ML20078A566
| ML20078A566 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 12/17/1987 |
| From: | GEORGIA POWER CO. |
| To: | |
| Shared Package | |
| ML20078A351 | List:
|
| References | |
| PROC-871217, NUDOCS 9406020222 | |
| Download: ML20078A566 (250) | |
Text
{{#Wiki_filter:- - - - A A - i O VOGTLE ELECTRIC GENERATING PLANT UNIT 2 READINESS REVIEW PROGRAM l MODULE 6 - ELECTRICAL EQUIPMENT ; 1 1 I i
)
1 0163f/287-7 9406020222 940512 PDR ADOCK 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, in depth self-assessment of work processes and verification of compliance with regulatory commitments. To accomplish the VEGP pilot Readiness Review Program, the work processes and regulatory commitments were divided into manageable segments called modules. There are 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
<- management in support of the VEGP Unit 1 operating license.
(_)g Conclusions reached regarding programmatic and technical adequacy through review of VEGP Unit 1 are indicative of Unit 2, since both units are being designed and constructed together under a single quality assurance program; with like management controls, procedures, 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. . 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 l or to diminish any authorities or regulatory responsibilities 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 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 so that they may initiate any needed corrective actions in an , orderly and timely manner. ' [,)1 0126f/337-7 iii
i l l l 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 lll the design, construction, and preoperational processes of nuclear power plants. It is the collective opinion of the Readiness Review Task Force, Readiness Review Board, and GPC management that. based on their experience, the methodology used in the module process will assess, on a programmatic basis, the adequacy of project commitment implementation. Readiness Review 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 i l 9 l 0126f/337-7 iv
EXECUTIVE
SUMMARY
This module documents a review process conducted to ascertain whether the design and construction aspects of Class 1E electrical equipment in Unit 2 of the Vogtle Electric Generating ' Plant (VEGP) comply with licensing commitments and whether compliance is verifiable using existing project documentation. Class 1E electrical equipment includes items such as transformers, switchgear, motor control centers, distribution panels, batteries, and electrical penetration assemblies. 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 sere 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 I.- Violation of licensing commitments, project procedures, or engineering requirements with indication of safety concern. 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 evaluation of electrical equipment 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 Program 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 0155f/337-7 y
E provided Readiness Review with updated implementation information which is presented in Section 3. h Unit 1 Finding Followup During the assessment of Unit 1, the project committed to the performance of certain corrective actions. For Unit 2, Readiness Review provided Project Engineering and Construction with a list of Unit 1 findings and corresponding corrective actions. These groups 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 electrical equipment 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, the 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 and installed lh equipment to verify acceptance to specified criteria and conformance to installation and procedural requirements. Seven pieces of equipment, four electrical penetrations, and approximately 200 documents were examined. Nine findings were issued during the assessment. One was classified as Level I, two as Level II, and six as Level III. The Level I finding, 2RRF-006-011, identified a difference between the wiring-fire separation criteria stated in the FSAR and those listed in the construction specification X3AR01. Preliminary evaluation of this condition on Deficiency Evaluation Report 186 resulted in notification to the NRC of a potentially reportable condition (CDR-M140). Final resolution is scheduled for March 1, 1987. 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. O 0155f/337-7 vi
Readiness Review
Conclusion:
O Based on the results of the review, and the implementation of effective corrective actions as committed to by the Project, Readiness Review concludes that adequate programs exist to ensure: the quality of design and construction; objective evidence that quality has been documented; and the licensing commitments within the scope of this module have been implemented. l O l 0155f/337-7 vit
f- MODULE 6 ELECTRICAL EQUIPMENT TABLE OF CONTENTS Section 1 Introduction 1.1 Scope 1.2 Module Organization 1.3 Project Status Section 2 Organization 2.1 Introduction 2.2 Design 2.3 Construction 2.4 Organizational Changes Section 3 Commitments 3.1 Introduction 3.2 Commitment and Implementation Matrices Section 4 Program Description t'] 4.1 Design V 4.2 Construction 4.3 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 Findings
Section 7 Assessment of Module Adequacy Project Quality Assurance Readiness Review Board Section 8 Assessment Plan and Checklists 0125f/337-7 ix
1 INTRODUCTION ['] %) 1.1 SCOPE This module is one in a series of modules that provides an evaluati.n 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 prior commitments. If any differences exist between the commitments discussed 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 safety-related (Class 1E) electrical equipment. This equipment is listed in the plant equipment index under the 16XX and 18XX series and consists primarily of large, floor mounted assemblies, and wall mounted regulating transformers. The following categories of equipment are included: o Switchgear. o Motor control centers. r^\ (/ o Distribution panels. o Control room panels. o Batteries. o Chargers. o Inverters. o Penetrations. j Motors are discussed in Modules 4, 16, 18A, and 20 and . instruments are discussed in Modules 18A and 20. 1 The checks, reviews, inspections, audits, and verifications performed to ensure the adequacy of design and. construction
. functions are examined. The organizations responsible for performing design and construction activities are identified.and ;
the. work activities that the organizations perform are I described. Also, the project commitments for electrical 1 equipment are identified, the method of implementation is 1 listed, and the results of a review for compliance to the committed requirements are presented. l 1 0127f/337-7 1-1 ! l 1
This module addresses those project commitments identified g through Amendment 33 of the FSAR. The effective date of this W , module is July 1, 1987, and changes to the included programs, organizations, commitments, etc., occurring after this date are i not necessarily addressed. i l i O O 0127f/337-7 1-2
/~T 1.2 MODULE ORGANIZATION O This module is divided into the following sections:
- 1. Introduction.
- 2. Organization - A brief description of the project organizations and their division of responsibilities as applicable to this module.
- 3. Commitments - Project licensing commitments pertaining to safety-related electrical equipment as found in the Final Safety Analysis Report, responses to generic letters, and responses to Inspection and Enforcement Bulletins. This section also lists the documents that demonstrate implementation of these commitments.
- 4. Program Description - A brief description of the processes for design and construction applicable to the scope of this module.
- 5. Audits and Inspections - Listings of Quality Assurance (QA) audits and findings and Nuclear Regulatory Commission (NRC) inspections and violations applicable to the scope of the module and conducted since the Unit 1 module. A description of special investigations
[\ is provided. The Readiness Review findings and NRC violations from the Unit 1 module activity are listed, the corrective actions are presented, and their applicability to Unit 2 is indicated.
- 6. Program Assessment - A description of the assessment plan development, plan implementation, and results, including corrective actions.
- 7. Assessment of Module Adequacy - The evaluations and conclusions by the Project, QA, and the Readinest Review Board of the module.
- 8. Assessment Plan - The assessment plan and checklists l utilized by the Readiness Review Team.
l l l f i 0127f/337-7 1-3
1.3 PROJECT STATUS
}
As of the July 1, 1987, the design of safety-related electrical equipment was essentially complete and Construction had mounted most of the equipment. Unit 2 work in progress includes termination of cables internal to the equipment and replacement of Unit 2 components transferred to Unit 1 during startup. O 0127f/337-7 1-5
2 ORGANIZATION O
2.1 INTRODUCTION
p Georgia Power Company (GPC), acting on its own behalf and as agent for the Oglethorpe Power Corporation, the Municipal Electric Authority of Georgia, and the City of Dalton is responsible for the design, procurement, construction, and operat'an of the Vogtle Electric Generating Plant (VEGP). GPC adminit,ters the overall quality assurance program, provides procurement services, controls materials issue, performs quality control inspections, and provides construction services for calibration, tests, inspections, document control, and nonconformance control. Bechtel Western Power Company (BWPC) is contracted by GPC to provide architect / engineering (A/E) services for plant equipment / systems contained within the Seismic Category I structures and is responsible for the overall design coordination of all plant equipment / systems. Southern Company Services (SCS) provides A/E services for plant equipment systems contained within the Seismic Category II structures (including the switchyard) and provides supplier quality assurance reviews. Cleveland Consolidated is the installer for all Class 1E electrical equipment and is responsible for installation and field fabrication activity, j Figure 2-1 shows the overall Project organizational structure. The following sections contain brief descriptions of the individual GPC, BWPC, SCS, and Cleveland Consolidation groups that perform activities concerning safety-related electrical equipment. O 0130f/336-7 2-1
i 2.2 DESIGN ] A brief description of the Project Engineering and the GPC organizations that perform design activities related to or ! interfacing with safety-related (Class 1E) equipment is presented in this section. 2.2.1 PROJECT ENGINEERING Project Engineering is responsible for design of Class 1E equipment with the exception of protective relaying as discussed in 2.2.2. This responsibility is divided between two Project organizations; Design Engineering (DE), and Installation Engineering (IE). These organizations are comprised of personnel from Bechtel Western Power Company (BWPC) and Southern Company Services, with BWPC having overall design responsibility. The overall project engineering organizational structure is shown on Figure 2-2. 4 2.2.1.1 Design Engineering DE is located at the'jobsite with support staff in Norwalk, I California. The design of Class 1E equipment is primarily performed by the electrical discipline with specialty support provided by the Environmental Qualification Group. The electrical design group is divided into five groups under the direction of the electrical engineering group supervisor (EGS). These groups are Site Design Engineering, Systems Design, Controls Wiring, Physical Design, and Circuits and r Raceway. Their functions are listed in Figure 2-3. ; Responsibility for the design of electrical equipment rests primarily with the Systems Design Group, with assistance provided by the Physical Design and the Controls Wiring Groups. 2.2.1.2 Installation Engineer $ng IE is located at the jobsite and is primarily responsible for resolution of field problems identified by the Project Construction organization. IE is responsible for updating the construction specification for installation of electrical equipment. They also serve as the primary contact for the Construction Discipline for resolution of field interferences and problems, and coordinate with DE the solution to field identified problems. IE reports to the Georgia Power Company (GPC) Electrical Discipline for project direction and to the electrical project engineer and the EGS, site design engineering, for technical direction. The IE organizational structure is shown on Figure 2-3. 0130f/336-7 2-3
2.2.2 GEORGIA POWER COMPANY The System Prote; tion and Control Department of GPC is responsible for the development and implementation of the protection policy for the GPC transmission system, generating plants, and distribution substations. Protection Engineering, which reports to System Protection and Control, is responsible for carrying out this policy and is specifically responsible for *aa selection and setting of Vogtle Electric Generating Plant protective relays, including Class 1E protective relays. The organizational structure of the GPC System Protection and Control Department is shown on Figure 2-4. O l til 0130f/336-7 2-4 l
l l l 2.3 CONSTRUCTION ; Project Construction is responsible for installation, maintenance, and inspection of Class lE equipment. This responsibility is divided between the Electrical Discipline, Civil Discipline, and Quality Control organizations. These organizations are comprised of personnel from Georgia Power Company (GPC), and contractors reporting to GPC. A brief description of these groups is given below. The overall project construction organization is shown on Figure 2-5. 2.3.1 ELECTRICAL DISCIPLINE The Electrical Discipline organization shown on Figure 2-6, is divided into four groups under the direction of the electrical discipline manager. These groups are: Electrical Installation, Installation Engineering (IE), Systems Completion, and Cleveland Consolidated. Cleveland Consolidated is the electrical ' contractor perforaing the actual hardware installation and is responsible for providing craft and supervisory personnel. The Electrical Installation Group performs construction support activities such as approving material requisitions, providing craft with vendor and design document information,-providing maintenance information to the Construction Maintenance Organization (CMO), and initiating and/or revising field procedures. They are also responsible for meeting established O- schedules and resolution of quality problems. IE, as described in section 2.2.1.2, performs design activities to support resolution of field identified interferences. The Systems Completion Group is primarily responsible for
- ensuring that the equipment is ready for turnover to the Startup organization and for completion of items subsequent to turnover, 2.3.2 QUALITY CONTROL Quality Control, whose organization is shown on Figure 2-7, is responsible for inspection L.id acceptance of the electrical equipment. The Electrical Inspection Group is the primary inspection group. The inspectors are qualified and certified as discussed in Appendix F. Table 2-1 gives a summary of the certification requirements for electrical equipment inspection.
The Civil / Mechanical Inspection Group performs inspections for housekeeping and maintenance of electrical equipment in > conjunction with the CMO group. O . 0130f/336-7 2-5
2.3.3 GEORGIA POWER COMPANY CIVIL DISCIPLINE The CMO is part of the Civil Discipline and is responsible for cleanliness, protection, and periodic maintenance of all permanent plant equipment during the construction phase. Y O m 9 0130f/336-7 2-6 1 I
q 2.4 ORGANIZATIONAL CHANGES b In January 1987, the design organization, then comprised of Home Office Engineering (HOE) and Project Field Engineering (PFE) was restructured to better support the construction effort. The major elements of this restructuring were: o Transfer of personnel from Norwalk (HOE) to the site. , This onsite core group, along with the few remaining > personnel in Norwalk, became Design Engineering (DE). o Relocation of PFE personnel from one central onsite location to individual groups located in proximity to each construction discipline. These groups became Installation Engineering (IE). o Designation of a single engineering group supervisor for each design discipline with overall responsibility for DE and IE work. l o Design activities in direct support of construction work ' were assigned to the IE groups. o Design activities of a general or oversight nature were assigned to the DE group. o Control of the Project Reference Manual, the Design ( Manual, and responsibility for providing technical > direction to the IE groups were assigned to DE. , b 0130f/336-7 2-7
TABLE 2-1 O DETAILS OF ELECTRICAL EQUIPMENT INSPECTOR CERTIFICATION The following work activities may be inspected using this certification: o Electrical equipment installation. o Rigging and lifting of equipment. o Penetrations. o Electrical instrumentation. The following courses are required for certification: o Basic Math I. o Basic Blueprint. o Installation of Electrical Equipment ")which I includes: { ( - Drawings. i
- Codes / standards / specifications / procedures.
- Grounding.
- Penetration Assemblies. ,
- Equipment. ,
- Rigging and lifting.
I
- a. Certification in visual inspection or an American Welding '
Society certification is required when weld inspections are performed. f 1 Ol33d/337-7 l
O O O LEGEND PROJECT DIRECTION
---ADMINISTRATIVE DIRECTION GENERAL PROJECT MANAGEli DIRECTOR NUCLEAR OPERATIONS I
GENERAL I MANAGER I QUALITY l ASSURANCE l ASSISTANT l PROJECT I MANAGER I PROJECT l QUALITY _ _ , , _ _ , _ _ _ , i MANAGER l i i 1 1 I l
~
I GENERAL UNIT 2 PROJECT PROJECT I AD MANAGER PROJECT ENGINEERING LICENSING I N U MANAGER PROJECT STARTUP MANAGER MANAGER SUPPORT MANAGER Figure 2-1 Project Organization
O O O LEGEND PROJECT DIRECTION PROJECT
--- ADMINISTRATIVE DIRECTION ENGINEERING
""" FUNCTIONAL. TECHNICAL MANAGER AND ADMINISTRATIVE DIRECTION BECHTEL PROJECT ENGINEERING MANAGER
~~~~~~~~~~~~~~~~~~~~]
3 1 1 PROJECT PROJECT PROJECT QUALW ENGINEER ENGINEER ASSURANCE FIELD HOME OFFICE ENGINEER 1 GPC COST AND CONSTRUCTION SCHEDULE DISCIPLINES MANAGER PROJECT PROJECT PROJECT PROJECT PROJECT ENGINEER ENGINEER ENGINEER ENGINEER ENGINEER MECHANICAL ELECTRICAL CIVIL MECHANICAL ELECTRICAL AND L INSTALLATION INSTALLATION INSTALLATION DESIGN civil DESIGN Figure 2-2 Project Engineering
O O 0 (DESIGN ENGINEERING) PROJECT ENGINEER ELECTRICAL AND CIVIL DESIGN ELECTRICAL ENGINEEhlNG GROUP SUPERVISOR (TO PAGE 2) 4 ---- --- TECHNICAL DIRECTION CONTROLS PHYSICAL CIRCulTS AND SITE DESIGN SYSTEMS DESIGN WIRING - DESIGN RACEWAY ENGINEERING (EE 580)
- SYSTEM CAI.CS
- CONTROL SYSTEM
- RACEWAY DESIGN
- CIRCUlT INPUT
- SYSTEM DESIGN DESIGN
- CIRCUlT ROUTING
- DESIGN CRITERIA
- ELEC PANELS
- RACEWAY INPUT
- ONE-LINES
- CONT / WIRING CALCS
- EQUIPMENT SPECS
- ELEMENTARY DIAGRAMS ,
- WIRING DIAGRAMS Figure 2-3 Project Electrical Engineering (Sheet 1 of 2)
_ _ _ _ - __ _ m ___ _ _ _ _ _ . _ _ . _ _ _ _ _ _ _ _ - . .= .- - , -
O O O (INSTALLATION ENGINEERING) PROJECT ENGINEER ELECTRICAL INSTALLATION PROCEDURES / TECHNICAL COMPLIANCE DIRECTION r-------(TO PAGE 1) l U ELECTRICAL CONSTRUCTION CONTRACTOR PRE-ENGINEERING DESIGN SUPPORT ENGINEERING
- LIGHTING
- TRAY SUPPORT BRACING = CONDUlT PACKAGING
- COMMUNICATIONS
- ANALYSIS OF OTHER
- CABLE PULL PACKAGING
- FIRE DETECTION COMMODITIES ON
- TERMINATIONS PACKAGING
- GROUNDING TRAY SUPPORTS
- HEAT TRACING = DISPOSIT10NING FCRs.
- CONSTRUCTION SPECIFICATIONS DRs, ATCWs
- CONSTRUCTION SUPPORT
- GREENLINING
- EE 580 SUPPORT I
Figure 2-3 Project Electrical Engineering (Sheet 2 of 2)
O O O 5 LEGEND PROJECT DIRECTION
---ADMINISTRATIVE DIRECTION SYSTEM PROTECTION
& CONTROL
- DEPARTMENT PROTECTION ENGINEERING SECTION I
I I I i TR ANSMISSION & l GENERATING DISTRIBUTION I PLANT PROTECTION PROTECTION l 1 I r---------T----'"----- 5 -----~~---"'~~~~~~~-~7 I s I I I i a 1 i I POWER BECHTEL - SOUTHERN CO. PLANT PLANT GENERATION CORP. SERVICES HATCH VOGTLE SERVICES Figure 2-4 GPC System Protection and Control Department
. , , w w.m-. w - .m.s,= _w ...w e.w+ g- - ,,-- m. -. ,,--w -we. - - - , - --- -e-v ,,.m . - , , . .- -.,m..* . ,
O O O i 1 VICE PRESIDENT l CONSTRUCTION , l MAP ; MANAGER REGULATORY LABOR i O, OF COMPLIANCE RELATIONS QUALITY CONTROL CONSTRUCTION
- INSPECTION I
SYSTEM CIVIL ELECTRICAL MECHANICAL COMPLETION DISCIPLINE DISCIPLINE DISCIPLINE MANAGER MANAGER MANAGER MANAGER
- CMO
- INSTALLATION Figure 2-5 Construction Organization I
l
O O O ELECTRICAL DISCIPLINE : MANAGER PROJECT SECTION SUPERVISOR ELECTRICAL l ELECTRICAL ELECTRICAL AD INSTALLATION INSTALLATION ONSOUDATED COMPLETION PROJECT MANAGER MANAGER ENGINEER MANAGER SEE FIGURE 2-3
- EQUIPMENT
- SYSTEM COMPLETION SUPPORT
- AREA MANAGERS
- RACEWAYS
- AREA COMPLETION SUPPORT
- SUPERINTENDENTS
- CABLE AND TERMINATIONS
- CRAFT TRAINING Figure 2-6 Electrical Discipline a- _a_ _ ._-_ _ _ _ - - -r .e- y: w , --_,m, y w ,_
O O O . MANAGER OF QUALITY CONTROL- [ b CIVIL / - TECHNICAL ' DOCUMENT CONTRACTOR MECHANICAL SUPPORT GROUP REVIEW QA/QC QC SECTION SECTION SUPERVISOR PROGRAMS SUPERVISOR SUPERVISOR
- DOCUMENT STORAGE
- TOOL CAllBRATION
- PROCEDURE REVIEW
- DOCUMENT REVIEW
- RECEIPT INSPECTION
- CMO INSPECTION ELECTRICAL ELECTRICAL ELECTRICAL INSPECTION INSPECTION INSPECTION SUPERVISOR SUPERVISOR SUPERVISOR
- RACEWAY
- CABLE PULLING
- EQUIPMENT
- SUPPORTS
- TERMINATIONS
- QC RECORDS Pigure 2-7 GPC Quality Control
._. _ _ _ - - _ - - _ _ _ - - - - _ _ _ _ _ _ _ _ _ - _ _ - _ - _ - - - _ - _ - _ _ = _ _ . . .
1 3 COMMITMENTS 0- , 31 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 described 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 for inclusion on the matrix using the following guidelines: o Specific design and or construction requirement. o Specific standards of acceptance. o Specific cited technical data used as a design basis 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: o Dimensions, o System operational concepts or operational descriptions. o Design calculation details such as strength parameters, flow rates, etc. o References to general standards such as 10 CFR 50, American Society of Mechanical Engineers, American Concrete Institute, etc. (specific requirements from such bodies, however, are commitments). O Ol34f/337-7 3-1 ! l l l
Implementation An implementing document is a working level document 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. o Drawings Additionally, the Project has a commitment to comply with 10 CFR 50, Appendix B, Quality Assurance Criteria, and industrial standards such as American National Standards Institute (ANSI) ANSI /ASME N45.2 and N45.2.11. Although they were not identified as specific commitments in this module, Readiness Review considered the applicable requirements of these types of commitments in preparing and assessing the scope of work presented by this module. Differences, if any, between the commitments discussed in this section and the FSAR are unintent;.'.onal and the commitments in the FSAR take precedence. O Ol34f/337-7 3-2
3.2 COMMITMENT AND IMPLEMENTATION MATRICES C During the Unit 1 Readiness Review Program, the task force performed a systematic review of licensing documents and 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 Report (ESAR) 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 appropriate Project organizations for updating the implementation matrix data to reflect the latest implementing documents. Upon completion, the updated matrix was returned to Readiness Review, who verified the accuracy, on a selective 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. O \/ The commitment and implementation matrices are presented following this section and are current through Amendment 33 of the FSAR. 1 e t 0134f/337-7 3-3
\w f PLANT VOGTLE UNIT 2 HEADINESS REVIEW PROGRAM COMMITMENT MATHIK
==============================u=======
NEF. COMMITMENT COMMITMENT COMMITMENT DOCUMENT / MOD DES CON FSAR REMAHKS NUMBER SOURCE SECTION SUBJECT FEATURE ULE IGN ST AMEN ======= ========== ==================== ==================== ==================== === === === _=== ===:==.== :e==: ===s ExpLAhATION OF FIELDS REF. NO. - A reference mueber that correspeeds to the appropriate flee entry le the leptementettee matrix COMMITMENT SOURCE - The docuseet costeleleg the commitment IFSAR. Generic Letter, l.E. Bullette Response, etc.) COMMITMENT SECTION - Identifles the FSAR secties, letter number, or questlos mueber COMMITMENT SUBJECT - The subject of the FSAR section or Generic Letter DOCUMENT / FEATURE . - The document discussed la the FSAR settles or the plant feature described la the FSAR section MODULE - The module for uhtch the comalteemt is Implemented DESIGN / CONSTRUCTION - Aa X is pieced under the headlag for the orgeolsettee responsible for leptementatlos of the commitment FSAR AMENDMENT - FSAR eseedmont number for revised commitments le aero t0) is pieced la this celues for changes made prior to Amendment 13 Intert of Uelt i Reedleess Revleell NOTE: Commitment changes from these presented le the Welt I module are Identified by a vertical row of X's in the left mergia.
Page No. I 11/23/87 PLANT V0GTLE UNIT 2 READINESS REVIEW PROGRAM COMMITMENT MATRIX CURRENT THRU FSAR AMENDMENT 33 i
================================-=====
REF. COMMITMENT COMMITHENT COMMITMENT DOCUMENT / MOD DES CON FSAR REMARKS NUMBER SOURCE SECTION SUBJECT FEATURE ULE IGN ST AMEN
======= ========== ==================== ==================== ==================== === === === ==== ====================
i 108.00 FSAR 1. 2. 12. I SINGLE FAILURE, IEEE 279-1971 06 I O t REDUNDANCY & INDEPENDENCE CRITERIA 1491.00 FSAR 1. 2. 12. 1. 2.L SINGLE FAILURE, IEEE 279-1971 06 X 0 ! REDUNDANCY AND , INDEPENDENCE CRITERIA 1503.00 FSAR 1. 3. 2-1 BATTERT SIZING BATTERY SIZED TO 06 X 0 SEE SECTION 8.3 PROVIDE DC POWER FOR 2-3/4 HOUR 955 DEGREES F 1601.00 FSAR 1. 9. 6. 2 INDEPENDENCE BETWEEN RG 1.6, REY. O, 3/71 06 X 0 SEE FSAR SECTIONS REDUNDANT STAND-BY 8.3.1.1.2.D. 8.1 AND l (ON-SITE) POWER 8.3 SOURCES AND TREIR DISTRIBUTION SYSTEM ? 1602.00 FSAR 1. 9. 22 PERIODIC TESTING OF RG 1.22 REY. 0 06 I O SEE FSAR 7.1.2.5 PROTECTION SYSTEM (FEB. 72) EXCEPT AS ACTUATION FUNCTIONS INDICATED IN FSAR SECTION 1.9.22.2 AND 7.1.2.5 126.00 FSAR 1. 9. 29 SEISMIC DESIGN RG 1.29 REV. 3, 06 X 0 REF. TABLE 3.2.2-1 CLASSIFICATION 9/78 686.00 FSAR 1. 9. 30 0.A. REQUI'REMENTS RG 1.30, 8/72 06 X X 0 FOR INSTA Q., INSP., '
& TESTING OF INSTRUMENTATION &
ELECTRIC EQUIPMENT 687.00 FSAR 1. 9. 30 0.A. REQUIREMENTS ANSI M45.2.4-1972 06 I X 0 FOR INSTALL., INSP.,
& TESTING OF INSTRUMENTATION &
ELECTRIC EQUIPMENT
=
_ _ _ _ _ . - - _ __.__. __ _-___.___m ___.__2 m__ -___.___e_. .- _ _ _ _ _ _ _ - e- ______a - , e+- ---+' eve =+-wur_ee r -e- + s an - w w i w* g e
Page No. 2 11/23/87 PLANT V0GTLE UNIT 2 READINESS REVIEW PROGRAM COMMITMENT MATRIX CURRENT THRU FSAR AMENDMENT 33
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REF. COMMITMENT COMMITMENT COMMITMENT DOCUMENT / MOD DES CON FSAR REMARKS NUMBER SOURCE SECTION SUBJECT FEATURE
= ===== =======e==
ULE IGN St AMEN
==================== ==================== ==================== === === === ==== ================:-==
688.00 FSAR 1. 9. 30 Q.A. REQUIREMENTS IEEE 336-1971 06 X X 0 FOR INSTALL., INSP.,
& TESTING OF INSTRUMENTATION &
ELECTRIC EQUIPMENT 131.00 FSAR 1. 9. 32 CRITERIA FOR RG 1.32 REV. 2 06 X 0 SEE REG. GUIDE 1.6, SAFETY-RELATED 2/77 1.9 1.75, 1.81 AND ELECTRIC POWER 1.93. SEE FSAR 8.1 SYSTEMS FOR NUCLEAR AND 8.3 POWER PLANTS 132.00 FSAR I. 9. 32 CRITERIA FOR IEEE 308-1974 06 X 0 SAFETT-RELATED ELECTRIC POWER SYSTEMS FOR NUCLEAR POWER PLANTS 133.00 FSAR 1. 9. 32. I CRITERIA FOR 10CFR50 APP. A. GDC 06 X 0 SAFETY-RELATED 17 ELECTRIC POWER SYSTEMS FOR NUCLEAR POWER PLANTS 134.00 FSAR 1. 9. 32. 1 CRITERIA FOR 10CFR50, APP. A. CDC 06 X 0 SAFETY-RELATED 18 ELECTRIC POWER SYSTEMS FOR NUCLEAR POWER PLANTS 1551.00 FSAR 1. 9. 53, 2 APPLICATIOy.0F RG 1.53, REY. O, 06 X 0 REF. 7.1.2.6 & SINGLE FAILURE 6/73 15.0.8 CRITERION ' 2188.00 FSAR 1. 9. 61 DAMPING VALUES FOR RG 1.61, 10/73 06 X 0 SEISMIC DESIGN 157.00 FSAR 1. 9. 63 PENETRATION RG 1.63 REV. 2, 06 X 0 EXCEPTIONS NOTED IN ASSEMBLIES 7/78 FSAR 1.9.63 e O G
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REF. COMMITMENT COMMITMENT COMMITMENT DOCUMENT / MOD DES CON FSAR REMARKS
' NUMBER SOURCE SECTION SUBJECT FEATURE ULE IGN ST AMEN ,
======= ========== ==================== ==================== ==================== === === === ==== ====================
160.00 FSAR 1. 9. 75 PRTSICAL . RG 1.75 REY. 2, 06 X X 0 SEE SECTION 7.1.2.2 INDEFENDEMCE OF 9/78 ELECTRIC STSTEMS. , 171.00 FSAR 1. 9. 81 SHARED EMBRGENCT AND RG 1,81, REV. 1, 06 1 0 SEE FSAR 8.1 SHUTDOWN STSTEMS FOR 1/75 MULTI-UNIT NUCLEAR POWER PLANTS 172.00 FSAR 1. 9. 89 QUALIFICATION FOR RG 1.89, REV. O, 06 X 0 SEE FSAR 3.11.B. CLASS IE EQUIPMENT 11/74 173.00 FSAR 1. 9. 89. 1 QUALIFICATION FOR IEEE 323-1974 06 X 0 WCAP-8587 IMPLEMENTS CLASS IE EQUIPMENT IEEE 323-1974 FOR NSSS EQUIPMENT. SEE 3.ll.B 174.00 FSAR 1. 9. 92 COMBINING MODAL RG 1.92, REV. 1 06 X 0 SEE SECTION ; RESPONSES AND 2/76 3.7.B.2.7, 3.7.B.3.6 SPATIAL COMPONENTS & 3.7.B.3.7. IN SEISMIC RESPONSE ANALTSIS 175.00 FSAR 1. 9.100 SEISMIC RG 1.100 REV. 1, 06 X 0 SEE FSAR 3.10.B.2 OUALIFICATION OF 8/77
. CLASS IE ELECTRIC EQUIPMENT 177.00 FSAR 1. 9.106 THERMAL OVERLOAD RU l.lP6, REV. 1, 06 0 SECTION C.2 NOT PROTECTION FOR 3/77 APPLICABLE.
ELECTRIC MOTORS ON MOTOR OPERATED VALVES. 1610.00 FSAR 1. 9.106 THERMAL OVERLOAD RG 1.106/IEEE 06 X 0 PARA. #8.3.1.1.2, ' PROTECTION FOR 279-1971 SECTION ITEM K5 ELECTRIC MOTORS ON 4.1, 4.2, 4.3.'4.4, MOTOR OPERATED 4.5, 4.10 AND 4.13 YALVE. -- w-.- +-< e , . . , aw. - 4 . - < . er%4 - .- r, w r i.- 'e-.. . - - - - - - -. .*e--- ==-*.
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REF. COMMITMENT COMMITMENT COMMITMENT DOCUMENT / MOD DES CON FSAR REMARKS NUMBER SOURCE SECTION SUBJECT FEATURE ULE IGN ST AMEN
======= ========== ==================== ==================== ==================== === === === ==== ======-= ===========
182.00 FSAR 1. 9.128 INSTALLAT$0N DESIGN RG 1.128 REY. 1, 06 X 0 SEE FSAR 8.1 AND 8.3 AND INSTALLATION or 10/78 LARGE LEAD STORAGE BATTERIES l 4114.00 FSAR 3. 1. 1 CONFORMANCE WITH 10CFR50, APP. A, GDC 06 X 0 NUCLEAR REGULATORT 2 COMMISSION GENERAL DESIGN CRITERIA, CVERALL REQUIREMENTS. 4115.00 FSAR 3. 1. I CONFORMANCE WITH 10CFR50, APP. A. GDC 06 X 0 NUCLEAR REGULATORT 4 CONMISSION GENERAL DESIGN CRITERIA, OVERALL REQUIREMENTS. 4116.00 FSAR 3. 1. I CONFORMANCE WITR 10CFR50, APP. A. GDC 06 X 0 NUCLEAR REGULATORT 5 COMMISSION GENERAL DESIGN CRITERIA, OVERALL REQUIREMENTS 4118.00 FSAR 3. 1. 2 PROTECTION BT 10CFR50, APP. A, GDC 06 X 0 MULTIPLE FISSION 17 PRODUCT BARRIERS 4119.00 FSAR 3. 1. 2 PROTECTION BT 10CFR50, APP. A. GDC 06 X 0 , MULTIPLE FISSION 18 PRODUCT BARRIERS 4132.00 FSAR 3. 1. 5 REACTOR CONTAINMENT 10CFR50, APP. A. GDC 06 X 0 l 50 835.00 FSAR 3. 2. 2-1 CLASSIFICATION OF RG. 1.29-NOTE (e) 06 X 0 STRUCTURES, COMPONENTS, STSTEMS l l i l i O O _ O
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REF. COMMITMENT COMMITHENT COMMITMENT DOCUMENT / MOD DES CON FSAR REMARKS NUMBER SOURCE SECTION SUBJECT FEATURE ULE IGN ST AMEN
======= ========== ==================== ==================== ==================== === === === ==== ====================
B49.00 FSAR 3. 2. 2-1 ( 0FFSITE PONER SYS. OFFSITE PONER 06 X 0 EQUIPMENT IS DESIGNED AND ARRANGED TO PROVIDE REDUNDANCY AND SEPARATION FOR INCREASED RELIABILITY 4370.00 FSAR 3. 7.8. 1-1 DAMPING VALUES FOR PERCENT OF CRITICAL 06 X 0 FIXED BASE DAMPING PER MODE STRUCTURES AND COMPONENTS 981.00 FSAR 3. 7.B. 1. 3 SEISMIC DAMPING RG 1.61 06 I O REFER TO REF. NO. VALUES FOR IT ett 4370 OTHER TRAN CABLF TRAYS AND SUPPOR' SYSTEM 1016.00 FSAR 3. 7.B. 3. 6 TCJEE COMPONENTS OF IEEE 344-1975 FOR 06 X 0 ANALYSIS MEETS RG EARTHQUAKE MOTION QUALIFICATION BY 1.92 TESTING. 1978.00 FSAR 3. 8. 2. 3 STEEL CONTAINMENT, ASME III, NE3000 06 X 0 SEE FSAR SECTIONS LOAD & LOAD 3.8.2.1 THRU COMBINATION, CLASS 3.8.2.1.5 FOR MC ITEMS DESCRIPTION OF CLASS MC ITEMS. 1984.00 FSAR 3. 6. 2. 3 STEEL CONTAINMENT, RG 1.57 06 X 0 LOAD AND LOAD COMBINATIONS 1113.00 FSAR 3. 8. 2. 4 ELECTRICAL ASME III, NE3000, 06 I O PENETRATION 1977 THROUGR SUMMER ASSEMBLIES 1979 ADDENDA.
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REF. COMMITMENT COMMITMENT COMMITMENT DOCUMENT / MOD DES CON FSAR REMARKS NUMBER SOUffCE SECTION SUBJECT , FEATURE ULE IGN ST AMEN
= ===== ========== ==================== ==================== ==================== === === === ==== ====================
1991.00 FSAR 3. 8. 2. 6 STEEL CONTAINMENT, ASME III, NH2000 06 X 0 SEE FSAR SECTION CLASS MC MATERIALS 3.8.2.1 FOR LIST OF CLASS MC COMPONENTS 1993.00 FSAR 3. 8. 2. 7 STEEL CONTAINMENT, ASME III, NE6000 06 X 0 CLASS MC ITEMS, TESTING 1117.00 FSAR 3. 8. 2. 8 STANDARD REVIEW PLAN ASME III, NE3000 06 X 0 EVALUATION 1994.00 FSAR 3. 8. 2. 8 STEEL CONTAINMENT, ASME,III, NE3000 06 I O CLASS MC ITEMS, LOAD
& LOAD COMBINATION l 1995.00 FSAR 3. 8. 2. 8 STEEL CONTAINMENT, RG 1.57 06 X 0 NOTE: SECTION CLASS MC ITEMS, LOAD 3.8.2.8 REFERS TO
& LOAD COMBINATION SECTION 1.9.57 AND l SECTION 1.9.57 j REFERS TO SECTION O F R Ah E i 1202.00 FSAR 3.10.B. I SEISMIC QUAL. AND IEEE 344-1975 06 X 0 DOCUMENTATION FOR i SAFETY RELATED l EQUIP. AND SUPPORTS.
1203.00 FSAR 3.10.B. I SEISMIC RG 1.100 06 X 0 QUALIFICATION AND DOCUMENTATION FOR SAFETY RELATED EQUIP., AND SUPPORTS 2007.00 FSAR 3.10.8. I SEISMIC SEISMIC CATEGORY I 06 I O QUALIFICATION OF SAFETY RELATED CATEGORY I MECHANICAL & l MECHANICAL & ELECTRICAL EQUIPMENT EI.ECTRICAL BOP IS QUALIFIED TO EQUIPMENT, CRITERIA WITHSTAND THE EFFECTS OF SEISMIC LOADS RESULTING FROM OBE AND SSE O O O
e
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L REF. COMMITMENT COMMITMENT COMMITMENT DOCUMENT / MOD DES CON FSAR REMARKS NUMBER SOURCE SECTION SUBJECT I FEATURE ULE IGN ST AMEN.
======= ========== ==================== ==================== === === === ==== ====================
========={h=========
i 1199.00 FSAR 3.10.B. 2. 1 MEANS OF SEISMIC- THE OBEs 06 X 0 .: QUALIFICATION SHALL CONTAIN A .! MINIMUM OF 50 CTCLES ! 0F MAXIMUM STRESS 1206.00 FSAR 3.10.B. 2. I MEANS OF SEISMIC IEEE 344-1975 06 X 0 QUALIFICATION OF MECH. & ELECT. EQUIP. 4 1207.00 FSAR 3.10.B. 2. I MEANS OF SEISMIC RG 1.100 06 X 0 QUALIFICATION OF MECH. & ELECT. EQUIP. 1210.00 FSAR 3.10.B. 2. I MEANS OF SEISMIC-ALL 06 X 0 QUALIFICATION INTERFACES AND THE EFFECTS OF THE AMPLIFICATION WITHIN THE EQUIPMENT DUE TO THE INTERFACES AND SUPPORTING STRUCTURES ARE CONSIDERED IN Tl!E SEISMIC QUALIFICATION. ! 1213.00 FSAR 3.10.B. 2. 2 MEANS OF SEISMIC RG 1.100 06 I O QUALIFICATION TESTING BT t MULTI-FREO. OR l SINGLE FREQ. INPUTS 1215.00 FSAR 3.10.B. 2. 2 METHOD OF SEISMIC IEEE 344-1975, SECT. 06 X 0 . QUAL. 5 ! ANALYSIS W/0 TESTING i I
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REF. COMMITMENT COMMITMENT COMMITHENT DOCUMENT / MOD DES CON FSAR REMARKS NUMBER SOURCE SECTION SUBJECT [ FEATURE ULE IGN ST AMEN
======= ========== =============r====== =========3========== ==================== === === === ==== ========= ===: =====
1216.00 FSAR 3.10.B. 2. 2 ANALTSIS SEISHIC-WHEN AN 06 X 0 EQUIVALENT STATIC COEFFICIENT ANALYSIS IS PERFORMED. JUSTIFICATION FOR ITS USE IS PROVIDED BY THE SUPPLIER 1220.00 FSAR 3.10.B. 2. 2. 2 METHOD OF SEISMIC IEEE 344-1975 SECT. 06 X 0 QUALIFICATION 6 TESTING 1217.00 FSAR 3.10.B. 2. 2. 3 COMBINED ANALYSIS IEEE 344-1975, 06 X 0 EQUIP. QUAL. TEST AND TEST METHOD OF SECTION 7 METHODS OF PARA. EQUIP. QUALIFICATION 3.10.B.2.2.1 & 3.10.B.2.2.2 APPLY 1219.00 FSAR 3.10.B. 2. 2. 4 METHOD OF SEISMIC IEEE 323-1974 SECT. 06 X 0 QUALIFICATION TEST 6 SEQUENCE VERIFICATION 1228.00 FSAR 3.10.B. 4. 1 Ol ,IFICATION AND RG 1.100 06 X 0 F UMENTATION Ph0CEDURES 1229.00 FSAR 3.10.B. 4. I QUALIFICATION AND IEEE 344-1975 06 X 0 DOCUMENTATION PROCEDURES 1231.00 FSAR 3.10.B. 4. 2.E STANDARD REVIEW PLAN BC-TOP-4A USED AS 06 X 0 MEETS INTENT OF RG EVALUATION - SEISMIC GUIDANCE FOR 1.92 QUALIFICATION OF BOP COMBINATION OF EQUIPMENT MULTIMODAL RESPONSE 1262.00 FSAR 3.II.B. 2 ACCEPT. CRIT. ENV. RG 1.89 06 X 0 OUAL. SAFETT RELATED EQUIPMENT O O 9
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RET. COMMITMENT COMMITMENT COMMITMENT DOCUMENT / MOD DES CON FSAR REMARKS o NUMBER SOURCE SECTION SUBJECT FEATURE ULE IGT ST AMEN d
======= ========== ==================== ==================== ==================== === === === ==== ==================== [
, 1263.00 FSAR 3.ll.B. 2 QUALIFICATION TESTS IEEE 323-1974 06 X 0 AND ANALYSES. TYPE TESTING. l 1264.00 FSAR 3.ll.B. 2 QUALIFICATION TESTS RG 1.100 06 K 0 AND ANALYSES X 1268.00 FSAR 3.11.B. 2 QUALIFICATION TESTS SUPPLIBRS OF 06 X 27 X AND ANALYSES. SAFETY-RELATED Y ACCEPT. CRIT. FOR ELECTRICAL & X ENV. QUAL / SAFETY MBCRANICAL EQUIPMENT REL. EQUIPMENT MUST MEET IEEE 323-1974 PARA 6.3.2
- , SEQUENCE REGARDLESS
. OF EQUIPMENT
*: LOCATION IN THE
{ PLANT 1269.00 FSAR 3.11.B. 2 QUALIFICAT50N TESTS NUREG-0588 06 X 0 AND ANALYSES 264.00 FSAR 5. 4. 1. 1 DESIGN BASES TMI ACTION ITEM 06 X 0 MESTINGHOUSE LETTERS II.K.3.25 00-110 (12-11-83). & 0G-117 (3-9-83) 2343.00 FSAR 5. 4. 1. 3. 8 RCP OVERSPEED RCP OVERSPEED ~ FOR 06 X 0 NCAP 8163 CONSIDERATION TURBINE TRIPS BY 4 REACTOR TRIP SYSTEM } OR TURBINE PROTECTION SYSTEM GENERATOR. AND RCP's REMAIN CONNECTED FOR 30 SECONDS 2390.00 FSAR 6. 1. 1. I SPEC. FOR PRINCIPAL -ASME III. NE-2000 06 X 0 REFERENCE TO TABLES PRESSURE - RETAINING (CONT. PENETRATING. 3.2.2-1 AND 5.2.3-1. MATERIAL MATERIALS) l
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REF. COMMITMENT COMMITMENT COMMITMENT DOCUMENT / MOD PES CON FSAR REMARKS NUMBER SOURCE SECTION SUBJECT FEATURE ULE IGN ST AMEN
======= ========== ==================== ==================== ==================== === === === ==== ====================
2399.00 FSAR 6. 2. 2. 1. 1. 1.0 CONTAINMENT C00 LINO RG 1.32 06 I O SYSTEM SAFETY DESIGN BASES
- 6. S. 2. I ELECTRIC RYDR0dBN EACR RECOMBINER IS 06 X 0 2445.00 FSAR 2.
