REV. 1, 4-4-83, DMCN-9, 6-5-87 9 9
[ T Page Co. v/21 11/10/87 PLANT V0GTLE UNIT 2 READINESS REVIEN PROGRAM IMPLEMENTATION MATRIX a MODULE 04
=======_______________.__2============
DESIGN CXMST REF. SOURCE AND DOCLNENT DES COM CURRENT DESIGN CURRENT CONSTRUCTION NINBER MODULE SECTION SUBJECT DOCUMENT / FEATURE SECTION IGN ST. AS OF: IMPIRIENTATION AS OF: IMPLE N NTATION REMARES
======= ====== ======_______A_ ==================== ==================== ============ === === ======== =============== ======== =============== =============
2314.00 04 FsAR AUX. FEEDNATER NUREG-0737. II.E.1.1 X 07-13-87 DC-1302-2.2 RELIABILITY SYSTEM SAFETY & II.E.1.2 REY. 5, 4-18-83 ANALYSIS
- 10. 4. 9. 3 BVALUATION 2321.00 04 FSAR Afit SYS1EM NUREG-0611. APP. III X 07-13-87 DC-1302-2.2, NTHODOIDGT - & ANN 1 0F APP. X REY. 5, 4-18-83 IDA. 3. 1 RELIABILITY EVALUATION 2346.00 04 FSAR APPLICABLE CODES AND THE ENTIRE RRRS IS X 07-13-87 DC-1205-2.08.1 CLASSIFICATION DESIGNED AS NUCLEAR REV. 2,
- 5. 4. 7. 2. 5 SAf1TY CLASS 2 WITR 3-17-83 THE EXCEPTION OF THE DC-1010-TI-P.10 SUCTION ISOI.ATION , REY. 5, VALVES NHICH ARE 2-7-86 SAFETT CLASS I.
2386.00 04 FSAR ESF MATERIAL COPFATIBILITY WITH X 07-13-87 SEE REF. NO. SELECTION AND RCS & CONTAlleGINT 2030 FOR DESIGN
- 6. 1. 1. I FABRICATION SPRAT SOLUTIONS IWIREtNTATION 2397.00 04 FSAR CONTAllMElrf 000'i.ING DESIGNED AND X 07-13-87 DC-1501-3.lJ. SEE FSAR SYSTEM SAFETT ERSIGN FABRICATED 1U CODES REY. 5 TABLE 3.2.2-1
- 6. 2. 2. 1. 1. BASES CONSISTENT MITH RG 12-11-78 FOR QUALITT 1.0 1.26 S Me CLASS 2398.00 04 F3AR CONTAllMENT C00LIlm DESIGNED AND X 07-13-87 DC-1010-TI-P.60 SER 73AR SYSTEM SAFETT DESIGN FABRICATED TC CODES , REY. 5 TABIE 3.2.2-1
- 6. 2. 2. 1. 1. BASES CONSISTENT NITH RG 2-7-86 FOR SEISMIC 1.G 1.29 CATEGORY 2407.00 04 FSAR CIS SAITTY DESIGN DESIONED TU SEISMIC X 07-13-87 DC-2415-1.0, BASES CAT. I REY. 1, 6-16-83
- 6. 2. 4. 1.
1.F. 2 2408.00 04 FSAR CONTAIINENT ASPEI III, CLASS 2 X 07-13-87 DC-2415-1.0 ISOLATION SYSTEM, REY. 1, 5-16-83 6, 2. 4. 1. SAf1TY DESIGN BASIS 1.F. 3
Page No. 22 11/10/87 PLANT V0GTLE UNIT 2 READINESS REVIEW PROGRAM IMPLEMENTATION MATRIX MODULE 04
=============_========================
DESIGN CONST REF. SOURCE AND DoctNENT DES CON CURRENT DESIGN CURNENT CONSTRUCTION NtNDER MODULE SECTION SUBJECT DOCINENT/ FEATURE SECTION IGN ST. AS OF: IMPIJNENTATION AS OF: INLDtENTATION REMARKS
======= ====== =============== ==================== ==================== ============ === == ======== =============== ======== =============== =============
2409.00 04 FSAR CONTAINMENT TMI ACTION PLAN TASK R 07-13-87 DC-2415-2.0 ISOLATION SYSTEM II.E.4.2 REY. 1, 6-16-83
- 6. 2. 4 DESIGN 2422.00 04 F3AR SYSTEM GENERAL BTP CSB 6-4 X 07-13-87 DC-2415-1.0, TABLR 9.4.6-4 DESCRIPTION - REV. 1, 6, 2. 4. 2. 1 CONTAIPMENT PURGI 5-16-83, SYSTEM DC-1505-1.0, REV. 5, 7-26-83 DC-1506-1.0, REY. 5, 8-2-83 2432.00 04 FSAR CONTAIPNENT 10CFR50, APP. J X 07-13-87 DC-2415-3.lD, ISOLATION SYSTEM REY. 1,
- 6. 2. 4. 4 TESTS AND 5-16-83, SEC.
INSPECTIONS 2.0 2444.00 04 FSAN ELECTRIC RTDROGEN 2 RECupeINERS ARE X 07-13-FT DC-1513-3.3.1, RECOMBINER PROVIDED 10 MEET THE REY. O, 6-3-83
- 6. 2. 5. 2. I Im0UIREMENTS FVR REDUNDANCY AND INDEPENDENCE.
2450.00 04 FSAR DESIGN DATA FUR H2 ASME II I 07-13-87 DC-1513-2.0, RECCMBINER REV. O, 6-3-83
- 6. 2. 5-1 2455.00 04 FSAR DESIGN DATA FUR R2 IEEE 323 I 07-13-87 DC-1513-2.0, REC 0MBINER REY. O, 6-3-83
- 6. 2. 5-1 2456.00 04 F3AR DESIGN DATA FUR R2 IEEE 344 X 07-13-87 DC-1513-2.0, RECUMBINER REY. O, 6-3-83
- 6. 2. 5-1 2471.00 04 FSAR ANALYTICAL MODEL FOR BPF-1VP-4 (REY.1) I 07-13-87 DC-1018-3.4E, COTUTER CONTAllNENT REV. 2,10-11-83 PROGRAM FUR
- 6. 2. 1. 2. 3. SUB-CCMPAR1 MENT PRESSURE I ANALYSIS TRANSIENT ANALYSIS O O O
w . Pcge No. '23 11/10/87 PLANT V0GTLE UNIT 2 READINESS REVIEN IPCCRAM IW LEMENTATION MATRIX MODULE 04
==================================== =
DESIGN CONST REF. SOURCE AND DOCtMINT DES CON CURRENT DESIGN CURRENT CONSMUCTION NtMBER MODULE SECTION SUBJECT DOCINENT/ FEATURE SECTION IGN ST. AS OF: INLINENTATION AS OF: IMPLEMENTATION REMARKS
======= ====== =============== ==================== ==================== ============ === === ======== =============== ======== =============== =============
2479.00 04 FSAR CONTAINMENT SPRAY SIIGLE ACTIVE X 07-13-87 DC-1206-3.lc. SYSTEM SAFETY DESIGN FAILURE PLUS LOOP REY. 2. 4-28-83
- 6. 2. 2. 2. 1. BASES (INJECTION PHASE) 1.C AND SINGLE ACTIVE OR PASSIVE FAILURE PLUS IDOP (RECIRCULATION PHASE) CANNOT IW AIR SAFETY FUNCTION 2480.00 04 FSAR CONTAINMENT SPRAY ASME III CLASS 2 X 07-13-87 DC-1010-TI-P.ll FSAR TABLE SYSTEM CODE AND . REV 5. 2-7-86 3.2.2-1 (SM.
- 6. 2. 2. 2. 1. STANDARDS .6) 1.0 2481.00 04 F3AR CONTAIfMENT SPRAY ASPE III CLASS 3 X 08-11-87 DC-1010-TI-P.ll FSAR TABLE ,
SYSTEM CODE AND , REV. 5 3.2.2-1 (SH. ;
- 6. 2. 2. 2. 1. STANDARDS 2-7-86 6) i 1.G 2482.00 04 FSAR CONTAINMENT SPRAY ASME III. CLASS MC X 07-13-87 DC-1010-TI-P.12 FSAR 3.2.2-1 SYSTEM CODE AND . REV. 5 (SH.6)
- 6. 2. 2. 2. 1. STANDARDS 2-7-86 1.0 2483.00 04 FSAR CONTAINPENT SPRAY MEMA-MGl X 07-13-87 DC-1010-TI-P.ll FSAR TABLE SYSTEM CODE AND . REY. 5 3.2.2-1 (SM. !
- 6. 2. 2. 2. 1. STANDARDS 2-7-86 6) I 1.0 l 2484.00 04 FSAR ALIDNED TIPE IUR 20 MINUTES X 07-13-87 DC-1206-3.30 OPERATUR 10 INITIAM REY. 2. 4-28-83 !
- 6. 2. 2. 2. 2. MANUAL SMITCHOVER 10 l 2 RECIRCULATION UTM RECEIPT OF A IDN LEVEL ALAIM IN RWST ;
2485.00 04 FSAR CONTAIMPENT SIMP MINIMtM pH OF 8.5 I 07-13-87 DC-1206-3.1H. + FLUID pH AT END OF REY. 2. 4-28-83
- 6. 2. 2. 2. 2. IPURCTION PHASE 2
1 -.- . . ~ , -- - . --- - , , - .- .. -, - - ., . . + - - - . .-.- .-. ~ . . - . . . .. ,
Page No. 24 11/10/87 PLANT V0GTLE UNIT 2 READINESS REVIEW PROGRAM IMPIR4ENTAT10N MATRIX MODULE 04
===============_======================
DESIGN CONST REF. SOURCE AND DoctP8ENT DES COM CURRENT DESIGN CURRENT Cuiuimm. TION NLPEER PODULE SECTION SISJECT DOCINENT/f1ATURE SECTION IGN ST. AS OF: IMPIEMENTATION AS OF: IMPLIMENTATION REMARKS
======= ====== ============== ===================_ _________=========== ============ === === ======== =============== ======== =============== =============
2486.00 04 FSAR MATERIAL THAT CAN AUSTENITIC S.S. X 07-13-87 DC-1206-4.0A, COME IN CONTACT WITH REV. 2, 4-2^-83
- 6. 2. 2. 2. 2. RECIRCULATION FLUID
- 3. 6 2503.00 04 FSAR ECCS MANUAL VALVES NO SINGLE VALVE CAN I 07-14-87 DC-1204-4.0C, ISOLATE BOTH TRAINS REY. 2, 2-11-83
- 6. 3. 2. 2.17 0F ECCS EQUlfNENT 2512.00 04 FSAR NPSR AVAILABLE 10 RG 1.1 X 07-14-87 DC-1206-3.lF, CONTAI!NENT SPRAT REY. 2, 4-28-83
- 6. 2. 2. 2. 2. PtNPS -
- 3. 2 1
2515.00 04 f3AR DESIGN OF THE HG 1.82 I 07-13-87 DC-1204-3.lJ. CONTAIPNENT REY. 2, 2-11-83
- 6. 2. 2. 2. 2. EMENGENCT CORE 3.6 COOLING SYSTEM SUMPS 2319.00 04 FSAR LOCATION OF THE ABOYE MARIM'JM I 07-14-87 DC-1003-3.2.0, ACTUATORS FOR ANTICIPATED REY. 2,
- 6. 2. 4. 2. 1 CONTAIPNENT CONTAlfNENT WATER 6-29-83, ISOLATION VALVES LEVEL INCN-2, 07-10-85 2808.00 04 FSAR FLUED READS - ASME III, DIV. 1 K 07-13-(FI I4A010-4. l A, FRACTURE TOUGINESS SUBSECTION NC, 1977 REV. 6,
- 6. 2. 7, 2.D TESTS THRU StPNER 1978 11-15-85 ADDENDA.
2809.00 04 FSAR PRESSURE BOUNDART ASME III DIV. 1 X 07-13-87 X4A001-6.2.1, MSIV, MFIV PIPING - MAIN S11AM SUBSECTION NC, 1974 REV. 16 DESIGNED PER
- 6. 2. 7. 2.8 AND FEEDWATER TRRU SIPNER 1975 7-20-84 1974 ED. THRU SYSTEMS - FRACTURE ADDENDA. StPNER I!F15 TULUBNESS TESTED ADDENDA W/0 FRACTURE 100GRNESS TESTS O O O
Py e No. 25 11/10/R7 PLANT V0GTLE UNIT 2 READINESS REVIEW PROGRAM IMPL'l MENTATION MATRIX MODUIE 04
=============================_========
DESIGN CONST REF. SOtSCE AMR DOCIMENT DES COM CURRENT DESIGN CURRENT CONSTRtCTION NUMBER MODULE SECTION SUBJECT DOCtNEtrf/ FEATURE SECTION IGN ST. AS OF: ITLDENTATION AS OF: IWLENENTATION REMARKS
======= ====== =============== ==================== ==================== ============ === === ======== =============== ======== =============== =============
2810.00 04 FSAR E11ACTURE MUGRNESS ASME III, DIV. 1 X 07-13-M X5AC01-8.0D, VALVES WIMIN TEST FOR PRESSURE SUBSECTION NC, REV. 10 NSSS NEED NOT
- 6. 2. 7. 2.F BOUNDARY MA R RIAL OF SUB-ARTICLE NC-2300, 7-17-84 BE FRACTURE MAIN STEAM AND 1977 EDITION. 1000RNESS FEEDWATER ISOLATION RSTED SINCE VALVES MATERIAL USED IS BITRER AUSTENITIC S.S. OR C.S.
I 2811.00 04 FSAR SAFETT EVALUATION - MINIMtM REQUIREPENTS X 07-13-M X5AC01-8.OD, DID NOT CONTA110EfrT OF ASPE III, 74 REY 10 REQUIRE
- 6. 2. 7. 4 ISOLATION BOUNDARY EDITION TRRU StrtER 7-17-84 IMPACT PIPING AND BOP 75 ADDENDA. ESTING CONTAI!9ENT ISOLATION BOUNDART VALVES 2812.00 04 FSAR ftEMAINING ASPE III,1974 TRRU X 07-13-87 X4A036-5.0A, CONTAI!NENT PRESSURE StPMER 1975 ADDENDA. REV. 10,
- 6. 2. 7. 2.R BOUNDARY PIPING 4-21-86 DESIGNED WIDOUT FRACTURE TUUGHNESS .
TESTING 2813.00 04 FSAR CONTAIIGENT PRESSURE ASME III, Dif.1, X 07-13-87 X5AC01-8.OD, BOUNDART VALVES SUBSBCTION NC, 1974 REV. 10,
- 6. 2. 7. 2.F OTHER TRAN MAIN NRU St99ER 1975 7-17-84 STRAM AND FREDWATER ADDENDA.
ARE PROCURED WI1110UT FRACTURE 1000HNESS TESTING 2816.00 04 FSAR REFUELING WATER DESIGNED 10 SEISMIC I 07-13-87 DC-2129-1.0 f, 510 RAGE TANK CA1EGORT I 3.18, REV. 4 .
- 6. 3. 2. 2. 9 REQUIREMEfrIS. B-9-83 l REATER PROVIDED 10 [
MAINTAIN MIN. WATER TEPf'. OF SO DEGREES F.
1 1
,, I 1
ll ll ll l 9'
= ll I !!
E ll 8 -k,l,l V .. ll El o !! 8 5 G ll Ei E ll . .B B B E 4 C: 8 8. 26 da dA JA JA J =. g ll 4 4 aA aA aa a6 a5 a a 55 kd Ed k# kd 74t74074 TJ kd TJ 84 T4 84
~s E #E k#
$48 W E: Ts?
g"l o I l! BEA8EA82 BE 8E 85 $E REA Eda EEE 5 g ll B E E E E B B g g' E
!! hltb!!Q llhB ll Et ll e . .,
h B h B h B h B h 8 h 8
;- ll 8 t; ll E E !! 12 G ll mg :: o - i. = = = = = = w h 3 ll ll ~E : ll E V E ll V ll E W 8 ll ! !l " t x ll g ll 25 ll m ll E g ll a e
y l; ll 5-- a c; ll t 3 c"E E C h, ll l< !lll ll 0 $ ~ t EE E ll lll 3 k $ 5E" g E "g ;ll5 H ll 2 ll 3 ll g38e$ "*? 64 - g auggsE E
" " ll ggSQ
= E 4 0 a m " < i2 " E ll ~g=p- - a : E52ats ll a
N
< $~- o t.
5 l
- 8 E t.~3555 5 a.
ll 5 gg ll
-l l
, 3 - m c
a ml 2
.. e et
=
ll
' o oc o
- ll
-l a
5 5" 5" nu B" er bl o E e llll g cm r' gg E
.m >e .c GE GE an
-- 8l~E 5 gu i ii $50 E E$ $$ E$ $hES 55 ll A
- 4
- = = =
$ s s 65 ll ll . d d '6 6 ".:
FQm :lll 5
$ E d
" 5 E S
. 5 . 5 E 2 2 2 2 : E D
. 5 . 5 . 5 E de
= $ ll E ll fl 3 8 8 8 3 8 E IE e 5 ". 8 8 8 8 8 8 8 05 m- "! !!. . i
~
i
~
i
~
i
~
i
~
i m i e
( Pcge No. O 27 I 11/10/87 I PLANT V0GTLE UNIT 2 READINESS REVIEN PROGRAM l IMPLDENTATION MATRIX l ' MODULE 04
======================================
i DESIGN CONST l REF. SOURCE AND DoctMENT DES CON CURRENT DESIGN CURRENT CONSTRUCTION MINBER MODULE SECTION SUBJECT DoctMENT/ FEATURE SECTION IGN ST. AS OF: IW LEMENTATION AS OF: IMPLFNENTATION REMARKS ! l ======= ====== =============== ==================== ==================== ============ === === ======== =============== ======== =============== ============= 3525.00 04 FSAR NSCW SYSTEM SAFETY TRE NSCW SYSTEM X 07-13-87 D0-1202-3.1E. DESIGN BASES. DESIGNED 10 MBET REY. 5. 4-19-83
- 9. 2. 1. 1. SEISMIC CAT. I l.C REQUIRDENTS 3539.00 04 FSAR CCW SYSTEM SAITTY TRE SAFETT RELA 1TD I 07-13-87 DC-1203-3.lF.
EVALUATION PORTION DESIGNED AND REY. 6. 11-2-83
- 9. 2. 2. 3.C CONSTRUC1TD AS SEISMIC CATEGORT I 3541.00 04 FSAR ULTIMATE REAT SINK FAN MOTURS PONERED X 07-13-87 DC-1202-A-3.18 (URS) COMFT) MENT BT CLASS lE FONER RdV. 5. 4-19-83
- 9. 2. 5. 2. 2 DESCRIPTION SUf7LT.
3542.00 04 FSAR ULTIMATE REAT SINK SINGLE FAILURE PLUS X 07-13-87 DC-1202-A-3.lc. MS COOLING (URS) SAFETT DESIGN L.0.0.P. WILL NOT REY. 5. 4-19-83 1DNERS
- 9. 2. 5. 1. BASES IMPAIR SYSTEM 1.A CAPABILITY 3543.00 04 FSAR CONDENSATE S10 RAGE SINGLE FAILURE PLUS X 07-13-87 DC-1302-3.1.lA. CONDENSATE FACILITT L.0.0.P. WILL NOT REY. 5. 4-18-83 510 RAGE TANK
- 9. 2. 6. 1. IM ATR SYSTEM 1.A 3544.00 04 FSAR SAFETT EVALUATION - CST'S AND ASSOCIATED X 07-13-87 DC-1302-3.1.ll.
CONDENSATE STORAGE SAFETY-RELATED REV. 5
- 9. 2. 6. 4.C TANKS (CST'S) PIPING AND VALVES 4-18-83 ARE DESIGNED AS DMCN-8. 2-3-86 SEISMIC CATEGORY l DC-1010-TI-P.34
. REY. 5 2-7-86 3549.00 04 FSAR It)ST ACCIDENT E3SENTIAL RNtTkONS X 07-13-87 DC-1212-3.15 ftNITIONS SAW LING SYSTEM DESIGNED FOR SEISMIC 3.1.D. REV. 2 WITRIN
- 9. 3. 2. 2. 5 CATEGORY l 5-16-83 CONTAlf9ENT DC-1010-TI-P.47 AND INCLUDING
. REY. 5 TRE OUTER 2-7-86 CONTAIIDENT ISOLATION VALVES i
i t__--__. . _ - - - _ - - - _ . __ . _ _ _ _ - _ - _ - - - - ___
PCse No. 20 11/10/87 PLANT VOGTLE LMIT 2 READINESS REVIEW f%0 GRAM IMPLEMENTATION MATRIX MODULE 04
====- ====== =========================
DESIGN CONST RE F. S0tHCR AND DOCUMENT DES CON CURRENT DESIGN CURRENT CONSTRUCTION NtNBER PODULE SECTION SUBJECT DoctNENT/ FEATURE SECTION IGN ST. AS OF: IMPLEMENTATION AS OF: IMPLEMENTATION REMARKS
======= ====== =============== ==================== ==================== ============ === === =-====== =============== ======== =============== =====e=======
3555.00 04 FSAR SAITTY EVALUATION SINGLE FAILURE OF 1 X 07-13-87 DC-1208-3.lG. REACTIVITY CONTROL - 0F 2 FIDfPATHS DOES REY. 1. 3-9-83
- 9. 3. 4. 1. 3. BORATION FIOfPATHS NOT RESULT IN I INABILITT M BORATE RCS.
3575.00 04. F3AR TEST AND INSPECTIONS ITESSLHIZED PORTIONS X 05-13-8T XI-I 6-15-86 DURING CONSTRUCTION RTUR0 STATICALLY
- 9. 3. 3. 4.A WAS11 COLLECTION TES1TD AT 1 1/2 SYSTEM. TIMES DESIGN PRESSURE 3721.00 04 FSAR SPENT FTJEL SMRAGE ALL INTERVENING I 07-13-8T 0C-1213-3.11 FACILITY DESCRIPTION PIPING DESIGNED M REV. 2. 5-31-83
- 9. 1. 2. 2 SEISMIC CAT. I REQUIREMENTS 3723.00 at FSAR SFPCPS DESIGN BASIS SYSTEM PIPING X 07-13-87 DC-1213-3.lG.
ARRANGED SO TRAT REV. 2, 5-31-83
- 9. 1. 3. 1.B FAILURE OF ANT PIPELINE CANNOT DRAIN SFP BRIDt WATER LEVEL REQUIREMENT FOR RADIATION SHIELDING 3749.00 04 FSAR NSCW SYSTEM SAITTY DESIGNED 10 PERF0fM X 07-13-87 DC-1202-3.lA, DESIGN BASIS ITS COOLING FUNCTION REV. 5, 4-19-83
- 9. 2. 1. 1. IVListING LOCA 1.0 AU10MATICALLY, ASSINING SINGIE FAILURE COINCIDENT WITH A L.O.O.P.
3750.00 04 FSAR NSCW SYSTEM SAITTY DESIGNED SUCH THAT I 07-13-87 DC-1202-3.lH. M PRECLUDE DESIGN BASIS SYSTEM PRESSURE IS REV. 5, 4-19-83 LEAKAGE M
- 9. 2. 1. 1. GREA1TR THAN ENVIROPMENT 1.1 CONTAI!9ENT BUILDING MAXIMtM DESIGN PRESSURE O O O
v Page No. 29 11/10/87 PLANT V0GTLE UNIT 2 READINESS REVIEW PROGRAM IWLEPENTATION MATRIX
=
MODU 12 04
========_ =======_====================
DESIGN CONST REF. SOURCE AND DOCtMINT DES CON CURRENT DESIGN CURRENT CONSTRtCTION NtfeER 90DUI2 SECTION SUBJECT DoctMINT/FTATURE SECTION IGN ST. AS OF: ITLRPENTATION AS OF: IPG'LEPENTATION REMARK 5
======= ====== =============== ==================== =________2========== ============ === === ======== ====.... ______ ======== =============== =============
3752.00 04 FSAR CCWS - SAFTTY DESIGN DESIONED 10 REMAIN X 07-13-87 DC-1203-3.lF. BASIS FUNCTIONAL DURING MV. 6, 11-2-83
- 9. 2. 2. 1. AND AFTER SSE 1.0 3753.00 04 FSAR CCWS - PONER DESIONED WITH IONER X 07-13-87 DC-1203-3.lA.
GRWERATION DESIGN PRES 5URE TRAN NBCW REV. 6, 11-2-83
- 9. 2. 2. I. -BASIS SYSTEM 10 PREVENT 2.B fUFENTIAL RADIATION IRAKAGE INIU NBCW ST5 TEM.
1 s 3755.00 04 F5AR ULTIMATE MAT SINK - DESIGNED 501 RAT I 07-13-87 DC-1202-A-3.1C, SAFETT DESIGN BASES SIMOLE FAILURE WITH REV. 6 19-83
- 9. 2. 5. 1. L.O.O.P. DOE 5 NOT 1.A RESULT IN INADBQUATE CORE COOLING OR PRVEWF A SAFE SRUTDONN.
3750.00 04 F5AR CONDENSATE STORAGE FAILURE OF NON-CAT. X 07-13-lF1 0C-2130-4.1, FACILITY - SAFETY I LINES ATTAC MD TO MV 3, 7-27-83
- 9. 2. 6. 1. DESIGN DASE5 CST'S CANNUT CAUSE I.C 1055 OF RESERVE CAPACITY REQUIRED FOR SAFE SRUFDONN.
3759.00 04 FSAR CODE 5/ STANDARDS STORAGE TAMES & X 07-13-87 DC-1010-T.1-P.9 SAFETT- MLATED 9. REY. 5,
- 9. 2. 6. 1. 3 PIPING DESIGNED AND 2-7-86, (XNESTRUCTED AS DC-1302-1.0 &
SEISMIC CAT. I. 3.1.11, M V. 5, 4-18-83 DC-2130-3.4.3, REY. 3, 7-27-83 3760.00 04 FSAR MACTOR MAKEUP WATER PORTION 5 OF IMNs X 07-13-87 DC-1228-3.lA. FACILITY 5AFTTY REQUIMD 10 SERVE A5 REY. O, 5-5-80
- 9. 2. 7. 3 EVALUATION BACRUP MAKEUP WATER SOURCE FOR SPENT FUEL PUOL IS DESIGNED / BUILT'TO CAT. I REQUIREMENTS.
4
Ptge No. 30 11/10/67 PLANT V0GTLE tmIT 2 READINESS REVIEN IPOGRAM IMPLEMENTATION MATRIX l ' l PODULE 04
======.============================;==
DESIGN CONST SOURCE AND DOCINENT DES COM CURRENT DESIGN CURRENT CONSTRUCTION REF. NUMBER MODULE SECTION SUBJECT DoctNENT/ FEATURE SECTION IGN ST. AS OF: IMPLEMENTATION AS OF: IMPLEMENTATION REMARKS
====-== ====== =============== ==================== =====-============== ============ === === ======== =============== ======== =============== =============
3834.00 04 FSAR NASTE COLLECTION NON-PRESSURIZED X 05-13-87 XI-I 6-15-fl6 SYSTEMS - TESTS AND IVRTIONS
- 9. 3. 3. 4.A INSPECTIONS DURING HYDR 0 STATICALLY CONSTRUCTION TESTED (IMDER AIMOSPRERIC PRESSURE)
X 09-09-87 FOR DESIGN GENERIC ISSUE 4169.00 04 NRC QUESTION SilU1VONN DECAY REAT NUREG 0737. ITEM CORRES. REMOVAL REQUIREMENTS II.E.1.1 AND IMPLEMENTATION (A-45) 0F SEE RET 2314 NUREG 0636 0730.01 (A-45) II.E.1.2 4191.00 04 NRC QUEST. INTERNALLY GENERATED 10CFR50 APP.A GDC 4 X 07-13-87 DC-1006-1.0, CORRES. MISSILE SotmCE BY REV. 2, 7-13-83 0110. 05 NON-SAFETY-RELATED SYSTEM OR COMFVNENT. 4195.00 04 NRC QUEST. SEISMIC INDUCED SEISMIC 2-OVER-1 X 09-11-87 DC-1005-3.5B. CORRES. FAILURE OF SEISMIC ANALYSIS REV. 1, 4-4-83, 0410. 06 CAT. 2 COMIVNENT INCN-9, 6-5-ETT (NILL NOT RESULT IN FAILURE OF ESSENTI AL EQUIINENT) 4197.00 04 NRC QUEST. TwoDIPM ANALYSIS BTP PEB 3-1 PARA. X 08- 11-87 DC-1003-1.0, CORRES. B.2.C(2) 3.2C, & 3.20, 0410. 17 REY. 2, 6-29-83 AUXILIARY FEED NATER RG 1.139, POS. C.6 I 08-11-87 DC-1302-1.0A, 4202.00 04 NRC QUEST. CORRES. SYSTEM: CST REY. 5, 4-19-83 0110. 39 CAPACITY DC-2130-3.lA. REV. 3, 7-27-83 DPCN-1, 7-10-85 4203.00 04 NRC QUEST. AUXILIART FEED NATER BTP RSB 5-1. PARA. G X 08-11-87 DC-1302-1.0A, SYSTEM: CST REY. 5, CORRES. 4-18-83, 0110. 39 CAPACITY DC-2130-3.lA, REY. 3, 7-27-83, DMCN-1, 7-10-85 I O O O
Page No. O al 11/10/87 PLANT YOGTLE t! NIT 2 READINESS REVIEW PROGRAM IMPLEMENTATION MATRIX MODUIJC 04
======================22 ____22_:====
DESIGN CONST REF. SOURCE AND DoctMENT DES COM CURRENT DESIGN CURRENT CONSTRUCTION NUMBER MODULE SECTION SUBJECT DOCINENT/ FEATURE SECTION IGN ST. AS OF: DE'LEPENTATION AS OF: IMPLEPEINTATION REMARES
======= ====== =============== ====_________=====-= ==================== =_========== === === ======_= =============== ======== =============== =============
4219.00 04 NRC QUEST. TUBE AND SHELL SIDE ASME III. CLASS 2 X 07-13-87 DC-1010-TI-P13, CORRES. (ACCW) OF SEAL WATER AND 3 RESPECTIVELY REY. 5, 2-7-86 0210. 09 REAT EXCHANGER OF CVC SYSTEM 4220.00 04 NRC QUEST. CENTRIFUGAL CEARGING ASME III, CLASS 3 I 07-13-87 DC-1010-TI-P.17 CORRES. PtMP LUBE OIL , REV. 5 0210. 10 COOLERS: 2-7-86 CONSTRUCTION REQUIREMEN11i I 4221.00 04 NRC QUESTION NSCW SYSTEM COOLING ASMP SECTION III, X 08-ll-ErF DC-1010-TI-P.19 RESPONSE 10 CORRES. WATER SUPPLY AND CLASS 3 OUALITT . REY. 5, QUESTION 0210.11 RETURN PIPING FOR GROUP C 2-7-86 PtDW' MOTOR COOLERS DC-1202-3.15 REY. 5, 4-19-83 4223.00 04 NRC QUEST. AUXILIART FERD WATER ASME III, CLASS 3 X 07-13-87 DC-1010-T1-P.34 0210.12 CORRES. TURBINE LUBE OIL . REY. 5 COPETNIENTS 0210. 13 COOLERS 2-7-86 LISTED IN A.B.C, RESIMSE 10 00ESTION 4226.00 04 NRC QUEST. BTDROGEN RECOPSINERS ASME III, CLASS 2 X 07-13-87 DC-1010-TI-P.64 0210.12 CORRES. . REV. 5 COPfMENTS 0210. 17 2-7-86 LISTED IN A.B.C. REsfW SE TO QUESTION 4230.00 04 NRC QUEST. CRITERIA FOR FICOD SINGLE ACTIVE X 07-13-87 DC-1003-3.2D, CORRES. ANALYSIS FAILURE COINCIDENT REV. 2 0110. 13 WITN POSTULATED 6-29-83, PIPINO FAILURE DC-1009-3.3D, EXCEPT PUR DUAL REV. 2, 6-3-83 PURPOSE MDDERATE ENENGT SYS111M g
Page Co. 32 11/10/87 PLANT V0GTLE UNIT 2 READINESS REVIEW ITOGRAM IMPLEMENTATION MATRIX PODULE 04
======================================
DESIGN CONST REF. 50tmCE AND DOCtHENT DES COM CURRENT DESIGN CURRENT CONSTRUCTION NtNBER PODULE SECTION SUBJECT DoctHENT/ FEATURE SECTION IGN ST. AS OF: IMPLEMENTATION AS OF: IMPLEMENTATION RDtARKS
======= ====== =============== ==================== ==================== ============ === === ======== =============== ======== =============== =============
4262.00 04 NHC QUEST. BTP RSB 5-1 A1MOSITERIC DINP I 07-13-87 DC-1010-TI-P.32 CORRES. REQUIREMENTS FOR VALVES DESIGNED M , REY. 5, 0140. 26 STRAM GENERAMR SAFETY-CRADE 2-7-86 ATNOWPIIERIC DUMP STANDARDS VALVES 4370.00 04 FSAR DAMPING VALUES FVR PERCENT OF CRITICAL I 07-13-87 DC-1005-3.6.2, FIXED BASE DAMPING PER MODE REY. 1, 4-4-83,
- 3. 7.B. 1-1 Su<wiunu AND DMCM-4, CCMF%$ENTS 08-23-85 4506.00 04 GENERIC LETTER ADDITIONAL IN M. ON ASMB III, SUBARTICLE I 07-13-87 X4AQ34. PAGE 2 IEB 83-06 CORR. NON-CONFU MING NX-2000 REY. II, C-85/01/14 MATERIALS SUPPLIED 1977 EDITION 6-27-85 BY TUBk LINE CORP. -
1MO INCII AND SMALLER FITTINGS 4507.00 04 GENERIC LETTTR ADDITIONAL INID. ON ASME III, SUBARTICIR R 07-13-87 I4AQ34 PAGE 2 IEB 83-06 CORR. NON-CONIUMING NA 3767.4 REY. 11 C-85/01/14 MATERIALS SUPPLIED 1777 EDITION 6-27-85 BY TUBE LINE CORP. - TWO INCR AND SMALLER FITTINGS 4516.00 04 FSAR AIWS - DESIGN BASES NO SINGLE FAILURE X 07-13-87 DC-1302-3.1.2.1 i SRALL PREVENT TRIS , REV. 5,
- 7. 3. 7. 1. 2 SYSTEM IROM 4-18-83 OPERATING 4523.00 04 FSAR AFS TER SYSTEM MUST X 07-13-87 DC-1302-3.1.1.B DESIGN BASES PROVIDE FULL , REY. 5,
- 7. 3. 7. 1. 2 AUXILIARY FREDWATER 4-18-83 FLON WITHIN 1 MINVTE.
4526.00 04 FSAR AFS 10CFR50, APPA, GDC I 07-13-87 DC-1302-1.0, ANALYSIS OF 34 REV. 5, 4-18-83
- 7. 3. 7. 2.A. COMPLIANCE 3
O O O
s - Pz o No. 33 11/10/87 PLANT V0GTLE UNIT 2 READINESS REVIEW PROGRAM IMPLEMENTATION MATRIX MODULE 04
======================= . ____.__===-=
DESIGN CONST REF. SOURCE AND DOCtMENT DES COM CURRENT DESIGN CURRENT CONSTRUCTION NtMBER MODULE SECTION SUBJECT DOCtNENT/ FEATURE SECTION IGN ST. AS OF: IMPLEMENTATION AS OF: IWLEMNTATION REMARES
======= ====== =============== ==================== ==================== ============ === === ======== =============== ======== =============== =============
4673.00 04 IEB 79-28 POSSIBLE MALITNCTION REPAIR VALVES WITH 189-79-28 X 07-13-87 FILE X7BC24 ALL VALVES OF NAMCO MDDEL EA180 NAMCO BA 180 80-10254 REPAINED PER C-80/08/05 LIMIT SWI1tRES FOSITION SWITCHES 7-7-80 BG-10254 SELEVAT1tD WITH SWITUR NOUSING 7-7-80 TEWERATURES 8'S BE1 WEEN 01-79 (SAFTTT-RELATED AND 09-79. PIACING EQUIIVENT) VALVES ON HOID UNTIL REPAIR IS CO W LETE. 4674.00 04 IEB 80-05 VACUUM CONDITION IDW PRESSURE OR X 07-13-87 DC-1203-4.0, Gft RESPONSE RESULTING IN - AMAGE BOIDUP TANES THAT REY. 6 TO NRC DATED C-00/08/05 10 PROCESS OR ROLDUP CAN CONTAIN 11-2-83 8-5-80. IRB TANES. RADI0 ACTIVE MATERIAL DC-1217-4.0 80-05 ARE DESIGNED WITH REY. 1. 3-9-83 FEATURES TO PRECLUDE DMCN-2 VACUtM CONDITIONS 8-30-83 DC-1901-4.0.E. REV. 1, 5-4-83 DC-1208-4.0, REV. 1. 3-9-83 - DMCN-4. 11-4-86 i 4675.00 04 IRB 83-06 NONCONFUfMING INV0ER SUBARTICLE I 07-13-87 X4A034-PAGE 2 MATERIALS SUPPLIED NX-2600. A5M III REY. 11 C-83/ll/23 BY TUBE-LINE CORP. 17I7 WHICH EXE W TS G-27-85 2-INCE & SMALLER FITTINGS FROM NA-3700/NCA-3800 EXCEPT 79R REQUIRDENTS OF MA-3767.4 4679.00 04 IRB 79-24 FROZEN LINES ALL SAFETT-RELATED 158-79-24 X 07-13-87 DC-100049-4.7 PROCESS INSTR. & REY. 2., C-79/11/01 SAWLING LINES THAT 4-12-78 ARE PETSICALLY DC-1817-3.3A. ROUTED IN AN AREA REY. 4 EXPOSED 10 EXTREPELT 6-11-84 Cold WEA11IER SRALL DMCN-1817-1 88 PROVIDED WITH 10-12-84 ADEQUATE REAT TRACING
- u. . - _ - - - , _ _ ~ -. . . , ,
Page No. 34 11/10/87 PLANT V0GTLE UNIT 2 READINESS REVIEW FROGRAM IMPLEMENTATION MATRIX MODUIJE 04
==_________ _==~.===========-==========
DESIGN CONST REF. SOURCE AND DOCUMENT DES CON CURRENT DESIGN CURRENT CONSTRUCTION NtNBER MODULE SECTION SUBJECT DoctNENT/FEAWRE SECTION IGN ST. AS OF: IMPLEMENTATION AS OF: INPLEMENTATION REMARKS
======= ====== =========_===== ===================_ ==================== =-======_=== === === ======== =============== ======== =============== =============
4681.00 04 FSAR CA REQUIREMENTS MR ANSI N45.2.1-1973 I 07-13-87 I4AZ01-Pl.ll.0. CLEANING OF FLUID A. REY. 18,
- 1. 9. 37. 2 SYSTDtS AND 5-11-87 ASSOCIATED I44001-12.1, CDSVNENTS REV. 16, 07-20-84 4777.00 04 FSAR ULTIMATE HEAT SINE BTP RSB 5-1 A.4 I 07-13-87 DC-1202-A-3.lc, SYSTDI PERNRMANCE REV. 5, 4-19-83 S. 2. 5. 2. 4 4892.00 04 IRB 79-03A SA-312 OR A-312 TYPE DESIGN S NESSES IN I 08-11-87 BWPC LTR M 300 SERIES FUSION SAFETT-RELATED GPC, BG-9960, C-81/04/02 WELDED PIPE COMfVMENTS LIMITED DTD 6-3-80, M 85% MAX. WSWN3 LTR M ALLOWABLE STRESS AT BWPC, GF4731 DRSIGN TEMPERATURE DTD 4-2-81 4901.00 04 NRC QUEST. FEEDWATER SYSTEM BTP ASB 10-2 I 07-13-87 DC-1305-3.lG, GENERIC ISSUE CORRES. DESIGN AGAINST WATER REV. 4, 3-22-83 (A-1) 0F 0730. 01 RAPNER ( A-1) NUREG 0606 4912.00 04 FSAR NSCW SYSTEM SAFETT NSCW DESIGNED M I 08-11-87 DC-1202-3.1P, DESIGN BASES PREVENT BOILING IN REV. 5,
- 9. 2. 1. 1. CONTAINMENT COOLERS 4-19-83, l.R DURING IOCA DPEN-3, 5-15-85 CONDITIONS 4913.00 04 FSAR NSCW SYSTDf DESIGN MAXIMtM TUTU, NsCW X 08-11-87 I4Cl202V18, HEAT LOAD DURING REY. 1, 1-4-84
- 9. 2. 1-1 ACCIDENT CONDITIONS IS 349.8 MILLION BTU / HOUR 4914.00 04 FSAR NSCW SYSTEM DESIGN MINIMtM NSCW Flow I 07-13-87 DC-1202-3.lG, PER TRAIN REQUIRED REY. 5,
- 9. 2. 1-1 FUR ACCIDENT 4-19-83, CONDITIONS 15 15,733 UNCN-3, GItt 5-15-85, 14Cl202V03, REV. 1, 4-1-85 O O O
Pese No. 35 11/10/87 PLANT 70GTLE tMIT 2 READINESS REVIEW PROGRAM IMPLEMENTATION MATRIX MODULE 04
===e===========================_======
DESIGN CONST REF. SOURCE AND DOL, W NT DES CON CURRENT DESIGN CURRENT CONSTRUCTION MINRER PODULR SECTION SUBJECT DOClMINT/ FEATURE SECTION IGN ST. AS OF: IN'LEMINTATION AS OF: IMPIRMENTATION REMARKS
======= ====== =============== ==================== ==================== ============ === === ======== =============== ======== =============== =============
4915.00 04 FSAR NSCW SYSTEM NSCW SUPPLIES WATYR X 09-11-87 DC-1202-3. lR, OPERATION AT A RIORER PRESSURE REV. 5
- 9. 2. 1. 2. 3 111AN FLUID IN THE 4-19-83, COOLED SAFETT I4Cl202V15 RELATED CON'ONENT. REY. 1, 9-25-85 4916.00 04 f3AR NSCW SYSTEM DESIGN NSCW VALVES AND X 07-13-87 DC-1202-3.lE. SREET 14, PIPING OLTISIDE REV. 5, 4-19-83 ITEM 10
- 3. 2. 2-1 CONTA!!9EtNT ARE ASMI III CLASS 3.
4917.00 04 FSAR NSCW SYSTEM DESIGN NSCW VALVES AND X 07-13-87 DC-1202-3.lE, SHEET 14 PIPING INSIDE REY. 5, 4-19-83 ITEM 11
- 3. 2, 2-1 CONTAINMENT ARE ASPWI III CLASS 2.
4918.00 04 FSAR CCW SYSTEM SAFETT 9ESIONED 10 TRANSFER I 07-13-87 DC-1203-1.0 & DESIGN BASES REAT FROM RRR SYSTEM 3.1.J.1, RET.
- 9. 2. 2. 1. M NSCW SYSTEM AT A 6, 11-2-83
- 1. A SUFFICIENT RATE TO AVOID FUEL OR CORE DAMAGE FULI4 WING A f- IDCA, IN ACCORDANCE WITH 10Cf1t50, APP.
A, GDC 44 4919.00 04 FSAR CCW SYSTEM SAFETT DESIGNED M REMOVE I 08-11-87 DC-1203-3.lE, DESIGN BASES REACM R DECAT HEAT RET. 6,
- 9. 2. 2. 1. SUFFICIENT 10 BRING 11-2-83, l.F REACMR 10 COIR DMCN-4 SRUTDOWN CONDITION li ?9-86 IN 36 ROURS WITR DC-1203-3.35, LOSS OF OFFSITE REV. 6, 31-2-83 POWER AND ASStNING MOST LIMITING SINGLE FAILURE IN ACCORDANCE WITH RG 1.139
Page No. 36 11/10/87 PLANT YOGTLE UNIT 2 READINESS REVIEW PROGRAM IMPLEMENTATION MATRIX PODULE 04
===-= ===================e============
DESIGN CONST RE F. SOURCE AND DOCtMENT DES CON CURRENT DESIGN CURRENT CONSTRtCTION MINBER MODULE SECTION SUBJECT DoctNENT/FTATURE SECTION IGN ST. AS OF: IN LEMENTATION AS OF: IMPIEMENTATION REMARKS
======= ====== =============== ==================== ==================== ============ === === ======== == ============ ======== =============== =============
4921.00 04 FSAR CCW SYSTEM SAFETT DESIGNED SO THAT A X 08-II-EP DC-1203-3.lc, DESIGN BAaES SINGLE FAILURE OF REY. 6,
- 9. 2. 2. 1. ANT COMPONENT 11-2-83. DMCM-1 1.C ASSINING L.O.0.P.
CANNOT IMPAIR SYSTEM CAPABILITT 10 COMPLY WITH THE SAFETY-RELATED REAT REMOVAL IUNCTION 4923.00 04 FSAR CCW SYSTEM SAFETY DURING ONE TRAIN X 08-11-87 DC-1203-3.lE, EVALUATION 000lbOWN, THE MAE REV. 6,
- 9. 2. 2. 3.A IAAD IS 11-2-83, APPROXIMATELY 189X10 DP O 4-4 ,
6 BTU /IOUR AND COLD 12-29-86, SRUTDOWN IS ACHIEVED WESTINGHOUSE IN 34 HOURS. LETTER F3D/SS41AE-2477 01-17-83 4924.00 04 FSAR AFW SYSTEM DESIGN CONDENSATE STORAGE I 07-13-IFF DC-1302-3.1.2.1 TANE PROVIDES FUR B, REY. 5,
- 10. 4. 9. 2. 1 COLD SRUTDOWut IVR A 4-18-83, DMcN-5 PERIOD OF 9 HOURS S-10-85, 4 HOURS AT HOT X4Cl302V06 STANDBT IVLl4WED BT R3V. O, 3-25-85 A 5 HOUR C00LDOWN 4925.00 04 FSAR AfW SYSTEM DESIGN AfW SYSTEM IS HOUSED X 07-13-87 DC-1302-3.1.10 IN SEISMIC CATEGORT REF. 5, 4-18-83
- 10. 4. 9. 3 1 STRUCTURES 4926.00 04 FSAR AFW PtifS EACH AUXILIART I 07-13-87 DC-1302-3.1.lW.
FEEDWATER PlNP 15 REY. 5,
- 10. 4. 9. 4 RTDROSTATICALLT 4-19-83 TESTED IN ACCORDANCE X4AF03-5.3.1.4, WIN ASPE III CLASS REY. 12, 3 12-2-06 9 9 9
P:Re No. 11/10/87 O'37 O PLANT VOCTLE IMIT 2 READINESS REVIEW PROGRAPI IMPLEPENTATION MATRIX MODUIJE 04
======================================
DESIGN CONST REF. SOURCE AND DOCIMENT DES CON CURRENT DESIGN CURRENT CONSTRUCTION NINRER MODULE SECTION SUBJECT DoctMENT/77ATURE SECTION IGN ST. AS OF: IMPLEMENTATION AS OF: DFLEMENTATION REMARES
======= ====== =============== ==================== ==================== ============ === === ======== =============== ======== =============== =============
4927.00 04 F3AR AfW PtM'S TURBINE-DRIVER IS X 07-13-87 X4AFD3-5.3.1.2 TESTED IN GIVEN A HYDROSTATIC REV. 12, ACCORDANCE
- 10. 4. 9. 4 TEST, PetCHANICAL 12-2-86 WITH API RUNNING 11tST AND AN AX4AF03-191-1 STANDARD GIS OVERSPEED TRIP TEST AI4AF03-161-2 PRIOR TO SHIf99 TNT.
4928.00 04 FSAR BPEMGENCY CORE PIPING IS AUSTENITIC X 08-11-87 DC-1204-4.00, COOLING SYSTEM STAINLESS STFEL REY. 2, 2-11-83
- 6. 3. 2. 5. DC-1205-4.0.A.
2.B. 5 REV. 2, 3-17-83 DC-1208-3.3C, REY. 1, 3-9-83 IX4DR004, REV. 22, 2-13-87 AX4DR001 REV. 19, 7-24-86 4929.00 04 FSAR IDGIRGENCY CORE PIPING IS ANSI X 07-13-87 DC-1010-TI, COOLING SYSTEM SAFETY CLASS 2 AND REY. 5, 2-7-06,
- 6. 3. 2. 5. ASME CLASS 2 OA IX4DR004 REY.
2.B: 1 PROGRAM 22, 2-13-87 4930.00 04 FSAR BPetRGENCY CORE ELEVATED TEPE'ERATURE X 07-13-FT XOCHG18.3 WESTINGNOUSE COOLING SYSTIM OF StPF SOLUTION IS CAICULATION
- 6. 3. 1 (ECCS) WELL WITHIN DESIGN timerERAWRES OF BCCS COPE'ONENTS DURING RECIRCULATION 4931.00 04 FSAR BORIC ACID STORAGE BORIC ACID S1VRAGE X 07-13-87 SEE REMARES (MDST TAME (BAST) TAME IS SIZED 10 REACTIVE
- 9. 3. 4. 1. 2. S10RE SUFFICIENT CONTROL ROD
- 5. 12 SOLUTIOO FDR ONE NOT INSERTED)
REFUELING SHUTD0068 PLUS ENDUGH FOR ONE WESTINGHOUSE COIR SHUTDONN FROM CAlfULATED FULL-PONER OPERATION THE CAPACITY D9EDIATELT AS DoctFEtNTED IDLIDMING REFUELING IN GP 1649 WITH (SEE REMARES) AND GP 2033. S
.,._ _, , - . . - . _ . , - - ~ . - - . _ _ _ - .,. . , _ , , _ . - . . _ , .m__ _ -. . -. - , _ - .
Pu r No. 38 11/13/87 PLANT YOGTLE L' NIT 2 NEADINESS REVIEW PP0 GRAM IMPLEMENTATION MATRIX MODUIJE 04
======================================
DESIGN CONST REF. SOURCE AND DOCIPENT DES CON CURRENT DESIGN Ct'RRENT CONSTRtCTIOM NINBER M)DULE SECTION SUBJECT DOCtNENT/FTATURE SECTION IGN St. AS OF: IMPLEMENTATION AS OF: IMPLDENTATION EmARKS
======= ====== ====e========== ==================== ==================== == ========= === === ======== =============== ======== =============== =============
4932.00 04 PSAR BORIC ACID STORAGE BORIC ACID STORAGE I 07-13-87 I4AR03-3.1.1, SREET 7. ITEM TANK (BAST) TANK IS ASME CLASS 3 REY 9, z
- 3. 2. 2-1 4-29-86 WG.
SE-4-76 4933.00 04 F3AR BORIC ACID S1VRAGE BORIC ACID STORAGE X 09 M I4AR03-3.3.2, SREET 7. ITm TANK (BAST) TAMK IS SEISMIC REY. 9, 4-29-86 2
- 3. 2. 2-1 CATEGORT 1. QA REQUIREMENT FDR CLEANING OF FLUID SYSITMS AND COMPONENTS 5023.00 04 IEB 81-02 WESTINGROUSE 3-INCR MODIFT WESTINGROUSE I 07-13-87 SPEC K6AA06, IUR DETAILS AND 4-INCR GATE 3-INCR & 4-INCR FECO N-45-BF, ALSO SEE CORRESP., GEN. VALVE CIOSURE VALVES TO CORRECT REV. 1 WESTINGROUSE LTR. C-81/07/02 PROBLEM CLOSURE PROBLEM 07-18-85, CCP ItM B10154E. RET. GAEM-10549 0, 09-03-85 5026.00 04 FSAR WELD INSPECTION ASME III 1977 NX-4400 & X X 07-13-87 I4AZOI-P3.3.0.A 05-13-87 ITP PROCEDURE ACCEPTANCE CRITERIA EDITION TRRU WINTER 5300 , REV. 19 IX-3-7.0 REY.
- 3. 9.9. 1. 5. 1977 ADDENDA 6-16-87 6-15-86, X-18 I REY. 2-7-87 5027.00 04 FSAR WElb INSPECTION ANSI B31.1 CODE 1977 SECTION 136 I I 07-13-W X4 AZ01-P4.3.0. A 05-13-87 ITP PROCEDURE ACCEPTANCE CRITERIA EDITION TRRU WINTER , REY. 17 IX-15-8.4.1,
- 3. 9.B. 1. 5. 1977 ADDENDA 6-9-M REY. 6-15-86, I X-18, REY.
