ML13317B320
| ML13317B320 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 02/28/1991 |
| From: | Curran J, Schone D Southern California Edison Co |
| To: | |
| Shared Package | |
| ML13317B318 | List: |
| References | |
| DBD-1, NUDOCS 9103130136 | |
| Download: ML13317B320 (33) | |
Text
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g DBD-1 PROGRAM PLAN Design Bases Documentation (DBD) Program San Onofre Nuclear Generating Station (SONGS)
Unit 1,2, and 3 Prepared by:
D. A. CHONE Approved by:
J. M. CURRAN Revision 5 February, 1991 Sothm Cal iamia Edison 9103130136 910311 PDR ADOCK 050026
SCE'S DESIGN BASES DOCUMENTATION & RECONSTITUTION -
PROGRAM PLAN TABLE OF CONTENTS SECTION DESCRIPTION PAGE I.
INTRODUCTION......
1 II.
OBJECTIVES.......
2 III.
SUB-OBJECTIVES.......
3 IV.
SCOPE........
3 V.
VALIDATION.......
5 VI.
OPEN ITEMS.........................
6 VII.
PILOT DBDs.......
7 VIII.
IMPLEMENTATION SCHEDULES..
8 IX.
DBD FORMAT.........................
11 X.
DBD REFERENCE DATA RETRIEVAL.
.....13 XI.
NOTES...........................
15 APPENDIX A - DBD Preparation Schedule Process APPENDIX B - DBD Program Related Definitions APPENDIX C - DBD Program Guideline Listing of Reference Sources
SCE'S DESIGN BASES DOCUMENTATION & RECONSTITUTION - PROGRAM PLAN I.
INTRODUCTION The purpose of Southern California Edison's San Onofre Design Bases Documentation and Reconstitution Plan is to outline a program to retrieve, reconstruct, confirm, and document San Onofre Nuclear Generating Station's nuclear power plant design bases in a series of Design Bases Documents. The intent of the program is to establish and document the rationale or "whys" for the design bases.
There has been a growing concern over the past few years within the nuclear industry regarding design basis issues. NRC activity in this area has included a variety of inspections and surveys.
The Nuclear Management and Resources Council (NUMARC) has recently issued NUMARC Design Basis Program Guidelines, NUMARC 90-12 dated October 1990. One of the issues that has been identified as a result of these activities is the potential lack of retrievability and accessibility of design documents.
The NRC has determined that there have been instances where "modifications have been made without sufficient engineering basis and have compromised safety system functionality."
Per the NRC, "missing or unretrievable design documentation appears to be a root cause of these problems."* The NUMARC Design Basis Program Guidelines note that many design documents for a plant may be stored without an easy means of retrieval, and NUMARC urges that utilities consider indexing such documents.
Without modifications, plant improvements, or repairs, the only documents that would be required to operate a nuclear power plant would be the operational and maintenance manuals and procedures together with the Hazards Analysis or Safety Analysis Reports. However, equipment degrades, plants experience transients, and modifications and improvements are implemented to increase efficiency and sustain long term operation. In large complex and interactive designs such as commercial nuclear facilities, a minor alteration could result in the degradation of system performance in the long or short term which may reduce the margins of safety beyond the approved design envelope. Design basis and supporting information is essential for use in selected plant activities that support the continued safe operation of the facility.
A systematic Design Bases Documentation (DBD) development process establishes meaningful plant design bases and ensures prompt access to associated documents. Access to DBDs will facilitate greater efficiency and increased quality of future plant changes and associated safety evaluations. The DBD Program will improve the SCE technical staff's design bases understanding.
The program will document the original bases of the design for consistency comparison with existing design details and as-built, as-operated, as maintained information. Such data will be accessible to SCE's operating, maintenance, oversight groups and engineering staffs.
Quotations taken from a slide presented by Brian K. Grimes, Director, Division of Reactor Inspection and Safeguards, presented at the NRC Regulatory Information Conference, Washington D. C., May 1-2, 1990.
-2 The SCE DBD Program documents detailed design bases information that reflects plant design at the time of the operating license issuance with subsequent design basis modifications incorporated. Development of the DBDs will result in a significant data base of essential design basis information being established and verified.
The SCE DBD Program Plan is a living document throughout the DBD preparation program. Lessons learned are incorporated. Industry DBD efforts are reviewed for applicability to SONGS. SCE's DBD Program conforms to or exceeds development guidelines prepared by:
o The SCE Independent Assessment of the Engineering and Technical Support to San Onofre Nuclear Generating Station, Three (3) Volume Report dated August 1988.
o The INPO Design Requirements Documentation Guidelines, June 13, 1988, draft. Per INPO, the draft effort was transmitted to NUMARC as input for consideration into the final 1990 NUMARC DBD Program Guidelines.
o Region V Utilities - Guidelines for the Establishment of Design Bases Documentation Programs, dated May 19, 1989.