RECOMBINER POWERED FROM A SEPARATE SAFEGUARD BUS AND IS PROVIDED WITR A SEPARATE POWER PANEL AND CONTROL PANEL. 4483.00 FSAR T. 1. 2. 1. 3.E INSTRUMENTATION AND IEEE STD. 308-1974 06 X 0 CONTROL POWER SUPPLY SECT. S.4 SYSTEM - RTS 4549.00 FSAR 7. 6. 1. 2 I & C POWER SUPPLY IEEE 308-1974 06 X 0 SYSTEM ANALYSIS 4808.00 FSAR 7. 6. 1. 2 I & C POWER SUPPLY RG 1.6 06 X 0 SYSTEM ANALY IS 4800.00 FSAR 7. 6. 1. 2 I & C POWER SUPPLY VITAL AC-NO SINGLE 06 X 0 SYSTEM - ANALYSIS FAILURE IN THE I&C POWER SUPPLY SYSTEM OR ASSOCIATED POWER SUPPLIES CAN CAUSE LOSS OF POWER TO MORE TRAN ONE OF TRE REDUNDANT LOADS. 2360.00 FSAR 8. 1-1 ACCEPTANCE 10CFR50, APP.A. GDC 06 X 0 CRITERIA / GUIDELINES 2 FOR ELECTRIC POWER SYSTEMS O O e
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REF. COMMITMENT COMMITFENT COMMITMENT DOCUMENT / MOD DES CON FSAR REMARKS NUMBER SOURCE SECTION SUBJECT FEATURE ULE IGN ST AMEN
======= ========== ==================== ==================== ==================== === === === ==== ====================
2361.00 FSAR 8. 1-1 ACCEPTANCE 10CFRSO, APP.A. GDC 06 X 0 CRITERIA / GUIDELINES 4 FOR ELECTRIC POWER SYSTEMS 2362.00 FSAR 8. 1-1 ACCEPTANCE 10CFR50, APP.A. GDC 06 X 0 CRITERIA / GUIDELINES 5 FOR BLECTRIC POWER SYSTEMS 2363.00 FSAR 8. 1-1 ACCEPTANCE 10CFR50, APP.A. GDC 06 X 0 CRITERIA / GUIDELINES IT FOR ELECTRIC POWER SYSTEMS 2364.00 FSAR 8. 1-1 ACCPETnNCE 10CFR50, APP. A. GDC 06 X 0 CRITERIA / GUIDELINES 18 FOR ELECTRIC POWER SYSTEMS 2365.00 FSAR 8. 1-1 ACCEPTANCE 10CFR50, APP. A.GDC 06 X 0 CRITERIAL/ GUIDELINES 50 FOR ELECTRIC POWER SYSTEMS 2366.00 FSAR 8. 1-1 ACCEPTANCE RG 1.6 06 X 0 CRITERIA / GUIDELINES FOR ELECTRIC POWER SYSTEMS 2368.00 FSAR 8. 1-1 ACCEPTANCE RG 1.32 06 X 0 CRITERIA / GUIDELINES FOR ELECTRIC POWER SYSTEMS 2369.00 FSAR 8. 1-1 ACCEPTANCE RG 1.47 06 X 0 CRITERIA / GUIDELINES FOR ELECTRIC POWER SYSTEMS
*I
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REF. COMMITMENT COMMITMENT COMMITMENT DOCUMENT / MOD DES CON FSAR REMARKS NUMBER SOURCE SECTION SUBJECT FEATURE ULE IGN ST AMEN
======= ========== t=================== ==================== =============== -=== === === === ==== ====================
2370.00 FSAR 8. 1-1 ACCEPTANCE RG 1.63 06 X 0 CRITERIA / GUIDELINES FOR ELECTRIC POWER SYSTEMS 2371.00 FSAR 8. 1-1 ACCEPTANCE RG 1.75 06 X 0 CRITERIA / GUIDELINES FOR ELECTRIC POWER SYSTEMS 2372.00 FSAR 8. 1-1 ACCEPTANCE RG 1.81 06 K 0 CRITERIA / GUIDELINES FOR ELECTRIC POWER SYSTEMS 2373.00 FSAR 8. 1-1 ACCEPTANCE RG 1.106 06 I O CRITERIA / GUIDELINES FOR ELECTRIC POWER SYSTEMS 2375.00 FSAR 8. 1-1 ACCEPTANCE RG 1.118 06 X 0 CRITERIA / GUIDELINES FOR ELECTRIC POWER SYSTEMS 2376.00 FSAR 8. 1-1 ACCEPTANCE RG 1.128 06 X X 0 CRITERIA / GUIDELINES FOR ELECTRIC POWER SYSTEMS 2380.00 FSAR 8. 1-1 ACCEPTANCE BTP ICSB ll(PSB) 06 X 0 CRITERIA / GUIDELINES FOR ELECTRIC POWER SYSTEMS 2382.00 FSAR 8. 1-1 ACCEPTANCE BTP ICSB 21 06 I O CRITERIA / GUIDELINES FOR ELECTRIC POWER SYSTEMS i.l O O O
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2383.00 FSAR 8. 1-1 ACCEPTANCE BTP PSB-1 06 X 0 CRITERIA / GUIDELINES FOR ELECTRIC POWER SYSTEMS 2180.00 FSAR B. 1. 4. 2.A ONSITE POWER SYSTEM 10CFR50 APP.A. GDC 06 X 0 17 4810.00 FSAR 8. 1. 4. 2.B ONSITE POWER SYSTEM 10CFR50 APP. A. GDC 06 X 0
- CAPABILITY OF EACR 17 ONSITE lE AC POWER SYSTEM TO MAINTAIN ONE UNIT SAFE CONDITIONS 94.00 FSAR 8. 1. 4. 2.E ELECT *IC POWER 10CFR50, APP. A, GDC 06 K 0 DESIbd BASES ONSITE 5 POWER 4813.00 FSAR 8. 1. 4. 2.F ONSITE POWER 10CFR50 APP.A. GDC 06 K 0 SYSTEM-SINGLE 17 FAILURE CRITERIA 2181.00 FSAR 8. 1. 4. 2.0 ONSITE POWER SYSTEM BATTERIES ARE SIZED 06 X 0 FOR 165 MINUTES OF OPERATION WITHOUT SUPPORT OF BATTERY CHARGERS 4814.00 FSAR 8. 1. 4. 2.L ONSITE POWER SYSTEM 10CFR50, APP. A, GDC 06 X 0
- PERIODIC TEST 18 CAPABILITIES OF CLASS IB EQUIPMENT.
2.00 FSAR 8. 1. 4. 3 DESIGN CRITERIA, 10CFR50, APP. A. GDC 06 X 0 REGULATORY GUIDES 4 AND IEEE STANDARDS m r_-.- -.. = - _ - . - - - - - - - _ _ . ----_-_--_- - -- - ---______----- - - - _ - . - - . - _ - ,- - w - - ---_a--..- ----_---_ . - - - - _ _ _ - - - _ - - - - _ , - - . . . - - . _
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REF. COMMITMENT COMMITMENT COMMITMENT DOCUMENT / HOD DES CON FSAR REMARKS NUMBER SOURCE SECTION SUBJECT FEATURE ULE IGN ST AMEN
======= ========== ==================== ==================== ==================== === === === ==== ============ ======e 3.00 FSAR 8. 1. 4. 3 DESIGN CRITERIA, 10CFR50, APP. A. GDC 06 X 0 REGULATORY GUIDES 5 AND IEEE STANDARDS 4.00 FSAR 8. 1. 4. 3 DESIGN CRITERIA, 10CFR50 APP. A. GDC 06 X 0 REGULATORY GUIDES 18 AND IEEE STANDARDS 5.00 FSAR B. 1. 4. 3 DESIGN CRITERIA, 10CFR50, APP. A, GDC 06 X 0 REGULATORY GUIDES 50 AND IEEE STANDARDS 6.00 FSAR 8. 1. 4. 3 DESIGN CRITERIA, RG 1.6 06 X 0 REGULATORY GUIDES AND IEEE STANDARDS 8.00 FSAR 8. 1. 4. 3 DESIGN CRITERIA, RG 1.22 06 X 0 t REGULATORY GUIDES l AND IEEE STANDARDS
! 9.00 FSAR 8. 1. 4. 3 DESIGN CRITERIA, RG 1.29 06 X 0 REGULATORY GUIDES AND IEEE STANDARDS 10.00 FSAR 8. 1. 4. 3 DESIGN CRITERIA, RG 1.30 06 X 0 REGULATORY GUIDES AND IEEE STANDARDS 11.01 FSAR 8. 1. 4. 3 DESIGN CRITERIA, RG 1.32 06 X 0 REGULATORY GUIDES AND IEEE STANDARDS t l 13.00 'SAR 8. 1. 4. 3 DESIGN CRITERIA, RG 1.41 06 X 0 REGULATORY GUIDES AND IEEE STANDARDS l l 14.00 FSAR 8. 1. 4. 3 DESIGN CRITERIA, RG 1.47 06 X 0 REGULATORT GUIDES AND IEEE ETANDARDS
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=======
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15.00 FSAR 8. 1. 4. 3 DESIGN CRITERIA. RG 1.53 06 K 0 i REGULATORY GUIDES ' AND IEEE STANDARDS 17.00 FSAR 8. 1. 4. 3 DESIGN CRITERIA. RG 1.63 06 X 0 REGULATORY GUIDES AND IEEE STANDARDS 4 18.00 FSAR 8. 1. 4. 3 DESIGN CRITERIA. RG 1.75 REV. 2 06 X X 0 SEE TABLE 8.1-1 RRGULATORY GUIDES 9/78 AND IEEE STANDARDS i 19.00 FSAR 8. 1. 4. 3 DESIGN CRITERIA. RG 1.81 06 X 0 REGULATORY GUIDES AND IEEE STANDARDS i 20.00 FSAR 8. 1. 4. 3 DESIGN CRITERIA. RG 1.89, 11/74 06 K 0 REGULATORY GUIDES i AND IEEE STANDARDS 21.00 FSAR 8. 1. 4. 3 DESIGN CRITERIA. RG 1.93 06 K 0 REGULATORY GUIDES , AND IEEE STANDARDS 22.00 FSAR 8. 1. 4. 3- DESIGN CRITERIA. RG 1.100 REV. 1 06 I O REGULATORY GUIDES 8/77 i AND IEEE STANDARDS . 23.00 FSAR 8. 1. 4. 3 DESIGN CRITERIA. RG. 1.106 06 X 0 i REGULATORY GUIDES AND IEEE STANDARDS 24.00 FSAR 8. 1. 4. 3 DESIGN CRITERIA. RG 1.128 06 X X 0 REGULATORY GUIDES . AND IBRE STANDARDS 26.00 FSAR 8. 1. 4. 3 DESIGN CRITERIA. IEEE 279-1971 06 X. O REGULATORY GUIDES AND IEEE STANDARDS 4 . 4 P
- . -- _ - _ - . . , _ . - - - _ . _ . . . - , . _ . _ . _ . - - , - - . . _ . . ._--. _ . -- -. _ _ _ _ _ _ _- ---.. _ _ . ,-.._.. _ _ _ -...~ _ .-- _ . _ _. _ ~ _ _ _. - -
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RE F. COMMITMENT COMMITHENT COMMITMENT DOCUMENT / MOD DES CON FSAR REMARKS NUMBER SOURCE SECTION SUBJECT FEATURE ULE IGN ST AMEN
==== == ========== ==================== ==================== ==================== === === === ==== ========-===========
27.00 FSAR 8. 1. 4. 3 DESIGN CRITERIA, IEEE 308-1974 06 X X 0 REGULATORY GUIDES AND IEEE STANDARDS 20.00 FSAR 8. 1. 4. 3 DESIGN CRITERIA, IEEE 317-1976 06 X X 0 REGULATORY GUIDES AND IEEE STANDARDS 29.00 FSAR 8. 1. 4. 3 DESIGN CRITERIA. IEEE 323-1974 06 X 0 REGULATORY GUIDES AND IEEE STANDARDS 31.00 FSAR 8. 1. 4. 3 DESIGN CRITERIA, IEEE 336-1971 06 X 0 REF. FSAR 1.9.30 REGULATORY GUIDES AND IEEE STANDARDS l , 32.00 FSAR 8. 1. 4. 3 DESIGN CRITERIA. IEEE 344-1975 06 X 0 REGULATORY GUIDES AND IEEE STANDARDS 33.00 FSAR 8. 1. 4. 3 DESIGN CRITERIA, IEEE 379-1972 06 X 0 REGULATORY GUIDES ,) AND IEEE STANDARDS 35.00 FSAR 8. 1. 4. 3 DESIGN CRITERIA. IEEE 384-1974 06 X X 0 REGULATORY GUIDES AND IEEE STANDARDS 36.00 FSAR 8. 1. 4. 3 DESIGN CRITERIA. IEEE 464-1975 06 X X 0 REGULATORY GUIDES AND IEEE STANDARDS 95.00 FSAR 8. 1. 4. 3 DESIGN CRITERIA, 10CFRF50 APP.A. GDC2 06 X 0 REGULATORY GUIDES AND IEEE STANDARDS 2352.00 FSAR 8. 1. 4. 3 DESIGN CRITTERIA, 10CFR50 APP.A. 06 I O SEE TABLE 8.1-1 REGULATORY GUIDES GDC17 AND IEEE STANDARDS O O O
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======= ========== ==================== ==================== ==================== === === === ==== ============-=======
2354.00 FSAR '8. 1. 4. 3 COMPLIANCE WITH RG RG 1.118 06 X 0
& IEEE STANDARDS 2355.00 FSAR 8. 1. 4. 3 COMPLIANCE WITH RG RG 1.129 06 X 0
& IEEE STANDARDS 2356.00 FSAR 8. 1. 4. 3 COMPLIANCE WITH RG IEEE 338-1977 06 X 0
& IEEE STANDARDS 37.00 FSAR B. 2. 1. 1 0FFSITE SOURCES OFFSITEPOWER-NATIONA 06 X 0
{ L BUREAU OF
. STANDARDS HANDB00E NO. 8 (NATIONAL ELECTRICAL SAFETT CODE PART 2) 38.00 FSAR 8. 2. 1. 1 0FFSITE SOURCES OFFSITE POWER STSTEM 06 X 0 HAS THE CAPACITT AND CAPABILITT TO SUPPLT THE POWER NECESSART FOR THE-SAFETT LOADS OF ONE UNIT WHILE PLACING THE OTHER IN COLD SHUTDOWN 41.00 FSAR 8. 2. 2. 4 CONFORMANCE TO 10CFR50, APP. A. GDC 06 X 0 CRITERIA (PREFERRED 4 POWER SOURCES) 42.00 FSAR 8. 2. 2. 4 CONFORMANCE TO 10CFR50. APP. A, GDC 06 X 0 CRITERIA (PREFERRED 17 POWER SOURCES) 43.00 FSAR 8. 2. 2. 4 CONFORMANCE TO 10CFR50, APP. A, GDC 06 X 0 CRITERIA (PREFERRED 18 POWER SOURCES) 44.00 FSAR 8. 2. 2. 5 STANDARDS AND GUIDES ANSI C37.010 - 1972 06 X 0
^ ^ - - - - - - ~ ' "
l Page No. 18 11/23/87 PLANT V0GTLE UNIT 2 READINESS REVIEW PROGRAM COMMITHENT MATRIX CURRENT THRU FSAR AMENDMENT 33
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REF. COMMITMENT COMMITMENT COMMITMENT DOCUMENT / MOD DES CON FSAR REMARKS NUMBER SOURCE SECTION SUBJECT FEATURE ULE IGN ST AMEN
=== === ========== ==================e= ==================== ==================== === === === ==== ======2=============
45.00 FSAR 8. 2. 2. 5 STANDARDS AND GUIDES ANSI C37.90 - 1971 06 X 0 l 0 46.00 FSAR 8. 2. 2. 5 STANDARDS AND GUIDES ANSI C57.12.00 - 06 X 1973 53.00 FSAR 8. 3. 1. 1 DESIGN CR TERIA FOR ANSI C37.010 - 1972 06 X 0 CLASS IE EQUPMENT
- 1. DESIGNCRkTERIA FOR ANSI C37.06 - 1971 06 X 0 54.00 FSAR 8. 3. I CLASS IE qUIPMENT
- 3. 1. I DESIGN CRITERIA FOR ANSI C37.13 - 1973 06 X 0 55.00 FSAR 8.
CLASS IE EQUIPMENT 56.00 FSAR 8. 3. 1. I DESIGN CRITERIA FOR NEMA ABI-1975 06 X 0 CLASS IE EQUIPMENT
- 3. 1. RESIDUAL HEAT IEEE 323 06 X 0 63.00 FSAR 8. 1 REMOVAL ISOLATION VALVE POWER SUPPLY 64.00 FSAR 8. 3. 1. 1 RESIDUAL REAT IEEE 344 06 X 0 REMOVAL ISOLATION VALVE POWER SUPPLY
- 1. AC POWER SYSTEMS IEEE 323 06 X 0 96.00 FSAR 8. 3. 1 CLASS IE QUALIrlCATION-INTERC ONNECTIONS
- 1. AC POWER SYSTEMS IEEE 344 06 X 0 97.00 FSAR 8. 3. 1 CLASS IE QUALIFICATION-INTERC ONNECTIONS
- 3. 1. AC POWER SYSTEMS RG 1.75 06 X 0 98.00 FSAR 8. 1 CLASS IE INTERCONNECTIONS 9 9 9
I
+ . ,
l . s Page No. 19 11/23/07- , PLANT V0GTLE UNIT 2 READINESS REVIEW PROGRAM COMMITMENT MATRIX CURRENT THRU FSAR AMENDMENT 33
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, REF. COMMITMENT COMMITMENT COMMITMENT DOCUMENT / MOD DES CON FSAR REMARES l NUMBER SOURCE SECTION SUBJECT FEATURE ULE IGN ST AMEN ! ======= ========== ==================== ==================== ==================== === === === ==== ==================== 99.00 FSAR 8. 3. 1. 1 AC POWER SYSTEM RG 1.32 06 X 0 CLASS lE -SHARING OF , SYSTEM BETWEEN UNITS
- i 100.00 FSAR 8. 3. 1. 1 AC POWER SYSTEM. RG 1.81 06 X 0 CLASS lE. SRARING OF SYSTEMS BETWEEN UNITS e*
1 104.00 FSAR 8. 3. 1. 1 AC POWER CONTAINMENT 10CFR50 APP. A. GDC 06 X 0 ELECTRICAL 50 PENETRATIONS 4815.00 FSAR 8. 3. 1. 1 CLASS lE BUS IEEE 279 06 X 0 UNDERVOLTAGE
' PROTECTION SENSORS 4817.00 FSAR 8. 3. 1. 1 CLASS lE SYSTEMS ALL SAFETY RELATED 06 X 0 EQUIPMENT LAYOUT EQUIPMENT HOUSED IN SEISMIC CAT. I STRUCTURES 82.00 FSAR 8. 3. 1. 4. 3 CABLE ROUTING SEPARATION- WITHIN 06 X X 0 PANELS AND CONTROL BOARDS. S IN. MIN.
i SPATIAL SEPARATION OR BARRIERS ARE PROVIDED BETWEEN COMPONENTS OR CABLES OF DIFFERENT SEPARATION GROUPS [ 4824.00 FSAR 8. 3. 2. I 125-V DC SAFETY IEEE 308 06 X 0 FEATURES SYSTEMS - DESIGNATION AS lE 4825.00 FSAR 8. 3. 2. I 125-V DC SAFETT NO SINGLE FAILURE IN 06 X 0 FEATURES SYSTEMS ANY 125-V DC SYSTEM WILL RESULT IN ; CONDITIONS THAT WILL PREVENT SAFE i SHUTDOWN. I i i 1
. - _ . . . . . - _ _ . ~ , . ~ ~ , _ . . _ , , _ . . ., -- -. ~ . _ _ _ _ _ _ - _ _ _ _ . _ _ -. . _ _ _ _ _ _
Page No. 20 11/t3/87 PLANT V0GTLE UNIT 2 READINESS REVIEW PROGRAM COMMITMENT MATRIX CURRENT THRU FSAR AMENDMENT 33
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REF. COMMITMENT COMMITMENT COMMITMENT DOCUMENT / MOD DES CON FSAR REMARKS NUMBER SOURCE SECTION SUBJECT FEATURE ULE IGN ST AMEN
======= ========== ==================== ==================== ==================== === === === ==== ====================
4826.00 FSAR 8. 3. 2. 1 SIZING OF BATTERIES IEEE 485- 1978 06 X 0 SIZED TO PROVIDE REQUIRED LOAD FOR 2 3/4 HRS. 4828.00 FSAR 8. 3. 2. 1 SIZING OF' BATTERIES BATTERY CAPACITY IS 06 X 0 INCREASED BY 10% FOR
'p LOAD GROWTH AND 25%
FOR AGING 4829.00 FSAR 8. 3. 2. I SIZING OF BATTERIES BATTERY MIN. VOLTAGE 06 X 0 DESIGN LIMIT IS 1.80-V/ CELL OR 106.2-V/ BATTERY 4830.00 FSAR 8. 3. 2. I 125V-DC SAFETY IEEE 308 06 X 0 FEATURES SYSTEMS SIZING OF BATTERY CHARGERS 4831.00 FSAR 8. 3. 2. I 125V-DC SAFETY RG 1.32 06 X 0 FEATURES SYSTEMS SIZING OF BATTERY CHARGERS 4832.00 FSAR 8. 3. 2. I 125V-DC SAFETY CHARGERS SPECIFIED 06 X 0 FEATURES SYSTEMS TO MAINTAIN OUTPUT SIZING OF BATTERY VOLTAGE REQUIRED + CHARGERS OR - It FROM NO LOAD TO FULL LOAD 4833.00 FSAR 8. 3. 2. I 125V-DC SAFETY CHARGER OUTPUT 06 X 0 FEATURES SYSTEMS FILTERED TO LIMIT SIZING OF BATTERY RIPPLE VOLTAGE TO CHARGERS MAX. 3% RMS WITH BATTERY DISCONNECTED 4838.00 FSAR 8. 3. 2. I MAINTENANCE AND RG 1.129 06 X 0 TESTING - PERIODIC CAPACITY TESTS O O O
4 1 O O Page No. 21 i 11/23/87 PLANT V0GTLE UNIT 2 READINESS REVIEW PROGRAM COMMITMENT MATRIX CURRENT THRU FSAR AMENDMENT 33
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REF. COMMITMENT COMMITMENT COMMITMENT DOCUMENT / MOD DES CON FSAR REMARES NUMBER SOURCE SECTION SUBJECT FEATURE ULE IGN ST- AMEN
======= ========== ==================== ==================== ==================== === === === ==== ====================
4839.00 FSAR 8. 3. 2. I DC POWER SYSTEM - IEEE 450-1975 06 I O MAINTENANCE AND TESTING-PERIODIC CAPACITY TESTS 4827.00 FSAR 8. 3. 2. 1. I SIZING OF BATTERIES BATTERIES SIZED AT 06 X 0 MIN. TEMP. OF 55
, DEGREES F 4836.00 FSAR 8. 3. 2. 2 ANALYSIS - TRAIN C&D IEEE 384 06 X 0 BATTERY CHARGERS QUALIFIED AS ISOLATION DEVICES 4837.00 FSAR .B. 3. 2. 2 ANALYSIS - TRAIN C&D R0 1.75 06 X 0 BATTERY CHARGERS QUALIFIED AS ISOLATION DEVICES 3527.00 FSAR 9. 2. 1-3 NSCW COMPONENT DATA CLASS lE POWER 06 X 0 SUPPLY.
2319.00 FSAR 10A. 2. 6 AUX. FEEDWATER R.G. 1.75 06 X 0 SYSTEM PHYSICAL SEPARATION BETWEEN ELECTRICAL COMPONENTS 2320.00 FSAR 10A. 2. 6 AUX. FEEDWATER IEEE 384 06 X 0 SYSTEM PHYSICAL SEPARATION BETWEEN ELECTRICAL ' COMPONENTS 4880.00 FSAR 12. 3. 4. 1. 6 POWER SUPPLIES MONITORS THAT ARE- 06 X- 0 (ARMS) IDENTIFIED AS SAFETY RELATED ARE REDUNDANT AND ARE SUPPLIED POWER FROM THE PLANT 120-V SAFETY RELATED BUSES _ _ _ _ _ _ _ - . . . _ _ _ _ _ _ _ - _ _ _ _ - - - _ - _ - _ . _ _ - _ . . . . - . . _ . . - - .- .- . . . . - .-~, ,- -- . _- - .
Page No. 22 11/23/87 PLANT V0GTLE UNIT 2 READINESS REVIEW PROGRAM COMMITMENT MATRIX CURRENT TRRU FSAR AMENDMENT 33
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REF. COMMITMENT COMMITMENT COMMITMENT DOCUMENT / MOD DES CON FSAR REMARKS NUMBER SOURCE SECTION SUBJECT FEATURE ULE IGN ST AMEN
======= ========== ==================== ==================== ==================== === === === ==== ====================
4881.00 FSAR 12. 3. 4. 1. 6 POWER SUPfLIES POWER TO THE 06 X 0 (ARMS)
- CHANNELS THAT MONITOR ONLY NORMAL OPERATIONS IS SUPPLIED FROM THE
{ ; REGULATED 120-V INSTRUMENTATION BUS
, THAT IS BACKED BY THE DIESEL GENERATOR.
2905.00 FSAR 17. 1. 2 Q. A. PROGRAM RG 1.30 (8-11-72) 06 X 0 2968.00 FSAR 17A. O INTRODUCTION ANSI N45.2.4-1972 06 X 0 REF. FSAR SEC. (IEEE 336-1971) 1.9.30 754.00 FSAR 17A. 1 QUALITY ASSURANCE RG 1.30, 8/11/72 06 X 0 REF. FSAR 1.9.30 REQ. FOR INST. AND INSP. OF ELECT. EQUIP. 5019.00 I.E.B. C-77,06/27 ITE IMPERIAL PNEUM. TIME DELAY 06 X 0 RESPONSE TO IEB CORRES. PNEUMATIC 'IME DELAY RELAYS WITH A REPEAT 77-01 RELAYS ACCUR. RANGE OF + OR
- 15% OR GREATER WILL NOT BE USED.
SOLID STATE T.D.R. OR PNEUM. T.D.R. WITH A REPEAT ACCUR. RANGE BETTER THAN + OR - 15% WILL BE USED. 5020.00 I.E.B. C-77/II/ll WESTINGHOUSE TYPE AR NO WESTINGHOUSE TYPE 06 X 0 RESPONSE TO IEB CORRES. RELAY "AR" RELAYS WILL BE 77-02 USED IN THE B.O.P. SAFETY CIRCUITS i O O -- 9 ___.______ _ i I
a . i i Page No. .23 11/23/87 PLANT V0GTLE UNIT 2 READINESS REVIEW PROGRAM COMMITMENT MATRIX CURRENT TRRU FSAR AMENDMENT 33
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REF. COMMITMENT COMNITMENT CCMMITHENT DOCUMENT / MOD DES CON FSAR REMARKS NUMBER SOURCE S EC'.* I O N SUBJECT FEATURE ULE IGN ST AMEN
======= ========== ===========s======== ==================== ==================== === === === ==== ====================
5 4668.00 1.E.B. C-79/12/28 WESTINGHOUSE (SEE D.E. MATRIX) 06 X 0 RESPONSE TO IEB CORRES. ELECTRIC RELAYS MEASURES WILL BE 79-25 TAEEN TO ENSURE THAT
- (
e DEFECTIVE W-BFD RELAYS ARE NOT USED I 4289.00 NRC QUEST. 0260. 61 PRESSURIZER RELIEF POWERED FROM CLASS 06 X 0 REFERENCE TO FSAR CORRES. VALVES. BLOCK IE AC/DC SYSTEMS TABLE 3.2.2-1. VALVES, LEVEL RESPONSE TO QUESTION INDICATORS
- 4310.00 NRC QUEST. 0420. 10 ISOLATION DEVICES IEEE 472 06 X 0 RESPONSE TO CORRES. QUESTION.
4319.00 NRC QUEST. Q420. 46 BALANCE OF PLANT WCAP B760 06 X 0 RESPONSE TO QUESTION , CORRES. INTERFACE WITH WESTINGHOUSE DESIGN 4272.00 NRC QUEST. 0430. 5-1 MAIN CONTROL BOARD & THE EMERGENCY 06 X 0 RESPONSE TO QUESTION ! CORRES. REMOTE SRUTDOWN LIGRTING POWER PANEL ILLUMINATION DISTRIBUTION SYSTEM LEVELS IS CLASS lE FROM i 4.16KV TO 480-V LEVEL. 4274.00 NRC QUEST. Q430. 59 POWER SUPPLY TO 10CFR50, APP. A, 06 X 0 RESPONSE TO CORRES. CLASS IE BUSES GDC-17 QUESTION. 4275.00 NRC QUEST. Q430. 59 POWER SUPPLT TO IEEE 308-1974 06 X 0 RESPONSE TO QUESTION CORRES. CLASS IE BUSES 4276.00 NRC QUEST. 0430. 59 POWER SUPPLT TO RG 1.32 06 X 0 RESPONSE TO CORRES. CLASS IE BUSES QUESTION. 4277.00 NRC QUEST. 0430. 61 120V AC POWER RG 1.75 06 X 0 RESPONSE '
.CORRES. SUPPLIES 4280.00 NRC QUEST. Q430. 64 MOV OL PROTECTION RG 1.106 06 R 0 RESPONSE CORRES. PER RG POS. C.l(e) i
_._ __ ~ . _ . ._ .- .- .___ _
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REF. COMMITHENT COMMITMENT COMMITMENT DOCUMENT / MOD DES CON FSAR REMARKS NUMBER SOURCE SECTION SUBJECT FEATURE ULE IGN ST AMEN
======= ========== ==================== ==================== ==================== === === === ==== ====================
i 4281.00 NRC QUEST. Q430. 64 MOV's - MOV MOTOR OVERLOAD 06 X 0 RESPONSE CORRES. $ IS ANNUNCIATED IN CONTROL ROOM 4283.00 NRC QUEST. Q430. 68 QUALIIICATION OF IEEE 323-1974 06 X 0 RESPONSE TO QUESTION CORRES. DEGRADED VOLTAGE PROTECTION EQUIPMENT 4284.00 NRC QUEST. 0430. 68 QUALIFICATION OF IEEE 344-1975 06 X 0 RESPONSE TO QUESTION CORRES. DEGRADED VOLTAGE PROTECTION EQUIPMENT 4181.00 NRC QUEST. Q430. 69 QUALIFICATION OF IEEE 344-1975 06 X 0 RESPONSE TO QUESTION CORRES. LOAD SEQUENCER. PROTOTYPE TEST 4286.00 NRC QUEST. 0430. 69 QUALIFICATION OF IEEE 323-1974 06 K 0 RESPONSE TO QUESTION CORRES. LOAD SEQUENCERES. PROTOTYPE TEST 4329.00 NRC QUEST. Q430. 75 QUALIFICATION OF ASTM E-Il9 06 X 0 RESPONSE TO QUESTION CORRES. FIRB-RESTRAINT MATERIAL USED AS SEPARATION BARRIERS WITRIN PANELS AND CONTROL BOARDS 4936.00 NFC QUEST. 0430. 75(E) HIGH ENERGY EQUIP. RG 1.75 06 X 0 RESPONSE TO QUESTION CORRES. IN CABLE SPREADING ROOMS 4937.00 NRC QUEST. Q430. 75(E) RIGH ENERGY EQUIP. IEEE 384 06 X 0 RESPONSE TO QUESTION CORRES. IN CABLE SPREADING ROOMS w
& O O
PLANT YOGTLE UNIT 2 NEADINESS REVIEW Ph0 GRAM IMPLEMENTATION MATHIX
- :::= = = = 1:: :::::= = = == :- ============
DESIGN CONST REF. SOURCE AND DES CON CURRENT DESIGN CURRENT CONSTRUCTION Nt7tBER SECTION SUBJECT DoctMENT/ FEATURE IGN ST. AS or- IMPLUtENTATION AS OF: IMPLDlENTATION l& MARKS
- =2 :::============ ==================== ::::::===== :a:: :: ::: 2:= :: mas::: ::::::::::::::::::::: :::::= : :::::: ======*:3 3:: - : :::: 35 ::: "2" t
4 EXPLANATION OF FIELOS REF NO. - A reforesce number that corresponds to the oppropriate IIne entry la the commitment metrin. SOURCE AND SECTION - The commitment source end section to be implemented SUBJECT - The s ubj ec t of the comeltment peregraph DOCUMENT / FEATURE - The doceaeet discussed In the FSAR section or the pleet feature described in the FSAR sectIos. BSee Commitment Matrix.) DESIGN / CONSTRUCTION - An X ls placed under the headlag for the orgenlastles responsible for Implementetlom of the commitment DESIGN CURRENT - The date that comaltment loplementetles was verified AS OFs CONST CURRENT AS OFs DEStGN - The Project documentist that were revleved to verify commitment IMPLEMENTATION laplementetlee CONSTRUCTSON IMPLEMENTATION
l'nge No. I 12/03/87 l'I. ANT V0GTIE UNIT 2 READINESS REVIEW PIM3IWI I IMI'LDfENTATION MATRIX - MODULE 06 [
= =========== _ = ==========-=======
DESIGN CONST REF. SOURCE AND DES CON CURRENT DESIGN CURRENT CONSTRUCTION NTNUFR SECTION SUBJECT- DOCUMENT / FEATURE IGN ST. AS OF: IMPLEMENTATION AS OF: IMPIFMENTATION REMARKS
= ==== ==============z ============e======= == ================= === === ======== ======== ============= ======== ====================== ============= ====
2.01 FSAR DESIGN CRITERIA, 10CFR50 A?P. A GDC X 06-22-87 DC-1000-E.RV.6,8-29-85 DC-]O10 AITLIES REGULATORY GUIDES 4 (FSAR 8.1.4.3) .C.S.DC-1806,RV.5,8-23 DC-1007 CRITERI A
- 8. 1. 4. 3 AND IEEE STANDARDS - -85,C.S.DC-1816.RV.3,9 TO SAFETY-RRI.AYED ENVIRONMENTAL AND 85,C.S.DC-1818, RV.3 ELECTRICAL ,
MISSILE DESIGN BASES 8-22-85,C.S.DC-1821,R EQUIINENT. V.5,5-2-83,C.S.DC-1006
,RV.2,7-13-83,C.S.DC-1 007,RV.6,3-24-86.C.S 2.02 FSAR. DESIGN CRITERIA, 10CFR50, AIT. A, GDC X 06-22-87 DC-1010,RV.5.2-7-86,PG DC-1010 AITLIES REGULATORY GUIDES 4 (FSAR 8.1.4.3) 5.90-94,DC-1003,RV.2,6 DC-1007 CR11ERIA
- 8. 1. 4. 3 AND IEEE STANDARDS -- 83.C.S. 10 SAFETY-RELATED ENVIROPMENTAL AND ELECTRICAL HISSILE DESIGN BASES EQUIINENT.
3.00 FSAR DESIGN CRITERIA, 10CRF50 AFT. A. GDC X 06-22-87 DC-1000-E. REY.6,8-29-8 HEGULATORY GUIDES 5 (FSAR 8.1.4.3) 5,C.S..DC-1806.REV.5,8 ,
- 8. I. 4. 3 AND IEEE STANDARDS - 85,C.S.DC-1815 REV '
SHARING OF .2,5-18-83,C.S.,DC-181 l STRUCTURES SYSTEMS, 6,REV.3.9-3-85,C.S..DC AND COMFVNENTS -1818,REV.3,8-22-85,C. S.,DC-1821.REV.S.5-2-8 , 3.C.S. 4.01 FSAR DESIGN CRITERIA, 10CRF50 AIT. A, GDC X 06-22-87 DC-1000-E.REV.6,8-29-8 NEGULA1 DRY GUIDES - 18 (FSAR 8.1.4.3) 5,C.S..DC-1801.REV.3,7
- 8. 1. 4. 3 AND IEEE STANDARDS - 83 C.S..DC-1804,RE INSPECTION AND V.5,10-2-85,C.S..DC-18 TESTING CF ELECTRIC 05,REV.S.8-6-85,C.S..D POWER SYSTEMS C- 1806. REV. 5,8 85, C
.S.,DC-1807, REY.3,8-23
- 85,C. S . . DC- 1815, REY. 2 5-18-83 C.S.
4.02 FSAR DESIGN CRITERIA, 10CRF50 AFT. A. CDC X 06-22-87 DC-1823.-REV. 3 REGULATURY GUIDES 18 (FSAR 8.1.4.3) 2-3-84, C.S., DC-1826,
- 8. 1. 4. 3 AND IEEE STANDARDS - REV. 1, 9-18-78, C.S.,
' INSPECTION AND DC-1625. REV. 1 TESTING OF ELECTRIC 8-2-83 IVWER SYSTEMS
---,__-----_----_.-_____---e _ r, , e,a +,--we- +w w - - - . , , , - - - . , ,-- ,,m.. , , , ,.. _ , , , , , _ , a
Par.e No. 2 12/Ob tf7 PIANT VOGTLE UNIT 2 READINESS REVIFW PIf0 GRAM IMPIEMENTATION MATRIX - MODULE 06
====- r======== ===========-===~===
DESIGN CONST REF. SOURCE AND DES CON CURRENT DESIGN CURRENT CONSTHtK' TION NINBER SECTION SUBJECT DOCtHENT/ FEATURE IGN ST. AS OF: ?MPLEMENTATION AS OF: IMPIEMENTATION RFMARES -- = := ==e== ========= ==================== ================= == === === ======== ====================== ======== ====================== ================== 4.03 FSAR DESIGN CRITERI A, 10CRF50, APP. A. GDC X 06-22-87 DC-1816, REY.3,9-3-85,C REGULATORY GUIDES 18 (FSAR 8.1.4.3) .S. DC-1821,REV.5.5 8. 1. 4. 3 AND IEEE STANDARDS - 83.C.S. INSPECTION AND TESTING OF ELECTRIC POWER SYSTEMS 5.00 FSAR DESIGN CRITERIA, 10CRF50, APP. A GDC X 06-22-87 DC-1000-E.REv.6,8-29-8 REGULATORY GUIDES 50 (FS AR 8.1.4.3) 5,C.S..DC-1818,REV.3,8
- 8. 1. 4. 3 AND IEEE STANDARDS - 85,C.S.,DC-1823,RE REACTOR CONTAlfNENT V.3.2-3-84,C.S.
DESIGN BASES 6.00 FSAR DESIGN CRITERIA, RG 1.6 (FSAR X 06-22-87 DC-1000-E REV.6,8-29-8 " REGULATORY GUIDES 8.1.4.3) 5,IV.16,0C-1804,REV.5,
- 8. 1. 4. 3 AND IEEE STANDARDS - 10-2-85,C.S..DC-1805,R INDEPENDENCE BE1HEEN EV.5,8-6-85,C.S..DC-18 REDUNDANT STAND-BY 06 REV.5,8-23-85,C.S.,
(ON-SITE) POWER DC- 1807, REV.3,8 85, SOURCES AND THEIR C.S. DISTRIBUTION SYSTEM ft.00 FSAR DESIGN CRITERIA, RG 1.22 (FSAR X 06-22-87 DC-1000-E, REV. 6 REGULATORY GUIDES 8.1.4.3) 8-29-85, PG. 16,
- 8. 1. 4. 3 AND IEEE STANDARDS - DC-1605, REV. 1, PERIODIC TESTING OF 3-29-83, C.S.,
PROTECTION SYSTEM DC-1625. REV. 1 ACTUATION FUNCTIONS 8-2-83, C.S. 9.00 FSAR DESIGN CRITERIA, RG l.29 (FSAR X 06-22-87 DC-1000-E.REV.6,8 29-8 REGULATORY GUIDES 8.1.4.3) 5,IV.16.DC-1005, REY.1,
- 8. 1. 4. 3 AND LEER STANDARDS - 4-4-83,C.S..DC-1010,RE SEISMIC DESIGN V.S 2-7-86,C.S.