2-7-87, II-40, REY. 1-20-87 5091.00 04 FSAR ENVIROPNENTAL DESIGN DESIGNED 10 BREAK B.I.b X 07-13-87 DC-1018-3.3.9.6
- MAIM STEAM FIPIN3 EXCLUSION , REY. 2, 3.11.B. 1 IN PEilV COMPAR1MENTS (SUPERPIPE) CRITERIA 10-11-83 OF BTP MIB 3-1 IUR PORTIONS PASSING TRRU CONTAIPNENT &
EXTENDIPk310 5-WAY RESTRAINT PAST MSIVe O O O
Page No. 39 11/10/87 PLANT 90GT13 (MIT 2 READINESS REVIEW PROGRAM IMPLEMENTATION MATRIX MODULE 04
======================================
DESIGN CONST REF. SOtJRCE AND DoctMINT DES COM CURRENT DESIGN CURRENT CONSTRUCTION N19eER MODUIR SECTION SUBJECT DOCIMENT/ FEATURE SECTION IGN ST. AS OF: DE'LEPENTATION AS OF. IMPLEMENTATION REMARKS
======= ====== =============== ==================== ==================== ============ === === ======== =============== ======== =============== =============
5099.00 04 FSAR INTEGRITY OF MINIMUM PERFORMANCE I 08-11-87 DC-1018 3.6.A. ESSENTIAL COMFONENTS CAPABILITIES NOT REY. 2,
- 3. 6. 2. 3. 2. AND ESF STS11M5 REDUCED BEIDN THAT 10-11-83 1.A REQUIRED 10 PROTECT AGAINST TRE POSTULATED BREAK
$100.00 04 FSAR INTEGRITY OF CONTAIPNINT I 07-13-8T DC--1018-3.6E.2, ESSENTIAL COPFONENTS LEAK-TIGNTNESS IS REV. 2,
- 3. 6. 2. 3. 2. AND ESF SYSTEPE NOT DECREASED BEIDN 10-11-83 1.B DESIGN VALUE IF BREAK LEADS 10 A w IOCA
/
5101.00 04 FSAR INTEGRITY OF PROPAGATION OF I 07-13-87 DC-1018-3.63.1. ESSENTAL COMFTMNTS DAMAGE LIMITED 10 e. REY 2,
- 3. 6. 2. 3. 2. AND ESF SYSTEMS EXTENT TRAT A PIPE 10-11-83, l.C BREAK NhICH IS NOT A DMCN-6, 3-10-86 IDCA WILL NOT CAUSE A LOCA OR STEAM OR
. FERDNATER LINE BREAK 5102.00 04 FSAR RELIEF VALVE SPACED ON READER SO X 08-11-87 DC-1017-3.2.A.3 CONNECTIONS THERE IS NO IDCAL , REV. 5,
- 3. 9.B. 3. 3. INTERACTION 3-19-86 1
5103.00 04 FSAR REACTION FORCES AND BLONDONN IDAD I 08-11-87 DC-1017-3.2.1 PEMINT EFFECTS OF CARRIED BT STRtETimE REY. 5, 3-19-86
- 3. 9.B. 3. 3. BIDNING YALVES USING PISTON TYPE I DESIGN 5104.00 04 FSAR VALVE MANUFACTURER'S VERIFIED BY TCTAL X 0& ll-87 DC-1017-3.2.1, REACTION FORCE NTDRAULIC REACTION REY. 5, 3-19-86
- 3. 9.B. 3. 3. IVRCE ANALYSIS 1
Page No. 40 11/10/87 Pl. ANT V0GTLL INIT 2 RRADINESS REVIEW PROGRAM IMPLEMENTATION MATRIX j M00t*LE 04 , ================================= ==== I DESIGN CONST REF. SOURCE AND DOCtNENT DES CON CURRENT DESIGN CURRENT CONSTRUCTION NIMtER MODUIE SECTION SUBJECT DOCINENT/ FEATURE SECTION IGN ST. AS OF: IWIEMENTATION AS OF: INPIR4ENTATION RIMARES
======= ====== =============== ==========e========= ==================== ============ === === ======== =============== ======== =====-========= =============
l l 5105.00 04 FSAR STRESS ANALYSIS OF STRESS CATEGORIZED I 08-11-87 DC-1017.3.2.1 SAFETY AND RELIEF ACCORDING TO REV. 5, 3-19-86 ( 3. 9.B. 3. 3. VALVE SYSTEM APPROPRIATE CODE 1 l l l 5106.00 04 FSAR MATTRIAL THICENESSES MAINTAIN STRESSES X 08-11-87 DC-1017-3.2.1, OF COMPONENTS IN THE WITHIN ALIDWABLE REY. 5. 3-19-86
- 3. 9.B. 3. 3. SAFETT AND RELIEF LIM'TS 1 VALVE SYSTEM 5107.00 04 FSAR HIGH ENERGY MAIN NO WEIDED X 07-13-87 DC-1018-3.3.B.3 ALTERNATE TO STEAM AND FEEDWATER ATTACINENTS WITHIN 5 .d.1.a. REY 2 BTP MEB 3-1,
- 3. 6. 2. 1. SYSTEMS PIPE BREAES Nr)IINAL PIPE 10-11-83 B.I.c(2) PER I.B. 4 POSTtTLATED AT DIAMETERS OF RIGREST DMCN-12 MRC IETTER INTERMEDIATE STRESS LOCATION (5) 10-30-86 D'TD G-29-84 IDCATIONS (NG-84-51) 5108.00 04 FSAR PIPE BREARS NO WEIJED ATTACH'S X 07-13-87 DC-1018-3.3.B.3 ALTERNATE TO IVSTULATED AT WITHIN 3 X SQ. ROOT .d.l.b. REV. 2 B1? MEB 3-1
- 3. 6. 2. 1. INTERMEDIATE OF (RT) 0F HIGHEST 10-11-83, B.I.C(2) PER
- 1. B ._ 4 LOCATIONS IN HIGH STRESS IDCATION(S) IM.9-12, NRC LETTER ENERGY PIPING SYS'S 10-30-86 D'TD G-28-84 OTHER TRAN MAIN (NG-84-51)
STEAM & ITEDWATER 5119.00 04 FSAR ETEWASH FACILITIES DESIGNED TO PRECLUDE X 09-24-87 X4AP01-ATTACH.4 GENERIC PROVIDED IN ALL SPILLING OF WATER ON -TABLE 4-1, LETTER
- 8. 3. 2. 2 BATTERT ROCMS BATTERIES REV. 15. 7-2-87 GN-1218 DIRECTS THAT AN INSULATOR WRAP AND 2 LATERS Of METALLIC SHEATH COVER PIPING 5348.00 04 FSAR ASME CLASS 1, 2, & 3 DESIGN OF CLASS 1 X ll-09-M DC-1017-2,1 COEVNEMTS. PIPING IS IN REY. 5
- 3. 9.B. 3 COMPONENT SUPfVRTS, ACCORDANCE WITTI 3-19-86 AND CORE St,TFORT SUBSECTION NB 0F DMcN-10, STRUCTURES IW7 EDITION THRU 12-5-86 StPNER 1979 ADDENDA WITH STATED EXCEPTIONS 9 9 9
Page No. 41 11/10/87 PI, ANT V0GTLE UNIT 2 READINESS REVIEN PHOGRAM ITIJMINTATION MATRII MODUIJt 04
====================================== l DESIGN CONST REF. SOGICE AND DoctNINT DES COM CURRENT DESIGN CURRENT CONSTRUCTION NUPSER MODULE SECTION SUBJECT DoctNINT/ITATURE SECTION IGN ST. AS OF: ITIJMINTATION AS OF: IWIJMINTATION REMARKS
- ======= ====== =============== ==================== ==================== ============ === === ======== =============== ======== =============== =============
t 5349.00 04 FSAR ASMt CLASS 1. 2 & 3 DESIGN OF CLASS 2 & I 11-09-87 DC-1017-2.1 00r oNENTS. 3 PIPING IS IN REY. 5
- 3. 9.B. 3 QPPONENT SUPPORTS. AC W RDANCE WITH 3-19-87 AND CORE SUPPORT SUBSBCTION MC & ND DMCN-10 STRUCTURES OF IM4 EDITION THRU 12-5-86 StpMtR IM5 NITH STATED RECEPTIONS i
i t w I
- ,, , ., . - . . , . . - - , - .- ,,---.e.,,..,, ,,.-.n-,,, . , m-v,- ,w,,-n,-~..a.,--gr. , ,, . - - . - , . - . .e -n, ,-- r,-.-...,n-_---..-.. . - ,, w - ~, - , - . - ... ~ , ~ - - ~ . - - -
4 PROGRAM DESCRIPTION O 4.1 DESIGN This section provides a description of design procedures, documentation, design control, and as-built activities related to the design of American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel (B&PV) Code, Section III, Division 1, i Class 1, 2, and 3 mechanical equipment and piping. l 4.1.1 DESIGN PROCESS ; The design end layout of ASME B&PV Code, Section III, mechanical ; equipment and piping are based upon the design and operational requirements of the Final Safety Analysis Report and as delineated in the Vogtle Project Design Manual. Most of the ; design work was conducted concurrently for both Units 1 and 2 . with no significant changes in the work flow since the Unit 1 Readiness Review assessment. The design work flow process has ; been divided into the following six phases: l o Development of design criteria. o Preliminary design and layout considering the nuclear steam supply system (NSSS) system and interface () requirement, Codes of Federal Regulations, Nuclear Regulatory Commission (NRC), industrial /Bechtel Western [ Power Company (BWPC) standards and guides, and client requirements (includes development and issue of , specifications for auxiliary equipment). ! o Final design and clarification of technical interfaces and release of drawings. ! o Review of process calculations (Section 4.1.3.3) sensitive to Unit 2-specific conditions. l o Construction support and interface (determining disposition of. Field Change Requests and Deviation j Reports). ! o Finalization Programs. The following paragraphs describe the work flow process outlined f above. , 4.1.1.1 Design Criteria Development, j r The initial criteria for the design of safety-related mechanical , systems and components are contained in the Preliminary Safety (f { i 0143d/005-8 4-1 !
f Analysis Report, submitted to tne NRC in August 1972. Subsequently, detailed design criteria were developed and issued, with the General Design Criteria (Mechanical), h DC-1000-M, first issued on May 1, 1973. A construction permit was obtained June 28, 1974. The mechanical design criteria were established through various multidiscipline interactions; were based on applicable licensing commitments, industry codes and standards; and were implemented in accordance with establisherl and controlled project procedures. Design criteria were developed to establish identical requirements for the design of both Units 1 and 2 except for certain design and construction schedule restraints where it has become necessary to distinguish between Unit 1 and Unit 2 requirements within the common design criteria documents. 4.1.1.2 Preliminary Design The preliminary design of the plant was developed using general arrangement and equipment location drawings which depict plant overall and individual building layouts, location of major equipment, and routing of major piping and raceways. The development of these drawings was the primary responsibility of the BWPC Plant Design Group which had lead responsibility for a multidiscipline interactive design effort. The Mechanical Group participated in this activity using the various system and interdiscipline criteria (equipment separation, postulated pipe breaks, radiation shielding, etc.) to develop the basic layout l of each system. The system layouts include the location of equipment, required structural openings, space requirements for maintenance, necessary foundati.ons, and piping layout. Schematic drawings of process systems (flow diagrams), and piping and instrumentation diagrams (P&ID) were then prepared by the Mechanical Group in accordance with the developed system design criteria. The identifying equipment tag numbers and strainer numbers were assigned by the Mechanical Group. Line numbers and manual valve numbers were assigned by Plant Design and were included in the line designation list and valve designation list, respectively. Instrument numbers and control valve numbers were assigned by the Control Group and are listed in the instrument index. Preliminary P& ids were distributed to Control, Nuclear, Plant Design, and Electrical Groups for interdiscipline coordination and review. Separate drawings were prepared and difterent numbers were assigned to equipment, pipelines, valves, and instruments for the Unit 2 installation. The Plant Design Group then prepared piping area drawings based on the equipment location drawings, P& ids, physical plant design criteria, and various interdiscipline design criteria (e.g., DC-10ll, Inservice Inspection, DC-1014, As Low As Reasonably Achievable (ALARA), etc.). Piping area drawings are distributed g 0143d/005-8 4-2
I to the Mechanical, Electrical, Civil. Nuclear, and Control Groups for interdiscipline coordination and review. Here too, O separate drawings were prepared for the Unit 2 i'nstallation. The Mechanical Group also coordinated with other disciplines and - the major equipment vendors to obtain information necessary to perform various analyses and to support the overall design process. Procurement specifications (items identical for both units are procured to the same specification) for mechanical equipment and piping were developed by the Mechanical and Plaat Design Groups and were issued by the Procurement Department. Calculations and analyses were prepared during this phase to support the design of mechanical systems and the issue of material specifications. Process system calculations were developed for like systems and components in both Units 1 and 2 by making sufficient allowances (design margin) in input data to accommodate normally anticipated variations in physical plant layout. Piping material specifications and master valve lists were developed to standardize the type of piping, valves, and fittings to be used in both Units 1 and 2. () 4.1.1.3 Final Desian After the system and equipment layout was defined and interface , requirements were obtained from the various engineering disciplines and equipment vendors, the final design phase for i Units 1 and 2 began. Design criteria are maintained current to serve as a basis for completion of the final design of Unit 2. System design calculations common to both units were completed, logic diagrams for system operations were developed (refer to Module 20 for detailed discussion of logic diagrams), and P& ids were issued separately for the construction of Units 1 and 2. Piping area drawings (orthographics) were issued for the construction of Unit 2 after concurrent design review by the Mechanical, Electrical, Control, and Nuclear Groups. Fabrication isometrics for Unit 2 were then prepared for pipe fabrication and subsequent installation. Hazards analyses were conducted during this phase to establish i pipe whip restraint location, jet impingement loads on pipes (if : any) for pipe support design, and maximum flood levels in each l room for safety-related' component location. Potential , internally generated missiles were identified and possible resulting interactions were identified and developed. (:)- ; 0143d/005-8 4-3
I During the final design phase, engineering construction specifications (common to both Units 1 and 2) were developed and issued by Engineering to support construction activities associated with the scope of this module, l 4.1.1.4 Construction Support The Mechanical and Plant Design Disciplines have provided support to the field engineering group in processing for design changes, Deviation Reports, Supplier Deviation Disposition Requests, and calculation revisions incorporating system modifications. These activities have assured that design developments and as-built conditions are considered. The first three phases of the design process are substantially complete and engineering drawings, construction specifications, and material specifications have been issued. The current activities of the Installation Engineering (1E) groups involve processing Field Change Requests (FCRs) and Deviation Reports (DRs) and issuing change notices or revisions to engineering design documents and drawings. The final documentation verification of calculations and issue of as-built drawings conclude the construction support phase. Also, at this time the engineering groups who are supporting construction completion activities are receiving feedback from Georgia Power Company (GPC) Nuclear Operations regarding problems encountered during preoperational test activities of both Units 1 and 2 and the operation of Unit 1. llh 4.1.1.5 Finalization Procrams The following finalization programs within the scope of Module 4 are initiated to confirm that certain as-built conditions of the plant are consistent with project design requirements and licensing commitments. For Unit 2, the finalization programs were evaluated in the light of Unit 1 results and were then ; modified to meet the specific needs of Unit 2. These programs j include consideration of NRC violations, audit findings, and Readiness Review assessment results. j o FP-2 Hazards Finalization - Includes walkdowns by DE personnel to review high energy line break (pipe whip I and jet impingement), flooding, seismic 2/1, and l internally generated missile hazards. l o FP-14 Seismic Separation - Includes walkdowns by IE personnel to review the seismic separation between equipment, components, commodities, etc., for compliance with Appendix SC, Seismic Separation 4 Criteria. l 0143d/005-8 4_4
4.1.2 DESIGN CRITERIA This section describes the criteria which provide the basis for design of safety-related mechanical equipment, components, and systems. These criteria are organized as follows: 4.1.2.1 Physical Plant Desion Criteria These criteria are found in Volume 1 of the Vogtle Nuclear Project Project Design Manual and consist of three sections. Section 1 has a brief introduction and outline of their scope. Section 2 covers criteria for the physical layout of the plant and provides an acceptable basis for protection of safety-related structures and systems from possible damaging effects of postulated events or hazards. This section is used by all engineering groups in coordinating design interface of technical information with other groups as it affects the physical layout of safety-related systems. Section 3 defines the maintenance and serviceability criteria to be considered in developing the general arrangement. 4.1.2.2 General Mechanical Desion Criteria These criteria (DC-1000-M) are also found in Volume 1 and include general mechanical applications criteria such as O. meteorological data, water supply data, codes and standards, piping to be used, nuclear safety system classification, and the plant operating level. Data in this document are used primarily by the Mechanical Group in the engineering and design of mechanical systems including piping. 4.1.2.3 Interdiscipline Desion Criteria These are criteria which have multidiscipline applicability. The interdiscipline criteria pertaining to this module are listed in Table 4-1. The Civil / Structural, Plant Design, Mechanical, Control Systems, Nuclear, and Electrical Groups use these interdiscipline criteria to coordinate design interface of technical information on safety-related systems. The Nuclear Group uses these criteria to conduct hazards reviews, ALARA radiation exposure reviews, and to coordinate the relevant input from other groups. The Mechanical Group uses them to prepare mechanical equipment specifications and P& ids. The plant design group uses them to prepare and maintain plant general arrangement and equipment location drawings and piping area drawings. (D \_/ 0143d/005-8 4-5
4.1.2.4 Mechanical Systems Design Criteria These are criteria for mechanical process systems and equipment which are safety-related or have a significant safety impact on lh the plant. The criteria for these systems fall into two categories: those developed by Westinghouse which were dictated by the requirements of the NSSS, as shown on sheets 4 and 5 of Table 4-2, and others that were developed by BWPC, as shown or cheets 1, 2, and 3 of Table 4-2. Design criteria for the reactor coolant system (DC-12Ol) are addressed in Module 16. The following systems are not safety-related, but portions of the systems associated with containment penetration and/or isolation are designed to the ASME B&PV Code, Section III, requirements: o System 1212 - Liquid sampling system. o System 1214 - Containment and auxiliary building drain system. o System 1217 - Auxiliary component cooling water system. o System 1222 - Miscellaneous leak detection. o System 1418 - Plant demineralized water storage and distribution system. lh o System 1901 - Liquid waste. o System 2301 - Fire protection water system. o Systems 2401 and 2420 - Instrument, service, and breathing air system. o System 2702 - Post-accident sampling system. The following systems are not safety-related, are not associated with containment penetration or isolation, but do have portions designed and/or procured to the ASME B&PV Code, Section III, requirements: o System 1215 - Auxiliary building drains, nonradioactive
- valves procured to Class 3.
o System 1225 - Control building drains - valves procured to Class 3. o System 1227 - Fuel handling building drains - valves procured to Class 3. G 0143d/005-8 4-6
. = .- . - - -- ._
I o System 1314 - Waste evaporator steam supply - valves ; procured to Class 3. o System 2303 - Fire protection - seismic Category I water system - all piping and valves are Class 3. f 4.1.3 DESIGN DOCUMENTATION This section addresses the design documents (drawings, calculations, studies, etc.) used for project design of mechanical equipment and piping. Design documentation is categorized as follows. l l 4.1.3.1 Studies Engineering studies are used '. nvestigate alternate solutions to engineering problems, or tc I- aort on the anticipated results of a particular engineering solttion. Informal studies are used to develop project design within the scope of the contract. Formal studies investigated concepts or developed criteria that define the project scope. 4.1.3.2 Analyses () Most engineering analyses are prepared in the form of a calculation and are logged as such. The types of analyses conducted on the Vogtle project are as follows: o Failure mode and effects analyses (FMEA) for equipment and systems were prepared by the Mechanical Discipline in accordance with BWPC Vogtle Electric Generating Plant _ (VEGP) Project Reference Manual (PRM), part C, i section 16. The failure modes of components that could contribute to unsafe system operations were identified and corrective action was taken to obtain compliance with the single fa!. lure criteria (Design Criteria Document DC-1009). FMEAs are applicable to Units 1 , and 2. )
)
o Hydraulic transient analyses were performed by the ; Mechanical Discipline to evaluate system performance and ' to generate dynamic loads to the piping systems / pipe supports resulting from hydraulic transients induced by pump. start /stop, valve closure, flow orifices, etc. Analyses were also performed to evaluate the mass-energy releases from a system as a result of a postulated pipe rupture. Data generated by these analyses were input into pressure-temperature analyses performed by the ; Nuclear Group for environmental effects on equipment and j .O.
-0143d/005-8 4_7
pressure loadings on the structures. All such analyses are applicable to Units I and 2. o Hazards analyses are performed in accordance with Design O Criteria DC-1003, DC-1006, DC-1018, et.al. on a room-by-room basis for each unit. Components within each room are reviewed for postulated high energy line breaks (pipe whip and jet impingement), flooding, internally generated missiles, and seismic 2/1 interaction. portions of these analyses are presently ongoing for Unit 2. A set of separation review books, which is a summary of the above hazards, was prepared and is being maintained by the hazards review team, Design Engineering (DE). Detailed high energy line break analyses (HELBA) are being maintained in individual system HELBA books by the hazards review team, DE. The HELBA discussed in this section addresses only the pipe whip and jet impingement effects of a high energy line break. The pressure and temperature effects of a high energy line break are addressed in section 4.1.3.3. Calculations (e.g., pipe whip / jet impingement calculation, jet impingement load calculation, flooding calculation, and internally generated missile calculation) were performed to support the evaluation of hazards analyses and are also lll described in section 4.1.3.3. 4.1.3.3 Calculations Calculations are prepared and controlled in accordance with the VEGP PRM, part C, section 9. For VEGP (and typically for other multiple unit plants), the process systems are designed to be identical in both units (except for common systems which are not duplicated but are shared). Accordingly, design margins are included to account for unit-specific variances in pipe routing which may affect pressure drop calculations, minimum net positive suction head, total developed head, etc. To confirm that the design margin envelopes Unit 2 piping configurations, 41 hydraulic calculations will be reviewed by Engineering. These reviews include all safety-related process pumps and pumps for radwaste service (except for small sump pumps). Because of the conservatism in the initial design of small sump pumps, coupled with the low usage factor. Engineering evaluation of the Unit 2 piping configurations are not warranted. ; 1 0143d/005-0 4-8 l l
I The following paragraphs provide a description of the contents : of.the various types of calculations within the scope of this O module. I o Equipment design calculations (Mechanical) were performed for equipment sizing, control valve sizing, and flow element sizing. pump parameters such as net positive suction head, capacity, head, brake horsepower, and efficiency were evaluated. The results of these calculations were used for input to procurement and ; design specifications as well as system calculations. Specific process design conditions at control valves such as inlet pressure, differential pressure at design flow, flashing, cavitation, etc. were developed by the Mechanical Group and provided to the Control Group. 4 preliminary sizing of flow orifices was calculated for ; input into system design calculations. o System design calculations (Mechanical) were performed ' to determine process design conditions such as. pressure, j temperature, pressure drop, and setpoint pressure of j safety relief valves for input into procurement specifications. Calculations were also performed to size the vent stacks of safety and relief valves and to I determine the reaction forces in the pipes for input to the pipe stress and supports groups.
) o System / Equipment verification calculations were done for each safety-related system using finalized data from l equipment suppliers and completed isometric piping l drawings. The results verified pipe size, pump sizing, l tank volume, and heat exchanger capacity. Operating modes were evaluated to assure the system met the design requirements and would perform its function for various ,
required conditions. ; I o A minimum pipe wall thickness calculation was performed for each piping material class by the MIN-WALL computer. program considering material properties, pipe design pressure and temperature, pipe bending allowance, and corrosion allowance. The required pipe schedule for each piping material class was then specified in the Piping Material Classifications (Drawing AX4DR001), o Hazards review calculations were performed by the l Nuclear / Hazard Group to support the hazards analyses discussed in section 4.1.3.2. ' Hazards review calculations consist of:
- pipe whip calculations to determine the plastic hinge lengths and restraint design for pipe thrust loads.
Results of-these calculations were then included in O the pipe whip restraintLisometric sketches and 0143d/005-8 4_g l I i ___________.j
transmitted to the Civil / Structure Group for their use in pipe whip restraint design.
- Jet impingement calculations which were made using the O
Standard Jet Impingement Code NE 155 computer program. These calculations resulted in jet tables which were used in developing the jet impingement zone-of-influence (ZOI) figures and to calculate the jet impingement loads on identified essential targets.
- Thrust / time history calculations which were performed in certain cases to allow for frictional losses in high energy piping.
- Jet impingement load calculations which were made to determine the impingement loads on identified, essential targets. Target lists were provided by the disciplines in their reviews of the ZOI. The hazards engineers then determined the essential targets to be analyzed.
- Flooding calculations which were made to determine the worst flooding source in a particular room or area.
As a rule, safety-related equipment and components were designed to be located above maximum calculated flood level. Safety-related equipment below the flood level was reviewed to determine whether the component would be required to mitigate the effects of the flood, and if so, to relocate it or provide additional lll protection. Internally generated missile calculations which were made to identify possible sources of such missiles. These sources were analyzed for credibility, casing penetration, or concrete penetration where applicable. Escaping missiles, if any, were reviewed for impact on safety-related equipment or components in the vicinity. o Pressure-Temperature calculations include:
- Containment pressure and temperature (P/T) transient calculations which were performed by Westinghouse for a loss-of-coolant accident and main steam line break.
Data generated by these analyses were used to establish the design pressure of the containment structure.
- Subcompartment P/T analyses are performed by the DE nuclear group to determine the maximum differential pressure across the subcompartment walls. Data generated by these calculations were provided to the Civil / Structural Group for design.
O 0143d/005-8 4-10
- Pressure and temperature effects of high energy line breaks analyzed by the DE Nuclear Group. Data O- generated by these calculations were provided to the Equipment Qualification Group for incorporation into the procurement specifications.
4.1.3.4 Drawinos Design drawings were prepared and controlled by BWPC in accordance with the VEGP PRM, part C, section 4. Drawings, l sketches, and figures needed to support the design of the mechanical equipment and components and piping systems covered by this module are: o Flow diagrams initially prepared by Westinghouse for the ; NSSS and transmitted to BWPC for use in detailed design. These flow diagrams were redrawn into P& ids and issued for project review. P& ids for balance-of-plant systems were then developed based on plant-specific ; conditions, GPC requirements, economic considerations, { NSSS vendor interface requirements, and regulatory ~ requirements. o General arrangement drawings showing the configuration of the power block, building dimensions, and basic equipment arrangement which were the first plant design O drawings developed. The basic framework of general arrangement drawings was the structure column grid layout. A set of these drawings consists of plans for each major floor level and enough sections to indicate the essential relationship between floor and equipment. o Equipment layout drawings were later developed to dimensionally locate major equipment in'the plant by coordinating inputs from all disciplines. In addition to showing location dimensions of major equipment, they also designate equipment laydown or tube pullout space to ensure proper installation and maintenance. These layouts were developed based on equipment configuration, vendor requirements, system process requirements, NRC requirements, and industry /BWPC standards. o Area piping drawings which-were generated by the Plant ' Design Group to record all applicable dimensions, sizes, specifications and specialty requirements pertinent to-the installation of pipe. Each piping system was laid out to satisfy all performance requirements in accordance with P& ids and design criteria. Background , information, such'as structural steel, mechanical- I equipment. ducts and trays, etc., was also shown to 1 control possible interferences. 0143d/005-8 4_11
~~- - . _ . . _ _ . . _ __ _ _
o Piping fabrication isometrics which were developed from the piping area drawings by Plant Design. These drawings show pertinent piping data and are issued for h pipe spool fabrication and subsequent pipe installation. o Three types of sketches which were issued for high energy line break analyses:
- 1) Stress isometrics for break locations.
- 2) Pipe whip restraint isometric figures.
- 3) Jet impingement 201 figures.
These sketches provide information to affected disciplines for detailed design, and are controlled by the Nuclear Group. The pipe whip restraint figures and 201 figures were made a part of the high energy line break analyses boo,c. The pipe whip restraint figures were prepared by the originator and issued to the Civil / Structural Group via a memorandum signed by the engineering group supervisor (EGS). o Isometrics of each high energy line which were generated by Plant Design to support stress analyses to determine specific break locations. The Piping Stress and Support Group (PSSG) then performed a stress analysis on each ll high energy line and determined the required locations of postulated pipe breaks as well as their type. With this information, the PSSG marked up the appropriate isometric drawing to indicate the precise location of each postulated high energy line break. The figures were organized and numbered by the corresponding system and line number. The original stress isometric figures have been maintained current by the PSSG. o A pipe whip restraint figure that was developed for each high energy line identified. This figure identified the line number, system, description, plant design isometric figure revision number, revision date, figure number, pipe whip restraint number, restraint location and direction, restraint design load, plastic hinge length, pipe break locations, type of pipe breaks, and pipe break event numbers. The pipe whip restraint figure was transmitted to the Civil / Structural Group for restraint design. The original pipe whip restraint figur,es are maintained current by the hazard review team, DE, and are part of the HELBA books. o The jet impingement ZOI figures which were developed after completion of the pipe whip restraint figures. A jet 201 was developed for each pipe break event llh 0143d/005-8 4-12
i t identified in the pipe whip restraint figure. The system and line number, break event number, break type, figure number, revision, break elevation, jet description, reference jet calculation, and reference drawings were identified. [ The ZOI figures are developed to scale, using plant l design area piping drawings, with sectional views for clarification where appropriate. The ZOI packages were : then issued to all disciplines for review. Original ZOI ! figures are maintained and controlled by the Hazard Review Team, DE, and are part of the'HELBA books discussed in section 4.1.3.2. ; F o The Line Designation Report (Drawing'2X4DR004) which is ; a summary of lines as shown on the P& ids. Pertinent - information included is: , The identification of the line t by a unique' number and line size, wall thickness or pipe ; schedule, material classification, type of insulation, insulation thickness, project classification, system i description, design pressure, design temperature, operating pressure, operating temperature, cleanliness ! class, startup system number, and drawing number on [ which the line appears. ' o The Valve Designation Report (Drawing 2X4DR005) which is [ a summary of manually operated process valves (except O control and instrument valves) shown on the P& ids. Each valve is identified by a unique number. Pertinent information included is: project classification, master j valve list mark number, paint code, system line number, ' cleanliness class, size, type, rating, design pressure and temperature, operating pressure and temperature,. - , I client purchase order number, manufacturer's name and activity package number, including the delivery data i required at the jobsite. l t o The Roots, Vents, Drains, and Instrument Control Valve Designation Report (Drawing 2X4DR007) which provides a u listing by valve tag number and information similar to l that on the value' designation list. ; o Piping material used on the Vogtle project is: listed in the Piping Material Classifications Document (Drawing AX4DR001). It includes pipe, flanges, fittings, bulk i order valves, and gaskets. They are designated by 4 pressure / temperature rating,' type of material, and ASME or American National Standards. Institute (ANSI) Code. [ . In addition.to the above, procedures related to pipe { spooling =are identified to cover such things as-cleaning and coating requirements; weld end preparation: instrument, vent, and drain connection details; spool-O numbering; etc. In procuring fabricated pipe spools, 0143d/005-8 4-13
l l I this document, along with the Line Designation Report, is appended to the procurement specification. o The Master Valve List (Drawing AX4DR002) which O identifies the applicable valve, by mark number, type, rating, material, and any specialty feature. 4.1.3.5 Specifications Material, equipment, and components are procured and installed at Plant Vogtle in accordance with a specification. The following specifications were prepared by the Mechanical and Plant Design Groups: o ASME design specifications on the VEGP project which are either in the form of a free-standing document, such as those written for the Code piping systems, or as part of procurement specifications in the form of the ASME B&PV Code, criteria locator for Code Class 2 and 3 pumps, valves, tanks, and vessels. The procurement / design specifications for ASME Code Class 1, 2, and 3 components, excluding piping systems, were prepared in accordance with the PRM, part C, sections 8 and 29. The design specifications for the Code piping systems were prepared in accordance with PRM part C, section 29. Procurement specifications for piping were prepared in accordance with the PRM, part C, section 8. lh Desic- specifications for all ASME B&PV Code, Section III, components, parts, appu?;tenances, and piping systems are listed in the ASME Design Specification Matrix (Document X4POOO5). This document identifies the supplier, purchase order number and date, Code cases, Code edition and addenda, specification revision, and Supplier Deviation Disposition Request numbers for each ASME B&PV Code, Section III, design specification and is updated annually, or more frequently if necessary, by the project code engineer. o Construction specifications are originated by IE to give specific instructions for field construction and installation activities. The divisions of Construction Specification X4AZ01 applicable to this module are: Division Title P1 General Requirements P3 ASME Section III Piping Field Fabrication and Installation O 0143d/005-8 4_14
1 1 l 1 P6 Mechanical Equipment Field Handling,
. Installation, and Setting P8 Field Installation of Welded SteeliBuried Piping P9 Permissible Consumable Materials for Use during Construction Division P1 defines the conditions and general requirements for field fabrication and erection of piping and pipe supports, including setting of mechanical equipment.
The permitted welding processes and their restrictions, permitted welding materials, ferrite control requirements, preheat and interpass temperature, and postweld heat treatment requirements are specified in sections Pl.7.1 through Pl.7.7 of division Pl. Weld workmanship and visual quality examination requirements are specified in section P.1.7.8 of division Pl. Each contractor (and subcontractor) was required to prepare
-written welding, brazing and heat treatment procedures and submit them to BWPC engineering with procedure qualification records for review and concurrence.
Division P3 defines the conditions and requirements for field fabrication and/or installation and field modification and installation of ASME B&PV Code, Section III, piping and associated work. Division P6 defines the conditions and requirements for the handling, setting, and alignment of rotating equipment, and handling and setting of nonrotating equipment. Division P8 specifies the requirements for the installation of shop and field fabricated ASME B&PV Code, Section III, Class 3 ANSI B31.1; and other welded, flanged, l threaded, and galvanized carbon steel buried piping systems. I Division P9 provides a list of permitted consumable materials I and construction requirements for the listed consumable material. l 4.1,4 DESIGN CONTROL AND REVIEW i The overall project and technical responsibility for j safety-related system (equipment and piping) design within BWPC r is assigned to the project engineer, mechanical design; the , chief mechanical / nuclear engineer, and the chief plant design engineer, respectively. The primary responsibility for the system design is assigned to the mechanical EGS, and the primary 1
-responsibility for piping design is assigned to the plant design i EGS. The design process-is controlled by PRM, part C, and is- :
implemented by the use of the Design Manual and various control l tools such as discipline desk instructions, interdiscipline ' reviews, and chief reviews. l During the design process, periodic technical and administrative , , _ reviews of design documents are conducted. These reviews ! i 0143d/005 4-15 i
involve interdisciplinary coordination and review, and approval of design documents by the chief or designated staff member. The following sections describe the various design reviews and interdiscipline coordination, and documentation / drawing control. 4.1.4.1 Design Reviews UWPC design work was periodically reviewed as follows: o Concurrent discipline reviews were performed using specific design documents, such as design criteria, drawings, specifications, vendor prints, and other documents. Information was transmitted between discipline groups in the form of coordination prints, Document Review Notices (DRNs), etc. These reviews took place concurrently within the discipline groups and comments were transmitted to the originating discipline for resolution and incorporation. o Interdiscipline group design reviews involved group consultation and frequent coordination among personnel from affected disciplines. Examples of group design reviews were the licensing reviews and system design reviews performed during 1977 and 1978. o Design verification reviews were pecformed on all VEGP h safety-related components and systems. These reviews resulted in no significant findings pertaining to the design of safety-related systems or components. o Technical reviews of safety-related system design were primarily the responsibility of the chief mechanical engineer who was assisted by a staff of technical specialists and experienced personnel from other similar nuclear projects. The chief mechanical engineer reviewed and approved certain specific engineering documents, which were identified on the Design Control Checklist (DCCL). In addition to the review and approval of specific documents, the chief engineer and his staff performed reviews during the design process. These reviews included the presentation and status of the work by the project team. The chief plant design engineer reviewed and approved the plant general arrangement drawings, equipment location drawings, material specifications,the piping system design specification for ASME B&PV Code, Section III, components / systems, construction specifications (safety-related divisions only), and the ASME B&PV Code, Section III, design specification matrix. The DCCL is prepared and controlled in accordance with subsection 20.7 of the PRM, part C, section 20. lh 0143d/005-8 4-16
In addition to formal reviews, the chief engineer and r- his staff provided informal reviews and consultation as requested when specific items arose that necessitated either special consideration or contact with other BWPC entities. As part of his project technical review and supervisory responsibilities, the chief engineer also issued problem alerts describing problems encountered on other Bechtel projects. The problem alerts required a project response concerning the applicability of the particular problem with the specific project action taken to assure it did not occur at Plant Vogtle. 4.1.5 DESIGN CHANGE CONTROL Subsequent to the revision 0 issue of design documents, changes may be made by approving FCRs, by issuing change notices against the design documents, or and by taking appropriate action on DRs. These changes, to be considered part of the design documentation, are logged and tracked by project administration and approved by discipline engineering supervision. The PRM provides procedures for identifying changes to the design, evaluating the licensing impact, assessing cost and schedule impact, ensuring timely approval by project management, tracking and implementation of approved changes, and incorporating the O changes into original documentation. The following sections discuss the process by which potential engineering changes, FCRs, DRs, and specifications are controlled. 4.1.5.1 Potential Chance Control A potential change to the plant design generally results from new or revised regulatory requirements, changes to codes, client requests, requests from Construction, startup problem reports, or the results of design verification reviews. Changes may be identified by BWPC, GPC, Southern Company Services, Westinghouse, or other suppliers. The control process for potential changes is discussed in PRM, part C, section 27. 4.1.5.2 Field Chance Reauests Physical changes initiated to resolve installation problems such as interferences or nonconforming conditions are exceptions to , this procedure, unless such changes involve a significant ' procurement change or modification of components or equipment, a 1 7g significant interdisciplinary interface requirements or a V 0143d/005-8 4_17
schedule or bulk commodity impact. Examples of these exceptions which may be reviewed and approved by the normal change process, include all editorial document changes, FCRs, DRs, or Request for Engineering resolutions concerning large- and small-bore piping (including design, supports, anchors, and restraints), raceway, tray, instrumentation, and associated items that do not affect other installations. FCRs are processed in accordance with the procedure described in the operations PRM, part C, section 17. As a result of Institute of Nuclear Power Operations Finding DC.6-1, section C-17 of the PRM was revised to require documented justification for approval of an FCR. When appropriate, the FCR now states whether calculations are required (as determined by the approving engineer) and an engineering rationale or numerical justification is provided. When calculations are required, the FCR documentation further indicates that the appropriate calculations have been reviewed before an FCR is approved by Project Engineering. For piping FCRs, the PRM, part C, section 17, is supplemented by PFM, Appendix 2, sections 7 and 10. The procedure may also be used to propose changes to supporting documents such as the Valve Designation Report and Line Designation Report. Since a critical part of the construction process is material requisitioning from site storage facilities, material (valves and piping) callouts on the piping isometrics must be in agreement with the specified parameters in order to complete the f material requisition process. For limited and predefined areas, construction may continue while an FCR is processed by issuance of an Authorization To Continue Work (ATCW). The ATCW is initiated by checking the ATCW box in block 14 of the FCR as described in Appendix 2, section 14, of the PRM. With an ATCW approved by designated IE personnel, work may proceed and in-process inspections may be performed according to the requirements of the ATCW. After Engineering approval of the FCR, acceptance is based on final inspection to the approved FCR. 4.1.5.3 Deviations The procedure for processing DRs is discussed in the PRM, part C, section 18. In the IE Mechanical Group, this procedure is supplemented by desk instructions number 1, which provides clarification of project requirements, and number 4 for instructions on processing the DR within the Mechanical Group. l 9 0143d/005-8 4-18 I i
For piping DRs, PRM section 18, is supplemented by PRM, Appendix 2, section 10. 4.1.5.4 Specification Chances . The responsibility for issuance and control of specifications is described in the PRM, sections 8, 23, and 26. As previously < described (4.1.1.4), the IE group is responsible for construction specifications: o The Mechanical Group is responsible for Construction Specification X4AH03, Field Erected Tanks Built to Section III of the ASME B&PV Code o The Plant Design Group is responsible for:
-X4AZOl, Piping and Instrumentation Construction Specification
-X4AQ34, ASME III Small Bore Pipe and Fittings
-X4AQ36, ASME III Large Bore Pipe and Fittings ;
-X4AQ37 Weld Filler Metal a
f, -X4AQ38, Bolting Material (. The following documents, when evaluated and approved, may result l ' in changes to specifications: o FCR - Initiated by the field, dispositioned by Project j Engineering. ! o Drawing Change Notice - Initiated by the Mechanical or Plant Design Discipline, dispositioned by Project ! Engineering. o DR - Initiated by anyone, validated by Quality Control (OC) and dispositioned by Project Engineering. Changes to construction or procurement specifications may be i made by a Construction Specification Change Notice (CSCN) or by I a Material Specification Change Notice (MSCN), respectively. CSCNs or MSCNs are initiated by engineering. CSCNs or MSCNs pertaining to DE documents require the approval of the DE EGS and project engineer. Once approved, these changes are considered part of the parent document and are incorporated into i a revised specification. i l O 0143d/005-8 4_19
4.1.5.5 Equipment Modification Program Prior to any modification or repair to project quality class (Q-class) equipment, non-O-Class fire protection and radwaste-related items, the supplier is notified of the proposed changes / repairs and is requested to revise applicable drawings. Revisions to supplier drawings are made by engineering only when the supplier has indicated concurrence, in writing, with the proposed changes but has declined to provide revised drawings. Changes to installed supplier equipment are initiated by preparing a Field Equipment Change Order form, as discussed in the PRM, part C, section 24. Repairs to ASME B&PV Code, Section III, items may also be initiated by an approved repair disposition of a DR. The instructions for the control of repairs, modifications, and replacements to Code-stamped items are discussed in the PRM, Appendix 2, section 12. Before a repair or modification is performed, the supplier and Project Engineering must be notified, and their concurrence must be given in writing. In addition, repairs to Code-stamped installations and components require approval of the authorized nuclear inspector (ANI). Repairs and modifications to an N-stamped item is preferably to be performed by the original N-certificate holder (manufacturer). When the manufacturer of the component no longer possesses an ASME certificate of authorization to construct the component, or it is not practicable to be done by the manufacturer, repairs are performed by an NA-certificate holder at the jobsite. A revised, or supplementary, Code data report signed by the ANI is provided by the manufacturer or installer after the repair / modification is completed. Supplementary reports documenting repairs, modifications and replacements are referenced and attached to the original data report for the item. 4.'.5.6 As-Built Verification for Safetv-Related Piping Systems Prior to hydrotesting, the piping shown on each isometric drawing is walked down by a GPC/ Pullman Power Products (PPP) inspection team to confirm the as-built condition of the system. The as-built inspection includes a verification of piping dimensions and geometry, valve tag numbers, valve operator orientation, and floor and wall penetration clearance. A revision to these isometric drawings will be initiated by PPP indicating "As-built, within tolerances". The as-built isometric drawings are then reviewed and reconciled with the latest P&ID. The reconciliation is noted in the revision block of the isometric drawinc. The as-built design verification program is discussed in the PRM, Appendix 2, section 17. As-built walkdowns are discussed further in Module 11. 0143d/005-8 4-20
4.1.5.7 Chance Control Package () After a system or component is turned over, or about to be turned over, by GPC Construction to GPC Nuclear Operations, design changes requiring physical modification are documented on a Change Control Package (CCP). CCPs are not required to document as-built conditions, to make editorial changes, or to replace temporary components with permanent components where design drawing changes are not required. CCPs are not issued for changes specifically requested or approved by GPC Nuclear Operation. However, for all changes made after system turnover that are not covered by a CCP, a copy of all resulting documentation is sent to GPC Nuclear Operations. Changes to design drawings to implement physical changes to a system or component are made on Interim Drawing Change Notices (IDCNs). Changes to IDCNs can be made on Interim Field Change ] Requests. New drawings issued in the CCP can be used only in j conjunction with the work described in the CCP. Changes to supplier drawings and equipment are implemented by issuing an Interim Drawing Change Notice-Supplier. These interim documents 1 will be converted to drawing change notices only after the CCP I is closed out. The CCP is prepared, processed and controlled in accordance with the PRM, part C, section 35. { l O 1 l (~h L) 0143d/005-8 4-21
+au __ .-a---
. mMsm . . ea- m. -,.
l r L O I i r I i 1 l l 0143d/005-8 4-22 ,
-- - ' ~ , . . -
4.2 EOUIPMENT AND MATERIALS () Safety-related mechanical equipment and piping outside the Westinghouse scope of supply were procured through a group of specifications written and controlled by Bechtel Western Power company (BWPC). These specifications were prepared in accordance with the design criteria prepared by BWPC and contained in the Vogtle Electric Generating Plant (VEGP) Project Design Manual. Bulk materials in this module consist of pipe and fittings for safety-related piping systems. This material is procured ! through a series of specifications also written and controlled by BWPC. These specifications cover both piping which is shop fabricated and that which is field fabricated and installed. Pipe, fittings, and valves are specified in accordance with the Piping Materials Classifications sheets prepared by BWPC in conjunction with Westinghouse. The piping class sheets were prepared by BWPC in accordance with the design criteria contained in the VEGP Project Design Manual. Georgia Power Company is the purchasing agent for equipment and materials discussed in this module and supplies them to the contractors for installation. Most of the Unit 2 equipment was procured concurrently with that of Unit 1, but under separate purchase orders. ( O 0143d/005-8 4-23
4
)
O l 1 i O l O 0143d/005-8 4-24
4.3 SITE MATERIAL CONTROL Georgia Power Company (GPC) purchases, receives, inspects, and stores piping, equipment, and material, including welding materials, required for construction at Plant Vogtle. GPC is also the material supplier for the equipment and materials to be installed in piping systems which require certification and stamping to the requirements of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel (B&PV) Code, Section III. Division 1. Requirements of the ASME B&PV Code, Section III, Division 1, necessitates that receipt, inspection, and control of ASME Code items and materials be performed by the NA-installers, Pullman Power Products (PPP), Nuclear Installation Services Company (NISCO), or the GPC Nuclear Construction Team (NCT). NISCO responsibility is limited to components and activities that are within the Westinghouse Electric Company scope of supply. For materials and equipment installed by GPC NCT, GPC has subcontracted the receipt, inspection, and control of the ASME B&PV Code items to PPP. Other activities regarding site material control procedures remain the same as for Unit 1. O 0143d/005-8 4-25
T 1 0' i r O W 1 7 0 0143d/005-8 4-26 J
4.4 FABRICATION, INSTALLATION, INSPECTION, AND TESTING The Georgia Power Company (GPC) Vogtle Project Construction is managing site fabrication, installation, inspection, and testing activities for process piping and equipment. GPC construction quality control (OC) monitors these activities in accordance with Vogtle Field Procedure QC-T-ll. The work for these activities is contracted to Pullman Power Products (PPP) with the exception of work at the auxiliary feedwater pump house, which is being performed by the GPC Nuclear Construction Team (NCT), and site fabrication and inspection activities for various tanks and containment penetrations which were contracted to Chicago Bridge and Iron. This section describes the site l fabrication and installation activities, the generic inspection points, and the types of tests performed with references to the controlling document (i.e., code, specification, or implementing procedures). The specific technical requirements for any one of the activities, inspections, or tests described are found in the referenced documents. Bechtel Western Power Company (BWPC) Construction Specification X4AZOl governs process piping and mechanical equipment fabrication and installation. The divisions of X4 AZO 1 applicable to this module are listed in section 4.1.3.5 The following supplementary documents, as designated in X4 AZO 1 are also applicable: Document Number TITLE I Drawing AX4DR001 Piping Material Classifications Drawing AX4DR002 Master Valve List Drawing AX4DR004 Line Designation Report Appendix D Butt Weld End Preparation and Transitions Appendix E Piping System Cleanness During Construction Appendix VC Visual Inspection Criterion for Welds Appendix SC Seismic Separation Criteria Both PPP and GPC are responsible for the fabrication and the installation of piping and mechanical equipment in accordance with these documents. American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel (B&PV) Code, Section III, work is performed in accordance with the 1977 Edition through the Winter 1977 Addenda under ASME certificates of authorization for NA-installation and NPT-fabrication. Prior to implementation of work activities at the jobsite, the PPP and GPC Quality Assurance Manuals (QAM) were approved by BWPC. BWPC is designated as the owner's agent for certain activities, and is the responsible N-certificate holder for the ASME B&PV Code piping related to the scope of this module. (aD 0143d/005-8 4-27
=
4.4.1 CHANGES IN FABRICATION, INSTALLATION, INSPECTION, AND TESTING SINCE THE UNIT 1 ASSESSMENT Significant changes in fabrication, installation, inspection, and testing of Module 4 equipment and components since the Unit 1 Readiness Review assessment are the inclusion of GPC as an NA-installer and issuance of GPC procedures for those activities. These procedures are listed in Section 4.4.3. 4.4.2 PULLMAN POWER PRODUCTS ACTIVITIES 4.4.2.1 Pullman Power Products Prerequisities 4.4.2.1.1 Pullman Power Products Quality Program The PPP QAM has 18 sections which correspond directly to the 18-point quality assurance criteria of 10 CPR 50, Appendix D, and ASME BGPV Code, Section III, subsection NCA 4134. PPP project procedures were developed to effectively implement PPP QAM requirements and are included in a Project Procedures Manual. The individual procedures that were developed have, as their prefix, the Roman numeral of the applicable PPP QAM cection they implement. The following PPP project procedures (others, including a series of Site Instructions and procedures incorporated by reference are not listed) are within the scope of this module: g PROCEDURE TITLE II-2 Levels I and II Nondestructive Examination Personnel Control and Administration of Training, Examination, Qualification, and Certification. 11-3 Level III Nondestructive Personnel, Control and Administration of Examination, Qualification, and Certification 11-4 Inspection and Testing Personnel Control and Administration of Training, Examination. Qualification, and Certification. II-5 Quality Engineering Personnel Control and Administration of Training, Examination, Qualification, and Certification. 11-8 Welder Performance Qualification 11-13 Eye Examination for QA/QC Personnel III-3 Stop Work Order Procedure 0143d/005-8 4-28 l i
. -. .. _- - - _ - _ - _ - . -. ~ - - i i k III-4 Drawing and Design Control Procedure ; O. t VI-1 Document Control ! VI-5 Control of Process Sheets and Weld Rod Stores Requisitions VI-6 Field Preparation and Control of Project Procedures and their Revisions i VII-2 Material Control ' VII-13 Control of Tools for Use on Stainless Steel ~ Materials ! VIII-l Identification of Materials, Parts, and Components ' VIII-3 Control of Welding Materials (Field) ' VIII-10 Procedure for Control of Consumables Used on Stainless Steel Materials 1 IX-1 Installation and Inspection of Concrete Anchors IX-3 Fabrication and Field Installation Specifications for Nuclear Power Plant Components, Piping Systems, 1 [ O and Appurtenances, ASME - Section III, Winter 1977 Addenda i IX-5 Installation of Threaded Fasteners (bolting ; procedure) i l
-IX-14 Defect Removal and Repair by Welding IX-15 Field Fabrication and Installation of Non-Nuclear !
Piping Systems - IX-16 Cold Bending of 2-Inch N.P.S. and Smaller, Nuclear l and B31.1 Pipe IX-19 Requirements for Alignment and Fit-up ! IX-29 Control and Use of Purge Dams IX-43 Procedure for Preheat, Interpass, and Postweld Heat Treatment - IX-44 Installation and Removal of Temporary Attachments ! IX-48 Procedure for Equipment Installation ! IX-51 Procedure for Fabrication of Vent and Drain O Assemblies I i t 0143d/005-8 4-29
IX-52 Procedure for Removal of Weld Spatter and Arc , Strikes IX-55 Procedure for Disassembly and Re-assembly of Valves 1 IX-60 Thermocouple Attachment by the Capacitive Discharge Method IX-62 Procedure for Performing Reinforcement Calculations for Internal Pressure in Branch Connections IX-64 Control of Piping Spool Closures (ASME, Section III and ANSI B31.1) IX-69 Procedure for Acid Etch of Welds, Weld Boundaries (HAZ), and Base Metal X-4 Final Inspection X-5 Field Receiving Inspection Procedure X-10 Welding Surveillance Procedure X-ll Visual Examination - General Y.- 18 Field Welding Inspection X-20 Ultrasonic Thickness Measurement of Materials X-28 Procedure for Evaluation of Inspections XI-l Field Leak Testing, Hydrostatic and Pneumatic XI-3 Demineralized Water Control XII-2 Procedure for the Calibration of Tools, Measurements, and Test Equipment XIII-4 Cleaning Procedure XIII-5 Field Storage Procedure l l XIII-9 Field Rigging and Handling of Materials and Equipment XV-2 Procedure for Handling Nonconformances (Field) l XV-3 Reporting of Defects and Noncompliance to the NRC (10 CFR 21) XV- 4 Hold Tag Usage O 0143d/005-8 4-30 1
XVI-l Procedure for Assigning Cause and Trending Codes to DRs XVI-2 Corrective Action Procedure XVII-1 Field Quality Assurance Records Procedure XVIII-l Internal Auditing Procedures of Field QA Programs by the Quality Engineering Group XVIII-4 QA Internal Audit Procedure GWS-III/I General Welding Standard 4.4.2.1.2 Pullman Power Products Document Control Portions of PPP Project Procedures III-3, III-4, VI-1, VI-5. and VI-6 establish the drawing and design control required by sections III and VI of the PPP QAM. These procedures involve documents which generally fall under the following categories: o Owner-supplied documents, which include piping Mylars, specifications, Design Change Notices, approved Field Change Requests (FCRs), and vendor instructions. These O- documents are distributed to the PPP Main Document Control Department by the GPC Document Control Department. l o The PPP document control supervisor is responsible for l controlling the receipt, maintenance, and distribution l of these documents. The main drawing control clerk (MDCC) receives these documents and records the information on a Drawing Control Card (PPP QAM Form 14) which is completed per PPP Project Procedure III-4. Owner-supplied documents are distributed by the MDCC l using a transmittal (PPP QAM form 15) which is completed per PPP Project Procedure III-4. This distribution is also noted on the Drawing Control Card (PPP QAM Form 14). There have been no changes in the procedure for processing superseded or voided documents since the Unit 1 assessment. The field drawing control rupervisor or his designee provides drawings to the craftsmen and is responsible for maintaining control of the drawings at the work station. Voided drawings are not permitted at the work station. o PPP-generated documents include the PPP QAM, the Project r') k/ Procedures Manual, drawings, requisitions, and process sheets. There has been no change in the initiation and i 0143d/005-8 4-31
distribution of these documents except that the Quality Assurance (QA) manager shares responsibility for initiating the manuals with the Quality Engineering Group. PPP field-initiated documents are the responsibility of the chief field engineer or the QA manager for maintenance, indexing, and distribution. The chief field engineer is responsible for:
- Field drawings (including FCRs).
- Stop Work Orders. l
- Field requisitions.
- Process sheets (in-process).
- Drawing records.
o The field QA manager is responsible for:
- Project procedures.
- Nonconformance Reports.
- Process sheets.
- Site instructions.