Reference:
John B. Martin, Regional Administrator Region V NRC, presentation at the April 18-20, 1989 NRC Regulatory Information Conference, Washington D.C.
o NUMARC Design Basis Issues (DBI) - Design Basis Program Guidelines, NUMARC 90-12 dated October, 1990.
II.
OBJECTIVES The DBDs are intended to be used to support a variety of engineering, licensing, and plant activities such as operations, maintenance, and site technical.
However, without a clear sense of the objectives that the DBDs are developed to achieve, the program could produce documents of minimal value to the intended users. Thus, it is imperative that objectives be identified as an initial step in the program. As DBDs are developed, they are evaluated by the degree to which they fulfill the following program objectives.
A) Consolidate basic design bases information into a single source document, system or topical DBDs, which communicate basic design bases, including reference to sources; B) Preserve corporate memory and understanding of the underlying technical rationale for the original plant design and subsequent design changes. Minimize the effect of normal attrition of key individuals within SCE, the NSSS Supplier, and other key contractor personnel; C) Enhance the quality of design changes through improved accuracy, accessibility, definition, and understanding of the design basis; D) Provide controlled design bases information to organizations who must follow design requirements in fulfilling their responsibilities;
-3 E) Provide condensed technical information used to improve the quality of safety evaluations of plant changes and improve the process and thoroughness of 10CFR50.59 evaluations; F) Provide a documented reference to support operability evaluations and the development of justifications for continued operation (JCOs); and G) Provide a documented reference to support the review of Technical Specifications changes.
The above listed objectives are certainly not all inclusive. They are targeted at the engineering and licensing areas as the primary beneficiaries of DBDs. There are many other plant activities that should benefit from-a design bases program. For example, documentation management aspects are improved as a result of the preparation and related configuration control of the plant systems and topical DBDs.
III.
SUB-OBJECTIVES, Data Management It is necessary to maintain DBD data in a form that is usable, current and accurate. Objectives in this area are to:
o Document and address design database omissions; 0
Provide procedures that ensure information pertinent to the design bases, such as correspondence and procedure changes is properly reviewed. Assure that appropriate information is incorporated, and that the documentation is current. Refer to Section VI, herein Open Items, for the DBD program process for identifying and correcting data control deficiencies; o Provide a cross-index to lower tier design database documents, including an index of applicable calculations to enhance retrievability by key users; and o
Improve the effectiveness and efficiency of the plant design change process through use of an organized database that reduces and streamlines design document searches.
IV.
SCOPE The scope of this program is provided in the schedule of plant systems and topical areas listed in Appendix A. The schedule includes systems with safety-related functions, systems considered important to plant safety, key and non-safety related systems. Systems covered in the Technical Specifications have been included.
The DBDs are structured on a "mixed approach", which includes descriptive text plus appropriate document referencing. The mixed approach includes texts of:
o design bases o
supporting design information o
component descriptions
-4 With references to:
o calculations o
specifications o codes and standards o other documents In general, the contents of self-contained documents are not duplicated in the DBD. Rather these documents are incorporated by reference, when applicable. Examples of self-contained documents include:
o ASME Code Stress Reports.
o Equipment Qualification Data Packages o Vendor Manuals o Operations and Maintenance Procedures o
Industry Codes and Standards o Specifications o Design Changes, Calculations o Design Detail Drawings Typical source and reference documents having relationship to DBDs and Configuration Management are depicted graphically to aid in DBD preparation, as follows:
Terminology Relationships D8&M Procedures Instructions Configuration 5her Man agemnen t Physical Plant Other Controlled Documents Design BasesCotl esg Hases Calculations Sp~ecs Req Regs-Analysis Drawings Other osegn R e-gs
-EvTaluat17ons Lists Design Design Des ig n Des ig n Documents Input Process Output NUMARC 90-12, Fig 1
-5 V.
VALIDATION Each SCE DBD will be validated through a process intended to provide reasonable assurance that the DBD is complete, accurate and consistent with the existing as-designed, as-licensed, as-built, as-operated, as-maintained configuration of.the plant.
The objectives of the validation process are:
- 1. to provide reasonable assurance that the information included in the DBD is consistent with the plant's design and configuration, and
- 2. to identify programmatic deficiencies or systematic errors occurring in the preparation of DBDs and recommend corrective action.
- 3. to apply lessons learned applications, the DBD Program will:
o Clarify key design bases parameters for the systems and major components. The program will do this for each plant, scheduled system, and major component operating mode.
o Provide special attention for vendor supplied subsystems (i.e., skid mounted equipment).
o Verify key engineering parameters used to determine system and component operability are incorporated into operations and maintenance procedures (maintenance procedures principally means those involved with surveillance).
o Verify that operational and maintenance parameters used to demonstrate system and component operability have been properly derived from the design bases.
o Verify the post-installation testing program for system and/or components meet these parameters, following design modification activities.