CLASSIFICATION 10.00 FSAR DESIGN CRITERIA, RG 1.30 (FSAR X X 06-22-87 DC-1000 E. REV. 6, 05-21-87 SEE REMARKS EUR CONSTRUCTION REGULATORY GUIDES 8.1.4.3) 8-29-85, N. 16 IMPLEMENTATION,
- 8. I. 4. 3 AND IEEE STANDARDS - DC-lR18, HEV. 3, SEE PEF. No. 31 ottf.i,!Tv ASSURANCE 8 85, C.S.
SEO. FOR INST. AND INSP. OF EIECT. EQUIP. O O O
t ry b% b' U Page No. 3 12/03/87 PLANT V0GTLE UNIT 2 READINESS REVIEW PIUJRAM IMPLEMENTATION MATRIX - MODULE 06
=============================== ====
DESIGN CONST REF. SOURCE AND DES CON CURRENT DESIGN CURRENT CONSTRUCTION NtHDER SECTION SUBJECT DOCINENT/ FEATURE IGN ST. AS OF: IMPLEMENTATION AS OF: IMPLEMENTATION REMARKS
= =============== ==================== ==================== === === ====e=== ======== ============= ======== ======== ============= ========_===
11.01 FSAR DESIGN CRITERIA, RG l.32 (FSAR X 06-22-87 DC--1000--E.REV.6,8-29-8 REGULA MRY CUIDES 8.1.4.3) 5,PG.16,0C-1801.REV.3,
- 8. 1. 4. 3 AND IEEE STANDARDS - 7 83.C. S . . DC- 180 4, R CRITERIA FOR EV.5,10-2-85,C.S..DC-1 SAFETY-RELATED 805, REY.5,8-6-85,C.S.,
ELECTRICAL F0WER DC-1806 REV.5,8-23-85 SYSTEMS FOR NUCLEAR C.S..DC-1807,REV.3,8-2 IVWER PLANTS 3-85,C.S..DC-1815, REY. 2,5-18-83,C.S. 11.02 FSAR DESIGN CRITERIA, RG 1.32 (FSAR X 06-22-87 DC-1821 REV. 5 REGULAM RY GUIDES 8.1.4.3) 5-2-83, C.S., DC-1823,
- 8. 1. 4. 3 AND IEEE STANDARDS - REV. 3, 2-3-84, C.S.,
CRITERIA IVR DC-1826. REV. 1 SAIETY-RELATED 9-18-78, C. S. ELECTRICAL IVWER SYSTEMS FOR NUCLEAR POWER PLANTS 11.03 FSAR DESIGN CRITERIA, RG 1.32 (FSAR X 06-22-87 DC-1816,REV.3,9-3-85,C REGULAMRY GUIDES 8.1.4.3) .S..DC-1818,REV.3,8-22
- 8. 1. 4. 3 AND IEEE STANDARDS - -85,C.S.
CRITERIA IVR SAFETY-RELATED ELECTRIC POWER SYSTEMS FOR NUCLEAR IVWER PLANTS 13.00 FSAR DESIGN CRITERIA, RG 1.41 (FSAR I 06-22-87 DC-1000-E,REV.6,8-29-8 REGULA MRY GUIDES 8.1.4.3) 5 PG.16,DC-I804 REY.5,
- 8. 1. 4. 3 AND IEEE STANDARDS - 10-2-85,C.S..DC-1806,R PREOP TESTING OF EV.5,8-23-85,C.S.
ONSITE POWER SYSTEMS TO VERIFY LOAD GROUP ASSIGNMENTS 14.00 FSAR DESIGN CRITERIA, RG l.47 (FSAR X 06-22-87 DC-1000-E REV.6,8-29-8 REGULATURY GUIDES 8.1.4.3) 5,INI.17,DC-1801,REV.3,
- 8. 1. 4. 3 AND IEEE STANDARDS - 7-19-83,C.S..DC-1804,R BYPASSED AND EV.5.10-2-85,C.S..DC-1 INOPERABLE STATUS 805,REV.5,8-6-85,C.S.,
INDICATION TUR DC-1625,REV.1,8-2-83,C SAFETY SYSTEMS .S.
Page No. 4 12/03/07 PI 4NT V0GTIE UNIT 2 READINESS REVilV I'ROGRAM IMPIFMENTATION M4TRIX - MODUIE 06
- .= =- ,= ================= ========
DESIGN CONST REF. 500HCE AND DES CON CURRENT DESIGN CURRENT CONSTRUCTION NINDFR SECTION StfBJECT DOCtNENT/ FEATURE IGN ST. AS OF: IMPLEMENTATION AS OF: IMPIDfENTATION RFMARKS
=======e==e====.: ======== ====== ==== =====,=== ========== === === ======== ====================== ======== ====================== =====,========e===
15.00 FSAR DESIGN CRITERIA, RG l.53 (FSAR X 06-22-87 DC-1000 E.REV.6,8-29-8 REGULATORY GUIDES 8.1.4.31 5,FC.17,DC-1605,HEV.I.
- 8. 1. 4. 3 AND IEEE STANDARDS - 3-29-B3,C.S.
APPLICATION OF SINGLE FAILURE CRITERION 17.00 FSAR DESIGN CRITERIA, RG 1.63 (FSAR X 06-22-87 DC-1000-E.REV.6,8-29-8 REGULATORY GUIDES 8.1.4.3) 5,PG.17,DC-1805,REV.5,
- 8. 1. 4. 3 AND IEEE STANDARDS - 8-6-85,C.S..DC-1818,RE PENETRATION V.3,8-22-85,C.S.
ASSEMBLIES 18.00 FSAR DESIGN CRITERIA, RG 1.75 (FSAR X X 06-22-87 DC-1000-E,REV.6,8-29-8 05-21-87 SEE RDfARKS FOR CONSTRUCTION REGULATORY GUIDES 8.1.4.3) 5 PG.17,DC-1804,REV.5, IMPLEMENTATION SEE
- 8. I. 4. 3 AND IEEE STANDARDS - 10-2-85,C.S..DC-1805 R REF. NO. 35 PRYSICAL EV.5.10-2-85,C.S..DC-1
, INDEFENDENCE OF 805,REV.5,8-6-85 C.S., ELECTRICAL SYSTDIS DC-1806,REV.5,8-23-85, i J.s.DC-1807,REV.3,8-23
-85,C.S..DC-1816,REV.3 9-3-85,C.S. DC-1818,R IW.3,8-22-85,C.S.
19.00 FSAR DESIGN CRITERIA, RG 1.81 (FSAR X 06-22-87 DC-1000-E REV.6,8-29-8 REGULA1VRY GUIDES 8.1.4.3) 5,0G.17,DC-1801,REV.3,
- 8. 1. 4. 3 AND IEEE STANDARDS - 7-19-83,C.S. DC-1804,R SHARED EMERGENCY AND EV.5.10-2-85,C.S..DC-1 l SlfUTDOWN SYSTEMS FOR 805,REV.5,8-6-85,C.S.,
MULTI-UNIT NUCLEAR DC-1806,REV.5.8-23-85, I l POWER PLANTS C.S..DC-1807, REY.3,8-2 3- 85,C. S . 20.00 FSAR DESIGN CRITERIA, RG 1.89 (FSAR X 06-22-87 DC-1000-E,HEV.6,8--29-8 DC-1010 APPLIES REGULA1 DRY GUIDES 8.1.4.3) 5,PG.17 DC-1805 REV.5, DC-1007 CRITERIA
- 8. 1. 4. 3 AND IEEE S TANDARDS - 8 6-85,0G,10,DC-1816.R TO SAFETY-RELATED QUALIFICATION POR EV.3.9 3- 85,C.S. DC-10 ELECTRICAL CLASS lE EQUIINENT 07,REV.6,3-24-86,C.S., EQUIINENT DC-1010,REV.5,2-7-86,P GS.90-98 0 9 9
Page N<>. 5 12/03/H7 PLANT YOGTIE UNIT 2 RE ADINESS REVIEW PROGRAM IMPtfMENTATION MATRIX - MODULE 06
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DESIGN CONST REF. SOURCE AND DES CON CURRENT DESIGN CURRENT CONSTRIK' TION NIHilFR SECTION St!BJFCT DOCINENT/f EATURE IGN ST. AS OF: IMPLEMENTATION AS OF: IMPIEMENTATION REMARKS
-e = m u =.=====- : ==== ==================== ==================== === === ======== === ================== ======== ======= = ========,=== " ,t==-====.======
21.00 PSAR- DESIGN CRITERIA. RC 1.93 (FSAR X 06-22-87 DC-1000 E.REV. REGULATORY GUIDES 8.1.4.3) 6,8-29-85 P0.17
- 8. l. 4. 3 AND IEEE STANDARDS -
AVAILABILITY OF l ELECTRIC 00WER SOURCES 22.00 FSAR DESIGN CRITERIA. RG 1.100 (FSAR X 06-22-87 DC-1000-E.REV.6,0-29-8 DC-1010 APPLIES REGULA1DRT GUIDES 8.1.4.3) 5 PG.17,DC-1816.REV.3, DC-1005 CRITERIA
- 8. 1. 4. 3 AND IEEE STANDARDS - 9-3-85,C.S..DC-1005,RE TD CAT. I .i SEISMIC V. I .4 83.C.S. . DC-101 ELECTRICAL QUALIFICATION OF 0,REV.5.2-7-86,NS.90- EQUlINENT ELECTRIC EQUIINENT . 98, APPENDIX 10 SPEC. ,
'00 ' REv.0,PG.00.2 23.00 FSAR DESIGN CRITERIA, RG 1.106 (FSAR X 06-22-87 DC-1000-E REV.6,8-29-8 l
REGULATORY GUIDES 8.1.4.3) 5,PG.18.DC-1805.REV.5 [ 8. I. 4. 3 AND IEEE STANDARDS - 8 85.C. S. . DC-1806. RE TitERMAL OVERIDAD V.S.8-23-85,C.S..DC-18 PROTECTION FOR MOV 23, REY.3.2-3-84.C.S. MOTORS 21.00 FSAR DESIGN CRITERIA. RG 1.128 (FSAR X X 06-22-87 DC-1000-E.REV.6.8-29-8 05-21-87 SEE REMARKS FOR CONSTRUCTION REGULATORT GUIDES 8.1.4.3) 5,it.18,DC-1806,REV.5, IMPLEMENTATION SEE
- 8. 1. 4. 3 AND IEEE STANDARDS - 8-23-85.C.S. REF. No. 36 INSTALLATION DESIGN AND INSTALLATION OF LARGE LEAD STORAGE BATTERIES 26.01 FSAR DESIGN CRITERIA. IEEE 279-1971 (FSAR X 06-22-87 DC-1000-E.REV.6.8-29-8 REGULATORY GUIDES 8.1.4.3) 5. N.13.DC-1804,REV.5,
- 8. I. 4. 3 AND IEEE STANDARDS - 10 85.IV. I . DC -1805, R SINGLE FAILURE. EV.5,8-6-85.FG.I.DC-18 REDUNDANCY & 06.REV.5,8-23-85.PG.I.
INDEPENDENCE DC-1807.REV.3,8-23-85 CRITERIA FG.I.DC-1816. REY.3.9-3
-85.PG.2.DC-1823,REV.3
,2-3-84.19.1 L
I i L _-
Pa g e- No. 0 12/01/H7 Pl. ANT YOGTI.E I? NIT 2 READINESS REVIEW PROGRAM IMPLEMENTATION MATRIX - MO9ULE 06
==_== ============= ===- =====- e===
DESIGN CONST IfEF. SotiRCE AND DES CON CURRENT DESIGN CURRENT CONSTRtK' TION N?tFER SECTION SUBJECT DOCiffENT/FEATt'RE IGN ST. AS OF: IMPIEMENTATION AS OF: IMI'IDtENTATION RI}tARKS
===== : = = = ====== ==================== = = ====== ========= === === ======== ====================== ======== =====-================ ======= ==========
26.02 FSAR DESIGN CRITERIA, IEEE 27F 1971 (FSAR X 06-22-87 DC-1009,REV.2,6 3-83,P REGULATORY GUIDES 8.1.4.3) G.I.DC-1605 REV.I.3-29
- 8. 1. 4. 3 AND IEEE STANDARDS - - 83, N. I SINGLE FAILUPE, REDUNDANCY &
INDEPENDENCE CRITERIA 27.01 FSAR DESIGN CRITERIA, IEEE 308-1974 (FSAR X X 06-22-87 DC-1000-E.REV.6,8-29-8 05-21-87 *X3 AR01-E2, REV. 16, REF. RRF 6-49 REGULATORY GUIDES 8.1.4.3) 5.PG.13,DC-1801,REV.3, 3-13-86 *X3AR01-E2 DID
- 8. 1. 4. 3 AND IEEE STANDARDS - 7-19-83 PG.1,DC-1804,R ED-T-04, REY. 9, NOT ADDRESS LABEIS CLASS lE POWER EV.5.10-2-85.PG.1,DC-1 1-G-87 UNTIL ISSUE OF SYSTEMS 805, REV. 5,8-6-85, N. I . E- NRB 19,674 DC-1806.REV.5,8-23-85, APPROVED 4-7-87 N. I . DC- 1807, REV . 3,8 -2 (NO RETROFIT 3-85 PG.1,DC-1816.REV. REQUIRED) 3,9-3-85 PG.2 27.02 FSAR DESIGN CRITERIA. IEEE 308-1974 (FSAR X X 06-22-87 DC-1821.REV.S.5-2-83.P 05-21-87 SEE REMARKS SEE REF. NO. 27.01 REGULATORY GUIDES 8.1.4.3) G.I.DC-1823,REV.3,2 FUR CONSTRilCTION l 8. 1. 4. 3 AND IEEE STANDARDS - 84. N. I l CLASS lE IW ER
( SYSTEMS 2H.00 FSAR DESIGN CRITERIA. IEEE 317-1976 (FSAR X X 06-22-87 DC-1000-R,REV.6,8-29 8 05-21-87 X3AR01-E3, REV. 5 REGULATORY GUIDES 8.1.4.3) 5,0G.14,DC-1818,REV.3, 1-10-86, ED-T-19, REV.
- 8. 1. 4. 3 AND IEEE STANDARDS - 8 85, N .1 2, 5-19 86 ELECTRICAI.
PENETRATION ASSEMBLIES 29.00 FSAR DESIGN CRITERIA, IEEF 323-1974 (FSAR X 06-22-87 DC-1000-E,REV.6,8-29-8 DC-1010 APPLIES REGULATORY GUIDES 8.1.4.3) 5, N.14, DC- 1804, REV . 5, DC-1007 CRITERIA R. 1. 4. 3 AND IEEE STANDARDS - 10-2-85,W.I.DC-1805,R TO SAFETY-REI.ATED QUALIFYING CLASS IE EV. 5,8 85, PG.1, DC- 18 ELECTRICAL EQUIINENT 06,REV.5,8-23-85,00.I, EQUllMENT. DC-1807,REV.3,8-23-85, PG.I.DC-1816.REV.3,9-3
-85 PG.2.DC-1818,REV.3 j ,8-22-85 N.I l
l O O O
f% f% O Page N<>. 7 12/03/H7 PI ANT V0GTI.E UNIT 2 READINESS REVIFW l'ROGR4M IMPLEMENTATION MATRIX - MODULE 06
=--===-=======:====== =====- == :- ==
DESIGN CONST REF. SOURCE AND DES CON CURRENT DESIGN CURRENT CONSTRUCTION NINHER SECTION SUBJECT DOCINENT/ FEATURE IGN ST. AS OF: IMPLDfENTATION AS OF: IMPLDfENTATION REMARKS
- =:s== ========= ===e= ======== =========== ==== =============== === === ======== ====================== ======== ====================== ================ =
29.02 FSAR DESIGN CRITFRIA, IEEE 323-1974 (FSAR X 06-22-87 SI'EC. APPENDIX 'EA', REGULATORY GUIDES 8.1.4.3) REV. 3
- 8. 1. 4. 3 AND IEEE STANDARDS -
QUALIFYING CLASS lE EQUIINENT 29.03 FSAR DESIGN CRITERIA, IEEE 2 3-1974 (FSAR X 06-22-87 DC-1821.REV.5,5-2-83.P REGULATORY GUIDES 8.1.4.3) 0.l.DC-1823,REV.3.2 8. 1. 4. 3 AND IEEE STANDARDS - 84.PG.I.DC-1007,REV.6 QUALifTING CLASS IE 3-24-86 EQUIINENT 31.01 FSAR DESIGN CRITERIA, IEEE 336-1971 (FSAR X X 06-22-87 DC-1000-E REV.6.8-29-8 05-2 p B7 ED-T-04 R/9. 1-6-86 REGULATORT GUIDES 8.1.4.3) 5 N.14,DC-1806,REV.S. ~ ED-T-19 R/2, 5-19-86
- 8. 1. 4. 3 AND IEEE STANDARDS - 8-23-85. N.I.DC-1807,R ~
ED-T-34 R/0. 1-23-87 INSTALLATION, EV.3,8-23-85 PG.I.DC-1 CD-A-04 R/12, 3-17-86 INSPECTION, t, 816. RE V. 3,9 85, N . 3, CD-A-08 R/lT. 10-2-86 TESTING REQUIREMENTS DC-1818,REV.3,8-22-85, GD-A-30 R/13 FOR INSTUINENTATION PG.1 I1-26-86 AND ELECTRICAL GD-T-01 R/15, 1-29-87 EQUIINENT DURING CM-T-03 R/0. 5-23-86 CONSTRUCTION GD-T-31 R/2. 11-7-86 DC-A-06 R/II, 5-7-86 QC-A-01 R/5, 4-6-87 31.02 FSAR DESIGN CRITERIA. IEEE 336-1971 (FSAR X X 06-22-87 SEE REMARKS 05-21-87 23AR01-E2 R/16, SEE REF. NO. 31.01 REGULATORY GUIDES 8.1.4.3) 3-13-86 EUR DESIGN
- 8. 1. 4. 3 AND IEEE STANDARDS - X3AR01-E3 R/5, INSTALLATION, 1-10-86 INSPECTION, 8, X3AR01-E12 R/8, TESTING REQUIREMENTS 3-5-87 FUR INSTRtNENTATION AND ELECTRICAL EQUIINENT DURING CONSTRUCTION 32.01 FSAR DESIGN CRITERIA. IEEE 344-1975 (FSAR X 06-22-87 DC-1000 E.REV.6,8-29 8 REGULATORY GUIDES 8.1.4.3) 5, N.14, DC- 1804, REV. 5,
- 8. 1. 4. 3 AND IEEE STANDARDS - 10 -b 85, N.1, DC-1805, R SEISMIC EV.5,8-6-85,0G.I.DC-18 QUALIFICATION OF 06,REV.5,8-23-85,PG.1, I
CLASS lE EQUIINENT DC-1807.REV.3,8-23-85 PG.2.DC-1816 REV.3,9-3 l
-85 PG.3,DC-lRl8,REv.3
,8 22 Res .N.1
Page N n. H 12/ 0.t / H7 PLANT VOGTIE UNIT 2 READINPSS REVIEW PROGRAM IMPILMENTATION MATRIX - MODUI.E 06
--.:e: ::==:: -::: -- ::::::
DESIGN CONST REF. SOfWCE AND DES CON CURRENT DESIGN CURRENT CONSTRUCTION NIMDER SI:CTION StfBJECT DOClNENT/FEATlWE IGN ST. AS OF: IMPLEMENTATION AS OF: IMPIEMENTATION REMARKS
- - _= - =--------=:::=:::ee:- ==::========:-::====n: :=- == == == :::::::===:=========== ======== :::-- : : ==== ::::::= - ==.====:-- = -:
32.02 FSAR DESIGN CRITERIA. IEEE 344-1975 (FSAR X 06-22-87 DC-1005, REV. 1 DC-1010 AITIIES REGULATORY GUIDES 8.1.4.3) 4-4-83, N. 3A, DC-1005 CRITERIA
- 8. 1. 4. 3 AND IEEE STANDARDS - DC-1010 REV. 5, TO CAT. I SEISMIC 2-7-86, PGS. 90-98 ELECTRICAL QUALIFICATION OF SPEC. APPENDIX 'QG', EQUIIMENT CLASS lE EQUIINENT REY. O, SPEC. APPENDIX
'EA', REY. 3 32.03 FSAR DESIGN CRITERIA, IEEE 344-1975 (FSAR X 06-22-87 DC-1821.REv.5,5-2-83.P REGULATORY GUIDES 8.1.4.3) G.I.DC-1823,REV.3.2 8. 1. 4. 3 AND IEEE STANDARDS - 84 N.1 SEISMIC QUALIFICATION OF CI. ASS IE EQUlit1ENT 33.00 FS4R DESIGN CRITERIA. IEEE 379-1972 (FSAR X 06-22-87 DC-1000-E, REY.6,8-29-8 REGULATORY GUIDES 8.1.4.3) 5,PG.14 DC-1804,REV.5, i 8. 1. 4. 3 AND IEEE STANDARDS - 10-2-85,N.1,DC-1806,R APPLICATION OF EV. 5,8 85,IV. I . DC- 1
, SINGLE FAILURE 807. REV. 3,8-23-85,PG. 2 i CRITERION ,DC-1818.REV.3,8-22-85 l 0G.1,DC-1823,REV.3.2-l 3-84,N.I.DC-1009, REY. 2,6-3-83 PG.I 35.01 FSAR DESIGN CRITERIA. IEEE 384-1974 (FSAR X X 06-22-87 DC-1000-E. REY.6,8-29-8 05-21 87 X3AR01-E8 REV. 24 REGULATORY GUIDES 8.1.4.3) 5,PG.15.DC-1804,REV.5, 2-11-87 H. 1. 4. 3 AND IEEE STANDARDS - 10-2-85,PG.I.DC-1805,R X3AR01-E9 REV. 19 CRITERIA FOR E V. 5,8 85, N. I . DC-- 18 2 5--87 INDEPENDENCE OF 06 REV.5,8-23-85,N.I. ED-T-08 REV. 9, CLASS lE EQUllNENT DC-1807,REV.3,8-23-85, 7-31-86 AND CIRCUITS N. 2. DC-1816, REV. 3,9 -3
-8'i,PG.3 DC-1821,REV.S 5-2-83 PG.I 35.02 FSAR DESIGN CRITERIA. IEEE 384-1974 (FSAR X X 06 87 DC-1823, REV. 3, 05-21-87 SEE RD1 ARKS SFR REF. No. 35.01 REGULATURY GUIDES 8.1.4.3) 2 fM. N. I FOR CONSTRUCTION H. 1. 4. 3 AND IEEE STANDARDS -
CRITERIA FOR INDEPENDENCE OF CLASS IE EQUII?fENT I AND CIRCUITS l l l I e e e
.l o l Page No. 9 12/03/H7 PLANT V0GTIR I! NIT 2 READINESS REVIFM PROGRAM IMPI.EMENTATION MATRIX - MODUI.E 06
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DESIGN CONST REF. SOURCE AND DES CON CURRENT DESIGN CURRENT CONSTRUCTION NINDER SECTION SUBJECT DOCINENT/ FEATURE IGN ST. AS OF: IMPintENTATION AS OF: IMPLINENTATION Rf7tARKS
_:==== e====.========= ==================== =========== =. ===== === === === ==== ====================== ======== ====================== ====== ==== - = =
36.00 FSAR DESIGN CRITERIA, IEEE 484 -1975 (FSAR X X 06-22-87 DC-1000-E, REV. 6 05-21-87 GD - A-30. REV. 13 REGULA1 DRY GUIDES 8.1.4.3) 8-29-85. PG. 15, 11-26-86
- 8. 1. 4. 3 AND IEEE STANDARDS - DC-1806 REV. 5, ED -T-04, REV. 9 INDEPENDENCE OF 8-23-85. IXI.2 1-6-86 CLASS lE EQUIINENT ED -T-09, REV. 6 AND CIRCUITS 5-19-86 X3AR01-E2, REV. 16, 3-13 86 37.00 FSAR DESIGN OF NATIONAL BUREAU OF X 06-22-87 DC-1826, REV. 1 TRANSMISSION LINE STANDARDS HAND 800E 9-18-78
- 8. 2. 1. I ' STRUCTURES FOR NO. 8 (NATIONAL OFF3tTE SOURCES ELECTRICAL SAFETY CODE PART 2) (FSAR 8.2.1.1) 38.00 FSAR CAPACITY OF OFFSITE OFFSITE IUfER SYSTEM X 06-22-87 DC-1801,REV.3,7-19-83 SOURCES IIAS THE CAPACITT AND 00.4 P. 2. 1. I CAPABILITY TO SUPPLY
. TifE POWER NECESSARY
'FOR THE SAFETY IhADS OF ONE IINIT WHII.E PLACING THE OTHER UNIT IN COLD SHUTDOWN (73AR 8.2.1.1) 41.00 FSAR CONIDff4ANCE TO 10CFR50, APP. A, GDC X 06-22-87 SEE REMARKS SEE REF. No. 2 CRITERIA (OFFSITE 4 (FSAR 8.2.2.4)
- 8. 2. 2. 4 POWER SOURCES) 42.01 FSAR CONF 0HMANCE 10 10CFR50, APP. A GDC X 06-22-87 DC-1000-E.REV.6,8-2F 8 CRITERIA - 0FFSITE 17 (FSAR 8.2.2.4) 5,C.S.,DC-1801 REY.3,7 H, 2. 2. 4 ELECTRIC POWER 83 C.S..DC-1804 RE SYSTEMS V.S.10-2-85,C.S..DC-18 05,REV.5,8-6-85,C.S.,D C-1806 NEV.6,7-28-85,C
.S. DC-1809,REV.4.1-21
-82.C.S. DC-1815, REV.2
,5-t8-83,C.S.
Paste No. 10 12/0:t/H7 Pl. ANT V0GTI.E tfNIT 2 f1FADINESS REVIEW PlFCIf AM IMPLFMENTATION MATRIX - MODill.E 06
= = = = - = = = = = = = = - = - - = = = = = = = = = = - = =
DESIGN CONST REF. SOURCE AND DES CON CURRENT DESIGN CURRENT CONSTRUCTION NittIIER SECTION StfBJECT DOClHENT/ FEATURE IGN ST. AS OF: IMPIIMENTATION AS OF: IMPIFffENTATION IGNARKS
- . - =====-- ==== == == =======- ======= == ======== m ====== === === ======== ========= ============ ======== ====================- == ==- ====== ===-
42.02 FSAR CONF 0lNANCE TO 10CFR50, APP. A, CDC X 06-22-87 DC-1823 REV. 3 CRITERIA - OFFSITE 17 (FSAR 8.2.2.4) 2-3-81, C.S., DC-1826,
- 8. 2. 2. 4 El.ECTRIC POWER REV. I, 9 18 -78, C.S. ,
SYSTEMS DC-1009, REV. 2, 6-3-83 C.S. 42.03 FSAR CONFDINANCE 10 10CFR50, APP. A. GDC X 06-22-87 DC-1816,REV.3,9-3-85,C CRITERIA - 0FFSITE 17 (FSAR 8.2.2.4) .S..DC-1821. REY.5.5 8. 2. 2. 4 ELECTRIC POWER 83.C.S. SYSTEMS 43.00 FSAR CONFOINANCE TD 10CFRSO, APP. A. GDC X 06-22-87 SEE REMARKS SEE REF. NO. 4 CRITERIA (OFFSITE 18 ( FSAR 8.2.2.4)
- 8. 2. 2. 4 NWER SOURCES) 41.00 FSAR STANDARDS AND GUIDES ANSI C37.010-1972 X 06-22-87 DC-1000-E.REV.6,8-29-8
- AC HIGH VOLTAGE (FSAR 8.2.2.5.8) 5 N.3,DC-1804, REY.5.1
- 8. 2. 2. 5.B CIRCUIT BREAKERS 0-2-85,0G.I.DC-1825 RE V . 2,9 85, N .1. DC - 18 26, REV.1,9-18-78, N. I 15.00 FSAR STANDARDS AND GUIDES ANSI C37.90-1971 X 06-22-87 DC-1000-E. REY.6,8 8
- RELAYS AND REl.AY (FSAR 8.2.2.5.C) 5,PG.4,DC-1804,REV.5.1 H. 2. 2. 5.C SYSTEMS 0-2-85 N.2 DC-1805,RE V.5,8-6-85 M.2.DC-180 7,REV.3,8-23-85,N.I.D C-1816,REV.3,9-3-85 PG
.2 46.00 FSAR STANDARDS AND CUIDES ANSI C57.12.00-1973 X 06-22-87 DC-1000-E,REV.6,8-29-8 DC-1802 REFERENCES
- GENERAI. (FSAR 8.2.2.5.D) 5, N. 4, DC- 1801, REV. 3,7 THE C57 SERIES
- 8. 2. 2. 5.D REQUIREMENTS FOR 83.PG.I.DC-1802,RE DISTRIBUTION, POWER, V.1,ll-7-80,DC-1805,RE REGULATING V. 5,8 85, N.1,0C- 180 TRANSFOINERS, AND 7,REV.3,8-23-85.N.I.D SifDNT REACTORS C-1826,REV.1,9-18-78,P G.1 O O O
Para No, 1I e IL O3/87' Pl. ANT V0GTLE UNIT 2 READINESS REVIEW PIKK; RAM IMPLEMENTATION MATRIX - PODULE 06
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DESIGN CONST REF. SOURCE AND DES CON CURRENT DEstGN CURRENT CONSTRtlCTION l NtHHER SFCTION SUBJECT DOCilMENT/ FEATURE IGN ST. AS OF: IMPLEMENTATION AS OF: IMPLEMENTATION RIMARKS
====== =============== ====== ============= ==e================= === === ======== ====================== ======== ====================== ==,== === =e======
53.00 FSAR DESIGN CRITERIA FOR ANSI C37.010 - 1972 X 06-22-87 SEE REMARKS SEE REF. No. 44 CLASS IE EQUllNENT - (FSAR 8.3.1. I.8.G)
- 8. 3. l. 1. SWITCHGEAR MEDItN 8.G VOLTAGE SHORT CIRCUIT INTERRUPTING CAPACITY 54.00 FSAR DESIGN CRITERIA FOR ANSI C37.06-1971 X 06-22-87 DC-1000-E,REV.6,8-29-8 CLASS IE EQUllNENT - (FSAR 8.3.1.1.8.G) 5,FG.3.DC-1804, REY.5.1 !
- 8. 3. 1. l. SWITCHUEAR HIGII 0-2-85 PG.I.DC-1825,RE H.G VOLTAGE SHORT V.2,9-24-85,tu.1 CIRCUIT INTERRUPTING -
CAPACITY 55.00 FSAR DESIGN CRITERIA POR ANSI C37.13-1973 X 06- 22-87 DC-1000-E,REV.6,8-29 -8 CLASS IE EQUlfMENT - (FSAR 8.3.1.1) 5,FG.3 DC-1805, REY.5,8
- 8. 3. 1. 1 SWNETRICAL SHORT 85,P0.1 CIRCUIT INTERRUPTING CAPACITY 56.00 FSAR DESIGN CRITERIA FOR NEMA AB l-1975 (FSAR X 06-22-87 DC-1000-E.REV.6,8-29-8 CLASS IE EQUIINENT - 8.3.1.1.8) 5 PG.8.DC-I805,REV.S.8 !
- 11. 3 . 1. 8 SDNETRICAL SHof?T 85,00.12,DC-1806 RE CIRCUIT CURRENT FOR V. 5,8 85. PG . 2, DC- 18 MOLDED CASE CIRCUIT 07, REY.3,8-23-85,PG.1 i BREAKERS [
63.00 ISAR NESIDUAL HEAT IEEE 323-1974 (FSAR X 06-22-87 SEE REMARKS SEE REF. NO. 29 REMOVAL ISOLAT10:1 8.3.1.1.)
- 8. 3. 1. I VALVE IVWER SUPPLY l 1
64.00 FSAR RESIDUAL HEAT IEEE 341-1975 (FSAR X 06-22-87 SEE REMARKS SEE REF. No. 32 < REMOVAL ISOLATION' 8.3.1.1)
- 8. 3. 1. I VALVE POWER SUITLY H2.00 FSAR CABLE ROUTING - WITHIN PANELS AND X X 06 87 DC-1000 E. REV. 6, 05-21-87 X3AR01-EH, REV. 24 SILE REF. NO. 35.
CABLE SEPARATION CONTROL BOANDS, 6 8-20-85, N. 26, 2-11-87 USE OF ANALYSIS
- 8. 3. 1. 4. 3 WITilIN PANELS AND 'IN. MINIMlH SPATIAL DC-1816. REV. 3, X3AR01-E9, REV. 19 (WYLE LADS) ADDED CONTROL BOARDS SEPARATION OR 9-3-85 PG. 7 2-5-87 BY AMENUMENT 25.'
BARRIERS ARE ED - 0 09. REV. 9 PROVIDED BE1 WEEN 7-31-f16 COPWVNENTS OR CABLES - OF DIFFERENT SEPARATION GROUPS OR ANALYSIS IS PERFOINED (FSAR 8.3.1.4) l l
l'.ig No. 12 12/n1/87 l'l ANT V0GTIE UNIT 2 RE ADINFSS REVIFW IHOGRAM IMI'11NENTATION MATRIX - MODULE 06
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DESIGN CONST DES COM CURRENT DESIGN CURRENT CONSTRUCTION REF. SOURCE AND IGN ST. AS OF: IMPl.FNENTATION AS OF: IMPIEMENTATION REMARKS Ntt1BER SECTION SUB.IECT DOCUPfENT/ FEATURE
===========tm===~=
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k NO SIIARING OF ONSITE 10CfR50, APP. A, GDC X 06-22-87 SEE REMARRS SF:E REF. NO. 3 fil.00 PSAR ITMER SYSTEMS 5 (FSAR 8. l .4.2. E)
- 8. 1. 4. 2.E PE1MEEN UNITS DESIGN CRITERIA, 10CFR50 APP. A. GDC X 06-22-87 DC-1000 E.RV.6,8-29 85 DC-1010 APPLIES fl5.00 FSAR DC-1005 CRITERIA REGULATORY GUIDES 2 (FSAR 8.1.4.3) ,CS.DC-180G.RV.5,8 R5,CS .DC- 1816, RV . 3,9-- 3 TO CAT. I
- 8. 1. 4. 3 AND IEEE STANDARDS -
DESIGN BASES FOR -85,CS.DC-1818,RV.3,8- EIICTRICAL PROTECTION AGAINST 22-85,CS.DC-1821,RV.5, EQUllitENT. SFE 5-2-83 CS.DC-1005,HV.1 RHF 6-56 AND 6-61 NATURAL PitENNIENA c 4-4-83 CS.DC-1010,RV. 5.2-7-86,0GS.90-91 DC-1001 RV.3,8-23-83,CS _ IEEE 323 (FSAR X Ofr22-87 SEE REMARKS SEE REF. NO. 29 tlG.00 FSAR AC POWER SYSTEMS CLASS IE 8.3.l.l.2.E)
- 8. 3. 1. 1. QUALIFICATION-INTERC 2.E ONNECTIONS 06-22-87 SEE REMARKS SEE REF. No. 32 117. 00 FS AR AC POWER SYSTEMS IEEE 341 (FSAR X CLASS IE 8.3.1.1.2.E)
- 8. 3. I.1. 2. QUALIFICATION -INTERC E ONNECTIONS RG 1.75 (FSArt 06-22-87 SEE RFNARKS SEE REF. NO. 18 fHi 00 FSAR AC POWER SYSTENS X CLASS IE 8.3.1.1)
- 8. 3. l. I INTERCONNECTIONS 06-22-87 SEE HENARKS SFE REF. NO. Il T1.00 FSAR AC POWElf SYSTEM RG 1.32 (FSAR X Cl. ASS lE -SRARING OF 8.3.1.1)
- 8. 3. l. I SYSTEM BE1 WEEN UNITS AC IWER SYSTEM, 06-22-87 SEE REMARKS SEE REF. NO. 19 100.00 FSAR RG l.81 (FSAR X CLASS lE SilARING OF 8.3.1.1)
- 8. 3. 1. 1 SYSTEMS BETWFFN UNITS AC IWER CONTAINtfENT 10CFR50 APP. A, GDC X 06 22-87 SEE RENARKS SEE REF. No. 5 101.00 FSAR ELECTRICAL 50 (FSAR 8.3.1.1)
II. 3. 1. I PENETRATIONS O O O
Page No. 13 12/01/H7 PLANT VtXITIE tHIT 2 READINESS REVIEW PROGRAM IMPLEMENTATION MATRIX - MODUIE 06 j
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DESIGN CONST REF. 50tfRCE AND DES CON CURRENT DESIGN CURRENT CONSTRUCTION NIHi1ER SFCTION SUBJECT DOCIMENT/ FEATURE IGN ST. AS OF: IPFLEMENTATION AS OF: IMPLEMENTATION REMARKS s=== == ==== ========== ==================== ==================== === === ======== ====================== ======== ============== ====e== ================== 100.00 PSAR SINGLE FAILtmE, IEEE 279-1971 (FSAR X 06-22-87 SEE RDIARKS SEE REF. NO. 26 REDUNDANCY & l.2.12.1)
- 1. 2. 12. 1 INDEPENDENCE CRITERIA 126.00 FSAR SEISMIC DESIGN EG 1.29 REV. 3, X 06-22-87 SEE RINARKS SEE REF. NO. 9 CLASSIFICATION 9/78 (FSAR 1.9.29)
- 1. 9. 29 131.00 FSAR CRITERIA FOR RG 1.32, REY. 2, X 06-22-87 SEE RDtARKS SEE REF. NO. 11 SAFETY-RELATED 2/77 (FSAR 1.9.32)
- 3. 9. 32 ELECTRIC IWER SYSTEMS FOR NUCLEAR I IWER PLANTS i 132.00 FSAR CRITERIA FVR IEEE 308-1974 (FSAR X 06-22-87 SEE REMARKS SEE REF. NO. 27 f
SAFETY-RELATED 1.9.32)
- 1. 9. 32 ELECTRIC I M ER I SYSTEPt3 FOR NUCLEAR POWER PLANTS 133.00 FSAR CRITERIA FOR 10CFR50, APP. A. GDC X 06-22-87 SEE RENARKS SEE REF. NO. 42 ,
SAFETY-RELATED 17 (FSAR 1.9.32)
- 1. 9. 32. 1 El.ECTRIC POWER SYSTEMS FUR NUCLEAR F0WER PLANTS 134.00 FSAR CRITERIA FUR 10CFR50, APP. A. GDC X OG-22-87 SEE RfMARKS SEE REF. NO. 4 S A FETY-RELATED 18 (FSAR 1.9.32.1)
- 1. 9. 32i ! ELECTRIC POWER t SYSTEMS FOR NUCLEAR POWER PLANTS - >
INSPECTION AND I TESTING OF ELECTRIC IWER SYSTEMS 157.00 FSAR PENETRATION RG 1.63. REV. 2, X 06-22-87 SEE REMARKS SEE REF. NO. 17 ASSEMBLIES 7/78 (FSAR I.9.63) 1.-9. 63 i
l l'nre- No. 11 12/01/H7 FLANT V0GTIE UNIT 2 READINESS REVIEW Fif0 GRAM IMP!EMENTATION MATRIX - MODULE 06 ! =============== =============r==,==- DESIGN CONST REF. SOURCE AND DES COM CURRENT DESIGN CURRENT CONSTRUCTION
- Nttif1ER SECTION SUBJECT DoctNENT/FEAftrRE IGN ST. AS OF
- IMPLINENTATION AS OF: IMPLfMENTATION RfMARKS
==== - -===,========== ============== ===== ==================== === === ======== ====================== ======== ===================-== ==================
- IfdLOO FSAR I'tIYSIC AL RG 1.75 REV. 2, X X 06-22-87 SEE REMARKS SEE REMARKS SEE REF. NO. 18
! INDEPENDENCE OF 9/78 (FSAR 1.9.75) FOR DESIGN, SEE
- 1. 9. 75 ELECTRIC SYS19tS REF. NO. 35 FUR CONST.
171.00 FSAR S!!ARED EMEftGENCT AND RG 1.81 REV. 1, X 06-22-87 SEE REMARKS SEE REF No. 19 l SifUTDowN SYSTEMS FOR 1/75 (FSAR 1.9.81) l 1. 9. 81 MULTI-trNIT NIX' LEAR l IVWER PLANTS 172.00 FSAR QUALIFICAfl0N FUR RG 1.89 REV. O, X 06-22-87 SEE REMARKS SEE REF. No. 20 CLASS IC EQUIIMENT 11/74 (FSAR 1.9.89)
- 1. 9. 89 l 173. 00 FS AR QUALIFICATION FOR IEEE 323-1974 (FSAR I 06-22-87 SEE REMARKS SEE REF. NO. 29
! CLASS IE EQUlfMENT 1.9.89.1)
- 1. 9. 89. I 171.00 FSAR CMtBINING MODAL RG 1.92, REV. 1 X 07-15-87 DC-1000-E.REV.6,8-29-8 DC-1010 AITLIES RESIVNSES AND 2/76 (FSAR I.9.92) 5,PG.17,DC-1005,REV.I. DC-1005 CRITERIA I. 9. 92 SPATI AL COMIVNENTS 4-4-83,C.S..DC-1010,RE 10 CAT. I IN SRISMIC RESTVNSE V.5,2-7-86,IUS.90-94,A ELECTRICAL ANALYSIS ITENDIX 10 SPEC EQUIINENT
'QG',REV.0,00.OG-2 175.00 FSAR SEISMIC RG l.100 REV. I, X 06-22-87 SEE REMARKS SEE REF. NO. 22 QUALIFICATION OF 8/77 (FSAR l.9.100)
! 1. 9.100 CLASS IE ELECTRIC EQUIINENT 177 00 FSAR TREINAL 0"ERIDAD RG 1.106, HEV. I, 06-22-87 SEE REMARKS SEE REF. No. 23 FROTECTION FON 3/77 (FSAR 1.9.106)
- 1. 9.106 EIECTRIC MOTORS ON MOTOR OPERATED VALVES.