After approval, process sheets are controlled by logging them on the Package Index Sheet (Attachment 2 of PPP Project Procedure VI-5). The package is controlled via log books maintained in each area. Return of superseded process sheets and issue of new process sheets are both documented on the Package Index Sheet. The issue of process sheets from the Weld Material Distribution Center (WMDC) to the craft is documented on the package log books. These field-issued process sheets must be returned to Field Document Control Centers at the end of each shift. Completed process sheets are transmitted to the QA Department using the Process Sheet Transmittal (Attachment 6 of PPP Project Procedure VI-5). 4.4.2.1.3 Preparation of Documents The Project Procedures Manual, installation drawings, and process sheets are the three principal documents used by PPP for site fabrication, installation, inspection, and testing of piping and equipment. Their preparation is described as follows: o PPP Project Procedures Manual was developed, approved, revised, and distributed in accordance with sections 2.4, 3.4, 5.2, 6.2. 6.4.6, and 6.4.7 of the PPP QAM. There has been no change in the manner in which the project procedures are revised and distributed since the Unit 1 assessment. O 0143d/005-8 4-32
l r I o Isometric drawings are used for piping insta.llation. " The original piping isometric Mylars (K-series, PPP QAM O- form 7B) are aupplied by BWPC Engineering with the exception of small-bore, field-routed, ASME Class 2 and 3 syntems. BWPC issues orthographics to GPC Document ; Control. These orthographics are used for the i preparation of isometrics at the jobsite for small-bore field-routed systems. The isometrics are prepared by the Vogtle-Structural Analysis Mobile Unit as J-series isometrics which.are then submitted to GPC Document 3 Control for distribution. PPP Project Procedure III-4 controls PPP preparation of, and revision to, installation drawings. l The PPP MDCC is responsible for storing and maintaining all original Mylar isometric drawings and SK-Q sketches. When new documents are received, it is the ! PPP chief field engineer's responsibility to review them and initiate Stop Work Orders for superseded drawings in accordance with PPP Project Procedure III-3 when required. ' BWPC may prepare and issue revised piping isometric Mylars through GPC Document Control; however, the preparation or drafting of the majority of isometric revisions is completed by the PPP Engineering Drafting Department at the jobsite. The PPP drafting department
.() clerk obtains the original Mylar drawings from the MDCC by means of a routing slip (Form SF3.5 of PPP Project Procedure III-4) when revisions are' required to be made. Revisions to the original piping isometric Mylar are made to add supplementary information required for l installation and/or to incorporate one or more of the ;
following documents: '
- Design Change Notice (DCN) - issued by BWPC Project Engineering.
- FCR - initiated by BWPC Project Engineering, PPP engineering, or GPC Engineering. Approval by BWPC Project Engineering is required before implementing a drawing revision.
- Construction Specification Change Notice - issued by BWPC.
- Deviation Report (DR) - initiated by GPC or PPP. An approved disposition by BWPC Project Engsneering is required prior to implementing a drawing revision.
, - Field Engineering Drawing Change Request - initiated by PPP Field Engineering and does not deviate from
() design requirements. Approval of the PPP chief field 0143d/005-8 4-33
engineer or designee is required before implementing a drawing revision. Installer notes are added to the drawing by the PPP Engineering Drafting Department. When the piping isometric does not have sufficient detail for field installations, PPP Engineering may prepare an SK-Q sketch (Form 7C of the PPP QAM) to provide the additional detail required. For safety-related piping, the PPP QA Department is required to review and approve SK-Q sketches. For nonsafety-related piping, only PPP engineering approval is required. When revising drawings and SK-Q sketches, the PPP drafting department clerk obtains the original Mylar from the PPP MDCC. The revision is made by the PPP Drafting Department and approval of the revision is the same as that required for the original issue. After the revision is approved, the drafting department clerk returns the original Mylar drawing to the PPP MDCC for processing. o The PPP QA program utilizes process sheets for installation activities. Process sheets outline the planned sequence of operations necessary to perform a specific work activity. They provide reference to special processes (e.g., the applicable procedures, including revision), accept / reject criteria, and status h signoff by the PPP QC/QA inspector and the authorized nuclear inspector (ANI). There have been no changes in the procedure for preparing, reviewing, revising and approving these process sheets since the Unit 1 assessment. They are also issued and controlled in the same manner as for Unit 1 except that the return of a superseded sheet and issuance of a new sheet is documented on the Package Index Sheet instead of the Isometric Package Review Checklist and that they are stored in the Field Document Control Center when not being used by the craft or QC personnel. 4.4.2.1.4 Work Preparation The PPP construction superintendent is responsible for coordinating site fabrication and installation activities for piping and equipment to support the project schedules. There have been no changes since the Unit 1 assessment in the duties of the personnel reporting to him, including area managers, craft superintendents, and craftsmen. O 0143d/005-8 4-34
- -- . - ~ ~ . - -. . . - _ _ - . .= , -
i I 4.4.2.2 Installation Activities O 4.4.2.2.1 General Requirements t Craftsmen perform the physical work activities under the i technical direction of craft superintendents and field i engineers. The primary documents used by the craftsmen are piping drawings and process sheets. The process sheets specify work activities, sequence, procedural references, and inspection hold points. Craftsmen notify the QC inspector when a hold ' point is reached, and inspections are performed in accordance with, and documented on, the process sheet. Once inspections are completed, the inspector notifies the ANI of corresponding hold points for ASME B&PV Code, Section III, installations. 4.4.2.2.2 Fitting and Alignment l Pitting and alignment activities are conducted in the following manner- - o Once an item is properly prepared, the craftsman notifies the QC inspector of the required hold point. j The QC inspector performs the required inspections in O accordance with PPP Project Procedure X-18 using Attachment G. Pipe Weld Inspection Check List. ; o Piping systems, erection sequence, and closure points ' are derived through coordination between BWPC l Installation Engineering (IE) and PPP Field Engineering as described in PPP Project Procedure IX-64. Once determined, the erection sequence and closure point, as applicable, are noted on the drawing. PPP Field Engineering evaluates and performs closure inspections and records the closure inspection results for each closure point on Attachment A to PPP Project Procedure IX-64, which is then routed to IE for evaluation. Project Engineering evaluates misfit measurements in accordance with Construction Specification AX4AZ01. There have been no changes since the Unit 1 assessment in the way field verified closure misfits are evaluated, piping is reworked, or a misfit is accepted. After the piping, materials, or components are placed in , position, the craftsmen install temporary supports to restrain movement. There has been no change since the Unit 1 assessment : in the.way temporary supports are handled when they involve , welding-to-pressure boundaries 0143d/005-8 4-35
4.4.2.2.3 Mechanical Joints Bolting verification process sheets are required for all work on h ASME B&PV Code, Section III, installations. The required bolting material, gasket type, and recommended torque are entered on these sheets by PPP Engineering. Hold / observation points are entered on these sheets by the designated QA engineer and/or ANI during his review. The field OC inspector verifies the correct bolting material per the process sheet and records the heat numbers / heat codes. He also records any in-line component serial number or heat number (e.g., orifice plates, valves, etc.). When bolting up to an ASME valve, he verifies the valve's serial number and mark number against the Piping Material Requisition. He records these numbers, and the heat number of random materials such as blind flanges, at the time of joint makeup. The field engineer inspects bolted connections prior to torquing to ensure use of the correct gasket, that bolts are properly lubricated, and that flange alignment is acceptable. He then verifies that the recommended torquing sequence is used and that the recommended torque value is reached. 4.4.2.3. WELD FILLER METAL CONTROL This section describes PPP control of weld filler material at h the issuance to the welder, and while in the possession of the welder. o Welding material is handled and stored in a manner that prevents contact with dirt, dust, grease, moisture, or other contaminants. The WMDC is a level B storage area. Specific types of storage and controls for weld filler materials at the WMDC are outlined in PPP Project Procedure VIII-3. o Field issuance of weld filler materials to the welder is controlled through the use of the Weld Rod Stores Requisition (Form 25). The craft foreman prepares a ' Weld Rod Stores Requisition in accordance with the isometric or piping detail. It is then submitted to the WMDC where it is reviewed for accuracy and completeness by the OA engineer (WMDC). Once the requisition has been reviewed, the welder submits it to the rod room attendant where the quantity, type, and size of weld j material specified on the requisition is issued and the correct log, heat, or control number of weld filler materials is recorded on the requisition. The PPP ! engineer verifies that the welder is qualified to make i the weld. The welder retains the Weld Rod Stores ! Requisition and process sheet while welding. h 0143d/005-8 4-36
. . . . - _ - - - -. - - . .-= -. l Low hydrogen electrodes are issued in portable electrode : O holding ovens which are assigned to each welder. Portable electrode holding ovens and unused welding materials not in ovens are returned to the WMDC at the l end of each daily shift or upon completion of the weld, whichever occurs first. Weld filler materials, portable ; ovens, and rod requisitions are redistributed to the welder daily. : 4.4.2.4 Weldino/ Nondestructive Examination l I 4.4.2.4.1 In-process and Final Inspections The in-process and final inspection requirements for pipe welded in accordance with the ASME B&PV Code or the American National ' Standards Institute Power Piping Code. B31.1, under the PPP scope of work, are described below: o PPP has an established welding surveillance program as described in PPP Project Procedure X-10, Welding l Surveillance Procedure. The QA manager assures program ' implementation through QC inspectors. QC inspectors randomly surveil welders during the welding process as an ongoing activity. O performed and documented in accordance with PPP Project Procedure X-10 and Attachment 1, Welding Surveillance Inspections are Record. If a welder is found welding outside the-parametersHof the applicable welding procedure specification (WPS), the responsible foreman and welder are notified and the problem is corrected. The corrective action taken is recorded in the comment section of the Welding Surveillance Record and the , completed form is forwarded to the QC supervisor. The , corrective action taken is reviewed and, if found t unacceptable, a DR is initiated, as per PPP Project Procedure XV-2. The QC supervisor performs a monthly review of all Welding Surveillance Records generated during the month i to detect any trends. When a trend is detected, a i written report is submitted to the QA manager for further action as required by PPP Project Procedure X-10. j o Final weld inspections are performed by PPP QC inspectors as required by PPP Project Procedures IX-3, ; IX-15, and X-18. PPP Project Procedure X-18 instructs and guides inspectors in weld inspection activities. Visual inspections are performed in accordance with PPP Project Procedure X-18. Welders are responnible for ( assuring that their welds are complete and meet the-0143d/005-8 4-37 _j
requirements of (PPP) GWS-III/1, applicable welding procedure specifications, and any other requirements indicated by the craft superintendent or on the process sheet. For safety-related welds the welder verbally g notifies the QC inspector that the weld is completed. Upon notification, the QC inspector evaluates conformance to the final inspection requirements by following the guidelines of PPP Project Procedure X-18. The contents of Project Procedure X-18 define the acceptance criteria. The procedure provides the inspector with the description, technical requirements, and/or reference to a technical procedure (s). These guidelines are followed to assure that the final weld conforms to codes, specifications, and procedure requirements, including surface preparation requirements of the applicable nondestructive examination (NDE) procedures. The inspector documents inspection results on the process sheet for ASME B&PV Code welds and on the weld inspection record for other welds. The process sheet or weld inspection record is routed to the PPP Engineering Group, who reviews it for completion status and determines whether NDE and/or postweld heat treatment (PWHT) is required. If NDE and/or PWHT is required, the appropriate supervisor is responsible for scheduling the required NDE and/or PWHT. The original process g sheet or Weld Inspection Record is filed at the Field W Document Control Centers to await NDE acceptance and further processing. 4.4.2.4.2 Nondestructive Examination Acceptance PPP ic responsible for performing NDE. PPP has an internal l group that performs the examinations (QC/NDE Group). A report j is issued for each examination performed in accordance with the I applicable NDE procedure. The item examined, method of examination, and examination results (accept or reject) are recorded on attachment 4 (Daily NDE Report) to SI-26 (Site Instruction for Initiation and Control of Repair Process Sheets and Repair Orders). The completed NDE report is forwarded to the QA Department in accordance with Project Procedure VI-5. Upon receipt of the completed NDE report verifying acceptance, the NDE technicians enter their initials and date of inspection on the process sheet for ASME items, or on the weld inspection record for B31.1 items. The NDE report and original process sheets are stored in j the QA vault for later processing. G 0143d/005-8 4-38 l
[ If an NDE examination indicates the need for repair, the QC/NDE O Group issues a repair order. The repair order and rejected NDE , report are prepared and issued to the field, in accordance with ' Procedures VI-5 and SI-26. A new process sheet is then generated and issued for reworking the rejected weld. 4.4.2.4.3 Defect Removal and Repair by Welding ! i Defect removal, weld repair of the removal area, and weld repair of end preps are performed and controlled in accordance with PPP Project Procedure IX-14, Defect Removal and Repair by Welding, ' IX-52, Removal of Weld Splatter and Arc Strikes, and SI-26. The PPP field process engineer prepares a weld process sheet (repair) using technical requirements from PPP Project Procedure IX-14. The actual weld operation, inspection, and documentation follow the same procedure as the original weld with the exception that the PPP QC inspector performs wall thickness verification inspection of the removal and/or repair area in accordance with PPP Project procedure X-20, Ultrasonic Thickness ' Measurement of Materials. The QC inspector records the results . on Attachment 1 to PPP Project Procedure X-20 to provide ' documented evidence that section thickness requirements have been satisfied. 4.4.2.5. Post Weld Heat Treatment The PPP Project Procedures used in conjunction with the PWHT process are IX-43, GWS-III/1, and the applicable WPS. , Electrical resistance heating is the primary method used at VEGP ' for PWHT. The chief engineer or his designee determines the heat treatment { requirements and implements them through the use of process ) sheets as required by PPP Project Procedure IX-43. The craft superintendent assigns craft personnel knowledgeable in PWHT requirements, who set up the heat treating equipment (thermocouples, wiring, wrappers, temperature recorder / power source, etc.) to perform the PWHT operation. The operator assures that setup and heating operations are in accordance with PPP Project Procedure IX-43 and the applicable WPS. When the PWHT is completed, the operator applies a PWHT stamp [ Attachment 2, Pullman Power Products (PWHT) Temperature Record) and fills in the blocks as required by PPP Project procedure IX-43. A log (Attachment 1 of PPP Project Procedure IX-43) of all heat treatments performed with electrical resistance heat is retained in the WMDC. During a given operation, the operator maintains a usage log for each piece of heat treatment equipment used in accordance with PPP Project Procedure IX-43. O 0143d/005-8 4-39
PPP Project Procedure IX-43 requires the QC inspector to inspect the PWHT setup prior to heating, and to verify that the setup is in compliance with the requirements. The QC inspector reviews the PWHT log and temperature record for proper entries, and upon acceptance, initials and dates both documents. When the heat treatment operation is completed, the temperature recording chart, forms, and process sheet are turned over to the WMDC quality assurance engineer for transmittal to the QA Department for review and filing (except for the heat treatment log). Upon review by the QA engineer in accordance with SI-24 (QA Documentation and Review of PNHT Operations), the heat treat file is placed in the vault. 4.4.2.6 Mechanical Equipment Installation 4.4.2.6.1 Foundation Release All equipment installed by PPP is controlled by using equipment installation process sheets in accordance with PPP Project Procedure 1X-48. 4.4.2.6.2 Equipment Setting The setting of system-associated equipment in safety-related systems is performed by Pullman Power Products per PPP Project Procedures IX-1 and IX-48. As delineated in section 4.2 of this module, GPC procures and receives all equipment and associated materials on site. PPP requisitions material from the GPC warehouse for use in their installation activities, as discussed in section 4.3 of this module. Upon completion of the above activities, the PPP equipment field engineer checks the equipment foundation for anchor bolt configuration, length, and size, and ensures that the bolts and sleeves (if used) are cleaned in accordance with PPP Project Procedures IX-40 and IX-1. There have been no changes in equipment setting and other foundation preparation procedures since the Unit 1 assessment. After the grout has cured (discussed in Module 1), the anchor bolts are tightened / torqued to the full specified value. Rotational alignment checks and verification of internal cleanliness, are carried out in the same manner as was done for Unit 1. O 0143d/005-8 4-40
4.4.2.7. System Connection and Final Alignment () Connection of system piping is described in section 4.4.2.2.3. Torquing of threaded fasteners on equipment, as well as flanged connections to systems, is performed in accordance with PPP Project Procedure IX-5, Installation of Threaded Fasteners, and the manufacturer's instructions. Procedures for disassembly and re-assembly of equipment, completion of piping connections, hydrostatic testing of connected piping, and final alignment of rotating equipment remain the same as for Unit 1. 4.4.2.8 Hydrostatic and Pneumatic Testing PPP Project Procedure XI-l is used during hydrostatic or pneumatic pressure tests to meet the requirements of the ASME B&PV Code, Section III, Division 1, ASME B&PV Code, Section I, the ANSI Power Piping Code, B31.1, or the National Fire Protection Code. 4.1.2.9 Preparation of Data Reports and Application of Code Stamps In response to the requirements of the ASME B&PV Code, PPP () prepares a series of partial ASME N-5 partial data reports for each piping system. These reports are scoped and prepared per PPP Project Procedure X-21 using as-built drawings, walkdown checklists, pressure test reports, and documentation status forms generated by procedures III-4, X-4, XI-1, and XVII-5. These lead to a master or system N-5 which encompasses all of the partial data reports. Any errors or deficiencies noted in reviews of these N-5 data reports and associated documentation are identified to and corrected by PPP with DRs written as needed. Upon satisfactory review of the final (system) N-5, the, N-certificate holder (BWPC) and ANI certify the system N-5 and participate in installation of the NA-nameplate per PPP Project Procedure X-21. The completed packages of N-5 data reports are transmitted to GPC Nuclear Operations for permanent retention and are utilized in preparation of the Form N-3, Owner's Data Reports. Where ASME B&PV Code, Section III, piping subassemblies are fabricated on site by PPP for use by others, they will be documented by a NPP-1 Data Report, as detailed in Attachment 1 of PPP Project Procedure X-21. This is reviewed by the responsible QA engineer against the as-built isometric. His acceptance is documented on the Package Index Status Form per 0143d/005-8 4-41
PPP Project Procedure XVII-5 and the NPP-1 Data Report, and associated documentation is then presented to the ANI for review and approval. 4.4.3 GPC NUCLEAR CONSTRUCTION TEAM ACTIVITIES 4.4.3.1 Prerequisites 4.4.3.1.1 Georgia Power Company Field Procedures These field procedures are established for GPC activities related to the fabrication, installation, modification, repair or replacement of permanent plant facilities. They define the extent of field engineering, QA/QC, and Construction supervision participation, including that of the NCT, for ASME B&PV Code, Section III, activities. GPC field procedure FP-N-101 provides instructions for the preparation, review and approval, revision, control, and distribution of these Field Procedures. 4.4.3.1.2 Document Preparation and Control Documents are prepared and controlled as follows: o Controlled design documents, including drawings and specifications, are furnished by BWPC. GPC Field Procedure FP-N-101.2 establishes measures for the review and control of these documents. i o Work packages are used to control and document the ASME B&PV Code, Section III, work, and may also be used for work performed in accordance with other codes when directed by the mechanical discipline manager (MDM). These packages are prepared, processed, controlled, and revised in accordance with GPC Field Procedure FP-N-101.3. A work package will always include the document list and installation drawings. It will also include DCNs, bills of material, weld records (WR-5, WR-5A), construction I plans, inspection reports, and DRs if these documents l are created. Documents such as field-generated l (as-built) drawings, NDE reports, and other pertinent documents may be included. Weld records, construction l Plans, inspection reports, and DRs are removed from the I work package by the QC inspector, and processed in I accordance with field procedures, on completion of their ! respective phases of the work. 0143d/005-8 4-42
o A construction plan is used when directed by a field q procedure or for work operations not adequately covered s by existing field procedures. Typical uses for a construction plan are to implement complex DR dispositions, investigate industry-related problems, set mechanical equipment, handle a complex valve disassembly /re-assembly and act as a shop traveler for pipe spool fabrication. Construction plans are always used for non-welding activities. A construction plan is essentially a checklist of characteristics to be examined and/or actions to be performed, as described in GPC Field Procedure FP-N-101.1. It is prepared from project documents such as procurement specifications, construction specifications, drawings, vendor instruction manuals, industry codes and standards, and/or other GPC ASME B&PV Code, Section III-related field procedures. 4.4.3.2 Cuttino. Bending. Fittino, and Alionment 4.4.3.2.1 Piping Installation Requirements for fabrication, installation, inspection, and (^) documentation of piping materials, subassemblies, components, x_j parts, and/or appurtenances in accordance with the ASME B&PV ! Code, Section III, 1977 Edition through the Winter 1977 Addenda, are stipulated in GPC Field Procedure FP-N-130. This procedure l requires piping to be installed in accordance with VEGP Construction Specification X4AZOl, and other approved l engineering design and installation documents as listed in the : applicable work package. In addition, it calls for other work l to be performed in accordance with the following field procedures: Activity Field Procedure No. Change requiring an FCR DC-A-03 i Attachment and removal of ASME nameplate FP-N-101.1 l Cold bending of piping FP-N-132 Field adjustment of piping by thermal methods FP-N-130.8 Control of tools used on austenitic stainless steel FP-N-ll2 0143d/005-0 4-43
Preparation of a DR for any material or components that do not conform to applicable revisions of engineering drawings, piping isometrics and/or specifications FP-N-116 Welding documentation FP-N-120.1 Protective coating and wrapping FP-N-130 Attachment 130-A Disassembly and re-assembly of valves FP-N-130 Attachment 130-B Fabrication of ASME B&PV Code, Section FP-N-130 III, NPT-stamped spools Attachment 130-C Bolting of ASME B&PV Code, Section III, FP-N-130 mechanical joints Attachment 130-D Maintenance of piping cleanliness FP-N-133 Pressure testing FP-N-130.4 Documentation of as-built information FP-N-130 Attachment 130-E Inspection for physical damage FP-N-120.5 h Specific instructions are given in the body of Field Procedure FP-N-130 for the maintenance of heat number identification on cut lengths of pipe, installation of manual and control valves, documentation of piping cleanliness prior to flange bolt-up, guidelines for craft installation work, and field engineer verifications and OC inspections works. 4.4.3.2.2 Thermal Pipe Adjustment Field Procedure FP-N-130.8 establishes the method to be used for thermal adjustment of piping for proper alignment during field installation. This procedure is only applicable to carbon steel pipe materials listed in ASME B&PV Code, Section IX. This procedure details the method to be used for heating the pipe and lists all the steps necessary for adjusting the line or spool alignment and documenting the activity. 4.4.3.2.3 Cold Bending of Small Bore Pipe Field Procedure FP-N-132 establishes the requirements for cold bending of two-inch and smaller ASME B&PV Code, Section III, or 9 0143d/005-8 4-44
ANSI D31.1 piping. This procedure is used for bending carbon, low alloy, or austenitic stainless steel pipe. 4.4.3.2.4 Alignment of Mechanical Equipment Alignment of mechanical equipment is addressed in Field Procedure FP-N-150. This procedure contains requirements for obtaining an Equipment Foundation Release, setting equipment on the foundation in accordance with established centerlines and benchmarks, locating equipment as shown on location drawings, shimming, and aligning rotating equipment. 4.4.3.2.5 Welding Filler Material Control Field Procedure FP-N-120 establishes requirements for the control of storage, issuance, and return of welding filler material. It requires the procurement, receipt, storage, and issuance of all welding filler material to meet the requirements of Bill of Material X4AQ37, Welding Filler Materials for Nuclear Service, FP-N-106 Issuing Material / Component, and FP-N-114, Storage of Material and Components. In the body of this procedure, storage and issue areas are described, metlods of storage and handling are specified, rules for the issue of filler material are stipulated, means of field control are described, and rules for the return of unused filler material O and stubs are specified. 4.4.3.2.6 Installation and Removal of Temporary Attachments 1 Field Procedure FP-N-120.4 describes requirements for installation and removal of temporary attachments on ASME B&PV Code, Section III, components. This procedure describes the conditions under which such attachments may be welded to the component material but leaves the selection of the WPS to the project welding supervisor or his designee. It also requires that the attachment location be documented on the Construction Plan, WR-5, or WR-5A, as applicable. Removal of the temporary attachments is accomplished by grinding or thermal cutting, and the removal area is to be examined by magnetic particle or liquid penetrant methods for ASME III Class 1 and 2 components and the results documented. O 0143d/005-8 4-45 i
4.4.3.3 Weldina/ Nondestructive Examination 4.4.3.3.1 General Welding Standard for ASME Code Applications O Field Procedure FP-N-120.6, is used in conjunction with the applicable WPS and Procedure Qualification Record contained in the GPC Nuclear Construction Welding Manual. It stipulates that the welding processes or combination of welding processes to be used shall be as specified in the applicable WPS. It controls the use of base materials, foreign materials on austenitic stainless steel, weld filler materials, backing materials, and miscellaneous welding materials such as electrodes for gas tungsten-arc welding. It describes the steps to be followed for preparing the base material prior to welding, thermal cutting or gouging, use of shielding and backing (purge) gases, preheat and interpass temperatures required, and process parameters to be used. General welding requirements outlined in this procedure include process restrictions and methods to be used for completing a weld. Procedures concerning weld interruptions and performance of in-process rework are also described in this specification. Reference is also made to post weld heat treatment which is covered by Field Procedure FP-N-120.3, and welder and/or welding operator performance qualification which is specified in Vogtle Field Procedure WG-T-02 and Sections III and IX of the ASME Code. O 4.4.3.3.2 Control of Purging and Purging Dams When an internal gas purge is required by a welding procedure specification or engineering specification, Field Procedure FP-N-120.7 is used to provide instructions for the control of purging and purging dams. 4.4.3.3.3 Inspection of Piping Installation Field procedure FP-N-130 contains inspection instructions required to complete the Insnection Report for Pipe Line Installation. Exhibit 130-1. which is a comprehensive documentation of inspection activities on piping installations. These instructions specify tLat the field engineer (FE) or quality control inspector (OCI) shall visually verify / inspect the installed line for general configuration conformance to the design drawings, that the piping is free from physical damage, that there are no signs of permanent deformation from rigging or temporary supports, that damaged coated and wrapped areas have been repaired, and that temporary attachments have been removed. This procedure also instructs the FE/QCI to visually verify / inspect valve location, mark number, plant tag numbers, pressure class, clearance for operation, and flow direction for h 0143d/005-8 4-46
conformance to the Valve Designation List, piping and instrumentation diagram and piping layout drawings. The FE/QCI .O also verifies / inspects other in-line components for general location, tagging, and conformance to piping layout and l isometric drawings. Finally, the FE/QCI visually verifies / inspects the installed line to determine field closure , completion, that the as-installed condition is within the i tolerances allowed in Construction Specification X4AZ01, Division P3, and that pipe-to-conduit separation has been ! maintained in accordance with Construction Specification X3AR01. 4.4.3.3.4 Nondestructive Examination ' Field Procedure FP-N-175 describes the method used for controlling NDE during fabrication and installation activities to meet the requirements of the ASME B&PV Code, Section III. ' This procedure requires that NDE be performed in accordance with the following field procedures: o QC-T-05, Visual Inspection. o QC-T-06, Magnetic Particle Inspection, o QC-T-07, Radiography Inspection. o QC-T-08, Liquid Penetrant Inspection. l o QC-T-09, Ultrasonic Inspection. 1 o QC-T-13, Thickness Measurement. ' The adequacy of these procedures is demonstrated to the satisfaction of the ANI prior to use and is documented on the test report. This procedure describes the duties of the QCI who is responsible for performing NDE and documenting the results. All GPC personnel performing NDE are certified in accordance with Field Procedure QC-A-03 with copies of the qualification records maintained at the jobsite. Radiography (RT) is performed by NDE subcontractor personnel; however, all RT film and reader sheets are reviewed for final ' acceptance by a GPC Level II or III RT inspector. These are-also made available to the ANI for review. NDE services and subsequent documentation are requested in a step-by-step procedure detailed in section 3.0 of Field Procedure FP-N-175. O 0143d/005-8 4_47
s 4.4.3.3.5 Elimination of Defects Field Procedure FP-N-120.5 establishes the method for evaluating and eliminating surface damage and defects on ASME B&PV Code, Section III, material and components. This procedure covers repairs to mechanical damage, arc strikes and material defects, but does not address repairs, rework or modification of N-stamped components. The identification and removal of arc strikes, weld spatter, and mechanical damage is documented on a Surface Condition Inspection Report (SCIR), but minor surface damage (which is defined in Field Procedure FP-N-120.5) may be corrected and need not be documented. Steps for processing the SCIR are included in this procedure. This procedure describes various methods of making repairs, including blending with emory cloth, steel wool, fine file, or a grinder. Repairs by welding may be made, but a WR-5 must be prepared and the work must be performed in accordance with a WPS assigned by the project welding supervisor. Following the removal of defects, an examination is made in accordance with this procedure. 4.4.3.3.6 Postweld Heat Treatment Field Procedure FP-N-120.3 specifies detailed requirements for performing the local PWHT of field welds. These requirements are in accordance with ASME B&PV Code, Section III, 1977 Edition through Winter 1977 Addenda. This procedure specifies width of the heated area, the heating and cooling rate, the heat treatment temperature and time cycle, measures to be taken for interrupted PWHT, temperature control, means of recording the PWHT cycle, the application of thermal insulation, and documentation of the process. Field Procedure FP-N-120.2 is used for attaching thermocouples to ASME B&PV Code, Section III, components using the capacitor discharge method. This procedure specifies the materials to be used for controlling and recording PWHT and describes the steps to be taken for attaching and removing the thermocouples and their leads. 4.4.3.4 Mechanical Equipment Installation Field Procedure FP-N-150 is used for installing mechanical equipment in accordance with Construction Specification X4AZOl, division P6. 4.4.3.4.1 Pre-installation Requirements This procedure requires the FE to obtain a copy of the Equipment Foundation Release, to check the foundation drawings, to verify 0143d/005-8 4-48
anchor bolt details, and to see that anchor bolts are cleaned and sleeves blown out with compressed air. b(~N 4.4.3.4'.2 Installation Requirements Field Procedure FP-N-150 requires that installation of equipment be accomplished with a construction plan, that loose personal l items be removed from the vicinity before starting the work, that equipment is set on the foundation in accordance with , centerlines and benchmarks provided by the owner, that the l location of the equipment be as specified on the drawings, that ' nozzle elevations be compared with the piping isometrics, that l slide plates are properly greased, and that baseplates and/or soleplates are set level within 0.002 inch per foot unless specified otherwise. This procedure also specifies the shimming i requirements and methods of securing equipment to the anchor bolts. 4.4.3.4.3 Alignment of Rotating Equipment Rotating equipment is aligned in accordance with Field Procedure FP-N-150 and the manufacturer's instructions. The alignment is verified prior to grouting (alignment check A), and after grouting and anchor bolt tightening (alignment check B). The alignment of rotating equipment with flanged piping connections C,g) is verified during bolt up (alignment check C) and after hydrotest (alignment check D). The alignment of rotating equipment with welded piping connections is monitored during welding (alignment check C) and verified after hydrotest (alignment check D). 4.4.3.5 Hydrostatic and Pneumatic Testing Field Procedure FP-N-130.4 establishes the requirements for performing, inspecting, and documenting pressure tests of piping systems in accordance with ASME B&PV Code, Section III, 1977 Edition through Winter 1977 Addenda. This procedure describes the steps to be taken in preparation for testing and the contents of the pressure test record. It also includes the process of verifying pressure gage calibration and for checking the relief valve setting prior to each test. The procedure lists requirements and limitations for conducting hydrostatic and or pneumatic tests and describes the procedures on Exhibits 130.4-6 and 130.4-7, respectively. O 0143d/005-8 4_.49
4.4.3.6 Control and Application of Code Stamps 4.4.3.6.1 Preparation of N-5 Code Data Report and Placement of e NA-Code Nameplate Field Procedure FP-N-109.1 provides specific instructions for preparation of the ASME Form N-5, Data Report for Field Installation or Shop Assembly of Nuclear Power Plant Components, Component Supports, and Appurtenances. It also contains the requirements for the selection, stamping, and placement of the appropriate code data nameplate. The MDM or a designee is responsible for preparation and certification of N-5 forms in accordance with the instructions given in this procedure. BWPC, the N-certificate holder, is responsible for certifying the design for piping system installation, and the ANI is responsible for providing the Certificate of Inspection information on the N-5 form. The Document Review Section under the direction of the manager of quality control, is responsible for compilation of the N-5 Data Package, which supports the N-5 form. Field procedure FP-N-109.3 provides a description of these activities. 4.4.3.6.2 Preparat$0n of the NPP-1 Form for ASME III Piping i Sub-assemblies Field Procedure FP-N-109.2 provides instructions for the h preparation of the NPP-1 Code Data Report forms for piping l subassemblies that are to be stamped. The MDM is responsible for the preparation of these forms and for coordination with the DRs in accordance with Field Procedures FP-N-109.1 and FP-N-109.3 to assure material traceability and retrievability. Complete instructions for the preparation of the NPP-1 form are given in Field Procedure FP-N-109.2. Piping subassemblies requiring rework after completion of the original NPP-1 form shall be cause to initiate a new NPP-1 form or shall be documented in the N-5 Data Package. l 9 0143d/005-8 4-50
TABLE 4-1 ( APPLICABLE INTERDISCIPLINE DESIGN CRITERIA FOR ASME SECTION III, CLASS 1, 2, AND 3 MECHANICAL EQUIPMENT. PIPING, AND COMPONENTS Design , Criteria Date of Designation Initial current Number Issue Revision _ Date Title DC-1001 01/24/78 1 04/25/86 Separation (DMCN 1001-2) DC-1002 12/20/77 2 01/05/83 Fire (DMCN 1002-1) J l DC-1003 01/12/78 2 04/28/87 Flooding (DMCN 1003-6) ; DC-1004 08/14/78 3 06/05/86 Tornado (DMCN 1004-2) ; 1 DC-1005 03/10/80 1 07/28/87 Seismic l (DMCN 1005-10) DC-1006 12/19/77 2 02/26/86 Missile () (DMCN 1006-3) DC-1007 06/06/79 6 03/24/86 Environment DC-1009 03/23/77 2 10/21/86 Single Failure (DMCN 1009-2) Criteria DC-1010 08/04/78 5 02/18/87 Project (DMCN 1010-3) Classification List DC-10ll 05/27/77 1 10/11/83 Inservice (DMCN 1011-4) Inspection DC-1014 01/08/79 1 05/02/83 ALARA DC-1018 12/13/77 2 01/02/87 Pipe Break Criteria ; (DMCN 1018-15) j 1 I i (::) l 0144d/356-7/1
f~h '\ O L k 1ABLE 4-2 MECilANICAL SYSILMS DESIGN CRITERI A (SilELT I 0F 5) BALANCE OF PLANT: lbsign Criteria Date of Designation initial Current Number issue Revision Date Title Safety-Related Equirrent DC-1202 06-26-73 5 01-08-87 NUCLEAR SERVICE COOLING WATER (NSCW) NSCW punps and rnotors (DMCN -1202-5) SYSTEM NSCW transfer pumps and motors Contal wnent air coolers Containment auxiliary air coolers Containment cavi ty coolers Piping penetration area coolers Coolers for the motors of the following pumps: Centrifugal charging pumps Containment spray punps Residual heat removal punps Conponent cooling water pumps Safety injection pumps NSCW punps DC-1202-A 06-26-73 5 % 85 NUCLEAR SERVICE COOLING TOWERS Cooling tower fans and motors (DMCN-1202-A-2) DC-1203 ' 06-26-73 6 12-29-06 COMPONENT COOLING WATER (CCW) SYSTEM CCW surge tanks (DMCN-1203-4) CCW pumps and rnotors CCW heat exchangers DC-1217a 11-22-77 1 07-23-84 AUXILIARY COMPONENT COOLING WATER ACCW pump motors (DMCN-1217-3) (ACCW) SYSTEM ACCW heat exchangers DC-1218 04-01-74 4 04-11-84 AUXILIARY BUILDING FLOOO RETAINING Only ESF pump room isolation valves (DMCN-1218-2) ROOMS ALARMS. AND DRAINS are safety-related
O V J O V T ABLE 4-2 MECitANICAL SYSTEM DESIGN CRITERI A (SitEET 2 0F 5) BALANCE OF PLANT: (continuad) Design Criteria Date of Designation initial Current Number issue Revision Date Title Safety-Related Equipment DC-1228 05-05-80 0 12-24-86 REACTOR MAKEUP WATER STORAGE TANK (Equipment is not safety-related) (DMCN-1228-3) (RMWST) AND DEGASSIFIER SYSTEM DC-1301 05-14-73 5 08-20-85 MAIN STEAM SYSTEM Steam generator (shell side) (DMCN-1301 -i l) Steam diffuser Safety velves Atmospheric power operated relief valves Main steam isolation valves Main steam isolation valve bypass valvos Steam packing exhauster condenser DC-1302 05-14-73 5 01-22-87 AUXILIARY FEEDWATER SYSTEM (AFS) Auxiliary feedwater pumps and (DMCN-1302-IO) turbines Auxiliary feedwater pump and motors Auxillary feedwater turbine steam supply valves AFW turbine lube oil cooler DC-1305 05-11-73 4 04-19-85 CONDENSATE AND FEEDWATER SYSTEM Main feedline isolation valves (DMCN-1305-8) Feed inlet check valve Main feed regulating valves and bypass valves DC-1320 12-06-77 2 05-24-84 MAIN STEAM LINE AND FEEDWATER ISOLATION Main steam isolation valves and (DMCN-1320-3) SYSTEMS MSIV bypass valves Ol45d/356-7/2
~T (d
?*
f~ r I2 ! i 1 *5 IT 8 j $ is
'% e 82 v 0
'8 t'&2- =r[
E&
.5 EtE! I 8
I 4
.8 1:
E. b 2 .ei3"- 8:e gt E m e2*h s es:- t.?151$ p 5%i 4*8Eb th 'f ee .:j"
- u. u 4> .3 % $g "
- I: b b b
- IS Sri '
?* >.osa: t%%1""
t S,y *az-*2 12:: 2 2 2 e '*?
?!*
(c5' h ? 44 1 ke?EET A**** tee 8** 85* ?? E es a &5 5 t e>gw2233 3 3 ,j44832 ttt27
- m 8 8 8 e e !
- z d W -$ 5 5
e z E 5 W W W
~ t -
4 s*
~ 5 e i h o /^ d ; b 5 g p g g d s e - -
w g y & 5 g w 5 $ $ b G E 5 G $ d a 8 w e m a Baa e 3 a 5 2 s O E e 4 @ @ @ 9
% : 2 -
R e q n n = m 8
~ A 4 4 A
- t ? m S 8 ?
]. Ex --
o7 "7 7 ^7 , 5 5 h h h h s b -- 9 9 9 9 9 38 0 y $ K t j$"" d 8 8 d d b
- s ,
5 e2=u *
- ~ L - 8 8 *b2R ? m S 8 ? $
?1 7 7 7 7 7 n i S" a: 6 8 8 8 8 8 5 o
v/
O O O TABLE 4-2 MEOlANICAL SYSTEM DESIGN CRITERIA (SilEET 4 OF 5) BALANCE OF PLANT DICTATED BY NSSS REQUIREMENTS: Design Criteria Date of Designation initial Current Number issue Revision Date Title Safety-Related Equipment DC-2415 03-23-78 1 05-14-B6 CONTAINMENT ISOLATION SYSTEM isolation valves (DMCN-2415-2) DC-1204 03-18-79 2 12-05-85 SAFETY INJECTION SYSTEM (SIS) Accumulators (D'CN-1204-3) Safety injection pumps and motors Safety injection pump LO coolers DC-1205 12-13-77 2 03-21-85 RESIDUAL llEAT REMOVAL SYSTEM (RilRS) RilR pumps and motors (DMCN-1205-2) R!lR heat exchangers RilR pump seal coolers Emergency sump screen Encapsulation vessels DC-12% 01-06-78 2 07-23-84 CONTAINMENT SPRAY SYSTEM (CSS) Containment spray pumps and motors (CMCN-1206-2) Spray additive tank Spray eductors Encapsulation vessels Spray nozzles DC-1208 05-09-78 l 11-04-86 OIEMICAL AND VOLUME CONTROL SYSTEM Volume control tank (DMCN-1208-4) JCVCS) AND BORON RECYCLE SYSTEM (BRS) Boric acid storage tank Boric acid transfer pumps and motors Centrifugal charging pumps and motors Pos. Disp. charging pump and motor Centrifugal charging pump lube oil coolers OI45d/356-7/4
O O O 1ABLE 4-2 MEQlANICAL SYSTEM DESIGN CRITERIA (SIIEET 5 0F 5) BALANCE OF PLANT DICTATED BY NSSS REQUIREMENTS: (continued) Design Criteria Datr, of Designation Initial Current Number issue Revision Date Title Safety-Related Equipnent DC-1208 Regenerative heat exchanger (continued) Letdown heat exchanger (tube side) Excess letdown IlX (lube side) Seal water llX (tube side) Letdown reheat heat exchanger Moderating heat exchanger Letdown chiller llX (tube side) Reactor coolant filter housing Seal water return filter housing Boric acid filter Seal injection filter housings Positive displacement pump coolers Thennal regenerative domineralizers CVCS cation bed domineralizers Mixed bed demineralizers (Boron recycle holdup tanks shared with Unit f) DC-1213 09-16-77 2 01-24-85 SPENT FUEL COOLING SYSTEM (SFCS) AND SFP heat exchangers (DMCN-1213-3) PURIFICATION SYSTEM (SFPS) SFP pumps and motors
- a. System classified as having safety impact. All other listed are safety-related.
Ol45d/356-7/5
5 AUDITS AND INSPECTIONS O
5.1 INTRODUCTION
Section 5 of this module contains a listing of Quality Assurance (QA) audits, Nuclear Regulatory Commission inspections, and special evaluations performed in the area of mechanical equipment and piping. These design and/or construction audits were conducted by Georgia power Company, Southern Company Services, and Bechtel Western power Company QA personnel to provide assurance that design and construction activities conform to the requirements of 10 CFR 50, Appendix B, the project QA program, commitments defined in the Final Safety Analysis Report, and the Design Manual. The resulting findings or violations applicable to mechanical equipment and piping are listed at the end of this section. These findings were reviewed by the Readiness Review Team and factored into the assessments presented in section 6 of this module, as appropriate. O I Ol70d/006-8 5-1
a # _. . 2,2a.,.a -th_,s 6.a .__2 .- A..A _.. . - -*.- _m - a_-e.mm.ma h A Am.- em.,h_. , - A .ut-a.aa mn_._ O d O
)
i 1 ' O 0170d/006-8 5-2 i 1
5.2 PROJECT AUDITS () Project Quality Assurance (QA), consisting of Georgia Power Company (GPC) QA, and Bechtel Western Power Company (BWPC) QA, conducts regularly scheduled audits to verify compliance to project requirements. Any finding is reported to the management of the audited organization for corrective action. A listing of QA audits and findings addressing subjects within the scope of the module is presented as Table 5-1. The audits in this table were identified subsequent to the Unit 1 Module 4 report and prior to October 18, 1987. 5.2.1 GEORGIA POWER COMPANY AUDITS AND FINDINGS GPC QA audits are performed in functional areas such as mechanical equipment, piping, installation, etc., and are readily identifiable to module scopes. GPC QA conducted 31 audits related to the scope of this module. These audits resulted in 40 findings which identified discrepancies in documentation requirements, incidences of hardware nonconformance, and failure to follow procedures. For each finding, the extent and significance of the discrepancy was identified and corrective action was taken or is currently underway to resolve the deficiency. 5.2.2 BECHTEL WESTERN POWER CORPORATION AUDITS AND FINDINGS BWPC QA audits are generally performed in design functional areas such as drawings, calculations, Field Change Requests, and are applied to all disciplines, rather than a specific , discipline or hardware category. Therefore, it is generally , difficult to associate audits with a specific module: however, findings are easier to categorize by module. Seven findings l were related to the scope of this module. They identified i design and documentation deficiencies, failure to take actions in a timely manner, and failure to adequately track or complete i required actions. ; i l 1 l 0170d/006-8 5-3
i O O 4 0170d/006-8 S-4
I I 1 5.3 NUCLEAR REGULATORY COMMISSION INSPECTIONS 1 Readiness Review has identified 38 inspections conducted by the Nuclear Regulatory Commission (NRC) which are related to the scope of this module, as shown in Table 5-2. These inspections 1 resulted in 19 violations, 14 of which were identified as having ) a severity Level IV and four with Level V. One severity Level III violation resulted from an inspection conducted prior j to the Unit 1 Readiness Review assessment but was not listed in ' the Unit 1 report. This involved a contractor for which there j was perceived intimidation / harassment of quality control I inspectors. The violation was for insufficient organizational l freedom / control of services through effective audits. Seven violations were for failure to protect permanent plant equipment and material, one of which was a repeat of a previously identified violation (motor heaters not energized). Three i violations were for not providing adequate procedures or j acceptance criteria, and eight were for not following procedures or adequately performing the assigned task. Responses to these violations were submitted to the NRC and corrective actions are either completed or are still in progrecs. O l O Ol70d/006-8 5-5
=
0 0 0 4 01706/006-8 5-6
5.4 REPORTABLE AND POTENTIALLY REPORTABLE ITEMS Since completion of the Unit 1 Module 4 assessment. 12 conditions have been identified for which the Nuclear Regulatory Commission (NRC) has received noticca of potential reportability under the requirements of 1C CFR 50.55(e), as shcwn on Table 5-3. Ten of these were found to be reportable and the appropriate reports have been submitted to the NRC. Corrective actions have been completed on six of the deficiencies and are in progress for the remainder. L/ O 0170d/006-8 5-7
.A . _ ,
9 O O 0170d/006-8 5-8
i 5.5 UNIT 1 FINDING FOLLOWUP i The Unit 1 finding followup consisted of the identification of all the findings and corrective actions taken as a result of the
~
Unit 1 Readiness Review and Nuclear Regulatory Commission evaluation of module assessments. In Module 4, there were 60 Unit 1 findings which required corrective action by the Project. For Unit 2, a list of those findings, and the corresponding corrective actions, Table 5-4, was compiled and transmitted to the Project for verification that corrective action, if appropriate, continued to be implemented in Unit 2.
- The Project evaluated each finding to categorize the corrective actions as defined below:
- 1. The finding was an isolated occurrence in Unit 1 and did not require continuance of any action in Unit 2 (or was '
applicable to Unit 1 only). t i
~
- 2. Corrective action taken for Unit 1 remains in effect for Unit 2 without change. ,
- 3. Corrective action taken for Unit 1 has been eliminated .
or enhanced for Unit 2 as a result of program evolution.
- 4. Corrective action taken for Unit 1 has not been entirely effective in Unit 2 and additional corrective action is l required to prevent recurrence. I O The Project verified that 15 findings belonged to Category 1 and i
1 required no further action for Unit 2. Corrective action taken in Unit 1 was continued for Unit 2 on 42 findings, as defined by Category 2. The Project identified three Unit 1 findings described below where corrective actions taken in Unit 2 differed from those taken in Unit 1 for the same Readiness Review finding, as shown in Category 3: o RRF-004-045 (Level II). Unit 1 corrective actions, though implemented, were not clearly defined in GPC Field Procedures MD-T-19 and MD-T-20. These procedures are being revised for clarification. o RRF-004-059 (Level III). The Unit 1 corrective actions were modified to improve their efficacy by use of checklists during the inspections and final review of Pullman Power Products (PPP) process sheets. o RRF-004-063 (Level III). One of the Unit 1 corrective actions called for changes in responsibility of maintaining the Pullman Power Products (PPP) field engineers stick files of drawings. In the Unit 2 program, only the PPP Document Control Group maintains stick files. l Ol70d/006-8 5-9 1 l- - .. . - - . - _ . - - .
There were no cases in Module 4 where the Unit 1 corrective action was not entirely effective, as described in Category 4. The listing in Table 5-4 presents the above findings, a description of the corrective action taken for Unit 1, and the categorization of the Unit 2 action. Selected findings were included in the assessments discussed in section 6 to provide independent Readiness Review confirmation of the project evaluation results. O O Ol70d/006-8 5-10 l
. 1 I
O O O TABLE 5-1 (SilEET I 0F 10) QUALITY ASSURANCE AUDllS AUDITING AUDIT FINDING FINDING ORGANIZN NUMBER NUf0ER LEVEL DATE DESCRIPTION REMARKS __ 8WPC CAR RRF - - 10/17/85 RR finding 4-96 proc.. dure involving Section C39 added to PRM 03-85 interdiscipline interfaces in hazards analysis not added to PRM by dale comiiied BWPC CAR RRF-H - - - 09/05/86 RR finding 4-21, no evidence of annual Nuclear desk instruction revised 21-86 review of nuclear discipline "Q" calculations BWPC CAR Vll-85-92 -- - 11/26/85 4 of 17 design calculations not signed Action recomended to have by originator or checker calculations properly signed and other calculations to be checked BWPC CAR VS-85-162 - - II/Ji/85 Not incorporating greenline changes of EGLs instructed to prioritize all radioactive piping into drawings incoming Isos. PRM changed to within 30 days delete secondary Nuclear review BWPC CAR VS-86-182 - - 03/14/86 Nozzle loads exceeding vendor allow- Exceeded loads +ransmitted to vendor ables not tracked by BWPC with request for early response. Action from CAR VS-85-148 verified BWPC CAR VS-86-185 - - 04/14/86 Discrepancies in hangers shown not Discrepancies corrected. V-SAMU shown on fabrication Isos revised instructions to piping analysis BWPC CAR VS-86-192 - - 03/14/86 Displacement data for penetration seals V-SAMU instructed all personnel by provided by 8WPC and V-SAMU based on memo and training session. Checklist design temperature only for final design verification revised to include thermal modes 0163d/356-7/l
O W f
- - 0 s/
6 i
. o n6
. o a0 s o t f r
p r/ t 2 r i r 1 e d e u p d g k b a n r n m u a s lois oo w n Pi u d x P s t e f e S K d e i P y s r e oso R A - t a t r 6 la 8 n u q r e nl oc P i a 9 a eo i E t m 1 rf t d R i d d s e n f e t ni ob lena i os s es u r a t s p R 6 7 n i v gT b u d m ea wW cC 1 ioer A y t e 2 1 t u5 dd h
.l cb e
oo t t
- b0 n et r n P i 0 a w n i o nd P r0 t P yi m eo d t ioer C sA v P s t r R
N i4 DX lu en J r o P e Pt Af c e d s s n s a e h a , t n e g t n s g i iora a o n r n d k iwi oen u d e t c t it s a m eb cl a d a it i s s a , a v u a p ec al k ee0 f e oo r n r i c c t r 5 o b rt t o t af a a p
)
0 si nt s e pi ec ilor r b o d r nl F R s w g n p g an 1 oc c n t r e p p f a p e p f oa aC n i e i t np i F N u e s gi ,o0 v f ei 0 r e s n p e i PPP sf s ni1 h p IO u r n ot r 2 T f f 7 s e g 'n i l d loicf l w d T P P n s e wi s oen r u a rt n o t cu ly f oy P e E IR f r s e i f n uf a h b Tr I i E C o i p ed , or i t g u O S s r n n s y q l i d , s ct 6 r S E t e n uC n s r s e or i t b e ( D ni et i d P eW ak e n n cn rt ioei meg l d o r d r mi e cB eai t c p r f a n p eg l s v c o gt l a c ona a e t n
- si n rd d m n,a s 7 h r ai 5 et s c a
n p le if t r one a o B em c et d n o E s a n t l B ri g 1 nA t s i i L B a d o s o er x oon nm gt n g x eQ a e lat d f n oai ni d ut vi e A l e t t gii r c pi d P q - n sk T at u a o c oni r or at a pii r p ee r n ivP ef i poro nl n e n o d ct icct e n Pb v p eP oy d o a o s s w iy n a h r o P af op n r Ri e A r N l um C ec Pf ocA Nb I p Dd r 5 5 5 6 6 6 6 6 8 8 8 8 8 0 8 8 E / / / / / / / / T 3 0 0 1 2 2 2 2 A 1 2 2 3 0 0 0 0 D / / / / / / / / 9 9 9 1 9 9 9 9 0 0 0 0 0 0 0 0 G N L I E l l 1 1 l DV - i l - - 1 1 l N E t I L IF G _ 5 6 9 0 1 N R_ 4 4 5 6 6 l E 8 8 9 9 9 0B - 0 0 - - 0 0 0 NM I U R R R R R FN F F F F F _ A A A A A 8 3 1 6 0 4 TR / / / E 5 6 6 IDB UM 8 8- 8 AU 1 1 2 N 10 0 0 / P P P 7 C C C - 6 GN 5 N Z 3 I I A A A / _ T N Q Q Q d _ I A 3 . DG C C C 6 UR P P P _ O AO G G G Ol I-
gY f o t l n a w e u o t n l n n l i ad a
- e y i t o f b n t i e r d m d a n u e a c is S
K lc dd o v R o e e A - t - - - t d r M c n E d 8 ea 9 R e2 0 u - sT leds e T s - m - D r D i G leo G 6 nf
. r e n r oe ee r m ou N d s p r dt ui e ek e N c p c c e C o e o o r P r Ah r F p Q c P m t -
h , s o ic g e t
- d n ,t n t t e h , i s i t t n c
e l l wl o ,id lal rdd n a n ma o n en mi l e or l s s o r mr s r n oa at g e a c r lp s it ph a t r n nt h eg o l ui q w
) n g oia r n f t e lCde
,t 0 l n o oc w md i n s e
'l a o c r a n s r s e s d c c E t pn r ,a s u t n e f e onr oe cesa F N M n g gd n n a v 0 O ind S e n gi em 3
I T h a a n A m u i w i n s ,i g e st a i m -ve mr e pe 6 t u nt P c 7 c r a dd ea r p r c o r f o ee cr T et 0 o uit ,dn I E E R C mne 2 d d lef w od f s ea iuf q o g r eto c c p q S ei e n l f f s ou mr n i S E ol i S w cl , n , r eg ig ( D a r W e oat al 0 nt 5 v t Ai r u p mo h a r 5 s 1 o e / v p qi r r t r u t ios p n iwtso 1 m m E e eot y rd 5
- t i a ly r e o s
M r S
,d t n er o cf n lepo re izdnt s n i A a n a r e cp e lad t ei a r uq E ot e t cd t u e L a n n l f d mg , t n n n n ni m B la e n e a oe enl s n e a a e n n g e A b , - nP os e m ep m a e ixn r udu nr i r emp wkopi i
T i n a l igP P t cit c ui lpci - mu oi rd e n c ai o r o r y ilc d u n r oa r orno q oc u m oa q n u imce o p n im pi C r c W w Ob Ai pt cpd e C n e Sd Af t _ 5 5 5 7 5 5 5 8 8 8 8 8 8 8 _ E 1/ 1/ / / / / / T 6 0 5 5 5 _ A 3 3 3 2 2 2 D / 0
/
0 I/ 2 4
/ /
1 1/ / 1 1 1 1 0 1 1 1 . G . N L _ I E - i - - l l DV I - i l INE L t I F G 7 4 5 N R 5 6 6 I E 8 8 8 DB - 0 - - 0 0 N M I U R R R F N F - F F A A A _ 8 5 8 _ 1 8 1 7 T R 0 / / / I E P 5 7 5 DO U? S
/7 8
8- 8 3 AU 2 7 2 4 7 N 0/ 0 O 0 / 7 P 5 P P P C8 C C C 6 GN 5 _ N Z 3 I I A A A A / T N Q Q Q Q d 3 I A DG C C C C 6 UR P P P P l AO G G G G O p L
m p 3 TABLE 5-I (SilEEf 4 OF 10) AUDITING AUDIT FINDING FINDING ORGANIZN NUf(3ER NUMBER LEVEL DATE DESCRIPTION P9tARKS GPC QA CP08-85/61 - - 08/08/85 Audit of material supplier program - GPC QA CP08-86/13 - - 03/18/86 Compliance of GPC material supplier - program with VEGPs QA program GPC QA CP08-86/44 - - 08/26/06 GPCs material supplier program GPC QA CP08-67/13 - - 04/03/87 Audit of the GPC material supplier - program to detertnine its offec-tiveness and compiiance with VEGPs AS E QA program requirements GPC QA CP10/IP10/ - - 08/28/85 Audit of mechanical systems (1204 - - TP03-85/55 Safety injection System selected) AFR 0836 11 08/28/85 Pump / motor coupling alignment check Attachment D to PPP procedure IX-48 documentation could not be retrieved revised GPC QA CP10/86-02 - - 01/29/86 Adequacy and implementation of QA - program with respect to installation of containment spray system GPC QA CPIO-86/26 - - 06/06/86 Adequacy of GPC ASME program using NQA-l - and NCA-4000 as an 18 point checklist AFR 0934 III 06/06 86 Incorrect storage of audifor m alifi- ASME manual revised cation records specified in 2LME manual AFR 0935 Ill 06/06/86 Requirements for adequate control of Section 4 of ASME QA manual revised supplier responsibilities under ASME Ill NCA-4134.4 and NQA-1 when issuing procurement docunv3nts not listed in GPC QA manual 0163d/356-7/4
O O O' TABLE 5-1 (SHEET 5 0F 10) AUDITING AUDIT FINDING FINDING ORGANIZN NUPBER NU!EER LEVEL DATE DESCRIPTION REMARKS i GPC QA CP10/0Pl5 - - 30/13/06 Walkdown of auxiliary feedwater system -
-86/53 and review of preoperational and normal plant operation procedures ATR 0979 -111 10/13/86 Design manual in conflict with BWPC response clarified finding surveillance procedures on control of locked open single valves in AFW system GPC QA CP10-87/08 - - 03/09/87 Audit of mechanical systems GPC QA CP10-87/32 - - 08/05/87 Audit of Unit 2 mechanical equipment -
(pumps) installation activitles GPC QA CP20-85/92 - - 12/20/85 Adequacy of QA program with respect to - installation of pipe hanger assemblies AFR 0887 11 12/20/85 RRF 4-63 changes to PPP procedures not PPP complied with commitments to made to require return of superseded Readiness Review findings drawings before more can be drawn. RRF 4-44/49 procedure not revised to state "Q-sketches for vent and drain assenblies will be identified by spool mark no.", RRF 4-64 " Troy I" storage area not being inspected, t GPC QA G007-85/22 -
- 03/29/85 Audit of PPP drawing and document control -
AFR 0773 1 03/29/85 Inadequate control of drawings and OCNs PPP Initiated program for self-by PPP monitoring. i j Ol63d/356-7/5' I'
O O O
~
TABLE 5-1 (SitEET 6 0F 10) AUDITING AUDIT FINDING FINDING ORGANIZN NUNER NUNER LEVEL DATE DESCRIPTION REMARKS GPC QA G008-84/87 - - 01/15/85 AWS welding-related activlties. - ATR 0743 11 01/15/85 M&TE - calibrated pyrometer used af ter Deficient instruwmts recalibrated recalibration date AFR 0744 I! 01/15/85 M&TE - Amp / volt meters found to be out DRs written -l of calibration but PPP QA manager not notified GPC QA NO2/WH01 - -- 01/30/85 Audit of small bore pipe storage, -
-84/60 issuance, and nondestructive testing AFR 0750 II 01/30/85 l) Liquid penetrant developer not 10 fittings reexamined properly removed after test
- 2) Incorrect infortnation on final test reports GPC QA OP24/SP01 - - 05/30/06 Technical audit of equipment qualifi- -
-86/10 cation AFR 0013 1 10/17/06 Discrepancy in high-strengh anchor bolt Engineering review made to determine torquing specifications magnitude of problem. DR No.