The scope of the validation process may vary from a selective educated sample to a more comprehensive validation of the information, as warranted. The scope will be prescribed by several factors including importance to safety of the system components, history of past problems, complexity, size, etc.
The DBD Program validation technique elements are:
- 2. Supervisory review of the document throughout the DBD preparation stages, in addition to the documented evaluation by an Independent Review Engineer (IRE), and
- 3. An interdisciplinary review performed by cognizant technical personnel from Nuclear Engineering, Nuclear Licensing, Station Technical and other sections of the Nuclear Organization, independent of the DBD Section.
-6 A vertical assessment (SSFI type inspection/audit) of select areas by an independent group specially dedicated to this task may be used as a supplement to the validation process. The selection of the appropriate method, dependent on.the DBD System, is made by DBD Management on a case by case basis. The vertical assessments consist of a review, on an educated sampling basis, of the adequacy, completeness, and consistency of the material presented in the DBD package. Procedures are developed to provide guidance to the personnel participating in validation activities.
VI.
OPEN ITEMS A process is in place to effectively manage and track the resolution of open items, inconsistencies, or discrepancies identified during the implementation of the DBD program. The fundamental purposes of the Open Item Report (OIR)
Process are:
- 1.
To act as a mechanism for establishing the correctness of the design bases of a system where questions, concerns, lack of information, or errors exist.
- 2.
To provide a thorough, comprehensive process that will adequately assess the impact of open items on the continued safe operation of the plant.
Examples of the types of open items which have arisen or can be expected are:
o Documents are not readily retrievable, o
Data and/or documents cannot be located, o
Discrepancies/contradictions between references, and o
Errors of omission.
A controlled listing of open items is prepared during the process of drafting the DBDs.
Following the identification of an open item, a screening review is performed to quickly determine its potential safety significance. If the identified open item does not involve a safety concern, the Open Item Report (0IR) will continue to be evaluated and dispositioned and will be subject to supplemental review during the final evaluation. If the identified open item is determined to be potentially safety significant, then the Non-Conformance Report (NCR) process is initiated. In accordance with the SCE Topical Quality Assurance Manual (TQAM), safety significant discrepancies items are reviewed for inclusion in SCE's NCR Program. Thus, DBD open items that meet the test of a non-conformance are:
o Assessed for reportability as required by 10CFR50; o
Assessed for impact on operability; and o
Cause and corrective action appropriately documented, etc.
0-7 All other open items will be separately tracked through resolution, via issuance of DBD OIRs.
All NCRs and OIRs that affect the DBD content or conclusions are listed in each DBD at issuance.
The OIR procedure (NES&L Quality Procedure 25-5-1) includes an Open Item priority system. The OIRs and the DBDs are linked together on a priority basis to ensure that the disposition and resolution of the OIR is incorporated into the DBDs.
SCE, as part of the NUMARC DBI Working Group, reviewed the NUMARC Design Basis Program Guidelines with special attention to Open Items to ensure that SCE's program is consistent with or exceeds the generic guidelines.
VII.
PILOT DBDs To adequately evaluate and confirm the initial DBD Program path SCE had chosen to follow, SCE initiated four pilot DBDs. The prime selection criteria for the 1989 Pilot DBDs, were as follows:
o Produce Pilot DBDs, representative in both their technical and administrative aspects; o
Select Pilot DBDs that addressed recent issues such as the Units 2/3 Component Cooling Water (CCW) System task force effort; o
Select a representative number of systems in all units that also provide a typical cross-section of engineering disciplines of primary interest to an operating plant; and o
Include at least one Topical pilot DBD sample that illustrates the inherent differences which exist in Topical DBDs (e.g., EQ,.
Seismic, Fire Protection) as compared to single System DBDs (e.g.,
CCW System, etc.).
The above listed criteria were met with the selection of the following Pilot DBDs:
- 1. S023, Component Cooling Water (CCW) Systems. - Mechanical discipline/builds on recent Operability Assessment.
- 2. SO1, Environmental Qualification (EQ). - Electrical discipline and a Topical area.
- 3. 301, Safeguard Load Sequencing System (Sequencer). - I/C discipline/builds on related design change interfaces.
- 4. S023, Instrument Air Systems. - Mechanical discipline/builds on work required to respond to NRC Generic Letter.
During the Fourth Quarter of 1989, two of these pilot DBDs, i.e., SO1 Sequencer and 5023 Instrument Air System, were subjected to vertical assessments using a process similar to the NRC's Safety System Functional Inspections (SSFIs). Following these efforts, the program was revised, as appropriate, and development of production DBDs began.
-8 Note, two of the pilots were not fully completed in 1990 and have been incorporated into the production schedule for 1991. However, lessons learned from all four pilots and the vertical assessment were incorporated into the 1990 and beyond DBD program.