IR2.00 FSAR INSTALLATION DESIGN IFI l . P8, REV. 1 X 06-22-87 SEE REMARKS 05-21-87 SEE REMARKS SEE REF. NO. 24 AND INSTALLATION OF 10/78153AR l.9.128)
- 1. 9.128 LARGE LEAD STURAGE BATTERIES O O O
l' age No. 15 12/01/H7 Pl. ANT VOGTIE UNIT 2 READINESS REWlEW PROGRAM IMI'LEMENTAT10N MATRIX - MODUIE 06
==== =-= ===u === =#===r== = == = =
DESIGN CONST REF. SOURCE AND DES CON CURRENT DESIGN CURRENT CONSTRUCTION NtttilFR SECTION SUltfECT D0ctffENT/FFATifRE IGN ST. AS OF: IMPIEMENTATION AS OF: IMPlfBENTATION HINARKS
-=~u a- - ==----== == =====u n-, r ~ = ====== ========== == :-- == === ==r- ======-,=---=-=,===========,=-=====--=~===========u----=,==:=-
2fL1.00 FSAR DESIGN RASES INI ACTION ITDI I 06-22-87 DC-1217 5.0 ITIN 12 II.K.3.25 REY. 1, 3-9 83
- 5. 4. 1. I FJE.00 SSAR Q. A. REQUIRD,dNTS RG 1.30, 8/72 ( FS AR X X 06-22-87 SEE RENARKS 05-21-87 3EE REMARKS SEE REF. NO. 10 FOR INSTALL., INSP., 1.9.30) FUR DESIGN, SEE I. 9. 30 & TESTING OF REF. No. 31 50R INSTRINENTATION & CONSTRtCTf0N ELECTRIC EQUIINENT IJ17. 00 IS AR O.A. REQUIREMENTS ANSI N15.2.4-1972 X X 06-22-87 SEE RENARKS 05-21-87 SEE RDIARKS SEE REF. No. 31 FOR INSTALL., INSP., (IEEE 336-1971)
- 1. 9. 30 & TESTING OF (FSAR 1.9.30.1)
INSTRtNENTATION & EIECTRIC EQUIIMENT F+HH.00 FSAR Q.A. REQUIRDIENTS IEEE 336-1971 (FSAR X X 06-22-87 SEE RDIARKS 05-21-87 SFE RIHARKS SEE REF. NO. 31 FOR INSTALL., INSP., 1.9.30.1)
- 1. 9. 30 & TESTING OF INSTRtHENTATION &
ELECTRIC EQUIIHFNT 751.00 TSAR QUALITY ASSURANCE RG l.30, 8/11/72 X X 06-22-87 SEE REMARKS 05-21-87 SEE RFMARKS SEE REF. NO. 10 REO. FOR INST. AND (FSAR 17. A.1) AND NO. 31 17A. I INSP. OF ELECT. EQUIP. H35.00 FSAR SEISMIC RG. 1.29-NOTE (c) X 06-22-87 SEl* RDIARKS SEE REF. NO. 9 CLASSIFICATION OF (FSAR 3.2.2-1)
- 3. 2. 2-1 STRtCTURES, CtNfDNENTS, SYSTD13 Hitt.00 FSAR REDUNDANCY AND OFFSITE POWER X 06-22 87 DC-1000-B.REV.6,8-29-8 SEPARATION OF EQUI M NT 15 5,00.20,DC-1801. REY.3,
- 3. 2. 2-1 0FFSITE IUWER SYS. DESIGNED AND 7-19-83,IV.I.DC-1815,R ARRANGED TO PROVIDE EY.2.5-18-83.PG.1,DC-1 REDUNDANCY AND 826,REV. l 9-I8 -78 PG.1 SEPARATION FOR INCREASED RELIABILITY (TABl.E 3.2.2-1, NOTE n, 511.
95) e
l' arf No. IG 12/0t/li7 l'I ANT WOGTI E UNIT 2 READINESS REVIFW l'ROGRAM IMPLD1ENTATION MATHlX - MODULE 06
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DESIGN CONST DES CON CURRENT DESIGN CUHHENT CONSTRtCTION IIEF. SOURCE AND RD1 ARKS IKCINENT/ FEATURE IGN ST. AS OF: IMPI D1ENT ATION AS OF: IMPIU1ENTATION NIMDER SECTION SUBJECT ============= === ========== ===
- == == =-- = =====-= ==,=========-======= ==================== === === ======== ============-========= ======== =====.=2 06-22-87 DC-1005,REV.I.4-4-83,C DC-1010 APPLIFS 901.00 FSAR SEISHIC DAMPING ffG l.61 (FSAR X DC-1005 CRITERIA 3.7.B.1.3) . S . , DC- 1010, REV . 5. 2 VALUES FOR ITEMS TO CAT. I
- 3. 7.B. 1. 3 OTHER THAN CABLE 86,IUS.90-94 ELECTHICAI.
TRATS AND SUPIURT EQUlltfENT SYSTD1 X 06-22-87 SEE REMARILS SEE REF. NO. 32 1016.00 FSAR THREE C(NPONENTS OF IEEE 344-1975 IVR EART10UAKE HOTION OUALIFICAtl0N BT
- 3. 7.B. 3. 6 TESTING. (FS AR 3.7.B.3.6) 06-22-87 DC-1818, REV. 3, SEE RiiF 6-34 1813.00 ISAR DESIGN OF ELECTRICAL ASME 111, 1977 X PENETRATION TilHOUGli StPf ?ER 1979 8-22-85, PG. I
- 3. 8. 2. 4. 3 ASSDtBLIES ADDENDA (FSAR 3.8.2.4.3)
X 06-22-87 SEE REMARKS SEE REF. NO. 1113 1117.00 ISAR EIECTRICAL El.ECTRICAL l'ENRTRATION - IENETRATION IDADING
- 3. R. 2. H STANDARD REVIEW PLAN COM!ilNATIONS DIFTER EVALUATION FROM STANDARD REVIEW PLAN. (FSAR 3.8.2.H)
SEISMIC- THE OBEs X 06-22-87 SPEC. AITENDIX '0G', ll!N.00 ISAR MEANS OF SEISMIC QUAI.lFICATION SHALL CONTAIN A REV. 0 3.10.B. 2. 1 MINIMIM OF 50c 0F MAXIMIM 8 TRESS (FSAR 3.10.B.2.1) b 06-22-87 SEE RD1 ARKS SEE REF. No. 32 1202.00 FSAR SEISMIC QUAL. AND IEEE 344-1975 (FSAR X DOCINENTATION FOR 3.10.B.1) 3.10.B. I SAfETT RELATED EQUIP. AND StlPIURTS. 06-22-87 SEE RDtARMS SEE REF. NO. 22 1203.00 FSAR SEISMIC RG 1.100 (FSAR X OUAI.lFICATION AND 3.10.B.1) 3.10.B. I DOCtMENTATION FOR SAFETY RELATED FQUIP., AND SU" PORTS O O O
O O O Iwge Nn. 17 12/03/187 Pt. ANT VOGTI.E ITNIT 2 RFADINESS REVIFW PROGRAM iMPIEMENTATION MATRIX - MnDUI.E 06
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DESIGN CONST REF. SoflHCE AND DES CON CURRENT DESIGN CtniRENT CONSTR1CTION NtNitER SECTION SUBJECT DOCtNENT/ FEATURE IGN ST. AS OF: IMPLEMENTATION AS OF: IMI'IENENTATION REMARKS
,1 ==== = = = = = = = = = = = = = , = =========== == ===== ==== =============== === === === ==== ====================== ======== ======,=============== ===-==============
1206.00 FSAR MEANS OF SEISMIC IEEE 314-1975 (FSAR X 06-22-87 SEE RINARKS SEE REF. No. 32 QUALIFICATION OF 3.10.B.2.1) 3.10.B. 2. I MEClf. & ELECT. EQUIP. 1207.00 FSAR MEANS OF SEISMIC RG 1.100 (FSAR X 06-22-87 SEE REMARKS SFE REF. NO. 22 QUALIFICATION OF 3.10.B.2.1) 3.10.B. 2. I MECII. & EI.ECT. EQUIP. 1210.00 FSAR MEANS OF SEISMIC SEISMIC-ALL X 06-22-87 CPEC. APPENDIX 'OG', QUALIFICATION INTERFACES AND TIIE REV. 0 3.IO.R. 2. I EFFECTS OF TIIE ~~ AMPLIFICATION WITRIN TifE EQUIIMENT DUE TO Tite INTERFACES AND SUI'IVRTING STRUCTURES ARE . CONSIDERED IN Tite SEISMIC QUALIFICATION. (FSAR 3.10.B.2.1) 1213.00 FSAR MEANS OF SEISMIC PG 1.100 (FSAR X 06-22-87 SEE REMARKS SEE REF. NO. 22 QUALIFICATION 3.10.B.2.2) 3.10.H. 2. 2 TESTING BY MULTI-FREQ. OR SINGLE FREQ. INPl!TS 1215.00 FSAN METilOD OF SEISMIC IEEE 311-1975. SECT. X 06-22-87 SEE REMARKS SEE REF No. 32 QUAL. 5 (FSAR 3.10.B.2.2) 3.10.R. 2. 2 ANALTSIS W/0 TESTING 1216.00 FSAff ANALYSIS METil0D OF SEISMIC-WIIEN AN X 06-22-87 SEE REMARKS SEE REF. NO. 32 SEISMIC EQUIVALENT STATIC 3.10.R. 2. 2 00ALIFICAT10N COEFFICIENT ANALYSIS IS l'ERFORMED. JUSTIFICATION F0ft ITS tiSE IS PROVIDED BY Tile SUPPLIER (FSAR 3.10.B.2.2) j
7 Page No. lit 12/0.1/87 l'LANT V0GTIE !! NIT 2 IIEADINESS liEVIEW PIMX; RAM IMI't.DfENTATION MATHlX - 79)DillE 06 mm- ::::: :: :== e ------ e--- :: DFSIGN CONST REF. SOUllCE AND DES CON CURRENT DESIGN CUliRENT CONSTRLUTION NttilGR SECTION SUBJFCT IXX'tNENT/ FEATURE IGN ST. AS OF: IMI'LDfENTATION AS OF: IMPIDfENTATION RFMARKS -- .- - ----- -- -- : : - :: - :--- :::::--: ::::=-:::::===:::::- :: :: :::::::: :::= ::===: :==- : e:: ::====:: ==-- : : 2:--- =- re-- ::::: - - :: -- e - -- 1217.00 FSAR COPmlNED ANALYSIS IEEE 344-1975 X 06-22-87 SEE RD1 ARKS SEE REF. NO. 32 AND TEST METIR)D OF SECTION 7 (FSAR 3.10.B. 2. 2. 3 EQUIP. QUALIFICATION 3.10.B.2.2.3) 1219.00 FSAR MET 110D OF SEISMIC IEEE 323 -1974, SECT. X 06-22 .7 SEE RIMARKS SEE REF. NO. 29 OliALIFICATION TEST 6 (FSAR 3.10.B.2.4) 3.10.B. 2. 2. 4 SEQl!ENCE VERIFICATION I220.00 ISAR METil0D OF SEISMIC IEEE 314-1975. SECT. X 06-22-87 SEE RDtARKS SEE REF. No. 32 QUALIFICATION 6 (FSAR 3.10.B.2.2) 3.10.B. 2. 2. 2 TESTING 1228.00 FSAR QUALIFICATION AND RG 1.100 (FSAR X 06-22-87 SEE RENARNS SEE REF. NO. 22 DOCINENTATION 3.10.B.4.1) 3.10.B. 4. I rixx:EDURES FY)H ELECTRICAL EQUlINENT 1229.00 FSAR Qt!ALIFICAtl0N AND IEEE 344-1975 (FSAR X 06-22-87 SEE RDtARKS SFR REF. No. 32 DoctNENTATION 3.10.B.4.1) 3.10.B. 4. I PROCEDURES FOR El.ECTRICAL EQUlINENT I231.00 FSAR STANDARD REVIEW FLAN BC-11)P-4 A (FS AR X 06-22-87 SEE RDIARKS SEE REF. NO. 174 EVALUATION-EQUIP. 3.10.B.4.2) 3.10.B. 4. 2 SEISMIC QUA L. -MULTI- MOD A L RESIVNSES 1262.00 FSAR ACCEPT. CRIT. ENV. IRI 1. 89 ( FS AR X 06-22-87 SEE REMARKS SFR REF. NO. 20 offal. SAFETY RELATED 3.11.B.2) 3.II.B. 2 EQUlINENT
!2G3.00 FSAR QUALIFICATION TESTS IEEE 323-1974 (FSAR X 06-22-117 SEE RFNARKS SEE REF. NO. 29 AND AN4 LYSES. TYPE 3.11.B.2) 3.II.B. 2 TESTIMI.
1261.00 FSAR OllALIFICATION TESTS INI 1.100 (FSAR X 06-22 (17 SEE REMARKS SEE REF. NO. 22 AND ANALYSES - 3.II.B.2) 3.II.B. 2 SEISMIC OtlALIFICATION OF EIECTRICAL E0lillHENT O O O
A
~ - O Page No. 19 12f01/H7 Pl. ANT VuGTI.E ITNIT 2 READINESS REvilli Pff0 GRAM IMPLFMENTATION MATRIX - MODULE 06
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DESIGN CONST REF. SotHfCE AND DES CON CURRENT DESIGN CtHIRENT CONSTRIK' TION Nttif4R SECTION SUll3ECT IMrtMENT/FEATtfRE IGN ST. AS OF: IMPIDfENTATION AS OF: IMPII}tENTATION RFNARKS
=-- = === =========== ============== ===== ======= ============ === === ======== ============ ========= ======== ====================== === ===========- =
126H.00 FSAR QUALIFICATION TESTS IEEE 323-1974 (ISAR X 06-22-87 SEE REMARKS SEE REF. NO. 29 AND ANALYSES. 3.II.B.2) 3.II.B. 2 ACCEPT. CRIT. IOR ENV. QUAL. SAFETY REL. EQUlINENT 1269.00 FSAR ACCEPTANCE CRITERIA NUREG 05R8 (FSAR X 06-22-R7 DC-1000-E REY.6.8-29 8 FOR ENVIRONMENTAL 3.ll.B.2.) S, ft.18. DC-1805,RE Y. S. 3.11.B. 2 QUALIFICATION OF 8 6-85,IM.9,DC-1818,RE EOUllNENT V.3,8-22-85 PG.1.DC-10 07.REV.6.3-24-86,PG.1 DC-10l0.REV.S 2-7-86 1191.00 FSAR SINGLE FAILURE, IEEE 279-1971 X 06-22-87 DC-1009. REV. 2 REDUNDANCY AND 6-3-83
- 1. 2. 12. 1. INDEPENDENCE 2.L CRITERIA 1503.00 FSAR BATTERY SIZING BATTERIES SIZED TO I 06-22-87 DC-1806 REV.5,8-23-85 PROVIDE DC POWER IVR IV.5
- 1. 3. 2 -1 2 3/4 IIOUR a SS DEGREES F (FSAR 1.3.2-1) 1551.00 FSAR APPLICATION OF RG 1.53. REY. O, X 06-22-87 SEE REMARKS SEE REF. NO. 15 SINGLE FAILUliE 6/73 (FSAR 1.9.53)
- 1. 9. 53. 2 CRITERION 1601.00 FSAR INDEPENDENCE BETWEEN RG 1.6 REV. O, 3/71 X 06-22-87 SEE RD4 ARKS SEE REF. NO. 6 REDUNDANT STAND-BY (FSAR 1.9.6)
- 1. 9. 6. 2 (ON-SITE) 00WER SOURCES AND THEIR DISTRIBUTION SYSTEM 1602.00 FSAR PERIODIC TESTING OF RG 1.22. REV. 0 X 06-22-87 SEE RdMARKS SEE REF. NO. R PROTECTION SYSTEM (FEB. 72) EXCEPT AS
- 1. 9. 22 ACTUATION filNCTIONS INDICATED IN FSAR SECTION l.9.22.2 AND 7.1.2.5 (73AR I.9.22)
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ .__ __ _ _ _ _ _ _ . _ _ _ _ _ __. _ ___ _ _ _ _. J
T Par.e No. 20 12/03/R7 I*I ANT YOGTIS UNIT 2 READINE - 7tEW PIRMIRAM IMPIDtENTATION MATRIX Mr.dE 06
= = .= ========== = === ====
DESIGN CONST DES CON CURRENT DESIC* CL'RRENT CONSTRUCTION REF SOtmCE AND R! NARKS St'BJECT DOClHFNT/FEATimE IGN ST. AS OF: IMPIFNr.N RATION AS OF: IMPIEMENTATION NitfPFR SECTION
-=======-============================-=================1== === === ======== ====================== ======== ======= ====== ======= ====-== ==========
RG l.106/IEEE 06-22-87 SEE REMARKS SFE REF. NO. 23 1610.00 FSAR TliFINAL OVERIDAD X PROTECTION FOR 279-1971 SECTION
- 1. 9.106 ELECTRIC MOTORS ON 4.1, 4.2, 4.3, 4.4, MOTOR OPERATED 4.5, 4.10 AND 4.13 VALVE. (FSAR I.9.106) 06-22-87 SEE REMARKS SEE REF. NO. 1113 1978.00 FSAR EIECTRICAL ASME 111 (FSAR X PENETRATION - LOAD & 3.8.2.3)
- 3. 8. 2. 3 IDAD COMBINATION, CLASS MC ITEMS 1981.00 FSAR ELECTRIAL RG 1.57 (FSAR X 06-22-87 DC-1000-E.REV.6,8-29-8 FENETRATION - IDAD 3.8.2.3) 5,0G.17,DC-1818, REY.3,
- 3. 8. 2. 3 AND IDAD 8-22-85,C.S.
COMBINATIONS 06-22-87 SEE REMARKS SEE REF. No. 1113 1991.00 FSAR ELECTRICAL ASME Ill (FSAR X i PENETRATION - 3.8.2.6)
- 3. 8. 2. 6 MATERIALS l
10CFR50, APP. J. X 06-22-87 SEE REMARKS SEE REF. NO. 1113 I W1.00 FSAR ELECTHICAL PENETRATION -
- 3. 8. 2. 7 TESTING 06-22-87 SEE REMARKS SEE REF. NO. 1113 l!nt.00 FSAR ELECTRICAL ASME III (FSAR X PENETRATION - CLASS 3.8.2.8)
- 3. B. 2. 8 MC ITEMS, LOAD &
IDAD CCHBINATION 06-22-87 SEE REMARKS SEE REF. NO. 1981 1995.00 FSAll ELECTRICAL RG 1.57 (FSAR X PENETRATION - CLASS 3.8.2.8)
- 3. 8. 2. 8 MC ITEMS, thAD &
LOAD COMBINATION 2007.00 FSAR SEISMIC SEISMIC CATEGORY I X 06-22-87 DC-1005, REY. I, QUALIFICATION OF SAFETY RELATED 4-4-83, PG. 3A, PARA. 3.10.B. I CATEGORY I MECliANICAL & 3.6.3 MECRANICAL & ELECTRICAL EQUllNENT EIFCTRICAL BOP IS QUALIFIED TO EQUIIMENT, CRITERI A WIfitSTAND TiiE EFFECTS OF SEISMIC LOADS REStTLTING FIMH OBE AND SSE (FSAR 3.10.B.1) O O O , J 1 _ _ _ 1
- i l' age No. 21 12/0.1/H7 l'LANT YOGTLE UNIT 2 READINESS REVIEW PHOGRAM IMPLEMENTATION MATRIX - MODUl.E 06
===e===.===-===e=== ======- =r==,===
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21HO 00 FSAR ONSITE POWER SYSTEM 10CFR50, APP. A CDC X 06-22-87 SEE RENARKS SFE REF. No. 42
- INDEPENDENCE 17 ( FSAR 8. l.4.2. A)
- 8. 1. 4. 2.A BETWEEN UNITS 21Hl.00 FSAR ONSITE 00WER SYSTEM BATTERIES ARE SIZED X 06-22-87 DC-1806 REV.5,8-23-85
- BATTERY SIZING FOR 165 MINUTES OF TV.ll H. 1. 4. 2.G OIERATION WITHOUT SUPPORT OF BATTERY CHARGERS (F3AR 8.1.4.2.G) l 2lHR 00 FSAR DAMPING VALUES IVR RG l.61, 10/73 (FSAR X 06-22-87 SEE REMARKS SEE REF. NO. 9BI SEISMIC DESIGN 1.9.61)
I. 9. 61 l 2319.00 FSAR AUX. FEEDWATER PHYSICAL SEPARATION X 06-22-87 DC-1302-3.1. lM REV. SYSTEM FHYSICAL (AUX. FEEDWATER 5, 4-18-83 10A. 2. 6 SEPARATION BENEEN SYSTEM) RG 1.75 ELECTRICAL COMIVNENTS. 2320.00 FSAR AUX. FEEDWATER I'HYSICAL SEPARATION X 06-22-87 DC-1000E-2.0.DI, REV. SYSTEM PHYSICAL (AUX. FEEDWATER 5, 8-29-85 10A. 2. 6 SEPARATION BEWEEN SYSTEM) IEEE 384 ELECTRICAL COPWVNENTS 2313.00 FSAR RCP OVERSPEED RCP OVERSITED-FOR X 06-22-87 DC-1825 REY. 2 CONSIDERATION TURBINE TRIPS BY 9-24-85 IV. 3
- 5. 4. 1. 3. 8 REAC10R TRIP SYSTEM OR TURBINE PROTECTION SYSYEM, GENERATOR AND RCP's REMAIN CONNECTED FOR 30 SECONDS (FSAR 5.4.1.3.8) 2352.00 FSAR DESIGN CRITTERIA, 10CFR50, APP. A GDC I 06-22-87 SEE RINARKS SEE REF. No. 42 REGULA1 DRY GUIDES 17 (FSAR 8.1.4.3)-
R. 1. 4. 3 .AND IEEE STANDARDS - ELECTRIC FOWER SYSTEMS __ _ - _ _ _ _ ____ ___ _ _ _ . _ _ _ _ _ _ - _ _ __ _ _ _ _ _ _ _ _ _ _ _ _______________-________________.___J
l',,g e Nrs. 22 12/OL H7 PL ANT V0GTI.E PNIT 2 READINESS REVIrw I'fMURAM IMFLDfENTATION MATRIX - PODULE 06
- :--- ================= = ========
DESIGN CONST REF. SolfRCE AND DES CON CURHENT DESIGN CURRENT CONSTRUCTION NittflFR SECTION Sl'BJ ECT DOClNENT/IE Af tHE IGN ST. AS OF: IMPLDfENTATION AS OF: IMPIEMENTATION RfMARKS
--- =:- =- : =- -====== ==,========== = ==== ==========-========= === === ======== ==================== = ======== ====================== ==================
2354.00 FSAR COMPLI ANCE WITH IM3 RG 1.118 (FSAR X 06-22-87 DC-1000-E,REV.6,8-29 8 l
& IEEE STANDARDS - 8.1.4.3) 5 N.18,DC-1804, REY.5, 1
- 8. 1. 4. 3 PERIODIC TESTING OF 10-2-85.C.S..DC-1806 R l P0hTH & PROTECTION EV.5,8-23 85,C.S..DC-1 I SYSTEMS 807,REV.3,8-23-85,C.S. l
.DC-1816,REV.3,9-3-85, C.S..DC-1818,REV.3,8-2 2-85,C.S..DC-I823,REV.
3,2-3-84,C.S. 2 ES.00 FSAR COMi'LIANCE WITH RG RG 1.129 (FSAR X OG-22-87 DC-1000-E.REV.6,8-29-8
& IEEE STANDARDS - 8.1.4.3) 5 N.18 DC-1806 REV.5,
- 8. 1. 4. 3 MAINTENANCE AND 8-23-RS.C.S. -
TESTING - PERIODIC BATTERY CAPACITY TESTS 2356.00 FSAR CCNPLI ANCE WITil RG IEEE 338-1977 (FSAR X 06-22-87 DC-ID00-E.NEV.6,8-29-8
& IEEE STANDARDS - 8.1.4.3) 5 N.14.DC-1806,REV.5, H. 1. 4. 3 PERIODIC TESTING OF 8-23-85,PG.I.DC-1807,R CLASS lE PROTECTION EV.3,8-23-85,PG.I.DC-1 STSTDt3 816 REV.3,9-3-85 N.3 23GO.00 FSAR ACCEPTANCE 10CFR50, APP. A. GDC X 06-22-87 SEE REMARKS SEE REF. NO. 95 CRITERIA / GUIDELINES 2 (FSAR 8.1-1)
- 8. 1-1 FOR ELECTRIC ITMER SYSTDts - DESIGN l BASES FOR PROTECTION AGAINST NATURAL l'!IENOMENA 23Gl.00 ISAR ACCEPTANCE 10CFR50, APP. A, GDC I 06-22-87 SEE REMARKS SEE REF. N0. 2 l
CRITERIA / GUIDELINES 4 (FSAR 8.1-1)
- 8. 1I IVR ELECTRIC ITMER SYSTDtS -
ENVIIONMENTAL AND MISSILE DESIGN RASES O O O
R U,R U O Page No. 23 12/03/87 PLANT V0GTI.E UNIT 2 READINESS REVIEW PROGRAM IMPLEMENTATION MATRIX - MODULE 06
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DESIGN CONST REF. SOURCE AND DES CON CURRENT DESIGN CURRENT CONSTRUCTION WlHDER SECTION SUBJECT DoctHENT/ FEATURE IGN ST. AS OF: IMPLEMENTATION AS OF: IMi'LEMENTATION REMARKS
-==e-== ========s==e=== ==================== ==================== === === ======== ====================== ======== ====================== ==================
2362.00 FSAR ACCEPTANCE 10CFR50. APP. A. GDC X 06-22-87 SEE REMARKS SEE REF. No. 3 CRITERIA / GUIDELINES S (FSAR TABLE 8.l-1)
- 8. 1-1 FOR ELECTRIC IMR SYSTEMS - SHARING OF STRUCTURES SYSTEMS.
AND COMPONENTS 23G3.00 FSAR ACCEPTANCE 10CFR50. APP. A. CDC X 06-22-87 SEE REMARKS SEE REF. NO. 42 CRITERIA / GUIDELINES 17 (IJAR 8.1-1)
- 8. 1-1 50R ELECTRIC POWER SYSTEMS 2361.00 FSAR ACCFETANCE 10CFR50. APP. A. CDC X 06-22-87 SEE REMARKS SEE REF. NO. 4 CRITERIA / GUIDELINES 18 (FSAR 8.1-1)
- 8. 1-1 FOR ELECTRIC POWER SYSTEMS - INSPECTION AND TESTING OF ELECTRIC TWER SYSTEMS 2365.00 FSAR ACCEPTANCE 10CFR50. APP. A. CDC X 06-22-87 SEE REMARKS SEE REF. No. 5 CRITERI AL/ GUIDELINES SO (FSAR B.1-1)
- 8. 1-1 FVR ELECTRIC POWER SYSTEMS -
CONTAINMENT DESIGN BASES 236G.00 FSAR ACCEPTANCE RG 1.6 (FSAR 8.1-1) X 06-22-87 SEE RINARKS SEE REF. NO. 6 CRITERIA / GUIDELINES
- 8. 1-1 FOR ELECTRIC POWER SYSTEMS -
INDEPENDENCE BETWEEN REDUNDANT STAND-BY (ON-SITE) F0WER SOUllCES AND TifEIR DISTRIBUTION SYSTEM 2368.00 FSAR ACCEPTANCE RG I.32 (FSAR 8.1-1) X 06-22-87 SEE REMARRS SEE REF. NO. 11 CRITERIA / GUIDELINES
- 8. 1-1 }DR ELECTRIC IWFR SYSTEMS l
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Psge No. 21 12/03/R7 PLANT YOGTIE IfNIT 2 READINESS REVIEW PROGRAM IMPLEMENTATION MATRIX - W)DULE 06
============================ === ===
DESIGN CONST REF. SOURCE AND DES CON CURRENT DESIGN CURRENT CONSTRtCTION NINDER SECTION SUBJECT DoctMENT/FEAft'RE IGN ST. AS OF: IMPIEMENTATION AS OF: IMPLEMENTATION RIMARKS
- -=== = === = ======= = ==================== ==============e:==== === === ====== = ====================== ======== ================= ==~_= ======= ==_=======
2369.00 FSAR ACCEPTANCE RG 1.47 (FSAR 8.1-1) X 06-22-87 SEE REMARKS SEE REF. No. 14 CRITERIA / GUIDELINES
- 8. 1-1 FOR ELECTRIC POWER SYSTDt3 2370.00 FSAR ACCEPTANCE RG 1.63 (FSAR 8.1-1) X 06-22-87 3EE REMARKS SEE REF. NO. 17 CRITERIA /GUIDELIhTS
- 8. 1-1 FVR ELECTRIC PWER SYSTEMS -
PENETRATION ASSEMBLIES 2371.00 FSAR ACCEPTANCE RG 1.75 (FSAR 8.1-1) X 06-22-87 SEE RDtARKS SEE REF. NO. 18 CRITERIA / GUIDELINES
- 8. 1-1 FOR ELECTRIC POWER SYSTDG 2372.00 FSAR ACCEPTANCE RG 1.81 (FSAR 8.1-1) X 06-22-87 SEE RDtARKS SEE REF. NO. 19 CRITERIA / GUIDELINES
- 8. 1-1 FVR ELECTRIC POWER SYSTDG - SRARED UfERGENCY AND SHUTDOWN SYSTEMS FOR MULTI-UNIT NUCLEAR IUWER PLANTS 2373.00 FSAR ACCEPTANCE RG 1.106 (FSAR X 06-22-87 SEE RDtARKS SEE REF. No. 23 CRITERIA / GUIDELINES 8.1-1)
- 8. 1-1 frR ELECTRIC 00hTR SYSTEMS 2375.00 FSAR ACCEPTANCE RG 1.118 (FSAR X 06-22-87 SEE REMARKS SEE REF. No. 2351 CRITERIA / GUIDELINES 8.1-1)
- 8. 1-1 FOR ELECTRIC IVWER SYSTD15 - PERIODIC TriSTING OF IUvTR AND PlVTECTION SYSTD13 O O 9
,- p
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I'm. Nes. 25 12/ 0 ij ff7 Pl. ANT VOCTI.E UNIT 2 READINESS REVIFW PIKX; RAM IMPIPfENTATION MATRIX - MODULE 06
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DESIGM CONST REF. SOURCE AND DES CON CURRENT DESIGN CURRENT CONSTRilCTION NitfDER SECTION SUBJECT DOCtP!ENT/ FEATURE IGN ST. AS OF: IMI'LINENTATION AS OF: IMPIMfENTATION REMARKS
===== =============== ========== === === = == ================= === ==e =e ===== ===== ================ ======== ==s=================e= ==~======== ===,-=
2376.00 FSAR ACCEPTANCE IM1 1.128 (FSAR X X 06-22-87 SEE REMARKS 05-21-87 SER REMARKS SEE REF. NO. 21 CRITERIA / GUIDELINES 8.1-1)
- 8. I-1 IUR ELECTRIC POWER SYSTEMS -
INSTALLATION DESIGN AND INSTALLATION OF LARGE LEAD STORAGE BATTERIES 2380.00 FSAR ACCEI"TANCE BTP ICSB X 06-22-87 DC-1000-E, REV. 6 CRITERIA / GUIDELINES II(PSB)(FSAR 8.1-1) 8-29-85, C.S., H. 1-1 FOR El.ECTRIC POWER DC-1801, REY. 3, SYSTEMS - STABILITY 7-19-83, C.S., OF OFFSITE F0WER DC-1815. REV. 2, 5-18-83, C.S. 23F12.00 ISAR ACCEPTANCE BTP ICSB 21 (FSAR X 06-22-87 DC-1000-E, REY. 6 CRITERIA / GUIDELINES 8.1-1) 8-29-85, C.S.,
- 8. 1-1 FOR BLECTRIC IUWER DC-1605. REY. 1 SYSTEMS - SAFETY 3-29-83, C. S. ,
SYSTEM BYPASSED AND DC-1625. REV. 1, INOPERABLE STATUS 8-2-83, C.S., DC-1801, INDICATION REV. 3, 7-19-83, C.S. ??Hl.00 FSAR ACCEPTANCE BTP PSB-1 (FSAR X 06-22-87 DC-1000-E, REV. 6 CRITERIA / GUIDELINES 8.1-1) 8-29-85 C.S., fl. 1-1 FOR ELECTRIC POWER - DC-1801, REV. 5 SYSTEMS - ADEQUACY 10-2-85, C.S., , OF STATION DC-1816. REY. 3, i DISTRIBUTION SYSTEM 9-3-85, C.S., DC-1821 VOLTAGES REV. 5, 5-2-83, C.S., DC-1823. REY. 3 i 2-3-84, C.S. I I 2390.00 FSAR SPEC. IVR PRINCIPAL ASME III NE-2000 X 06-22-87 SEE RF}fARKS SEE REF. No. Ill3 PRESSURE RETAINING (CONT. PENETRATING '
- 6. 1. 1. 1. I HATERI AL FOR ESF MATERIALS) (FSAR i SYSTEMS 6.1.1.1.1) l l
1 l
P.ege N s. 26 12 /0lI/ H7 Pl. ANT YOGTIE PNIT 2 READINESS REVIFW PHOGRAM IMPIDfENTATION MATRIX - FR)Dut.E 06
==== =- -- =====~=-===-=======---===
DESIGN CONST REF. SOURCE AND DES CON CURRENT DESIGN CURRENT CONSTRICTION NINiif R SECTION St'DJ ECT DoctNENT/FRATLHK IGN ST. AS OF: IMPl.ENENTATION AS OF: IMPIDfENTATION RINARKS
=-- ~:,: ====== === : = =.=== ========== ==================== === === ======= ====================== =====.== r == ========== = == = ====--==== =======
237).00 FSAR CONTAINMENT COOLING RG 1.32 X 06-22-87 DC-1206 REV. 2 SYSTEM SAFETY DESIGN 4-28-83
- 6. 2. 2. l. 1. BASES
- 1. G 2415.00 FSAR ELECTRIC RYDROGEN EACH RECOMDINER IS X 06-22-87 DC-IS13-3.3.1, REV. O, REC & MINER IVWERED ITEM A 6-3-83
- 6. 2. S. 2. I SEPARATE SAFEGUARD BUS AND IS PROVIDED WITH A SEPARATE IVfER PANEL AND CONTidOL PANEL 2968.00 FSAR Q.A. REQUIREMENTS ANSI N45.2.4 -1972 X X 06-22-87 SEE RDtARKS 05-21-87 SEE RDIARKS SEE REF. No. 31 FOR INSTALL., INSP., (IEEE 336-1971)(FSAR 17A. 0 & TESTING OF 17.A.0)
INSTRINENTATION & EtECTRICAL EQUltitENT 3527.00 ISAR NSCW CtMVNENT DATA CLASS lE IVWER X 06-22-87 DC-1202-3.10, REV. S. SUPPLY. 4-19-83
- 9. 2. 1-3 411100 FSAR CONIVINANCE WITil 10CFR50 APP. A, GDC X 06-22-87 SEE REMARKS SEE REF. No. 95 NICLEAR REGULATURT 2 (FSAR 3.1.1)
- 3. 1. 1 CONISSION GENEllAL DESIGN CRITERIA, OVERALL REQUIRatENTS
- DESIGN BASES FOR PROTECTION AGAINST NATURAL PliENMfENA 4115.00 FSAR CONFVINANCE WITil 10CFR50 APP. A GDC X 06-22-87 SEE RDtARKS SEE REF. NO. 2 NUCLEAR REGULATORY 4 (FSAR 3.1.I)
- 3. 1. 1 C0tNISSION GENERAL DESIGN CRITERIA, OVERALL REQUIRDfENTS
- ENVIRONMENTAL AND MISSILE DESIGN BASES O O O
o Page No. 27 12/03/R7 PLANT V0GTLE liNIT 2 READINESS REVIEW PROGRWt IMPLDfENTATION MATRIX - P9)DULE 06
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DESIGM CONST REF. SOlllCE AND DES CON CURRENT DESIGN CURRENT CONSTRICTION NiteER SECTION SimJECT DOCINENT/FEATUlfE IGN ST. AS OF: IMPLEMENTATION AS OF: IPLPI EMENTATION REMARKS
==r==== r= ============ ==================== ========== ===== === === === ======== ====================== ======== =====================e = ================
4116.00 FSAR CONFORMANCE WITH 10CFH50, APP. A. GDC I 06-22-87 SEE REMARKS SEE REF. NO. 3 NUCLEAR REGULATORY 5 (FSAR 3.1.1) i ' 3. l .. I COPNISSION GENERAL DESIGN CRITERIA, OVERALL REQUIRINENTS
- SHARING OF-STRICTURES, SYSTFMS, AND COMIBNENTS 4118.00 FSAR PROTECTION BY 10CFR50, APP. A GDC X 06-22-87 SEE REMARKS SEE REF. NO. 42 MULTIPLE FISSION 17 (FSAR 3.1.2)
- 3. 1. 2 PRODICT BARRIERS -
ELECTRIC 00WER
~
SYSTEMS
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4119.00 FSAR PROTECTION BY ~ 10CFH50, APP. A, CDC X 06-22-87 SEE RDIARKS SEE REF. NO. 4 MULTIPLE FISSION 18 (FSAR 3.1.2)
- 3. 1. 2 PRODUCT BARRIERS -
INSPECTION AND TESTING OF ELECTRIC POWER SYSTEMS 4132.00 FSAR REACTOR CONTAIPNENT 10CFH50, APP. A CDC I 06-22-87 SEE REMARKS SEE REF. NO. 5
- DESIGN BASES 50 (FSAR 3.1.5)
- 3. 1. 5 4181.00 NRC QUEST. QUALIFICATION OF IEEE 344-1975 (FSAR X 06-22-87 SEE REMARKS SEE REF. No. 32 CORRES. ' LOAD SEQUENCER,.. 0430.69) 0430. 69 PROTUTYPE TEST 4272.00 NHC QUEST. MAIN CONTROL BOARD & THE EMERGENCY X 06-22-87 DC-1808, REV. 4 CORRES. REMOTE SHUTDOWN LIGif7ING POWER 11-7-85, PG 3 0430. 5-- I PANEL ILLININATION DISTRIBUTION SYSTEM LEVELS - IS CLASS IE FROM 4.16KV TO 480 -V LEVEL. (FSAR 0430.5-1)
_m. -, .- + m. _s ~ , . _ _ _ _ .m _.