PP-14672 written and bolts retorqued. W procedure IX-48 was revised AFR 0014 II - 01/20/87 Discrepancies in nunter and type of Response details for EQDP X4AF02 as anchor bolts used on electric stated in letter from BWPC BG-34788 penetrations and NSCW pumps were verified and accepted Ol63d/356-7/6 k
,-n.* ,- sw- . us r - . , w -e,-- *am -. ,i-w w r
--.-. --94-+ -e--- T-=+v-- --- a - - * - - - - - - - - - - - - -v'--*----------e-*
O O O TABLE 5-l (SilEET 7 0F 10) AUDITING. AUDIT FINDING FINDING ORGANIZN NLNR NUPEER LEVEL DATE DESCRIPTION REMARKS GPC QA SP01-85/18 - - 04/15/85 Assessment of NDE performed by PPP - I AFR 0777 1 04/'3/85 trregularities in inspector qualifi- ITP incorporated the radiation safety cation / certification program AFR 0778 11 04/15/85 NDE procedural discrepancies PPP procedure IX-RT-3-W77 revised j AFR 0779 11 04/15/85 Required NDE records not on file Required records located in GPC quality records vault AFR 0780 11 04/I5/85 Inadequate inspection records ITP explanation of their procedures was acceptable [ AFR 0781 111 04/15/85 Approval of yoke method (magnetic Approval was produced particle examination) not evident AFR 0782 lil 04/15/85 M&TE - use of instrument after -Calibration stickers placed on survey expiration of calibration due date meters ! , GPC QA SP01-86/23 - - 05/20/06 NDE performed by Pullman, NISCO, Chicago - l_ Bridge and Iron l AFR 0930 til 05/20/06 incorrect weld numerical designations Drawing 2K3-1208-066-01 revised to , shown on fabrication Iso for chemical incorporate FE DCR 3F-2009. Training ! and volume control system perfonned by PPP and QA i j 0163d/356-7/7-l I _ _ _ _ _ _ _ _ _ _ _ _ _ . _ . _ - . - . . - . - . . . . - - . - . . - . - - . ~ . . . , - - - .- . .. . . . . . . - . - . - . . . . . -
-O O O TABLE 5-1 (SilEET 8 0F 10)
AUDITING AUDIT FINDING FINDING ORGANIZN NtMIER NUfEER LEVEL DATE DESCRIPTION REMARKS GPC QA SP01-86/51 - - 10/09/06 Planned and systematic controls applied - l In finalization walkdown program AFR 0968 11 10/09/86 Scope of ALARA/ Shielding finalization PRM change notice 175 initiated to program not in accordance with PRM delete requirements for a "PT"
- or Readiness Review comitments walkdown from FP-l. PRM Section C41 1
and FSAR 12.3.l.2 made consistent 4 AFR 0970 il 10/09/06 Inadequate finalization program Program description for PF-7 revised. procedures Turnover procedure GO-A-50 revised GPC QA SP01-B6/61 - - 11/20/86 Revision of Pullman QA manual reviewed - for compliance with GPC QA requirements GPC QA SP01-87/34 - - 08/20/87 Audit of QA requirements for tracking - the removal, installation, and replace-mont of permanent plant materials, conp-onents, and equipment ATR 1029 til 08/20/87 Approval of equipment / component removal Open forms by nonauthorized personnel AFR 1030 ll 08/20/87 Improper use and completion of equipment / Open component removal fonns AFR 1031 tl 08/20/87 Procedure GO-T-28, Rev. 4, not revised May affect availability of hardware to reflect current work practices and alI code 4 and 5 Items not tracked Ol63d/356-7/8
~ : - - , ' ! : tP i' , , a O e r
a w d r a h g in t c n n n S e e e K e f e p p p _ R r f A a a - O O O M w r E d R r o a f _ h l t a y _ c it _ e t i _ f nl f ei a t b oa . d pl _ l i . u s a _ o ia v a C l s _ d s g . e h s n r _ s h e nt V er iai e t s E a c l b oid i w n Pt
& c n o ef u wd n a n Mt t s a t a B e r f a r u ixES eS A a t c nil c e ecs ,f l s n
a wl s o md d , _ A el a S n e E e o A oe Af l l
)
0 n on en d o n o;o av ,i u a r M ri S t rt et a Q oel
,gfiI 1 iil p a m el d At c r nd .
tatabh m e d p e o n u op I n n F N nt ot r cu omc C o o inn fu d c u e ii eo i nh i _ O O t r ei cr p cn r I T n ecs es w rh o of V d ed s oi o nli t tc _ 9 eo n r af P m ad s ot P e ioneiSn e uf s e g /i e & r , Pt l T E I R c oiia dn w im B ul ind a n s e t e E C o d f t s a f l n 1 onon c n cr eg ne e O e a o adt , s u . l S dl i 1 e i S E e2 t l E a n d ui io S od _ ( D t v a od e v n a l s vt o a M S om a s a a nt 1,toirs s ,s sd o C h nrnd o a m At a mz en v op e eeg . 1 t r ai m r e i r r eno C mQ A nA n i d os r d r nV od iP _ 5 e ,er e i P a oQ a g C e pg Cd e& _ ct s r t yt G r , o n abB _ E n r t et al a gI it , r V d ri V L eo n w n e ml t f oI s aI o P or Pt sE
& oiM m B d p e a orI g zi & mn e _
A p n s n 2 c p n i I l B a e B n S a m_ i v u n a p voe o T i t ,i r t n hA r g _ es p w a e u E gf c oo ml a m o t s inhph y
- i , E d l uiS r M a gd t r oc M o a g S r r n i
Eseieo S oh h r N t cv c U Al Ad OC a AP ce Ad wt p 7 1 7 7 7 7 8 8 8 8 8 8 E / / / / / / _ T 0 0 7 7 7 7 _ A 2 2 0 0 0 0 D / / / / / / 8 8 0 0 0 0 0 0 1 1 1 1 G . N L I E 1 l - l l i DV i l i I NE t I L F _ G 2 3 6 7 8 N R 3 3 3 3 3 l E 0 0 0 0 0B 1 10 - 1 1 1 N M . I U R R R R R FN F F F F F A A A A A _ 4 4 _ 3 4 T R / / _ ,. I E 7 7 DE 8 8 . UP AU N 10 1 0 9
/
P ) P 7 Sd S - g e 6 GN u 5 Z n 3 Ai A / NI AIN T Qt n Q d 3 IDG UR C o P c C P 6 l O AO G( G O
a s ; O y d ,
.l d r yi e
eel f is pt on ir v ep r c vee e r m t r t 7 n n .
- e r e M
U ph mem Si t ip S n u ouq n n K e d q e p e p R p n ef e A O - a o - O O M f f E 8 on o - R 4 w
, - s o s A ed eg
- ck c n D el ei Gi ai g pW p g e a r c .dt ui e d f d s r eie c c ge a ep oe gl o r p a er _
PS t r P . d t e t e od m l u r n he r a f o _ u s d d c or f g i l h t n n a o a i _ ef a idt mr a p u q w d oh t t t l o n g a r gy s a
)
oe t n o o n B 0 1 ni ooi i gs ot 1 U e r f si mt t ri 1 a o et s c s a pl F N d t i a u et a t 0 n t t a r t A u a . e g y IO s e n t l Qq h c 0 T er iv e r s r a t n at 1 P I r r u u tcl af on in oC on f o B0 U0 e I ri ol T cg t i . R d c i i 8 E C e ap s dt l 3 n n sb O a E S ct ml n s ec e ei t i S E o c ri oen si hA d r n e D r e e r e o ad t C ivenee c i ( a pl vd t wi es N d r f on nt t i f 1 d e 1 r na oea r cb r ler r u oot eg i nt u 0 y s ut e j n t v n or 5 1 t nl n p s ioen i e f e . E n e a oO t e c e t bn L fnt leo f m ri n u t n m aa e ce el l a u B i op ut r el jg i at odi a nb ni r i n A a ri es e o il i b n r 1 i ud t v lec nl p e mpu oa et r cn e c o i d ue r oa r uc m v o a an q xo e or i t a e a C a c Ad pt N Ch E cr Nt Mh 7 7 7 7 7 7 8 8 8 8 8 8 E / / / / / / T 7 7 7 4 4 4 A 0 2 2 2 2 2 D / / / / / / 0 5 5 8 8 8 1 0 0 0 0 0 G N L E i 1 IDV NE I
- 1 - - -
I L _ F G 9 8 N R 3 2 E 0 10 I IDB N M 1 - 1 - N N I U R R F N F F A A - - 4 5 4 6 4 - T R / 2 / . I E 7 P 7 DB 8 03 8- 0 . U M - /2 , AU 1 2/ I 1
/
O N 0 07 7 P ) P8 P - . Sd T - S - e 6 GN u 5 N Z n 3 I I A i A A / T N Qt Q Q d I A n 3
. DG C o C C 6 O UR P P l P c( O AO G G G e: ! , ; i l i]
O. O O i-TABLE 5-2 (SitEET I 0F 8) NRC INSPECTIONS AUDITING AUDli FINDING FINDING ORGANIZN NUPOER NUMBER LEVEL DATE DESCRIPTION REMARKS i NRC 424/85-04 - - 03/08/85 Review of status of Readiness Review No violations were identified 425/85-04 Program NRC 424/85-05 - - 03/11/85 Inspection of in-place storage and No violations were identified 425/(35-05 protection of safety-related equipment i_ and piping installation NRC 424/85-07 - - 03/28/85 Inspection of reactor coolant loop pipe welding and preservice inspection program 85-07-01 Viol V 03/28/85 Use of tools on stainless steel that wore not marked for such use 85-07-02 Viol V 03/28/85 Failure to follow procedure for fit-up inspection on reactor coolant pressure < boundary piping i NRC 424/85-011 - - 04/08/85 Inspection of reactor cooling pressure ' 425/85-011 boundary and safety-related piping , S i 85-11-02 Viol IV 04/08/85 Failure to follow procedure for field welding inspection ' NRC 424/85-017 - - 06/10/85 Inspectien of procurement, receiving Violation notice issued but later
'424/85-017 and storeje activities and the in-depth deleted on 08/16/85 QA insprtion of performance l
Ol65d/356-7/9 l
._ . . _ . . - _ . . , - , , - . . . ...~..m.,. -,. . . _ . . ~ . , . . , . . _ . . - - - , . _ - . _ _ _ _ _ . . _ - _ _ _ _ . .
O d i e f i t n S e K d R i A M e r E R e w s n o it . a lo i v o N h s , t es t e i p w u rt n u n e y g n lou r q 4 ol w t cwp m lo r f is i p t i n n s r u r vi dt d r s ip oh cc e t e el o t yud q n leno leee v n nt a a luf s uea b c b n i , rt o lphe c efuln d m
)
d ,la s, e o lo f r 8 M o o. n st s a r e s t r F t a tsi ca m s s a e t n ep e n o O N w c a e ail s r c o r or u r u et n o O e e tn e+ t rg r s r 2 I i p v s ep c os i iu d i e dt t c d pt ema am T m p P en n p e rl e ci r r p m l T E I Ri nul p o pr i m a o e e pum E R i s e a i n w u r mc u s i r r g p pn n p i C s6 yt O l S S s t d ,t n pp pel e ie t d _ ( E ed n n si o n es nn n c a t a w vt cW eC z e D in and oa ml c ol e c e a ot s ioa m l on t S i 2 d i s t u e i a e t er s v e oN g
- ad f f m s q v t u n t pt f t lon v r r 5 eei oe y ,it cqi cen s os f i o p s e s
je d n e a n R vt t >t ecit ns n n n o loen E s a j c ogd e f oy y lert n a a na pe o u t n n t . iy ut prun m L e t. osd i s r v i a
.i on
,t B
A T w r ienu m ei s t cgi ai enl cn ab s i t olc t y u t o e i it c ec v ed rl s u et e r u v m _ pi s p xd i ai eh a eh t ua q p l w e l e v e r f t e f t sd i e ia q iu er _ et t ni u nd p a a a ai r aih e n n af h Ri i I S w a S wt r i a F es F ew 5 5 5 5 5 5 5 8 8 8 8 0 8 8 E / / / / / / T A UI 4 2 4 2 4 2 3 0 3 0 3 0 TI / / / / / / / 2 9 9 9 0 0 0 1 0 0 0 1 1 1 G V V V V N L I I I I I E D V - - l l - l l N E o o o io I L i i i _ F V V V V G 1 2 3 3 4 _ N R 0 0- 00 0 I E - - - -
- 7 7 - 01 0 -
N IDm 3 3 43 4 U - - - - - - F N 5 5 55 3 8 88 8 5 3 7 9 3 2 8 01 4 3 T R 0- 00 - - 00- - I E 5 55 55 DW U A U 8
/
88
//
88
//
0 1 N 4 4 5 4 5 / 2 22 2 2 7 4 4 4 4 4 - 6 GN 5 3 NI Z I / T N d I A 5 DG C C C l6 U R R R R O A O N N N O ~
' . ii! 1 ! , ,I i l l j' ll ll i !
lI. O i n o ot t c a d e e u e i d v f i i dt t n iecee S e v r e A d lerons R i A c e M e t c E r oei R e n vL w ys y i s _ n i tenb t o l d a x e it n et l a e p , e n y m io lele _ l _ v i v img o i N Ct i F , y d eS s , l e vE est r r v yy i rt n e e l t . un e p t o e t f a g tcne pm o a C s / vf eii t d r w P ed miocrt enl uoi p d G r e ot n on t a v ob t r mqn ud t e e nUi Q n vC e d c y ah e eet rt d r el orr o s co ea ot ni f t g ef rf i u ui s a iwn I
)
8 pp d l , n r c P. r f eis o r t n , a s s u o i e 6 b at t s or n ast icm len t s dd p l a g h a n y em n F O N O n coo t r r r a ni a n r o r f o n uit i o I r e inf c n ot g a ei Ieae .a h g oo i 3 T T P I c n o r oon o s n ep cos mp erl nul p o l pd t e nt ea gc er1 n c 0 e t tatht h i r el uf r aficdee E R c i s i s e r a c i n5 - m z quf E C et e a yt ce mf e85 s i s n s O 1 l S e t a r t d ,t n i t ai r / 0 s n eig l S ( E e a d. us nn si o r o ed e5 - a a c n ea gi v ns y u t o f 2 4 r gi D coa mle ca t r o l a .- a st u e cp e sm n/8 a o9/h r orIv n rna h iom e 2 ip v mner f ms q v r f e c 5 / et o t l m e oe y ,it leo ol z n2 n t sl f oab 5 e u. e t s / nz t o4 o n s n u rt z o toi-mc E ns s a dd es ,i ef oep s e s n p i r L f n oy y er n n aa oon t r i c r n a B o a s i s rl t i ml 4 a o s ogy A w es r rn ee r t cgi ai ab s sd t - cJ ea2 dt ci4 i c i rt f los ni rt T e l enl cn ee e r c me f ot oi i v lu dnl i a t nii pi s p xd n i i l v r o pg s n oimip f f et s utnd s i rs nd c la R e a eah F v mc Inip a ua nd a at V s Inir nf t n n E oiii Incaou pf aqeu nu 5 5 5 5 5 5 5 8 8 8 8 8 8 8 E / / / / / / / T 3 3 7 7 4 5 5 A 0 0 1 1 2 1 D / / / / / 1/ 1/ 0 0 0 0 1 0 1 1 l 1 1 1 1 G V V i INL I I l E l DV - l - l - - i o o INE L io i V i V F V G 1 1 1 NR I E 0- 100- - 0 DB - 2 - 3 2 - - 9 4 43 4 N P I t - - - - F N 5 55 5 8 88 8 2 3 2 74 96 4 43 43 4 3 T R 0- 00 - - 00- - 00 - - _ I E DB UP 5 8 55 88 55 88 55 88 l AU / // / / / / 4 5 l
/
N 4 4 5 4 5 2 22 2 2 2 2 7 4 4 4 44 4 4 - 6 GN 5 NZ 3 I I / T N d I A 5 DG C C C C 6 UR R R R R l AO N N N N O i !! , ;i
l l ( ' 's ! i l
* \
f I M
$ 8 if ;
& 2 2>
ei s 25 4 a 2:* 2 2i[ 8 .
" ^
EI g 8 l.- 87, t' .5 ._ 27= . e A 17 3 7 "E E*o= 5 a s"?E= .- : 81 5 B g 7.7 ar s I S3 22 t 2, # E
- a8
. _r}
2 1
.t et t
-' L l L g E'2 m 8.
E
.!> st?
,o2 5 .!> 8 Im 2 ,
0 -
", t*
2 2 J.: 8 _a
.2 g ba a 8*2
.! _ E E3 1 (3; $ 2b b8: 8 i
8 gag:*8 4 "s ( s _4 a usy 8,
~i NM see 8,
- a. e s_8 a 3g e of;h. .:
a L O >
"* 8
+c o*W 6 .M
", 3 o%&
. L 80 St. 8EE &J SE- 87-g ;"p5* .2% gsi Is7
% . gl It 37
. 8~
[F: 87 ,g
= 1 3- t.:
=82 [rE
.3; t E 3,
.2 51 5. =1I dk 5[ *!
2
- -22 at: 5: 2 =Ig 2 e s s s s s s s W > > k b b 3 3 8 R R R R t t t i 5 5 5 8 8 s s 9a E > t 5W , -
2 e i - i l 6d 6 > 2 _2 0 - _ N _M o ,
~ i i ~ , ~
l Eg 9 9 9 i s s 8 l
~n se ~ --
i e5 99 99 4 @@ : sg
< =
ss x ss s 88 ~ !
- : : :: C 00 00 0 00 i l w=
~z~
s m w & l c 1 f,
< z = = = o ;
O O O TABLE 5-2 (SilEET 5 0F 8) Ath iTING AUDIT FINDING FINDING ORGANIZN NUmER nut 0ER _ LEVEL DATE DESCRIPTION REMARKS NRC 424/06-009 - - 04/I8/86 Inspection of containment and structures, 425/06-004 piping systems and supports, components, auxiliary sy: tems, electrical equipnent and cables, instrumentation, preop. test program, quality programs, and adnini-strative controls 86-09-01 Viol IV 04/18/06 Failure to perform an adequate system walkdown during the turnover of safety-related systems - incorrect valve installations NRC 424/06-011 - - 04/24/06 Review of Readiness Review fiedule 4 425/06-006 86-1l-01 Viol IV 04/24/86 Inadequate measures to assure correction 86-06-01 of design criteria documents - 5D pipe break criteria 86-11-02 Viol IV 04/24/06 Failure to promptly identify undersize 86-06-02 welds in isolation valve encapsulation vessels 86-11-03 Viol IV 04/24/06 Failure to provide adequate instructions for removal of shipping supports frcrn RilR isolation valve encapsulation vessel NRC 424/06-017 - - 04/25/86 inspection of NDE procedures on piping No violations were Identified 425/06-009 and vessels including qualification of personnel and calibration of test l equipment l I l l l Ol65d/356-7/13 ... - - _ . . . __ _ .- _ _ _ _ ______-_--_-_____
O d e u s s i d d d e e e t i i i o f f f n i t i t it s n n n , S a e e e K w d di d _ R i i A n M io e e r e r E r - R t e e e a w w w - lo s s s i n n n v i o io i o f t t t o l a l a l a e io o io c i i v v v t o o o o - N N N N h n g t , o n i m n? t i s i n w e on cs lo d io ne ut t t is t r aen let 4 i n n dl n a d d r o t mpi n r i a w a lepu ai ai n C p o opr m p a r a A p c f t n r u w xt g e V u
) n es oo d o en o
nt a l o H s B i t e if ol ip m la a r t n Ml l c r depe i ei a ii o a ipg t F 0 N r t d pi s wf md n l i O e a ei r ig e r nt n o l p 6 I t r mh e u n i r ea s e ni c a T a ur wt qi v o h od t d s T P I m ce ct d r i es r R c et t g
, t gl u
la s nd n a a E ec n c o E R C g n ani t y ism s p e gn y nit i n i r i el O H S e s s it di e t p S E ip dfocia0 5 l r - en ps i r t ci n ( D i e ini i e g lel a ep o ip v ons n o g pl oa dl pt e t w ee m t o ,it 2 f r osi ri a a f n n f t f r s c 5 o pi at p r eno ooi os os pt u r r t e e i m E n oad ot R i d ntr la nl oa n e oot t o t n n a m t a f t e ioa r iot s t p s p n i i m oii i r 3 N t c em ri s u t e r r wdd f i t b u cit t ui ct o t y cs eu r s oc 1 e luleahk o u e e at n ev c ecr e u p l l i p u p ut pC l t m s n ia n r et i l ai v end ee sd r n nt s r n sA i a u r c o I F ob iw F f R oi I a s Ints o c InV H Fd f 6 6 6 7 6 6 6 6 0 8 8 8 8 0 0 0 E / / / / / / / / T 8 8 8 0 3 3 2 2 A 0 0 0 3 2 0 0 0 D / / / / / / / / 2 2 2 1 9 9 0 0 1 1 1 0 0 0 1 1 G V N L I V I E DV - l - - - - l o o N E I L i F V Vi G 1 2 3 2 1 N R 0 00 - - 00- - E - IDB N M 9 3 99 3 1
- - - 1 7 3 4 -
I U - - - - - F N 6 66 66 8 88 88 99 4 71 92 2 4 3 1 5 64 63 7 3 R 00 0 00 00 00 TI D3 E 66 6 66 66 66 U1 AU 88
/ /
8
/
88
/ /
88
//
88
/ /
4 1 N 4 5 4 4 5 4 5 4 5 / 2 2 2 2 2 2 2 2 2 7 4 4 4 4 4 4 4 4 4 - 6 GN 5 Z 3 NI I / T N d I A 5 DG C C C C C l6 UR R R R R R O AO N N N N N O
O i d ie f t d i i t f e n n e e d d d i d d d d i d ie e ie e e ie e i i i e f r f f f f r f i t e i i i i e i w t t t t w t n n n n n n S e s e e e e s e K d n d d d d n d R i i o i i I i o i i M E e r t e r e r e r e r t a e r R u e e e e l e w i o w w w w io w s v s s s s v s n n n n n n i o 4 i o i o io o 4 o i i t a e t t t t e t l a a a a l a l u l l u l o d lo o io lo d io o i i i o iv M v v v v M v o o o o o o o o N N N N N N N N l g g
, r - e s s w g o i n m n n e n t l n e l ip lm ip p iv ei c a o t a p s a u s f s i dl o e ri u e q r oy r ip ne at ip lor f op
,sn g
n r , gd p e n s t e n , s s i ,n n iog u o
)
8 s loe r s l l o r t s n e a n s g gt isi nil s o l u o lop ri i a n
,i o t in i d r
F 0 N e r t n e s t n lod i l y p eb d f t n pC t A c d n ipp n a IO d u ov c o c oa ce a ip n eo r m e oyV e cri p l o cd 2 7 T e n ,R adt h t a s n P c o ea c s l d ,n t a t T E I o lai las rf cta lp an y ia un ngi l i E l R C r p i t r a i r a l t oo s iml s r oif i u r k U n en cw a e me s ee n O i S S el W eb ip o b o ( E E t u t r i r s o C t - w E D D as a e eit e - ai S a ep s sl D N mpt a n mt n r vi e s yb s t n N mrud r d a e e N 2 f f ci f i f r n f ed a f f s e o f t f 5 o onejo o o e of n p o ost c os o n n n o r d p n n o a a x n s , e n ea e n rl r nl n E o ot oa o L i iofoon i c ioa,4 io t s e io iop er n i r B t t t a t t l t t t t t - o t u i t e A T c cr is ce cg e cir e c cn yi ct cg e p ei n p a a er p enl pi u eu o r pb p c e p eat t pl ea ec p u ea p r s s p p sd s pd s - p n s s of c s r s o _ I n I n rexe I n n a InipM o I n s u o as c I n I n oai csf Ints Ints - 6 6 6 7 7 6 6 7 7 0 0 0 8 8 8 8 8 8 . E / / / / / / / / - T 0 3 4 5 1/ 7 9 3 9 A 1 0 2 0 1 1 2 - D / / / / 1/ / / 1/ 1/ - 9 0 1 2 2 2 2 1 0 1 1 0 0 1 1 0 0 . G _ N L _ I E _ DV - - - - - - - - - NI E. I F _ G N R I E - - - - - - Dm N I U F N 5 6 67 3 3 109 165 1 99 00 44 7 3 7 3 94 4 5 25 3 6 00 T R 40 00 00 10 10 12 1 0 10 00 I E - - - - - - - - - - - - - - 66 66 66 66 66 6 66 66 7 7 Dm U AU 88
//
88
/ /
08
/ /
88
//
8 8
/ /
8
/
88
/ /
88
//
88
/ /
5 1 N 4 5 4 5 4 5 4 5 4 5 4 4 5 4 5 4 5 / 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 7 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 - 6 GN 5 _ N Z 3 . I I
/
T N d _ I A 5 DG C C C C C C C C C 6 _ UR R R R R R R R R R l O AO O N N N N N N N N N -
O d i i t f e d ie f t i n n e e d d i i d d d e ie e e r e i i r f f f e e i i i w w t t t n n n S s s e e e K n n d d d _ R io o i i i A i M t a t e e e E a r r r _ R l e e e lo i io w w w v v s s s n n n 4 4 i o i o i o e e t t t l a a a lu u l d o d lo lo io o i i M M v v v o o o o o N N N N N l a d m l g n e a _ i at r n s ic t e 2 i ey e , r _ n n c n ove t c -s rl t a a t r n i e e ,m i ed aW f s eii lp ip sn , yf U n c a mF n n s rA s ges ea a
,l t t g
,p iono t o E
ooct f f o n vt r ,t nt r
)
n i g n i d r os e s en egr o 8
,t s l D
at i m a n s N o s u op mmi ip eeitl i n a a uit r mp t p e u n F 0 N O pt mn g r qd r l o n o i t a u ct c ri n lcc n a s st m ut ri _ 8 I T ,s r eme ro l a e p w p i t
- e. t o ad t s os i e
rd s n a y sd T P t el t u p a r ic d s u c u em e y ran e s a , a y n i d E r n r e E T IR C er dt y r u n st t aE t g st n n l e et ni ee rt g a s a r , n I S S ct a ni c I s a eet ew ae ni y E n c e , n r ic ema a , u g t ( i l ril D ou se cr ,u a l leor as s oo ct L c ql s 2 c pi w s ni x em 2 f t sbS l S q f f s f r e ee od st t op u c a a a r t l i c 5 o aS d onC ol ofn a ie n ,t , , r g
,cN n o a l U o E n s ,a n cl ni n eod a n n s , r L
B ionos,s , io l a c iore io s t ei c f oet t p oi m ri n s t i t yl t ai t t t u et t t n e yl A T ct r a o e a ow r ci r e rt c a em c or ai ei u w ci ee a yil smt
-i vpi r o
p r p et s e p c n n p u a o p st e n al e c p sd n n s ei lua er p vl n r a v r c it t v on wqu er o u a o t n I o s r c I me I a i pf ep R p cc eq c 7 7 7 7 7 8 8 8 8 8 E / / / / / T 3 4 5 7 8 A 0 1 0 2 2 . D / / / / / 4 4 5 3 5 0 0 0 0 0 G N L I E DV - - - - - N E I L F G N R E ID3 NM - - I U F N 2 8 4 0 62 7 2 6 1 0 1 1 1 1 2 1 TI RE 04 - 104- 04 - 0- 00 - - D0 Uf 7 7 88 7 7 88 7 7 88 7 8 7 7 88 AU / / / / / / / / / 16 N 4 5 4 5 4 5 4 4 5 / 2 2 2 2 2 2 2 2 2 7 4 4 4 4 4 4 4 4 4 - GN 6 5 N Z 3 I I T N
/
A d 5 IDG UR C R C C C C 6 R R R R l O AO N N N N N O
O O O TABLE 5-3 (SilEET I 0F 5) REPORTABLE AND POTENTIALLY REPORTABLE DEFICIENCIES AUDITING AUDIT FINDING FINDING ORGANIZN NUmER NU mER LEVEL DATE DESCRIPTION REMARKS GPC CDR - M082 - 08/25/85 Inadequate clearances between seismic OER 099 was prepared. GPC removed bowl restraints and pump columns of NSCW the pumps and reworked the seismic pumps restraints to ensure existence of proper clearances. Condition found to be reportable under 10 CFR 50.55(e) but not reportable under 10 CFR 21 GPC CDR - M086 - 09/26/85 Nitrogen vent lines on Units I and 2 DER 098 was prepared. Aside from accumulators erroneously shown on issuance of 3 DCNs and an FCR to orihographie drawings as requiring remove caps from accumuIator vent ihreaded caps Iines of Unit I and Unit 2, ali Project P&lDs were reviewed and 22 vent lines were identified as required to be open to the atmosphere. Their orthographic anri isometric drawings were reviewed and none of the vents were shown as capped. Condition found to be reportable under 10 CFR 21 and 10 CFR 50.55(e) GPC CDR - M088 - 10/11/05 Failure to postulate longitudinal DER 104 was prepared. The engineering pipe breaks at ASME B&PV Code, Section evaluation and subsequent hazard 111, Class 2 and 3 intermediate analysis of four postulated inter-break locations in accordance with mediate longitudinal breaks resulted BTP MEB 3-1 in rerouting of power cables to valve HV-880lB. Cwdition found to be reportable under 10 CFR 21 and 10 CFR 50.55(e) Ol71d/356-7/l
O O O 1ABLE 5-3 (SilEET 2 0F 5) AUDITING AUDIT FINDING FINDING ORGANIZN NUmER NUTER LEvrL DATE DESCRIPTION REMARKS GPC CDR - M091 - 12/30/85 Disc in Dresser Industries Y-paltern DER 112 was prepared. Identified 68 diaphragm valve may stick due to valves of this type ranging in size unanticipated operating condition of from 3/4 " to 2" for Unit I and unequal forces Unit 2, which are used as root valves, drain and vent isolation valves, normally closed process l valves, and normally open process valves. Modification kits were furnished and parts replaced in each identified valve installed in Unit 1. Unit 2 valves were sent back to the vendor for rework and returned to VEGP for installation. Condition found to be reportable under 10 CFR 21 and 10 CFR 50.55(e) I GPC CDR - M093 - 02/03/06 Process and root-vent-drain valves not DER l13 was prepared. Records for ) installed in accordance with design 2775 valves were surveyed for j requirements installed conditions not conforming I to design requirements. 1978 were l Inspected by walkdown for as-installed cmpliance with these requirements. Of those, 14 (including 9 Identified on DR MD-8515) were found discrepent. Eleven were dispositioned "use-as~is", ihree were replaced, and l one was reworked. Condition found to be reportable under 10 CFR 21 and 10 CFR 50.55(e) l 1 0171d/356-7/2 1 1 t - - - _ _ _ _ _ _ _ - - _ _ - _ - _ _ - - - _ - - - .
.O O O :
TABLE 5-3 (SilEET 3 0F 5) k AUDITING AU91T FINDING FINDING ORGANIZN NtM3ER NUPEER LEVEL DATE DESCRIPTION REMARKS GPC CDR - M090 - D3/13/06 incperable butterfly valves in DER 126 was prepared. Failure of su yu.e t cooling water and auxillary valves to operate was duo to broken gear feeth in worm gear sectors. Gearing is being replaced. it was found that none of these valves perform a safety function. Therefore, the condition is considered not reporteble under .! 10 CFR 21 and 10 CFR 50.55(e) GPC CDR - Mlli - 04/10/06 CVCS centrifugal charging pump installed DER 136 and ODT T-1-06-30 were with holdown bolts of potentially prepared. Enginearing'- evaluation inadequate strength levels indicated that the bolts were either stressed to the yield strength or were stressed above the yield strength of the bolting material. Westinghouse Electric Corporation's evaluation concluded the equipment would rernain operable. Unit I bolts have been replaced and Unit 2 bolt replacement is documented and tracked by PCW. Condition is considered to be not reportable under 10 CFR 21 and 10 CFR 50.55(e) GPC CDR - Mll6 - 04/25/86 Onission of lock-welds on internal DER 150 was prepared. Identifled 56 ! uw yvisits of Anchor / Darling swing check discrepant valves in both Unit I and valves Unit 2. All deficient valves have been reworked to bring them into conformance wIth the Anchor /DariIng design drawings. Condition found to be reportable under 10 CFR 21 and 10 CFR 50.55(e) 4 0171d/356-7/3
- - _ - _ _ _ - - . _ _ _ _ _ _--i6+______sm-.-*evs. .wget. ,w- m + + +%*- as= e, se ve e V " IFr*,-r w w. __
q-w r w' ?4 - 4 4 g ,,,%a_, g,,,,,,,,,, ,,,gy,.w.
O . O O TABLE 5-3 (SiiEET 4 0F 5) AUDIT lNG AUDIT FINDING FlNDING ORGANIZN nut 0ER nut 0ER LEVEL DATE DESCRIPTION REMARKS GPC CDR - Mil 7 - 05/14/86 Required disc travel (full lift) not DER 151 was prepared. All 20 Unit I achieved in test of Crosby Model 6R10 steam line safety valves were shipped rain steam line spring loaded safety to Crobsy's facility for testing and valves adjustment. All valves for Unit 2 will be adjusted in the future and are being tracked by PCW. Condition found to be reportable under 10 CFR 50.55(e) . 10 CFR 21 notification is not required since NRC was previously inforTned of this condition for Crosby valves GPC CDR - MI21 - 07/28/86 Potentially defective welded joint in Quality concern No. 86V0515 identified NSCW stainless steel pipe fit-up a potential problem in a nuclear service cooling water field weld joint due to a partially consumed weld insert, joint mismatch and alleged loss of purge gas. An extensive engineering evaluation and review of quality records dunonstrated no hardware or program deficiencies. Condition was not reportable under 10 CFR 50.55(e) Ol71d/356-7/4
t) J O TABLE 5-3 (Sl(EET 5 0F 5) AUDillNG AUDIT FINDING FINDING ORGANIZN NUNER NUSER LEVEL DATE DESCRIPTION REMARKS GPC CDR - Ml31 - 11/04/86 Failure of turbine driven AFW purp DER 170 was prepared. The Unit I governor to control pump speed and Unit 2 governors were defective and were returned to the vendor. New governors were installed, tested, and operated properly for Unit 1. The Unit 2 governors will be supplied, installed, and tested comensurate with the Unit 2 construction schedule. Condition found to be reportable under 10 CTR 21 and 10 CFR 50.55(e) GFC CDR - M135 - 12/05/86 Fuel oil transfer lines embedded in DG DER 176 was prepared. Stress building basemat without sleeves are analysis showed that calculated subject to o'eerstressing from stresses in subject lines exceeded differential seismic motion and the ASME code alleeables. Installed building settlement guard pipe around the subject lines to provide adequate flexibility. As-built stress calculation for Unit I train A and train B have boon completed. Corrective actions for Unit 2 are tracked by PCW and will be completed ccanensurate with the Unit 2 construction schedule. Condition found to be repottable under 10 CFR 21 and 10 CFR 50.55(o) Ol7td/356-7/5
Page Na. O I O 12/0H/87 ) I' L A N T V0GTLE UNIT 2 READINESS REVIEW PROGRAM l FOLLOW-UP OF UNIT I FINDINGS (RR.IDR.NRC) TABLE 54
=-== ,e====== ==============================================
EDIT SOURCE AND DESCRIPTION OF DESCRIPTION OF UNIT I DESCRIPTION OF UNIT 2 No FINDING DESIGN CONST LEVEL FINDING CORRECTIVE ACTION FOLLOW-UP ACTION
=== =============== ====== ====== = === ===== =======-===-=== ======== ======== -=========== ======== ==== ===== ==-=== ============
l R8 IDR X I LONGITUDINAL PIPE BRFAKS RAVE PRM SECTION C-39 REVISED TO CORRECTIVE ACTION REMAINS 22-9001 NOT BEEN EVALUATED AT RIGH EXPLICITLY IDENTIFY THE IDENTICAL AND ACCEPTABLE STRESS POINTS DISCIPLINE INTERFACES FOR RAZARDS ACTIVITIES l 89 IDR X I INADEQUATE FLOODING EFFECTS COMMITMENT TO (I) REVISE FSAR CORRECTIVE ACTION REMAINS l 22-B003 ANALYSIS TABLES 3F-I AND 3F-3 IDENTICAL AND ACCEPTABLE PENETRATION SCHEDULES. AND FACILITY RESPONSE ANALTSIS, (2) REPLACE CIRCblT BREAKERS 90 IDR X I DOCUMENTATION OF DESIGN CALCULATIONS REVISED TO ADD CORRECTIVE ACTION REMAINS 22-8004 INPUTS / JUSTIFICATION OF AND DELETE REFERENCES IDENTICAL AND ACCEPTABLE ASSUMPTIONS FOR "Q" CLASS HAZARD CALCULATIONS INADEQUATE 93 IDR X 11 DISCREPANCIES IN STEAM LINE COMMITMENT TO REVISE DC-1302 CORRECTIVE ACTION PEMAINS 22-G007 BREAK MAXIMUli AFW FLCW RATE TO TO INDICATE A 996 GPM AFW FLOW IDENTICAL AND ACCEPTABLE A FAULTED STEAM GENERATOR AS SHOWN IN THE FSAR AND DESIGN CRITERIA 95 IDR X II FSAR INACCURACIES AND LACK OF COMMITMENT TO REVISE FSAR CORRECTIVE ACTION REMAINS 22-G009 SUPPORTING DOCUMENTATION SECTION 10.4.9 IDENTICAL AND ACCEPTABLE REGARDING AFW SYSTEM DESIGN 96 IDR X II DISCREPANCIES IN CALCULATIONS DESIGN PERSONNEL RETRAINED ON ISOLATED INSTANCE /0NE TIME 22-GOII VERIFYING AFW STSTEM DESIGN CALCULATION DEVELOPMENT CORRECTIVE ACTION 97 IDR X II AFW PUMP MINIFLOW REQUIRED FOR DESIGN PERSONNEL RETRAINED ON ISOLATED INSTANCE /0NE TIME 22-0013 SAFE CONTINUOUS OPERATION VENDOR DRAWING REVIEW AND CORRECTIVE ACTION SIGNIFICANCE OF PUMP MINIFLOW 99 IDR X II ERROR ON DRAWING NUMBER DCN ISSUED TO CORRECT ERROR CORRECTIVE ACTION REMAINS 22-G016 IX4DL3G03 IDENTICAL AND ACCEPTABLE 100 IDR X II INCOMPLETE AFW PIPING DESIGN COMMITMENT TO REVISE CORRECTIVE ACTION REMAINS 22-G017 BASIS CALCULATION AX4DR008 TO IDENTICAL AND ACCEPTABLE l CORRECTLT SHOW OVERPRESSURE I CONDITIONS
i Page No. O 2 O O ' 12/08/87 i PLANT VOCTLE UNIT 2 READINESS REVIEW PROGRAM FOLLOW-UP OF UNIT 1 FINDINGS (RR.IDR.NRC) f' TABLE 5-4
=========-======================== ========================: l EDIT SOURCE AND DESCRIPTION OF DESCRIPTION OF UNIT I DESCRIPTION OF UNIT 2 l NO FINDING DESIGN CONST LEVEL FINDING ,
CORRECTIVE ACTION FOLLOW-UP ACTION 1
==se ===e=========== ====== ====== ===== =======================-====== ============================== = ============================
'101 IDR X II DISCREPANCIES IN CALCULATION PORTION OF CALCULATION ISOLATED INSTANCE /0NE TIME 22-G018 0F AFW PIPING DESIGN PRESSURE X4Cl302903 VOIDED CORRECTIVE ACTION 102 IDR X II No ESTABLISHED TRANSMITTAL DWG. AX4DR008 ISSUED TO CORRECTIVE ACTION REMAINS I
4-014 PROCEDURE TO PIPE STRESS GROUP PROVIDE ALL NECESSART IDENTICAL AND ACCEPTABLE ! 4 FOR SYSTEM OPERATING INFORMATION ON SYSTEM L f CONDITIONS THAT EXCEED DESIGN CONDITIONS WHICH EXCEED VALUES SPECIFIFED DESIGN VALUES 103 IDR X II FSAR AND DESIGN CRITERIA NEW CALCULATION IN PROCESS AT CORRECTIVE ACTION REMAINS 4-015 COOLDOWN COMMITMENT TIMES NOT TIME OF OBSERVATION RECQGNIZES IDENTICAL AND ACCEPTABLE IN ACCORDANCE WITH ANTICIPATED THE ANTICIPATED CCW SYSTEM COMPONENT COOLING WATER SYSTEM THERMAL PERFORMANCE. .FSAR WAS THERMAL PERFORMANCE REVISED 104 IDR X II COMMITMENT FOR DESIGN FEATURES REQUIREMENT FOR PREVENTION OF CORRECTIVE ACTION REMAINS I 4-016 TO PREVENT NON-LOCA TO LOCA BREAK PROPAGATION IN SOME IDENTICAL AND ACCEPTABLE BREAK PROPAGATION NOT MET BRANCH LINES RELAXED FSAR AND 'l DC-1018 REVISED 105 IDR X 11 NORMAL OPERATING CONDITIONS OF CALCULATION REVISED TO CORRECTIVE ACTION REMAINS 4-017 AUXILIART FEEDWATER SYSTEMS DEMONSTRATE THAT OPERATING IDENTICAL AND ACCEPTAQLE EXCEED SYSTEM DESIGN PRESSURE CONDITIONS ARE WITHIh DESIGh , AND FLANGE RATINGS PRESSURE AND FLANGE RATINGS 107 IDR X I AFW PUMP SUCTION PIPING RELIEF VALVES ADDED TO SUCTION CORRECTIVE ACTION REMAINS 4-019 OVERPRESSURE PROTECTION NOT PIPING OF THE 3 AFW PUMPS IDENTICAL AND ACCEPTABLE DETERMINED , 111 IDR X II CCW FLOW PRESSURE DROP AND OTHER CALCULATIONS WERE ISOLATED INSTANCE /0NE TIME 4-023 NPSH VERIFICATION CALCULATION SURVEYED AND IT WAS DETERMINED CORRECTIVE ACTION USED INCORRECT ASSUMPTIONS AND THAT THIS OVERSIGHT WAS l AN INAPPROPRIATE FORMULA LIMITED TO ONE ENGINEER 4 114 IDR I II CALCULATIONS BASES FOR CCW CALCULATIONS TO DOCUMENT CORRECTIVE ACTION REMAINS J 4-026 DESIGN CONDITIONS NOT DESIGN PARAMETERS WERE IDENTICAL AND ACCEPTABLE , AVAILABLE UNDERWAT AT TIME OF IDR l t 115 IDR X II USE OF CCW SURGE TANKS FOR DC-1203 REVISED TO CLARIFT CORRECTIVE ACTION REMAINS 4-027 RELIEF PROTECTION OF RHR HEAT REQUIREMENT FOR OVERPRESSURE IDENTICAL AND ACCEPTABLE EXCHANGER PROTECTION - 4 e
-<a _a_. __=a _ ._____.e.- ~e- _ .e, me,-s - _ m _ m,= ,-r-.e e er e - _ v ,--- .. & ___.m._ -______.__ _ _ _ _ _ _ . _ _ _ _ _ . _ _ _ _ . _ _ . - - _ _ _ - _ _ _ _ . _
Psge No. O 3 O O 12/08/87 PLANT V0GTLE UNIT 2 READINESS REVIEW PROGRAM FOLLOW-UP OF UNIT 1 FINDINGS (RR.IDR.NRC) TABLE 5-4
============================================================
EDIT SOURCE AND DESCRIPTION OF DESCRIPTION OF UNIT 1 DESCRIPTION OF UNIT 2 NO FINDING DESIGN CONST LEVEL FINDING CORRECTIVE ACTION FOLLOW-UP ACTION
=-e= =======e== ==== ====== ====== ===== ============ =========-======= ==============e=============== ==============================
IIB IDR X I FLOODING ANALYSIS OMISSIONS CALCULATIONS WERE UPGRADED TO CORRECTIVE ACTION REMAINS 4-030 INCLUDE OMITTED CONSIDERATIONS IDENTICAL AND ACCEPTABLE 12I IDR X II INSUFFICIENT JUSTIFICATION FOR DR JUSTIFICATION REVISED TO ISOLATED INSTANCE /0NE TIME 4-033 WAIVER OF TILTING DISC CHECE REFLECT RATIONALE FOR CORRECTIVE ACTION VALVE AIR LEAK TESTING RYDROTEST ONLY - CONSIDERED AN ISOLATED CASE 124 IDR X II CONTROL OF WELDING MATERIALS PULLMAN DOCUMENT VIII-3 CORRECTIVE ACTION REMAINS 4-037 PER PPP DOCUMENT VIII-3 NOT REVISED TO CLARIFY PROCEDURES IDENTICAL AND ACCEPTABLE EXPLICIT ENOUGH 128 IDR X I RAZARD ANALYSIS OMITTED AXIAL COMMITMENT MADE TO COMPLETE CORRECTIVE ACTION REMAINS 4-092 VANE FAN UNITS AS A SOURCE 07 MISSILE ANALYSIS FOR FANS BT IDENTICAL AND ACCEPTABLE MISSILES 10-15-86 150 NRC X VIOL INADEQUATE MEASURES TO ASSURE CRANGES IMPLEMENTED IN DESIGN CORRECTIVE ACTION REMAINS 86-11-01 CORRECTION OF DESIGN CRITERIA CRANGE CONTROLS AND REMEDIAL IDENTICAL AND ACCEPTABLE TRAINING GIVEN DESIGN PERSONNEL 151 NRC X VIOL INADEQUATE AND DELAYED DR'S ISSUED AND DIRECTIVE CORRECTIVE ACTION REMAINS 86-11-02 RESPONSE TO IDENTIFY AND PREPARED AND DISTRIBUTED TO IDENTICAL AND ACCEPTABLE CORRECT UNDERSIZE WELDS RESPONSIBLE MANAGEMENT AND SUPERVISONY PERSONNEL TO PRECLUDE REPETITION 152 NRC X VIOL FAILURE TO DOCUMENT REMOYAL OF PPP PROCEDURE CRANGED. CORRECTIVE ACTION REMAINS 86-11-03 SRIPPING DUNNAGE INSTALLATION DOCUMENT REVIEW IDENTICAL AND ACCEPTABLE . PERSONNEL TRAINED.AND NEN PROCEDURE IMPLEMENTED 154 RRF X II VEGP FIELD PROCEDURES MANUAL DESKTOP INSTRUCTION MI-A-24 CORRECTIVE ACTION REMAINS 4-601 DOES NOT PROVIDE-FOR THE MILL BE INCORPORATED INTO FPM IDENTICAL AND ACCEPTABLE INDOCTRINATION AND TRAINING OF TO PROVIDE A CONTROLLED GPC ENGINEERING PERSONNEL PROCEDURE 155 RRF X III PPP SKETCHES FOR TYPICAL VENT CONTROL TURNED OVER TO CORRECTIVE ACTION REMAINS 4-004/049 & DRAIN DETAIL (SK-0-163) NOT DOCUMENT CONTROL AND IDENTICAL AND ACCEPTABLE CONTROLLED BY DOCUMENT CONTROL IDENTIFICATION REQUIRMENTS CENTER & NOT PROPERLY NUMBERED REVISED TO REFLECT APPLICABLE SPOOL MARK NUMBER k __ _.____.___________m____. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ m____ _ _ _ _ _ - . - m e - - . . . . _ _ . - - .___,.m_- _ _ _ _ . _ . _ . _ , _ _ _ _ _ . _ _ _ . _ _ _ _ . _ _ _ . --
Page No.