VIII. IMPLEMENTATION SCHEDULES A. Program Procedures The Procedures governing the DBD Program activities are being developed in compliance with the SCE Quality Assurance Program. The DBD Program is addressed in the Topical QA Manual in Chapter 2-A Design Development, Review and Approval under TQAM Sections 1.0 and 3.0.
The DBD Program includes development of a system of procedures and guides to control the production of the DBD packages. The following categories of documents are being developed.
Procedures for the preparation of DBDs Procedures for the administration of DBDs Desktop Guides A listing of these procedures and their status is provided below.
Completion of the original issuance is scheduled by the end of the First Quarter of 1991.
Procedures for the Preparation of DBDs:
All are available except as noted(*)
25-1-1 Guidelines for System DBD Preparation 25-1-2 Calculation Review Methodology 25-1-3 Setpoint Studies & Documentation Review Methodology 25-1-4 Margin/Uncertainty Assessment * (in preparation) 25-1-5 System Boundary Definition Methodology 25-1-6 Methodology for the Review of References in Plant Operating Instructions for the Design Bases Documentation Program 25-1-7 Motor Operated Valve Review Methodology for the Design Bases Documentation Program 25-1-8 Limiting Conditions for Operation and Technical Specification Bases Review Methodology 25-1-9 Licensing Basis and Commitments Review Methodology 25-1-10 Electrical Interlock Functional Testing and Review Methodology 25-1-12 Preparation of the Environmental Qualification Master List Verification in Conjunction with the Development of the System DBD Report 25-1-13 Inservice Testing Review Methodology
- 9 25-1-14 Post Modification Testing and Review Methodology 25-1-15 Spurious Circuit Actuation * (in preparation) 25-2-1 Guidelines for Topical DBD Preparation Procedures for the Control of DBDs 25-5-1 Open Item Report for the Design Bases Documentation Program 25-5-5 Review, Approval, and Issuance of Design Bases Documents 25-5-6 Revision, Maintenance, and Control of DBDs Desktop Guides DBD-3 Style Guide for DBD Writers and Text Processors ID-pending Ultimate Heat Sink Operability Review Methodology B. DBD Reviews, Milestones o
At the 10%, 50%, and 90% DBD development milestones, DBD Management Staff reviews are held.
MILESTONE(%)
DBD REVISION DEFINITION NA NA o Initial reference data retrieved and System Design Engineer (SDE) on-board 10 %
NA o System/Topical functions defined o System/Topical interfaces established o System/Topical boundaries (DBD Scope) established o Confirmation of resource and documentation adequacy 50 %
NA o
Draft DBD completed o Open items identified o Supervisory review complete o Plan Validation 90 %
A o Validation Implementation o Interdisciplinary review o Final supervisory review of comments 100 %
0 o All comments resolved and incorporated o DBD complete, CDM issues DBD C. Graphical Schedule - See next page for 1991 Target DBD Implementation
UT&A DISC UN IT OBO 110/30 11/90 112/90 1/91 2/91 3/31 4/31 5/91 E5/9 S
/91 3/91 9/311 10/911 11/91 112/91 I
J 1
NIS 2
M 1
AIR/B/U NITROGEN 3
i SAFEGUARD LOAD SEQUENCINGI 4
M 1
W 5
A I
PLANT LEVEL 6
m 1
SWC 7
E 1
EO 9
E 1
- 4KV, 12KV, 480V 9
E 2/3 125V & 25OVDC 10 N
A SINGLE FAILURE 0
11 M
2/3 CW I
12 1
A HUMAN FACTORS 12 13 IvI 2/3 SWC 1
14 M
2/3 AFW 15 J
1 RAD M4ONITORING I
16 E
2/3 E0 17 E
1 125V DC I
0 19 M
2/3 AI/
9/U NITROGEN 19 A
2/3 PLANT LEVEL I
NOPMA.L AND EMERG I
20 M
2/3 CHILLED WATER I
21 J
2/3 Rx PROTECTION SYS I
22 J
2/3 ESF I
23 A
A CODES & STANDARDS I
24 N
A HAZARDS I
25 N
2/3 ACCIDENT ANALYSIS I
199-1 FEBRUARY 91 DBD DEVELOPMENT PLAN FILE:DBDMA.N
- 11 IX.
DBD FORMAT Although the DBD Program Procedures provide the specific guidelines for the preparation of the DBDs, the program format elements are addressed below to provide general information on the level of detail and content of the DBDs.
A. SYSTEM DBD PACKAGE CONTENT FORMAT The format guidelines for the DBD Packages are as follows:
TABLE OF CONTENTS PREFACE:
- 0.
PURPOSE
- 1.
SYSTEM OVERVIEW 1.1 System Boundaries 1.2 System Interfaces 1.2.1 Services Supplied 1.2.2 Support Services Required 1.3 Quality Classification and Seismic Classification 1.4 System Programmatic Issues
- 2.
FUNCTIONAL DESCRIPTION 2.1 Safety Function 2.2 Important to Plant Safety Functions 2.3 Non-Safety Functions
- 3.