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Paspa No. 28 12/03/R7 PLANT V0GTLE UNIT 2 READINESS REVIFW PROGRAM IMPLD1ENTATION MATRIX - PODUI.E 06
===--======= =======================
DESIGN CONST REF. S0t!RCE AND DES CON CURRENT DESIGN CURRENT CONSTRtCTION NINDER SECTION SUBJECT DOCTMFNT/5'EATURE IGN ST. AS OF: IMPIDfENTATION AS OF: IMPLDIENTATION RUtARKS m === ===:=========== ==,================= ======== ===== =-=== === === = ==== = ====================== ======== == ======= =========== ================== 4274.00 NTC O!TST. POWER StTPLY TO 10CFR50, APP. A, X 06-22-87 SEE REMARKS SEE REF. NO. 42 CORRES. CLASS IE BUSES GDC-17 (FSAR 0130. 59 0430.59) 4275.00 NRC QUEST. POWER SUPPLY TO IEEE 308-1974 (FSAR X 06-22-87 SEE REMARKS SEE REF. N0. 27 CORRES. CLASS IE BUSES 0130.59) 0130. 59 4276.00 NIC QUEST. POWER SUPPLY TU RG 1.32 (FSAR X 06-22-87 SEE r.EMARKS SEE REF. NO. 11 CORRES. CLASS IE BUSES 0430.59) 0430. 59 1277.00 NIC otTST. 120V AC POWER RG 1.75 (FSAR X 06-22-87 SEE RDtARKS SEE REF. NO. 18 CORRES. SUPPLIES 0130.61) 0130. 61 4280.00 NRC QUEST. MOV OL PROTECTION RG 1.106 (FSAR X 06-22-87 SEE RDtARKS SEE REF. NO. 23 CORRES. PER RG POS. C.l(e) 0130.64) 0130. G1 4281.00 NifC OtTST. MOV OVERIDAD MOV MOTOR OVERIDAD X 06-22-87 IX3D-BG-C010,REV. 3, SEE FINDING CORRES. ANNUNCIATION IS ANNUNCIATED IN IX3D-BG-C0lX,REV. 3, 2RRF-006-013 0130. 64 CONTROL ROOM (FSAR IX3D-BG-ColV REV. 0430.64) 1.DC-1805, DMCN 1805-5 42H3.00 NRC QUEST. QUALIFICATION OF IEEE 323-1974 (FSAR X 06-22-87 SEE REMARKS SEE REF. NO. 29 CORRES. DEGRADED VOLTAGE 0130.68) Q130. 68 PROTECTION EOUll? TENT 4281.00 NRC QUEST. QUALIFICATION OF IEEE 344-1975 (FSAR I 06-22-87 SEE REMARKS SEE REF. NO. 32 CORRES. DEGRADED VOLTAGE 0130.68) 0130. 68 PROTECTION EQUllitENT 4286.00 NRC OUEST. QUALIFICATION OF IEEE 323-1974 (FSAR X 06-22-87 SER RFMARKS SEE REF. NO. 29 CORRES. IDAD SEQUENCERES, 0130.69) 0135. 69 PRO 1DTYPE TEST 4289.00 NRC QUEST. PRESSURIZER RELIEF PRESSURIZER RELIEF X 06-22-87 00-1201, COVER PAGE, CURRES. VALVES, BLOCK VALVES, BIDCK VALVES REV. 2, 3-9-111 02t>0. 61 VALVES, LEVEL LEVEL INDICATORS DC-1010-TI, REV. 5, INDICA 1DRS POWERED FROM CLASS 2-7-86 DWGS. lE AC/DC SYSTDtS 213D-BD-B02A, -8028
-803H, -803F, 2X6AV01-287. -317
-316, 2X3D-AA-G02A O O O
f a Page No. 29 12/03/87 PLANT V0GTIE trNIT 2 READINESS REVIEW PIR.1 GRAM IMI'LEMENTATION MATRIX - MODULE 06
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DESIGN CONST REF. SOURCE AND DES CON CURRENT DESIGN CURRENT CONSTRUCTION NIMi1ER SECTION SUBJECT DOCINENT/ FEATURE _ IGN ST. AS OF: IMPLEMENTATION AS OF: IMPLEMENTATION RENARKS , e-ess== =============== ================== = ==================== === === ======== ====================== ======== ====================== ================== ; 4310.00 WilC OUEST. ISOLATION DEVICES IEEE 472 (FSAR X 06-22-87 DC-1000-E.REV.6,8-29-8 CORRES. 0120.10) 5,fu.15.DC-1816,REV.3, 0420. 10 9-3-85 PG.3 4319.00 NRC QUF.ST. BALANCE OF PLANT WCAP 8760 (FSAR X 06-22-87 DC-1009 REY.2,6-3-83,P INTERFACE CORRES. INTERFACE WITH 0420.46) 0.3 REFERENCE TO 0420. 46 WESTINCI!OUSE DESIGN DC-1009 IN DC-lR25 4329.00 NHC QUEST. QUALIFICATION OF AS1M E-Il9 (FSAR X 06-22-87 DC-1000-E, REV. 6, ! I CORRES. FIRE-RESTRAINT 0430.75) 8-29-85, PC. 7 Q130. 75 MATERIAL USED AS IEEE-384 SEPARATION BARRIERS WITHIN PANEL 3 AND CONTROL BOARDS 4370.00 FSAR DAPFING VALUES fDR EEISMIC PERCENT OF X 06-22-87 SEE REMARKS SEE REF. NO. 2188 FIXED BASE CRITICAL DAMPING PER
- 3. 7.B. 1-1 STRUCTURES AND MODE (FSAR COMPONENTS 3.7.8.1-1) 4183.00 FSAR INSTRtNENTATION AND IEEE STD. 308-1974 X 06-22-87 SEE REMARKS SEE REF. NO. 27 CONTROL ITWER SUPPLT SECT. 5.4 (FSAR
- 7. l. 2. 1. SYSTEM - RTS 7.1.2.1.3.E) 3.E 4519.00 FSAR I & C POWER SUI' PLY IEEE 308-1974 (FSAR X 06-22-87 SEE REMARES SEE REF. NO. 27 f SYSTEM 7.6.1.2)
- 7. 6. 1, 2 ANALYSIS 4668.00 I.E.B. CORRES. _WESTINGNOUSE MEASURES WILL BE X 06-22-87 DC-1804,REV.5,10-2-85 FILE: IEB 79-25 ELECTRIC RELAYS TAKEN 10 ENSURE THAT PG.10,DC-1805,REV.5,8-C-79/12/28 -DEFECTIVE W-BFD 6-85. 0G.13.DC-I825, REV [
RELAYS ARE NOT USED .2,9-24-85,0G.5
-(IEB CORRES.
C-79/12/28) 4688.00 FSAR SEISMIC SUBSYSTEM. COMPONENT EARTHOUAME I 06-22-87 SPEC. APPENDIX 'QG,' ANALYSES - TifREE EFFECTS COMBINED BY REV. 0
- 3. 7.B. 3. 6 ' COMPONENTS OF SRSS METHOD (FOR EARTHQUAKE MOTION. QUAL. BY ANALYSIS)(FSAR 3.7.B.3.6)
_ _ _ _ _ _ . _ _ _ _ _ _ - ._ _ ~ - _ - - . _ _ _ . _ _ _ ~ - . ._. . . .. . _., - . _ _ . -. . _ . . - _ , . , .. _ .- , . , . . _ .
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-- = == - m= =- = ======= - ---- =
DESIGN CONST ITF. SOIWCF AND DES CON CURRENT DESIGN CURRENT CONSTRtICTION NtPtRER SECTION SUBJECT DoctPfENT/ FE ATliRE IGN ST. AS OF: IFfPLFNFNTATION AS OF: IMPl fMENT ATION RFMARKS
- - == =,=======-- =--- = ==- ======-= - -- == === === ======= == =- ================ ======== == ==: =============== ===---r - =- -~~
1H08.00 FSAR I & C I M ER SUPPLY RG 1.6 (FSAR X 06-22-87 SEE RfMARKS SEE REF. NO. 6 SYSTEM 7.6.1.2)
- 7. 6. 1. 2 ANALYSIS 1R09.00 FSAR 1 & C IW ER SUPPLY VITAL AC-NO SINGLE X 06-22-87 DC-1000-E, REV. 6 SYSTEM - ANALYSIS FAltt!HE IN THE I & C 8-29-85, PGS. 22, 24 &
- 7. 6. 1. 2 FWER StirPLY SYSTEM 25 DC-1807. REV. 3, OR ASSOCIATED 00WER 8-23-85, PG. 2 StTPLIES CAN cat!SE LOSS OF POWER TO MORE THAN ONE OF THE REDUNDANT LDADS.
(FSAR 7.6.1.2) 1H10.00 FSAR ONSITE IVWER SYSTEM 10CFR50, APP. A. GDC X 06-22-87 SFE REMARKS SEE REF. NO. 42
- CAPABILITY OF EAcil 17 (FSAR 8.1.4.2.B)
- 8. 1. 4. 2.B ONSITE IE AC POWER SYSTEM TO MAINTAIN
! ONE UNIT SAFE CONDITIONS l 1H13.00 FSAR ONSITE POWER 10CIR50, APP. A GDC X 06-22-87 SEE REMARKS SEE REF. NO. 42 SYSTEM-SINGLE 17 ( FS AR 8.1. 4. 2. F) R. 1. 4. 2.F FAllt!HE CRITERIA 1Hl4.00 FSAR ONSITE fwER SYSTEN 10CFR50, APP. A CDC I 06-22-87 SEE REMARKS SEE. HEF. No. 4
- I'ERIODIC TEST 18 (FSAR 8.1.4.2.L)
- 8. 1. 4. 2.L CAPABILITIES OF CLASS 18 EQUIItfENT.
1H15.00 FSAR CLASS lE BttS lEEE 279 (FSAR X 06-22-87 SEE RDtARKS SEE REF. NO. 26 IINDERVOLTAGE 8.3.1.1) i H. 3. 1. I rif0TECT10N SENSORS l 1H17.00 FSAR CLASS lE SYSTEMS ALL SAFETT RELATED X 06-22-87 DC-1005, REV. 1 EQUIINENT LAYOUT EQUlINENT HOUSED IN 4-4 -83, ITI. 2, PARA.
- 8. 3. 1. 1. 2 SEISMIC CAT. 1 3.4 l STRUCTURES (FSAR l 8.3.1.1.2)
O O O
V Page No. 31 12/03/R7 Pl. ANT V0GTLE UNIT 2 READINESS REVIEW PROGRAM IMPLEMENTATION MATRIX - MODULE 06
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DESIGN CONST REF. SOURCE AND DES CON CURRENT DESIGN CURRENT CONSTRUCTION N17fitER SECTION SUBJECT Dot'tNENT/ FEATURE IGN ST. AS OF: IMPLEMENTATION AS OF: IMPinfENTATION REMARKS
====== ============= = ===================- ==================== === === ======= ====================== ======== ============== ====== ==================
4821.00 FSAR 125-V DC SAFETY IEEE 308 (FSAR X 06-22-87 SEE REMARKS SEE REF No. 27 FEATURES SYSTDts - 8.3.2.1)
- 8. 3. 2. I DESIGNATION AS lE 4R25.00 FSAR SINGLE FAILIrRE IN NO SINGLE FAILURE IN X 06-22-87 DC-1000-E.REV.6,8-29-8 125-V DC SAFETY ANY 125-V DC SYSTEM 5,ra.24,DC-1806. REY.5,
- 8. 3. 2. I FEATURES SYSTEMS WILL RESULT IN 8-23-85,P0.4 CONDITIONS THAT WILL PREVENT SAFE SHUTDOWN (FSAR 8.3.2.1) 4826.00 FSAR SIZING OF BATTERIES LEER 485-1978 (FSAR X 06-22-87 DC-1000-E,REV.6,8-29-8 8.3.2.1) 5,IV.15,DC-1806, HE V. 5,
- 8. 3. 2. I 8-23-85,PG.2 4827.00 FSAR SIZING OF BATTERIES BATTERIES SIZED AT X 06-22-87 DC-1806 REv.5,0-23-85, MIN. TEMP. OF 55 FC.5
- 8. 3. 2. l. I DEGREES F (FSAR 8.3.2.1.1) 4828.00 ISAR SIZING OF BATTERIES BATTERT CAPACITY IS X 06-22-87 DC-1806.REV.5,8-23-85, INCREASED BT 10% EUR PG.5
- 8. 3. 2. I LOAD GROWTH AND 25%
IVR AGING (FSAR 8.3.2.1) 4829.00 FSAR SIZING OF BATTERIES BATTERY MIN. VOLTAGE X 06-22-87 X3AD01, REV. 10 PG. DESIGN LIMIT IS 5, PARA. 3.2.1.1B
- 8. 3. 2. I 1.80-V/ CELL OR 106.2-V/B ATTEI;Y (FSAR 8.3.2.1) 4830.00 ESAR 125V-DC SAFETY IEEE 308 (FSAR X 06-22-87 SEE REMARKS SEE REF. NO. 27 FEATURES SYSTEMS 8.3.2.1)
- 8. 3. 2. I SIZING OF BATTERY CHANGERS
Page- No. 32 12/03/R7 Pl. ANT V0GTI.E UNIT 2 READINESS REV!FW PINW; RAM IMPLDfENTATION MATRIX - MODULE 06
=======:==========-=======---===-
DESIGN CONST REF. SOHirE AND DES CON CtmRENT DESIGN CtrHRENT CONSTRICTION NIHitFR SECTION SUBJECT DoctNENT/FFAT1!RE IGN ST. AS OF: IMPLDtENTATION AS OF: IMPIDfENTATION RDiARKS
- -- = =====- = ====== ===== =========== == ==- =.==========-=== == === ======== ,======== ============ ======== =====-=======s======== =======,====,=:-==
4H31.00 FSAR 125V-DC SAFETY RG 1.32 (FSAR X 06-22-87 SEE RDfARKS SEE RFF. No. 11 FEATURES SYSTD1S 8.3.2.1)
- 8. 3. 2. I SIZING OF BATTERY CilARGERS 4H32.00 FSAR 125V-DC SAFETY CIIARGERS SPECIFIED X 06-22-87 X3AD01 REV. 10, PC.
FEATURES SYSTDtS 1D MAINTAIN OUTITT G. FARA. 3.2.1.2.2 H. 3. 2. 1 SIZING OF BATTERY VOLTAGE REQUIRED + CilARGERS OR - 1% FROM N0 IDAD TO FULI, LOAD (FSAR 8.3.2.1) 4H33.00 FSAR 125V-DC SAFETY CHARGER OUTPUT X 06-22-87 X3AD01, REV. 10, PG. ~ FEATURES SYSTEMS FILTERED TO LIMIT 6, PARA. 3.2.1.2.2
- 8. 3. 2. I SIZING OF BATTERY RIITLE VOLTAGE TO CHAIN;ERS MAX. 3% Itts WITH BATTERY DISCONNECTED (FSAR 8.3.2.1) 4H36.00 FSAR ANALYSIS - TRAIN C&D IEEE 384 (FSAR X 06-22-87 SEE REMARKS SEE REF. NO. 35 BATTERY CHA!M;ERS 8.3.2.2)
- 8. 3. 2. 2 OUALIFIED AS ISOLATION DEVICES 4H37.00 FSAR ANALYSIS - TRAIN C&D RG 1.75 (FSAR X 06-22-87 SEE REMARKS SEE REF. NO. 35 BATTERY CIIARGERS 8.3.2.2)
II . 3. 2. 2 QUALIFIED AS ISOLATION DEVICES 4H30.00 FSAR MAINTENANCE AND RG 1.129 (FSAR X 06-22-87 SEE REMARKS SEE REF. NO. 2355 TESTING - PERIODIC 8.3.2.1)
- 8. 3. 2. I BATTERY CAPACITY TESTS 4R39.00 FSAR DC POWEll SYSTEM - IEEE 450-1975 (FSAR X 06-22-87 DC-1000-E, REV. 6, MAINTENANCE AND 8.3.2.1) 8 29-85, IYi. 15 R. 3. 2. I TESTING -l'ERIODIC DC-lH06, REV. 5 CAPACITY TESTS 8 85, PG. 2 O O O
l'.nc No. 33 12/fl3/87 t'LANT V0GTLE t! NIT 2 READINESS REVIEW I'IDIRAM IMf'LEMENTATION MATRIX - MODUl.E 06
==,==e===-========================e=
DESIGN CONST REF. Sot'HCE AND DES CON CtJRRENT DESIGN CURRENT CONSTItUCTION NINflER SECTION SIIBfECT DoctNENT/ FEATURE IGN ST. AS OF: IMPIfMENTATION AS OF: IMI' LIM WTATION RFMARKS r===r n===== s======= ==================== ==================== === === ======== =============-e====-== ======== ===================== ====--= ========== 4!I36.00 NHC OtfEST. - IIIGH ENERGY EQUIP. RG 1.75 (FSAR X 06-22-87 SEE REMARKS SEE REF. NO. 18 CORRES. IN CABLE SITEADING G130.75(E) 0430. 75(E) Ro0MS 4!!37.00 NHC QUEST. HIGH ENERGY EQUIP. IEEE 384 (FSAR X 06-22-87 SEE REMARKS SEE REF. No. 35 CORRES. IN CABLE SPREADING 0430.75(E) 0430. 75(E) ROOMS 5019.00 1.E.B. CORRES. ITE IMPERIAL PNEtM. TIME DELAY I 06-22-87 SEE RfMARKS FILE: IER 77-01 I'NEINATIC TIME DELAY RELAYS WITH A REPEAT REFER TO BECHTEL C--77/06/27 RELAYS ACCUR. RANGE OF + OR LETTER B.S 760
- 15% OR GREATER 6-22-77 WILL NOT BE USED SOLID STATE T.D.R.
OR PNEIM. T.D.R. WITH A REPEAT ACCUR. RANGE BETTER THAN + OR - 15% WILL BE USED 5020.00 I.E.B. CORHES. USE OF WESTINGHOUSE NO WESTINGHOUSE TYPE I 06-22-87 DC-1805,REV.5,8-6-85 P FILE: IEB 77-02 TYPE AR RELAY "AR" RELAYS WILL BE G.13 C 77/11/11 USED IN THE B.O.P. SAFETY CIRCUITS (I.E.B. CORRES. C-77/11/1I) l
4 PROGRAM DESCRI PTION O 4.1 DESIGN This portion of the module describes the processes and cont rols utilized by Project Engineering and Georgia Power Company (GPC) during generation of the various design documents used to f ac ilitate procurement , c o nst ru c tio n, a nd licensing ac tivities. The design and layout of elect rical equipment was based upon the design and operational requirements delineated in the Vogtle Project Design Manual and desc ribed in the Final Safety Analysis Report (FSAR). The Project Reference Manual ( PRM) cont ains the p rocedu res tha t cont rol the design, review, and revision p rocess. Design cont rol a nd review are performed in accordance with applicable sections of the Vogtle Elect ric Generating Plant (VEGP) PRM, part C. The design documents and drawings for equipment covered by this module were developed by the Bechtel We st er n Power Company (BWPC) pro ject Electrical, Plant Design, Control Systems, and Architectural Design Disciplines under the direction of the respective engineering group supervisor (EGS). Upon initial preparation and development, the documents /d rawings were reviewed by onproject teviewers (other disciplines, Quality Assu ra nce f or Q-class items, Quality Enginee ring , etc. ) to ensure proper implementation of project requirements and by of f p rojec t reviewers, including the discipline chief engineer, O as required by the pepign Control Check List (DCCL), to ensure technical adequacy. t a, Documents and drawings desc ribing equipment contained in the Q-list were identified by placing a Q on the cover / title sheet of documents and in the lower right-hand corner of drawings. Requi rements for the Q-list are cont ained in the VEGP PRM, part C, section 14, and the equipment is listed in Table 3.2.2-1 of the FS AR. The design work flow process has been divided into the f o llowing four phases:
- 1. Deve lopme nt of design criteria.
- 2. Preliminary design and layout considering the nuclear steam supply system (NSSS) a nd int er f ace requ ireme nt ,
Codes of Federal Regulations, regulatory guida nce, indust rial /BWPC standards and guides, and client requirements (includes development and issue of specifications f or aux iliary equipme nt ) ,
- a. The DCCL procedure is desc ribed in the VEGP PRM, part C, section 20. The DCCL originals are maintained in Projec t
.( File X7BD68. 0152f/337-7 4-1
- 3. Detailed design and clarification of technical interfaces and release of revision o d rawings. g
- 4. Const ruction support and interf ace [d e t e rmi ni ng disposition of Field Change Requests (FCRs) and Deviation Reports (DRs)].
Phases 1, 2, and 3 of the design process are substantially complete a nd engineering drawings, const ruction specifications, and material specifications have been issued. The cur rent activity of the design engineering groups centers on processing FCRs and DRs and issuing change notices or revisions to engineering design documents and drawings. The final documentation verification of calculations and the issue of a s-b u i lt drawings conclude the const ruction support phase. The following paragraphs describe the processes involved in the d eve lopme nt , review, and revision of the documents generated in each of the above stages. 4.1.1 DESIGN CRITERI A DEVELOPMENT The initial c riteria for the design of the safety-related systems and components are cont ained in the Preliminary Saf ety Analysis Report, which was submitted to the Nuclear Regulatory Commission (NRC) in August 1972. Detailed design criteria were developed and issued as the Design Manual. I The Design Manual is organized into sections as f ollows: o General Plant Crite ria - These c riteria provide the I overa ll plant physical protection criteria and the I maintenance and serviceability c riteria. The p rotection criteria provide acceptable design bases for the protection of systems and equipment important in saf eguarding against postulated events or ha zards. The maintenance and serviceability criteria define the design bases pertinent to the development of the general plant a r ra ng eme nt . o General Design Criteria - These criteria surnarize the i principal functions and safety design bases pertaining to the functional parameters of civil, electrical, a nd i mechanical design. DC-1000-E, the general elect rical I design criteria, ident ifies the codes, s t a nd a r d s , a nd regulations, including the applicable revisions, that govern the electrical design. o Interdiscipline Design Criteria - The interdiscipline design criteria provide the design bases applicable to 0152f/337-7 4-2
' r~g all disciplines such as seismic, environmental, etc. k,) Table 4-1 lists the interdiscipline design criteria
- applicable to Module 6. .
o System Design Criteria - The systems design criteria f provide detailed criteria (e.g., principal function, safety design bases, etc.) for each plant system. The 1800 series criteria specify the detailed design bases for electrical systems. Table 4-2 lists the criteria applicable to the scope of this module. The design criteria control and review process was performed in accordance with the procedures established in the Design Manual Preface, sections 1, 2, and 3. Table 4-1 indicates the groups having principal responsibility for the interdiscipline design criteria applicable to the scope of this module. The electrical design criteria were established through various multidiscipline interactions; were based on ' applicable licensing commitments, industry codes, and standards; and were implemented in accordance with established and controlled project procedures. 4.1.2 PRELIMINARY DESIGN . The preliminary design of the plant was developed using general ("/ s-N 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 Bechtel Plant Design Group which had lead responsibility for a multidiscipline interactive design effort. The electrical group participated in this activity using the various system and interdiscipline criteria (equipment separation, pipe break, radiation shielding, etc.) to develop the basic layout of each electrical system. This included defining the location of equipment, required structural openings, space required for maintenance, and necessary foundations. Studies Electrical equipment / system studies were prepared by the BWPC Electrical discipline and controlled and reviewed in accordance with the procedures established in the VEGP PRM, part C, section 12. The procedures address initiation and control of studies; documentation of studies; study development; study report i review / approval; and study report numbering, filing, and , distribution. The project engineer controlled the study and ol52f/337-7' 4-3 f
decided whether it was to be informalI ") or formal I) , h coordinated with GPC and Southern Company Services (SCS), and determined the extent of study documentation. The electrical EGS performed / evaluated the electrical equipment studies, maintained a study report control log, and assigned numbers to the studies. Studies are listed in the Electrical Studies Control Log. Sketches Sketches were generated to identify design concepts, requirements, and configurations. Sketches were not issued or used for fabrication or construction purposes. However, electrical sketches were used with, or attached to, bidding specifications, design proposals, studies, etc. Engineering sketches were prepared by BWPC and SCS. Sketch control and review were performed in accordance with the procedures established in the VEGP PRM, part C, section 4, subsection 4.3. This section addresses review, approval, issuance, distribution, filing, and numbering of sketches. The originating discipline EGS or designee coordinated, approved, and issued sketches. Data and Document Controls (DDC) input issue dates, distributes and files sketches, and maintains the sketch control log and numbering system, which lists electrical equipment sketches in the electrical design section. General Arrangement Drawing and Equipment Layout Drawings General arrangement drawings showing the configuration of the power block, building dimensions, and basic equipment arrangement were the first plant design 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. Equipment layout drawings were later developed to dimensionally locate major equipment in the plant, coordinating inputs of all disciplines. These drawings were generated for each building
- a. Informal studies develop project design within the scope of the contract to define physical aspects; to resolve problem areas; or to investigate new or improved methods, materials, or processes,
- b. Formal Studies investigate concepts or develop criteria that define project scope. They either verify the project scope or recommend a change in scope.
0152f/337-7 4-4 l
g . level. In addition to showing location dimensions of major equipment, they also designate equipment laydown or tube pullout , space to ensure proper installation and maintenance. The j layouts were developed based on equipment, vendor requirements, ; system process requirement, NRC requirements, and industry /BWPC l standards. i One-Line Diagrams l The one-line diagrams show the connection sketches, the power grid, generator, switchgear, motor control centers, and plant loads in simplified form. , They were prepared and controlled jointly by the Electrical Systems and Control / Wiring Groups. They were checked in accordance with the one-line drawing and Controls / Wiring Group one-line diagram checklists (reference BWPC Interoffice Memo (IOM) log No. BB 33958, file No. X3BK14). Coordination prints i were reviewed by the Electrical Physical Design Group to ; coordinate equipment location and cable / raceway interface requirements. Upon incorporation / resolution of comments, the drawings were approved for issue by the Systems and Control / Wiring Groups and the electrical EGS. The one-line diagrams are listed in the Electrical Drawing Control Log. ' Procurement Specifications i
/~ :
(_)T These specifications provide bases for the procurement of l electrical equipment. They conform to the project design , criteria and complement other project design documents. Procurement specifications for electrical equipment are listed ' in the Electrical Specs /MRs (material requisitions) Control Log. Procurement specification control and review were performed in accordance with the procedures established in the VEGP PRM, . part C, section 8, which addresses the procurement specification control, review, and approval process. The originating discipline EGS (or designee) was responsible for preparing, coordinating, initiating the review cycle, obtaining all signatures and approvals, issuing the specification, and providing input to the specification control log. Procurement ; specifications are listed in the Electrical Specs /MRs Control Log. Calculations i Calculations and analyses were prepared during this phase to ; support the design of electrical systems and the issue of material specifications. Calculations were initially prepared l by BWPC and SCS to determine electrical system and subsystem ! design parameters including electrical equipment ratings and
} ,
t 0152f/337-7 4-5 i
system capabilities and capacities. Calculations were prepared based on actual conditions, where known; otherwise conservative g conditions were assumed. Additional input sources included design criteria, licensing requirements, vendor data, industry standards, and BWPC design guides. The resulting design parameters were used as part of equipment procurement specifications. Those calculations that are common to both units are periodically reviewed to ensure that input data remains conservative when compared to as-built conditions. Where specific Unit 2 data is required due to design differences, the calculations are revised to reflect the Unit 2 uniqueness. Scheduled revisions are tracked in the Discipline Calculation Control Log. The calculations are controlled and reviewed in accordance with the procedures established in the VEGP PRM, part C, section 9. The procedures address calculation numbering, control, format checking, review and approval, microfilming, and transmittal to GPC. The electrical discipline EGS assigned the calculation numbern and provided input to and maintained the Calculation Control Log. The design calculation control, review, and approval process is similar to that for drawings except that calculations are not reviewed by other project disciplines and forms and format are different as shown in the VEGP PRM. Project Administration microfilms and files the originals of calculations. Electrical calculations are listed in the Electrical Calculation Control Log. Calculations for equipment covered by this module are summari ed in Table 4-3. ll 4.1.3 DETAILED DESIGN After the system and equipment layout was defined and interface requirements were obtained from the various engineering disciplines and equipment vendors, the detailed design phase began. Since the design criteria were assembled by Project Engineering on a discipline basis during the initial stages of the design work, criteria now had to be maintained current to serve as a basis for the design. System design calculations were completed, logic diagrams for system operations were developed, and elementary and wiring diagrams were issued for construction. Design drawing control and review are performed in accordance with the VEGP PRM, part C, section 4, which addresses numbering, reviewing, approving, issuing, distributing, and filing drawings. The originating discipline EGS or designee (engineering group leader) is responsible for the preparation, enumeration, coordination, review, and issue of drawings. In addition, the EGS or designee also provides input to the Drawing Control Log. DDC enters the issue dates and distributes and files the drawings. Drawings describing Q-list (safety-related) items are identified with the letter "Q". In addition, Class 1E 0152f/337-7 4-6
electrical drawings a re marked " Nuclear Safety Related." The ('N markings are located in the lower right-hand corner of the drawings di rectly above the title block. Logic diagrams are prepared and controlled by the Controls Diec ipline and are discussed in Module 20. Elementary Diag rams Elementary diag rans sche ma tically illust ra te the cont rol, protection, and monitoring functions of electrical circuits. They al(o show int erconnections and cabling between power sou rce s , apparatas, and device elements of a particular system. E leme nt ary d iag ra ns are prepared based on one-line diagrams, control logic diagrams, and equipment supplier drawings. W he n issued for equipment procure ne nt , they i nclude inf ormation sufficient for the suppliers to select electrical components and prepa re equipment inter nal wiring di ag r a ns . The diagrams were prepared and controlled by the BWPC Electrical Cont ro l Wiri ng G ro up . They were checked in accordance with the element a ry diag ram check.'.ist ( ref e rence BWPC IOM log No. BB 33958, file No. X3BKl4). Coordination prints were revi ewed by the Elect rical physical Design Group to coordinate cable / raceway and junction box location int erf ace rceuirements and by the EE580 Group for cable routing. Upon incorpora tion / resolution of comments, the drawings were approved O for issue by the Control Wiring Group and the electrical EGS. The elementary diagrams are listed in the Electrical Drawing Cont rol Log . Wiring Diagrams Wiring diagrams schematically illustrate the field-installed cable terminations at the equipment or device. I n f o rmatio n for int ernal wiring within the equipment or device is contained on vendo r supplied wi ring diag rams. Wiring diag rams a re p repa red based on eleme nt ary dra wings and ve nd or wiring diag ra ms. They were prepared, controlled, and checked in a manner identical to the elementary diagrams. Haza rds Analyses Hazards analyses for Units 1 and 2 were conducted during this I phase to establish pipe whip restraint location, jet impi ngeme nt loads on pipes (if any) for pipe support design, and maximum flood levels in each room for safety-related component l oca t io n. A basic design objective was to locate saf ety-related , elect rical components in nonhaza rdous a reas. To ensure that all l conditions are considered, detailed analyses of all potential j hazards are performed to ensure that the functional ability of the equipme nt is not af fected. Specific analyses are conducted to study the effects of: (^) V 0152f/337-7 4-7 i
o High-energy line breaks (pipe whip and jet impingement). lh o Internally generated missiles. o Seismic II/I interaction. o Flooding. o Fire. Portions of these analyses are presently ongoing for Unit 2. The structures enclosing the electrical equipment have been designed and analyzed to ensure protection against tornadoes and other external events. Failure Mode and Effect Analyses Failure mode and effect analyses (FMEAs) for electrical equipment and systems within the scope of this module were prepared in accordance with the bases established in the Plant Single Failure Criteria (Interdiscipline Design Criteria, DC-1009). FMEAs were conducted to determine the effects of failures of plant components critical to the achievement of overall system safety performance. The failure modes of components that could contribute to unsafe system operation were identified, and corrective action was taken to obtain compliance with the single failure criteria. Information used to prepare the FMEAs included data published by the NSSS supplier, NRC h requirements, and industry practices. FMEAs developed for electrical systems in Unit 1 are also applicable to Unit 2 due to the extreme similarity between Unit 1 and 2 systems and equipment (refer to note b on FSAR Table 8.3.1-3). FMEA control and review were performed in accordance with the procedures established in the VEGP PRM, part C, section 16, which addresses the processing, documentation, and control of FMEAs. The procedure for numbering, controlling, reviewing, approving, and documenting FMEAs is the same as those for calculations. In addition, FMEAs were reviewed and approved by the Mechanical, Control Systems, and Nuclear Disciplines to ensure that appropriate aspects were included, and that the analyses satisfied licensing requirements. Although not on the DCCL, the current FMEA revisionc have been reviewed by the electrical chief engineer. FMEAs are listed in the Electrical Calculation Control Log. Construction Specifications .During the detailed design phase, engineering construction specifications were developed and issued by Engineering to support construction activities associated with the scope of 0152f/337-7 4-8
this module. Construction specifications for electrical %;y equipment define general construction requirements, the scope of work, governing codes and standards, and provide a complete description of the equipment and tasks to be performed. They provide specific instructions / requirements for handling and installing electrical equipment at the jobsite. Construction ., specification control and review were performed in accordance with the procedures established in the VEGP PRM, part C, section 26, which addresses procurement specification numbering, , review, and approval. The originating discipline EGS was ' responsible for initially preparing, numbering, coordinating, initiating the review cycle, obtaining approvals, issuing the specification, and providing input to the specification control log. Construction specifications are listed in the Electrical Specs /MRs Control Log. Conduit and Tray Drawings Conduit and tray drawings were prepared and controlled by the Electrical Physical Design Group. They were checked in accordance with the physical design checklist (reference BWPC IOM log No. BB 33958, file No. X3BK14). Coordination prints were reviewed by the Electrical Control Wiring Group to ensure selection of optimum locations of junction boxes and by the Civil / Structural Discipline for the development of mounting details (Module 19, Electrical Supports). Additionally, the O locations of junction boxes were reviewed by the Electrical Physical Design Group for possible hazards (Module 17, Raceways). Upon incorporation / resolution of comments, the , drawings were approved for issue by the Electrical Physical Group and the electrical EGS. The conduit and tray drawings are listed in the Electrical Conduit and Tray Drawing Control Log. Design Document / Drawing Revisions The procedures for design document / drawing revisions are essentially identical to the procedures followed for their initial issuance. The major difference is that a different
- review process may have been followed due to the limited scope of a minor revision or (in the case of incorporating change notices) the change may already have been reviewed. '
Design Verification Reviews ' Design verification reviews were systematically performed to ensure that equipment, systems, and structures were properly designed and that the designs were properly coordinated. They were performed by BWPC in accordance with the criteria established in the Design Manual, Preface, section 4, Design Verification Review (DVR) of VNP Systems and Structures. This criterion provides guidance supplemental to the VEGP PRM, part C, section 20, procedure providing specific requirements () and guidelines for design reviews. The Design Manual criteria 0152f/337-7 4-9
i define the review procedures, including requirements establishing the division of responsibility for preparing and reviewing DVR requirements for design review meetings, and requirements for the report documenting the design review. Only safety-related electrical systema were subject to design verification reviews. The review packages for these systems were prepared by the electrical discipline group responsible for preparation of the system design criteria. The package concisted of design criteria, pertinent FSAR sections, one-line/ elementary diagrams, specifications, calculations, FMEAs, environmental qualification information, and equipment location drawings. The review was performed by the electrical and other discipline chief engineers, the Nuclear Control System Mechanical, and Civil / Structural Disciplines, the hazard analysis and equipment qualification coordinators, and Quality Assurance. 4.1.4 CONSTRUCTION SUPPORT AND DESIGN FINALIZATION During this phase, Project Design provided support to the construction discipline groups for design changes, deviation reports, supplier deviation disposition requests, and calculation revisions. These activities assure that consideration of design developments and that the as-built conditions are taken into account. Design changes for electrical equipment are realized by directly revising the design documents / drawings, by issuing Document Change Notices, by issuing Drawing Change Notices, or by converting FCRs to Change Notices. Ultimately, the design documents / drawings are revised and all changes incorporated therein. The alternate change methods used are interim measures that afford Engineering / Construction greater convenience, flexibility, communication, or speed in achieving the desired results. Changes may be initiated by Engineering or Construction, or may be the result of a Nonconformance (Deviation) Report. Changes may be approved only by the design engineering organization having responsibility for the document. Design Manual Change Notices Design Manual Change Notices (DMCNs) can be processed and issued as part of the manual faster than a design criteria revision, which must go through the full review and approval cycle. DMCNs are controlled in accordance with the procedures established in the Design Manual, Preface, section 3.7. DMCNs are prepared by the group responsible for the affected design criteria. They are reviewed and approved by the EGS and 0 0152f/337-7 4-10
~_ _
project engineer / responsible assistant project engineer. O- Changes affecting safety-related or safety-impact material in the manual are reviewed and approved by the BWPC project : licensing engineer and PQAE. ! DMCNs are sequentially numbered (by section/ criteria) by Project Administration and controlled by the project engineer through Project Administration. Project Administration maintains the design manual and is responsible for the Design Criteria Status Log, which is used to record and track revisions and changes to the design criteria. Drawing Change Notices DCNs afford a convenient method for Design Engineering to make changes to drawings without the immediate need to issue the drawing. DCNs are controlled in accordance with the procedures established in the VEGP PRM, part C, section 4.8. Either Design Engineering (DE) or Installation Engineering (IE) may initiate a DCN. However, DCNs on electrical equipment design drawings are only issued by DE. Checking, reviewing, and approving is similar to that as for design drawings. The review performed includes a review for hazards and verification of conformance to the FSAR and design criteria. DCNs are logged in the computerized DCN DDR. The DDR includes . A the DCN issue date, incorporation date, drawing revision, l issuing organization and discipline, and initiating document. ! Also, the latest approved DCN and the last DCN incorporated into the design drawing are listed in the Drawing Control Log. - Construction Specification Change Notices CSCNs afford a convenient means for making and documenting l changes to construction specifications. CSCNs are controlled by l the procedures established in the VEGP PRM, part C, section 26.7. f I Preparation, checking, reviewing, and approving CSCNs are essentially identical to those for the construction j specifications. ; Construction specification change notices are assigned sequential numbers and are logged in the CSCN Register. Field Change Requests ! FCRs afford a means for the field to obtain changes to design i drawings or construction specifications. Similarly, Interim Field Change Requests (XFCRs) are used by the field to obtain changes to Interim Design Change Notices (IDCNs) or other 0152f/337-7 4-11 1
documents in a Change Control Package (CCP). The change may be requested due to interferences, drawing discrepancies, or changes in arrangements required by job conditions, etc. Within the design organization, FCRs are controlled in accordance with the procedures established in the VEGP PRM, part C, section 17. GPC construction issues FCRs to IE. FCRs received by IE are logged in the FCR Register. FCRs are reviewed for conformance to the FSAR and design criteria. They may be processed by DE or IE. IE-processed FCRs on design drawings require DE concurrence. Approved FCRs affecting design changes may be converted to DCNs or CSCNs, as appropriate. Nonconformance (Deviation) Reports DRs are prepared by GPC disciplines or contractors to report deficiencies in material, documentation, or procedures identified during the construction phase of the project. Within the Design organization, DRs are controlled in accordance with the procedures established in the PRM, part C, section 18. DRs issued by GPC for Engineering disposition are transmitted to DDC. If the DR cannot be resolved by IE, it is forwarded to DE. For dispositions of use-as-is and repair, a justification is provided. Required design documents are prepared and noted on the DR. Their issuance is tracked via the DR Log. Interdisciplinary review is provided as required, and the DR is reviewed against FSAR licensing commitments. The GPC quality assurance site manager reviews the DR for potential 10 CFR 21 or 10 CFR 55.55(e) reportability. The disposition is approved by the responsible EGS and project engineer. DRs pertaining to Class 1E equipment are also reviewed by the Bechtel PQAE. Field Equipment Change Orders Field Equipment Change Orders (FECOs) are for field changes to equipment. They are controlled by the procedures established in the VEGP PRM, part C, section 24. FECOs are change packages consisting of revised drawings, document change notices, references to purchase documents and special instructions. Supplier drawing revisions are made by Engineering only after the supplier has declined to provide revised drawings. FECOs for safety-related equipment are identified as Q-class on the cover page. For this equipment, an Equipment Change Approval (ECA) is sent to the original supplier. The ECA describes the proposed change and requests the supplier to O 0152f/337-7 4-12
certify acceptance of the change. This certification includes Os acceptability of the equipment used for the change and seismic and environmental qualification effects, as applicable. The ECA must be closed out before the associated FECO is issued to GPC I for construction. Written approval from the GPC project engineering manager is required for any waiver to the ECA requirements. FECOs are prepared by the electrical group responsible for specification of the equipment. They are approved by the EGS and project engineer; for safety-related equipment the PQAE must provide approval. FECO log and revision numbers are controlled by the FECO Log which is maintained by Project Administration. Project Administration also files the FECO (including ECA) in the project files. Change Control Packages CCPs ensure that design changes requiring physical modification to systems or components that have been or are about to be released to the Startup Group for testing are coordinated with the startup engineer. CCPs are controlled by the procedures established in the VEGP PRM, part C, section 35. CCPs differ from the FECOs in that approval of the Startup Group is required prior to performing the physical modification. * ( CCPs describe the change and the design basis for the change. They identify the impact of the changes on the Design Manual, supplier technical manuals, hazard analyses, etc. They list the material required to implement the change. Also they include the design change documents (the system design documents are not changed until the physical changes required by the CCP have been completed). Design document changes are made by IDCNs. IDCN-Suppliers (IDCN-Ss) are used for revisions to vendor documents. ECAs are provided for safety-related equipment modifications, as described in the previous section. - CCPs containing safety-related documents are identified as Q-class on the cover sheet. The cover sheet also identifies the lead discipline. CCPs are approved by the EGS and PE. Project administration is responsible for issuing CCP numbers and maintaining the CCP and associated documents log. Upon completion of a CCP, the IDCNs and appropriate XFCRs are converted to DCNs. , 0152f/337-7 4-13