- O4 O O I2/08/87_ _
PLANT VOCTLE UNIT 2 READINESS REVIEW PROGRAM FOLLOW-UP OF UNIT 1 FINDINGS (RR.IDR.NRC) TABLE 5-4
============================================================ *
. EDIT SOURCE AND DESCRIPTION OF DESCRIPTION OF UNIT I DESCRIPTION OF UNIT 2 NO FINDING DESIGN CONST LEVEL FINDING CORRECTIVE ACTION FOLLOW-UP ACTION e=== ======ne=e===== ====== ====== ===== ============================== ================u========e==== ==============e===============
.156 RRF X III ANCHOR BOLT LOCATIONS DO NOT ACTUAL LOCATIONS REFLECT ISOLATED INSTANCE /ONE TIME 4-04I CONFORM TO VENDOR DRAWING SPACINGS ON PUMP. ARE .C0kPECTIVE ACTION REQUIREMENTS ACCEPTABLE. ARE WITHIN TOLERANCE OF VENDOR SPECIFIED LOCATIONS. AND ARE ADDRESSED j
IN DR NO. PP-9806 IST RRF X II ARC STRIKES AND WELD SPATTER STRIKES & SPLATTER REMOVED PER CORRECTIVE ACTION HAS CHANGED i' 4-045 WAS FOUND ON INSTALLED PIPING PPP PROCEDURE II-52. PIPE TO SEE SECTION 5.5 DUE TO WELDING IN ADJACENT BE INSULATED PRIOR TO TURNOVER e AREAS WILL BE INSPECTED BY GPC JUST PRIOR TO INSULATION. BY REVISION OF GPC PROCEDURES MD-T-19 & MD-T-20
'I58 RRF X III HEAT CODE IMPROPERLY RECORDED HEAT CODE NUMBER ON WELD ISOLATED INSTANCE /0NE TIME 4-046-1 ON WELD PROCESS SHEET PROCESS SHEET CORRECTED CORRECTIVE ACTION 159 RRF X III I 0F 2 WELDERS SYMBOLS ON PIPE DR NO. 9891 ISSUED TO ADDRESS ISOLATED INSTANCE /0NE TIME 4-046-2 NOT RECORDED ON WELD PROCESS ERROR BY WELDER IN APPLTING CORRECTIVE ACTION SHEET STAMP TO WRONG WELD
.I60 RRF I III NO DOCUMENTATION OF VALVE QC INSPECTOR WHO MONITORED ISOLATED INSTANCE /ONE TIME 4-050 LINEUP VERIFICATION PRIOR TO HYDROTEST REVISED RECORDS TO CORRECTIVE ACTION ,
HYDROTEST REFLECT THE VALVE LINEUP INSPECTION NE PERFORMED. ISOLATED OCCURRENCE I61 RRF X III LOCATION OF HYDROSTATIC VENT PROCEDURE XI-l REVISED TO CORRECTIVE ACTION REMAINS' i 4-052 LOCATIONS NOT RECORDED DELETE RE0'T BECAUSE IDENTICAL AND ACCEPTABLE < INFORMATION IS FOR HISTORICAL
- PURPOSES ONLY. DOES NOT AFFECT PERFORMANCE OR QUALITY OF TEST AND VENTING IS DOCUMENTED ON LEAK TEST RECORD BT TEST '
ENGINEER 162 RRF X III EYE EXAM REPORT MISSING FROM EYE EXAM RECORD LOCATED IN CORRECTIVE ACTION REMAINS 4-054 INSPECTOR CERTIFICATION DISCIPLINE CERTIFICATION FILES IDENTICAL AND ACCEPTABLE PACKAGE ~IN CPC VAULT AND TRANSMITTED TO VAULT. i I RECORD PACKAGES FOR ALL MECHANICAL INSPECTORS REVIEWED AND VAULT FILES CORRECTED AS REQ'D. '. -..._.n.. -.a,-,,,.,,--e,n~ -, ~ , -- + + . . , --..-u- -,-we,- ,m - -. en e- +. v -~~ ---sn w .--- m -- - - ---w - - - - - - - - - - - - - - -
'Page No.
O .5 O O 12/08/87 PLANT V0GTLE UNIT 2 READINESS REVIEW PROGRAM FOLLOW-UP OF UNIT I' FINDINGS (RR.IDR.NRC) TABLE 5-4
============================================================
EDIT SOURCE AND DESCRIPTION OF DESCRIPTION OF UNIT I DESCRIPTION OF UNIT 2 NO FINDING DESIGN CONST LEVEL FINDING CORRECTIVE ACTION FOLLOW-UP ACTION e2:= =============== ====== ====== ===== ============================== ======e======================= ==========e=================== 163 RRF X III RECORDS PACEAGE INCOMPLETE - DR No. PP-9917 PREPARED & ISOLATED INSTANCE /0NE TIME 4-055 MATERIAL REQUISITION FOR SMALL DISPOSITIONED "USE-AS-IS" CORRECTIVE ACTION BORE PIPING MATERIALS MISSING BASED ON REVIEW OF MATERIAL FROM ISOMETRIC DOCUMENTATION TEST REPORTS. PACKAGE DID PACKAGE CONTAIN REQUISITIONS AT TIME OF OA REVIEW AS EVIDENCED BY ANI ACCEPTANCE l 164 RRF X I HOT-PIPE-TO-RACEWAY SEPARATION I. DR NO. ED-8341 PREPARED & CORRECTIVE ACTION REMAINS 4-056 REQUIREMENTS OF SPECIFICATION DISPOSITIONED "USE-AS-IS". 2. IDENTICAL AND ACCEPTABLE X3ARDI. E8 VIOLATED DUE TO SPECIFICATION X4AZOI REVISED e PIPE INSTALLATION OCCURRING TO INCLUDE SEPARATION l AFTER RACEWAY INSTALLATION REQUIREMENTS. 3. PPP PROCEDURES REVISED TO INCLUDE SEPARATION REQUIREMENTS. 4. SYSTEMS ALREADY INSTALLED WILL BE INSPECTED 165 RRF X II 22 0F 920 RT FILMS REVIEWED PPP PROCEDURE IX-HT-I-W77 CORRECTIVE ACTION REMAINS 4-057 HAD LINEAR INDICATIONS WRICH REVISED TO ASSURE RECORDING OF IDENTICAL AND ACCEPTABLE WERE NOT IDENTIFIED ON TRE RT ALL LINEAR INDICATIONS AND TRE REPORT (ALL INDICATIONS WERE 22 if REPORTS WERE REVISED TO JUDGED TO BE ACCEPTABLE) LIST ALL LINEAR INDICATIONS I66 RRF X III STOCK MATERIAL REQUISITION ERROR ADDRESSED ON DR. No. ISOLATED INSTANCE /ONE TIME 4-058 ENTRY IMPROPERLY DESCRIBED PP-09914 NOTE: ONLY I 0F I30 CORRECTIVE ACTION ITEM AS SCHEDULE 80 PIPE ITEMS REVIEWED WERE IN ERROR - INSTEAD OF SCHEDULE 40 INSTALLATION WAS CORRECT 167 RRF X III WELDING PROCESS SREET ENTRIES WERE CORRECTED BASED CORRECTIVE ACTION HAS CHANGED 4-059 INDICATED PROCEDURE DEVISIONS ON NDE REPORTS IN RECORD SEE SECTION 5.5
. THAT WERE OUT-OF-DATE AT TIME PACKAGE WHICH VERIFIED WORK WORK WAS PERFORMED WAS PERFORMED TO PROPER REVISION 168 RRF X III AS INSTALLED LOCATION OF PIPE DR NO. PP-IO.000 PREPARED AND ISOLATED INSTANCE /ONE TIME 4-060 FITTING EXCEEDS ALLOWABLE DISPOSITIONED "USE-AS-IS" CORRECTIVE ACTION TOLERANCE DUE TO INCORRECT -
INCORPORATION OF DRAWING REVISION s
Q Page No. 6 12/08/87 PLANT VOGTLE UNIT 2 READINESS REVIEW PROGRAM FOLLOW-UP OF UNIT 1 FINDINGS (RR.IDR.NRC) TABLE 5-4
=========-= ======================~=========================
EDIT SOURCE AND DESCRIPTION OF DESCRIPTION OF UNIT I DESCRIPTION OF UNIT 2 NO FINDING DESIGN CONST LEVEL FINDING CORRECTIVE ACTION FOLLOW-UP ACTION
===e ===== ====== == ====== ====== ===== ============================== =e============================ ======================== =====
169 RRF X III JUSTIFICATION STATEMENTS FOR A RANDOM SAMPLE OF DR'S CORRECTIVE ACTION REMAINS 4-061 USE-AS-IS OR REPAIR WRITTEN PRIOR TO REVIEW OF PRM IDENTICAL AND ACCEPTABLE DISPOSITIONS ON 23 0F 100 DR'S (6-83) WILL BE REVIEWED TO ARE UNCLEAR DETERMINE WHETHER JUSTIFICATION STATEMENTS ARE ADEQUATE OR COULD BE FURNISHED IF REQUIRED 171 RRF X III ONE OF 15 DWGS. REVIEWED AT 1. RESPONSIBILITT FOR CORRECTIVE ACTION HAS CHANGED 4-063 PPP FIELD DOCUMENT CONTROL MAINTAINING CONTROL OF FIELD SEE SECTION 5.5 . STATION WAS OF AN IMPROPER ENGRS. STICK FILES WILL BE REVISION ASSIGNED TO PPP DWG. CONTROL PERSONNEL, 2. PPP SITE INSTR. 73 WILL BE USED TO VERIFY PROPER CONTROL OF DWGS., 3. SUPERSEDED DWGS WILL BE RETURNED WHEN OBTAINING NEW DWGS. 172 RRF X III REQUIRED INSPECTIONS OF " TROT INSPECTIONS WILL BE DOCUMENTED ISOLATED INSTANCE /0NE TIME 4-064 1" STORAGE AREA NOT DOCUMENTED IN THE FUTURE AMD DEFICIENT CORRECTIVE ACTION AND STORAGE DEFICIENCIES WERE CONDITIONS WERE CORRECTED IDENTIFIED AT 2 LOCATIONS IN CONTAINMENT 173 RRF X III DR No PP-5624 ERRONEOUSLT DR NO. PP-9928 WAS ISSUED TO ISOLATED INSTANCE /ONE TIME 4-065 REFERENCED ANSI B31.1 POWER CORRECT THE ERRONEOUS ENTRT CORRECTIVE ACTION PIPING CODE INSTEAD OF ASME SECTION III. THE INSTALLATION WAS TO ASME III AND THE ANI CONCURRED WITH THE DISPOSITION 174 RRF X III FAILURE TO REVISE DESIGN ISSUE DMCN'S TO DELETE CORRECTIVE ACTION REMAINS 4-066 MANUAL TO REFLECT DELETED REFERENCES TO DC-1023 IDENTICAL AND ACCEPTABLE DC-1023 175 RRF X III FAILURE TO LIST CDC-4 ON COVER DC-1018 REVISED TO LIST GDC-4 CORRECTIVE ACTION REMAINS 4-067 SHEET OF DC-1018 REY. 2 DUE ON COVER SHEET IDENTICAL AND ACCEPTABLE TO EDITORIAL OMISSION t I
Page No. 12/08/87 O 7 O O ., PLANT VOCTLE UNIT 2 READINESS REVIEW PROGRAM FOLLOW-UP OF UNIT I FINDINGS (RR.IDR.NRC) TABLE S-4
============================================================
EDIT SOURCE AND DESCRIPTION OF DESCRIPTION OF UNIT I DESCRIPTION OF UNIT 2 NO FINDING DESIGN CONST LEVEL FINDING CORRECTIVE ACTION FOLLOW-UP ACTION
=== =============== ====== = ==== ==e== ============================== ============================== ==============================
P 1 176 RRF X III FLOODING CALCULATIONS NOT CALCULATIONS UPDATED AND CORRECTIVE ACTION REMAINS ! 4-068 IDENTIFIED AS "Q" RELABELED AS "Q" IDENTICAL AND ACCEPTABLE 177 RRF X III REFERENCES 4 & 7 TO CALC. ADMINISTRATIVE ERRORS IN CALC. CORRECTIVE ACTION REMAINS 4-070 X7Cl301 V03 REV. O DATED CORRECTED (WRONG DOCUMENT IDENTICAL AND ACCEPTABLE 11-2-84 DO NOT CONTAIN NUMBERS USED) INFORMATION USED IN THE CALCULATION i 178 RRF I III QUALITY CLASSIFICATION FOR CALCULATIONS REVISED TO SHOW CORRECTIVE ACTION REMAINS 4-071 HAZARDS CALCULATIONS NOT IN "Q" CLASSIFICATION , IDENTICAL AND ACCEPTABLE ACCORDANCE WITH PRM. PART C. SECTION 9.6 . 179 RRF X II NO EVIDENCE THAT THE ALL AFFECTED CALCS. REVIEWED CORRECTIVE ACTION REMAINS 4-072 RESPONSIBLE HAZARDS ENGINEER TO CURRENT LDL. AND NUCLEAR IDENTICAL AND ACCEPTABLE IS AWARE OF MULTIPLE REVISIONS P4ZARDS GROUP SUPERVISOR ADDED TO LDL (APPLICABLE TO CALCS. AS SIGNATORT TO LDL I6 CIA, & X6CIC_) -[ 180 RRF X III CONFLICT IN AVAILABLE WATER I4AF02 (27 DAYS) IS CORRECT, CORRECTIVE ACTION REMAINS 4-073 SUPPLY WITROUT MAEEUP IN DC-1202 REVISED IDENTICAL AND ACCEPTABLE i DC-1202 (30 DAYS) AND SPEC. X4AF02. REY. 9 (27 DAYS) 181 RRF I III 5 ARBITRARY PIPE BREAKS DMCN'S TO BE SUBJECT TO CORRECTIVE ACTION RE;4AINS 4-075 DELETED IN CALC. X6CXB-74 STATUSING IN THE SAME MANNER IDENTICAL AND ACCEPTABLE RESULTING IN CONFLICT WITH AS OTHER CHANGE DOCUMENTS DC-1018, 3.3.B.3.C DUE TO LOSS (E.G.. DCN'S. FCR'Sr ETC.) 0F CONTROL OF DMCN 182 RRF X I PRM PROCEDURES DO NOT ADDRESS DC-1003 FLOODING CRITERIA. CORRECTIVE ACTION REMAINS 4-078 THE INTEPFACE. COMMUNICATIONS ISSUFD TO PROVIDE ADEQUATE IDENTICAL AND ACCEPTABLE AND DOCUMENTATION REQ'TS TO MEANS OF DISSEMINATING ASSURE ADEQUATE INTERFACE FLOODING ANALYSIS RESULTS TO BETWEEN PISCIPLINES FOR AFFECTED DISCIPLINES (ALSO SEE FLOODING ANALYSIS RRF 4-96) 183 RRF I III CALCULATIONS PERFORMED BT CALCULATIONS REVISED TO CORRECTIVE ACTION REMAINS 4-079 COMPUTER PROGRAM TE-601 DO NOT INCLUDE NECESSART INFO. PLUS IDENTICAL AND ACCEPTABLE INCLUDE PURPOSE. ASSUMPTIONS. ADDED TRAINING ' REFERENCES. OR CRITERIA AS RE0'D BY ANSI N45.2.ll s _ _ _ _ _ _ _ _ _ - _ _ _ - _ _ _ ....._m _ _ , .
Page No. O 8 O 12/08/87 PLANT VOC^ .E UNIT 2 READINESS REVIEW PROGRAM FOLLOW-UP OF UNIT I FINDINGS (RR.IDR.NRC) TABLE 5-4
=================================================,==========
EDIT SOURCE AND DESCRIPTION OF DESCRIPTION OF UNIT I DESCRIPTION OF UNIT 2 NO FINDING DESIGN CONST LEVEL FINDING CORRECTIVE ACTION FOLLOW-UP ACTION
=== ====e========== ====== ====== ===== ====================e========= ========e=====-=============== == ===========================
-IR4 RRF X III DOCUMENTATION OF RATIONALE FOR RAZARD ANALYSIS WAS PERFORMED. ISOLATED INSTANCE /0NE TIME 4-080 RESOLUTION OF FCR'S WHICR REVIEW OF 20 ADDITIONAL FCR'S CORRECTIVE ACTION REQUIRE RAZARDS REVIL'W MISSING VERIFIED TRAT TRIS WAS AN ON MFCR-B-1368F ISOLATED PERSONNEL ERROR. NO CORRECTIVE ACTIONS REQUIRED 185 RRF X III PROJECT CLASS FOR ISOLATION CFASS OIC ADDED TO COVER CORRECTIVE ACTION REMAINS 4-085 VALVE ENCAPSULATION VESSEL F.'87. OTRER DOCUMENTS ARE IDENTICAL AND ACCEPTABLE IMPROPERLY LISTED ON COVER CsHRECT SREET FOR SPEC. X4AR04 186 RRF X I PRM PROCEDURES DO HOT CALCULATIONS (16CXB_ SERIES) CORRECTIVE ACTION REMAINS 4-986 ADEQUATELY ADDRESS HELBA ISSUED TO ASSURE ADEQUATE . IDENTICAL AND ACCEPTABIE CONTROLS INFORMATION AND DISTRIBUTION AND CONTROL (SEE INTERFACES RRF 4-096 ALS0).
187 RRF X III CALCULATION X4CKA-34 DID NOT CALCULATION REVISED AND CORRECTIVE ACTION REMAINS 4-OR9 INCLUDE ADEQUATE DESCRIPTION SIMILAR CALCULATIONS REVIEWED IDENTICAL AND ACCEPTABLE OF DESIGN INPUT FOR ACCEPTABILITY. FURTRER PERSONNEL TRAINING PERFORMED
-188 RRF X I PROJECT PROCEDURES INA9 EQUATE PROCEDURES REVISED TO ADDRESS CORRECTIVE ACTION REMAINS 4-096 FOR RAZARDS PROGRAM INCLUDING RRF'S 4-072 4-078 & 4-086 IDENTICAL AND ACCEPTABLE RAZARDS ANALYSIS, REL3A. TRAINING OF PERSONNEL RAZARDS FLOODING ANALYSIS & WALEDOWN PROGRAM FORMALIZED INTERDISCIPLINE INTERFACE ON LDL DATA WITR RAZARDS GROUP [
(COMBINATION OF RRF 4-072,- ' 4-078 & 4-086)
'IR9 RRF X III DR-8691 WAS NOT SUBMITTED TO DR-8691 WAS SUBMITTED TO ISOLATED INSTANCE /0NE TIME 4-097 Y-SAMU FOR REVIEW PRIOR TO V-SAMU FOR REVIEW. NO IMPACT CORRECTIVE ACTION
" ACCEPT-AS-IS" DISPOSITION TO STRESS ANALYSIS OR RANGERS.
TRIS WAS DETERMINED TO BE AN ISOLATED INCIDENT BASED ON REVIEW OF APPROXIMATELY 1000 DR'S I
6 PROGRAM ASSESSMENT O
6.1 INTRODUCTION
This section describes the assessments and evaluations performed
~
to ascertain whether the design and construction activities related to mechanical equipment and piping for the Vogtle Electric Generating Plant Unit 2 have been controlled in a manner that continues to implement licensing commitments, to ascertain whether the corrective actions resulting from the Unit 1 Readiness Review were applied to Unit 2, and to verify that the results of the design and construction activities conform to project procedures and design requirements. The Readiness Review Team assembled for Module 4 consisted of three Readiness Review Task Force members, two certified quality control inspectors, and three members of site Quality Assurance, with a combined experience of over 100 years of nuclear design and construction experience. The personnel are identified on Table 6-1. Approximately 2000 manhours were expended in performance of the module review and assessment activities. Discrepancies noted during review activities were issued to the Project as findings. The Project was required to respond in a manner that addressed the specific issue identified, that addressed project investigative action to determine possible Os generic implications, and that discussed remedial and/or corrective actions. These project responses were evaluated and the findings were assigned levels of importance as follows: o Level 1 - Violation of licensing commitments, project procedures, or engineering requirements with indication of safety concern. o Level II - Violation of licensing commitments or engineering requirements with no indications of safety concern. o Level III - Violation of project procedures with no indications of safety concern. Section 6.5 presents the findings, project responses, and the assigned finding level. O 0155d/005-8 6-1
. m M
i l
)
l l l 9 l l l 1 0, , 0155d/005-8 6-2
6.2 PROGRAM DESCRIPTION
.I \
The evaluation of the design and installation of mechanical equipment and piping in Vogtle Electric Generating Plant Unit 2 consisted of four major activities. These were 1) commitment implementation review; 2) followup on Unit 1 finding corrective actions as applied to Unit 2: 3) development and execution of an assessment plan to examine programs, activities, and hardware: and 4) evaluation of the results of the above activities. The plan for assessment of Unit 2 project activities related to mechanical equipment and piping was developed to accomplish the following: o Provide added assurance that project procedures continue to implement licensing commitments. o Evaluate the acceptability of installed hardware . o Verify that actions taken to resolve problems identified during Unit 1 Readiness Review have precluded recurrence in Unit 2. o Verify that program and organizational enhancements made for Unit 2 have not compromised the quality of the design and construction efforts. (~h o Evaluate the compliance of design change activities with
\~/ engineering procedure controls.
The assessment plan is prepared by the Readiness Review module team, accepted by the Readiness Review program manager, and evaluated and approved by the Readiness Review Board. The plan provides for a disciplined review of those project activities performed for completion of Unit 2 work on mechanical equipment and piping. The plan is based on results of the Unit 1 Readiness Review Program, including continuation of corrective actions necessary to resolve Unit 1 problems; results of Quality Assurance audits; Nuclear Regulatory Commission inspections performed subsequent to the Unit 1 Readiness Review programs; and other references as described in cection 5. Readiness Review evaluates the results of the assessment and where appropriate, issues a Readiness Review finding describing deficiencies and requesting a project resolution. O i f 0155d/005-8 6-3
-a. gam - c
_--_ a -a _ . .-a e - a.w,. m 4 -- - a a .- _a ;t O l ( l l l t l , 9 I l l l l l 4 i b G r
. 0155d/005-8 6-4
; Ljea-
> d0 g,.$&,
- v. f,43 '
IMAGE EVALUATION /+g, t '*,[ ' 'iff* </ /('j[A (fgj
\//o TEST TARGET (MT-3) \\ t /// /
90(7/ 'k I.0 E 522 i .:. 4 ,..'2 m !iiliw:== l,l . Ll 2.0 lh , 1.25 1.4 1.6 : 4 .._ .. .. _ _ - _ . - 150mm - > > r 4 ._. ... _
.____..._.---6" >
i 3..s> /A % 5% leg
$}%,7;r + eg% ~ .
p ,oAy h sg, )) i
,/
m; 3~ ^ //A to 4 9 - ,0,p,esj'},
" 4 %%
e.> i~ '. . . . . . . . . s.&:MM'h__a,, , , , ,
% 1
,y ,1't N
4 \ O
\///
o
)6, IMAGE EVALUATION TEST TARGET (MT-3)
'/'/ -
.?
e4
'$* ??g
\ llll s 9 l.0 m
l,l ;:51 M l.25 IA [ 1.6 i 'lll- - J sm-s 15 0 m m - - - - - - - - - - - - - - *
- 6" - - - - - - - - - - -
ll l '
$ ,g f/4%
+
, /%,y}, + 4;b ,
zy, y %y
~ . . . .a
N. s l*
./Q ~I$9
't, M <j7 p 1 IMAGE EVALUATION (g
#.4
\
/'
9h" TEST TARGET (MT-3) /
[~
qyyy ////p ! )<f[%
+
l w__.._._.._______---- 6" > 8 sy?%/, 5,, .
/ !b y ;vp o
, .o#
- s. . . & WN ,._ , _, _
~
o) o _&c c Q+ (O a a i.
,O,
";. V ^ IMAGE EVALUATION
</ .f'p[%* /g
\//o//q [ 'Q; f f TEST TARGET (MT-3)
,lll 4 ggy ? V lQ Y fi 44,,,g?p 1.0 : 2 Gli u J" 2.2 e . . gm l,l
~
f I l _1.8._ l l.25 i.4 i.6 , y l 4-- 150mm > 4.._________.__. 6" > v$:p;>
,/
~
/ ;xb
,gs //xxxN e
0 P,f,,h w' $#4 1/ ,
. @e n
;, : ~ . . . . . . . cal %!dN) -
.,3, m _M
[~ ! 6.3 -
SUMMARY
AND CONCLUSIONS
}*
( ; This module addresses safety-related American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section III, mechanical equipment and piping. Verification of the adequacy of the design and construction processes and results was accomplished by visually examining a selected hardware sample, by observing construction and inspection activities, and by reviewing design and construct.)n documents related to the sample. Criteria developed for selection of the sample and assessment attributes are discussed in Section 3.5 of the Readiness Review Procedures and the Module 4 assessment plan. The assessment samples were selected from three piping systems; , component cooling water, residual heat removal, and the auxiliary feedwater. Installed hardware was evaluated by performing a walkdown of approximately 500 feet of pipe, including 132 welds and 7 major i pieces of equipment; by observing and reviewing nondestructive examinations and/or records; and reviewing quality documentation related to the installed items. Design activities were assessed by reviewing 30 licensing commitments, 14 drawings, 5 calculations, 12 change documents, and other design-related documents. The assessments emphasized installation of piping and equipment, review of quality records, and design changes.
,7 Assessment plans addressed:
s
\~'I o Implementation of licensing commitments. I o Unit 2 continuation of corrective actions resulting from the Unit 1 Readiness Review activities.
o Evaluation of the effects of program revisions and/or Unit 2-specific programs. In addition, because portions of the piping systems were installed during the period when Unit 1 programs were in effect for both units, selected checklist attributes were chosen to evaluate activities and installations performed during that period. The Unit 2 assessments resulted in 11 findings, 2 of which were classified as Level II, and nine as Level III. The findings were judged to be isolated instances of failure to comply with engineering requirements or construction procedures with no indications of safety concern. The individual findings and the Project retponses are presented in section 6.5. Evaluation of the findings for collective significance resulted in no areas of concern, and with correction of the specific _ findings identified in this report, design, and construction i v 0155d/005-8 6-5 n !
activities within the scope of this module comply with licensing commitments. G e 0155d/005-8 6-6
- - . . . . - - .. .. . ~~ . . -
6.4 ASSESSMENTS AND RESULTS [ Assessments were performed according to a series of checklists
% addressing the following general subjects: ;
o Implementation of licensing commitments. , o Followup of corrective actions which resulted from the i Unit 1 Readiness Review Program. .. o Project responses to requirements of the quality ! program, procedures, and design criteria and documents. I a Modifications To Assessment Plans j , Certain evaluations which the Readiness Review task force ! originally intended to perform as described in the assessment plan wero deleted or reassigned to alternate modules as described below: o Assessment of onsite mechanical equipmenc modifications : was deleted because none were being performed during the !' assessment period (Checklist RR-004-207 deleted). The project equipment modification program was evaluated during the Unit 2 Module 6, Electrical Equipment, assessment. o Assessment of equipment installation in progress was deleted because no mechanical equipment was being installed during the assessment period (Checklist RR-004-208 was deleted). Checklists RR-004-307 and RR-004-319 address evaluation of installed equipment. o Assessment of the construction acceptance tests and i system flushing was not performed because they are included within the scope of' Module 3A (Checklists i RR-004-313 and RR-004-320 through RR-004-323 were l deleted). l o Implementation of the finalization programs was not l a.sessed because there was no project activity during
*ae assessment period. However, the programs were reviewed and found to be acceptable (Checklists RR-004-303, RR-004-305, and RR-004-306 were deleted). i I l Planninc/ Preparation l
The development of the assessment plans was based upon the ' reference sources presented in more detail in section 5 of this module. The primary references evaluated for identification of suitable items for assessment are: lO 0155d/005-8 6-7
o Unit 1 Readiness Review Program results (including Independent Design Review (IDR) and Nuclear Regulatory Commission (NRC) reports, etc.). o Project QA audits.(a) o NRC inspection reports.(a) o Industry problems (as identified by I&E notices and bulletins).(a) o Quality Concerns.(a) Review of the Unit 1 Readiness Review Report, the IDR Report, and associated NRC inspection reports, established that there were 13 violations reported by the NRC and 10 Level I findings reported by the Readiness Review and IDR Teams. Checklist items identical to, or representative of, the reported deficiencies were included in the assessments. Table 6-2 lists the findings with their corresponding checklist items. To support the assessment objectives, the plan uses the data developed by the Unit 1 program. Unit 1 conclusions are retested because the sample selected for evaluation represents Unit 2 activities performed prior to the Unit 1 program (but not part of the sample) and after closure of the Unit 1 Readiness Review Program. Samples for this assessment (reference Table 6-3) were selected from three systemi (substitutions, when necessary, are identified on the checklists and in backup documentation); the component cooling water (CCW), residual heat removal (RHR), and the auxiliary feedwater (AFW) systems. All the systems selected are safety-related American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code, Section III, systems. The AFW system was selected because it represents Georgia Power Company's (GPC) activities as an installer of ASME systems under their ASME NA-certificate of authorization. The CCW and RHR systems include piping systems of ASME Classes 1, 2, and 3, interface with each other, and reflect activities of Pullman Power Products (PPP) as installer under their ASME NA-certificate of authorization.
- a. These references which are within the module scope, were published after completion of the Unit 1 Readiness Review Module 4 activities, g 0155d/005-8 6-8
6.4.1 PART 1, COMMITMENT IMPLEMENTATION AND FINDING FOLLOWUP The objectives of this portion of the assessments were to verify O- the recognition of licensing commitments and adequacy of the response (implementation) to those commitments. The commitment matrix-(section 3.2) contains 250 entries including 2 entries from the generic program commitments of the Final Safety Analysis Report (FSAR), Chapter 17. Of these commitments, a total of 30 were selected for assessment. Table 6-4 lists those commitments and the basis for their selection. During the Unit 1 program, the NRC identified 13 violations, the Readiness Review Team identified 3 Level I findings, and the IDR identified 7 Level I findings. These items, and the related Unit 2 checklist items addressing followup of corrective actions in the Unit 2 assessment, are identified in Table 6-2, 6.4.1.1 Commitment Implementation ' Licensing commitments are contained in the FSAR and in correspondence to the NRC. The commitment matrix presents the summary listing of the licensing ccmmitments identified during the Unit 1 Readiness Review Progran and updated for the Unit 2 program. Implementation of commit:nents is the responsibility of the Project and is demonstrated ir design documents, procedures, installed hardware, quality records, etc. The implementation of 1 O each commitment is reflected in the implementation matrix (section 3.2) by listing the implementation documents for the Module 4 commitments. i In preparation for the Unit 2 Readiness Review Program, the Readiness Review Task Force revised the commitment matrix to reflect the current project status and the module scope boundaries. This revision resulted in the deletion of 35 entries and the addition of 27 entries resulting in 248 entries - in the matrix (including 2 from chapter 17 of the FSAR). Approximately 100 editorial changes were made to clarify ; commitment subjects or improve the ability to locate the source of the specific entry. The implementation matrix was also revised to incorporate the revisions and clarifications resulting from the combined i NRC/ Readiness Review analysis of the Unit 1 report, to reflect the most recent implementation status, and to identify those new ! or revised commitments for which implementation had not been previously determined by the Readiness Review Task Force. The commitment and implementation matrices, as revised by the Readiness Review Task Force, were furnished to Project Engineering and Construction for the identification and updating , of the references to implementing documents. The revised . i 0155d/005-8 6-9 i
1 implementation matrix was returned to Readinees Review for incorporation of the revisions. Readiness Review Assessment The Readiness Review Task Force reviewed 30 commitments (listed in Table 6-4) to determine if the following requirements have been met: o Whether licensing commitments had been recognized and are addressed in primary design / construction documents [e.g., design criteria, piping and instrumentation diagrams (P& ids), construction specifications), and whether responses to those commitments have been included in the appropriate working level documents (e.g, calculations, drawings, construction procedures). o Whether the commitment and implementation matrices revised by the Project are accurate and demonstrate proper implementation of licensing commitments. The updated implementation matrix was assessed by comparing it with the Readiness Review evaluation of the 30 commitments. It was found to be accurate; however, there were a number of editorial changes necessary to assure consistent entries related to Design Manual Change Notices (DMCNs). As a result, a combined Project and Readiness Review Team reviewed both matrices and incorporated editorial clarifications. No findings were issued. During the Readiness Review evaluation of the implementation matrix, one Level II finding and two Level Ill findings (not directly related to the sample of 30 commitments) were identified when reviewing implementing documents. Thesa findings are summarized below and presented in detail in section 6.5. o Finding 2RRF-004-003 (Level II) Contrary to the requirements of the Vogtle Nuclear Plant Design Manual, the listing of certain NRC regulatory guides was deleted from mechanical heating, ventilation and air conditioning design criteria (1500 series). o Findino 2RRF-004-006 (Level III) The design requirements of system 1210, the boron recycle system, have been incorporated in Design Criteria DC-1208 but, because DC-1210 was not issued, there are no references to DC-1208. O i 0155d/005-8 6-10 i I l
o Finding 2RRF-004-012 (Level III) ( An ASME preface page, required by the Project Reference Manual for component design specifications for ASME B&PV Code, Section III, components was not consistently included in specifications prepared by the Mechanical Design Group. None of these findings, either individually or collectively, had an effect on the installed hardware, nor did they indicate a potential safety concern. 6.4.1.2 Unit 1 Finding Followup In order to determine whether Unit 1 corrective actions continue to be implemented in Unit 2 programs and work activities, Project Engineering and Construction reviewed the Unit ' NRC violations and Readiness Review and IDR findings. The results of these reviews are presented in section 5 of this module. . Readiness Review assessed the accuracy of the Project review and continued acceptability of corrective actions by including appropriate checklist items in parts 1, 2, and 3 of the assessments for each NRC violation and Level I finding as described on Table 6-2. () There were no findings issued as a result of the assessments and the sample of corrective actions resulting from the Unit 1 Readiness Review program have been properly implemented in the Unit 2 programs. 6.4.2 PART 2, PROGRAMS AND ACTIVITIES The objectives of part 2 of the assessment were to examine the i design procedures for: l o Design change control. o Calculation content and control. o Changes to the design control programs. l l and the construction processes for: l i o Installation activities. o Continued response to programs necessary for resolution l of Unit 1 findings. 1 o Program and organizational responsibility changes unique () to Unit 2. l 0155d/005-8 6-11
6.4.2.1 Design Chances The design portion of part 2 examined the implementation of , design programs. Eleven change documents, five calculations, and six drawings were sampled during this assessment. Activities and results are summarized below and the samples are ; described in detail on Table 6-3. The review included an I evaluation of interdiscipline review, conformance to the FSAR, ) incorporation of changes within procedural limits, impact of I design changes on previous installations, and the control and l technical adequacy of calculations. Tne above attributes of the i design change program were assessed and determined to be { acceptable. Field Equipment Chance Orders ; I Field Equipment Change Orders (FECOs) were evaluated using Checklist RR-004, which assessed the following attributes: o Authorization by original equipment supplier. o References included for all documents required. o Replacement materijl procured from original supplier or an acceptable alternate source. o FECO evaluated by Quality Assurance. o Adequate justification furnished for the change. Four FECOs were identified which were applicable to equipment included in the assessment sample. All four were reviewed and no deviations from checklist requirements were found. Drawina Change Notices / Field Chance Requests Drawing Change Notices (DCNs) and Field Change Requests (FCRs) were evaluated using Checklist RR-004-201 to address the following attributes: o Whether interdiscipline reviews were performed when required. o Whether a licensing deviation document was prepared to resolve conflicts with FSAR. o Whether changes were incorporated within procedural time limits. o Whether changes were technically adequate. o Whether appropriate calculations were revised. O 0155d/005-8 6-12
1 o NA/NA FCR (without design document change) conformance
. to Project Reference Manual (PRM) guidelines.
Five FCRs and two DCNs were examined and all complied with the . applicable checklist attributes. ! Desion Drawincs I Six piping and instrumentation diagrams (P& ids) were evaluated ! using checklist RR-004-204 for response to the Project Reference ; Manual requirements, response to design criteria, licensing ! commitments, approvals, conformance to supporting calculations, and revision of affected documents, if required. In addition, P&ID 2X4DB119 was individually evaluated and it was noted that , the boron recirculation loop had been entirely deleted. This , design change conflicts with FSAR Table 3.2.2-1 and Design Criteria DC-1010, revision 5, of the Vogtle Design Manual. This deficiency is summarized below and described in detail in Section 6.5. o Findinc 2RRF-004-005 (level II) , A single P&ID (of six reviewed) was issued which deleted - a system mandated by the design manual but a DMCN was not simultaneously issued as required. This finding was an isolated human error which did not affect () installed hardware and does not present a potential safety concern. } l Calculations Five calculations were assessed to evaluate technical adequacy I and compliance with project calculation control-procedures using - Checklist RR-004-203. The review addressed accuracy, content, i conformance to design criteria, reference to appropriate codes and standards, compliance with guidelines for documenting assumptions, input data, and proper entry in control logs. v During the assessment, three findings were issued, as summarized below, and are presented in detail in Section 6.5. ; o Findinc 2RRF-004-002 (Level III) A calculation was listed as valid rather than void on [ the Calculation Control Log even though the calculation j was clearly identified as "no longer needed" within the i body. o Findinc 2RRF-004-004 (Level III) , The five calculations do not contain clear descriptions as to unit applicability and the PRM does not clearly ! () address the subject. ; 0155d/005 6-13 j i e f
o Findino 2RRF-004-007 (Level III) Calculation checkers failed to exercise proper attention to details by not identifying and correcting numerical transposition errors and revision-specific limits on applicability within the body of calculations. However, the calcplation results are valid and hardware was not affected. None of those conditions described affected installed hardware nor do they indicate a potential safety concern. 6.4.2.3 Construction Assessments The construction portion of part 2 mo".itored work-in-progress subjects such as those listed below! o Working document packages. o Installation activities and response to construction procedures. o Welding and nondestructive examination. o inspection and inspection records. o Personnel qualification status. , These assessments (reference Table 6-3 for samples) were conducted by Project Quality Assurance using checklists prepared by Readiness Review. The assessments were conducted by observing installation activities, observing inspections and the preparation of inspection records, and reviewing completed (supporting) quality documentation. The installation activities of both ASME-authorized NA installers (reference section 4), PPP and GPC Nuclear Construction Team, were assessed. The procedures reflected construction specifications and were properly implemented. One Level III finding, as summarized below and described in greater detail in Section 6.5, was issued during these assessments: o Finding 2RRF-004-008 (Level III) The GPC NCT uses an index of welding procedures and nondestructive examination requirements to assure that only approved procedures are utilized. This index was incomplete in that it did not include requirements for l l 0155d/007-8 6-14
piping class LL1 (subsequently, the project identified
~s two additional pipe classes which were not included).
The finding did not affect installed hardware and has no potential safety concern because the project welding supervisor had properly prepared the Welding Record Forms (WR-5 and SA) which provide directions for welding and nondestructive examination. 6.4.3 PART 3, CONSTRUCTION AND DESIGN COMPLETION The objective of part 3 of the assessment was to evaluate the completion processes by examining: o A Change Control Package (CCP). o Acceptability of as-installed hardware. o Retrievability and acceptability of quality documentation. o Personnel certification records. The assessment samples for part 3 are described on Table 6-3. The quality documents reviewed were selected from those necessary to support work activities assessed in both parts 2 () and 3. 6.4.3.1 Desion Completion l l CCP B10310P was examined for satisfactory response to l Checklist RR-304-301. The characteristics evaluated include the j items listed below: j o Proper preparation, content, and approvals. o Design change bases, conformance to licensing commitments, and impact on other design documents or i discipline groups. l o Control of corresponding interim design change documents. The CCP was determined to be complete and responsive to appropriate project program requirements. 6.4.3.2 Construction Completion Installed equipment and piping was walked down and examined for appropriate and acceptable response to design requirements, care () and maintenance after installation, and based on data collected 0155d/005-8 6-15
during the walkdown, the acceptability and retrievability of quality documentation. The walkdowns were conducted according to the requirements of Readiness Review Checklists RRF-004-307, -308, -309, -310, -311, -312, -314, -315, -316, -317, -319, and -325. The assessment characteristics of installed hardware included: o Freedom from damage and evidence of maintenance, o Installed location, dimensional details, and clearances in conformance with design requirements. o Proper item and material identification. o Valve location and orientation. o Visual weld acceptability. o Bolting. The following records were retrieved from the storage vaults or active files and evaluated: o Maintenance records. o Welding and nondestructive examination records. o Installation process sheets. o Material and ASME component traceability and documentation. o Leak test records. o Certification status of inspection personnel. o Identification and qualification status of welders. The assessment demonstrated that the hardware sampled was installed and maintained properly and that quality documentation was readily retrievable and acceptable. The three findings issued during this assessment are summarized below and presented in greater detail in section 6.5. o Finding 2RRF-004-001 (level III) Due to lack of procedural clarity, it appeared that field engineers were performing an in-progress verification of equipment cleanliness, which was restricted to individuals certified to perform that activity in accordance with ANSI N45.2.6. O 0155d/005-8 6-16
o Findino 2RRF-004-009 (level III) ( Engineering was found to be using an attachment to GPC l Field Procedure MD-T-25 as an unauthorized (not i addressed procedurally) means of transmitting design . information, j o Findinc 2RRF-004-013 (level III) , t-A PPP procedure (Site Instruction SI-53) was incomplete in that it' failed to require seal welding of threaded 1 vents and drains added to radioactive lines by issue of an FCR facilitating hydrotesting. Of the three findings described above, only Finding 2RRF-004-013 had a potential effect on installed hardware by permitting a threaded joint on a radioactive line to be accepted without the specified seal weld. The project has directed PPP to seal weld all threaded joints on all vents and drains in radioactive service and PPP has revised their procedures and site i instructions to clarify this requirement. A review of all Unit 2 radioactive systems hydrotested to date verified that seal welding of vents and drains had been accomplished. None of the findings represent a potential safety concern. , O 0155d/005-B 6-17 i e
-l
_s ,. A, . - -- -,> _ -. aa-. .a n--a... O O I i i O 0155d/005-8 6-18
6.5 FINDINGS
) This section presents, in numerical order, the eleven findings issued during the assessment. Each finding contains the requirements, the deficiency, the project response, and the Readiness Review conclusion. A summary listing of Unit 2 findings is presented in Table 6-5.
O) u l A 0155d/005-8 6-19
Finding 2RRF-004-001 (Level III) Requirements:
- 1. American National Standards Institute (ANSI) ANSI N45.2.6 requires qualification of personnel who perform inspections.
- 2. Pullman Power Products (PPP) Quality Assurance (QA) Manual, paragraph. 10.3.1, states " Inspection shall be performed by a QC inspector to verify . . . quality requirements specified . . . have been obtained."
PPP QA Manual, paragraph. 10.4.1, states " Personnel performing inspections shall be qualified as required . . . PPP QA Manual, paragraph. 10.4.2, states "The site organization . . . precludes the possibility that inspections are performed by personnel who report to an immediate supervisor who is responsible for the work being performed." Findino: Contrary to the requirements described in various documents such as those summarized above, PPP Project Procedure IX-48 (1-9-48), paragraph 4.3.1.B allows:
- 1. Qualified but noncertified personnel (field engineers) to perform verification of cleanliness and freedom from damage during the installation of both safety and non-safety related equipment.
- 2. Allows inspection by field engineers who report to the same craft superintendent as the craft performing work.
Project Response: A review of PPP Project P';ocedure IX-48 revealed areas which inadvertently allow an interpretation by the reader that Quality Control (OC) hold pointo may be signed off by the field engineer. The verifications (not inspections) performed by the field engineer represent a program enhancement and in no way relax / relieve the required QC inspections. These QC inspections are performed (1) upon receipt of equirra nt, (2) prior to issue, and (3) at final acceptance /walkdown of installed equipment. It is the field engineer's responsibility to assure that cleanliness and freedom from damage of equipment is maintained
- and his sign-off is included on the process sheet to document this action.
l This finding resulted from a misinterpretation of the procedure and no remedial action is required. 1 0155d/005-8 6-20
In order to clarify the intent of PPP Project Procedure IX-48, it is.being revised to include separate engineering hold points / sign-off on the process sheets. The body of the procedure will also identify engineering involvement as ,
" verifications" instead of " inspections". This revision will be i submitted to Georgia Power Company (GPC) for review / approval by July 31, 1987. Full implementation of the revised' procedure will be no later than August 31, 1987. ;
Readiness Review
Conclusion:
The Project response accurately identified the concern as a lack , of clarity in the procedure and the lack of a definitive description of a " verification" versus an " inspection". The procedure text was revised to clarify the intent of f
" verifications" performed by qualified personnel (field engineers), and the process sheet was revised to clearly !
discriminate between activities to be performed by field ! engineers or by certified QC inspectors. ; The PPP QA Manual was revised to establish the independence of i the field engineer from the craft superintendent when he is , performing the verification of certain activities by establishing his relationship to the engineering manager and the ;. area manager. I l l I l l O ; 0155d/005-8 6-21
-. -. .. -. . -. . -. _I
Finding 2RRF-004-002 (Level III) Reatirements: The Project Reference Manual (PRM), section C9.5.2, revision 5, states that "The EGS is responsible for updating the Calculation Control Log. The log reflects ' superseded', ' void', etc. as necessary. Project administration enters an 'S' for superseded calculations and a 'V' for voided calculations adjacent to the last issued revision number recorded." Finding: Calculation X4Cl302V05, revision 3, Verification of (AFW) System Multiple Steam Generator Depressurization, is entered in the Calculation Control Log dated March 24, 1987, as status A, indicating that it is currently a valid calculation. On page 3A, the third paragraph states, in part, " . . . this calculation is no longer required." Since this calculation is no longer required, it should have been voided and the Calculation Control Log updated to reflect the changed status. Project Response: The failure of the engineer to follow the procedure is considered to be unique to Westinghouse /Bechtel Western Power Company (BWPC) interface involvement. In addition, no other known discrepancies of failing to properly void calculations & W have been previously noted. Engineering randomly sampled and reviewed four approved calculations of the category involved and determined that they were correctly statused; therefore, this condition is considered to be an isolated case. There is no impact on hardware or documentation since the proposed change was not used and the calculation has been voided. Calculation X4Cl302V05 has been voided. Mechanical design engineers will be retrained by September 30, 1987, on voiding calculations. Readiness Review
Conclusion:
The calculation was voided and personnel training was completed on September 28, 1987. This satisfies the Readiness Review finding. O 0155d/005-8 6-22
-l Finding 2RRF-004-003 (Level II) l ) Reauirements:
Final Safety Analysis Report (FSAR) paragraph 6.2.2.1.1.1.G l states that the containment cooling system is designed and i fabricated to codes consistent with Regulatory Guides 1.26 and 1.29. Paragraph 3.4.1 of the Vogtle Nuclear Plant Design Manual Preface states that the " design criteria cover page . . . j provides a centralized location for . . . regulatory commitments i
" Paragraph 3.4.1.8 requires listing the Nuclear Regulatory Commission (NRC) c3cuments which apply to the particular system or structure, and the basis for preparation of this portion of the cover sheet shall be the acceptance criteria listed in paragraph II of the corresponding standard review plan. The criteria listed in paragraph II, section 6.2.2 of the standard review plan includes Regulatory Guides 1.26 and 1.29.
Finding: j On February ll, 1933, a Design Manual Change Notice (DMCN), DMCN . 1501-3 was issued which deleted Regulatory Guide 1.26 and ! Regulatory Guide 1.29 from the cover page of DC-1501, The , Containment Air Cooling System. Regulatory Guide 1.26 defines the classification of systems and components while RG 1.29 l requires systems to withstand a safe shutdown earthquake. Vogtle Electric Generating Plant conforms to both regulatory ' O guides as shown in FSAR Table 3.2.2-1. Paragraph 3.4 of DC-1000-M, General Design Criteria (Mechanical) refers to the i individual system design criteria for NRC regulatory guides. l Proiect Response: ; Engineering has reviewed the deletion of regulatory guides from the cover page of the design criteria and has concluded that the ; deletion was made during design verification review (DVR) ! activities for DC-1501, which occurred in late 1982, early 1983. i Design criteria from other disciplines have been reviewed for i deletion of regulatory guides. It has been determined from the review that the deletion of regulatory guides from the cover page is limited to the DC-1500 series; i.e., mechanical heating, j ventilation, and air conditioning criteria. It appears that ;
=
during the DVR process, the requirement identified in paragraph 3.4.1.8 of the Design Manual Preface 3, was applied verbatim. Paragraph 3.4.1.8 states, " Listing of the NRC documents which apply to the particular system or structure. The basis for preparation of this portion of the cover sheet shall be the acceptance criteria listed in Paragraph II of the corresponding i Standard Review Plan." The above review also determined that the deletion of the regulatory guides was for those that were generic in nature such as: Regulatory Guides 1.26, 1.29, 1.53, () 1.75, 8.8, etc. The system-specific regulatory guides were not , I 0155d/005-8 6-23 i
deleted (probably because they were identified in paragraph II of the respective standard review plan) with the exception of Regulatory Guide 1.45 in DC-1501. Regulatory Guide 1.45 seems to have been deleted in error. A review of the design for the containment building air cooling system concluded the the deletion of the noted regulatory guide had no effect on hardware; however, DC-1501 will be revised to include Regulatory Guide 1.45 to eliminate documentation concerns. The deletion of the generic regulatory guides will have no impact on hardware, since they are addressed in the interdiscipline design criteria and have been applied, with the exception of quality assurance regulatory guides such as Regulatory Guide 1.28 and Regulatory Guide 1.29, which are programmatic types, and are not specifically required for a system design criteria. In lieu of revising the DC-1500 design criteria to include the generic regulatory guides, Engineering has elected to revise the Mechanical Discipline Design Criteria DC-1000-M, paragraph 3.4 to also refer to the interdiscipline design criteria. Readiness Review
Conclusion:
Readiness Review finds the response acceptable for explaining the cause. Hardware was not affected and the remedial action has been completed and is acceptable. O l \ l O 0155d/005-8 6-24
Finding 2RRF-004-004 (Level III) Requirements: The PRM, paragraph C9.1, describes the purpose of section C9 as providing procedures used by engineering disciplines for design calculations for the VEGP project. PRM, paragraph C9.2, states that the scope of this section defines the procedures for preparing, checking, reviewing, and approving engineering design calculations. Finding: A review of Calculations X4Cl2O3VO1, X4Cl2O3V07, X4Cl205VOl. X4Cl302S12, and X4Cl302V05 did not disclose any statements which show the applicability of the calculation to either Unit 1 or Unit 2, or both. A review of the Calculation Control Log dated March 24, 1987, revealed the unit designation as A. PRM Figure C5-3 and paragraph 7.3.5 defines A as an item common to both Units 1 and 2. The applicability of a calculation to both Units 1 and 2 may have been indicated on the Document Review Notice (DRN) (unavailable for review) but a review of the form showed no specific place for it. Copies of the actual DRNs used for the above calculations were not available. In either case, no evidence remains to show that a calculation made for Unit 1 was also checked for its applicability to Unit 2. () Proiect Response: The unit designation is given in the Calculation Control Log. If the calculation is common to both units, an A is listed in the unit column. Changes which are specific for Units 1 or 2 calculations are also identified on the calculation change notice form if that form is used to identify a change. The five calculations specifically cited in the finding have been evaluated. Calculation X4Cl203V01 tabulates user flow requirements for the component cooling water (CCW) systems and is valid for both units. Similarly, Calculation X4Cl2O3V07 tabulates CCW heat exchanger heat loads for various operating modes and is valid for both units. Calculation X4Cl302S12 resizes the auxiliary feedwater (AFW) pump discharge orifices, based on the initial preop test results, which showed the original sizing to be conservative and is valid for both Units 1 I and 2. Calculation X4C1302V05 was voided on July 28, 1987 (reference RR-004-002); therefore, it is no longer valid. Calculation X4C1205V01 evaluates residual heat removal system piping pressure drops against Westinghouse guidelines. This calculation is valid for both Units 1 and 2. The Calculation Control Log shows all of the above calculations as being () applicable to both Units 1 and 2. 0155d/005-8 6-25
l i To programmatically document Engineering's practice of 4 identifying the unit designator for calculations in the l Calculation Control Log, Change Request 270 to PRM C-9 has been l initiated. This change request is in the review / approval cycle, ! l and is forecast to be approved by September 17, 1987. In l l addition, Engineering will review the Calculation Control Log to l confirm that the practice was followed. This review will be completed by September 15, 1987. I Readiness Review Conclusion f The Project response satisfies the finding and proceduralizes calculation control. The Design Manual has been revised, the review of the Calculation Control Log has been completed, and necessary revisions have been completed. 1 O l l l I r 9 O 0155d/005-8 6-26
Finding 2RRF-004-005 (Level II) Requirements: The Vogtle Nuclear Plant Design Manual, Preface, section 3.6, states " Revision to design criteria shall be issued within 60 days from identification of a need for a change or revision by an engineer: however, no design deviating from existing design criteria may be issued without advance, or simultaneous issue of a Design Manual Change Notice (DMCN)." Findinc: The original design of the safety injection system 1204 called for a boron injection tank recirculation loop consisting of the boron injection tank, two boron injection recirculation pumps, and a boron injection surge tank with an agitator and an , electric heater. This is the system currently shown on Figure 6.3.2-1 of the FSAR and is included in Table 1 of DC-1204. Prior to December 15, 1986, it was decided that this recirculation loop would not be required and revision 19 of piping and instrumentation diagram (P&ID) 1X4DB119 was issued, which shows all the above equipment and piping except the boron injection tank disconnected in Unit 1. As-built Notice 87-V1000A076 dated April 29, 1987, shows only boron injection tank 1-1204-V6-001 remaining in the system. P&ID 2X4DB119, revision 15, shows all of the recirculation loop deleted, () including the boron injection tank, from the Unit 2 safety injection system. As of this date, the boron injection tank is shown as item 2 under the SAFETY INJECTION SYSTEM on sheet 3 of Table 1 in DC-1010, revision 5, and as item 2 under the SAFETY INJECTION SYSTEM on sheet 3 of Table 3.2.2-1 in the FSAR. Project Response: The cause is attributed to personnel not following the procedure. l 1 The safety injection system is in accordance with the l Westinghouse design documents. Therefore, there is no hardware impact. The design criteria need to be revised to reflect the j designed system. To determine the extent, the engineering group supervisors (EGSs) were requested to identify 20 major changes. ) l A 40-percent sample (8) of the major changes identified were ' then reviewed in detail to determine if the requirements for revising the design criteria were met. As a result of the review, it was concluded that five of the eight changes were processed in accordance with the requirements, and three of the eight changes were processed before the DMCN was issued. () Further review demonstrated that the failure to follow the l i i 0155d/005-8 I 6-27 l
procedural requirement had no impact; i.e., the subsequently issued DMCNs and the design changes were compatible and the delay in issuing the DMCN was of no significance. A DMCN to DC-1204 and DC-1010 will be issued and a change notice to FSAR Table 3.2.2-1 will be initiated and submitted to Southern Company Services Licensing by September 30, 1987. A meeting attended by Design Engineering project engineers (pes) and EGSs was held on August 18, 1987, concerning the timeliness of issuing design criteria changes. As a result of this meeting, the pes and EGSs were made aware of the identified concerns and acknowledged the need to follow the procedural requirement when a design change deviates from the design criteria. A letter has been issued to Engineering personnel which reiterates the requirement to issue a design criteria change simultaneously or prior to issuing the design change. Readiness Review
Conclusion:
Readiness Review agrees that the response and the corrective actions are adequate to close this finding. The installed equipment is in accordance with the P& ids, the Design Manual has been revised, and FSAR change notices have been issued. O O 0155d/005-8 6-28
Finding 2RRF-004-006 (Level III) J Requirements: Design Criteria DC-1208, revision 1, paragraph 1.F, states, in parenthesis, that system 1210 shall be used for the boron , recycle system. Findino: The Line Designation List, calculations, drawings, and other design documents refer to piping and equipment in the boron recycle system as being part of system 1210. There are no indications in these design documents that the design criteria for this system is to be found in DC-1208. A cover sheet for DC-1210 should be issued showing the reference to DC-1208, along with an appropriate revision to the Design Manual Table of Contents. There is no indication in the Design Manual that DC-1210 was previously issued. Project Response: The cause is attributed to a personnel oversight when the DC-1210 cover sheet was not included in the Design Manual, with a reference back to DC-1200 for the boron recycle system criteria. The boron recycle system is a subsystem of the chemical and volume control system. Four additional design criteria were randomly sampled (DC-1218, DC-1407, DC-1305, and DC-1224) and a review of the design criteria referenced therein was performed to determine the extent. The results of the review determined that the design criteria referenced were valid. Therefore, the identified concern is considered to be an isclated case.