SYSTEM OPERABILITY REQUIREMENTS
- 4.
COMPONENT PARAMETERS FOR SYSTEM FUNCTIONALITY
- 5.
APPLICABLE CODES, STANDARDS, AND REGULATORY DOCUMENTS 5.1 General Design Criteria 5.2 Regulatory Documents 5.2.1 As Licensed 5.2.2 Since-Licensed 5.3 Codes and Standards 5.3.1 Codes of Record 5.3.2 Additional Codes and Standards
- 12 6.0 ADDITIONAL DESIGN BASES CONSIDERATIONS 6.1 Testing and Inspection Requirements 6.2 Single Failure/Common Mode Failure 6.3 Internal and External Hazards 6.4 Leakage 6.5 Interlocks 6.6 Emergency Power Supply 6.7 Over-pressurization Protection
7.0 REFERENCES
8.0 APPENDICES APPENDIX A, Open Item Reports (OIRs)
APPENDIX B, Technical Data APPENDIX C, Tables APPENDIX D, Figures APPENDIX E, Licensing Bases/Commitments (optional)
APPENDIX F, Significant Design Modifications APPENDIX G, Summary of Design Basis Calculations Note:
The format and the content as previously described includes lessons learned from the pilot DBDs. In addition, specific sections of the DBD include a tabular summary presentation of the bounding parameters or values which confirm that the systems and their critical system components are capable of performing their intended functions.
Tabular presentation of bounding parameters and values is applicable to both System and Topical DBDs.
B. TOPICAL DBD GENERIC OUTLINES The following generic outline applies to Equipment, Event, and/or Activity Topical DBDs PREFACE 0.0 PURPOSE 1.0 TOPIC DESCRIPTION
-13 1.1 Definition of Topic 1.2 System Applicability 1.3 Background (Event Topicals) 2.0 APPLICABLE CODES, STANDARDS, AND REGULATORY REQUIREMENTS 2.1 General Design Criteria 2.2 Codes and Standards 2.3 Regulatory Documents 3.0 TOPICAL DESIGN BASES 3.1 Historical Bases 3.2 Current Bases 4.0 TOPICAL REQUIREMENTS Equipment Related:
OR:
Event Related:
4.1 General Considerations 4.1 Safety Functions 4.2 Parameters 4.2 Method of Analysis 4.3 Limitations 4.3 Results Summary 4.4 Conclusions OR:
Activity Related:
4.1 Safety Analysis 4.2 Limitations 5.0 Design Bases Modification History
6.0 REFERENCES
Reports Appendix A Open Item Reports Appendix B Tables Appendix C Figures X. DBD REFERENCE DATA RETRIEVAL A. Reference Sources:
In addition to record retrieval from SCE's Corporate Document Management (CDM) system, it is necessary to retrieve select data records from three primary sources, namely:
o Combustion Engineering (C-E), SONGS Unit 2/3 Nuclear Steam Supply System (NSSS) Vendor, o
Westinghouse (W), SONGS Unit 1 NSSS Vendor, and o
Bechtel Power Corporation (BPC), SONGS 1, 2 and 3 Architect Engineer (AE)
14 The C-E data retrieval effort was part of a joint effort of the C-E Owners Group (CEOG) Configuration Management Task Force (CMTF).
The C-E CMTF systematic approach effort was completed in 1990. The product includes a value added index of over 80,000 documents with over 17,000 San Onofre related documents containing an estimated 360,000 pages of calculations, studies, evaluations, and correspondence.
The product options included optical disk transfer of the index and image of the 360,000 pages. SCE elected to select the optical disk option for ultimate integration into existing SCE PC applications beyond the near term DBD preparation effort. The C-E FileNet optical image system became an integral part of the DBD Library in mid-1990.
In addition, the C-E database index has been combined with two other related SCE databases for over 80,000 document indices available on the mainframe-host called Nuclear Document Reference System, NDRS. Other applicable databases are planned for relation database integration with release 2 of NDRS.
A Westinghouse WCAP Index of Westinghouse (W)
SONGS-1 records was obtained in Mid 1989 and retrieval of selected (W) records and calculation summaries will be under way throughout 1991.
During the 4th Quarter of 1990, four (4) additional WCAPs were completed as a result of a pilot (W) effort for SONGS concentrating on Unit 1 fluid systems.
The majority of design documentation produced by Bechtel (BPC) was transferred to SCE's CDM at commercial operation. As part of the DBD effort, a review of older Unit 1 BPC records not transferred to CDM was recently performed. From this review approximately 20,000 design documents are being indexed. A computer index of the effort is available and is in use within the DBD Section.
B. Computer Assistance and Control Aspects Most utilities use their existing design change control process to control changes to DBD information. As the design authority, the design engineering organization usually has the primary responsibility to ensure changes are properly reviewed, verified, and approved.