Protective Relaying Calculations for protective relaying setpoints and tripping schemes are unique for each unit and are prepared by the GPC Protection Engineering Section (PES) using the controls imposed by GPC System Protection Section Note 28. The FES utilizes design information provided by the BWPC and SCS design groups to prepare preliminary relaying data sheets, which are transmitted to Nuclear Operations. During the initial test program, the adequacy of the trip setting is confirmed and relays are functionally tested. The preliminary data sheet is signed, dated, and returned to the PES. This information is transferred to the Final Relay Data Sheet which represents the as-installed condition. Finalization /As-Built Program The finalization /as-built program defines the methods for providing certain as-constructed design drawings as required for the following: o Future operation and maintenance of the plant. o To meet the requirements of IE Bulletin 79-14 for piping. o To assure that design documents address the effects of cumulative changes to the design. lh The administrative controls for this program are contained in the Vogtle Project Policy and Procedures Manual, part B, section 5. As a part of the process for developing the final as-built documents, several areas of the plant will be walked down to observe as-constructed conditions. The procedures for these walkdowns are contained in the Finalization /As-Built Program Manual. In mid 1987, the Project evaluated the results of the Unit 1 finalization program to identify lessons that could be applied to the Unit 2 program. This effort received input from Project Engineering, Project Construction, and Nuclear Operations, and considered other information such as Unit 1 NRC, Quality Assurance, and Readiness Review evaluations and findings. The modified finalization programs were reviewed by involved project organizations, including Readiness Review, who provided comments on the proposed modifications. Resolution of these comments and approval of each finalization plan by project management was ongoing at the time this module was prepared. Finalization programs FP-2, Hazards, FP-6, Cable Separation Within Class IF Equipment, and FP-14, Seismic Separation, are applicable to the scope of this module and are presently scheduled for the latter part of 1988. 0152f/337-7 4-14
4.2 CONSTRUCTION O This portion of Module 6 contains descriptions of the basic processes that are used for installation and inspection of electrical equipment. The applicable electrical construction sp ecifications, field procedures, design drawings, vendor re qui rements , and the applicable codes which govern each installation and inspection process are addressed. The prerequisite activities, the movement of equipment and its requirements from issue to placement at the design location, the final assembly process including any required modifications, and the in-place maintenance prior to system turnover are described. The instructions used in the installation process are contained in Georgia Power Company field procedures, the electrical construction specification, instructions provided by vendors, and procedures generated by the contractor. Schedules relevant to the installation process are the integrated project schedule, the construction summary schedule and the five-to-eight-week construction schedule. The accompanying flow charts (Figures 4-1 and 4-2) indicate the flow of activities associated with the installation and inspection of electrical equipment and electrical penetrations. Also shown is the documentation flow associated with each activity and the procedure controlling the inspection and/or O documentation flow. Figure 4-3 indicates the activity flow associated with the replacement of components sent to Unit 1 to support startup activity. Table 4-4 lists the specifications and procedures controlling these activities. 4.2.1 ELECTRICAL EQUIPMENT Electrical equipment installation requirements are contained in Construction Specification X3AR01, sections E2 and E12, and vendor documents. Equipment mounting details are specified on the AX2D11R drawing series. Field Procedures ED-T-04, CM-T-03, CM-T-04 and GD-T-11 were developed from the construction specification and contain installation instructions, responsibilities, inspection attributes, and documentation requirements. Figure 4-1 illustrates the installation, inspection, and maintenance activities associated with major electrical equipment and the documentation flow corresponding to each activity, along with the procedure controlling each activity. This flowchart contains nine major node points that represent hold points for which preceding inspection activity must be completed in order to continue with the installation process. The flowchart does not illustrate the flow of documents such as Deviation Reports (DRs) or Field Change Requests (FCRs) as they O may be generated at any time. 0152f/337-7 4-15
The first and second nodes on the flowchart indicate the activities that the Warehouse, Quality Control (QC) lh Receipt / Inspection, and Equipment Engineering Groups perform to ensure that the equipment satisfies the requirements of the specification, is placed in the correct level of storage, and is available for issue only when vendor documentation has been received or when a conditional release is written. The third and fourth nodes on the flowchart track the equipment from the warehouse to storage of the equipment in its permanent area and include the requirements for rigging and handling the equipment and release of the equipment foundation. The fifth, sixth, and seventh nodes of the flowchart follow the equipment for orientation, assembly of sections, and the final attachment of the equipment to the foundation. These nodes show the requirements for Construction and QC to monitor document handling, location, orientation, bolt torquing, and welding of the equipment. The final two nodes concern the installation of internal jumpers, tophats, driphoods, and Field Equipment Change Orders (FECOs). The component removal process, discussed below, also occurs at this time. The process of equipment turnover / release to Nuclear Operations is shown along with steps for signing of final documentation, review of DRs, inspection of FECO packages, and listing of punchlist items. Component Removal To allow for rapid completion of Unit 1, a program was developed to allow for component transfer from Unit 2 to Unit 1. This program, controlled by Field Procedure GD-T-28 and shown on Figure 4-3, includes provisions for maintaining traceability of the removed component, ensuring that qualified replacement parts were procured in accordance with the original specification requirements, and tracking the re-installation status of the replacement. To ensure that any work performed prior to issue of the procedure was identified, the construction disciplines performed an indepth walkdown during the first quarter of 1987. 4.2.2 ELECTRICAL PENETRATIONS Containment electrical penetration installation requirements are contained in Construction Specification X3ARO1, section E3, and Vendor Manual X3AB03-34. Field Procedure ED-T-19 was developed from the constructien specification and vendor manual and contains specific installation instructions, responsibilities, inspection attributes, and documentation requirements. During the development of this module, ED-T-19 was deleted and its requirements incorporated into ED-T-04. 0152f/337-7 4-16
Figure 4-2 illustrates the installation, inspection, and maintenance activities associated with the electrical penetration assemblies in the containment building. Also included is the documentation flow corresponding to each activity along with the procedure that requires the document to be initiated. This flowchart reflects the use of ED-T-04 as the controlling procedure and contains seven major nodes that represent hold points for which preceding activities must be completed prior to continuing the installation process. DRs and FCRs are not represented in the flow of documents as they may be generated at any time. The first two nodes illustrate the activities that are performed prior to installation of the penetration assemblies. These activities cover the equipment maintenance requirements, the installation and inspection of the penetration nozzle inside ci outside mounting rings, the equipment requisition and issue for traceability of equipment, and the equipment maintenance while in storage in the work areas. The third and fourth nodes illustrate the installation of the penetration feed-through module, enclosure boxes, and pressure switch. The initial leak rate test is performed when the penetration feed-through module is installed. The final leak rate test is performed after the pressure switch and the pressure monitoring pipe are installed. After the successful completion of the final leak rate test, the engineer initiates a OA request for Nuclear Operations to perform the electrical tests and the leak test. The engineer also notifies the Construction Maintenance Organization to periodically monitor the pressure of the assembly. The fifth and sixth nodes illustrate the tests performed by Nuclear Operations, the review of the test results by the engineer for acceptability, the QC function for completion of paperwork, and the periodic monitoring of the penetration pressure. The seventh node represents the cable pulling and termination to the penetration assembly. These functions are covered in Module 12 and are performed prior to turnover of the penetration assembly to Nuclear Operations. O 0152f/337-7 4-17
i I I l l l 4.3 PROGRAM CHANGES b v Several programs have been modified or added since completion of 2 the Unit 1 Readiness Review Program to reflect the effort of ! management to incorporate lessons learned from Unit 1, and to reflect construction interface with an operating unit. The major changes affecting the scope of this module are: o Initiation of the component removal p2.ogram to accommodate the immediate needs of tb3 operating unit. (reference 4.2.1). 1 o Transfer of design responsibility to personnel located at the jobsite. (reference 2.2). l o Addition of interdiscipline separation criteria to upfront installation and inspection activities, and less i reliance on after-the-fact finalization walkdowns. (reference 4.1.4). o Consolidation of penetration and equipment installation procedures. (references 4.2.2). O C e O 0152f/337-7 4-19 '
O O O TABLE 4-1 INTERDISCIPLINE DESIGN CRITERIA Designation Principal Number Title and Description Responsibility DC-1001 Separation - This document provides design bases to ensure that systems, Plant Design components, and structures important to safety are adequately separated. DC-1002 Fire - This document provides design bases for preventing and mitigating Mechanical the consequences of fires. DC-1003 Flooding - This document provides design bases to ensure that safety- Nuclear related systems and structures are protected against flooding caused by postulated pipe breaks or activation of the fire protection system. DC-1005 Seismic - This document provides bases for designing systems, structures, Civil / and equipment having safety impact to withstand seismic events. Structural DC -1006 Missiles - This document presents the criteria for analysis of Nuclear internally generated missile hazards. DC-1007 Environmental - This document provides design bases for environmentally Nuclear qualifying safety-related equipment to ensure that it will perform its required safety functions during normal, abnormal, test, accident, and post-accident conditions. DC-1009 Plant Single-Failure Criteria - These criteria provide design bases to Nuclear ensure that safety-related systems can perform their safety functions in the event of a single failure. DC -1010 Pro _iect Classification List - This list defines the extent to which Nuclear components, equipment, and structures are related to nuclear safety and seismic qualification requirements. It also identifies the principle codes and standards. DC-1018 Pipe Break Criteria - This document defines the criteria to be used Nuclear for determining the types of pipe breaks, their locations and their effects. OlS3f/337-7/1 _ _ _ _ - - - _ _ - _ _ _ _ _ _ _ _ ~ _ _ _ . _ . - _ _ - -
O- O V b] U TABLE 4-2 (SHEET 1 0F 2) SYSTEM DESIGN CRITERIA Designation Number Title and Function Subject DC-1801 Offsite Power System - The offsite power system Reserve auxiliary trans-provides the normal source of electric power for formers, 4160-V cable bus. the Class lE distribution system and also supplies the non-Class lE distribution system during startup or shutdown operations. DC-1804 ac System-4160 V - The 4160-Vac system distributes 4160-V switchgear. electric power to 4-kV auxiliary loads and to the 480-V subsystem. DC-1805 ac System-480 V - The 480-Vac system transforms 480-V unit substations, power f rom the 4160-V or 13,800-V systems and 480-v motor control centers. distributes it to 480-V auxiliary loads. DC-1806 dc System-Class 1E - The 125-Vdc Class 1E system Batteries, battery chargers provides a reliable source of power for safety- 125-Vdc switchgear,125-Vdc related control, instrumentation and motor loads. DC-1807 120-Vac Power System - The 120-Vac system consists of Inverters, distribution vital (Class 1E) and essential (non-Class 1E) power panels, regulated trans-sources providing 120-V power for control / formers. instrumentation. 0C-1809 Cable System - The cable system provides electrical 4160-V cable bus, electrical connections for power, control, and instrumentation. penetration assemblies. DC-1815 Switchyard Interfaces - The switchyard interface Reserve auxiliary criteria provide the design bases for interfaces t rans f ormers . between the high-voltage switchyard systems and plant generation and electrical auxiliary systems. 0153f/337-7/2
O. O 0: TA8LE 4-2 (SHEET 2 0F 2) Designation Equipment Number Title and Function Covered s DC-1816 Multisystem Panels and Boards - The multisystem panels Panels: auxiliary relay iso-and boards provide electrical protection and auxiliary lation device, protective control functions. relay, local control. Boards: electrical auxiliary, safety features sequencer. DC-1818 Electrical Penetration System - The electrical Electrical penetration penetration system provides electrical connections assemblies. , for power, control, and instrumentation inside the containment, while ensuring containment pressure boundary' integrity in_the event of an accident. DC-1821 Standby Power System - The standby power system pro- Safety features, sequencer vides electrical power to safely shut down and isolate boa rds , the reactor under any operating and accident condition. DC-1823 Electrical Protection Criteria - The electrical protec- 4160-V switchgear, 480-V criteria serve as a guide for determining the protec- switchgear, 480-V motor . tive relaying required for plant electrical equipment. control centers, 125-Vdc switchgear,125-Vdc MCCs, 120-Vac distribution panels, protective relay panels. DC-1825 aC System - 13800 V - This system provides power to 13.8-kV RCP switchgear. the Reactor Coolant Pumps (RCSs) f rom the Of fsite Power System. 0C-1826 High-Voltage Switchyard - The high-voltage switch- Switchyard, 500/230-kV yard distributes generated power to the transmission auto transformer banks. grid and supplies of fsite power to the plant auxili-aries via the reserve auxiliary transformers. 0153f/337-7/3 '
O O O , TABLE 4-3 (SHEET 1 0F 3) ELECTRICAL CALCULATIONS Calculation Designation No. Calculation Title and Subject Transformer System X3CA02 Unit Auxiliary Transformer Sizing (determines adequacy of transformer tap setting, NVA, and impedence rating) X3CA03 Reserve Auxiliary Transformer Sizing (determines adequacy of transformer tap setting, MVA, and impedence rating) X3CA03-1 Auxiliary Power System Voltage Study (determines that the electrical auxiliary system meets the requirements of Branch Technical Position PSB-1, dated July 1981, revision 0) , X3CA04 Load Center Transformer 1NB01 Sizing (typical) (determines adequacy of transformer tap setting) X3CA05 Main Transformer Sizing (determines adequacy of transformer tap setting, MVA, and impedence rating). Auxiliary System Short Circuit X3CCO2 480-V Breaker Short-Circuit Sizing (determines short-circuit ratings of 480-V system power and molded-case circuit breakers) X3CCl4 Bus Transfer - Final Recommendations (finalized bus transfer schemes to be implemented on the non-Class lE buses and present recommendations for , relays to supervise the transfer) 0153f/337-7/4
O O O TABLE 4-3 (SHEET 2 0F 3) Calculation Designation No. Calculation Title and Subject Auxiliary System Voltage Regulation Studies X3CD04 Station Auxiliary Voltage Regulat' ion (determines tap requirements for the station auxiliary transformers) Diesel Generator System X3CE01 Diesel Generator Loading (tabulates loads on Diesel Generators) X3CE400 EE-400 Load Study Program (periodically updated calculation that provides a data base of plant ac auxiliary power system loads and totals bus loadings) 120 VAC System X3CH01 120 Volt AC Vital Bus Loading (determines acceptability of Vital AC voltage levels) Battery, Battery Charger, and Inverter Systems X3CF02 Class lE Battery Systems (determines Class lE battery sizes and charger capacity ratings) X3CF07 dc Breaker Sizing (determines dc system breaker and bus short-circuit ratings) 0153f/337-7/5
O O O TABLE 4-3 (SHEET 3 0F 3) Calculation Designation No. Calculation Title and Subject Cable Bus Sizing X3CK04 Cable Bus or Nonsegregated Phase Bus Sizing (13.8-kV and 4.16-kV) Electrical Penetration X3CM01 Electrical Penetrations Short-Circuit Currents (determines acceptability of electrical penetration feedthroughs to withstand fault currents) Grounding System X3CN07 Maximum Line-to-Ground Fault Value 13.8-kV and 4.16-kV System Unit 1 Miscellaneous Systems X3C107 480-V MCC Field Cable Weight File X3AC01 Plant Vogtle Relay Documentation (calculations and relay set points)
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r T TABLE 4-4 O INSTALLATION SPECIFICATIONS AND PROCEDURES Document Number Document Title Construction Specifications X3AROl-E2 Station Service Equipment X3AROl-E3 Reactor Containment Electrical Penetrations X3AROl-E12 Installation Procedures for Electrical Equipment GPC Field Procedures CM-T-03 Inspection of Items in Storage CM-T-04 Maintenance of Items in Storage ED-T-04 Installation of Major Electrical Equipment ED-T-19 Installation of Electrical Penetration Assemblies (incorporated into ED-T-04 during the assessment) GD-T-ll Rigging, Hoisting, and Transporting of Permanent Plant Equipment GD-T-25 Changes to Supplier Equipment at the Jobsite GD-T-28 Component Removal O 0157f/336-7/1
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(} 5 AUDITS AND INSPECTIONS
5.1 INTRODUCTION
Module section 5 contains a listing of Quality Assurance (QA) audits, Nuclear Regulatory Commission inspections, and special evaluations performed in the area of electrical equipment. These design and/or construction audits were conducted by Georgia Power Company and Bechtel Western Power Company QA personnel in order to provide assurance that design and construction processes function as required by 10 CFR 50, Appendix B; the project QA program; commitments defined in the Final Safety Analysis Report; and the Design (Criteria) Manual. The resulting findings or violations applicable to electrical equipment 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. l 0137f/341-7 5-1
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 from an audit is reported to the management of the audited organization for corrective action. The audit report at the end of this section lists the audits conducted and findings issued since completion of the Unit 1 module. 5.2.1 GEORGIA POWER COMPANY AUDITS AND FINDINGS GPC QA audits are performed in functional areas such as equipment, piping, cable installation, etc., and are readily identifiable to module scopes. GPC QA conducted 14 audits within the scope of this module. These audits resulted in eight findings, which identified ; discrepancies in documentation requirements and incidences of hardware nonconformance. For each finding, the extent and significance of the discrepancy were identified and adequate corrective action was taken to resolve the deficiency. 5.2.2 BECHTEL WESTERN POWER COMPANY AUDITS AND FINDINGS BWPC QA audits are generally performed in design functional areas such as drawings, calculations, and Field Change Requests, and are applied to all disciplines, rather than a specific ; discipline or hardware category. Therefore, it is impractical to assign audits to a specific module; however, findings were categorized by module. The three findings within the scope of this module identified only minor documentation discrepancies, were resolved by correction of the appropriate document, and did 1 not affect the adequacy of the design. O 0137f/341-7 5-3
(} 5.3 NUCLEAR REGULATORY COMMISSION INSPECTIONS The Nuclear Regulatory Commission conducted five inspections related to this module. These inspections resulted in three violations. Violation 85-43-01 identified electrical equipment which was not stored in a manner to preclude damage from adjacent construction activity. Violation 85-60-01 addressed the failure to identify Unit 1 design changes which were also applicable to Unit 2. Violation 86-109-01 identified a deficiency in the performance of moment loading calculations for electrical penetration assemblies. Corrective action for all violations was initiated and completed. O O 0137f/341-7 5-5
)
l 5.4 REPORTABLE AND POTENTIALLY REPORTABLE ITEMS Since completion of the Unit 1 module, 11 deviating conditions in the plant applicable to the scope of this module have required formal evaluation for reportability on Deficiency Evaluation Reports (DERs). Of these, four were determined to be reportable per the requirements of 10 CFR 50.55(e) and assigned three construction deficiency report (CDR) numbers. These are discussed below. DER-125 (CDR-M103) identified that several regulating transformers used as isolation devices do not have the required six-inch separation between field cabling and the terminal blocks. The evaluation concluded that hardware modification was required to preclude failure of the isolation mechanisms and possible degradation of the Class 1E power sources, and was determined to be reportable under 10 CFR 50.55(e). DER-141 and -142 (CDR-M104) identified the lack of interdiscipline seismic separation criteria, resulting in potential seismic interferences with electrical equipment. Evaluation of this condition identified seven pieces of equipment where impact loads would be significant and could possibly cause loss of function. The hardware was modified. This condition was reportable under 10 CFR 50.55(e). DER-168 (CDR-M126) identified that during the Unit 1 containment O, integrity testing, electrical penetrations were found to be leaking at a rate in excess of the allowed design leakage rate. The deficiency was determined to be caused by a hole drilled by the vendor in the penetration header plates during manufacturing. The vendor had failed to seal the hole subsequent to factory testing. A Field Change Request was generated to seal the opening with a welded plug per vendor instructions. All affected Unit 2 penetrations were inspected and found to have plugs welded in place as required. This condition was reportable under 1.0 CFR 50.55(e) I t n 0137f/341-7 5-7 l
F 5.5 UNIT 1 FINDING FOLLOWUP C) Unit 1 finding followup consisted of identification of all findings and corresponding corrective actions as a result of Unit 1 Readiness Review or Nuclear Regulatory Commission evaluation of the Unit 1 modules. For Unit 2, a list of those findings was compiled and transmitted to the Project to evaluate and to determine the following: o If the finding was an isolated occurrence in Unit 1 and did not require Unit 2 action (or was applicable to Unit 1 only). o If corrective action taken for Unit 1 remains in place and acceptable. c Tf corrective action in place for Unit 2 has changed from that specified in the Unit 1 module, but is still acceptable. o If corrective action taken for Unit I has not been entirely effective in Unit 2 and therefore has been modified. For each finding that the Project determined was applicable to i Unit 2, a response was returned to Readiness Review that stated O which documents identified the corrective action required, any changes to committec'. actions, and action taken if corrective action was not effective. The listing at the end of this section presents the findings, the type of action taken for Unit 2, and explanations if corrective action was changed or not entirely effective. Selected findings were included in the assessment discussed in section 6 to provide independent Readiness Review verification of the project evaluation results. Seventy one Unit 1 findings were identified as applicable to Module 6. The Project Design and Construction Departments evaluation of these findings concluded that all but one, 6-037, were properly addressed in Unit 2 programs. Unit 1 Readiness Review Finding 6-037 addressed inadequate seismic separation criteria for electrical equipment. The corrective action for this finding involved the revision of appropriate construction specification selections to add or clarify the seismic separation criteria for electrical components. Subsequent to the Unit 1 Readiness Review effort, seismic separation requirements applicable to the installation of certain mechanical equipment were erroneously specified as optional. This resulted in uncertainty concerning the adequacy of seismic reparation between mechanical and electrical equipment, Action has been taken to re-establish clear seismic . separation criteria to ensure adequate separation as discussed in the response to Finding 2RRF-004-009 in Module 4. Ol37f/341-7 5-9
Page No. I 10/19/87 PLANT WOGTLE UNIT 2 RE Af*INESS HEVIEW PHOGRAM QUALITY ASSUHaNCE AUDITS TABLE 5-1
= = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = ====
AUDITING AUDIT FINDING ORGANIZATION NUMBER ' NUMBER LEVEL DATE SUBJECT NEMARKS
============= ============= =========== ===== ======== ====s======== a================================ = ========a= _. == = .= :2; BWPC CAR. W H F-II- I I - 86 05/29/86 HR FINDING 6-87 CALC NOT HEVISED. FSAR NOT UPDATED. DESIGN CRITERIA NOT REVISED. EVALUATION OF A DER NOT COMPLETED & PROJECT INVESTIGATION OF NON-CLASS IE MOTORS NOT CONCLUDED BY DATES COMMITTED BNPO CAN. RHF-H-16-86 07/03/86 HR FINDING 6-92 I&C & C/S NOT ADDED TO REVIEW CYCLE FOR DC-1818 BY DATE COMMITTED BWPC CAR VH-86/102 07/31/86 FAILURE MODE AND EFFECT ANALYSIS (FMEA) NOT PERFORMED AND FSAR NOT HEVISED FOR LATEST CHANGES TO FMEA*S GPC QA CP02-85/77 10/31/85 CANNIBALIZAITON OF MECHANICAL. ELECTRICAL. AND INSTRUMENT & CONTROL COMPONENTS t
GPC 04 CP02/CP05-86/ AFH 0963 II 09/10/86 NO OBJECTIVE EVIDENCE OF TESTING ADMINISTERED TO CP02/CP05-86/4G 46 ELECTRICAL FIELD OPERATIONS OR CLEVELAND ELECTRIC PERSONNEL GPC QA CP07-87/07 03/09/87 AUDIT OF EFO,'CE EQUIPMENT INSTALLATION /PHOTECTION GPC QA CP07-87/07 AFH 1006 II 03/09/87 TEN TRAY SECTIONS IN CONTHOL BUILDING WERE CP07-87/07 ACCEPTED AND VAULTED YET THE 6" SEPARATION PETWEEN THE LAST TRAY AND EQUIPMENT WAS NOT IN CONFORMANCE WITH PHOJECT REQUIREMENTS GPC QA CP09-85/86 12/18/85 INSTALLATION OF COMPONENTS IN ELECTHICAL SUBSYSTEM IGA 02-03 ESSENTIAL CHILLED WATER-THAIN B GPC QA CP09-86/14 03/27/86 INSTALLATION OF ELECTHICAL COMPONENTS WITlilN THE CONTAINMENT SPRAY SYSTEM GPC QA CP09 -86/60 01/16/87 EVALUATION OF CLEVELAND ELECTRIC'S CONTROLS APPLIED DURING FABHICATION. INSTALLATION. AND INSPECTION OF ELECTHICAL SYSTEMS ON UNIT 2 GPC 04 CPO9-86/60 AFH 0995 II O2/25/H7 INVERTER WELDED USING SHIMS NOT SPECIFIED ON DWG. DETAIL PER ED-T-04. ALSO. A FCH (INSTEAD OF A DH. PER GD-T-01) WAS GENERATED TO DOCUMENT COMPLETED WOHh ON AN AS-BUILT CONDITION AND TO OBTAIN APPHOVAL
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O O O Page No. 2 10/19/87 PLANT VOGTLE UNIT 2 READINESS REVIEW PROGRAM QUALITY ASSURANCE AUDITS TABLE 5-1
==================================-== .= ==
AUDITING AUDIT FINDING ORGANIZATION NUMBER NUMBER LEVEL DATE SUBJECT REMARKS
============= ============= =========== ===== ======== ================================================= ===================2==
GPC QA CP09-86/60 AFR 0996 III 01/16/87 ALL CRAFT PERSONNEL NOT BEING TRAINED ON CP09/86/60 INSTALLATION OF EQUIPMENT AS REQUIRED BY PROJECT PROCEDURES GPC QA CP09-87/12 04/02/87 AUDIT OF RECEIPT INSPECTION THROUGH INSTALLATION OF THE UNIT 2 MAIN CONTROL BOARD INCLUDING AN IN-DEPTH LOOE AT THE STATUS OF ELECTRICAL COMPONENT REMOVALS GPC QA CP09/TP02-86/ 08/05/86 INSTALLATION OF ELECTRICAL COMPONENTS WITHIN THE 37 AUXILIARY COMPONENT COOLING WATER (ACCW) SYSTEM GPC QA cpl 7-86/36 07/l7/86 IMPLEMENTATION OF CORRECTIVE ACTIONS PERTAINING TO READINESO REVIEW FINDINGS REGARDING INSTALLATION OF CABLE TRAYS GPC QA CP20-85/76 10/21/85 ELECTRICAL SUPPORTS GPC QA CP20-85/76 AFB 855 II 10/21/85 INADEQUATE CLEARANCE BETWEEN SUPPORTS AND EQUIPMENT GPC QA SP01-86/51 10/09/86 PLANNED AND SYSTEMATIC CONTROLS APPLIED IN FINALIZATION WALEDOWN PROGRAM GPC QA SP01-86/51 AFR 0970 II 10/09/86 INADEQUATE FINALIZATION PROGRAM PROCEDURES GPC QA SP01-87/17 04/28/87 AUDIT OF INSTALLATION AND PROTECTION OF ELECTRICAL EQUIPMENT THAT HAS BEEN DESIGNATED APPLICABLE TO READINESS REVIEW MODULE 6 ASSESSMENT GPC QA SP01-87/37 08/05/87 READINESS REVIEW MODULE 6 PART 3 ELECTHICAL EQUIPMENT INSTALLATION GPC QA SPOl/OP24-86/ AFR 0014 II 01/20/87 DISCREPANCIES IN NUMBER & TYPE OF ANCHOR BOLTS 10 USED ON ELECTRIC PENETRATIONS & NSCW PUMPS GPC QA SP01/OP26-86/ 08/20/86 IMPLEMENTATION OF CORRECTIVE ACTIONS PERTAINING 42 TO PEADINESS REVIEW FINDINGS l GPC QA SPOl/OP26-86/ AFR 0957 II 01/I4/87 DRAWINGS AND QC DOCUMENTS NOT ATTACHED TO FECO'S 42 3 % ,-- ., -w. ., , , _ , , , , -- - v- . - t, -c- - - - - - ~
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O O O Page No. 3 10/19/87 PLANT V0GTLE UNIT 2 READINESS REVIEW l' HOG R AM OUALITT ASSURANCE AUDITS TABLE 5 -1
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AUDITING AUDIT FINDING OkGANIZATION NUMBER NUMBER LEVEL DATE SUBJECT HEMAWKS
============= ============= =========== ===== ======== ==================c == ========_======. ===e===== ==_ ===_=_ _ _= . ===2 GPC QA TP02/OP26-87/ 05/27/87 AUDIT OF TURNOVER ACTIVITIES TO ENSURE 23 DEVELOPMENT AND IMPLEMENTATION OF PROCEDURAL CONTHOLS FOR A SMOOTH TRANSITION BETWEEN CONSTH.
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I Page No. l 10/19/87 .I PLANT VOGTLE UNIT 2 READINESS kEVIEW PROGRAM NRC INSPECTIONS T TABLE 5-2
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INSPECTION FINDING ORGANIZATION NUMBER NUMBER LEVEL DATE SUBJECT kEMARKS l
============= ============= =========== ===== ======== ======================================= ======_== ======================
L NRC 424/85-043.42 VIOL IV 10/17/85 VALVES AND ELECTRICAL PANEL NOT PROPERLY STORED I , INSPECTION 5/85-032 85-43-01 AND/OR PROTECTED IN UNIT " NRC 424/86-109 VIOL IV 12/10/86 TOTAL WEIGRT OF CABLE NOT CONSIDERED IN INSPECTION 86-109-01 PERFORMING MOMENT LOADING CALCULATION ELECTRICAL PENETRATION ASSEMBLY NRC 424/86-060.42 VIOL IV 09/04/86 UNIT I DESIGN CHANGES IMPROPERLY EVALUATED AS NOT INSPECTION 5/86-027 86-60-01 APPLICABLE TO UNIT 2
- NRC 424/87-015 03/24/87 INSPECTION OF EMPLOYEES CONCERNS. LICENSEE EVENT INSPECTION 425/87-011 REPORTS. AND CONSTRUCTION DEFICIENCY REPORTS PERTAINING TO ELECTRICAL EQUIPMENT AND RACENAYS NRC 425/87-022 05/28/87 REVIEN OF UNIT 2 AREAS--FIRE PROTECTION.
INSPECTION CONCRETE. REACTOR VESSEL. CONTAINMENT STRUCTURES. PIPING AND SUPPORTS. SAFETY-RELATED COMPONENTS. AUXILIARY SYSTEMS. ELECTRICAL EQUIPMENT. RACEWAYS. INSTRUMENTATION. QUALITY PROGRAMS AND ADMINISTRATIVE CONTROLS 6 4.
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U i Page No. I 12/07/87 PLANT WOGTLE UNIT 2 READINESS REVIEW PROGRAM REPORTABILITY EVALUATIONS TABLE 5-3
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EDIT EVALUATION NO ORGANI2ATION NUMBER DATE SUBJECT REMARKS e=== ============= =========== ======= ====================== ========================== ==============v======= 114 BPC DER 108 REV. O 10/03/85 MOV'S PROCURED TO OPERATE FROM 105 TO 140 VDC ON , 100 TO 140 VDC POWER *.YSTEMS 125 BPC DER 120 REY. O I2/12/85 POTENTIALLY DEFECTIVE NAMCO LIMIT SWITCHES ON MOV'S 129 BPC' DER 124 REV. O 01/20/86 MOTORS FOR OPERATING FISHER BUTTERFLY VALVES FURNISHED WITH INCORRECT OPERATING SPEED 130 BPC DER 125 REV. 0 02/04/86 INADEQUATE SPACING OF FIELD WIRING ON TERMINAL M103 BLOCKS IN ISOLATION TRANSFORMERS 117 BPC DER 141 REV. 0 03/20/86 UNACCEPTABLE SEISMIC SEPARATION BETWEEN CLASS IE M104 EOUIPMENT AND RACEWAY SUPPORTS 11H BPC DER 142 REY. 0 03/20/86 INADEQUATE CLEARANCES BETWEEN SEISMIC CATEGORY I M104 ELECTRICAL PANELS I M) BPC DER 153 REY. 0 05/01/86 FLAKING POSITIVE STRAPS AND DEGRADATION OF CELL VOLTAGE FOUND IN LEAD-CALCIUM TYPE. CLASS IE STATION BATTERIES 166 BPC DER 159 REV. 0 08/06/86 INADVERTENT SWITCRYARD BREAEER TRIP CAUSED BY AN EXTRA WIRE JUMPER LOCATED IN A WESTINGHOUSE DESIGNED PANEL IN THE CHEMICAL AND VOLUME CONTROL SYSTEM 175 BPC DER 168 REY. 0 09/12/86 LEAKING ELECTRICAL PENETRATIONS IN CONTAINMENT M126 1R5 BPC DER 178 REV. 0 12/19/06 POTENTIALLY DEFECTIVE BATTERY GROUND DETECTOR RELAYS FURNISHED WITH CLASS IE 125 VDC SWITCHGEAR 191 BPC DER 184 REV. 0 07/08/R7 INCORRECTI.Y DESIGNED POWER CIRCUITS FED FROM 120 VAC DISTRIBUTION PANELS LOCATED IN MCCS.
I / () > (/ l'ag e Na. I 10/19/87 READINESS REVIEW PROGRAM FOLLOW flP OF UNIT 1 FINDINGS (RR,lDR NRC) TABLE 54
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SOURCE AND DESCRIPfl0N OF DESCRIPTION OF UNIT I DESCRIPTION OF UNIT 2 flNDING DESIGN CONST LEVEL FINDING CORRECTIVE ACTION FOLLOW-tfr ACTION
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IDR X I FINAL BATTERY VOLTAGES NOT DESIGN CRITERIA REVISED TO CORRECTIVE ACTION REMAINS 22 F00I INCORPORATED INTO CABLE DESIGN INCORI' ORATE IITV BATTERY IDENTICAL AND ACCEPTABLE CRITERIA VOLTAGE IDH X II INCORRECT USE OF VENDOR DATA ISOLATED CASE, CALC. REVISED ISOLATED INSTANCE /0NE TIME 22 F00H IN ELECTRICAL CALCS. TO REFLECT CORRECT MOTOR CORRECTIVE ACTION HORSEPOWER IDR X I DC VALVE SPECIFICATION SPECIFICATIONS UPDATED TO CORRECTIVE ACTION REMAINS 22 F010 SPECIFIED INCORRECT MINIMUM DC INCLUDE REVISED APPENDIX "AD". IDENTICAL AND ACCEPTABLE SYSTEM VOLTAGE EQUIPMENT QUALIFICATION DATA REVIEWED TO ENSilRE ACTil AL EQUIPMENT PERFORMS OE. I Dit X II INCOMPLETE ANALYSIS OF EFFECTS NO ADDITIONAL ANALYSIS CORRECTIVE ACTION REMAINS 22-F020 0F JET IMPINGEMENT ON REQUIRED. COMMITMENT TO IDENTICAL AND ACCEPTABLE PRESSURIZER REATER PONER CLARIFY FSAR SUPPLIES IDH X II THERMAL OVERLOAD SELECTION FOR ADEQUACY OF DESIGN EXPLAINED ISOLATED INSTANCE /0NE TIME 22-F02G IE MOV'S WITH MANUFACTURERS BY PROJECT RESPONSE AND VENDOR CORRECTIVE ACTION RECOMMENDATIONS DOCUMENTATION - NO CORRECTIVE ACTION REQUIRED IDH X II AUXILIARY FEEDWATER Pt;MP MOTOR DESIGN PERSONNNEL RETRAINED. CORRECTIVE ACTION REMAINS 22 F030 OVERLOAD MAY REACH THERMAL ADDITIONAL DoctfMENTATION IDENTICAL AND ACCEPTABLE LIMIT REQUESTED FROM VENDOR IDR X I INCONSISTENT IDENTIFICATION OF NOTES ADDED TO ELEMENTARY CORRECTIVE ACTION REMAINS 22-F033 EQUIPMENT FOR IEN 84-68 DIAGRAMS TO IDENTIFY USE OF IDENTICAL AND ACCEPTABLE SOLENOID VALVES NOT IDENTIFIED ECSA'S TO PROVIDE HIGH AS REQUIRING HIGH TEMPERATURE TEMPERATURE WIRE WIRE IDH I Il CALCULATION RESULTS NOT IN CALCULATION REVISED TO AGREE CORRECTIVE ACTION REMAINS 6 008 AGREEMENT WITH FSAR LOAD WITH FSAR IDENTICAL AND ACCEPTABLE git 0WTH MARGIN IDR X II SEQUENCE LOGIC SETP0lNTS AND SPECIFICATION REVISED TO AGREE COIIRECTIVE ACTION REMAINS G 00'3 TIME DELAYS DIFFER BETWEEN WITH FSAR IDENTICAL AND ACCEPTABLE SPECIFICATION AND FSAR IDH X III TYPE TEST DATA FOR MOTOR TEST DATA RECEIVED FROM CORRECTIVE ACTION REMAINS G 010 CONTROL CENTERS AND LOAD VENDORS AND Pl. ACED IN PROJECT IDENTICAL AND ACCEPTABLE CENTERS NOT AVAILABLE IN F I I.E S PROJECT VENDOR DATA FILks
O O O Page No. 2 10/19/RT READINESS REVIEW PROGRAM FOLLON UP OF UNIT I FINDINGS (RR.IDR.NRC) TABLE 5-4
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SOURCE AND DESCRIPfl0N OF DESCRIPTION OF UNIT I DESCRIPTION OF UNIT 2 FINDING DESIGN CONST LEVEL FINDING CORRECTIVE ACTION FOLLOW-UP ACTION , -,s- .=2 ~ ,2 ree:: == =:2 -- := ses ===-= 2= ,::s: :r: =-, = <===-3,22,e=======s==:r======= :s== :t :::=e=,=::ame== r= :
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i I ICR I II FACTORY BATTERT TEST NOT REVISION TO LOAD CALCULATION CORRECTIVE ACTION REMAINS 6-013 PERFORMED IN ACCORDANCE WITH ENVELOPES EXISTING TEST IDENTICAL AND ACCEPTABLE SPECIFICATION IUR I II No GUIDELINES EXIST IN DC-1816 DC-1816 REVISED TO REMOVE 4NY CORRECTIVE ACTION REMAINS 6 041 FOR USAGE F0F PVC TERMINAL RESTRICTION ON PVC LUGS IDENTICAL AND ACCEPTABLE LUGS IDR I II 480V FEED DELETED FROM VENDOR REVISED DRAWINGS TO CORRECTIVE ACTION REMAINS 6-051 INVERTERS NOT IN AGREEMENT ELIMINATE 4807 FEED IDENTICAL AND ACCEPTABLE WITN VENDOR REQUIREMENT IDR I II PROCUREMENT SPECIFICATION FSAR UPDATED TO AGREE WITR s CORRECTIVE ACTION REMAINS 6 052 I3AD01 SPECIFIES DUTT CTCLES CALCULATION TRAT CRANGED IDENTICAL AND ACCEPTABLE INCONSISTENT WITH THE FSAR SPECIFICATION f IDH I I CALCULATION DOES NOT INCLUDE SIX CALCULATIONS REVISED TO CORRECTIVE ACTION REMAINS 6-076 SOURCE OF ASSUMED LOADS INCLUDE APPLICA8LE SOURCE DATA IDENTICAL AND ACCEPTABLE RRF I III PROCEDURE DOES NOT ADDRESS PROCEDURE REVISED TO INCLUDE CORRECTIVE ACTION REMAINS 6 001 APPROVAL OR PROCESSING OF APPROVAL AND PROCESSING IDENTICAL AND ACCEPTABLE EQUIPMENT REQUISITIONS REQUIREMENTS RRF I III INSPECTION REPORTS FOR PROCEDURE CRANGED TO REFLECT CORRECTIVE ACTION REMAINS 6-002 PENETRATIONS ARE NOT PROCESSED ACTUAL DOCUMENT FLOW IDENTICAL AND ACCEPTABLE PER PROCEDURE RRF I III EE580 CARDS NOT FILED PER CARDS RE-FILED ISOLATED INSTANCE /ONE TIME 6-003 PROCEDURE CORRECTIVE ACTION RRF I III NO EVIDENCE EXISTS TRAT PROCEDURE REVISED TO REQIIIRE CORRECTIVE ACTION REMAINS 6 004 PENETRATION TEST RESULTS WERE SIGNITURE OF ENGINEER IDENTICAL AND ACCEPTABLE ; REVIEWED AND ACCEPTED PER PROCEDURE RRF I III PENETRATION RAS CABLE ColLED REMOVED CABLE ISOLATED INSTANCE /0NE TIME 6-005 ON TOP CORRECTIVE ACTION HRF I III ED-7-19 CONTAINS CONFLICTING PROCEDURE REVISED TO AGREE CORRECTIVE ACTION REMAINS 6 006 REQUIREMENTS WITR %ESSOR REQUIREMENTS IDENTICAL AND ACCEPTABLE RRF I Ill PENETRATIONS ROTATED PRIOR TO NONE ISOLATED INSTANCE /0NE TIME 6 007 DRAWING REVISION CORRECTIVF ACTION
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O n g,9 No. 3 10/I9/H7 HEADINESS REVIEW PROGRAM FOLI.0W- IIP OF IIN IT I FINDINGS (RR.IDR NRC) , TABLE 5-4
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SolfRCE AND DESCRIPTION OF DESCRIPTION OF IfMIT I DESCRIPTION OF UNIT 2 FINDING DESIGN CONST LEVEL FINDING CORRECTIVE ACTION FOLLOW-UP ACTION
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RRF X I VENDOR AND FIELD WIRING OF WIRING ANALYZED, FIELD WIRING CORRECTIVE ACTION REMAINS G-OlG REGULATED TRANSFORMERS DO NOT MODIFIED IDENTICAL AND ACCEPTABLE MEET SPEARATION REQUIREMENTS RRF I 11 SWITCHGEAR WELD NOT PER VENDOR EXISTING W3LDS ANALYZED, CORRECTIVE ACTION REMAINS G-017 DRAWING ACCEPTED AS IS IDENTICAL AND ACCEPTABLE j r RRF X III INSTALLATION DOCUMENTS POCUMENTS RE-FILED CORRECTIVE ACTION REMAINS G 020 MISFILED IN VAULT IDENTICAL AND ACCEPTABLE < HRF I III DEVIATION REPORTS NOT FIELD FROCEDURE CHANGED, DR'S CORRECTIVE ACTION REMAINS G 021 WITH ASSOCITED COMPONENT ENTERED INTO RMS SYSTEM IDENTICAL AND ACCEPTABLE RRF X Ill INSPECTION REPORTS SIGNED OUT PROCEDURE MODIFIED TO ALLOW CORRECTIVE ACTION REMAINS G 025 0F SEQUENCE CONDITIONAL WORE RELEASE IDENTICAL AND ACCEPTABLE i RRF X II BATTERIES AND RACES NOT COMPONENTS LABELED WITH PLANT CORRECTIVE ACTION REMAINS I 6 027 - PERMANENTLY IDENTIFIED TAG NUMBERS IDENTICAL AND ACCEPTABLE RHF X III SIDE PANEL OF SWITCHGEAR DAMAGE REPAIRED ISOLATED INSTANCE /0NE TIME G 029 DAMAGED CORRECTIVE ACTION a RRF X III EMSL CARDS NOT ON FILE FOR CARDS LOCATED AND FILED ISOLATED INSTANCE /0NE TIME G--030 EQUIPMENT CORRECTIVE ACTION i RRF X I CABLE TRAY SUPPORT HAS ALL EQUPMENT WALEED DOWN, CORRECTIVE ACTION REMAINS G 032 INADEQUATE CLEARNANCE TO FIELD PROCEDURES REVISED TO IDENTICAL AND ACCEPTABLE EQUIPMENT AGREE WITH SPECIFICATION Hiti X III DC-1000-E DOES NOT REFER TO DC-1000-E REVIGED TO INCLUDE CORRECTIVE ACTION REMAINS 6-034 ASME Ill FOR MC COMPONENTS ALL REFERENCES FOR IDENTICAL AND ACCEPTABLE , CODES / STANDARDS IN ELECTRICAL DESIGN CRITERIA RRF X III FCR*S USED IN LIEU OF FECO*S FCR'S IIEVIEWED, PRM REVISED CORRECTIVE ACTION REMAINS G 036 170 MAKE TECHNICAL CHANGES TO IDENTICAL AND ACCEPTABLE E0lll PME N T HRF X I SEISMIC SEPARATION ALL EQUIPMENT WALKED DOWN, CORRECTIVE ACTION NOT ENTIRELY 6-037 REQUIREMENTS FOR ELECTRICAL CONSTRUCTION SPECIFICATION EFFECTIVE ITEMS OTHER TIIAN CONTROL X3AR01 SECTIONS E2 & E8 55P SECTION 5.5 PANELS NOT SPECIFIED REVISED e - . - . . . - . . . , , _-.-,_a - , - . . . _ 2. . - . y 3.. ..w . . , ..~i , , . -.,a .. ,p, ,e- . , - .
i O O Page Nrn 4 10/19/87 READINESS REVIEW FROGRAM ) FOLLOW-UP OF UNIT I FINDINGS (RR.IDR.NRC) TABLE 5-4
========,==========es===:==========.=====v====
SOURCE AND DESCRIPTION OF DESCRIPTION OF UNIT I DESCRIPTION OF UNIT 2 FINDING DESIGN CONST LEVEL FINDING CORRECTIVE ACTION FOLLOW-UP ACTION e : ===::===== ===t=- s .=== -= e= ===,========================== 3:===============,============ ===============-,======== =:- RRF . X III NO ANALYSIS PEI! FORMED FOR USE DESIGN CRITERIA REVISED TO CORRECTIVE' ACTION REMAINS 1 6 039 OF PVC TERMINALS AS REQUIRED ALLOW USE OF PVC TERMINALS IDENTICAL AND ACCEPTABLE BY PROCEDURE RRF X II NO PROGRAM CONTROLS EXIST TO PROCEDUEE DEVELOPED CORRECTIVE ACTION REMAINS 6 045 ENSURE GROUNDING OF IDENTICAL AND ACCEPTABLE NON-ELECTRICAL INSTALLED EQUIPMENT RRF X III FECO PACEAGES NOT CONTROLLED PROCEDURE REVISED TO REFLECT CORRECTIVE ACTION REMAINS 6 046 OR PROCESSED PER PROCEDURE ACTUAL WORE FLOW IDENTICAL AND ACCEPTABLE ' RRF X III DOCUMENT PACKAGES MISFIELD IN PACKAGES RE FILED CLRRECTLY CORRECTIVE ACTION REMAINS 6-047 VAULT IDENTICAL AND ACCEPTABLE RRF X III DEVIATION REPORTS PROCEDURE REVISED TO CLARIFT ISOLATED INSTANCE /0NE TIME 6-048 INCONSISTENTLT HANDLED DURING METHODS OF ORIGINATING AND CORRECTIVE ACTION DISPOSITIONING PROCESSING DEVIATION REPORTS HRF X II PROCEDURE DID NOT INCORPORATE PROCEDURE REVISED TO INCLUDE CORRECTIVE ACTION REMAINS 6-049 LICENSING COMMITMENT REQUIREMENT IDENTICAL AND ACCEPTABLE REQUIREMENT
- RRF X 11 PROCEDURE DID NOT INCORPORATE PROCEDURE AND SPECIFICATION CORRECTIVE ACTION REMAINS 6-050 LICENSING COMMITMENT REVISED TO INCLUDE REQUIREMENT IDENTICAL AND ACCEPTABLE REQUIREMENT RRF X III COVER AND DUST FILTER LOOSE ON PROCEDURE REVISED TO CLARIFY CORRECTIVE ACTION REMAINS 6 054 ' EQUIPMENT REQUIREMENTS IDENTICAL AND ACCEPTABLE RRF X III INTERFACING DESIGN CRITERIA DC'S REVIEWED. INTERFACES CORRECTIVE ACTION REMAINS 6-055 NOT CONSISTENTLY LISTED IN THE ADDED IDENTICAL AND ACCEPTABLE DESIGN CRITERIA RRF X III GDC'S 2.4.5 & RG'S- DC'S REVIEWED. REFERENCES CORRECTIVE ACTION REMAINS 6-056 1.29.1.89.1.100 NOT ADDED IDENTICAL AND ACCEPTABLE CONSISTENTLY REFERENCED IN THE CLASS IE SYSTEM DESIGN
. CRITERIA RHF X !!! REQUIRED LEVEL or APPROVAL ALL ELECTRICAL DESIGN CRITERIA CORRECTIVE ACTION REMAINS 6-057 INDICATED ON DESIGN CRITERIA REVIEWED TO ENSURE PROPER IDENTICAL AND ACCEPTABLE COVER SHEET NOT COMPLIED WITH APPROVAL WAS PERFORMED m__-m_.. _ . _ . . , _ . - , . _ ,,_.,.