)
The design criteria for the boron recycle system is included as part of DC-1208. In addition, the system Design Specifications X4P1208 and X4P1210 refer to DC-1208 for the design criteria; therefore, no impact on hardware exists. To resolve the potential impact in documentation, the Design Manual will be revised to indicate that system 1210 criteria will be found in DC-1208. DC-1210 is scheduled to be issued by September 15, 1987. I No remedial actions are required. No actions to prevent recurrence are required. Readiness Review
Conclusion:
Readiness Review agrees that this finding is an isolated occurrence. The cover page for DC-1210 has been issued and this {} satisfies the concern. 1 0155d/005-8 6-29 1 l
l Finding 2RRF-004-OO7 (Level III) ' i Requirements: PRM, section 9, revision 5, paragraph 9.7.1.C, states, in part, "The checker is responsible for the following as applicable: verifying that the numerical results are consistent with the required mathematical accuracy of the calculation and that any numerical differences found do not affect the validity of the results. Checker signoff indicates that mathematical accuracy is appropriate and does not conflict with design commitments." Fjnding:
- 1. Contrary to the requirement, Calculation X4Cl302S10 (AFW Pump Motor Overloading) contains mathematical errors on pages 3A and 3B.
On page 3A the value of 1025 was misstated as 1205 when utilized in computing the value of K. Additionally, on page 3B, the value of K was misstated as 1240.5 versus 1204.5. Note: The calculation was rechecked and it was determined that, although the above numbers were not correctly stated, the actual computer calculation and results were accurate. The calculation has been revised to reflect the correct number.
- 2. The calculation has apparently been inadvertently invalidated during the preparation of revision 2 because the note on sheet 3B states " . . . the above entries . . . are applicable only to revision 1 of this calculation."
Project Response: For both finding items, the cause is attributable to personnel errors. For item 1, the originator and checker failed to identify the transpositional error even though the correct value wr3 used for input to the computer calculation. In the case of item 2, the originator and checker failed to consider the statement " . . . applicable only to revision 1 of this calculation" which was intended to avoid misuse of the orifice information after the hot functional testing results required a decrease in auxiliary feedwater purified discharge orifice size. To determine the extent of similar errors, Design Engineering examined all process calculations to identify the work of each checker and to review all calculations checked by the individuals involved in this finding. In the case of item 1, four additional calculations were reviewed and one, X4Cl206V01, wa; found to contain a similar transposition error, No additional calculations were identified where the checker for item 2 had checked other calculations. In addition, revision 3 of the calculation was issued to correct the oversight g 0155d/007-8 6-30
identified in finding item 2. The transposition errors on item 1 Calculation X4Cl302S10, revision 1, had no effect on I') hardware because the correct values were used for calculation k/ purposes. The transposition errors on Calculation X4Cl206V01 had no effect on hardware because the errors were not large enough to affect the final result; the calculation, however, will be corrected by October 30, 1987. To minimize the potential for recurrence, checkers have been verbally instructed to be more attentive when checking calculations. Readiness Review
Conclusion:
Readiness Review agrees with the Project responses. Both calculations have been revise 6 and the verbal caution to the checkers are adequate to close this finding. O </, N. 0155d/007-8 6-31
Finding 2RRP-004-008 (Level III) Requirements: l Georgia Power Company procedure FP-N-120.1 (issued for use by the Nuclear Construction Team), rev'sion 0, dated March 24, 1986, paragraph 2.3.1, states, in part "only the latest revision of welding procedures . . . specified . . . on the WM-2 . . . or other applicable documents shall be used." Finding:
- 1. The WM-2, a listing of welding and nondestructive examination (NDE) procedures for use on various classes of piping does not contain a listing of welding or NDE requirements for pipe class LL1 installed to the code criteria of American Society of Mechanical Engineers (ASME)
Boiler and Pressure Vessel Code (B&PV), Section III, Class 3.
- 2. No other documents were located which provided that information for preparation of the welding record sheet (WR-5).
Note: Pipe class LL1 to ASME B&PV Code, Section III, Class 3 is being installed by the Nuclear Construction Team. Readiness Review Comment: This finding is not related to hardware or quality. The project welding supervisor (PWS) specified the proper welding and NDE procedure on the WR-5. The quality records verify acceptable installation of Class LL1 piping assessed by Readiness Review. Project Response: The root cause of the finding was a failure to list pipe class LL1, Class 3 in the Nuclear Construction Welding Manual (Drawing WM-2), when the manual was originally published. The fact that pipe class LL1, Class 3 was not listed in the WM-2 is insignificant, since paragraph 2.1 of WM-2 provides directions for selection of a welding procedure when a pipe class is not listed. There has not been any impact, actual or potential, on hardware, technical adequacy, test results, etc., due to pipe class LL1, Class 3 not being listed in the WM-2. As a result of this finding, the PWS has compared Drawing WM-2 with Project Specification AX4DR001 (Piping Material Classifications) to determine that a sheet of " Welding and Nondestructive Examination Requirements" has been provided in WM-2 for all classes listed in AX4DR001. There were two other pipe classes (FG1, Class 3 and KKO, Class 3) identified that were not listed in the WM-2. O 0155d/005-8 6-32
t Drawing WM-2 was revised July 23, 1987, adding pipe class LL1, Class 3. Drawing WM-2 will be revised adding the other missing () pipe classes on or before August 21, 1987. When Project Specification AX4DR001 is revised, the PWS will revise Drawing WM-2 if required to provide welding and nondestructive examination requirements. Readiness Review
Conclusion:
The Project response and the addition of the missing data (completed) for pipe classes (FKO, Class 3; LL1, Class 3; and KKO, Class 3) satisfies the concern expressed in the finding. In addition, the Project has chosen to clarify procedural requirements to assure proper maintenance and control of WM-2 by revising GPC Field Procedure WG-A-01. O I l 1 0155d/005-8 6-33 i 1
Finding 2RRF-004-009 (Level III) Requirements: l FSAR Section 17A.3 states, in part:
- 1. "
. . . Engineering department . . . procedures, and instructions are employed . . .
- 2. "
. . . design changes, including field changes, are subject to design control measures commensurate to those applied to the original design . . .
- 3. "
. . . construction site changes to engineering design are documented by means of change notices or change requests which require authorization by Project Engineering . . .
Finding: Contrary to these requirements, the following has been noted:
- 1. GPC Field Procedure MD-T-25 (construction activities),
paragraph 4.5, directs engineering response to be recorded on the Separation Evaluation Notice described below. Readiness Review was unable to identify a corresponding engineering document accepting / authorizing enginee? :g response to the construction procedure.
- 2. Engineering is documenting accept-as-it conditions on seismic separation by providing a just?.fication statement on a Separation Evaluation Notice ( MD- T ,~. 6 , Exhibit 04, revision 0).
- 3. There appears to be a conflict in Appendix SC (referenced in MD-T-25) and DC-1005, paragraph 3.6.5.B. The design criteria specifies a seismic separation of 5 and 1/2 inches in the horizontal direction while Appendix SC allows a separation of 4 inches.
Proiect Response: , Investicative Action (Cause) l Items 1 and 2. The cause is attributed to personnel error when the determination was made that PRM procedure Appendix 2-21, Field Design Questions, was l adequate for addressing the MD-T-25 program. , Item 3. For attachments made to the exterior of a i structure crossing the seismic gap, l Seismic-Interdiscipline Design Criteria, DC-1005, par <'raph 3.6.5.B, specifies a horizontal separation of 5 and 1/2 inches. Appendix SC, g 0355d/005-8 6-34
Seismic Separation Criteria, which is referenced in the construction specification and field () procedure, specifies (in paragraph 2.1.6) a horizontal separation of 4 inches. This does not ' present a conflict between these two criteria as explained below. The horizontal separation of 5 and 1/2 inches between the components specified in DC-1005 was based on the calculated maximum structure-to-structure displacements and a conservative allowance for the component displacements and construction tolerances. This criteria was intended to be a conservative guideline to be followed during the design phase. DC-1005, paragraph 3.6.5.B, also states that exception to this criteria is allowed based on case-by-case evaluation by Engineering. During the independent design review of the Readiness Review Program for Unit 1, the subject of separation between components received a detailed review. The result was the development of the finalization program FP-14 and Appendix SC relating the seismic separation. The separation values provided in FP-14 and Appendix SC are supported by the guidelines provided by the chief () civil-structural engineer [ Reference Inte; office Memo (IOM) 4353 dated August 29, 1986 fram ; L. G. Hersh to D. Houghton). These guidelines for the Vogtle Project were developed from a i review of the types of equipment and Equipment l Qualification Data Packages by the chief I engineer's staff, and offer refined values for l component separation requirements. Based on j these refined values for component displacements and the calculated structure-to-structure displacements, a horizontal separation of 4 inches was determined to be adequate for , components with potential for crossing the j seismic gap. The guidelines specified 1.5 inches I as the generic criteria for component l separation. Adding to this are the maximum structure-to-structure displacements of 1.75 selected for use in Appendix SC. In summary, DC-1005 provided the separation dimension of 5 and 1/2 inches for obtaining a conservative design. Appendix SC provides the 4 inch separation dimension for field installation separation based on the evaluation ) discussed above, as allowed by DC-1005. ! 0155d/005-8 6-35 l I
(Extent) i Items 1 and 2. A multi-discipline meeting was held on July 29, 1987, to review methods for reporting, h controlling, processing, and dispositioning seismic separation notices by Construction and Engineering. Corrective action was taken by Construction and Engineering to revise Appendix SC, and Appendix 2, section 21, of the PRM and Field Procedure MD-T-25. As a result of this meeting, this concern was determined to be limited to MD-T-25. o Appendix SC was revised to clarify the scope for reporting seismic separation conflicts and to include separation requirements for non-IE conduit, fire protection piping, and small bore B31.1 piping (DRN FS-0441 dated August 12, 1987). o Appendix 2, section 21, was revised to define the program for the review, control and disposition of seismic separation conflicts (PRM Change Request 266, dated August 3, 1987). o MD-T-25 was revised (Revision 1 dated October 7, 1987) by Construction to clarify (to agree with Appendix SC) separation requirements for Class lE equipment, piping, g valves, etc. Item 3. The investigation to determine extent is based on the rationale provided in the above reviews and changes since the adoption of MD-T-25 and revision of Appendix SC in May 1987. Significance Items 1 and 2. Engineering reviews of separation notices to date have not indicated any impact on hardware. Open evaluation notices submitted as of May 6, 1987, with potential seismic impact will be evaluated by Engineering in accordance with the revised Appendix 2, section 21, procedures. All evaluation notices generated will be also included in the FP-14 finalization program review. Item 3. There is no significant impact on the installation or documentation due to the conservatism in the original design phase to
- O 0155d/005-8 6-36
allow for component displacements and construction tolerances. O Remedial Actions See Extent above. Actions to Prevent Recurrence Items 1 and 2 Supervisors interfacing with construction were made aware of this condition when the investigation to determine the extent was initiated. In addition, a memorandum will be issued to the EGSs requiring that they provide their respective discipline personnel training: i.e., Engineering will not provide design information to construction on documents that are not addressed by the PRM. Completion date for the training is September 30, 1987. Item 3. Actions to preclude recurrence are not required. Readiness Review
Conclusion:
The Project response and the corrective actions (completed) satisfy'the finding. O O 0155d/005-8 6-37
~
l Finding 2RRF-004-012 (Level III) Requirements: Part C, section 8.4.lb of the PRM states that "For items defined in the ASME B&PV Code, Section III, as components, the specification shall contain a preface page, certification of design specification page, and an attachment as the ASME B&PV Code, Section III, Code criteria locator page." Findinc: Contrary to this requirement, the following specifications for ASME B&PV Code, Section III, Code components do not contain a preface page: X4AD02, Nuclear Service Cooling Water (NSCW) Cooling Tower Components X4AE01, Component Cooling Water (CCW) and Auxiliary Component Cooling Water (ACCW) Heat Exchangers X4AF01, CCW and ACCW Pumps X4AF02, NSCW Pumps X4AF03, AFW Pumps X4AF04, Diesel FO Pumps X4AH04, Shop Fabricated ASME III Tanks X4AR17, Main Steam Isolation Valves X4AR19, Main Feedwater Isolation Valves This finding uncovers no defect in hardware but shows where a specification was not prepared in accordance with documentary requirements. Project Response: Engineering personnel failed to follow the PRM when preparing a specification. In addition to the requirements for a design specification, design specifications for ASME Class 1, 2 and 3 components require a preface page, certification page, and the ASME criteria locator. A random review of five additional specifications was performed. As a result of this review, Engineering concluded that the failure to use the preface page : l was generic to component design specifications. The review also verified that the certification page and the criteria locator page were included in the specifications, as required. The preface page contains the same information as the ASME criteria locator page; therefore, there is no impact on hardware. However, to resolve the potential impact on I documentation, the PRM will be revised to delete the reference to the preface page, since the information required by the 0155d/005-8 6-38
s preface page is duplicated by the information required by the ASME criteria locator page. O PRM sections C-8 and C-29, will be revised by October 30, 1987, to delete the preface page. A memo requiring Engineering personnel to follow the requirements of the PRM will be issued to appropriate personnel by September 15, 1987. Readiness Review
Conclusion:
The Project response and corrective actions (completed) satisfy the Readiness Review concerns. A Readiness Review assessment of vendor documents verified that the AFW pumps were furnished with ASME B&PV Code, Section III, Class 3, certification. O 0155d/005-8 6-39
I Finding 2RRF-004-013 (Level II) Requirements: h Piping Material Classification AX4DR001, revision 19, General Notes, sheet GN-4, paragraph 8.d. states " Seal welding shall be performed when threaded connections are provided on radioactive systems . . . Finding: Contrary to the above requirements, PPP Site Instruction SI-53 Temporary Vents or Drains for Hydro Testing, fails to require seal welding of threaded caps or plugs in drain or vent lines which are installed on the basis of a Field Change Request if required to perform hydrostatic tests. Proiect Response: The root cause of this finding is the failure by PPP to add AX4DR001, General Note, paragraph 8.d, seal welding requirements, to their Site Instruction SI-53. Site Instruction SI-53 was written to reflect the requirements of AX4DR001, General Note, paragraph 13, Vents, Drains, and Test Connections. The requirement to seal weld threaded connections provided on radioactive systems was not included in SI-53 due to the absence of this requirement from paragraph 13, which was specific to vents and drains. However, it should be noted that no actual impact on hardware has occurred because there have ll been no drains or vents added to Unit 2 radioactive lines for hydrotesting purposes. Site Instruction SI-53 has been revised adding paragraph 4.1.3 stating "On Radioactive systems, the threaded caps or plugs shall be seal welded after the hydro test is performed." Readiness Review
Conclusion:
The Project response satisfactorily addresses the deficiency in PPP Site Instruction SI-53, revision O. It should also be noted that additional investigations by the Project indicated similar concerns on Unit 1 piping and the potential lack of seal welding of threaded joints on radioactive lines by PPP. To assure consideration of these potential problems, the Project informed Unit 1 of the concern anr directed PPP to seal weld the appropriate threaded connections on Unit 2 radioactive drains and vent li,nes prior to turnover and to revise their procedures IX-3 and IX-15 to address the seal welding. PPP Site Instruction SI-53 has been revised to require the seal welding. 0155d/005-8 6-40 l
TABLE 6-1 () READINESS REVIEW TEAM - MODULE 4 NAME ORGANIZATION R. D. Andrews Readiness Review Task Force G. L. Crowe Pullman Power Products Quality Control S. R. Esperanza Readiness Review Task Force R. M. Grimm Project Quality Assurance N. C. Isbell Project Quality Assurance C. K. McGee Georgia Power Company Quality Control R. C. Sommerfeld Readiness Review Task Force J. L. Taylor Project Quality Assurance O O 0175d/356-7/1
TABLE 6-2 (SHEET 1 OF 2) UNIT 1 FINDING FOLLOWUP Unit 1 Checklist Checklist Finding Issue Number Item No. NRC VIOLATIONS: 86-11-01 Inadequato measures taken to assure correction of 101 2b. design criteria. (commitment 5107) 86-11-02 Inadequate and delayed response to identify and correct 308 2(b) undersize welds. 86-11-03 Failure to document removal of shipping dunnage. 309 2b. 85-37-01 Safety injection pump disassembled without adequate 208 4. procedure to control area cleanliness. 85-37-02 Safety injection pump disassembled without acceptance 307 6. criteria to verify that pump internals met cleanliness 309 2. requirements. 85-40-03 Failure to follow procedures for control of welding 209 3(b)- involving improper technique sheets and oven temperatures.
- 85-40-04 Nuclear service cooling water pump motor heaters not 307 2.
energized. 309 4b. 85-43-01 Valves and electrical panel not properly stored and/or 307 4(a) protected in unit. 85-52-01 Failure to provide adequate maintenance procedures for work 208 7. on safety-related equipment appropriate to the circumstances 309 2. (CVCS centrifugal charging pumps). 86-09-01 Failure to perform an adequate system walkdown during the 307 2. turnover of safety-related systems. 86-39-O
. Failure to provide accurate information for elimination of 101 3a.
intermediate pipe breaks and associated pipe whip (commitment 5107) restraints. 86-39-03 Failure to properly requisition weld filler material - 209 2(a) information missing from requisition. 86-72-01' Failure to protect installed'HVAC duct, duct supports, 208 4. pipe, and pipe supports from construction loads. 308 2(b) 0157d/356-7/1
r TABLE 6-2 (SHEET 2 OF 2) O Unit 1 Checklist Checklist Finding Issue Number Item No. READINESS REVIEW FINDINGS - LEVEL I: 4-78 PRM procedures do not address interface, communications, 101 2e. and documentation requiremen?s to assure adequate (commitment 4230) interdiscipline interface for flooding analysis. . i 4-86 PRM procedures do not adequately address HELBA controls 101 2a. i information and interfaces. (commitments 1543 ; and 4230) t 4-96 project procedures inadequate for hazards program including 101 2a. hazards analysis, HELBA, flooding analysis, and inter- (commitments 1543 discipline interface of LDL data with Hazards Group. and 4230) INDEPENDENT DESIGN REVIEW FINDINGS - LEVEL I: . 4-19 Auxiliary feedwater pump suction piping overpressure 204 1. protection not determined. 4-30 Flooding analysis omitted consideration of effects of 101 3a. flooding to or from other areas and levels, and the time (commitment 4230) l O required to terminate a flood. 203 5. , l 4-92 Hazard analysis omitted axial vane fan units as a source 101 3a. of missiles. (commitment 4194) j l 22-B) Longitudinal pipe breaks were not evaluated at high stress 101 3a. l points. (commitment 956) l 209 9. 1 22-B3 Flooding effects analysis within Auxiliary Building did not 101- lb. completely address source of flood, flood flow paths, or (commitments 4197 consequences beyond flooded volume. and 4230) 22-B4 Inadequate documentation of design inputs / justification of 203 9. assumptions for "Q" class hazard calculations. 22-B5- Seismic adequacy of AFW area unit heater supports was not 203 3. documented. 319 3(a) ()*OventemperaturesalsoevaluatedbyGPCQAinauditnumberCPO4-87/15 I 0157d/356-7/2 j
TABLE 6-3 (SHEET 1 OF 6) ., ASSESSMENT SAMPLE
SUMMARY
Total Number l Checklist Documents or Components Reviewed of Documents or Components i RR-004-101 Design Commitments: 2 QA commitments 47 in "21A" overall QA program 27 design commitments (see Note 1) 244 design commitments including 5 that also involve construction t RR-004-102 Construction Commitments: l entry from construction commitment 16 entries comprising 7 con-880.00 struction commitments including 5 that also involve design RR-004-201 Field Change Requests (FCRs): . Y-FCRB-5435 : M-FCRB-16,549 Approximately 16,000 mechanical . M-PCRB-0845F FCRs have been approved M-FCRB-12,833 O M-FCRB-4456F ~ Drawing Change Notices (DCNs): ; Dwg. 2X4DB134 DCN No. 42 49 DCNs have been issued against this drawing DWg. 2X4DB161 DCN No. 48 53 DCNs have been issued against this drawing ; RR-004-202 Field Equipment Change Orders (FECOs): i J-002-0-S 14 issued by SCS P-20-B 20 issued by BWPC HOE N-318-BF 367 issued tQr BWPC PFE J-57-B 65 issued by BWPC HOE ; i RR-004-203 Design Calculations: (see Note 4) X4Cl203V07 Rev. 2 12 mechanical cales. on system ) 1203 , X4Cl205V01 Rev.'3 1 raechanical calc. on system ) 1205 l X4C1302S10 Rev. 1 (see Note 2) 19 mechanical Q class cales. on l system 1302 X4Cl302S12 Rev. 1 . O. X4Cl302V05 Rev. 3 (see Note 3) 0154d/356-7/1
= - , - , . . - . . . ,
TABLE 6-3 (SHEET 2 OF 6)
Checklist Documents or Components Reviewed of Documents or Components RR-004-209A Nondestructive Examination - ,
Piping Installation (supplemental assessment):
- 7 surface examinations were observed:
Iso. 2X5DY09020B - liquid penetrant examination of weld number W-14. Iso. 2K5-1301-007 magnetic > particle inspections of 6 welds on restraint 2T-M5-6-3 ; RR-004-210 In-Process Piping Installat!.on: No. of ! Field Isometric Drawings Welds 2K5-1302-057-01 3 System 1302 - estimated number of 4 2K5-1302-058-01 - field welds = 525 Q + 130 non-Q ; 2K5-1302-069-01 2 = 655 2K5-1305-038-02 _9 O< 14 System 1305 - estimated number of ; field welds = 80 0 + 1275 non-Q l RR-004-301 Change Control Package: = 1355 No. B10310P Modification of clamp's 1 CCP has been issued set screw locking device of Anchor Darling manual globe valve. RR-004-307 Walkdown of lastalled Mechanical Equipment: 2-1203-E4-001 CCW Heat Exchanger 2 units in system 1203 2-1203-P4-001 CCW Pump 6 units in system 1203 i 2-1203-T4-001 CCW Surge Tank '2 units in system 1203 I 2-1205-E6-001 RHR Heat Exchanger 2 units in system 1205 2-1205-P6-001 RHR Pump 2 units in system 1205 2-1205-V4-001 RHR Isolation valve 2 units in system 1205 Encapsulation Vessel O 0154d/356-7/3
{ TABLE 6-3 (SHEET 4 OF 6) O Checklist Documents or Components Reviewed 4 Total Number of Documents or Components i l RR-004-308 Walkdown of Installed Piping: No of No. of Field Isometric Drawings Spools Welds i 2K3-1203-010-01 1 1 System 1203 - estimated number of , 2K3-1203-021-02 2 1 field welds = 290 Q + 65 non-Q ) 2K3-1203-021-03 2 3 = 355 2K3-1203-026-01 1 2 2K3-1203-034-01 3 3 2K3-1203-034-02 2 2 2K5-1203-063-01 3 4 2K5-1203-086-01 N/A 7 2K5-1203-088-01 N/A 6 2K5-1203-088-02 1 2 ! 2K4-1205-001-03 1 2 System 1205 - estimated number of 2K3-1205-003-01 3 3 field welds = 400 Q + 40 non-Q 2K3-1205-003-02 4 9 = 440 2K3-1205-005-01 2 2 2K3-1205-005-02 2 5 l 27 52 RR-004-309 Acceptability of Quality Documentation
- Mechanical Equipment: l 2-1205-P6-001 RHR Pump 16 units of major safety-related DR PP 17297 (2-1205-V4-001) equipment in systems 1203 and DR PP 14672 (2-1203-E4-001) 1205 DR PP 10391 (2-1205-T4-001)
DR MD 2896 (2-1205-E6-001)- RR-004-310 Acceptability of Quality Documentation
- Materials:
No. of Isometric Drawings Spools 2K3-1203-021-02 5 2K3-1203-021-03 1 2K3-1203-026-01 2 2K3-1203-034-01 1 2K3-1203-034-02 5 2K3-1203-063-01 1 2K3-1203-086-01 1 (small bore) 2K5-1203-088-02 1 , 2K3-1205-005-01 1 2K5-1205-003-02 3 O 0154d/356-7/4
+- - ,~ ~
TABLE 6-3 .(SHEET 5 OF 6) Total Number checklist Documents or Components Reviewed of Documents or Components , RR-004-311 Acceptability of Quality Documentation
- Field Weld Process Sheets:
(see Note 5) 53 field welds in this documentation Systems 1203, 1205 and 1302 - 14 QA engineer's certification total estimated number of field 17 QC visual welding inspector's welds = 1215 Q + 235 non-Q certification = 1450 16 welder's qualifi:ation , 8 NDE people's certification l 8 welding procedure revisions RR-004-312 Acceptability of Quality Documentation
- Leak Test Records:
Test package No. 2-1205-1 RR-004-314 Walkdown of Installed Piping - AFW Pumphouse: No of No. of Field Isometric Drawings Spools Welds O 2K5-1301-012-02 2K5-1302-017-01 2 2 4 System 1302 - estimated number of field welds = 525 0 4 130 non-Q. 1 2K5-1302-024-01 3 5 = 655 I 2K5-1302-038-02 1 .8 2K5-1302-048-01 1 - 7 19 RR-004-315 Acceptability of Quality Documentation
- Mechanical Equipment - AFW Pumphouse: .
2-1302-P4-001 AFW Pump Turbine Driven 1 turbine driven and 2 motor (no DRs) driven pumps comprise the major safety-related equipment in system 1302 - Module 4 RR-004-316 Acceptability of Quality Documentation )
- Materials - GPC - NA-Stamp Program.
'l No. Test I No. _Fld. Rpt. ]
Isometric Dwas. Spls. Wids. Rvw'd. l 2K5-1302-024-01 3 5 7 2K5-1302-017-01 2 4 6 i 2K5-1302-048-01 1 2 1 O 2K5-1305-038-02 2K5-1301-012-02 1 3 2 2 1 4 10 15 19 I 0154d/356-7/5
t TABLE 6-3 (SHEET 6 OF 6) + Total Number l Checklist Dracuments or Components Reviewed of Documents or Components RR-004-317 Acceptability of Quality Documentation
. Welding Records Sheets
- AFW (GPC Scope): .
9 field welds in this documentation ! 4 Welders qualification records 4 QCI Certificaticn and Eye examination records y 3 NDE Certification and Eye ! examination records ~ 2 Weld procedures l Weld procedure revision 5 Isometric drawings used i RR-004-319 Walkdown of Installed Mechanical Equipment - AFW Pumphouse: 2-1302-P4-001 AFW Pump Turbine Driven 1 turbine driven and 2 motor driven pumps comprise the major safety-related equipment in the . AFW Pumphouse O RR-004-325 RT Film Assessment: ? No. of Field + Isometric Drawings Welds : 2K3-1205-003-01 5 System 1205 - estimated number of 2K3-1205-007-02 _7 field welds = 400 Q + 40 non-Q 12 = 440 l l i
- 1. Finding number 2RRF-004-012 resulted from the review of commitment ref. no. 457. ,
- 2. Finding number 2RRF-004-007 resulted from the review of calculation X4Cl302S10. .!
- 3. -Finding number 2RRF-004-002 resulted from the review of calculation X4Cl302v05. i
- 4. Finding number 2RRF-004-004 resulted from the review of all design calculations in sample. ;
5.- Finding number 2RRF-004-008 resulted from the review of checklists regarding the O quality documentation of welding activities. .)
.0154d/356-7/6 i I
O O O TABLE 6-4 (SilEET l OF 7) C0ffitTENT VERIFICATION MATRIX Refor- Source & Basis for Irnplementation Document ence No. .Section Subject Document / Feature Selection Type Number and Section Comments 146.00 FSAR QA requiremer.ts for ANSI N45.2.2- 1 of 2 generic Spec. X4AF03-6.2 & 6.3 - 1.9.38.2 packaging, shipping, 1972 ccmni tments GPC GD-A-30 receiving, storage and from FSAR FP's GD-T-ll handling of items for Chapter 17 MD-T-12 water cooled nuclear PPP X-5 power plants 333.00 FSAR ESF construction limited to no Questioned by DC DC-1204-4.0L Yield strength limited 6.l.1.1.2 material - cold worked greater than NRC on in- Specs. X4AQ01-6 lA & E to 90,000 psi by con-austenitic stainless 90,000 psi spection B5-35, X4AQ01-9.1.7 trolling heat steel yield strength Ta' ole I X4AQ34-7.lB treatment and cold X4AQ W 7.lB bending. X4AZ01 --P3.4.0A X4AZ01-P3.4.0B X4AZOI-P3.5.3 PPP IX-16 390.00 FSAR CCW system cold shut- BTP RSB 5-1 typical CCW DC DC-1205-l.0 During 1-train cool-9.2.2.3.A down requirements system comitment DC-1203-3.lK down, cold shutdown Calc. X4Cl2O3V08, sheet achieved in 34 hours numbers 10 and 14 after reactor trip. 418.00 FSAR Ultimate heat sink - R3 1.27 related to RR DC DC-1202-A-1.0A FSAR CN 559 shows 9.2.5.1.1 safety design bases finding 4-073 Calc. X4Cl202W23 conbined inventory
.B reduced to 25.B days.
451.00 FSAR Auxiliary Foodwater BTP ASB 10-1 related to IDR DC DC-1302-l.O 10.4.9.3 system observation DC-1302-3.1.lA, 4-017 B, E and G DC-1302-3.l.2.IA DC-1302-3.1.3.2A Calc. X4Cl302S00FI P&lD 2X4 dbl 6l-2 0150d/3 W J/1 . . . _ _ _ _ . _ .m__________.__m.__._ - - _ _ _ _ _ _ _ _ - - - - , - - _ - - - _ _ + . m -. -- - - --e, - - - - - +- - - i>--*-"m+ _ - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -
O O O 1ABLE 6-4 (SHEET 2 0F 7) Refer- Source & Basis for Inplementation Document-ence No. Section Sub.iec t- Document / Feature Selection Type Number and Section Corments 457.00 FSAR Auxiliary Feedwater ASME lil, Class related to IDR DC DC-1302-3.1.lW finding 2RRF-004-012 10.4.9-1 system 2 and 3 observation PalD 2X4 dbl 61-2 issued 4-017 Specs. X4AF03-4.2.1 X4AC01 - data sheets , 880.04 FSAR Principal codes and ASME Section ill Typical con- PPP IX-19-l.I, 3.1.1 Includes requirement 3.2.2-1 standards for Table (1977 through struction cormit- and 3.4.1 to grind exposed 3.2.2-1 Winter 1977) ment IX-43.1.1, 5.1.2, threads prior to seal NB/NC/ND-4400, 5.1.7 and 5.1.11 welding and not allow-l Making, ex- IX-44-2.2A and ing peening at VEGP. amining, and 5.1.2, repairing welds X-18-l . l . & 5.1 Xlli-4-1.1 and 13.2.3 951.00 FSAR High energy pipe BTP MEB 3-l, Questioned by NRC DC DC-1018-2.3.B.2 Break locations 3.6.2.1 breaks (excluding Sections B.I.a, on Inspection and 3.3.B.3 assumed per FSAR reactor coolant loop) B.I.b, & B.I.c 85-35, Table I Calc. X4CP-7110 3.6.2.1.1.A.2 sheet 6 , 954.00 FSAR High energy pipe BTP MEB 3-1, Questioned by NRC DC DC-1018-2.3.B.2 Break locations now 3.6.2.1.1. break intermediate Sections B.3.a on inspection Calc. by Westinghouse affected by Unit 2 A locations (ASME lit and B.3.b 85-35, Table I snubber reduction Class 1) program per GPC letter GN-1364 dated 4-29-87 956.00 FSAR High energy break BTP MEB 3-I, Questioned by NRC DC DC-10lB-3.3.B.3 3.6.2.1.1. locations (ASME 111 Sections B.I.b on Inspection and 3.3.B.4 B Class 2 and 3) and B.I.c 85-35, Table I Calc. X4CP-7110 shoet 6 Ol50d/356-7/2
v v G TABLE 6-4 (SilEET 3 0F 7) Refer- Source & Basis for Irnplementation Document ence No. Section Subject Document /Feafure Soiection Type Number and Section Carments 1543.00 FSAR Protection against BTP MEB 3-1 and Questioned by NRC DC DC-1018-l.0 Ref. to FSAR 3.6 and 1.9.46.2 pipe break inside ASB 3-1 on inspection llELBA IX6llEL-Ol Table 3.6.l-2, WCAP-containment 85-35, Table I (Unit I ilELBA 8172A, ANSI 20.2 draft Book #1) in lieu of RG l.46 1841.00 FSAR Restraint of large Propagation of Questioned by NRC DC DC-1018-App. D Affected by Unit 2 3.6.2.3.2. RCL branch lines break to un- on Inspection Calc. by Westinghouse snubber reduction 2.A affected loops 85-35, Table i program per GPC letter prevented GN-I564 dated 4-29-87 2174.00 FSAR CCW system safety 10 CFR 50, Related to IDR DC DC-1203-1.0 Ref. to FSAR 3.1.4 9.2.2.1. design bases Appendix A, observation Dwgs. 2X4DE315 1.E GDC 45 4-026 2X4DE321 2175.00 FSAR CCW system safety 10 CFR 50, Related to IDR DC DC-1203-l.0 Ref. to FSAR 3.l.4 9.2.2.1. design bases Appendix A, observation and 3.lG l.E GDC 46 4-026 P&lD 2X400136 2311.00 FSAR Auxillary Feedwater AFW minimum flow Typical AFW DC DC-1302-3.1.lB Must be verified by 10.4.9.2.1 system general to at least 2 system Calc. 4XCl302S08 Preop. test pro-description S/G's is conmi tmen t Spec. 4XAF03-3.2.2.7 cedures, see FSAR delivered with- and App. BB-5.5A 14.2.8.1.5 and in ? minute of 14.2.8.1.6 receipt of signal 2314.00 FSAR Auxiliary Feedwater NUREG-0737, Typical AFW DC DC-1302-2.2 Reliability analysis 10.4.9.3 system safety action items system Calc. X4Cl302S00FI evaluation ll.E.1.1 and ccanitment II.E.I.2 0150d/356-7/3
O O O TABLE 6-4 (SiiEET 4 0F 7) Refer- Source & Basis for implenuntation Document ence No. Section Subject Document / Feature Selection Type Number and Section Conments 1 2321.00 FSAR AFW system method- NUREG-0611, Typical AFW DC DC-1302-2.2 Data from 10A.3.1 ology - reliability Appendix Ill system Calc. X4Cl302500FI calculation evaluation & Annex 1 of commitment used in evaluation Appendix X 2346.00 FSAR Applicable codes and The entire R!lRS Typical RilR DC DC-1205-2.08.1 5.4.7.2.5 classification is designed as system DC-1010, Table I nuclear safety comi tment page ll class 2 with the PalD 2X4DB121 exception of the 2X4 dbl 22 suction isolation LDL 2X4DR004 valves, which are safety class 1 3363.00 FSAR GPC QA Program - ANSI N45.2.ll I of 2 generic PRM Part A, Sect. 8 17.1.2 design of a nuclear draf t 2, rev. 2, comi tments Part C, Sect. 2 power plant May 1973 from FSAR Part C, Sect. 3 Chapter 17 Part C, Sect. 4 Part C, Sect. 8 i Part C, Sect. 9 Part C, Sect. 20 Part E, Sect. I Part E, Sect. 6 Part E, Sect. 7 3752.00 fSAR Corrpunent Cooling Designed to Typical CCW DC DC-1203-3.lF Also covered by piping 9.2.2.1.1. Water System - remain function- system DC-1010, Table I stress calculations in D design bases al during and containment page 20 Module 11 after a SSE Spec. X4AE01-3.3.5.1 X4AF01-4.lA & Appendix QG Ol50d/356-7/4 i _m____m___ ___ ___m_ . _ __e__ __m_.___ .._m __o_
- _ _ . _ _ _ _ _ _ _ _ _ _ - . _ _ _ _
m - ---->m _+, i _- +. .c -- .- .ri_a i--- - , -=.- -
O O O TABLE 6-4 (SifLET 5 OF 7)
' Refer- Source & Basis for implementation Document ence No. Seetten Sub.iect Document / Feature Seiection Type Number and Section Comments '
i 4194.00 NRC Internally generated 10 CFR 50, Related to RR DC DC-IDO6-1.0 Question missile source by non Appendix A, finding 4-067 Calc. X6CXD-25 Q410.05 safety-related system GDC 4 or emponent 4197.0J NRC Flooding analysis BTP MEB 3-1, Related to IDR DC DC-1003-l.0, 3.2C Question Paragraph observation and 3.2G Q410.17 B.2.c(2) 4-030 Calc. X6CXC-26 4230.00 NRC Crlieria for flood Single active Related to RR DC DC-1003-3.2D Flood level for Aux. Question analysis failure co- finding 4-078 DC-1009-3.3.D bldg. room R-BIS cal-Q410.13 incident with Calc. X6CXC-30 culated on sheet 52 of postuIaied X6CXC-30 piping failure except for dual purpose moderate energy system 4516.00 FSAR Auxiliary Feodwater No single Typical AFW DC DC-1302-3.1.2.lA, 7.3.7.1.2 system - design bases failure shall system 3.1.2.2A, prevent this comi tment 3.1.3.lA, system from 3.1.3.2A, and operating 3.l.4.lA Calc. X4Cl302S00FI 4523.00 FSAR Auxiliary Feedwater The system Typical AFW DC DC-1302-3.1.lB Must be verified by 7.3.7.l.2 system - design bases must provide system Spec. X4AF05-3.2.2.7 & Preop. test pro-full auxiliary comitment Appendix BB-5.5A cedures, see FSAR feedwater flow 14.2.8.l.5 and within i minute 14.2.8.1.6 4 Ol50d/356-7/5
O O O TABLE 6-4 (SilEET 6 0F 7) Refer- Source & Basis for inplementation Document ence No. Section Subject Documen t/Fea t ure Selection Type Number and Section ___ Connan ts 4892.00 NRC IE SA-312 or A-312 type Design stresses inappre >ria tely Ltrs. BWPC ltr.- IEB 79-03 super-Bulletin 300 series fusion in safety- referred to IEB BG-9960 seded by lEB 79-03A welded pipe related comp- 79-03 in Unit I West. ltr.- 79-03A C-81/04/02 onents limited Readiness Review GP-4731 to 85% maximum allowable stress at design temperature 4918.00 FSAR Ccr9onent Coo!Ing Designed to Related to IDR DC DC-1203-1.0 9.2.2.l.1. Water System - transfer heat observation and 3.1.J.I A safety design bases from RitR system 4-015 Calc. X4Cl2O3V08 to NSCW system at a suf-ficient rate to avoid fuel or core damage following a LOCA in accordance with 10 CFR 50, Appendix A, 1 GOC 44 4919.00 FSAR Component Cooling Designed to Related to IDR DC DC-1203-3.3B 9.2.2. l.1. Water System - safety remove reector observation and 3.3K F design bases decay heat 4-015 Calc. X4Cl203V08 sufficient to bring reactor to cold shutdown condition in 36 hours with loss Ol50d/356-7/6 .m__ _._.mm.__i________m__.__.._________________________...______--______m-, - -
.- -. - - - - -.v. .,w
O O O TABLE 6-4 (SHEET 7 0F 7) Refer- Source & Basis for inplementation Document once No. Section Subject Document / Feature Selection Type Number and Section Convnt=nts 4919.00 of offsite power (cont'd) and assuming most limiting single failure in accordance with RG l.139 5107.00 FSAR 'High energy main No welded at- Related to NRC DC DC-10lB-3.3.B.3. Alternate to BTP 3.6.2.1.1. steam and feedwater tachments within violation d.l.a MEB 3-1, Para. B.4 systems pipe breaks 5 nominal pipe 86-11-01 Memo instruction memo B.I.c(2) per NRC postulated at inter- diameters of Nunber 34-a.2 letter dated 6-2844 mediate locations highest stress (NG-84-SI) loca tions 5108.00 FSAR Pipe breaks postu- No welded at- Related to NRC DC DC-1010-3.3. Alternate to BTP 3.6.2.l.1. lated at intermediate tachments within violation B.3.d.l.b KB 3-1, Para. B.4 locations in high 3 times square 86-11-01 Memo instruction memo B.I.c(2) per NRC energy systems other root of (Rt) number 34-a.1 letter dated 6-28-84 than main steam and (NG-84-51) feedwater 0150d/356-7/7
TABLE 6-5 (SHEET 1 OF 2) () UNIT 2 FINDINGS Findino Number Description Level 2RRF-004-001 Contractor's procedure does not clearly III differentiate between Quality Control inspections and in-process verifications by field engineers. 2RRF-004-002 Calculation X4Cl302 VOS, revision 3, is III identified in the control log as status A (valid) even though Westinghouse rejected the calculation and marked it "No Longer Required". 2RRF-004-003 DC-1000M refers to system design criteria II for Regulatory Guide. All but Regulatory Guide 1.7 has been removed from DC-1501. 2RRF-004-004 Calculations do not indicate whether they III are applicable to Unit 1 Unit 2, or both. 2RRF-004-005 A P&ID was revised without issuing II the required advance or simultaneous f") v issue of a DMCN. 2RRF-004-006 Design requirements for system 1210 is III included in DC-1208 but no reference is made to DC-1208, 2RRF-004-007 Specific mathematical entries in one III calculation were erroneous due to transposition of digits, and similar transposition errors were found on calculation X4Cl206V01 (same checker). 2RRF-004-OO8 GPC document intended to include III welding procedure and nondestructive examination procedure selection for piping systems. 2RRF-004-009 GPC Construction Procedure MD-T-25 is III being used as a vehicle to report, evaluate, and accept deviations in the seismic separation requirements without being addressed in the PRM. 2RRF-004-012 The preface page for procurement III specifications is missing on 9 specifications. Ol76d/012-8/l
l TABLE 6-5 (SHEET 2 OF 2) Findinc Number Description Level l 2RRF-004-013 PPP site instruction allows use of III threaded plugs in radioactive systems without requiring seal welding as specified in AX4DR001. O.- 0 0 Ol76d/356-7/2 l l
Georgia Power Company Project MInagemInt - Fost offica Box 282 Waynesboro. Georgia 30830 Telephone 404 724 8114 404 554-9961 Vogtle Project DATE: November 16, 1987 4 RE: Pla nt Vog tle Unit 2 ; Readiness Review Module 4 FROM: W. C. Ramsey TO: R.W. McManus Engineering has reviewed Module 4, Mechanical Equipment and ; Piping, for general accuracy and completeness. To the best of our knowledge and belief, the module is a complete and accurate representation of the engineering process and conmi tme nt s related thereto. , J
- d. +
a C.hRamsey,\Jr. W.
/m /
Project Engineering anbger RWM /WCR/bj d i t t O
, . - .,.y. m - - - - . - ..c_..y- ,,,, , _ . . _ . , - ~ . - . .,-,w-> -
,,-r--
ty-, ,,v-v
Georgia Power Company Project Man:gemInt Post Offica Box 282 Wayn;sboro, Georgia 30830 TeIIphona 404 724-8114 404 554-9961 o h
'" Vogtle Project November 16, 1987 MEMO TO: R.W. McManus
SUBJECT:
Plant Vog t_l e U n_i_t 2 Readiness Review, Module 4 Nuclear construction has reviewed Module 4. To the best of our knowledge and belief, the module is a complete and accurate representation of the site Mechanical Equipment and Piping installati 'n prog ram and commitments related thereto. l 7
/ * ' . jpegn l R. H. Pinson i Vice President Vogtle Construction es J RWM/RH P/bj d .
I i 1 sm '(_/l
Georgia Power Comp;ny Project Mrn gement Pc:t offica Box 282 W1yrcstoro Georgia 30830 Telephone 404 724-8114 404 554-9961 o n Vogtle Project DATE: November 16, 1987 RE: Pla nt Vogtle Unit 2 Readiness Review Module 4 Pii C M : C. W. Hayes TO: R.W. McManus Project Quality Assurance has reviewed Module 4, Mechanical Equipment and Pi pi ng . To the best of our knowledge and belief , the module is a complete and accurate representation of the site programs and commitments related thereto. 7 s., V Y M~ C. W. Hafes Project Quality Assurance Manager RWM/CWH/bjd n] _
1 l 1 PLANT V0GTLE UNIT 2 ' READINESS REVIEW PROGRAM Mechanical Equipment and Piping - Module 4 , Readiness Review Board Acceptance Letter l t s The Readiness Review Board has been apprised of the scope and content _ of Module 4. Mechanical Equipment and Piping. l 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, upon their ; implementation, the mechanical equipment and piping at Plant Vogtle will be sound and comply with commitments set forth in the FSAR. ! O l t bs _ APPROVED: %* [' Doug Dutton' Chairman, Readiness Review Board , Vogtle Electric Generating Plant i [ .O m -._-.. ., _.m..m -- -,.
,A Qs ASSESSMENT PLAN FOR UNIT 2 MECHANICAL EQUIPMENT AND PIPING MODULE 04 O Su bmitted by: - . dO ONb /7(( R. C. Sonmerfeld ' Mechanical Team Leader Approved by: _] ' e b y/ y'j M g/E/4 87 R. W. F.cManus Readiness Review Program Manager I i (D LJ 0123d/119-7 l l
ASSESSMENT PLAN FOR
'O UNIT 2 MECHANICAL EQUIPMENT AND PIPING 1.0 OBJECTIVE This plan provides directions for assessing selected pro ject !
design and construction activities to evaluate continuing compliance to licensing commitments during Unit 2 completion, ! continuing implementation of corrective actions resulting from i deficiencies identified during the Unit 1 Readiness Review l 1 Program, and a review of selected Construction Acceptance I Te st ing ( CAT) activities for mechanical equipment and piping. I
)
1 2.0 SCOPE 2.1 MODULE 4 SCOPE I The scope of Module 4 - Mechanical Equipment and Piping , I includes those design, procurement, construction, and inspection activities associated with saf ety-related mechanical equipment and piping system components classified as ASME Boiler and Pre ssure Vessel Code, Section III, Class 1, 2, or 3 in the balance of plant (not a part of the Nuclear Steam Supply System) . I l () , l l J
2.2 ASSESSMENT SCOPE
) '
The assessment of Unit 2 mechanical equipment and piping will address the following items: o Additional or revised commitments; 9 1 o Revisions to design and construction progrars examined during the Unit 1 Readiness Review Program; o Cont inuing and acceptable implementation of cor rective actions taken as a result of the Unit 1 Readiness Review assessments including the Independent Design Review (IDR), Quality Assurance ( QA) audits, and Nuclear \ Regulatory Commission (NRC) in spe ctions ; , o Control of design changes for work performed before or af ter construction turnover; o Design finalization /as-built programs (scope, plans, re sults ) ; o Insta]1ation/ inspection activities with checks on l significant deficiencies identified during Unit 1 Readiness Review Program; o Documentation; , 2 i
I o Equ ipme nt /Compo nent removal program (cannibalization, i modification, or use of spare parts during Unit 1 construction); o Const ruc tion acceptance testing progra m. i Initial design, procurement, and receipt activities for Unit 2 were essentially complete at the tire of the Unit 1 assessment and were included with the programs assessed during the Unit 1 Readiness Revi ew. To ensure continued acceptability of these programs, on-site equipment modifications (including replacements for the equipment /corponent removal program) will be assessed if applicable to the sample selected. O
- 3. 0 ASSESSMENT ACTIVITY ASSIGNMENT The Unit 2 Readiness Review Program utilizes resources from the 1
entire project team as summarized below and described in ' Section 4.0 of_this plan. 3.1 READINESS REVIEW Readiness Review prepares and maintains the Commitrent and Implementation matrices, prepares the assessment plan, ; l participates in assessment ac tivi tie s, issues Readiness Review O j 3
1 I findings, and evaluates project responses to Readiness Review O. related QA Audit Finding Reports (AFRs), Corrective Action Requests (CARS), and Readiness Review findings. Finally, the , team prepares a supplemental report for each module which will i summarize and display the results of these activities. l l 1 3.2 PROJECT DESIGN AND CONSTRUCTION ORGANIZATIONS 1 Project design and construction are responsible for continuing impleme nt ation of commitments. They will review the Implementation matrix for accuracy and will advise Readiness Review of necessary re. visions to the matrix which reflect changes in (or additions to) commitments, programs, or pro ced ure s. l 3.3 QUALITY ASSURANCE Project QA will perform the assessments described in Section 4.0 of this plan. Readiness Review personnel will participate in the assessments and will support the QA audit tr ams as necesaary. Additional personnel f rom Southern Company Services, Project design, construction, contractors, or of f-project organizations may be utilized with the approval of the Readiness Review Manager. l 4
4.0 ASSESSMENT DETAILS AND GUIDELINES O This assessment plan involves a phased group of activities consisting of th ree parts as follows: o Part 1 addresses verification of implementation of l licensing commitments into design and construction , 1 d ocume nts . I I 1 l \ l o Part 2 addresses design and construction progrars and j activities with regard to compliance with applicable pro cedur e s. o Part 3 addresses conf ormance of as-installed hardware and documentation with commitments and procedural requ ir e ne nt s . It is not intended that the activities described in these parts necessarily be conducted sequentially but will occur within the tine constraints of the Readiness Review program for each module. The following sections describe each part of the plan and the checklists which have been developed to control the assessment. Use of the checklist is described in Section 5.0. O 5
4.1 PART 1 - VERIFICATION OF COMMITMENT IMPLEMENTATION The project has the responsibility for continued implementation of commitments and will review the matrices for accuracy. Implementation of a sample of commitments will be verified by QA to provide added assurance that all levels of design documents and construction procedures are in agreement and responsive to th e c ommi tme nt s . For verification of the implement ation of design commi tments, first-order documents [ e. g . , Desi gn Crit eri a, Process and Instrumentation Diagram (P& ids), or Pro ject Reference Manual (PRM) sections) and second-order documents (e.g., drawings, specifications, calculations, finalization /as-built program records, etc.) will be reviewed. For verification of construction commitments, the Field Construction Procedures and field procedures of responsible contractor organizations will be ! reviewed. i 4.1.1 SAMPLE SELECTION The Mechanical Implementation Matrix lists approximately 260 ent ries which identif y commitments in Module 4. Table 4.1-1 lists 30 entries, including two f rom the Module 21A QA program list (applicable to all modules), that Readiness Review has selected for verification of first and second-order commitment 6
implementation by QA during the assessment activities for the Unit 2, Module 4, Readiness Review Program. The sample selection is biased to place emphasis on those conni tments which have been changed or added to the module and those which involve corrective action as a result of the Unit 1 Readiness Review. 4.1.2 COMMITMENT IMPLEMENTATION CHECKLISTS The checklists identified below are to be used for assessment of commi tme nt s : ; t]% Checklist Nu mber Sample Ide nt ifi ca t ion
)
RR-004-101 Design Commitment Implementation RR-004-102 construction Commitment Impleme nt ati on l 4.1.3 COMMITMENT ASSESSMENT l Review each selected commitment by referring to the commitment source (usually the FSAR) and section to develop a clear understanding of the commitment and its scope (reference to the i subject, document / feature, and document section fields in the implementation matrix will provide further sources for O 7 i i
j definition). By comparing the listed implementing documents and commitment details, identif y any inconsistencies, conflicts, or omissions as "Re j ec t
- on the checklist and provide an appropriate description of the recommended cor rection.