Similarly, changes to DBDs often affect many documents and analyses. To assist in identifying affected documents and analyses, matrices that cross reference documents is under on going development. These matrices are often computer-based because of the number and complexity of interactions involved.
The extent of SCE's first phase DBD computerization was finalized prior to beginning the 1990 production DBDs, namely:
The Rev-0 DBDs are entered into two (2) connected computerized PC applications, namely:
o Text-Search of SONGS Documents (TextWare) contained in the IOC Network Library of the Nuclear Retrieval Data System and at the Site. TextWare allows section index searches, key-word and phrase searches and text viewing. Text-Search normally contains text only.
-15 o
San Onofre Document Management System (SDMS). SDMS is an optical image of the entire document including signature approvals and all tables and figures. Optical image systems do not presently contain word search features.
The combination of Text-Search and SDMS affords flexibility in the access of DBD packages. Text-Search and SDMS are linked between NES&L Irvine Operation Center (IOC) and the SONGS Site. DBD revisions are controlled via a single input to SDMS that automatically updates the Text-Search application. Hard copy of the DBD packages are also issued to select controlled locations at the IOC and Site.
The original DBD packages are filed in Technical Services-Drawing Control at the Irvine Office and indexed in Corporate Documentation Management (CDM)-SCE Document Configuration System (SDCS) as a design disclosure, revision controlled document.
Additional computerization under review, on an initial development basis, for the DBD effort includes:
o Optical imaging and computer assisted user-friendly menus for a DBD document review/retrieval work station(s).
o "Value-added" indexing and integration of existing computer databases for retrieval of select engineering and licensing documentation, applicable for expansion to optical imaging.
o Computerization of engineering and licensing documents on a hierarchy reference basis.
XI NOTES:
The SCE Design Bases Documentation Program Plan is routinely updated. As DBD activities progress, pertinent information, direction and insights from lessons learned will be incorporated into the Program Plan updates.
Refer to the attached Appendices:
Appendix A - DBD Preparation Schedule Appendix B - DBD Program Related Definitions Appendix C - DBD Program Guideline Listing of Reference Sources
APPENDIX A DBD PREPARATION SCHEDULE PROCESS A. DBD PREPARATION SCHEDULE CRITERIA The following criteria were used in preparing the attached schedule:
- 1.
The plant systems were ranked separately for Unit 1 and Units 2 and 3.
- 2.
Ranking was performed based on:
o Importance to plant safety o
Design considerations o
Operations and maintenance considerations
- 3.
The schedule covers the period 1990-1995 with approximately fifteen systems completed every year.
- 4.
Systems ranked as low priority are not included in the schedule.
Sub-Objectives:
o Where practical, issue the production DBDs to match the needs of San Onofre; o
Target DBD completion prior to planned design change activities for particular systems; and o
Schedule Design Engineering/Station DBD support compatible with unit outages and specific needs.
B. Summary:
Unit 1 Units 2 & 3 Units 1/2/3 Plant Systems DBDs Scheduled 31
+
34
=
65 Topicals DBDs Scheduled 13
+
13
=
26 TOTAL SCHEDULED 44
+
47
=
91 The previous listed planned DBDs represent consolidation and additions.
However, the nuiber of planned DBDs, i.e.
91 DBDs, is same as in the previous Program Plan revision.
The 91 DBDs scheduled through 1995 include the four pilot DBDs started in 1989.
A2 DESIGN BASES DOCUMENTATION PREPARATION SCHEDULE FOR THE YEAR 1990 START REV. 0 UNIT DBD ID SYSTEM TITLE REMARKS Feb 89 Dec 1990 1
DBD-SO1-590 Safeguard Load Sequencing