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I'ase No. 5 10/19fM7 READINESS RF. VIEW PROGRAM FOL LOW - t!P OF UN IT I FINDINGS (RR.IDR NRC) TABLE 5-4
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SOURCE AND DESCRIPTION OF DESCRIPTION OF UNIT I DESCRIPTION OF UNIT 2 FIMPING DESIGN CONST LEVEL FINDING CORRECTIVE ACTION FOLLON-UP ACTION , =:==,=======r ====== ====== ===== ====================== -====== =============== ============== === === = ==============r===== RRF X II CLASS lE REGULATING DESIGN CRITERIA AND CORRECTIVE ACTION REMAINS 6 060 TRANSFORMERS NOT SPECIFIFED AS PROCUREMENT SPEC. REVISED IDENTICAL AND ACCEPTABLE ISOLATION DEVICES IN PROCUREMENT SPECIFICATION OR DESIGN CRITERIA RRF X III DESIGN CRITERIA FOR RCP DC-1825 REVISED TO ADD ISOLATED INSTANCE /ONE TIME 6 061 SWITCHGEAR NOT CLASSIFED AS APPROPRIATE SAFETY-RELATED CORRECTIVE ACTION SAFETY-RELATED RFFERENCES RRF X III SEE RRF 6-057 ISOLATED INSTANCE /0NE TIME 6-062 CORRECTIVE ACTION RRF X III STANDARDS REFERENCED IN TEXT DESIGN CRITERIA REVISED ISOLATED INSTANCE /0NE TIME 6-063 0F DESIGN CRITERIA NOT LISTED CORRECTIVE ACTION IN PARAGRAPH 2.0 RRF X III EQUIPMENT LOCATION DRAWING IN DRAWING REVISED ISOLATED INSTANCE /ONE TIME 6-064 ERROR CORRECTIVE ACTION RRF X III REGULATORY GUIDE NOT DESIGN CRITERIA REVISED TO ADD ISOLATED INSTANCE /0NE TIME 6-065 REFERENCED ON DESIGN CRITERIA REFERENCE CORRECTIVE ACTION COVER SHEET RRF X III RG 1.'53 AND IEEE-379 NOT DESIGN CRITERIA REVISED TO ADD CORRECTIVE ACTION REMAINS 6-066 CONSISTENTLY REFERENCED IN THE REFERENCE IDENTICAA AND ACCEPTABLE DESIGN CRITERIA RRF X II 480V SWGR. HAS LAC BOLTS IN LAG BOLTS REMOVED ISOLATED INSTANCE /0NE TIME 6-068 BASE CilANNEL CORRECTIVE ACTION RRF X III DC-1007 AND ATTACHMENT EA DESIGN CRITERIA, CORRECTIVE ACTION REMAINS 6-071 INCORRECTLY SPECIFY BATTERY SPECIFICATION, AND IDENTICAL AND ACCEPTABLE ROOM TEMP. OF SO DEG.F ARCHITECTURAL DRAWINGS REVISED RRF X III DC-1806 REY. O NOT APPROVED SEE 6-057 ISOLATED INSTANCE /0NE TIME 6-072 BY CHIEF ELECTRICAL ENGINEER CORRECTIVE ACTION RRF X III DC-1805 DOES NOT REFERENCE BTP L731GN CRITERIA DC-1805 ISOLATED INSTANCE /0NE TIME 6 073 PSB-1 REVISED TO ADD REFERENCE CORRECTIVE ACTION RRF X III DEVIATION REPORT DISPOSITION DEVIATION REPORT ISOLATED INSTANCE /ONE TIME 6-074 NOT CLEARLY JUSTIFIED RE-DISPOSITIONED CORRECTIVE ACTION
t Page No. G-IO/19/H7
-READINESS REVIEW PROGRAM FOLLOW-UP OF UNIT I FINDINGS (RR.IDR.NRC)
TABLE 5-4
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SOURCE AND DESCRIPTION OF DESCRIPTION OF UNIT I DESCRIPTION OF UNIT 2 FINDING DESIGN CONST LEVEL FINDING CORRECTIVE ACTION FOLLOW-UP ACTION
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HRF I III SEE RRF G-057 ISOLATED INSTANCE /0NE TIME G 079 CORRECTIVE ACTION RRF X III 10CFR50 APP. J& ASTM D635 DESIGN CRITERIA DC-1000-E & CORRECTIVE ACTION REMAINS G-ORD NOT APPROPRIATELY LISTED ON DC-1818 REVISED TO ADD IDENTICAL AND ACCEPTABLE DESIGN CRITERIA COVER SHEETS REFERENCE i RRF I til DESIGN CRITERIA DIFFERS FROM DESIGN CRITERIA REVISED TO CORRECTIVE ACTION REMAINS G-081 PURCHASE SPECIFICATION MATCH PURCHASE SPECIFICATION IDENTICAL AND ACCEPTABLE RNF X III DdSIGN CRITERIA DOES NOT DESIGN CRITERIA DC-1809 CORRECTIVE ACTION REMAINS G-082 SECIFY PENETRATION CONDUCTOR REVISED IDENTICAL AND ACCEPTABI.E SsZES RRF X III CRITERIA FOR APPLICATIONS OF DC-1809 REVISED TO ADD ECSA CORRECTIVE ACTION REMAINS ! 6 083 ECSA NOT IN DESIGN CRITERIA SELECTION CRITERIA IDENTICAL AND ACCEPTABLE DRF X III SAFETY CLASS DESIGNATOR CN REVISED DC-1818 COVER SHEET ISOLATED INSTANCE /0NE TIME 6-084 COVER SHEET OF DC-1818 IS IN CORRECTIVE ACTION ERROR RRF X 111 THE RE400 LOAD STUDY PROGRAM EE400 UPGRADED TO CALCULATION CORRECTIVE ACTION REMAINS G-085 IS NOT CONTROLLED BY PRM IDENTICAL AND ACCEPTABLE RRF X ll! ASSUMPTIONS AND REFERENCES FOR CALCULATION PREPARED TO LIST CORRECTIVE ACTION REMAINS , 6-08G 120 VAC LOAD DATA NOT LISTED LOAD DATA AND ASSUMPTIONS IDENTICAL AND ACCEPTABLE ON ONE-LINE RRF X I MAXIMUM VOLTAGES DURING NORMAL CALCULATION X3CA03-1 REVISED CORRECTIVE ACTION REMAINE G 087 UNIT OPERATION AND MINIMUM AND FSAR REVISED IDENTICAL AND ACCEPTABLE VOLTAGES DURING ALL TRANSIENT VOLTAGE STEPS NOT ANALY2ED PER BTP PSB-1 RRF X III CALCULATION IS CLASSIFIED AS PROJECT CLASSIFICATION CHANGED CORRECTIVE ACTION REMAINS G-088 NON-SAFETY RELATED BUT AFFECTS AND BROADNESS REVIEW IDENTICAL AND ACCEPTABLE SAFETY RELATED ITEMS PERFORMED. PRM REVISED. ENGINEERS TRAINED RRF X 111 THE BATTERY QUALIFICATIONS SEE G 071 ADN 21-J4 CORRECTIVE ACTION REMAINS G-090 REPORT SHOWS A QUALIFICATION IDENTICAL AND ACCEPTABLE TEMPERATURE OF 75 DEG.F. WHICH IS LESS THAN THE 80 DEC.F SHOWN IN TIIE DESIGN CRITERI A - AND ENVIRONMENTAL ATTACHMENT EA
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. rag,+ N es . 7 I U / I's / ft7 j READINESS REVIEW PROGRAM ,
FOLLOW ifl' 0F UNIT I FINDINGS (RR.IDR.NRC) TABLE 5 4 r=== =:== 2=== 2=== -= :==============2===== ====== i SOURCE AND DESCRIPTION OF DESCRIPTION OF UNIT 1 DESCRIPTION OF UNIT 2 FINDING DESIGN CONST LEVEL FINDING CORRECTIVE ACTION FOLLOW-llr ACTION
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HRF X III ALL INTERFACE CRITERIA NOT DESIGN MANUAL REVISED TO CORRECTIVE ACTION REMAINS 6-091 LISTED IN DESIGN CRITERIA REQUIRE ONLY MAJOR INTERFACE IDENTICAL AND ACCEPTABLE ' LISTING RRF X III 'THERE IS NO WRITTEN PROCEDURE APPROPRIATE INTERFACE CORRECTIVE ACTION REMAINS G 092 REQUIRING INTERDISCIPLINARY DISCIPLINES ADDED TO REVIEW IDENTICAL AND ACCEPTABLE REVIEW OF INTERFACE CRITERIA CYCLE FOR DMCN'S RRF X III OUTDATED VENDOR DRANINGS STILL ADDITIONAL TRAINING PROVIDED CORRECTIVE ACTION REMAINS i 6-093 ACTIVE IN SUPPLIER DOCUMENT TO ENGINEERS IDENTICAL AND ACCEPTABLE ' REGISTER
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j i 1 l l 6 PROGRAM ASSESSMENT i
6.1 INTRODUCTION
l 1 This section describes the program developed and actions performed to ascertain whether the design and construction activities related to electrical equipment for Vogtle Electric Generating Plant Unit 2 have been adequately controlled in a j manner that continues to implement licensing commitments, to l ascertain whether the corrective actions resulting from the 1 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. l 1 The Readiness Review Team assembled for Module 6 consisted of two Readiness Review Task Force members and two members of site Quality Assurance with a total of 50 of years of combined nuclear design and construction experience. Table 6-1 lists the members of the assessment team. Approximately 1200 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, addressed project investigative action to determine possible generic implications, and described corrective actions taken. These project responses were evaluated and the findings were categorized as follows: o Level I - 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 safety concerns. o Level III - Violation of project procedures with no safety concerns. l O 0139f/337-7 6-1
6.2 PROGRAM DESCRIPTION O The Readiness Review Program evaluation of electrical equipment for Vogtle Electric Generating Plant Unit 2 consisted of three major activities. These were the review of commitment implementation; a followup on Unit 1 finding corrective actions as applied to Unit 2; and development and execution of an assessment plan to examine programs, activities, and hardware. Sections 3 and 5 of this module discuss project actions related to the commitment matrix and Unit 1 finding followup into Unit 2, respectively. The assessment for Unit 2 electrical equipment was developed to accomplish the following objectives: o Provide added assurance that project procedures continue to implement licensing commitments. o Verify that actions taken to resolve problems identified during the Unit 1 Readiness Review have been effective in preventing recurrence in Unit 2. o Verify that program and organizational enhancements made for Unit 2 have maintained the quality of the design and construction effort. () o Assess the compliance of design completion and design change activities against engineering procedure controls, o Assess the compliance of installed hardware against engineering and vendor requirements. The assessment and results are discussed in the following sections. i i i \_) Ol39f/337-7 6-3 I i
I 6.3
SUMMARY
AND CONCLUSIONS Module 6 addresses Unit 2 safety-related (Class lE) electrical equipment. Verification that the design and construction processes and results meet licensing commitments was accomplished by visual examination of a selected hardware sample and by reviewing design and construction documents related to the selected hardware. Plans for selection of a verification sample and verification attributes were developed to ensure comprehensive coverage of the various types of hardware and documents. , The hardware sample selected consisted of seven pieces of equipment and four penetrations. Documentation assessed was directly related to the hardware sample. Design and installation activities were essentially identical to those ; assessed in Unit 1. Assessment actions primarily concentrated on: o Equipment installation and modification activity. I o Design change and design completion activity. ; The assessment addressed three issues: o Implementation of licensing commitment requirements. 1 O o Unit 2 application of corrective actions resulting from l 1 the Unit 1 Readiness Review. ' o Evaluation of the effects of program enhancements and newly developed programs. The above assessments resulted in nine findings, one of which was classified as Level I, two as Level II, and six as Level III. The Level I finding (Finding 2RRF-006-Oll) identified a difference between the wiring fire separation criteria stated in the Final Safety Analysis Report and those listed in Construction Specification X3AR01. Preliminary evaluation of this finding resulted in the issuance of Deficiency Evaluation Report (DER) DER-186 and has been reported to the Nuclear Regulatory Commission presently as potentially reportable. March, 1, 1988. Submittal of the final evaluation is scheduled for The Level II and III findings were judged to be instances of procedure noncompliance or inadequate procedures with no safety concern and do not indicate, either individually or collectively, a programmatic concern. Collective evaluation of the Level II and III findings resulted , in no areas of concern beyond the specific findings. With ! correction of the specific Unit 2 findings identified in this l (' ~' module, design and construction activicies within the scope of this module will comply with licensing commitments. 1 Ol39f/337-7 6-5
The evaluation and corrective actions that are controlled by the normal project process of resolving DERs ensure that design and construction activities relating to electrical separation (Finding 2RRF-006-Oll) will comply with licensing commitments. The individual findings and the Project responses are presented in section 6.5. O i 1 9 j Ol39f/337-7 6-6 1
6.4 ASSESSMENT ACTIVITIES AND RESULTS The majority of the Readiness Review activity for this module concerned the development and implementation of an assessment plan to provide a systematic review of activities, programs, and hardware associated with electrical equipment. This assessment was performed to provide added assurance that the Project continued to comply with licensing commitments. This section describes the d velopment and implementation of the plan and the results of the assessment. The assessment was organized into three parts: l o Part 1 - Commitment Implementation and Unit 1 Finding , l Followup. I o Part 2 - Design and Construction Programs and Activities. o Part 3 - Design and Construction Completion. As a preparatory activity for development of the assessment plan, Readiness Review examined the information presented in Section 5 of this module Caudits, Nuclear Regulatory Commission (NRC) items, etc.! to ensure that areas with a past history of l deficiency or weakness at Vogtle Electrical Generating Plant or l within the industry were factored into the assessment. () The following were evaluated for inclusion in the assessment: o Quality Assurance Audit Finding Reports and Corrective Action Requests. o NRC Violations. o Quality Concerns, o Inductry Problems (from inspection and enforcement notices and bulletins). o Licensee Event Reports form VEGP Unit 1. l This review and evaluation identified the following issues that { were included in the assessment plan. Issue Source Where Addressed Equipment Qualification QA AFR Part 2 Field Equipment Change QA AFR Parts 2 and 3 Orders O Ol39f/337-7 6-7
Protection of Equipment NRC Violation Parts 2 and 3 Quality Concerns Welding of Equipment to Quality Concerns Part 2 Foundations Penetration Leakage Deficiency Part 3 Evaluation Report Reportable Item A compilation cf problems encountered during the Unit 1 startup phase was obtained from Operations and was reviewed to identify those problem areas related to design or construction activities. Additionally, copies of the NRC inspections of Comanche Peak, Browns Ferry, Sequoyah, and Watts Bar for 1985, 1986, and the first quarter of 1987 were obtained from the NRC public document room and were examined to identify any new areas of industry concern. Within the scope of this module, no problem areas were identified from these sources that were not already identified from other sources. Certain attributes examined during Unit 1 were included in the assessment to demonstrate continuity. Some aspects of the construction acceptance testing portion of the initial test program were included in part 3 of the assessment. These aspects are discussed in Module 3A, Initial Test Program. During implementation of the plan, it was discovered that several activities within the scope of the module had not yet started in Unit 2. The program controls for these activities were examined and determined to be in compliance with licensing commitments. Assessment of the performance of the activity and conformance to the program controls has been deferred to other appropriate modules as indicated below: Activity Module Change Control Packages 3A Construction Specification Change Notices 12 Penetration Weight Loading Calculation 12 i l Internal Panel Separation (field cable installation) 12 A listing of the sample used for the module assessment is shown on Table 6-1. l l l i l Ol39f/337-7 6-8 l l l l
6.4.1 PART 1, COMMITMENT IMPLEMENTATION AND UNIT 1 FINDING FOLLOWUP The objective of part 1 of the assessment was to assess implementation of licensing commitments, with emphasis on those revised or added since Unit 1 Readiness Review by Final Safety Analysis Report (FSAR) amendments or project letters and to assess the adequacy of application of corrective actions resulting from Unit 1 Readiness Review to Unit 2. 6.4.1.1 Commitment Implementation Design The commitment matrix that follows section 3.2 contains 186 entries that represent 75 individual design commitments, 25 of which were chosen for assessment. This part of the assessment was controlled by Checklist RR-006-001. The checklist items consisted of individual commitments and were evaluated to ensure that the Project had adequately implemented the commitments in appropriate project design documents. The assessment included reviews of design criteria, calculations, drawings, and construction specifications. The assessment determined that design licensing commitments had been appropriately and adequately implemented, with one O exception. Finding 2RRF-006-011, Level I, identified a difference between the reduced separation criteria based on testing presented in the FSAR and that presented in the Construction Specification X3AR01. Deviation Evaluation Report -186 was initiated and is scheduled for final evaluacion by March, 1, 1988. Two other findings, 2RRF-006-008 and 2RRF-006-013, both Level III, identified minor inconsistencies in the method of specifying references to commitment requirements within the design criteria Construction The commitment matrix that follows section 3.2 contains 16 entries requiring construction implementation action. Thirteen of these were selected for verification and placed on the construction commitment Checklist RR-006-002. The majority of construction commitments for electrical equipment are contained in several general industry standards, as defined by the project position for the corresponding regulatory guide in section 1.9 of the FSAR. Implementation of these standards was assessed by selecting discrete requirements from within the body of the standards and verifying inclusion within an appropriate construction procedure or identifying documentation demonstrating compliance with the requirement. 0139f/337-7 6-9 I
All commitment requirements were found to be properly complied with by construction personnel. Findings 2RRF-006-001, (Level II) 2RRF-006-002 (Level III), and 2RRF-006-003 (Level III) were written, however, to identify requirements that were not included in the procedures. 6.4.1.2 Unit 1 Finding Followup The Unit 1 finding followup consisted of a review of actions taken by the Project to prevent recurrence in Unit 2 of the types of problems identified by Readiness Review during the Unit 1 assessment. A listing of the Unit 1 findings was provided to the Project Engineering and Construction Organizations, a review was performed by these organizations and, information indicating the actions taken to address Unit 2 programs was provided to Readiness Review. Readiness Review evaluated a sample of these responses in parts 1, 2, and 3 to assess the accuracy and adequacy of the information provided. For construction, 18 of 20 actions were examined, for design, 16 of 56 actions were examined. Table 6-2 cross references the finding and checklist numbers. The findings resulting from part 1, evaluated collectively, do not indicate any problem areas. Only one commitment requirement assessed was less than adequately implemented and was of any safety significance. The Project is taking appropriate corrective action as described above for the Level I lf finding. 6.4.2 PART 2, IN-PROCESS ACTIVITIES The objectives of part 2 of the assessment were to examine the design procedures for: o Design change control. o Calculation updating and revision, o Program changes to the design change review program resulting from Unit 1 Readiness Review findings. and to examine the construction processes for: o Component / commodity installation, o Component removal / replacement. o Changes to equipment internals. o Program changes to the controls for in-process installation, maintenance, and protection of equipment. h, 0139f/337-7 6-10
i l P t 6.4.2.1 Design Changes -O The design portion of part 2 examined the design programs controlling design changes and calculation development. Twenty-seven Field Change Requests (FCRs) and eight Design Change Notices (DCNs) were evaluated using Checklist RR-006-003 to assess compliance with applicable procedures and licensing commitments and control of design changes. The review included an evaluation of interdiscipline review, evaluation of effects on FSAR statements, incorporation in drawing within procedural limits, impact on previous installations and revision of calculations to support the change. The above attributes of the design change program were assessed and determined to be acceptable. Finding 2RRF-006-012 (Level III) identified minor instances of failure to follow procedure when assigning an approved disposition to FCRs.
- l Field Equipment Change Orders .
Field Equipment Change Orders (FECOs) were evaluated using Checklist RR-006-OO4. This checklist assessed the following attributes: o Authorization by original equipment supplier. o References of all drawings required. o Specification of material required. o Evaluation by Quality Assurance engineer. Five FECOs were examined and all complied with the above requirements. Calculations Two calculations were assessed to evaluated compliance with project calculation control procedures using Checklist , RR-006-006. The review addressed conformance to design ' criteria, reference to appropriate codes and standards, compliance with guidelines for documenting input data, and proper entry in control logs. The calculations were determined to be acceptable. Finding 2RRF-006-OlO (Level III) identified a minor discrepancy in the listing scheduling of calculations requiring review. 6.4.2.2 Construction The construction portion of part 2 examined the process for component removal / replacement, changes to equipment internals performed under the FECO program, in-process equipment installation, and changes resulting from Unit 1 findings that { ; Ol39f/337-7 6-11 1
modified the controls for in-process installation, maintenance and protection of electrical equipment. Seven pieces of equipment and four penetrations were selected for assessment. The component removals and FECO packages examined were those i related to the equipment sample. Checklist RR-006-OO7 was used I to assess FECOs and component removals. Checklist RR-006-008A l was used to assess in-process installation of equipment and i Checklist RR-006-008B for penetrations. l Component Removal The component removal program was developed subsequent to the Unit 1 assessment and provides a method of obtaining components from Unit 2 to support startup activities in Unit 1. The objectives of the assessment were to verify that the components removed from safety-related equipment were tagged as such, that the equipment from which the component was removed was tagged as requiring a replacement component, and that a tracking mechanism existed to ensure replacement. The method for performing this part of the assessment was to compare selected compartments of pieces of equipment with vendor drawings to identify any missing components. The area where the component was to be located was examined for the presence of a tag. Information from the tag was recorded and the Component Removal Form and Master Tracking System Tracking Log were examined to verify that the documentation agreed with the actual field configuration. Seven component removals were examined during this assessment. All equipment examined during this assessment was found to be l properly tagged, all missing components were accounted for, and tracking logs were accurate. It was noted that the Electrical Discipline had performed a comprehensive internal review several months prior to this assessment to ensure all missing components were accounted for, and that considerable attention was focused on maintaining the accuracy of the Component Removal Log. The program controls for procurement of replacement parts specify that the part must either be supplied by the original vendor or by a vendor who meets the original quality program requirements. Although none of the replacement parts examined had been purchased from a substitute vendor, the program controls appear adequate. Replacement components for the equipment examined that had been re-installed had been purchased from the original vendor, conformed with the established project requirements, and had been inspected by Quality Control (QC). The procedure controlling this process, GD-T-28, contains requirements that adequately control the component removal process and personnel were performing the work in accordance with the procedure requirements. Field Equipment Change Orders The FECO program controls were modified slightly as a result of a Unit I finding. This program is the method by which design changes to equipment are implemented after the equipment is Ol39f/337-7 6-12
received on site. The objectives of the assessment were to O verify that the FECOs we re properly controlled by construction and that the craftsmen performing the modifications were provided a package that contained all applicable drawings, t instructions, and material requisitions. Five FECOs were assessed during this part. The assessment was performed by obtaining a copy of the FECO and examining the package assembled by the engineer. The equipment affected was then examined for evaluation of the work performed. In-process performance of work required by a FECO was observed. All FECO packages examined were found to be complete and to contain information required to perform the work. It was noted during the observation of the in-process work that the craftsmen were using the controlled package and were knowledgeable about FECO work. The tracking log was accurate and up-to-date. The controlling procedure, GD-T-25, contained requirements adequate to control ; the work process, and personnel were conforming with the procedure requirements. Installation The program for installation of equipment was essentially the ' same as that used and assessed in Unit 1. The installation process is separated into three major activities; initial placement into the building, assembly and attachment to foundation, and final inspection and grounding. These activities are recorded on sequential parts of the installation () and inspection form. Due to the length of time between initial placement into the building and final completion and release to startup for testing, protection of the equipment and routine maintenance are required in the interim. The objective of the assessment was to determine the adequacy of project actions to ' prevent recurrence of problem areas identified in Unit 1. The assessment examined the sequence of installation as documented to verify that QC hold points were properly observed. The equipment was examined for proper protection against surrounding < construction activity, for evidence of maintenance (internal cleanliness, space heaters energized) and for identification of the equipment by tag number. All equipment was found to be in compliance with the requirements of controlling maintenance procedure CM-T-03. The Unit 2 program for installation of electrical penetration assemblies was essentially the same as that assessed for Unit 1. The installation process consists of two activities; installation of the penetration module and attachment of the enclosure boxes. Additionally, testing of the electrical continuity of each feed-through device and pressure integrity of each assembly is required prior to final acceptance. The objectives of the assessment were to verify observance of the , required QC hold points during the installation process, and to verify proper protection and maintenance of the penetration assemblies. All four penetrations assessed complied with the O , 0139f/337-7 6-13
3 i l l requirements of ED-T-19, the procedure controlling penetration installation activity. The above part 2 of the assessment verified that, with the exception of the findings discussed above, the Project has successfully incorporated corrective actions resulting from the Unit 1 findings and, additionally, has maintained conformance with the requirements of the procedures. Section 6.5 lists the individual findings, the Project responses, and the Readiness Review conclusions. 6.4.3 PART 3, CONSTRUCTION AND DESIGN COMPLETION The objectives of part 3 of the assessment were to evaluate the design completion process by examining: o incorporation of DCNs and FCRs examined during part 2. o updating of calculations as as-built information becomes available. o appropriate cross-reference between FECOs and corresponding drawings. and to evaluate the construction completion process by examining: l o conformance of installed equipment and penetrations to design requirements. o protection of equipment from surrounding construction activity. o adequacy of inspection documentation. The same equipment sample examined during part 2 was used for l th sample during part 3. l Aseessment of design completion activities was controlled through completion of checklist RR-006-Olla. This checklist was developed by selecting requirements from the Project Reference i Manual related to incorporation of design changes. The same documents assessed during part 2 were used as the sample. The assessment determined that the design completion activities evaluated were performed adequately and in accordance with applicable procedures. One finding, 2RRF-006-007 (Level II) was written to identify a calculation that had not been updated with available data. Readiness Review attended presentations on the scopes and plans for finalication walkdowns planned for Unit 2. A brief description of the differences between the walkdowns performed ll Ol39f/337-7 6-14
, in Unit 1 and that planned for Unit 2 is presented in ( Section 4.1. Readiness Review concurs with the proposed plans for Unit 2. Installed equipment and penetrations were assessed using Checklists RR-006-009A and -009B. The inspection documentation was evaluated using Checklists RR-006-010A and -010B. These checklists were developed by selecting installation attributes from the field procedures that were directly related to licensing commitment requirements. Examples of these attributes are: o Attachment to foundation. o Configuration. o Clearance from adjacent components or structures. o Internal separation, o Installation of replacement components. o Inspector certification. o Conformance of ir,spection document to hardware. () The assessment compared the installed hardware configuration to the design requirements'and noted the installed condition. The inspection documentation was then examined and checked for agreement with the as-found condition. Inspectors' names recteded and their level and area of certification at the time of inspection was verified. Configuration, orientation, location, and identification of all equipment checked was acceptable. All of the equipment was clean, protected, and had space heaters energized where required. All inspectors were properly certified as Level II in equipment installation. All documentation was retrievable and was legible and signed by appropriate personnel. The Unit 2 findings are tabulated on Table 6-3, and are listed numerically in section 6.5. O 0139f/337-7 6-15
6.5 FINDINGS O This section presents, in numerical order, the nine valid > findings issued during the assessment; the Project response, including corrective actions taken; and the Readiness Review Task Force conclusions for each finding. Findings 2RRF-006-004, 3
-005, and -006 concerned initial test program activities and ;
were transferred to Module 3A. Findings 2RRF-006-009 and -014 were found to be invalid based on additional information from the Project. O l l i 0139f/337-7 6-17 I l j
Finding 2RRF-006-001 (Level II) Requirements: Commitment number 31, IEEE 336-1971, paragraph 2.2.5(d). Commitment number 146, ANSI N45.2.2-1972, paragraph 5.2.2(2). Documentation demonstrating compliance by the manufacturer to fabrication, testing, and inspection requirements in the purchase specification / purchase order is available prior to installation of the item. Finding: Part 1- Procedure GD-A-30, revision 13, requires review of vendor documentation but provides no guidelinc- for the source or selection of these documents. Part 2 - Existing procedures do not require a final check of material received versus documentation placed in the vault or other methods to provide assurance that all documents for material shipments have received the proper technical review. Project Response:
- g. Part 1- GD-A-30 requires a copy of either the purchase order
- or the material requisition be provided to the Material Engineering Receiving Section for preparation of an Inspection Checklist. This checklist is used for receipt inspection of all permanent plant equipment / material. Although not required by procedure, the Material Engineering Receiving Section utilizes one of these two documents to determine the quality documents required to be on the checklist.
Because the proper source has been used for determining the required documents, there has been no detrimental impact as a result of the procedure omission. Field Procedure Change Notice (FPCN)-58 was issued to specify the source and selection of required quality documents. The procedure change noted above will ensure that the purchase order or material requisition will continue to be the source document for determining required quality documents. Part 2 - A review of the receiving quality program confirmed the possibility that material could be released for Ol39f/337-/ 6-19
installation without a review of the material documentation if quality documentation was not appropriately transferred from QC receipt inspection to QC document review. Prior to January 30, 1986, all material received on site would be put on " hold" and released only after a technical review of documentation was performed and accepted. This was changed by revision 11 to procedure GD-A-30 to allow for processing and releas> of material for installation with technical review o. documentation becoming a separate and parallel inspection function. This change negated the programmatic safeguard of insuring all documentation was reviewed for material that was released. Procedure DC-A-06 requires that the Document Review Section perform a technical review on documents that they receive, and specifies actions to take if the review is unacceptable. The requirements of this procedure are being complied with; therefore, investigative and corrective actions were directed to ensure that the Document Review Section does, in fact, receive the documentation. To reinstate necessary safeguards of ensuring that required documentation is received by the Document Review Section, revision 14 to GD-A-30 was issued. This revision requires the QC Receipt Inspector to maintain a log containing the necessary information to verify acknowledgement that the supporting documentation for released material was received by the Document Review Section. An internal audit was conducted by the document review supervisor to assure that required documentation was received by the Document R view Section during the period starting January So, 1986. One hundred and forty-six safety-related receipt reports were randomly selected from entries in the warehouse Receipt Inspection Log and compared with the documents on file in the vault. All records were on file. The procedure change noted above will provide further assurance that required documentation is properly accounted for. Readiness Review
Conclusion:
Readiness Review has reviewed the procedure changes and audit results and concurs with the response. O 0139f/337-7 6-20
Finding 2RRF-006-002 (Level III) O Requirements: Commitment number 31, IEEE 336-1971, paragraph 2.4 Each report shall identify the item to which it applies, the procedure or instruction followed in performing the work, and Finding: The inspection reports generated from the use of procedure ED-T-19 do not reference the procedure. Project Response: Vogtle Field Procedure ED-T-19 was reviewed for compliance with IEEE-336. It was determined that the following attachments in ED-T-19 do not identify the procedure number:
- 1. EE580 Control and Tracking System Installation Card, exhibit 01.
- 2. Electric Penetration Assembly Leak Test Inspection Report, exhibit 02.
() 3. Conax Penetration Loading, exhibit 05. Although this is a deviation from IEEE-336 requirements, there are no adverse hardware or quality effects from lack of compliance with this requirement. These records are not generated by any other procedures. Field Procedure ED-T-19 was incorporated into Field Procedure ED-T-04, revision 10, issued July 27, 1987. FPCN-29 was issued immediately thereafter, addressing the requirements as follows:
- 1. The quality control inspector wilz enter " Inspected / Accepted per ED-T-04, revision " in the " Remarks" block of the exhibit 01 card at time of final acceptance.
- 2. No action will be taken regarding the exhibit 02 record since these records have all been completed and will be filed with the exhibit 01 final acceptance record.
- 3. The Conax Penetration Loading, exhibit 05, will be revised to have " Inspected / Accepted per ED-T-04, revision "
in the " Quality control" signoff block. O Ol39f/337-7 6-21
Readiness Review
Conclusion:
Readiness Review has reviewed the procedure incorporation and changes and concurs with the response. O O 0139f/337-7 6-22 i
r 2RRF-006-003 (Level III) Requirements: Commitment number 35, IEEE 384-1974, paragraph 5.6.3 Class 1E wire bundles internal to the control boards shall be identified in a distinct permanent manner at a sufficient number of points to readily distinguish between Class 1E and non-Class 1E wiring. Finding: This was identified in Unit 1 on RRF 6-50. Corrective action was taken by adding the requirement to X3ARO1-E9 on CSCN 358, and by adding paragraph 6.22 to ED-T-08. Paragraph 5.4.5.4 of ED-T-08, revision 9, imposes this requirement for jumper wires, but does not currently address bundled field cabling within panels. Project Response: Vogtle Field Procedure ED-T-08 and Construction Specification X3AR01, section E9, were reviewed for compliance with IEEE-384-1974 requirement for identifying Class 1E/non-Class 1E wiring within panels containing different safety train wiring or safety train and non-safety train wiring. Review of Construction Specification X3AR01, section E9, confirmed that the requirement was adequately addressed in Attachment 2, paragraph 1.4, of the specification. ; It was determined through review of Field Procedure ED-T-08, that revisions 7 and 8 had properly addressed the requirement. In revision 9, the requirement was properly stated,(reference paragraph 5.4.5.4) but was in a section of the procedure that dealt specifically with " jumper" installations. Even though the procedural requirement was not addressed in the cable termination section of the procedure, cable bundles within these panels have been properly identified and comply with the IEEE-384 requirements due to the fact that inspectors were ! familiar with the requirement and that the correct requirement was referenced on the inspection check list. FPCN-72 was issued to ED-T-08 to address this requirement in the cable termination section of the procedure. This FPCN will i conclude action on this subject and will satisfy the requirements of the IEEE-384. Readiness Review
Conclusion:
Readiness Review has reviewed the procedure change and concurs with the response. 0139f/337-7 6-23 e _ __ _ _ _ _ _
2RRF-006-007 (Level II) Requirements: ANSI N45.2.ll, paragraph 4.2, requires justification of design analysis assumptions and identification of assumptions which must be verified as the design proceeds. The Project Referenc e Manual (PRM), paragraph 9.3.3, requires that calculations be based on actual conditions where known and review of design to determine impact on calculations when actual data becomes available. Finding: Calculation X3CC02, 480 Volt Breaker Short Circuit Sizing, does not justify load, load characteristic, and cable assumptions. The calculation has not been updated to reflect available actual data or indicate that a review has been performed or is required. Supplier breaker data used in the calculation is not referenced to documents identified as specifically applicable to the project. Project Response: Engineering has analyzed Calculation /_3CCO2 and has determined.
- a. The load used in the calculation is based on 100 percent O of the transformer rating. Since the actual loads were not known and due to the need to permit the orderly progress of design, a conservative load (worst case) was used when the calculation was originated. A motor load is a conservative (worst case) condition due to the fault current contribution made by a motor.
As a part of this review, it was noted that an X/R value of 5.0 was used for the load center transformer instead of the manufacturer's actual test value of 5.77. Since the use of an X/R of 5.0 would result in lower fault current values, the calculation was examined further, with the following results: o The actual cable impedance is higher than the assumed cable impedance; therefore, actual fault current would be less than c lculated. o The load center transformer impedance value of 5.32 percent used in the calculation was lower than the actual impedance value of 5.75 percent; therefore, the actual fault current would be less than calculated. O 0139f/337-7 6-24
The above conservative assumptions more than offset the O s difference in X/R ratios; therefore the original calculation was conservative and acceptable. The calculation will be updated, however, to use the actual i data now available,
- b. When the calculation was initiated for the initial '
design of the 480-volt breaker short circuit sizing, the calculation (including the cable assumptions) was checked. As changes to the design evolved, the design changes were reviewed for conformance with the calculation. The determination to revise the calculation is based on the results of these reviews (reference PRM C-9, paragraph 9.3.3). In essence, if the change does not impact the calculation, a calculation revision is not processed,
- c. Supplier breaker data is utilized in this calculation.
The data is of a generic type, readily available from standard supplier documents. The breakers used are also a standard type and have not been specially designed just for this plant. The data is referenced to a document traceable to its source, and the data is explicitly attached to the calculation. The data is specific for the type of breaker used. Engineering has determined that the data is valid and no O. further action is necessary.
]
As a part of the broadness review, it was noted that Calculation X3CM01, Electrical Penetration Short-Curcuit Currents, utilized-X/R ratios resulting from the above 480-volt calculation. Since some of these ratios are based on industry standard values, rather than actual values, the calculation does not comply with the project position to Regulatory Guide (RG) 1.63. This position, described in Final Safety Analysis Report (FSAR) paragraph 1.9.63.2.2, states that actual X/R ratios are used. The calculation uses actual values, which are based, in part, on ! industry standards, and values specified by RG 1.63. A Licensing Deviation Document (LDD)and FSAR change notice have been initiated to revise the project position in FSAR paragraph i 1.9.63.2.2 to address specifically what X/R ratios have been : used. Although the values selected for the calculation were to provide a conservative design margin, the calculation will be revised to ; incorporate the as-built transformer data and cable sizes / lengths as currently designed or installed. The revision to Calculation X3CCO2 is scheduled for completion by December 2, 1987. LDD 124 and FSAR Change Notice 612 associated with the X/R ratios for the containment electrical penetration protection calculation was issued by engineering. Ol39f/337-7 6-25
The engineering group supervisors (EGSs) have been issued instructions requiring that the Calculation Control Log for each discipline shall be changed to reflect those calculations that require review and the scheduled date for review. The review is to be documented on a calculation review form which is to be included in the calculation package, similar to a supplemental calculation. Readiness Review
Conclusion:
The above reverification and broadness review action adequately resolves the issue. O O 0139f/337-7 6-26
l i 2RRF-006-008 (Level III) Requirements: ! ANSI N45.2.11.3.1 requires that applicable design requirements such as design bases, regulatory requirements, codes and standards, shall be identified, documented, and their selection reviewed and approved. l Finding: A. Design Criteria DC-1807, revision 3, 120 Vac Power System, does not reference the applicable electrical penetration ; documents RG 1.63 or Institute of Electrical and Electronic Engineers (IEEE) Standard 317. B. Documentation of design requirements applicable to design criteria is inadequate in that design criteria reference applicable standards (in paragraph 2.0) without reference to controlling regulatory guides (on cover sheet), which may modify the standard requirements. This condition exists for the following:
- 1. IEEE-323 is referenced in DC-1804, DC-1805, DC-1806, DC-1807, DC-1818 and DC-823 without reference to RG 1.89.