4.1.4 FIRST-ORDER IMPLEMENTATION VERIFICATION 4.1.4.1 Design Impleme nt a tion First-or der inplementation of design connitments is normally found in Design Criteria. Some commitments, such as regulatory mandated details, may be implemented partially or entirely in the PRM, calculations, specifications or design drawings. First-or der implementation (or second-order, if first-order implementation could not be verified) is tabulated in the impleme nt ation matrices. 4.1.4.2 Const ruction Implementation First-order implementation of construction commitments is found in the Field Procedure Manual or, for contractors working to their own QA program, in their own field procedures. Only a few licensing commitments require first-order implementation by gg const ru c tion , ( mo st commitments which require implementation by 0 8
e i construction are reflected in documents developed by design or ga nizatio ns ) , so the najority of construction assessment activities are addressed in parts 2 and 3 of this plan. 4.1.4.3 Completion of Checklist ; i Verif y that the implementation documents cited on the matrix ; satisfies the commi tme nt . i t o If the cited document (s) has been revised and the current revision implements the commitment as presently i shown in the Implementation Matrix , the implementation ! is acceptable. Record the current revision as a :
"C o mme nt " for updating of the matrix by Readiness Review, o If the cited document (s) has been revised and the cur rent d ocu me nt issue does not adequately implement the
- commitment, attempt to identify other applicable Design Criteria and documents which verif y implementation. If the connitment is acceptably implemented elsewhere, record the changed implementation as a " Comment" for revision of the matrix by Readiness Review.
o If additional implementation documents should be cited, or if there are er roneous entries (e.g. , paragraph, table titles, or page nurbers) record the changes to be made as a " Comment". 9
4.1.5 SECOND-ORDER IMPLEMENTATION VERIFICATION [ k/ Second-order implementation of design commitments is the acceptable incorporation of connitments f rom first-order design documents (Design Criteria, etc. ) into calculations, drawings, specifications, etc. Se c ond-or de r implementation is presently tabulated on the implementation matrices only for those circunstances where first-order implementation could not be verified. Verif y second-or der implementation f or each cornitment listed on Ta ble 4.1-1. o If implementation of a connitment is found only in second-order documents (i.e., no first-order
'mplementing documents could be identified) such as t
ca'culations, drawings, or specifications (see 4.1.4.1, above), mark this section NA and explain in the
" Comme nt " section.
o If the commitment applies to a nurber of calculations, drawings or specifications, review a sample of at least two to verif y implementation, o If the commitment implementation requires a number of attributes to be applied to each calculation, drawing or specification, review a sample of six attributes (or all 10
if less than six) in each document to verify implementation. o Recor d the documents reviewed in the " Comme nt s" section and the attributes reviewed in the "R equ i r eme n ts " section. 4.2 PART 2 - PROGRAMS AND ACTIVITIES Part 2 of the assessment plan provides for evaluation of responses to design control prograns, adequacy of technical i design details, adequacy of construction procedures, and i responses to those procedures during installation of equipment and piping. It also includes review of selected design documents , proc edur e s, and qu ality recor ds to ensure maint enance of procedural changes made as a result of the Unit 1 Readiness Review Program. Part 2 (and Part 3) of the assessment plan will address the Component Cooling Water system to the maximum extent possible. In addition, certain portions of the Residual Heat Removal system are included to permit assessment of project classes 111 and 212. Selected portions of the Auxiliary Feedwater (AFW) system in the AFU pumphouse will also be assessed to address installation activities performed under the GPC ASME N-Stamp program. 11
4.2.1 DESIGN ACTIVITY ASSESSMENTS ; rm U The following checklists are to be used as guidelines for the assessment of design activities: Checklist Number Sample Identification RR-004-201 DCNs, FCRs, and CSCNs RR-0 0 4 -2 0 2 Field Equipment Change Orders ( F ECOs ) RR-0 0 4-2 0 3 Design Calculations RR-004-204 Design Drawings ; 4.2.2 CONSTRUCTION ACTIVITY ASSESSMENTS The following checklists are to be used as guides for assessment i of the construction program procedures: i Checklist Number Sample Identification RR-004-207 On Site Equipment Modification RR-004-208 Equipment Installation RR-0 0 4-2 0 9 Piping Installation 12 l
4.3 PART 3 - AS-CONSTRUCTED ACCEPTABILITY Part 3 of the assessment program will address the following subj ects: o The Change Control Package (CCP); o The Finalization /As-built Program; o Acceptability of as-installed hardware; o Acceptability of quality documentation. o Construction Acceptance Test (CAT) Program 4.3.1 DESIGN-RELATED ASSESSMENTS O Che cklist number RR-0 04-301 presents guidelines for assessment of the CCP Program. The following checklists are to be used as guidelines for the ; finalization program: Che ck list Number Sample Identification i RR-004-303 FP-2 Hazards Finalization i RR-004-305 FP-10 Saf ety Related Equipment Site Verification Walkdown ; RR-004-306 FP-14 Seismic Separation O 13
-j
_ . _ _ ____________1
1 4.3.2 CONSTRUCTION ACCEPTABILITY 1 l The following checklists are to be used as guidelines for assessment of as-installed hardware and quality documents: 1 Checklist Number Sample Identification - l RR-004-307 Walkdown of Installed Mechanical Equipment RR-004-308 Walkdown of Installed Piping RR-004-309 Acceptability of Quality Documentation - Mechanical Equipment RR-004-310 Acceptability of Quality Documentation - l Materials RR-004-311 Acceptability of Quality Documentation - Field Weld Process Sheets RR-004-312 Acceptability of Quality Documentation - Leak Test Records ' 4.3.3 CONSTRUCTION ACCEPTANCE TEST PROGRAM The Construction Acceptance Testing Program will be evaluated by use of checklist number RR-004-313. 14
5.0 CHECKLISTS Checklists were developed to direct and control assessment activities for each part of the assessment plan. 5.1 GENERAL GUIDELINES FOR CHECKLIST COMPLETION An individual checklist is to be used for each item as described in Section 4. The checklist column marked " Item" provides a nunerical ref erence, if needed, when corresponding with the project. The column marked " Reference" provides the source of the requirement to be verified. The column marked " Requirement" t asks specific questions concerning the source document. The column mar ked " Finding / Comment" is for describing the actual ' condition found. A checkmark in the acceptable column indicates that the condition found is acceptable. An N/A in the acceptable column indicates that the attribute listed is not appl icable. An N/V entry in the acceptable column indicates that the attribute was not verified (due to accessibility, work in progress, etc.). N/A and N/V entries require a short explanatory statement in the " Finding / Comment" column and all items not verified. r aquire Readiness Review concurrence prior to closing the checklist. O . 15 l
)
l
. \
l A checkmark in the "Re j e c t" column indicates that the l Os-requ i reme nt of the checklist item was not met at the time of ' l assessment. The " Resolution" column is used to indicate whether I a Readiness Review Finding or Audit Finding Report was issued, ' or if the Project was able to provide sufficient information to close the item. The checklists are to be signed and dated on each page by the person or persons performing the assessment or audit and are to be completed neatly and legibly in black ink. i e O i 1 O 0112d/119-7 16
(~ MODULE 4 (SHEET 1 OF 2) 6 CHECKLIST INDEX Description Checklist No. Remarks Part 1 Design Commitment implementation RR-004-101 Const. Commitment Implementation RR-004-102 const. Commitment Implementation RR-004-102A Part 2 - Design Design Change Documents RR-004-201 Field Equip. Change Orders RR-004-202 Design Calculations RR-004-203 Design Drawings RR-004-204 Part 2 Construction on Site Equip Modification RR-004-207 Deleted, refer to Module 6 Equip. Installation RR-004-208 Deleted, refer to - 307 and 319 Piping Installation RR-004-209 Nondestructive Examination RR-004-209A Added during assessment Piping Installation (Suppl. Assessment) In-Processing Piping Installation RR-004-210 Added during assessment I l Part 3 - Design (N- Change Control Packages RR-004-301 FP-2 Hazards Finalization RR-004-303 Deleted FP-10 Safety Related Equipment RR-004-305 Deleted, program reviewed and Site "erification Walkdown found to be acceptable FP-14 Seismic Separation RR-004-306 Deleted, program reviewed and found to be acceptable ; I Part 3 - Construction i Walkdown of Mechanical Equip. RR-004-307 Walkdown of Installed Piping RR-004-308 l Quality Documentation - Mech Equip RR-004-309 l Quality Documentation - Materials RR-004-310 l Quality Documentation - Field weld Process Sheets RR-004-311 ! Quality Documentation - Leak Test j Records RR-004-312 l Construction Acceptance Tests RR-004-313 Deleted, assessment will be ) made under Module 3A Installed Piping (AFW) RR-004-314 Added during assessment Acceptability of Quality Documentation RR-004-315 Added during assessment Mechanical Equipment (AFW) Acceptability of Quality Documentation RR-004-316 Added during assessment Materials Acceptability of Quality Documentation RR-004-317 Added during assessment Welding Records Sheets-AFW (GPC Scope) 0173d/356-7/1
MODULE 4 (SHEET 2 OF 2) O Part 3 - Construction (Con'td) Acceptability of Quality Documentation RR-004-318 Deleted Leak Test Records Walkdown of Installed Mechanical Equip- RR-004-319 Added During Assessment ment Construction Acceptance Tests construction Acceptance Tests RR-004-320 Deleted, assessment will be Safety and Relief Valves made under Module 3A System Flushing - AJW Subsystem 2AL01 RR-004-321 Deleted, assessment will be made under Module 3A System Flushing - RRR Subsystem 2BC00 RR-004-322 Deleted, assessment will be made under Module 3A System Flushing -CCW Subsystem 2EG01 RR-004-323 Deleted, assessment will be made under Module 3A RT Film Assessment RR-004-325 Added during assessment t' , 1 l l l I i l l l 1 l k 0 0173d/356-7/2 i
O O O READINESS REVIEW.. CHECKLIST '. NO. RR- N - /<3/ PREPARED BY DATE AUDIT NO. PAGE I OF 4 P O. Andc'>!: s a-n7 SAMPLE IDE NTIFIC ATION pesifi G:n/ir*//inent/try.7/cmen7a7/ov AUDIT DATE AREA Contmi!nica,t ReNI!cocc No. __ .-_ . ._.. - F5AE cc -ix: L o cation __._ _ _ . . - - - _ - - AUDITORS ITEM REFERENCE REQUIREMENT FINDING / COMMENT ACCEPT REJEC T , RESOLUTION
- 1. Co' nnidnc'1f, \ssessment:
- a. fs FSA 7. ^ ~'m '~h" cemp/c'ce n i :lc ?
- b. Are S iicsonc/Docan> crit /
rcalistc iiiao o dwi&i P:- FSMo n/c/wly' afe/co'!
- z. Fi's/-O? o v-1 up/cinentofron Verifiorlini1:
n i<p7 o. Are o'cssgo cn/crja po,a-c ;;?.ia graphor fab /c numbeislist-f oc- C0?'mf ic& naoaccors/c ?
- b. /s Hien,mmi/nenfunplemenf-ed 1 f 7 (c cunentrevision ?
P&ID No. Crnenled Is $1e a"i"ni!rnenfimp? /c- _ .. bya P4 ZD
- d. Does /bc Pd IO c/hr.!f Sl70W ll/C c ,rmtr!bnerrf /tr7-p/ernenfatiati ?
Pojcc? c. /s Oc rendmenlihp/cmcn/cd xcfccice by Hic PRH ?
* = n:a/(imn) ;. Arc !!c sec/r i, :liwsw; i
Scc ll? r No. nrnnbc: .: liW^<$(Y:?'/2! clrY ~ c <recuralc ? . e e
O O O READINESS REVIEW CHECKLIST . _ NO. RR- OC>4 - lo/ Ih'UDIT NO. PAGE 7. OF 4 CONTINUATION S HE E T sc " - .- r. o.' I ITEM REFERENCE REQUIR EMENT FINDING i COMME NT ACQEPT R,EJEC T , RESOLUTION
- 3. Second-Ora'c -1mp/cmenfafion VeriRcation:
Calc. No. a. Doea lhe ca/culatiori ac-curafely in?oh ~r r' fie COrruni5'v?r ,? ?
- b. Ate arWebo rekicnces
/u/ce'ceucc!' wiS respa-t '
16 /be esmmilmenf ? ' '
- c. Is calculatioriinpr f oa/h ;
con.shfant wiHi ff'e co n mi/ men? ?
- d. Atc engiocerinpuagemc?O
/assump/mns wilhrespect:
16 /hc esmmiImcn/ clear io%fiscdi' .- /7 '! c./hs 1%e calcolabon been gocesseda.s a ~Q'c/assi-I fica /iori documenf ? i I ~ e Diriwing No. g. //ove o'eany r e :!:?t:r imp /c-inen/Ing /he ccm.ni/ men /bec ? incmmatedmio / hec /rswng?
- h. Does lhechmingaccanklyim-phienf thecommi/menf.7
- i. Diddrawnqinclicate ilsop- .
porfinga? fro /aborp rebvrgf to the cecent!~ntwere ar- - fecteO'? PERFORMED BY DATE _ _ _ - - - - _ _ _ ---__.__m__ _ _ _ _ _ _ _ - - _ _ _ _ _ _ - _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ - _ _ _ __-_______ __* _ + a __ _ _ - _ _ _ _ _ _ _ - _ _ ' _ _ ----m __ - +- 2.___ _ __
O O O READINESS REVIEW GHECKLIST 10. RR- ood - / o/
"^"'" "#
CONTINUATION SHEET-m c - A/o. l^"" ITEM REFERENCE REQUIREMENT FINDING / COMMENT ACQEPT REJEC T , RESOLUTION
- 3. Sccend-Ora'e,' Imp /enrenia.% Verificafion ( 7m/inued) frOCurrD/CitT i.4003 7 lbcj?n)(uter 17Cufdf' Cc-Specifica//on kofik acrwMtinpfe-IVO. InCr?l0C Crir!U1/lirscr7f ?
- j. If/bc comur/ men /pe4ms/b I
an 8STIE SrY ion N 0'G{? com-portenf does f4cspen6urbon inchar Hicpreface page, lhe ccrfificafioripage, arid
/hcAstiE Codem criferia locaforpag'e ?
K.H/Ae ramnitipici!?rek~r: /s rz 0-C/01S !$'r? G' ors k're prJ-frosa/ krm con.hr 55c: *:O!'f Vcflllrn! tori dornmr:rkrb"7 /j3f (SQVOL) ? l.// E'c ccinn:lnco/reN7a Yo m llonsolyrc/ b e ?rirsoincnl /
.c,ustificotuo ic:li17 asper ,
ANSr N45. 2.II-l'i' wric fac yerjanen1en/s fsr ser fcsling i(7C/Do'rO'.? M. Yll1C crinnt/firretifrChr3 l0 lbe Size orrW11.(' rig 0fEcfr?'j>rnerrf ore ca/ce/ofiorisovah6/cond ! curirn/ ik sufsporf//scsc re-I <7airemenfs ? l i PERFORMED BY DATE
- __-___ __________ - ________ _ = - _- _ _______- ____ __- - -_____-_ _ _ _ _ _ _ _ _ _ _ - _ _ - _ - _ - _ - - - - - _ _ _ _ - . -- - _ - . _ .
O O O : READINESS REVIEW CHECKLIST NO. RR-ood- /o/ PAGE -/- OF 4 CONTINUATION SHEET-R' c/crence A/o. IAUDIT NO ITEM REFERENCE REQUIREMENT FINDING / COMMENT ACQEPT REJEC T < RESOLUTION S. Sccood Orde Implenicolafion Ve:i/Iarfik 7(Confinued) Procen ,ncat n. Ild4c commi/menftefer.s 15 speciscoleu fesfs ths/weie rectowed a No. en.nuespeciNedperdvm-once, weic /he /cs/,eso//: documen/co'? Vendor o. Docc lhe veixlor docwnent' L9dCufi1Clif GCCun1lrllimg?/cmenf lbc [C/Cfc!7CC (l0 Continifir?ct?f P. Arc dila codmalab/sper-l cult!!?g [6 //1C (vinm)krienk'And SbMYr1077 !!!C Vr/1dorC0'G!rnent jn COniplidrlcC Wllh YC/XO-Ct/lemCr7lSpecihrnftdir ?
- q. Arc om/crialsyerfatoine,15 thC ccmmi/menY, ona sLwasa l
lhe venost docnmen,/ in com-v/isoce wd4 /he cso'cils CCc{e llcr77 ?
- 4. Projecf Reco da Refention/Sforage Verift afton:
cs/c. M o. a. //as this c6/co/afbr been rniciofibned7
- b. If/hecs/culdi~r has no/ ben mictOS/mcd arecopicuon N/c o/SPC //OE andPFE ?
4 PERFORMED BY DATE
O O O READINESS REVIEW CHECKLIST . NO. RR - 004 - l o 'd : PREPARED BY g, DATE AUDIT NO. PAG E / OF 3 SAMPLE IDENTIFICATION-Consituc/ron Connni/inent/ rep /mfat/d? AUDIT DATE AREA (Onriniftr7enl/?cfc'rcocc Afo. _ - . . . - . _ . - - - - FSAR Sc>ction Location #UU' URS I ITEM REFERENCE REQUIREMENT FINDING / COMMENT ACCEPT REJEC T , RESO LUTION
- l. FSAE 3. 2 2 Do curten?reviticrrs e///ic eco-MiiE JE sfracfiotr itnp!rmco!nigprocco'-
c/oaa z urcs s//Hrc<w"c cmktmance t'a l (/777$1u W77) 01e{o/lowM nrllc!ca of/dc ASPIE (on?mit$ncp? ElCoo'c,ol7 u/jseribns NO,NC<!NDI EC1 ?y/O. 6SO. el N5/NC/ND-4/OO, Gencia/ Rcc uitenictris PPPProccafncs E-SPera.I.I Appliarfleto Ast1EEprocesss/irefs 2L-5 lo'ra. L 3 nrnent ofANE "/lo/clPo!'ils " G-z Ibra. &.l.4 Assig&r Fans dmorks wi!nessed E-2tha.6.2.l.C AN[ review 07dsgri-ON - VE-2li'v.8.I QCInspec!o rcrifries onprocess slicef
- EE-l 171ra.1. I Ke' qui!cmeris formaterialinarking V?l-1 Thra. G. I Tisasfer sl markings 171-l llhr. e. I QC ftlSpcr/o"en/nes ooprocessshecf 7m-3 I?ra. /. I Geab
. 12-3 i rra.<7.1 Appiam Re s/ctosafef(w-rdifea'wek forwseo cMnama/c ial LT-3 n,ici. l./ los6faAsa ohsystems designedin Asnr; G-3 R?t<r. 3. 7. Cstnpor;cn/s slagoca'wi07 Af" symbol ID3 Pars. 6.7.1. A Fmal1olcolsi'r drss /42 weldjolofs IX-3 lbrs. /O.2 Fiying sysle irirr/ son seguracc G-14 thv. l. 2 Accryfance-1ejer/ son cri/cria 5-l4 lirra.3.1. I IVdo's wilb uvacc.- , bble in<fcofioris E-14 I!r?.r. 6.4 Exann?iaber$ ofAstfEEwl(l(tpeu G-/4 /}r?r. 8. / OccutnOsbr/ f ort krAS//EEIref.>ri's PERFORMED BY DATE R.R. TEAM LE ADER DATE
i N 3 O O I T F U O L O S E Z R E T G C b A E /o P J Z E e 0 1 Il R, W . T n;
+ P E
i r i 0 Q a 0 C A p 7e R 'ori R a
. T o, O N E t i
N . M i i n O M m N O a C x T I
/ E D G j U N c A I i
n 3l D a k O i N I F fi i r o H a n o g e c i r
/m n li: E cH nr ss
/ o a
t uE e di c mn l os Ss GM bt t v - et ot mo l0 b t t Sd o w)n m T C,d oi iaa cwEm H, I e G g A no 'caAei G M u m. o jE s
- g. E ed iM ti d/w
/ t ('Eo/wf s Sdiec r n li Ec n 'i I t r e
.d i
e ? 'o a le 1 i n I,l lptos-Sflc fl oEu o /r e f 'c I' i c" e /s S 'o rcSeu t ? u t i a E
/c on LK/n /
'i c T N G '(e A a -
'M coArq c s, 1 cl s o R FAe t ci l osour r Ce ci t a l T A
g E 0,( $ $> i 0, o ne terr n A m f i gw fe r D CS/m M 0
' 0, an'or 'a ci ann E C aI t
E / /c !c b 'S/ C s!c 0 4 s ummpb/a!nek ee x
'ico/e als l s H T- R I
4ne a ar 3 't ae /c 4 i ni
/ y! t gts/ i c n ei".
U ic lY 4- lli i ofnc u - i i i? G Q oml l l rr of F
$ !o /c A e oi E
E E R 'n er pi pe aI h' D a u /c i sp/s s r
/N D f/ss i w/cf r m mf elio g m r.
i n r c go Mf W H C; w N n
/
C 's qmirr i s iAc C ial /a Tom e r a ccla/m md o E S n 3 S sl s cr liub d /N i
/ c/c i
/BN n/ smmI I n viek I
V 3C uc RAY N Pia'4l WDf i i G N lye e /s eem A /m f W a r lIn P P E I G / E 1 E I- 1 2 _ R N se/2. 2 s I I
. 271 1A. 2 O
E C t n r .2 l~ 3 c l. 8 8. a
/2 .
i o eI l ,mo I..I3. 4.
/. I.
75
/
S I N e /u1 5 n e r n l.. I o 3. / 5.. I. S. 152 Y a n m ras. a.r en.a
. - t S T E m o. 0 d h s.
' . 3 (o'n slfafa II irr aa h i m o. O rc orr B A R / r lm o O c 7 r iN.c///ib lim/8A 0wPl ab uRl iR uK Fa R l% D i
E E i N . :. t0o2R o ll OND U ml8R525 n 0iEEE l N F E me8P rd m 8 f P3Ss i 88 - m F999 PI l 1 333344 EM 444444 I R oK 'Y R Co Re 8PGGGvEE Cofe8 P FIX K K G XI 5 E- K 1-I T C P O H G- TW L O A N M F R E O E T I 2 3 E P R C I
O O O READINESS REVIEW CHECKLIST . NO. RR-oo4-/ o a Co'?sNucRon 0 mint /meni' x AuoIT N . PA E 3 OF 3 CONTINUATION SHEET- /mp/cmenfah l
,IT E M REFERENCE REQUIR E MEN T FINDING / COMMENT ACQEPT R,EJEC T , RESOLUTION
- 3. 7vrimd~'il At t No.
e60.04 NB/NClNQ-4400 (57nkwCO) IPP/7ecedures X-18 lo'ra. l 1 Inspecfionropectam/s for wek/s X-16 lhra. S-I GrllNcnfion sfwchlinqpectons Xill-4 Wira. l I f ffe//noso!c' bin.hqppmg XE-4 thra.13.2.3 Class C/evelofcktra/ mess 1 l PERFORMED BY DATE
O O O READINESS REVIEW CHECKLIST .
'. NO. RR- *M fo? A PREPARED BY DATE AUDIT NO. /
R. D. Ana'r c o v: 7-t - a7 I PAGE OF 2 l SAMPLE IDE NTIFIC ATION-(ons/rcec40 7 d-me/arnf'' 5"~ ~ ~ ~iori AUDIT DATE AREA (onrini/ine ! 5'lU^"rc flO-
< AUDITORS i ,_Or A n, u. .c. ne Lo calmn _ _ _ ._ _ _ _ _ _ _ _ _
ITEM REFERENCE REQUIR EMENT FINDING / COMMENT ACCEPT REJECT , RESOLUTION
, I. Gmmi! men?A sessinenf:
- a. .r= rsA eserli /ocofis i
<v :p?rV onclaccarate ?
l). ,NIC Sil3JEC7 o~a!Z20 Cut?ENTjl FEA7ticE itt acrerdtvi//r ife FSAir e?rdc/ car /y s,hico'?
- z. 4,mm/me :/ /m >/cmenfa/ ion:
Grc Field a./s Me tommi/menfimplemechd
/Jecrc'mc />y flits (210crckitc.?
G D - A-30
- i GPC DCd i b./s /bcp*rimd'irrahmp lemenfrWl7
/IrCnE'?r //riJprecr</are ?
G D - T- l/
- 1 GPC Ficld c.fs /bccotismd?rcti!iirij)/ crier >&d/>y Procec'?<c frispioccdure ?
?10- 7-iz
- l Prrnocckrc
- d.Is /%e m nw!hienfimp/cmecifrd X-5* by /4u p?ccMerc ? -
17/11s ing. 'em ulma dro nc..f mu od. ,!-,r ,i, nArs r. wfinrsr ren .rw ix PERFORMED BY DATE R.R. TEAM LE ADER DATE
O O O READINESS REVIEW CHECKLIST NO. RR-00 '- / 0 ZA
- On/nu# men / AUDIT NO' PAGE 4 OF E CONTINUATION SHEET /m/: mcc N >.
pTEM REFERENCE ftEQUIR E MENT FINDING / COMMENT ACQEPT R,EJEC T , RESOLUTION
- 2. /hmim/mcri/ E vpfen7enfailort:
Jixtikakui c.Is tho ro<mnilmoiihmple-k-1AF03* meufedbyNis.speci$cofiorr? Ecv.No.e (Typics/ o/ M /IE Eilem ' l pro:1ricment Sprrs.) l l 1 4 + 9 i 4 Tlris tiny 7rirnbikf Obr //trreirfIVas trofJben't7 '!? 2/ A13EOBF/;IAisr.FRt11riab iX n PERFORMED BY DATE
O O O READINESS REVIEW CHECKLIST .. NO. RR - <RM-7 o / AUDIT NO. PAGE / OF Z R d/7o#rC1FS _y,g . g ;r SAMPLE IDE NTIFIC ATION - DCN's, FCR'J, andCSC//3 AUDIT DATE AREA Orawing No. Ece DCNorFCR No. Cor?sfrucitori Spec.No. Rev. CSCN No. AUDITORS ITEM REFERENCE REQUIREMENT FINDING / COMMENT ACCEPT REJECT , RESO LUTION
- 1. Projecffef- Did f/ic c'umere affectofher e ,en r c t rari- driciphr?cs, aridifcq was l'>c
,,a/(pg?;) inferoksriphric review Wockso C4 4.8 markect,' cintfore /Acofriopr?afc C l 7 17. 5.3 stynafares,presenf C 26 26.7. I
- z. PfNI Pid //ic,r/ tang?c n,ri0ic! yj//
C4 4.8 or devinic ficoi //c FSAg or C17 /7. 5. 3 OLSER, sw//,40, Warn Lic-(26 26.7./ entitig Devinfiori Docurnent (L DD)irri//afed ?
- 3. FRtI thc cliccl/ialon f
/hel'ack C4 4. 7. 5 usitt$c of /t FCR Forml oe/ctminc if C I7 /7 5,3 the Cbonryees/kcfec equipn7enf C z & 7 6 . 7. t que///}co$10rr, hazaros,or I fire profeefton desi documcri/ oroce:gn.
- edinscre?dsxcIfso, was /be wJ/> cda 6lir4edp oecrhic: ?
4 PRti c4 4.8 IAbie //csjpfsyeo/cbso0 incorpornfrain f/ ere/a a!7 17. 6. 2. 6 drawiner srspcci,icanen ecricd C26 26.8 /y, anilw/O'n !be !irne linmc l s/sko in /Ac /Tl(? l PERFORMED BY DATE R.R.TE AM LE ADER DATE
O O O READINESS REVIEW CHECKLIST 10. RR- 004-20 / e PAGE L OF Z CONTINUATION SHEET-oced,Feesc" 17'S l AUDIT NO' ITEM REFERENCE REQUIR E MENT FINDING / COMMENT ACQEPT REJEC T , RESOLUTION E PR?f pic( ffe de:,ag (j,,,,g,,(p. C4 46 rcsruf po&u/!alricol,,f s,;d C/7 17. G. 2.4 i{So, yvaslbe cher,i7e coriccf/y C26 26.9 irdica/ro' j'
- 6. PRtl Werc revisions f6 </eciqndefails i
c1 4.8 invo/vedin this change,ano'ifso, C/7 I7,5,3 were f/>ey kcfmicall fao'equafe ? .
- 7. F12ii Diclll1C O'Caigt? clronge tcquirc c4 4. 8 anof ifSo, C/T l 7. & . 2 a cn/cn/ abort sension,lsboririot-er ca/Ca n'es eo on flro f
//ie cprop / range ?
lC26 26.7.1
?.'
- 8. FKt1 ((an FCli was afiProwt/wiNoal c ! 7 17.5. 2 n c/innge 6vyNA), (Nc/ ,
a O'esig/ wiffi /de PRt1goiab-ilconi;>7 lines .
- 9. PRif C /7 I7.8 ]{sti FCR was wrillenergai,si sipp licrcrpupmr rfy&cumen/s, Wss ilforininorchcoges on/y, os specifico% //c PRt1.?
T _ .. -- __ O O O READINESS REVIEW. CHECKLIST L NO. RR- 0o4- 2;z PREPARED BY D E AUDIT NO. PAG E / OF 4 SAMPLE IDENTIFIC ATION AUDIT DATE AREA FicidEca?pmenf Changc Ordr= [FECOa) FECO No. Rev. No. AUDITORS ITEM REFERENCE REQUIR E M EN T FINDING / COMMENT ACCEPT REJECT , RESOLUTION
- 1. /A'// ]{/4e FECO was wrifen tjsic? c C24 24.4 o C-c/ess, firepro/cchort, or red'was/c conysraii m3;%c ano a;yvopirek Aras &cFECO boxevalecho*
c:'iceIcof's,c!' skjnedbyMojeefQua/d As-sursacc Sigiurering ? Z. Peti Z{/be FECO wa.s wrifen agsinst C24 24.5 a G-chr.ss breprokchon, or rachens/c c,enl>vonen?l wirs on e no//roriza-egulppienf sco/c imig/0 //reoriginet/
/equpmen ton (ECA)/ supplic5 n proycof sndclosec/colprior 7,6 issue o///re FECO k GPCCxs/rac-fiort .7
- 3. Eh'lI '
,i'evc c,//ofoworgs and/orOcc-C 2424. 3 untrii/: required 12 work f/>c 24.4 FECOtc/crencrcion//rcFECO?
- 4. IK'l1 00es flic FECCprovic/c <rof-C7A 24 3 epicfejosfi/}calion G>r //je Change .?
PERFORMED BY DATE R.R.TE AM LE ADER DATE
O O O " READINESS REVIEW GHECKLIST NO. RR- 004- 202
"^*'* "*
CONTINUATION SHEET - FECO's l^"" ITEM REFERENCE REQUIR E MENT FINDING / COMMENT ACQEPT R,EJEC T , RESOLUTION
- 5. PR11 IAere l niaferiala or compsarnis C 24 24. G for FECOb fo 0-CS133, {irc pro /cc/ ton, or mdwc73feihms pia /
purc.besed sopphcrandiforffrom /bcon);f4c dd a// eras /c.sopp/iercomp/y , nin theannequo///p raysm re<70!?cmenisas /hoseimposcd on /Ae ortym/suppher ?
- 6. PRti Il/Ac FECO /7cis bctnc wp>k/-
C.24 21.7.8 ecf, /tes Scflojer/Eriguicer signed //curdrefurocdil/5 HOE!
~.
! PERFORMED BY DATE I l l
O O O READINESS REVIEW CHECKLIST ..
. NO. RR- 004- 203 PREPARED BY DT AUDIT NO. PAG E / OF 3 SAMPLE IDENTIFICATION Des /gn (a/cn/a//onS AUDIT DATE AREA Calculatico No. Rev. hto.
ITEM REFERENCE REQUIREMENT FINDING / COMMENT ACCEPT REJECT , RESOLUTION
- 1. PRt1 Does calcohlio, conform 15 the C7 9. 3.3 rego>iemenk of/Aeopy/? cab /c o'esign cri!cria !
Z. 72/1 270es eskuleiwn coverJdec/ C9 9.& confoin /AefoMnvingenhies? y classibenfiou
= Quslil a 736/c ofconfenk (ifca/ce/elen is conp/ex orio aMndedink sches/cu/a4sas)
- 3. FRr1 poeses/cuMon/4hjpropriufe c't 7.&
desipassum wWe s Asrsonday codes,p/sodeds / on,o/i-c re(crcnccc ? 4re itstie dalcs forf4c roc /c:.no/skohich
?n'"llc Scsigtsreb,c#'S
- 4. j'R?! /s catechnon ansis/en/wd4 c? 7. G requiscincnts of/4crehrenced -
l codessno'shn/ards ? l l
, e
O O O READINESS REVIEW CHECKLIST NO. RR- 004- 2 03 . . , E PAGE 7. OF 3 CONTINUATION SHEET-vesign G/cul77 eons l AUDIT NO. ITEM REFERENCE REQUIR EMEN T FINDING / COMMENT ACQEPT R,EJEC T , RESO LUTION
- 5. PRH C 'l 9.3.3 Mrsengine:ringjud exercisro'iima.fi ementg/birarl-culafion sodi/ a v d ccv7-form /o bC k//Gl+704//inifd!isf13 ?
oessisisdocomenfed.wlherenif 0,Crhonale esa Ac verised a re - simp /e handcs/co/abon,6/c doc-encefasoMbona/avai/a unien;'afior, ertefcicnec% in-foroxrfioin known in f4e inechanica/c4 cybac.
- 6. PRH Arc wri//r/
C7 9. 3. 3 hrc/ocaneuhi$!abbnesbvai/able, sand / sic %>acc fi>gadd da and do chdiyes in e cs/ca on 1 confsrin16 /hesegolde/ines ? 7 PRn Areknownic<7wrcinen/a forea/- i c9 'j. 3. 3 cu/ anon revistsas en/crcdend i sc/re&bde, /4c G3/cv/snon v l &nho/ Log ?
- 8. Fett ]>didradidrhevioliLzea arc c7 9.G.I shr>&redcompatry,opci, and I so pl3 br)?/8cfS101non?br?'OnoN of~nomcanof verslon rehrencec/.?
A
O O O READINESS REVIEW CHECKLIST NO. RR- 003- 2 o 3 CONTINUATION SHEET vesien G/cu4dous l^"""' ITEM REFERENCE REQUIR E MENT FINDING / COMMENT ACQEPT REJECT , RESOLUTION 9- FRt1 Poca flic ca/did?? ion as hsued C7 9. 7 reflect /baf $c 4!bwMgrAmb were performed ?
%/bi/sfion aftws ni/4desgo mpa/documeola forcoerfigo -
slico, dimensiso, aridms/cria/ regoircrneofs o EL*GignerfIo/Xff olI//2cOlc3-sampfrans, ans/yfica/me// ads orconseryanvcapproximatiori desigo methods o /Jumerica/resu//sste conSJS-fenferi/drayoiredmo/hemaf-icalaccorsey of the es/adr-ll071 PERFORMED BY DATE
O O O READINESS REVIEW CHECKLIST ..
. NO. RR- 004- Zo4-
# AUDIT NO.
2 f,2 /fr10rety3 I U#h 93.g7 PAGE _ / OF / SAMPLE IDENTIFICATION Des /g/7 D/gw/ngs AUDIT DATE AREA Prdwiric7 hl0. [cV.No. ITEM REFERENCE REQUIR EMENT FINDING / COMMENT ACQEPT REJECT , RESO LUTION
- 1. PC/1 poes Mcdrawingainforw to C4- 4.7
$s/icable iga cn/criarc7airementsof/Ac
?
- 2. PA??/
C4 4.7 P>es $1e drawinh)conbrm f/ie calcolatiori reviewec/ /5 unoer /h/sprogram ? 3 PRt/ Poes Nic cr'swingeonform ]Y> C4 4. 7 projectbea7singcommitmenfs ?
- 4. PRH Does a pipingor/do,qrapbic or c4 4. 8 r cewafe son isomeinc
/de P&ID,drawing sacrt C /so wirs a PCN wi.h agams/ ,$c P4m enO')SJorcipnor is er(c'?co r-renf/7wi/h f4epipingdrswmgr?
- s. PRn /lis ibe drawing receiveda//
C4 4.7.3 recjuiredsignefores ? PERFORMED BY DATE R.R. TEAM LE ADER DATE l
O O O READINESS REVIEW. CHECKLIST '. NO. RR m-2e PREPARED BY DATE ' AUDIT NO. 6 R. C. Sommerfeld PAGE 1 OF 4/16/87 SAMPLE IDE NTIFIC ATION - PIPIN G INSTA LL ATION AUDIT DATE AREA ISO NO: WELD NO's: AUDITORS ITEM REFERENCE REQUIR E MENT FINDING / COMMENT ACCEPT R,EJEC T , RESOLUTION
- 1. CONSTRUCTION PACKAGE 1(a) PPP SI-87 Are documents in construc-Attach: B tion documentation package the current issue?
1(b) Are all required documents in package? 1(c) Are they properly completed and signed off? NOTE: Also review docu-ments removed from package and stored in vault.
- 2. MONITORING SURVEILLANCE OF j INSTALLATION WORK 2(a) PPP VIII-3 Rod requisition required Para. 8.2 for withdrawal - review for correct entries (check 6 entries) white copy retain- ,
ed in document package. Yellow copy with filler
- metal.
j Returned filler metal recorded on white copy (if PERFORMED BY DATE R.R.TE AM LE ADER DATE
O O O
~
READINESS REVIEW GHECKLIST NO.RR-- 004-209 CONTINUATION SHEET- PIPING IN STALL AT104 ITEM REFERENCE REQUIR EMENT FINDING / COMMENT ACCEPT REJECT ,RESOLUTHM6 , 2(a) - CONTINUED - applicable).
>2(b) Para. 7.2.2 Low hydrogen covered carbon 8.1 steel and stainless stored and/or issued in heated containers.
Para. 8.1.4 Verify welder / portable oven assignment chart agrees wit) welder No. on rod requisi-tion with container. 2(c) PPP VIII-3 Verify satisfactory comple- F Para. 8.4.2 tion of semi-annual check of P PPP XII-2 >ortable rod ovens (check 2) Para. (All) 2(d) PPP VIII-3 Review accuracy of weld Para. 8.2.1 :netal traceability stamp fo) (accuincy - review against
, rod requisition. !(e)I PPP 2 VIII-3 Review for identification Para. 8.4.3 tags on each piece of bare 8.4.4 filler wire and consumeable insert (in welder's posses-sion). Check against rod requisition and weld metal traceability stamp.
O O O READINESS REVIEW CHECKLIST NO. RR- 004-209 CONTINUATION SHEET-PIPING WSTAU.ATION ITEM REFERENCE REQUIR E MEN T FINDING / COMMENT ACQEPT R,EJEC T , RESOLUTION
- 3. PPP VI-5, REVIEW OF PROCESS SHEETS SI-40, SI-87 3(a) VI-5 Review process sheet for:
Para. 4.0 1. Accuracy of entries on upper portion of form.
- 2. Review sequence of operations for logical progression and/or obvious omissions.
- 3. Assignment of hold points and initials for accepted hold points.
- 4. Check iso package, re-view checklist for logging of process sheet PPP VI-5 5. Review accuracy of Para. 6.2 listed procedure rev-isions.
3(b) PPP VI-5 1. Does welder have cor-Para. 7.0 rect process sheet?
- 2. Have hold points been passed? If so, how resolved.
- 1(c) PPP IX-3 Nondestructive examination i Para. 7.4 l. NDE is specified cor-rectly.
PERFORMED BY DATE
O O O READINESS REVIEW CHECKLIST NO. RR- 004-209
^ ' " ' ""
CONTINUATION SHEET-PPWG WSTAU. ATioN ITEM REFERENCE REQUIREMENT FINDING / COMMENT ACCEPT REJECT , RESOLUTION 3(c) - CONINUED - PPP VI-5 2. If weld repairs are Para. 9.5 required, a repair process sheet has been properly prepared.
- 3. NDE examiner has init-ialed and dated opera-tion entry if NDE was acceptable.
- 4. Review completed NDE report form for accur-acy and completion.
- 4. WITNESS OF INSTALLATION JPERATIONS PPP X-18 1. Monitor " prior to fitup*
Para. 6.0,7.0 inspection activity. 8.0, 9.0, 10.0, Attach. D. PPP X-ll 2. Monitor fitup/ alignment Para. - (all) activities and inspec-tions - use checklist on checklist on attach.
"D" to X-18. Verify inspector qualifications.
l)PP VIII-l 3. Monitor fitup/ alignment Para - as activities and inspec-appropriate tions - use X-18, attach. "D" checklist.
O O O READINESS REVIEW GHECKLIST NO. RR- 004-209 CONTINUATION SHEET- FIPINC INSTALLATION r- ' FINDING / COMMENT ACCEPT REJECT , RESOLUTION ITEM REFEuENCE REQUIR EMENT
- 4. - CONTINUED -
PPP IX-58 4. Monitor in-process insp-Para - as ection activities - use appropriate X-18, attach. "D" check-list. Verify inspector qualifications. PPP IX-19 5. Monitor final inspectior activities - from X-18, attach. "D" checklist. PPP X-10 6. Assure that " welding Para. - (All) surveillance" program is functioning. Request the performance of a " welding surveil-lance" report on at
, least 2 welding opera-tions during part 2 in-process reviews.
7 Monitor welding activi-ties. Review for con-formance to GWS III/1, IX-3, IX-19, IX-29 and welding procedure ref-erenced on process sheet NOTE: Auditor to select specific characteristics to be assessed based on work being performed.
- 8. Record welder's stamp number and name and verify qualification status. .
O O O READINESS REVIEW GHECKLIST NO. RR- 004-209
- CONTINUATION SHEET-Piemo mstau.ATION 1^ 'IT E M REFERENCE REQUIR EMEN T FINDING / COMMENT ACCEPT R,EJEC T , RESOLUTION
- 5. WITNESS OF NDE ACTIVITIES a
PPP Proc. Witness at least 2_ NDE IX-MT-3-W77 surface examinations for Para. - All conformance to procedure. Auditor.to select character-PPP Proc. istics to be assessed - at IX-PT-1-W77 least 4 of those listed below. Para. - All
- 1. NDE examiner is qualified to PPP Proc. perform activity.
IX-MT-W77 Pa ra . - All 2. Personnel qualification records support SNTTC-IA level of NDE examintr.
- 3. Pre / Post examin-tion cleaning materials and test materials meet procedural requirements and are documented
- 4. If using 11T process, review calibration status of equip-ment.
i
- 5. flonitor examination and ver-ify proper sequence and technique.
G. Review report for accuracy, completeness, signature, indication of examiner's qualification level. l _ -
O O O READINESS REVIEW. CHECKLIST . .. . NO. RR- ON -M- A PREPARED BY AUDIT NO. PAGE - 8 OF c g3DATEggg7 SAMPLE . lDE NTIFICATION hjouoEATTWCTiv'6 EXAM pIpuf(a IA)G74 I. t A T 'n t/ AuosioRs pomenenut Axssstwnr) ITEM REFERENCE REQUIREMENT FINDING / COMMENT ACCEPT REJEC T , RESOLUTION I v)ITb!h ~SS nc :OPFAu= l ^X/M7/b/ATIDF/5 a,, REtnGtx) PA6rE 7 FOR /%SSESSMP/lT .D/
- lPL' T'i 31! 5
- b. RELD?.b for G/V+1 E x4MIA/A T!txt ohTIJC- CFb:
- 1)u)G No :
WlGLb Mo: . idbE EXhMIklPT:- PF.RFORMED BY DATE R.R. TEAM LE ADER lDATE
O O O READINESS REVIEW CHECKLIST NO. RR- *4-209- A NouOEWorTNE CY,MA I AUDIT NO. I PAGE L _ OF A_ _ CONTINUATION SHEET-mmo insTAttATron i I
'IT E M REFERENCE REQUIREMENT FINDING / COMMENT ACCEPT REJECT , RESOLUTION
{ WITNESS OF NDE ACTIVITIES PPP Proc. Witness at least 2 NDE IX-MT-3-W77 surface examinations for Para. - All conformance to procedure. Auditor to select character-PPP Proc. istics to be assessed - at ' IX-PT-1-W77 least 4 of those listed below. Para. - All
- 1. NDE examiner is qualified to PPP Proc. perform activity.
IX-MT-W77 Para. - All 2. Personnel qualification records support SNTTC-IA level of NDE examiner.
- 3. Pre / Post examination cleaning materials and test materials meet procedural requirements and are documented
- 4. If using itT process, review calibration status of equip-ment.
. 5. flonitor examination and ver-ify proper sequence and i technique.
- 6. Review report for accuracy, completeness, signature, indication of examiner's qualification level.
4
O O O READINESS REVIEW CHECKLIST .. NO. RR- 00'4 - E lo PREPARED BY AUDIT NO. PAGE I OF u' R 5014MECFELD DATE 6 l!Sk7 SAMPLE IDENTIFICATION AFk) 04LY AUDIT DAT E AREA 150 140. _ _ _ - _ _ _ Wctu pjo., AuDiroRs ITEM REFERENCE REQUIREMENT FINDING / COMMENT ACQEPT REJEC T , RESOLUTION
'G "P~ " ~' " I IN-RTocGSS P/P(M4 lMSTALUW/%l
'7 W9Lbrtdq p gttgit pq7j4 courect/weumererat 3.o (b. FJ.s > t c o) i>3 % r ,.
FcR_ Acc_o n cy 4 . COM PLGT6 ygs3.sewq ' G GMTP,lc 5 (ses I F P- M - \ 7_o)- List EEltx0 l 0) WELD MomPJER j (2) Issue bmE (3) Wet beP~ mat 9G (q } W s Lh s t. SNMEO L. (s T t>n ATEP~lAL MEC_ , I
@) REAT MOMER l
b, t/ERIFf 1 lLLER. MGTAL McAT' Mt)tacGr; Vs TA/,5/ 67MMPlNCicsed A one.UD
; wh6 Rob PERFORMED BY DATE R.R.TE AM LE ADER DATE
O O O RE ADINESS REVIEW CHECKLIST NO. RR- 00'4 -a to
"^*'" '"
CONTINUATION SHEET l^"" ITEM REFERENCE REQUIR EMEN T FINDING / COMMENT AC4EPT REJECT , RESOLUTION I.l FP- AI-/EO / te. PseulEU3 (MGLACE 30 @O Alt F tr Aytry ! 5>T/YT0% O kl (1) WELbEt OOhttF-I C/NT tu\ LOC 7 (7 ' \A/B(brdt T9' RPl.BPb5
) . .L p ISSOGh IM PbR.TitCLG Ibob D V6H !
G H GC t' (VHGTNGP-GME(U}(EED. Z.D ~2, 4 gggyo op ggth l IM Eit- b. E c c r i . D .5
<t.. es u u en) Foll-ACCORAuf 0p eJLTPiES or.! FOf'I'l -
d,.[, Fol2 WR_.- 5, i TGM6 I T Hit 0 IIA & D G'
- o. 2. Folt. OR.-5A.; ITEMS i Tutt.o il PERFORMED BY DATE l
O O O READINESS REVIEW CHECKLIST NO. RR oc4- ato CONTINUATION SHEET l^""" ITEM REFERENCE REQUIREMENT FINDING / COMMENT ACQEPT REJECT , RESOLUTION A.2 fP-M-I20,l b. HAVE lbs!(TiFIGb 2'h'N HOLD ECYNT6 GGEM SIG7 F!GL: OcF &{ l
/\ NE 30 28 REVtGW FCR PlatFEt R AMbLIFJG Of MOM-CDMFO( r nhMc&G, !C NP[
L(ST bt o EeLta 0 FCf1 FOTOP-E. PJb' f 6 ' I . g saw.- 5/5A WGLhida o FERATQl5 l 4o1 AMt> 5XHISIG REVICO3 OF V3Elb6 L l 120.1-A Ndb 6tf.1/Gl?.lFv WGLb6Eci O' ! M/W\& AAlb 6yMP_ot
- b. , tocs o3GLbsP_
KklotD toGLbtMg PRIz.MAETSCS ! cow _teur V O LT Ah,E 4A% FLO LO C. bCGS usGL6EIL HhUE MCCSS To WPS :~ ' PERFORMED BY DATE I l
O O O READINESS REVIEW CHECKLIST NO. RR- n'4 - D I O
"^*'" ""
CONTINUATION SHEET l ^" " " ~ ITEM I REFERENCE REQUIR E MENT FINDING / COMMENT ACCEPT REJECT , RESOLUTION 42 03E-5/SA OELb Ius/E77C# 4 F(AMG " RECCRbGb l P-EcoLTG " EssJ l PI- OT@ f '/ SICSMGB O CU 1 p " q" on,
"%" Vo GUTGh2RIGD 0 10 i TG R5 I2A ryc0 14 A ?
to. ggs Qcc Retevre TDtKLT con OELbu sq f . HA6 6CL GBMPLG O V160th. IN61ELTIOAl O!= P/AlA(, tMELb A!U) W/ T/ALGb ? 5.0 FP- rq- lLD ! NOMDESIPLU & 6'fAIAlkikf(Did
- 6. I 8. 8' a . If As PteQU6% r F(E MbG CGCM PRE-PAteb/FDitta!UWGb l 4
l PERFORMED BY DATE
O O O READINESS REVIEW GHECKLIST NO. RR- 004 - alo CONTINUATION . SHEET l ^" " " ' ITEM REFERENCE REQUIR EMENT , FINDING / COMMENT ACQEPT REJECT , RESOLUTION
.5, z FP-M - 120,1 b. EP NS6 /S 2 89'.D 5.2159 (u)/GlE s S ip ib:sste w )
~~)
DIb fu)S A10Y2 FP- N- l 76
~ .,
ATGPTlr?EP/VR Grt;nx :
& . IG R.G PA / P_. / $ EcQ'h' l' u]AS MGt0 03R-G RCEPALEb ? ,
6.o Fr- u-/20 / conL!r/ R@'R5 I:P-M - IC1.3 GP-ti 101,3 6.l Rquica) I kl- PPLMSS RE(.oP lps OMl4: l09. 5 ( 2.l Y} (L.. RGvt2t>> tAoPJL L l9 pAcucac,s couTEAl75 (* ' D V3 D o c. e m e u r L r g ( 2,5.0, LtsY Duscecryttugs, (2. 7) fr AssOPs THAf C-( z. s. 7-] )PLSTGb lMSPEGIOkl R6FD275 Ahlh v)R.-5lEAs - HAv'E CGEtJ .s6Mr ID DRS
"'"' """ " "^"
I
O O O READINESS REVIEW CHECKLIST NO. RR- (')()u - R 10 CONTINUATION SHEET !*""'
'IT E M REFERENCE REQUIR EMENT FINDING / COMMENT ACCEPT REJECT , RESOLUTION L.I FSM- /01. 5 s , R s vic ui D2g in n
I**# - V)P /Wh Ascoeg
, runr na srnrus lS CDF2GCY 1
1 l
=
READINESS REVIEW CHECKLIST ..
. NO. RP- 00 4-3 o /
PREPARED BY DATE AUDIT NO. PAGE / OF E 2 D.Anam/ irs s-g -ey SAMPLE IDE NTIFIC ATION AUDIT DATE AREA C/ wage Cooko/Pc7ckages (CCPa) CCP No. Rev.A/o. AUDITORS ITEM REFERENCE REQUIREMENT , FINDING / COMMENT ACCEPT REJECT , RESO LUTION
/. PRt1 Aic the folloiring dscumco!=
C3535. 5 inc/na'co'in Revistorr 0 of/bc Changr &Is/fac/agc? 35.5.I CCPLbyri Cherforbicbc.vife-n7s:
!)CCP turnber z)Revistorr nunsber
- 3) Descry >llett cfcbangc 4)Sysfcar designefou andden-over cle 'es 5)/nfern7afton (orp/enologo-d sc/icc/chn7 c)Approvalsigneforcs 35.5.2 CCP Oe: sin rirarije Basis:
1)/1ovio'is o'cAnieclofwiip! iou of /Ac chcoac z)Ac/cless k?'rvr !Insis he nic k/n g lb c c h ritre c 3)cticoars rceruccbo desiga lesfaccep!ance cri/cna 4)an/hcls irib;or chvides from PSAR er OLSER 5)/ mix 7c/ca clocamien/s nafinc!~o!- ed'in the eCP(sheef zof3) f;)Rre'?'Oferfion clestgr1 Cbn'b'!!Gb (shecf 3 of3) PERFORMED BY DATE R.R. TEAM LE ADER DATE
O O O READINESS REVIEW CHECKLIST NO. RR- 001-30/
"^*'* "*
CONTINUATlON SHEET - n^F.s l^""' ITEM REFERENCE REQUIR E MENT FINDING / COMMENT ACQEPT R,EJEC T , RESO LUTION
- 1. (Confu:xd) 35.5.3 CCPI?ocumenfobon List 35.5.4 CCP Pfo/crie}c Sheet 35.5.5 Design Inp/cmen&ifiou Doc-untCnfy
- 2. . PRi/ Does the ccPirn/wfanyof/bc \
C35 35.5. L prog 3 o {be[raars/ia/cdons/>ceiszand Pesign Change Dosis Afechmeng sudifso is /he ;
//cm being /rockedo,n WiePCW !
Progran7? ,
- 3. 7Ktt Are allo'ocninents requirco'15 C35 35. 5. 5 imp /cinen/ /4e CCPreferenced onthe CCFDucumenfafjon /isf?
l 4. PRM 1s lbe CCPtrombered'cor-C35357 rec //
/?
- 5. FRH Were allIDCNbcmd'XFCRh c a s 3 5. 9 excep/ //wsc volo& dor used '
for voicbrig converko',$ PCN's wifbirr /0 wo" king day 5s(kv-recc/pfo!/beclosedoutCCF fioni GPC Nur/corOpernfions G. PRt1 Are confic//eo'copiesonlyis-C35 356 s'Hed to GPC Constructiori or i Noc/re-t/pera7Intis
' '? Arc un- '
controlled &oins amWah/e ? ' PERFORMED BY I DATE { u
* - - - - - - - - ~
O O O READINESS REVIEW.. CHECKLIST '
. NO. RR- 004-807 PREPARED BY DATE AUDIT NO. PAG E i S OF 60L R E s pe r:L/x st Y A. 2. / 9 /Fa 7
! E Lt i t c, FJ o , AUDI.T DAT E AREA O W C" ./ I ';> O M O . R e_v-AUDITORS AS M E COD E. CLA'3S ITEM REFERENCE REQUIR E MEN T FINDING / COMMENT R,EJEC T , RESOLUTION ACQEPT W AL1- '.DOW N OF l bj 5TA. LLE D MECHAN \ C AL E QU 1 Pi 4EA l PPP-1-s VerziF Y FizcE DOM FEoM - p s m Q p_ .