DBD-SO1-TR-EQ Environmental Qualification
- Topical Jan 90 Dec 1990 1
DBD-S01-410 Instr Air & Backup Nitrogen *
/420 (Compressed Gas & Air Systems)
Feb 90 Dec 1990 1
DBD-SO1-380 Nuclear Instrumentation System
- Feb 90 Dec 1990 1
DBD-S01-340 Saltwater Cooling System
- Mar 90 Dec 1990 1
DBD-SO1-330 Component Cooling Water System
- Completed -
6 DBDs completed in 1990 Note:
DBD Identifications (IDs) match System Descriptions IDs, (e.g., DBD-SO1-330 matches SD-SO1-330)
A3 DESIGN BASES DOCUMENTATION PREPARATION SCHEDULE FOR THE YEAR 1991 START REV. 0 UNIT DBD ID SYSTEM TITLE REMARKS Apr 90 1st Qtr 91 1
DBD-SO1-120 4KV, 480V & 12KV Electrical
/130 Dec 90 3rd Qtr 91 1
DBD-SO1-540 Radiation Monitoring Systems 550/560 Apr 91 4th Qtr 91 1
DBD-SO1-140 125V DC Mar 91 4th Qtr 91 1,2&3* DBD-S0123-TR-SF Single Failure Topical Feb 90 3rd Qtr 91 1,2&3* DBD-S0123-TR-HF Human Factors Topical Jan 91 4th Qtr 91 2&3 DBD-S023-TR-EQ Environmental Qualification Topical Dec 90 4th Qtr 91 2&3 DBD-S023-TR-AA Accident Analysis C-E performing a CEOG Topical Pilot on SONGS AFW-Phase 1 Apr 91 4th Qtr 91 2&3 DBD-S023-TR-PL Plant Level-Added DBD Topical Feb 91 4th Qtr 91 1,2&3* DBD-S0123-TR-CS Codes and Standards Topical Feb 91 4th Qtr 91 1,2&3* DBD-S0123-TR-HZ Hazards-Internal & External Includes pipe breaks, see Topical Fire Hazards & Seismic DBD
22 DBDs Scheduled for completion in 1991
A4 DESIGN BASES DOCUMENTATION PREPARATION SCHEDULE FOR THE YEAR 1991 START REV. 0 UNIT DBD ID SYSTEM TITLE REMARKS 1991 Continued Jun 89 4th Qtr 91 2&3 DBD-S023-400 Component Cooling Water System Feb 90 3rd Qtr 91 2&3 DBD-S023-780 Auxiliary Feedwater System Jan 90 4th Qtr 91 2&3 DBD-S023-410 Salt Water Cooling System Apr 90 4th Qtr 91 2&3 DBD-S023-140 125V & 250VDC Mar 89 4th Qtr 91 2&3 DBD-S023-540 Instrument Air & Backup Nitrogen Includes Aux Gas System
/570 On Hold Since Jan 90 Feb 91 4th Qtr 91 2&3 DBD-S023-800 Normal and Emergency Chilled Water Feb 91 4th Qtr 91 2&3 DBD-S023-710 Reactor Protection System Feb 91 4th Qtr 91 2&3 DBD-S023-720 Engineering Safety Feature (ESF)
Actuation System
A5 DESIGN BASES DOCUMENTATION PREPARATION SCHEDULE FOR THE YEAR 1992 START REV. 0 UNIT DBD ID SYSTEM TITLE REMARKS 1
DBD-SO1-190 Main Steam System 1
DBD-S0l-280 Reactor Coolant (RC) System Includes Reactor Core, 290/300/390 Vessel Internals, RC Pumps
& Primary Process Instrumentation.
1 DBD-SO1-320 Residual Heat Removal (RHR)
Westinghouse Owners Group System RHR retrieval in 1991.
1 DBD-S01-210 Condensate & Main Feedwater
/260 Control Systems 1
DBD-S01-150 Maintained 120V AC System 1
DBD-S01-TR-AA Accident Analysis Topical 1,2&3*
DBD-S0123-TR-ES Electrical Separation, Includes Cable/Raceway Topical separation 1,2&3*
DBD-S0123-TR-OA Operator Actions Topical 1,2&3*
DBD-S0123-TR-FP Fire Protection Topical
19 DBDs Scheduled for completion in 1992
A6 DESIGN BASES DOCUMENTATION PREPARATION SCHEDULE FOR THE YEAR 1992 START REV. 0 UNIT DBD ID SYSTEM TITLE REMARKS Year 1992 Continued Nov 91 2nd Qtr 92 1
DBD-SO1-TR-PL Plant Level-Added DBD Topical Dec 91 4th Qtr 92 2&3 DBD-S023-120 6.9KV, 4KV & 480V Electrical Systems 2&3 DBD-S023-360 Reactor Coolant System 2&3 DBD-S023-470 Excore Nuclear Instrumentation 2&3 DBD-S023-510 Control Element Drive Mechanism Control System 2&3 DBD-S023-460 Incore Nuclear Instrumentation 2&3 DBD-S023-740 Safety Injection, Containment Spray, and Shutdown Cooling
A7 DESIGN BASES DOCUMENTATION PREPARATION SCHEDULE FOR THE YEAR 1993 START REV. 0 UNIT DBD ID SYSTEM TITLE REMARKS Jan 90 Dec 93 1
DBD-SO1-580 Safety Injection System (SIS)
On 8/90 held a 10% DBD Review pending U-1 Chap 15 Accident Analysis Reconstitution.
Jan 90 Dec 93 1
DBD-SO1-580 Containment Recirculation On Oct 24, 1990 following and Spray System (CRS) the 50% DBD Review, it was determined that the CRS DBD could not be completed until the Unit 1 Chapter 15 Accident Analysis Reconstitution is complete in 1992.