N 2. IEEE-344 is referenced in DC-1804, DC-1805, DC-1806, DC-1807, DC-1818 and DC-1823 without reference to RG 1.100.
- 3. IEEE-379 is referenced in DC-1804, DC-1806, DC-1807, DC-1818 and DC-1823 without reference to RG 1.53.
Project Response: Engineering has reviewed the procedure for preparation and control of the design criteria manual. The Design Criteria Manual, Preface, section 2, " Organization of the VNP Design Manual" paragraph 2.2, states in part:
"The specific contents and organization of the VNP Design Manual are as follows: 1 Section II - Design Criteria Discipline Criteria - includes general design, Bechtel Western Power Company standards, and other l
references which are peculiar to either a system function or to system design for which the discipline is responsible. The word " system" as used herein includes structures. O 0139f/337-7 6-27 l
System Criteria - includes, as a minimum, the approved design basis for systems which must conform to the design control procedures. The design basis document includes the VEGP design control cover sheet with any attached substantiating documentation." The above excerpts are the basis used by engineering for determining the need of identifying regulatory guides in the design criteria. Finding A The design of the Electrical Penetration assemblies is controlled by DC-1818, Electrical Penetration System, and DC-1823, Electrical Protection Criteria, these criteria properly reference RG 1.63. Discipline Criteria, DC-1000-E, which provides the general criteria for the design of electrical systems, references RG 1.63 and IEEE-317. In summary, DC-1807 deals specifically with the design of the 120 Vac Power System. Since DC-1807 references DC-1823, as a system interface, and DC-1823 properly identifies RG 1.63; a designer using DC-1807 would be required to comply with DC-1823 requirements when the design involved a 120 Vac power system passing through an electrical penetration. ll Engineering was inconsistent when listing RG 1.63 on the cover sheets of the design criteria, i.e., DC-1805, -1806, -1807, and
-1825. However, engineering bas reviewed drawings and calculations pertinent to the above criteria (DC-1807) and confirmed that the design conforms to the regulatory guide, with the exception of the condition identified in Deviation Evaluation Report (DER)-184 which was identified by the project. The conditions identified by this finding is not considered to be the cause of the deficiency identified in the DER. The DER condition is a deficiency in cable sizing, which has been corrected.
To provide a uniform design criteria, engineering will issue a Design Manual Chance Notice to add RG 1.63 to the cover sheet of DC-1807 by September 15, 1987. Finding B For the respective design criteria noted in the finding, RG 1.89, 1.100, and 1.33 are considered to be generic (not system-specific). The E'ectrical disedpline criteria DC-1000E reference these regulatory guides. In addition DC-1005, -1007, and -1009 (interdiscipline) also address these regulatory guides. 0139f/337-7 6-28 l A
Based on the above justification, there is no impact on hardware 4
' O- or documentation and further investigative actions are not required.
a Readiness Review Conclusion Readiness Review concurs with the response. b b O i 4 4 ) lO r 0139f/337-7 6-29
2RRF-006-010 (Level III) g Requirement: ANSI N45.10.4.2 states design analysis shall be performed in a planned, controlled, and correct manner. Finding: Calculation X3CA03-1, Auxiliary Power System Vogtle Study, is identified as applicable to both units 1 and 2 but contains no input data for Unit 2. The calculation does not indicate that Unit 2 data are identical to Unit 1, that Unit 2 conditions are enveloped by Unit 1 conditions, or otherwise indicate that an evaluation of potential differences in input data has been performed. Project Response: Calculation X3CA03-1 was reviewed in response to the finding. The calculation demonstrates the acceptability of the minimum auxiliary power system voltage level from the reserve auxiliary transformers (RATS) to the motor control centers and is applicable to both units. The following discussion provides justification why the calculation conservatively envelopes the design conditions of both units. o Both Unit I and Unit 2 RATS are tied to a common switchyard, and therefore transmiseion system data is identical for both units. o For Class 1E systems, the impedance data for switchgear and motor control centers is identical for both units. o Loads common to both Units 1 and 2, which may be connected to either unit, were assumed to be connected to one unit only, which represents the maximum loading, o Cable bus arrangements are similar for both units. Minor length differences are inconsequential. Maximum cable voltage drop was utilized and specified for purposes of cable design. Specific Unit 2 design changes which may impact the analysis are examined as they become available. If the need for a calculation revision to incorporate these specific Unit 2 changes is indicated, it is entered and tracked in the Calculation Control Log. Additionally, calculations are periodically reviewed to determine if revision is needed. This review is also flagged and tracked in the Calculation Control Log. Reviews which do not result in revisions are documented on a calculation review form and placed with the calculation package. lll 0139f/337-7 6-30
. . - . . = . - - . . - . . - . . .--.- -. .-. . .-.~ - . - = . . - . . . . . - . . -
I
. Readiness Review
Conclusion:
- Based on the re-examination of the calculation performed by the Project and the correspondency results, Readiness Review agrees with the above response.
1
' *1 O
O 0139f/337-7 6-31
Finding 2RRF-006-011 (Level I) Requirements: A. FSAR 8.3.1.4.3.C states that "within panels and control j boards, ... where it is not possible to maintain " .. separation barriers are installed between components and wiring of different separation groups, or analysis has been performed to determine the minimum separation requirements. Refer to "... Table 8.3.1-4". l B. FSAR 8.3.1.4.3.C.3.a states that a single barrier is l provided with a 1-inch maintained air space between the components or cables of redundant separation groups and the barrier. Finding: A. -1. Construction specification X3ARO1, section E9, Attachment 2, Table 1, allows 480 Vac cable separation within enclosures which is less than that allowed by FSAR, paragraph 8.3.1.4.C.
-2. The specification allows reduced 125 Vdc and 120 Vac cable separation within enclosures for all cable sizes.
FSAR Table 8.3.1-4, item 18, restricts reduced separation to cable sizes number 8 AWG or smaller. lh B. Specification X3ARO1, section E9, Attachment 2, Figure 2, detail 1, allows cable-to-barrier separation of less than the 1-inch requirement specified in the FSAR. Project Response: The FSAR was changed to reflect Wyle Labs Test Report number 48141-02. The construction specification was updated to reflect the Wyle Lab Report and the FSAR; however, additional information was included in the specification that covered situations not explicitly tested. The additional information was not considered as a deviation from the FSAR commitment when the specification was revised; therefore, an FSAR change was not initiated. Since the change to construction specification is limited to application of the Wyle Lab Test Report, and the test report concerns cable separation, Engineering has conducted a study of X3ARO1, sections E8 and E9, and DC-1810 to determine if other similar conditions exist. The review identified separation concerns in the E8 and E9 and DC-1810 documents. DER-186 has been issued to document that the conditions found as a result of the study are potentially reportable to the Nuclear Regulatory Commission as a 10 CFR 50.55(e) and/or 10 CFR 21. h 0139f/337-7 6-32
t ,r g The corrective actions for the separation concerns identified (,,) will be tracked with the DER. Submittal on the final evaluation and proposed corrective actions for DER-186 is presently scheduled for March, 1, 1987. Readiness Review
Conclusion:
Readiness Review agrees that the evaluation and corrective action that is a part of the normal project process of closing DERs will ensure that the separation discrepancies identified in this finding are properly resolved. t t O f~ t 0139f/337-7 6-33 , s
l I l Finding 2RRF-006-012 (Level III) Requirements: PRM C17.5.3 requires: A. That the equipment qualification (EQ) checklist on the back of the form be used to demonstrate systematic review of the Field Change Request (FCR). B. Notation of required calculation revisions in the remarks section of the FCR. Finding: A. EQ checklist completion of FCRs is inconsistent as indicated by the following: o E-FCRB-19,472 and Q-FCRB-351 checklist were marked incorrectly indicating no modification of foundations, supports, or anchors. o M-FCRB-6916F has an incomplete EQ checklist. B. E-FCRB-19,472 approves an equipment mounting configuration which is not consistent with the configuration supported by applicable design calculation X2CK2.7.1.1, Control Building Category 1 Equipment Supports, Level B, revision 1. The remarks section of the FCR does not indicate a need to revise the calculation. Project Response: A. Vendor drawing BWPC log 2X6AS01-382-2 requires equipment tag number 2-1602-P5-NDS to be mounted using four 1/2-inch mounting screws. The mounting plate was not specified by the equipment vendor; it is the design of the architect / engineer (A/E); therefore, it is not part of the equipment qualification. The A/E's responsibility is to ensure that the response spectra provided for the qualification of the piece of equipment was valid for the equipment anchorage location. This was done in the original calculation (X2CK2.7.1 1) by showing that the attachment ! plate was rigid. The same verification of plate rigidity is ! confirmed for the modified plate size in the justification l on the back of the FCR. Since the equipment support still l meets the original rigid condition, the E-FCRB-19,472 did i not modify the equipment qualification support condition; i l therefore, there was no need to send the FCR to the EQ group l for review. Q-FCRB-351 provides shimming details for multiplex panels, tag number 2-2501-Al-059 and -60. This equipment is Project Class 62E and does not have safety-related equipment lh I qualification requirements; therefore, there is no impact to 0139f/337-7 6-34
g- the EQ checklist and all boxes may be checked "No" (,j (reference PRM section C-17, paragraph 17.11). M-FCRB-6916F relocated an instrument rack on the equipment location drawing. The equipment location drawing dimensionally locates equipment; however, the installation of the equipment is per a specific installation drawing. The location change, per this FCR, is not impacted by Zone-of-influence. Therefore, there is no impact on hardware or documentation by the identified concern. A random review of 20 FCRs approved by the same individual as MFCRB-6916F was performed and no discrepancies or similar j findings were noted. Therefore, this is considered to be an [ isolated case. l B. Detail 11 on drawing AX2D11ROO2 shows mounting details for NIS preamplifiers, BWPC log number 2X6AS01-382-2. The detail shows the equipment attached to a 1/2-inch plate with four 1/4-inch mounting screws as specified by the vendor. The plate is attached to the wall with four 5/8-inch concrete expansion anchors (CEAs). The FCR approves the attachment of the plate to two existing type TT embeds with 1/2-inch threaded rods welded to the embeds. The FCR l justification verifies that the 1/2-inch plate remains rigid l (natural frequency less than 33 Hz) and that the threaded rg rods are equal to or stronger than the 5/8-inch CEAs. The (_) FCR reviewer chose to calculate the loads on the threaded rod and compare them with the rod capacity. A statement j indicating that the 1/2-inch threaded rods are stronger than l the 5/8-inch CEAs would have been sufficient. The I calculation results are indicative of a minor change that is - applicable to the modification of a single support whose design is governed by a generic calculation. Therefore, the calculations are considered minor, as defined in section 17.6.5.1 of the PRM conditions 1, 2, and 5. Since the l acceptability of the proposed change is documented in the { FCR justification, the original calculation does not require ' revision. During the investigation, it was discovered that a previous FCR (E-FCRB-14,079) revised the same support. E-FCRB-14,079 revised the original support to the extent that the calculation was impacted. Since the impacted calculation was being maintained by the Home Office, a copy of the FCR was sent to the Home Office requesting that the calculations be revised. A revision to the calculation was prepared in the Home Office; however, page 59A, the sheet impacted by the revision, was inadvertently not replaced in the original calculation file. V("N 0139f/337-7 6-35
A random review of five FCRs which impacted calculations was conducted. As a result, it was concluded that the calculations that were impacted by the five FCRs were revised as required. Based on this review, the condition is considered to be an isolated case. For E-FCRB-14,079, a memorandum (BB-54052 dated August 18, 1987) has been issued to EGSs requesting that all Calculation Control Logs be changed to show review required with a scheduled due date. In addition, a memo (BB-54064 dated August 20, 1987) concerning the processing of design changes with EQ impact has been issued to all EGSs The memo clarifies that the EQ group is responsible for justifying or concurring with design changes with EQ impact, prior to the EGS approving the change. Readiness Review
Conclusion:
Readiness Review concurs with the above responses. O O Ol39f/337-7 6-36
Finding 2RRF-006-013 (Level III) Recuirements:
- 1. The response to FSAR Question Q430.64 states " Motor operated valve motor overload is annunciated in the control room."
- 2. PRM C17.5.3 requires documentation of required interdiscipline review.
- 3. PRM C17.6.2.4 requires completion of the FCR retrofit block l to indicate if the change represents a potential retrofit.
Finding: NOTE: The following discrepancies concern design program deficiencies which are considered minor in nature and not evidence of a generic program deficiency. The required response is limited to: A. A brief evaluation of actual or potential impact on hardware, technical adequacy, test results, etc., and, B. A discussion of the remedial action for the specific identified deficiency.
- 1. While examination of the elementary diagrams for motor O operated valves indicates that the above requirement has been implemented by connecting the heater overload contacts l
to the "MCC TROUBLE" annunciator circuit, the requirement to I do so cannot be located in the Design Criteria. This is l inconsistent with the method of implementing other specific j FSAR commitments. '
- 2. FCR M-FCRB-13,628 received inadequate interdiscipline review (NOTE: M-FCRB-6916F supersedes the subject FCR and received more extensive review in which the need to issue a DCN was identified by a reviewer).
- 3. Q-FCRB-367 and Q-FCRB-351 were approved without disposition of the retrofit block.
Project Response:
- 1. The design criteria inconsistency with specific FSAR commitments has no impact on hardware, technical adequacy or test results; however, a potential impact on the design documentation exists.
Paragraph 3.E.2 of DC-1805 will be revised to indicate that overload conditions for Class 1E motor operated valves will be annunciated in the control room. O 0139f/337-7 6-37
- 2. M-FCRB-13,628 was not routed to Civil or Controls for interdiscipline review.
The mounting details of the rack, which includes the surface mounting plates, were not changed. Civil interdiscipline review was not required. The originating engineer inadvertently omitted the routing for Controls interdiscipline review A potential impact on hardware and documentation could have existed; however, since M-FCRB-13,628 was superseded by FCR M-FCRB-6916F and M-FCRB-6916F received the needed interdiscipline review, the potential for impact has been precluded. The Installation Engineering Plant Design Discipline has - conducted a training session emphasizing the importance of FCR interdiscipline reviews in a training session.
- 3. Q-FCRB-351 and Q-FCRB-362 were evaluated and no retrofit was required. The retrofit blocks were marked "No" to correct the documentation.
Readiness Review
Conclusion:
Readiness Review agrees that the above responses resolve the specific issues identified as requested by the finding O II> 0139f/337-7 6-38
. .. I
_ _ _ _ _ _ - _ _ _ _ _ - ~ .
TABLE 6-1 READINESS REVIEW TEAM - MODULE 6 D .. L. Edenfield Readiness Review Task Force J. A. Lovoy Readiness Review Task Force D. G. Lunsford Quality Assurance J. L. Taylor Quality Assurance O ' O 0141f/341-7/1
TABLE 6-2 ASSESSMENT SAMPLE Item Number Assessed DESIGN-Design Criteria 24 Calculations 2 Field Change Requests 27 Design Change Notices 8 Field Equipment Change Orders 5 Licensing Commitments 25 Unit 1 Findings 16 CONSTRUCTION Field Equipment Change Orders 15 Component Removal 12 Equipment 7 Penetrations 4 Licensing Commitments 13 Unit 1 Findings 18 L O 0141f/341-7/2
l l TABLE 6-3 (SHEET 1 0F 2) UNIT 1 FINDING FOLLOWUP Unit 1 Finding Issue Checklist - Item No. i 6-2 Penetration inspection reports 008B - 03, 05 not processed per procedure 6-3 EE580 cards not filed per procedure 010B - 01 6-4 Penetration test results not reviewed 010B - 03, 04 6-5 Penetration used as work platform 009B - 01 6-6 Penetration orientation does not match 009B - 02 drawing 6-16 Field and vendor wiring does not meet 009A - 09 separation requirement 6-17 Switchgear not welded per drawing 009A - 03 6-20 Installation documents misfiled 010A - 01 6-25 Inspection reports signed 010A - 02 out-of-sequence , 6-27 Batteries and racks not permanently 008A - 07 identified 6-29 Damage to switchgear 008A - 03 6-30 EMSL cards not on file 010A - 03 010B - 02 , 6-32 Inadequate clearance from equipment 009B - 04, 05 to tray support 010A - 03 6-36 FCRs used instead of FECOs to make 003-08 technical changes to equipment , 6-37 Seismic separation for electrical to 009B-06 other disciplines not addressed 6-46 FECO packages not processed per 007-10 procedure , 6-47 Document packages misfiled in vault 010A-01 " (:) 0141f/341-7/3
. ~
r TABLE 6-3 (SHEET 2 OF 2) O Unit 1 Finding Issue Checklist - Item No. 6-49 Procedure did not incorporate 002-01 licensing commitment 6-50 Procedure did not incorporate 002-04 licensing commitment 6-54 Cover and dust filter loose 008A - 04 6-56 Licensing criteria not consistently 001 - 09, 11 referenced in design criteria 6-66 Licensing criteria not referenced in 001-14 design criteria 6-68 Switchgear has damaged base channel 009A - 03 O 1 0141f/341-7/4 l
1 TABLE 6-4 UNIT 2 FINDINGS Humber Level De sc ription 2RRF-0 0 6-0 01 II Procedure GD- A-30 recaires review of ve ndor docume nts but provides no guidelines for the source or selection of the se docu me nt s . Existing procedure does no t recuire reconciliation of material received with documentation tra nsmi tted to vault. 2RRF-006-002 III Inspection reports in Field Procedure ED-T-19 do not reference the procedure number . 2RRF-006-003 III Procedure ED-T-08 does not specify that Class 1E wire , bundles within mu lti-train panels be cl ear ly identified. 2RRF-006-007 II Calculation X3CC02 "480 Volt Breaker Short Circuit Sizing" does not just if y lo ad, load ch arac terist ics , and cable ass umptions. Actual data available has not been coapared to calculation assumptions. 2RRF-006-008 III Design Criteria DC-1807 - 120 Vac power system does not reference Regulatory Guide 1.63 or IEEE standard 317 for penetratio n circuits. IEEE stand ards 323, 344, and 379 /~ )
*s' are referenced in several DCs without reference to the cor responding Regulatory Guide.
2 RRF-00 6-010 III Calculation X3CA03 Auxiliary Power System Voltage Study is identified as applicable to both Units 1 and 2 but contains only Unit 1 data. [ 2RRF-006-011 I construction specification X3AR01, Section E9 allows separation between dif ferent safety trains less than specified in the PSAR. 2RRF-00 6-012 III EQ checklists on FCRs have been completed i nconsi ste ntly. One FCR was inappropriately noted as not recuiring calculation revision. i 2RRF-006-013 III FSAR recuirement to annunciate MOV overload in cont col ' room is not specified in Design Criteria. One FCR received inadecuate interdiscipline review. Two FCRs were approved wi tho ut dispo sitioning of the re trofit blo ck . O 0151f/341-7
Georgia Power Cornp;ny Project Minig:rn;nt Pc:t Offica Box 282 Wryncsboro. Georgis 30830 Telephone 404 724-8114 404 554 9961 o/ i L Vogtle Project DATE: tiovember 17, 1987 RE: Pl a nt Voq tle Unit 2
~~~ ~
Readines"s RdOl~ei51'odu1e 6 "L:. '. C. Ra11s ey TO: R. W. McManus Engineering has revi ewed Module 6, Elect ri ca l Equipme nt , for general accuracy and completeness. To the best of our knowledge and belief , the module is a complete and accurate representation of the Elect rical Equipment Prog ram, and the eng i neeri ng processes and commi tme nts re lated thereto. (3
%)
% b W. C. Ramsey, Jr.
Pro jec t Engineering Manager RWM /WCR /bj d i c) l 1
Georeta Power Company ProjIct Minec;m:nt Post Offica Box 282 W:ynssboro. Georgia 30830 Telephone 404 724-8114 404 554-9961 l en J Vogtle Project November 12, 1987 MEMO TO: R. W. McMa nu s
SUBJECT:
Plant Vog tle Uni t 2 Readiness Review, Module 6 Nuclear construction has reviewed Module 6. To the best of our knowledge and belief, the module is a complete and accurate representation of the site Electrical Equipment program and commitments related thereto. (j'\ \ j / mfW R. H. Pinson Vice Pre sident Vogtle Construction RWM /RH P/b jd (m 'N l
Georgo Power Company Project Minig mint Post Offica Box 282 Wryntsboro, Georgia 30830 Telephone 404 724-8114 404 554 9961 (~'t L
'~>
Vogtle Project i DATE: November 17, 1987 RE: Plant Vog tle Unit 2 Readiness Review Module 6 FROM: C. W. Hayes TO: R.W. McManus Project Quality Assurance has reviewed Module 6, Electrical Equipment. To the best of our knowledge and belief, the module is a complete and accurate representation of the site Electrical Equipment program and commitments related thereto. l [ d'h &g ' , C. W. trayes Project Quality Assurance Manager RWM/CWH/bjd i 1 ('%, (.)
t O t PLANT V0GTLE UNIT 2 READINESS REVIEW PROGRAM Electrical Equipment - Module 6 Readiness Review Board Acceptance Letter The Readiness Review Board has been apprised of the scope and content of Module 6, Electrical Equipment. 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 electrical equipment at Plant Vogtle will be sound and comply with comrritments set forth in the FSAR. O t l i - . I APPROVED: [ l Ifoug Dutton ' Chairman, Readiness Review Board , Vogtle Electric Generating Plant , i l O 6 _ _ s
e b PLANT VOGTLE READINESS REVIEW PROGRAM ASSESSMENT PLAN FOR MODULE 6 ELECTRICAL EQUIPMEllT ASSESStiENT PLAN APPROVAL U TEAfA LEADEM: -
))( DATE:
(([ RR PROGR\!! MANAGER: ,,,1 . - DATE: /f fBC/ 8 7 _vacass 1.n.,9 RR BOARD SPONSOR: d_ DATE: [ /.3!8[
/
i 0123f/195-7
i UNIT 2 ASSESSMENT PLAN L O. MODULE 6, ELECTRICAL EQUIPMENT TABLE OF CONTENTS 1.0 Objective , 2.0 Scope , 2.1 Module Scope [ 2.2 Assessment Scope 3.0 Assessment Activity Assignment 3.1 Readiness Review 3.2 Quality Assurance 4.0 Assessment Details and Guidelines 4.1 Part 1 - Cummitment Implementation and Corrective Action Verification 4.1.1 Design Checklist RR006-001 4.1.2 Construction Checklist RR006-002 4.2 Part 2 - Programs and Activities 4.2.1 Design Checklists RR006-003,-004, 005, and 006 4.2.2 Construction Checklists RROO6-007 and -008 4.3 Part 3 - Construction and Design Completion-and ' Construction Acceptance Testing , 4.3.1 Design Finalization, Checklists RR006-011A and B 4.3.2 As-built Construction, Checklists RR006-009A, B i and RR006-010A, B 4.3.3 Construction Acceptance Testing, Checklist
- RR006-012 5.0 Checklists 6.0 Item Selection !
O 0110 f/ 341-m
-. - = -. . _ = -
MODULE 6 SUPPLEMENT ( ASSESSMENT PLAN l FOR UNIT 2 ELECTRICAL EQUIPMENT l i i 1 1.0 OBJECTIVE l [ I i This assessment plan provides a means for evaluating the continuing conformance of design, procurement, construction, and l testing activities associated with electrical equipment for Vogtle Electric Generating Plant Unit 2 licensing requirements. (} 2.0 SCOPE . t 2.1 MODULE SCOPE The scope of this module covers those design, procurement, installation, and inspection activities associated with safety-related (Class IE) electrical equipment and their respective electrical systems. This equipment is listed in the equipment index under the 18XX series of tag numbers, and consists mostly of large, floor mounted assemblies. Installation / inspection aspects of electrical instrument / control () panels (not containing tubing connections) and design aspects of 0110f/341/7 1
5 Non-IE systems / equipment that interface with or affect -{ safety-related equipment are included in this module. Internal wiring and modifications to equipment by construction , are included in the scope of this module. Certain components and design activities normally associated with electrical equipment are not discussed in this module, but I are included in the scopes of modules closely related to the component use or design activity. Electrical motors are addressed in Modules 4 (pumps), 18A [ heating, ventilation, and air conditioning (HVAC)],and 20 (valve operators). I Installation / inspection of wall mounted electrical items, except for regulating transformers, is discussed in Module 17 (due to I
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the similarity of installation). Electrical instruments and local control stations associnted with HVAC control are ; i addressed in Module 18A. Other electrical instrumentation, with ! l the exception of the panels discussed above, is discussed in Module 20. Attachment of equipment to its support, or
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l attachment of equipment mounted directly to the building i structure is addressed in this module, but support assemblies , i are addressed in Module 19, embedded plates / struts are addressed : 1 in Module 8, and concrete pads / foundations are addressed in ) 1 Module 1. Other electrical modules are Module 12, Cables and Terminations, Module 17, Raceways, and Module 19, Raceway l l Supports.
] )
0110f/341/7 2
e l Table 2-1 depicts the assignment of electrical topics and hardware to their associated modules. { 2.2 ASSESSMENT SCOPE l The assessment for electrical equipment for Unit 2 is concentrated in the following areas: o Changes to the programs examined in Unit 1. o Corrective actions taken in response to Unit 1 Readiness Review, Quality Assurance (QA), and Nuclear Regulatory Commission findings. o Design change control. o Design finalization program scopes, plans, and results. l l o Hardware installation (with checks on deficiencies identified in Unit 1). 1 o Documentation. o Component removal (CR), replacement, and additions [ Field Equipment Change Orders (FECOs) and Change Control Packages (CCPs)).
}
0110f/341/7 3
i i .( o Configuration control after construction turnover. Initial design, procurement, and receipt activities were essentially complete at the time of the Unit 1 assessment.-. and were performed under the controls of the programs assessed at the time. Assessment of these topics is limited to those- ! i activities related to findings issued during the Unit 1 t assessment, the FECO and (CCP) program, and the CR program. A number of checklist items from the Unit 1 assessment are included to enable comparison of the Unit 1 and Unit 2 programs.
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() 3.0 ASSESSMENT ACTIVITY ASSIGNMENT The organizations responsible for implementing each part of this assessment are delineated in s'ection 4.0 of this plan as each part is discussed. This section provides an overall summary of those responsibilities. l 3.1 READINESS REVIEW l Readiness Review selects the commitments and corrective actions to be reviewed for' implementation into Unit 2 programs and ! processes and performs the Part I assessment. Readiness Review ; () also provides a listing of hardware items and types of 0110f/341/7 4 -;
documentation to be assessed in par ; 2 and 3 and participates in the assessments. 3.2 QUALITY ASSURANCE Quality Assurance performs the verification activities listed on
.e the checklists for parts 2 and 3 of this plan. It may be necessary to utilize personnel from project and/o: F nern Company Services design groups to perform desitt.4 verifleation activity (personnel selected must not have performed, checked, or approved the design)
O 4.0 ASSESSMENT DETAILS AND GUIDELINES i This assessment plan is a phased group of activities, consisting j 1 of three parts. Parts 1 and 2 contain design verification i 1 1 activities and construction verification activities. Part 3 1 1 contains construction completion verification activities and l verification activities directed towards the construction I acceptance testing portion of the Initial Test Program. The i following sections describe each part of the assessment plan and 1 assign the responsibilities for implementing the plan. l l O OllOf/341/7 5 l
['T N/ Section 5.0 of this plan gives general instructions for utilizing and completing the checklists described in this section. 4.1 PART 1 - COMMITMENT IMPLEMENTATION AND CORRECTIVE ACTION VERIFICATION Part 1 of this assessment plan consists of two checklists, RR006-001 for design and RR006-002 for construction. Readiness Review selects the items to be verified and performs the assessment. () The Final Safety Anelysis Report (FSAR) commitments for the electrical scope of work include designation of a number of general standards. The design checklists contain entries-for both the general standard to the extent committed in the FSAR (for first-level verification) and entries for individual requirements out of that standard (for second-level verification). The construction checklist contains individual requirements selected from those general standards for verification into the working-level procedure. I s .O 0110f/341/7 6
4.1.1 DESIGN CHECKLIST RR006-001 r-'} NJ l These checklist entries are selected to allow verification of continuing implementation of both licensing commitments identified during Unit I review and revisions or additions since then into design procedures (first-level documents) and Cesign , documents (second-level documents), and to verify that committed corrective actions for Unit 1 findings were incorporated into Unit 2 design activities. The commitment database contains approximately 190 entries which represent 75 individual commitments. The entries on the checklist provide verification of 25 of these commitments. These were selected as being representative of the major commitments and included those which required corrective action in Unit 1. The checklist is arranged so that both first-level and second-level implementation is verified. o The numbered entries are to be verified as properly ; referenced in the Design Criteria (first-level). o The numerical plus the alphabetical entries are to be verified as being complied with by an actual - specification, calculation, or drawing (second-level). 0110f/341/7 7
i i f 4.1.2 CONSTRUCTION CHECKLIST RR006-002 O . These checklist entries are selected to allow verification of continuing implementation of both licensing commitments identified during Unit 1 review and revisions or additions to ; them into construction specifications and field procedures and to verify that committed corrective actions for Unit 1 findings , were incorporated into Unit 2 construction procedures. Eighteen commitments were identified as being applicable to the construction scope of this module. The 10 commitments included , in the checklist were selected as representative of both : program-related requirements and individual technical
~
requirements. The corrective action items selected for inclusion on the checklist consist of the more significant actions to allow assessment of the inclusion of these corrective actions into Unit 2 construction procedures. 4.2 PART 2 - PROGRAMS AND ACTIVITIES , Part 2 of this assessment plan consists of six checklists; RR006-003,-004,-005, and-006-are design activity oriented and RR006-007 and-008 are construction oriented. Table 6-1 is a I listing of the equipment that is to be used for this part of the (~} 0110f/341/7 8
assessment. Specific design and construction documents and activities are to be selected from the listing on Table 6.2 and are to be directly related to the selected hardware sample. Quality Assurance is to perform the assessment for this part and will select specific documents for review based on the , guidelines in each checklist section below. 4.2.1 DESIGN CHECKLISTS RR006-003, 004, 005, AND 006 These checklists are composed of requirements selected from the Project Reference Manual and are structured to allow verification of compliance to the design change program controls required by American National Standards Institute, Inc. (ANSI) N45.2.11. In addition, checklist 007 contains individual. technical items to be verified in the appropriate calculations. 1 4.2.1.1 Checklist RR006-003, Design Change Control j 1 This checklist is to be used to assess the program controls for the various types of change documents utilized by design. Twenty Field Change Requests, 10 Design Change Notices and 10 Construction Specification Change Notices should be selected from the document types listed on Table 6.2 and assessed using one checklist for each of the above 40 documents. Change O 0110f/341/7 9
^
r~s documents that are for specific equipment numbers must be
' .d related to those tag numbers listed in Table 6.1.
4.2.1.2 Checklist RROO6-OO4, Field Equipment Change Orders l l l This checklist is to be used to assess the design program controls for Field Equipment Change Orders (FECOs). One FECO l related to each tag number listed in Table 6.1 is to be selected l (if available, if not select additional FECOs to a total of 12). l 4.2.1.3 Checklist RROO6-OOS, Change Control Packages a O This checklist is to be used to assess the design program controls for change control packages. Ten Change Control Packages (CCPs) should be selected that relate to the equipment listed in Table 6.1. One checklist is to be filled out for each CCP. 4.2.1.4 Checklist RROO6-OO5, Calculations This checklist is to be used to assess both the program controls for and technical adequacy of design calculations. The two calculations to be assessed are listed in Table 6.2. O 0110f/341/7 10
4.2.2 CONSTRUCTION CHECKLISTS RR006-007 AND -008 O These checklists are composed of requirements selected from the Field Procedures Manual and are structured to allow verification of compliance to the construction program controls of ANSI N45.2.2, N45.2.3, and N45.2.4. r l 4.2.2.1 Checklist RR006-007, Equipment Modifications This checklist contains requirements selected from Field Procedures GD-T-25, GD-T-28, and GD-T-33. Select 15 FECOs, 15 Component Removals (CRs), and 15 CCPs related to any of the hardware listed on Figure 6.1 and use one checklist for a group (one CCP, one CR, one FECO, 15 total checklists). 4.2.2.2 Checklist RR006-008, In-process Installation This checklist consists of two parts, 008A for equipment and 008B for penetrations. These checklists contain requirements from ED-T-04, CM-T-02, and GD-T-11 and are intended to assess the in-process program and technical controls imposed by these procedures. Use one checklist for each piece of equipment selected. r 1 () 0110f/341/7 11
4.3 PART 3, CONSTRUCTION AND DESIGN COMPLETION AND CONSTRUCTION ACCEPTANCE TESTING l l Part 3 of this assessment plan consists of ten checklists to assesc the continuing conformance of the as-built conditions to i regulatory requirements. Checklists RR006-009A and B contain attributes for installed hardware. Checklists RR006-010A and B contain attributes for completed construction documentation and associated turnover activities. RR006-011A examines incorporation of design change documents and finalization of I calculations. RR006-011B contains attributes to assess the FP-6 finalization program (FP) for internal electrical separation. Checklist RROO6-012 assesses procedures and activities of the construction acceptance testing program as applied to elec".rical component testing. 4.3.1 DESIGN FINALIZATION, CHECKLISTS RR006-011A and B These checklists are composed of requirements from the Project Reference Manual to allow verification of compliance to the design finalization requirements of ANSI N45.2.5 and to allow assessment of the effectiveness of implementation of corrective l actions identified during the Unit 1 review. ; i O , 0110f/341/7 12 t
. m. . . .. _ . . . __ __ __. ._. - . .. _ _ _ _ _ _ _ _
l l l 4.3.1.1 Checklist RR006-011A This checklist is to be used to verify that the change documents assessed in Part 2 have been incorporated into their respective parent documents (drawings, construction specifications) and that as-built information has been properly accounted for in finalized calculations, using the same calculations examined in-process in Part 2. 4.3.1.2 Checklist RR006-011B This checklist is to be used to evaluate the preparation, performance, and results of finalization program FP-6. 4.3.2 AS-BUILT CONSTRUCTION, CHECKLISTS RR006-009A, B, AND RR006-010A, B # These checklists are composed of requirements from procedures ED-T-04, GD-T-31, GD-A-48 and GD-A-50 and consist of C requirements selected to allow verification of the conformance of as-built hardware and related construction generated ' documentation to procedural requirements. . l 1 0110f/341/7 13 ,
4.3.3 CONSTRUCTION ACCEPTANCE TESTING, CHECKLIST RR006-012 This checklist contains attributes to verify that the Startup Manual procedures are utilized by personnel performing Construction acceptance testing activities. 5.0 CHECKLISTS The checklists were developed by applying the general attributes , listed in Table 5.1 to.the specific commitments, specifications, 1 procedures, and drawings applicable to electrical equipment and selecting a sufficient number of requirements to perform an assessment. Table 5.2 gives a listing of the checklists described within this plan. An individual checklist is to be used for each item as described in section 4. The checklist column marked " Item" provides a numerical reference, if needed when corresponding with the project. Numbers in this column in parenthesis () indicate reference to the Master Commitment Tracking List. The column marked " Reference" provides the source of the requirement to be verified. The column marked " Requirement" is repeated from the source document. Parts which have been condensed or paraphrased are delineated with brcckets []. 0110f/341/7 14 l
1 l The column marked " Finding / Comment" is for describing the actual condition found. A checkmark in the acceptable column indicates , i that the condition found is acceptable. An N/A in the acceptable column indicates that the attribute-listed is not applicable. 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. A checkmark in the " Reject" column indicates that the requirement tf the checklist item was not met at the time of i assessment. The " Resolution" column is used to indicate whether 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 :hecklists are to be signed and dated on each page by the person or persons performing the assessment and are to be completed neatly and legibly in black ink. 6.0 ITEM SELECTION The hardware and software items selected for the part 2 and part 3 assessment are listed in Tables 6-1 and 6-2. Hardware items were selected for the population of Class IE equipment Software items were selected from those design and construction 0110f/341/7 15
procedures / specifications directly applicable to electrical equipment design and installation. l l Due to the relatively small total population size, and the number of different types of equipment, statistical sampling methods are not used. The sample was chosen to allow assessment of the types of equipment that had identified discrepancies in Unit 1. l O O 0110f/341/7 16
TABLE 2-1 (SHEET 1 OF 2) O ELECTRICAL ITEM / ACTIVITY VS. MODULE Item 04 06 12 16 17 18A 19 20 Motors X X X Electrical Systems X Switchgear X MCCs X Distribution Panels X Battery Chargers X Inverters X Batteries X Penetrations X Cable Bus X l Transformers X Wire and Cable (All) X Terminations (Field) X Terminations (Vendor) X Jumpers (Field) X Jumpers (Vendor) X Heat-Shrink X Control Panels X Local Control Stations X Cabic Tray X Conduit X Junction Boxes X Pullboxes X Racewc.y Fittings X 0109f/085-7/1
[ TABLE 2-1 (SHEET 2 OF 2) O Item 04 06 12 16 17 18A 19 20 Special Raceway X Tray Supports X Conduit Supports X Box / Equipment Supports X i Electrical Instrumentation (Panel Mounted) X Electrical Instrumentation I (Field Mounted) X X 1 Electrical System Design X Cable System Design X Load Calculations X Voltage Drop X Raceway Fill X X Raceway Support Loading X X h 5 'O t 0109f/085-7/1
l l ('N TABLE 5-1 (SHEET 1 OF 2) (_) MODULE 6 - ELECTRICAL EQUIPMENT ASSESSMENT SCOPE 1 SCOPE ' Module 6 describes the design, procurement, installation, and inspection of the following Class IE equipment: o Transformers. o Switchgear. o MCCs. o Battery Chargers. o Batteries. ; o Control Panels and Boards. o Distribution Equipment, o Inverters. o Penetrations. o Bus Systems. -O Design Aspects: B o Design Criteria. o Studies. o Calculations. o Failure Mode and Effects Analysis. o Hazards Analysis Interface, o Drawings. o Procurement Specifications.
. o Equipment Lists.
o Construction Specifications. o Relaying Data Sheets. o Design Control and Review. o Design Change Control. o Non-IE systems as the interface with IE. , o Supplier Quality Program. i o Supplier Drawings and Data. 0112f/195-7/1 ) i
. /~) TABLE 5-1 (SHEET 2 OF 2)
D SCOPE Procurement Aspects: o Supplier Quality. o Supple nr Drawings. o Supplj ,r Deviations. o SQR. o Supplier Certification Document. Construction Aspects: o Welding, o Bolting / Anchors. o Internal Wiring.
/ o Location / Orientation, o FECOs.
o M&TE. o EMSL. o Vendor Requirements, o Special Requirements. o Deviation Reports. o Inspector Qualification / Certification. o Document Retrievability. o Document Accuracy. 0112f/195-7/2
. _ .. _ _ _ . _ _ - . . _ _ . . ._ - . . . . _ . _ _ _ _ . =_ .. () TABLE 5-2 MODULE 6 - ELECTRICAL EQUIPMENT CHECKLISTS Part 1 RR006-001 Design Commitment Implementation ' RR006-002 Construction Commitment Implementation Part 2 RROO6-003 Design Change Control RR006-004 FECOs RR006-005 CCPs RR006-006 Calculations RR006-007 Construction Equipment Modification RR006-008 Inprocess Installation and Corrective Actions Part 3 RR006-OO9A Installed Equipment RR006-009B Installed Penetrations RR006-010A Document - Equipment RR006-010B Document - Penetrations RR006-011A Incorporation of FCRs, DCNs, CSCNs RR006-011B Finali=ation Walkdowns - FP-6 RR006-012 System Turnover /RFT + l 0113f/195-7/3
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/' . TABLE 6-1 ;
MODULE 6 - ELECTRICAL EQUIPMENT HARDWARE SAMPLE Equipment Tag Number Description Plant Location ) i 2-1804-S3-A03 Med. Voltage Swgr. 2BB03 C.B. RAIS l 2-1805-S3-BBB 480V MCC. 2BBB Aux. Bldg. R147 l 2-1806-B3-BYB 125VDC Batt. & Rack 2BD1B C.B. RB 32 2-1806-B3-RYB 2-1806-Q3-DA1 125VDC Dist. Panel 2AD11 C.B. RB 29 2-1808-T3-106 120V Isol. XFMR 2BBF13X D.G. B 'B' 2-1821-U3-001 Safety Feat. Seq. Board Trn. 'A' C.B. RA 16
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2-1601-QC-MCB Main Cntl. Board, Section A01 Control Room 2-1818-H3-P13 M.V. Penetration (} 2-1818-H3-P29 2-1818-H3-P50 480V Penetration Control Penetration 2-1818-H3-P71 Instrumentation Penetrations i L 0113f/195-7/4 l
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' Design Criteria i DC-1000E DC-1807 ,
DC-1BO4 DC-1816 i DC-1805 DC-1825 ! DC-1806
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i Project Reference Manual C4 Drawings C17 Field Change Requests .. C5 Vendor Data C24 FECO C8 Specifications l C26 Construction Specifications , C9 Calculations C35 CCP f C16 FMEA C37 Equipment Qualification ' i Specifications ' g X3AB03 X3AE03 l [/ s_ . X3AC01 X3AE06 ' X3ACO2 X3AF04
}CLND01 X3ARO1 i
' Calculations X3CCO2 i X3CF02-Procedures l CM-T-01 GD-T-11 CM-T-02 GD-T-17 DC-A-06 GD-T-25 l ED-T-04 TD-T-28 ED-T-09 GD-T-33 l ED-T-19 QC-A-01 ED-T-32 QC-A-02 GD-A-04 l
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