~
Po R . G . I . I
$ PPP-M- 5 YERIF Y ev iD E R GE- of-Ps e s o- wouipmeMT tennistWEE o tq0E~ ELE',2 COV E12. ,
o IMSTo,LLA-{ f O 14 AW D Ecp%t O C. C/AN TLse c. t <tE U T C P o 1.-\ tE A] E ra s cu s12C,EE-
, Res \STA "ce T E ST'u('
O f E LECJ)2.8 CA L_ CCPL) I p M ELbt ]
. copsqtos A.w ro Lu t', e i c/AT IC N o tr-M G Cl-4 1ECP U ' P MIEt4T
) PERFORMED BY DATE R.R. TEAM LE ADER DATE
O o O READINESS REVIEW CHECKLIST NO. RR- 004-3o7
~
PAGE '2. OF 6 CONTINUATION SHEET l ^" " - 1 ITEM REFERENCE REQUIR EMENT FINDING / COMMENT ACQEPT R,EJEC T , RESOLUTION
, 3 FFP-H-48 Ass 1550 ) N LTA.LLE D PAR. 4 3.1 EQu tpM eMT E56id5T Th F_ MLLOW INC, .
p2& WIN Cr5 / PRocEDOETE5 3N PPP _T_-L 1 YaspoE De6w NC) - Fu . i.4 1 , 9ack 4.s Aucl-40e soLT PPP-K- 4 6, D f6CI W C, , 6 l'E E AMD Pe g s. t .'2 peoJEcyt osa . ppp. g .4g hes Mcholz so
~ @)
g g ,y peopsely pc,kTc EP fad 1,2' Auo e@'PMNT 2 l 4LIC,M (E D l l 3(C) PPP-E -46 LA Yo u 7 o R6-w i N c, PAe s.o (rouwcwTiou ocowiNCQ-Buck A.s oEin"TATio"> ELEVAT t 09 , N o Ef LE. l l__ c c A q f C) M , E-T C. . I ~-' PERFORMED BY DATE
O O O READINESS REVIEW CHECKLIST NO. RR- OOd - 3O 7 CONTINUATION SHEET l^""' "^*' " R,EJEC T , RESOLUTION ITEM REFERENCE REQUIR E MENT FINDING / COMMENT ACQEPT 3(1) P P P - F -4 6 P(_I D - euck A. s FL~rz. 5.O gu q p m s.93 Th c-, 90., Cn e p Et2/S.L MOTPJ , oizAa es 4 V t= tJ T 5 CcO D Ec TIOtd , 907.7,LFJ S\t c., i 3(c) PfY-E-46 Iso pgavviuc, - P/i2a.S.1 5 U CH A 5 w OV_-7,L E - 012 te 01 A7 t otd ,9( c E AMo ELevA t IOW 4 Pf2F-H-6 A%Ess sTo3Ac,E Awo M AIN TE N A N CE OF eo u i P M E N T d(4 FF' x4o, gqh bh u s/15 5' s3odofiwsrAaeo i PPoFEF1Y 4 W P P * ' # " ' #- g a gp E CT 1 o td W/1.,S Down witT -lI i fJ t 9pgcifiE D p p t2 t O D . 4
O O O READINESS REVIEW GHECKLIST NO. RR- 00 4 - 3 0 7
~
"^ ' " ""
CONTINUATION SHEET l ^" " " '
' ITEM REFERENCE REQUIR EMENT FINDING / COMMENT AC EPT R,EJEC T , RESOLUTION 5 PPP- Wili_-9 Ve. elf'/ WAND LIN C, of PAe 3.2 eQu t ptneuT
.T. p acqu iniE.D Foe t iFT, le ThE SKETCH ceieiiuc, How DE T t*~_
L)[#'[ W T o Fa E PEgpogtAED , ATTAdM To ThE f'EC)CC7 G s H 6 EE-T 6 FPP-51-41 House ke e pi>a c,
'E5 TH E '2Tb izac, E.
Ai2 E A pt70pE LL l N M At id-{A ltJ E D AND, PcOTlidELyIU6PEc P Df 7 FPP-XV-2 D EE.V T h T l CD bJ e p Pp -717ii_- 1 Is Tl4eRE AMN DEFictEtJ-CIES IN At47 OF ThE ASOVE IT EM 9 (f(A,3(6)i 3Cc ), 3@),3@), 4 (a), 5 Ano 4 1(<i) PFP-TV- 2 WAS DEFICIENCY PFcfEELY PAR 6.O iOEMTlfIF-p A,ta D REOLVE D ? '. PERFORMED BY DATE
O O O READINESS REVIEW GHECKLIST NO. RR- 00 4 - ?> O ~1
~
- PAGE 5 OF 6' CONTINUATION SHEET lAUITN
,ITEM REFERENCE REQUIR EMENT FINDING / COMMENT ACQEPT R,EJEC T , RESOLUTION
. f{b) f7 P- XV - 2 C6 The EtE."olu ptoMS PA e c, .o OF DEf tCIEklCIES W1Th "US E-/4 -) 5' o e ' E_EfA.lfR' DEspost po ea s k A.VE-CLE A R STATEMENT OF JusTIFl%~ Tion ? 7k) PPP-D -2 A iz e c o P IE 6 oP PA.R 1o D EN 1/A.Tl O N 9 (p52 s ') M A WJgMIE.D p e,2 P PF- Y\/11 - l 70 eev-xvii _i veaiyy TW4q closeo p g 30.0 orzs Aac sTomo iw rk e v,su LT - PERFORMED BY DATE
O . O O READINESS REVIEW..GHECKLIST '.. 5 NO. RR- "4-308 PREPARED BY DATE audit N . PAGE 1 OF 4 R. C. Sommerfeld 2/6/07 5/20/87 SAMPLE IDENTIFICATION - Field Walkdown of Installed AUDIT DATE AREA Pipino ISOMETRIC NO: REV. ITEM REFERENCE REQUIREMENT FINDING / COMMENT R,EJEC T . RESOLUTiGfi ACCEPT Field Walkdown of Installed Piping NOTE: It is suggested that the auditor utilize attachments to PPP p ocedure X-24 as method e t documenting the info mation and dimensional d ita required by this che :klist when applicable. Review PPP X-4 and X -24 for guidance on inspection methods. L. PPP VIII-1 /erify that material and Para. 1.0 components are properly 6.1 narked - record markings for 6.1.1 later reference. 6.1.2 6.1.4 6.2 6.3 8.0
?. PPP X-18 Enspect installed piping.
Para. 7.1.1 Jocument acceptability of : 2(a),
. Installed dimensions Slope i Sleeve clearances Valve orientation -
-Valve flow direction Valre size / press. cl's.
Pipe size schedule Piping material 6 e e
O O O READINESS REVIEW GHECKLIST NO. RR- 004-308 CONTINUATION SHEET - 0;$$lkM of l^"*~ ITEM REFERENCE REQUIR EMEN T FINDING / COMMENT ACQEPT R,EJEC T RESOLUTION 2(b) PPP IX-3 CONTINUED - Para. 10.1.1 Seismic and thermal separation between piping systems and other obstructions. Para. 10.1.2 Dimensional tolerances. Para. 10.1.3 Clearances in piping penetra-tions. Para. 10.1.4 Position tolerances of valves i and other in-line components. Para. 10.1.5 Position tolerances of metal bellows expansion joints. Para. 10.3.1 . Clearance requirements for inservice inspection of Code Class 1, 2, and 3 piping. Pa ra . 10. 3. 2 . Separation between components i attached to containment liner l plate and internal structure. Para. 10.4.1 Separation between hot pipe and electrical tray or conduit. PERFORMED BY DATE
O . O O READINESS REVIEW GHECKLIST NO. RR- 004-308 AUDIT NO. PAGE 3 OF 4 CONTINUATION SHEET - Field Walkdinsteiied pToinlf t ITEM REFERENCE REQUIR E MENT FINDING / COMMENT ACQEPT REJECT , RE.90LUTION CONTINUED - 2(c). PPP X-18 Welds meet visual Para. 7.1.5 quality requirements 9.0 - Welder's symbol
, 6.7 Weld contour
- -Weld size
Specified welds made
- Undercut PPP IX-52 - Free of arc strikes and spatter or eval-uated per PPP IX-52
- Free of cracks j 2(d). PPP X-18 Pipe and components are PPP IX-52 free from damage PPP X-24 . Dents, gouges, etc.
I PPP X-4 Arc strikes, spatter
- 1. PPP X-4 If as-builting and/or final PPP X-24 inspection has been complet-3d , compare assessment results to PPP records and record differences.
- 1. PPP IX-5 Assessment of bolted joints-when assessing the accepta-bility of bolted joints, use PPP IX-5 methods and record forms.
Pa ra . 6.2 Verify material accepta-6.3.1 bility and identifica-tion - bolts, studs, nuts, etc. PERFORMED BY DATE
O O O READINESS REVIEW CHECKLIST NO. RR- *4-308 l AUDIT NO. PAGE 4 OF 4 CONTINUATION SHEET - Field Walkdown Installed Pipingof I ITEM REFERENCE REQUIR EMENT FINDING / COMMENT ACCEPT REJECT < RESOLUTION
- 4. - CONTINUED -
Para. 4.4 Acceptablo number of threads beyond face of nut. Pa ra . 6 . 3 . 2 . C . Torque seal on all studs / nuts in carbon steel joints has been applied and is intact. Process No torque seal on studs sheet, items nuts making up stain-7 and 11.b less steel joints. SI-87 Bolting process sheets
- IX-5, 7.0 and supporting document: ;
are available. 4 4 PERFORMED BY DATE
O O O l READINESS REVIEW CHECKLIST .. '. NO. RR- 004- 3<99 PREPARED BY DATE AUDIT NO. PAG E / OF 3 g, SAMPLE IDENTIFIC ATION AUDIT DATE AREA l /CCrijfsbi/ilg O!Qua//by DocumC17lOfio!7 - l [fod 7on#c r! Ecj(tipnicol AUDITORS l i ITEM REFERENCE REQUIREMENT FINDING / COMMENT ACCEPT REJEC T , RE SOLUTION
- f. SwomenfMooli!icafion Er;7riloment Tac;No. .
ASn2 d>o'cseria/ Alo. Froject C/scs No. tlaoufacfucer. Purcl10se 0!$fNery1 hl0. v]Decifica$orr No. Ve90e' r.Doctwicnf SFC FPhlo.
- 2. /nsi,//abon Decamcoi%fron PP?nocco'v?c a. Insla//ofisriprsecas sAcc/s vi-s, Para.1.I, revieweaf for:
- 4. z, 4. 3, 7. 7. l o//olopoin/s syned oAppropriaTe edric.s made oAppropttaTcsgrxrfores FPPMocedorc b.Documen$ assocWm'ni07 /de lx-48, Para.4. 2 pio< css sherfsre atacbeo'os ;
app /iorb/c:
. *R)qqmp%od//ng ske/ches oAligoment c/ reefs oGroofrcyees/s oSupp/cmenh/procctrssberis PPPl'roccck.>c c ffocctiric revrJians lislea'on //re VI~5 lhra. 4.5, r
- 4. & pln:ocess shec/cic n~ircf kr 1c efittspecfion oc/Wilf Ix-40, Para.4.&
PERFORMED BY DATE R.R.TE AM LE ADER DATE
O O O READINESS REVIEW CHECKLIST NO. RR- 004-30S CONTINUATION SHEET- t/cc/7anico/Eegnpmen? t ITEM REFERENCE REQUIR EMEN T FINDING / COMMENT ACCEPT REJECT , RESOLUTION lo. lr73 fG llrff/O H N O C Hin C!!l0 ll0 R (b 7flyUcO') PPP FYocedu?C d. PersonocljussecsedConrci 11- 1, I?va. e.1 cer!/// cation aflime ofper-11-5; lbra. 9. l fornionce ofNic achvifj: VI- 5, Kra. 4. 2 o Roccss abec/(?A apprestrl y=c Rrfe x vII- 4, I?va. C,. I. ?. oHocess sberlhnalOA cl1cck be Dafc IX-40, Rra. 5.1. & PPPinsperfor(s)- finalencbor Wome bo//nrg Dafe . t/orne . D.7/t Xill ~ 9, Rrro. 8.3.3 o FPPinsperfor(s)- riggurj/ Warne frono'Itng pafe Wome _ Dafc Xtti-+, lh'a . 4. I OPPPinspecfor-inlcrnalc/ con- Home hoess oofe
- 3. VPP!i: In; c 0^0curcfrieof.00rutnrnfahon X-5,lhra.A l.I a. GA o'ocunicofotiori re9titrec/
b RO./.Spcc. isaval/ab/c x-5, Psm. 4.1.1. A b. lb(lC Gl'7??? re/~Wffarrns sedeb/c sna'cornp/efc~ (i(sp. p/ies/>/c) qcportiek,crurc thecouer/ serialNo. and<vo' c chss o arti4cic sh/csignsno'sho'o inspeenso is co,npfere PERFORMED BY DATE _____=__ __- ____________________-_______________________ - _____ _ _____________ ______-______- _ _ _____ _
O O O READINESS REVIEW CHECKLIST NO. RR- 004-3o9 IAUDIT NO~ PAGE 3 OF 3 CONTINUATION SHEET I ITEM REFERENCE REQUIR EMENT FINDING / COMMENT ACQEPT R,EJEC T , RESOLUTION
- 4. GPC Bacedu,c El13L DoetinnnhNon '
Cr1-T-02 [ha. U!lM
- s. t. + Q.referencca dirrcr7lnientcncoct l4c fo/es fr)frevi-sim/si,bmi%/ sfvenc6rc/oc-Ofr/cr7f3 CITT-oZ /f7ts. l]. Ifdin/enre frjxrf# nspecfron i 527 Jigno/arr3cyetvill>117 V/>c FCfju/TCYllH71e //7fCfVG/ ,
Cil-T-OZ lbn. C. Samp/c O!cne }!7sDCclOrd /nsj>cc/cr
' 2.5 Z. 5)gOn?p'!Cfit1llla/s f6 QSsorc pg/c CCr!ilIrd7/Or1 cllime ef/7?a/n-Cil-T-02 fir?a. lctrancC repor d.Deviofiori inJ)X'clJonls Wen /i-I 52.9 httlonll1eOOCUfrienfaffor7 Ore l'ff' IICCCNit c pref >rrlf(Visposi//orrecf c'en?-
X V-Z Ibia.&.0 p/c/cct,'emo!c/osedas mp4-ceble: BA A'O. PR No DR No. . . _ l OR tlo. . . . - _ . -_- Ylk1/fibM'0CC $$}.Cf L%13 fcf>f0CC JJ be 0/73ffGCbef?llaif7 CT10!?cC 0'O'r'f)?cccid WNr?! GD-T-og Wu fe/r!cc/on 06-09-86, bairmy l .s/iGbe usrc/p CM-T-0Z, Exhib }Oz,p. I PERFORMED BY DATE
O O O READINESS REVIEW.. CHECKLIST '. NO. RR- 004-3 /0 PREPARED BY p, g DATE AUDIT NO. PAGE i OF 3 SAMPLE IDENTIFIC ATION AUDIT DATE AREA Accegt pfg y ofQua/>fy Docomenlafion - 6,1/if AUDITORS ITEM REFERENCE REQUIREMENT FINDING / COMMENT ACQEPT REJEC T , RESO LUTION
- 1. Ifefene/ Idenfihcafiori vescnpfion
/ den /ificalisa Number Size of Namber Heaf Number Tag Number (fo00hCfuref" Rirchoue Orobr Alumber
- z. err /rocco'am tfa/enal dextipfiononre7aisi-wt-2 Para. &./. 2 l/en /s ma mement WWlr //1for-mafron in /g/em /above-
- 3. !faler/a/ K'ctralsIllon PPPProcedirre Piping maler/a/ regoulllon V//-2 Para. 6./. 7b SYock malerial requ/st/fon
/sapprovedbyQua41 7Assurance Msme vafe Cerfi(icahon checked _
Alame oo/e~ Cerfibcolon claded Wome Oste CerfiNeabon checked PERFORMED BY DATE R.R. TEAM LE ADER DATE l
O O O READINESS REVIEW GHECKLIST NO. RR- 004-3 /o
"^* " "
CONTINUATION SHEET- t/0/crials l^""~ lTEM REFERENCE REQUIREMENT FINDING / COMMENT ACQEPT R,EJEC T , RESOLUTION
- 4. Balk /hferla/Ath/c/Fi//er PZi crial licabic App No / Applicab/c n'Fl'rocrclec ReVicw Cerfilledffaterial Test x-s/h s. 4. 2A 2cpor/s (cmRc) for:
sice/ proper-oCbemice/cndp'y?vvdAmater-
//esin cyccaren ialsprohcattori o CY7 spy Vno/ch d'r$ sopphed if re7airco!
oSlai'cmen/ofcomplience 25 NcA-3scofan/cria/ spec. o z?et/a feriik(s/ani/csss/cc/ on/y)secepfab/c
- s. P)oe SpooA3 FPPReccc/wc licable ---
X-5 R1ra. Afp/Applictr6/c Ao - 4././A oNPP-/ code difa reporiovoi/-
- 4. /. 2 A s/>/c foropools x-2l Affach. 2 oNPP-/ referencrsa//mo/erto/
reparedfor /de syso/ X-ziAfach./ oleritficaleofshop mspechon cornple/c 4 PERFORMED BY DATE
O O O READINESS REVIEW CHECKLIST NO. RR- OM- 3/O
. PAG E 3 F 3 CONTINUATION SHEET- No/crio/s lAU IT N i
ITEM REFERENCE REQUIR EMEN T FINDING / COMMENT ACQEPT R,EJEC T , RESOLUTION
- 6. L47Ives/Purnus PPPfrocr<Ic?c hcable X-5 Faro. App No /Appliarb/c
- 4. /. I A 0NPV'-I code data repoefis
- 4. /. 2 A amiloWe oNPV-/ rekteorec /becorrecf senalnornberandcsde chs3 o NPV-l:/7ows (atiip/c>lcd:
Ccr/>knfE' of Cmp /woce Cetfilind olDe.g - {'cr/>&csI c sf6517sp 5r,pecit ~ri
- 7. r?rno<m/mc 27ewatioa reporis io'en-l X-5 Para. 7. 0 fi/ict/sn Sh
- !co ?r/c prsfer/
XV-z lbra. G.o dupos>lis ,00' comp'/eteo,' / i nridclosco': 09 No.
- on x0 OFC NO. . - - - - - - . .
I i i i PERFORMED BY DATE
O O O READINESS REVIEW CHECKLIST ..
. NO. RR- CO d- 3 //
PREPARED BY /, DATE AUDIT NO. PAGE <
~
OF 4 SAMPLE IDE NTIFIC ATION AUDIT DATE AREA
/hCCrPih7bi!' 'O h0Cill 00 cit /77('!)b7,Iid r! -
Field (1r/dihowss S/recis AUDITORS ITEM REFERENCE REQUIREMENT FINDING / COMMENT ACQEPT REJEC T , RESOLUTION
- f. Ficid J1;'-Ic! /o'c ifificafron Ficlo' lYeld No.
ISO Orotrmg No. - kev --
- 2. PPPnocedurc ISO Drawing revision is currect VI-5 fitra. (o.2. I forlInieofinsfa/faf or1 i 3 PFPnacedarc Linespec. civa'cso(_ classsbarn '
Vl-5lh?a.Z.I ott ISQ$30 n:'i~3 a rrellrrlCOI 4.l , on / Reprocess sheef
- 4. PPP noccclurc WP3hs/cc!ca /bcprocesschcet XVil-4 App.8, E isctwcc/for/urespeciNcc7liori SI-40 aridcoo'r class 5 Ajp// cab /c WPS dirif !y:c, nroibusf size,inserf per Pf'P Poce- nicIcnalffernia/ceinf prebCai d<nc31-40 nndirike NDE n&tdas passspmliedl>yh'P3 fanpersfarcs, ond arere&cldon /beprocesschecf G. !TFnerec4ac QA/Oc!7ersen,c/waccer/INcd'for XVII-4 I?im.6.1.2. perfornwocc oflbe fal/orvingac-Arp.5,3[ fivilles: .
oP)vcess shre!QA approval _. Narne -.-- .._-
.2dcsyned PERFORMED BY DATE R.R.TE AM LE ADER DATE L_._ _ _
O O O ' READINESS REVIEW GHECKLIST NO. RR- 004- 3 / /
" ^ ' ' "
- CONTINUATION SHEET-sc/,/IS/dnoccacc>3cc/s l^" " '
ITEM REFERENCE REQUIR EMEN T FINDING / COMMENT ACCEPT R, EJECT , RESOLUTION
- 7. ITPMocedurc QA/QCpersonrielcer/iNcelon (& vifinued)
XVil-4 R1ra.G.I.2 oProcess slicef hua!(?A circrk t!ame--. . App. e, X Zh!c signcd . o PPPtris/>cctors ^'sme - . Mc sigana' . . - . - . - -- ---. llGmc Pote signeo' -
- 8. PPP Proccclurc We/dcrs cytali4ca',$ pc? bar treH XVil-4 Appe,E o f?!;ce n th 3 : Naarc ' Symbo/
11 - 8 Fara. /. 0, Scricsigriecf______. __ .
- 4. 0, 5. 0, Name Symbo/
l0. 0 Zlate sigricd i
- 9. PPPRaccdurc We/arccl?n7~r.ndm3[orIye/t/
VIIl- 3 D ra. 6.2.5 nunibercerehinedin construc-tion documentafion package oNarnbc of regossifior13 IO. FrP Deccdurc Ec<!7 wr/of rodicqubiborragmes Vill-3 Rita.8.2.I Iyr/hiprocrsssbecfhe f'ic Vo//ory-j7g llcnis: N o. 0 Z S o nic ln c c'in w hi7 O lk'e/d A'O.
> tsicWer ID .
c Filke mcli/!yoc andaize e /fca/No. Si2c pe Mcn/No. 5/ze
>c //cal No. Oize --.
ve. // cal ^^. Size . I PERFORMED BY DATE
O O O READINESS REV!EW CHECKLIST NO. RR- 004-3/ / J I PAGE d OF 4 CONTINUATION SHEET-nc/dlWCor = J>%ms [ AUDIT NO' ITEM REFERENCE REQUIREMENT FINDING / COMMENT ACQEPT REJECT , RESOLUTION
/ /. r/'F M Or~lurc NDE r"pc'/3 regtiircr/byp'ro- >
ceas s/ier/ nic af.bchro Xvil- 4 lhn7. 6.0 l2. PPPl'rorco'irc 5,ch tw~ rcporfaftra wiNr XVII-4 Ajy). B, Y pvw3z,cv ,~'?:
!V-l,y Wo.
o /SO/7/eftw Drawiirg No,
/3. PPPFroccchirc tioE A ccvfoncc Accep'cd Repclec/*
XVil-4Arr.5,v o Leve/E ur/~p e/crfnnnirnwn) was 90aliNcris//he />mc Wome llt?e olinheprefahon_
%llNDE /J rqrrlrcf fcVirnt f4c weldrcynir pierrss usinga new cbrcklisf t
- 14. PffFroccchnc Froceduc revistoris /hteo'on /Ac Wil-4 lhm.6.7.2 processsherfore correrf for/bc f/me ofins1r//alion,8nspectsort I5. PPPProecobre efe/c,js/aesenpfiori f
ano'piccc/ XVit 4A;7,.6,1Y nior/cnumbers on fleprocess shectogice wilb ninierIn/fcyni- , f sific'rs ano'isonic/rfc orawings Spoo/ ^!o. -_ Jfock/!al71o-Vs!<c Wo. O//icr6/ex4r; PERFORMED BY DATE l
- - - - - - - - - - - - - _ ___ _ m_ _ _ _ _ - .m w
O O O -READINESS REVIEW CHECKLIST NO. RR- 00 d-3 // CONTINUATION SHEET-r/c/dnht/ProcessJ4cc/s l^" ' ' ITEM REFERENCE REQUIR E MENT FINDING / COMMENT ACQEPT R,EJEC T , RESOLUTION
/S. PPPftoccc/mc XVil 4 App.8,N l'fa!ct!aldescn,finord)trli011 numbers (Cou anclplecc/
33o0/ 7 Wo. . _ _ . - aloek Maf /ID Vn/vc Wo. _._ Oll1cr(d'estribc)
/6. FPP50crn'urc Devia/ Tori recp>oef iderr/ibcd XV//-4 App.8, VH on //ie rren?o's &s-XV- 2 lhu. 6.0 JJari/jonec{ c'onij2 ano' c/ssec/ DRMo. .-
DR No. OR No. PERFORMED BY DATE
l O O O READINESS REVIEW. CHECKLIST .
'. NO. RR- 001-3 / 2 PREPARED BY DATE AUDIT NO. PAGE / OF E SAMPLE IDE NTIFIC ATION AUDIT DATE AREA Accepfabilify'ccorasofQuaMy Leak Tes/ R Docuinculofiori- ,u ,,7ogg ITEM REFERENCE REQUIREMENT FINDING / COMMENT ACCEPT REJEC T , RESOLUTION
- f. Ps/ )0'rOllf/COilof7 iso!nc'.fric Drc1w!!7cr A/O. Key.
Tes/ Pacto _ - _ _ _ .. Sfar10).1 Mo.qc No. Systern NO. Pesl'an Pressure 23/ Dole -- -- 2- PPP&occdarc PSl pac l'ac7cO'cfinc3 boor 7-XI-/Firra.5.3 dcir/c3 of/hc 'cGi'
- 3. PPPFrocedarc Tesf rc, regoireo'by X/-f llrra . /O.0 CO n'as GC/1ieVecI
- 4. PPPfrecedure kSl171eo$ urn tierso!/bcy lpe/
X/-/ Rrin. 8. O c/00l/lfJ}7FCUYrdbff10CCWu!C 5 PPPDecedorc le'sfgotyrs: X/-l Fora. 7.0
- Corieri reirqc oCaIdsrs/cc/bekrcs,7daf/cr
~
lesf tie' TE Ho.- {}dda/&
/*ld TE No.- Orl.o'alc 4
e e
O . O O READINESS REVIEW GHECKLIST NO. RR-(Jo4- 3 / Z CONTINUATION SHEET-Leak Tes/ & cords l ^" " " ~ l ITEM REFERENCE REQUIREMENT FINDING / COMMENT ACQEPT R, EJECT , RESOLUTION
- 6. PPPProccclure Tesf activdie.s svi/nessed/
X/-/ thra.12.0 revicwed by: ' oQA/OC oBPC o A NI 7 PPP Proccc! arc DeviaCon repor/sIclenbhco! XV-Z Para. 6.o on //re records areproperly dispos frorrect, comple/cc/ond . c/osect DR No. , De No. D R No. _ l l l l l . PERFORMED BY DATE
O O O READINESS REVIEW CHECKLIST.. NO. RR- 00 + - 319 PREPARED BY DATE AUDIT NO. PAGE- I OF 5 R .c . sometrat> c/iek7 SAMPLE IDENTIFICATION lust /\tti ".13 P t Pi At(ci(AFV[ AUDIT DATE AREA I SO M/ T P_fC No: Rct! - AUDITCRS ITEM REFERENCE REQUIR E MEN T FINDING / COMMENT ACQEPT REJEC T . RESOLUTION FIFLb u mlY_ in'ani r)C T& TAIL.Cb P!PIML1 - AFW PuMPP 005G More: IT m su c, c_, r? Tcb TnAT THf A.Cl ST D 'r' " r i L i ? f~ A TTALHMIEO F, e n O P__ bl- I. n A c, /, - .. 3; cf pn" t,JALKDC dh} PORseses. PERFORMED BY DATE R.R. TEAM LE ADER DATE
O O O READINESS REVIEW CHECKLIST NO. RR Ni -S l4 CONTINUATION SHEET l^""' "^*' ITEM REFERENCE REQUIR EMEN T FINDING / COMMENT _ ACCEPT REJECT , RESOLUTION i FP M t30 EEOPb IMTEPJ AL 11MD SitOL t/l A P KlLIGx 5'. (G 2.5 9- )O 0-. tiU?fML SPECtFCCATfJ' I i (. s.t. 'O Akb GRADE
- h. M A1. E fe.lA I. t 15/ .T NOMEEt/CObG L. $PCnL. Mo. IF APPLIC.4BLE
'I d. FIELD W ELD Mo.
F P- M- 17.D b C. WELnepis) MO. FDPt ( 3. Io) EAcn F'iFLB VJELD C, FP- M-\to .Etsi$P6cf IMsTALLleb (315) P i PIM(7 - DccuMGMT l b 'E) /ACCE PTF\EILIT'/ OF : (S,z.O G IStGTAlt.r b DIMCMS-Ichts , b.6LOPC c.,$t.rrtr uLn\"NffF
.I O\LVE C R.tG k\ThTlCR G- i Y AL VC FLOC btPCCTIOH y 0 vruc s t ic/rt:"<.s.
LL hn PERFORMED BY DATE [
- l l
O O O ; READINESS REVIEW CHECKLIST NO. RR- N A - 3 \ d CONTINUATION SHEET l^""~ " * ' l ITEM REFERENCE REQUIREMENT FINDING / COMMENT ACCEPT REJECT , RESOLUTION 2 (Co M T' b.) g. P:Pc sitc/sc;gc3tgg
- h. I'IPC VNf6fMhL '
L , WGLCra MS&T ,\flSOAL 0,0 ALIT '/ P,CQ15-e tCEtb frnvd,
, iO El. b GLEE
, srsc tFIGb W6LbS M Ab6, FPLC OF hPL STPJm 4 S PATTCP. s
<0%CC O P l>A M Al iC. .
Y (, DC/17G, QCtryCS, GR.) [3.2.3) h, PIE To e,cudWT SGPAPATity y As teGM MAIMTAINEb IN. C-oMPAts As-tsottT ' IEco kb /4AtusT Y AssC%t4Qtr tcs)CG 1 PERFORMED BY 'DATE
O O O 9 READINESS REVIEW CHECKLIST . NO. RR- Co +- 5/r PREPARED BY DATE AUDIT NO. PAGE - / OF 3 it. sotataean:td s/is'/e7 SAMPLE IDE NTIFIC ATION AC.C_ epi ~ ABt LIT / OT' 31/d 11 '/ T' > 4' 7 ' ~~ N '." 0 ' AUDIT DAT E AREA
't rill'?I/.!. if3'JU ' ~fIi *'
./
AUDITORS ITEM REFERENCE REQUIR EMEN T FINDING / COMMENT ACQEPT REJECT , RESOLUTION NOTE: To SE.USEb f:OR G 7UIPMl5MT fN57ALLE b W 6e FC. WITHILL I G c.o Pri OF 6 D c_ W-5 PRtwiW 4. I fGUIPMEN.T lb6VDTY FLAMT T ALi h.lo. AStAG CODC ste_P_lAL Mo : FEDIECT C LtGS: M AMUFAf_To(Esta_ : PUPasASE obbEE./I' TEM Ab' ? S'PG&I f:IC A:T* Iou l\1o. VENEDR_ Coc.oMELir kici si ,,
-s ii ,,
2 F P- t4- 150 . INSTALL AT. tCu ht r otGIE (3,2) N. CmMT v o c-rw Mu(c.P) REVI2w1EL Fon F P-M- 101 I , HOLb Pot An5 $1 web ( S./ - 5,@ . A.PPi2.0 PP I A rt . EMTRIES AMb 5% HAT 0ktb t vihCLIT
. LOC 3 No,OM CP AND CP l.cq surE7 ccCWT PERFORMED BY DATE R.R.TE AM LE ADER DATE
O O O READINESS REVIEW CHECKLIST NO. RR- oO 4-315 PAGE A OF 4 CONTINUATION SHEET lAU IT N - ITEM REFERENCE REQUIR EMENT FINDING / COMMENT ACCEPT REJECT , RESOLUTION FP- u- 101 - FOP.Mt.3 /-4b comrttT (2, t 3) D[ C p l6 Rg5[.'etJ5ff: .
- 71) l' Z !s
- l V r t ?. 6 N T S ,*
*
- Zd 5 T'CLTICH C ITTfH,
,, DO( OH\rt n f;[7e r.1 17 (f'Qt) t (- ( r t'/?>!S
>TCC1ttC'.)
,, IEEPER6Alf5D
.bOLVMG'MT OGLIISibh5 ptto rCit FD M-F 6 R it b W H M W 0 tl K p c t f c V ! 't C D
[24.b) . DR.Cs) PRCPAttch AMb R6CDPASD Okt cP F OP- tO!CourCRiftt% CDMbiT10Li$ ,19 Nt'/ 1 l (5.2//s,'1) . QCJ_ Aub ANI M 5 IC,MGb G PC s) FOR. Awls WOPJ. TO IMb\c. ATE FIWid PsVIUto!MLEl' TAM'* L 3, \o ) C,oWWLE7Eb CP AMb REQ 0\tED IXCOMGiTATitM PERFORMED BY DATE
O O O READINESS REVIEW GHECKLIST NO. RR- 004 -515 l"" " " ' CONTINUATION SHEET l*' r ITEM REFERENCE IPEQUIR EMENT FINDING / COMMENT ACCEPT REJECT , RESOLUTION FEDFEtty $TDREb ,
=
IN, ANb CGTRICVAEL' FgoM QA UNLT i l PERFORMED BY DATE i
O O O READINESS REVIEW.. CHECKLIST '. NO. RR- 004-3 /6 PREPARED BY DAT AUDIT NO. PAGE / OF 3 SAMPLE IDENTIFICATION AUDIT DATE AREA Accepfobi/il y ofQualify Documenlofion - jfgf(, jg/3 AUDITORS ITEM REFERENCE REQUIREMENT FINDING / COMMENT REJEC T , RESO LUTION ACQEPT
- f. /4G/01/0/ .[Grribfirchar7 I
Ocacr/pfiori - fo'enl/ fica /jon Number _ _ ~ . . Size y _ ____. _ _ _ . . dC7/0/ Norri/>er. -. . Heaf Number 75q Warnber - lbr70hClurer
}Etrc/ieJe Crocr Alumber . . _ . _ . . _ _ _ _
2,. FrFFie<edirc Pfolct10/ G'rscripl}on or7 reculsI- + Vil-2 Psea. 4./. 2 lJerr /.s /nO reernenf wi/lr'//1for-mobon in /g!cm labove.
- 3. /folcrla/ Ecouisit'iotr PPP Procc&ric Mping ina/rrla/ requUi/iam V//-2 Fara. 6./. 7b uisll ion Slock mnfr?ialreq/ Assurance isopprorea'byOsa/i/
Weme oste - Cer/ibcobo, cliccked Wome oo/c~ Cerfilicabon chcrled , Wome Dstc \ (i7lllcabon C!?rcNCo' PERFORMED BY DATE R.R. TEAM LE ADER DATE
O O O READINESS REVIEW CHECKLIST NO. RR- 00 4 -5/ 6 CONTINUATION SHEET l#"" ' " " ' # " 1 TEM REFERENCE REQUIREMENT FINDING / COMMENT ACQEPT R,EJEC T . RE SOLUTION 4- SP-Al-IO6 80LK MATE 27AL - LGELb f/LLGR METAL.- l3'& s. TR@EARILITf /MPO FP-N-Io9,3 6M PMIK /s l'cMPrere
&Mb COR/C.ECT~
S#'O 3'0 .b. t/serfY T'HkT' A kMPI INSPECTION AMb 4%~ ri x OMGMY' %st/Gol d3 % tu.:. C PGefeR t4eb FP- Al-IAO C RM M MY cs.s.s') P!LGb ^ % "B R!*"'BIE J. newew cwes aoeWsT-z.075 ep WGLPlu S E./A L A N D ~3 0 M f/PIM6 *4ATEBb/AL F8E cc4FEPJ4AMCG TO U~ CHAGG GR.DSR K64OfR' HGMTS Lisr ITEMS Ryv/GW Eb AMD RG6OL76. g' ASMG P1PIFV;$P6 W W LG (pp-At zOls.43-Ic4a.. eta R P2ePERLY ceMP-L.GTGD AND APP)GDU8b sy MbM
- s. YK.ALSAbluTY INFO Chi PMz is ceMPt S7C AMD CORK.GCT'
, v'srify THAT'DE.E t/AS KGCGIV9D CterGS cf PERFORMED BY DATE l
O O O
' READINESS REVIEW CHECKLIST NO. RR- 90 4-3/6 CONTINUATION SHEET l^" " " '
ITEM REFERENCE REQUIR E MEN T FINDING / COMMENT ACQEPT R,EJEC T < RE SOLUTION PMR - ASSOCIkTGb KEC&lVING RER%t5 Auc veA6xt 64 4Dcu M GstTA1"iDLL
- b. SSRJAL MOMBEK/
CD 9 c(_ Ass DM ccMibusuT' sAMG As eM NPP-t/MPV-1 IqESRGND TO IYG6As L rt+Ru d Aseve M 6 SPGOLS AMb/eg sfM b FF-N-lllo %Wrr10M MMg , (.5. 2 ) 3.4 RsvlGt0 3 .b Rs -To 35 DGTERMIM6 5,6 6 , PR.cyse. /ALIDATTCM ls. 8) g, w LysPoslYlDAI \ r'rY 6- 3 c. ReW52. CLosattE l ,, , el . AML CCMC0kRAME i r,< w -- (, 4. 0) PERFORMED BY DATE {
O O O READINESS REVIEW.. CHECKLIST NO. RR 00V- 3/7 PREPARED BY DATE AUDIT NO. PAGE / 4 OF R. C . SOMMERFELD E-l9-21 SAleLE IDE NTIFIC ATION AUDIT DATE AREA ACCEPTABL,/TY 0F QUALITY lWL)MPhlTATIOM WELbud6 RE[Dhb $HeeTS - AFW (6IC.5C0FE) ""**'*** 7 ITEM REFERENCE REQUIREMENT FINDING / COMMENT ACQEPT REJECT , RESOLUTION . I PIGLD ul2Lb IDENTIFICA l~lDN FIELD tdELb Alo: ISO DGs Mo:. . . REV. 7.- FS N-l20. I L. 9.EIIIEul FDEXd FOR ( z.co z) C.LARITY AHb hrOLACI (wRs/sA.) oF THe fatoefuc, g m An Izo i-A MR- 5 WR-SA A77.17A l-8 ' 3
+ 7 6 9 8
11 10 to ly 2.5
- REce.D WGLD M84 YlEUX=C sYMtsCLt , M,. TL v) ELD 1D/srccL M ATEE lAL TYIVo.kE AND HEAT cobE. F6L F070rE (dEFEREtXE rcGCDPb Scr< at wRd5A PERFORMED BY DATE lR.R.TE AM LE ADER lDATE ,
O O O . RE ADINESS REVIEW CHECKLIST NO. RR- 00 4 -Sl7 CONTINUATION SHEET l ^" " " ' l ""*' # ITEM REFERENCE IPEQUIREMENT FINDING / COMMENT , RESOLUTION ACCEPT 47'ECT A FP-N-l20.l L. REVIGul FOR vilMESS j (2,g,l} 66 hCLD Ib/N75. IP A NY HAl/E BEEM
> SYPASS&b VEttFY TMT A be v)As PfL}% Reb AND bfSFD$/r/DNP.lt
- b. VECIFY AMZ ancotR-ENCG /F IMD FDIMTS WERE $PECiFIEh C . l/ g 2 / F y Q(J _5/GNM REVIGua QCL QUhL.
STATUS AIJD FELDR.D.
- d. COCG DEslGMArt0H A@ ,
i C. Lass GNT225 ARG RESRDu!SIFG Tb 130/Is0 HOTES. e, WPS SPECIFIED IS G26'LC.T FOR LIAlG M$lirNkr/DAL, C6DE ' GLA65 AND WM-2/ WM-3 t
~
O O O READINESS REVIEW GHECKLIST NO. RR- 00+ s'/ 7 CONTINUATION SHEET !*""' !" ETEM REFERENCE REQUIREMENT FINDING / COMMENT ACCEPT REJECT RESOLUTION f AlhE PKOCEJDURES AEG
. O) REsibHShE TO XyGDI '
F0K PHE CU)$5 FP-M-l75 ()} fyofgt p)eccg1)0kE AMb Revi6/oM 6PECICIED Pbli'. Alb2 3 P /20 vj sLDdE. &OALIF-
- 2. 0 RE t/IGuj SO ALIG.
n r--ol CALL) SNS O# 6 # MGLDE&. LisTGb ik.1
. ITEM 2, 8 ; A B o t/ G .
4 FF- Al-/bS,7. QUAllTV COMTROL IN5R kE(11F u) Q V M i'/ICATif41 STATOS of GCZs VJHosE SIGNATVtF/ INITIAL - APPEAP Or4 VRg6As As 32F_fD0.b En i Al . ITEM 7_.og A80PS. FP-M-[75 klDE. Fibres 6MAIR [ALL) REviEu) &VALIF/c4TIOM
- STATUS OF IJD6 GXA(HGF's A5 tDEMT1FICD t%1 MbE RE.P0bT6 PERFORMED BY DATE l _ _ . _ . _ _ . _ _- -- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - ~ ~
O O O READINESS REVIEW CHECKLtST NO. RR- 00 4 -317 CONTINUATION SHEET !""~ ~ lT E M REFERENCE REQUIREMENT , FINDtMe/ COMMENT ACCEPT REJECT < RESOLUTION 5 FP-bl-120,1 WGLDII% FlLLGR METAL ( 3 IO a . EscGE.b TYPE $ HEAT' Mo's oF fillet IAETAL h5 CELDb Eb MI WE-5/5 A.
- b. (DM1PAEG LA))TH W R - Co AND Raofb KESULTS L . LISINCs LIST ~ Pt&v) 3.% A 8 ot/G , REVItu)
DeCou\GUTATIbkI FER. C HGCXLIST RE~ DO 4-3l(o
- 6. FP.M-lLO. I Mbe
[3. 9) o.. MeIPY kid 6 of WB45 ACLEPTAMCE 8Y REVIEvJ OF NW EEPDr2TE
- 6. ret //EoJ NM /26675 FM d6NFCPAAIKE To AIDE Planx12E.
PERFORMED BY DATE __________m_ - ---
O O O READINESS REVIEW CHECKLIST ..
. NO. RR- 00 4 -cil 'l PREPARED BY DATE,.r r1, .. AUDIT NO. /
?.C. <;Omf4f(Yrt-b PAG E OF U
/ i U.\ i SAMPLE IDENTIFICATION AUDIT DAT E AREA EQUIPtAEMT' TAG hio .
Du)6 ISO tJo. Et/. AUDITORS hSmG. CnhE_ ctASS __ ITEM REFERENCE REQUIR E MENT FINDING / COMMENT ACQEPT REJECT \ RESOLUTION
,ylALi'btna u or l u STttLLP: b M66N/W/(/(( g,Gtj / p g/f", (('
I ~ VISOlu_LY Ex ANiud E Eau s wtG MT' FOR E\llDENCC DG DirtnMn
- 2. -
verQF1 EvitsrzucE. 05:
- EGolputGArr tr.romcu- '
- Aract , su cM AS:
- MorrL6_ Co tE/2.% !
- INSTA.LLAT1 Oil <T; REPLACCiMpkir OF DEMIC AAITE.
- 14 EATER.s FNE%tiEf l - IMCFT 6As a fMET l RofATIohl ANb LOPE '
l tttctvrtutt o r: r b ': II. l F G O)P M('hTT l t PERFORMED BY DATE R.R.TE AM LE ADER DATE
O O o . ' READINESS REVIEW CHECKLIST NO. RR- 004 -319 . CONTINUATION SHEET l^""' " " ' " ITEt$ REFERENCE IPEQUIR EMENT FINDING / COMMENT ACGEPT REJEC T , RESOLUTION
, 3 FP- bl- ISO Assg% iNWAtt E D EiQLilpMc NT AthAIM5'T WE. 1:OLLOW LNC, P94WIW C15 / P12oc.EDdEES 3@ (2 l) yggpoe Desw suc3 -
ouch As Auckoe soLT cPA.ciu ci , s i2 E Awo PROJECT t ot J . f g &gs Aechov2 Got -T 3(% (3 VJ pgoggety 7sc,uzeseo Aug equipswT 4 Ltc,y (E D ? A,R 6 I M U U DEVICES IMSTALLED [ 3Cc) (3. l. R) LAvou7 D R6.w iN G (rousoemou oeswiwcD-sock As oeie9^Tio"> st.evATioW , soEf LE t ock.T@9 , 6-T C . PERFORMED BY lDATE { .
i. O O O , READINESS REVIEW CHECKLIST NO. RR- 006 - 3/9
' CONTINUATION SHEET l"""' **' " '#
ITEM REFERENCE REQUIREMENT FINDING / COMMENT ACCEPT ftEJECT RESOLUTION P4?I.p - ouch A.s
~
- . 36) eau spMew TA c, rJa, i
c,rre sos. t- doTre_.s , pi2A.ses 4 V s u T s. coconcTiota , postuu S sts. , 3(c) - Iso ogA.vv i ta C, - sucHAsnotV.16 eese ol s iota ,3 =ce Av o e teva. t to tJ l l 4 dm-T-05 Ausss sToeAc,E AND l SM-T o'l M A.IN TE N A N CE_ a r Equ t PMENT 4N u WAG /l## speko/iwsrAu.e.c> pgogeitt. p u o p = = i o n ic-tu sD EcT i ctd WA. S ' DONE. WIThlN 9p gcifico PgizioD. A PERFORMED BY DATE g m
O O O READINESS REVIEW CHECKLIST ..
'. NO. RR- 004- 3 2c]
PREPARED BY gg DAT AUDIT NO. I PAGE / OF- 2 SAMPLE IDE NTIFlC ATlON - Con 57ruC//On Accep/arice 7es/s AUDIT DATE AREA Sn[clf andEcllc[ Vo/Ve AUDITORS TOq Noa. ITEM REFERENCE REQUIREMENT FINDINGi COMMENT ACQEPT REJEC T ; RESOLUTION 1 VEGP Alec/cavi- Allejij>htn6/c e!7/ ries ori/be O.emfions car-11-05.Dela Shre? were ccdure No. proper /y (inco'-in ondsigned-CA r- M- 05 off. Was A.N.LL no/ificd pasrfo fesfing ?
- 2. CA T-71-05 h/cmeploIe dala' recorobden
- 6. I. / 17sfa sheet includes set pressurc bresomeasspeci-Neo'orise/pom/deswirig.
- 3. CA T-tl- Os A visuallispceiion of/Ac
&. /. 2 Volve revenha l
//ia/noyrrN Were n1/ssing s<id 8e/cadsen/s were sh//in/sch
- 4. CAT-11-05 Was i/necessmy to conclicla
- 6. l. 3 va/ve /csf cis er S/cp G.E .?
(Hso, co, // ems sIhruI0) 5 CA T-t1-of EquVxncnf for /csbnq lbe vak/c
&.2.2 mu of & pro decoroa'nce wid;>cr rsnge (iiii/bcapplicablc andeahArsfier was tri/A-code)daedateshownon in/Le thedala sheet PERFORMED BY DATE R.R.TE AM LE ADER DATE
O O O READINESS REVIEW GHECKLIST 10. RR- 00+ 3 2 0
"~ "^*'* " "
CONTINUATION SHEET-cA7-So/Ayd.04cflG/ves l^"" ITEM REFERENCE REQUIREMENT FINDING / COMMENT ACCEPT REJECT < RESOLUTION
- 4. CAT- N- 05 when fec/cdwiHi hquio fof?o%
G 2. 5 ccilledpressore, wkcpeaf is zero (o). When lesf-cdw agas af To:tpressure, 20 ML/cspermmute is anac-cep4We /cahigc. ; 7 CA T-tl- 05 Li# pressure e/nerrec/wd/rin G. z. 7 16/emnce on /wo ceriscentive openings svas w//binAccep-fence Os/cretprovio'db,ysef-e po/rr/c/rawing.
- 8. CA T-t1- 05 Affer 1Ac li0pressore festwas G.3.I comp /efeo,' /bc /esfyre.sswc sws rcchiccd16 90% andNe seaf /arlage /csfwasrepmf- '
ecles in //cm 6.
/ O. CA T= tl- 05 A /mdscal was irisi,//cdevi G.4. 3 llc va4c to indicofei//7ad been fcc/cd General 7579aing Rocen?nc w/rere opt > fica!>lc, 25240-C, was usedw ben insfaN?ry /bc vake.
1 PERFORMED BY DATE
' __ ._ u
O O O READINESS REVIEW.. CHECKLIST '. NO. RR-004-32 l PREPARED BY DATE AUDIT NO. PAG E / OF ,/ AUDIT DATE AREA
- SAMPLE, IDENTIFICsATION Auet/m' FecdivalcrS -Sy/g/cgf f/us/////g Icar -shh S /m/
I Alo. 2 A L 0I AUDITORS ITEM REFERENCE REQUIREMENT FINDING / COMMENT ACCEPT REJEC T , RESO LUTION (Rocehe wMno/ /c ego n>'uoM7+s7) Assessineaf wn/ />c made uo. br Modu /c 3A PERFORMED BY DATE R.R.TE AM LE ADER DATE
O O O READINESS REVIEW CHECKLIST..
'. NO. RR- 004 -322 DATE AUDIT NO. PAGE / OF /
PREPARED BY ['. D /fna/rc"i: , SAMPLE AUDIT DATE IDENTIFICATION-Sy/g/enf //ffs////fc7 AREA 203/Ou0l .i!CWf Rem 0VGlSyGkW-Sib OfY!en NO ESC 00 AUDITORS ITEM REFERENCE REQUIR E MEN T FINDING / COMMENT ACCEPT REJEC T ; RESOLUTION (Rotra'v?e wil ins!begjprov. Wnnb/ 7-/- 87) Assessmeof wig be mde una r ModulesA PERFORMED BY DATE R. R.T.E AM LE A DER DATE
O O O READINESS REVIEW.. CHECKLIST . NO. RR-oM-323 PREPARL D BY DATE AUDIT NO. PAGE / OF /
,Y. .D bildfCWS f
SAMPLE IDENTIFlC ATION-SysIrn/ /~'uS/7//77 Gin)>G/7cn/ (S0.5??f lI/b/cr Syskwr-Su/nys/cm blo. 2 EGQl guoggoas ITEM REFERENCE REQUIR E MENT FINDING / COMMENT ACQEPT REJECT , RESO LUTION ([1occd?w Iyi//nolbe ipprov a Ionli/ 7-/-ST) Assessinent will be mode v ,& - NooVc 2A 9 4
O O O . READINESS REVIEW.. CHECKLIST NO. RR- 004- Sa5 : PREPARED BY DATE AUDIT NO. PAG E - 1 OF 3 R.c som mE rtr-etb b/7- /87 SAMPLE IDEN TIFICATION AUDIT DATE AREA R.T F1LM A.ssf=%S MEIdT AuDirORs - ITEM REFERENCE REQUIR E MENT FINDING / COMMENT ACQEPT R,EJEC T , RESOLUTION
- 1. RRF //-57 A. RGvten) PsT ritas Asvg Cone AMb RT RGTDR75 rcrq TFEtitPSTAT10M AT LGMX q v)GLb5 U+ IE - D IIE- Ho - Of.,) To vrn.iT:'/
e Ti&T ALL ^ LIM CAE INblCATitM"a PPP ttacWE, i I X-KT M Tl FILMG MF-AJc TEb A N D cl5 P-- o s: TID MF b col FT REltMT G. ' 14OTG : \F N1D LlotfAt 1NblCAT014 5 M'.S FOUhlb ntJ s ELec7Eb Fit.M a , C.c NTIM OE f lLM RGUIC \C3 i ! ~ O MTI L. AT~ L E A 'o T ~ 3 60C R (14bK I.T it W3 i t@f 5 V I t OdT~ RECC,t.b bOCs Llo Asr - hI GLT.h Mo's F'D UI G C = h PERFORMED BY DATE R.R.TE AM LE ADER DATE
O O O READINESS REVIEW CHECKLIST NO. RR- DO L/ - 31T - CONTINUATION SHEET l^" " " ' l"' ITEM REFERENCE REQUIREMENT FINDING / COMMENT ACCEPT REJECT RESOLUTION z,o iTr" tiltriety- %, Cmagmts gekyrk sgsq.T ; ly- RT-1-v)~11 It4CI' l'i ATICkt iO M Ii l NbG. P P.oc Cbut c % INSOIM 'T i l C i l l tfc @ l Wt PlWINtI\EMI S /\RC l H G T*.
- . P R o t c b o t*~ Aln/
IS S O G. D (qE (3,()) o YGMMNhGTGP site TYPE Lc,(#9'\Did M W)DMtRg (APP, G) oDRM91% Mo. t WGLb M O M P. Eft A4FIC v)tT/l PPMCZ
$M t*~C T e LEVEL lI/ICL NTGAWJE_TEPm R0httretc./W(oms IF COPE N O M R @ bG.E SHEET otTCt PERFORMED BY I DATE ,
0 0 0 READINESS REVIEW GHECKLIST NO. RR- 00 4- 3 2I - CONTINUATION SHEET l^""' l*
'IT E M REFERENCE REQUIR EMENT FINDING / COMMENT ACCEPT REKCT RESOLUTION 2- c o aTi14e b. Rat)tctO ow prcf .t.s (f,1O
, PILM lo t/PPell y -
m n o F As. 1 0 R c t,0 GXNICArlul D ATE HAs McT ECCri G/4GEtPb i I i l i I i l l l PERFORMED BY DATE
. - _ . . . _ _ _ _ _ _ _ _ _ _ _ _ _ , -.}}