1 DBD-SO1-620 Auxiliary Feedwater System 1
DBD-SO1-590 Engineering Safety Feature Combines existing Safeguard Actuation System (ESFAS)
Load Sequencer System (SLSS), with Containment Spray Actuation System (CSAS), Containment Isolation Actuation System (CIAS), and Aux Feedwater Actuation System (AFWAS) 1 DBD-SO1-600 Diesel Generator 1
DBD-SO1-570 Reactor Protection System and permissives 1
DBD-SO1-680 Dedicated Safe Shutdown System 19 DBDs scheduled for completion in 1993
A8 DESIGN BASES DOCUMENTATION PREPARATION SCHEDULE FOR THE YEAR 1993 START REV. 0 UNIT DBD ID SYSTEM TITLE REMARKS Year 1993 Continued 1
DBD-S01-640 Control Room and Tech Support Center (TSC) HVAC System 1,2&3* DBD-S0123-TR-ST Structures Topical 1,2&3* DBD-S0123-TR-SC Seismic Topical 2&3 DBD-S023-820 Accident Monitoring System 2&3 DBD-S023-130 120V AC System 2&3 DBD-S023-750 Emergency Diesel Generators 2&3 DBD-S023-690 Radiation Monitoring Systems
/700 2&3 DBD-S023-430 Fuel Handling and Refueling Systems 2&3 DBD-S023-390 Chemical and Volume Control System 2&3 DBD-S023-590 Fire Detection and Protection Systems
A9 DESIGN BASES DOCUMENTATION PREPARATION SCHEDULE FOR THE YEAR 1994 START REV. 0 UNIT DBD ID SYSTEM TITLE REMARKS 1
DBD-SO1-630 Containment and Containment Isolation Systems 1
DBD-SO1-450 Containment Monitoring System Includes Airborne HVAC,
/670 Hydrogen Monitoring and Recombiner Systems.
1 DBD-SO1-350 Fuel Transfer, Handling, and Storage Systems 1
DBD-S01-520 Liquid & Gaseous Radwaste Systems
/530 2&3 DBD-S023-770 Containment Systems 2&3 DBD-S023-250 Main Feedwater System 2&3 DBD-S023-160 Main and Reheat Steam System Includes Steam Bypass
/175 and Control Systems.
2&3 DBD-S023-260 Main Feed Systems, Mechanical and Controls Systems 2&3 DBD-S023-650 Coolant & Gaseous Radwaste System
/660 9 DBDs scheduled for completion in 1994
A1O DESIGN BASES DOCUMENTATION PREPARATION SCHEDULE FOR THE YEAR 1995 START REV. 0 UNIT DBD ID SYSTEM TITLE REMARKS 1
DBD-SO1-310 Chemical and Volume Control System 0
1 DBD-SO1-400 Rod Control System 1
DBD-S01-New Incore Instrumentation System 1
DBD-SO1-New Accident Monitoring System 1
DBD-SO1-650 Post Accident Sampling System 2&3 DBD-S023-810 Post Accident Sampling System 2&3 DBD-S023-620 HVAC-Misc. Ventilation Systems 7 DBDs scheduled for completion in 1995
All STATUS AND SCHEDULE CHANGES FROM REVISION 4 TO THIS REVISION 5 OF THE DBD PROGRAM PLAN:
UNIT DBD ID SYSTEM TITLE REMARKS A. DBDs Originally Planned and included in the total 91 DBDs, but are Pending a Reassessment of Need:
2&3 DBD-S023-480 Reactor Regulating System 1
Topical Security 2&3 Topical Security 2&3 DBD-S023-600 Plant Communication System 2&3 DBD-S023-530 Turbine Plant Cooling Water System 2&3 DBD-S023-190 Condenser Air Removal System 1
DBD-SOl-440 Meteorological/Seismic Monitoring System 2&3 DBD-S023-490 Plant Monitoring System 2&3 DBD-S023-550 Auxiliary Steam/Auxiliary Boiler System Clarification and reason for Schedule Changes are contained in the Remarks Section in the previous Yearly Lists.
A12 STATUS AND SCHEDULE CHANGES FROM REVISION 4 TO THIS REVISION 5 OF THE DBD PROGRAM PLAN:
UNIT DBD ID SYSTEM TITLE REMARKS Continued B. DBDs Added As A Result Of A Needs-Review:
1 Topical 1991 Plant Level, Overview Guide Plant Level Topicals assist the Systems DBD preparation.
2&3 Topical 1991 Plant Level, Overview Guide Plant Level Topicals assist the Systems DBD preparation.
2&3 DBD-S023-720 Engineering Safety Feature (ESF)
Actuation System 1
DBD-S01-590 Engineering Safety Feature (ESF)
Actuation System 1
DBD-SO1-670 Hydrogen Monitoring & Recombiner Added to Containment Monitoring (DBD-SO-1-450)
Clarification and reason for Schedule Changes are contained in the Remarks Section in the previous Yearly Lists.
APPENDIX B DBD PROGRAM RELATED DEFINITIONS B.1 Configuration Management:
An integrated process whereby (1) the design requirements for plant structures, systems, components, software, and hardware are defined and documented. (2) changes to these design requirements are identified, documented, controlled, evaluated, and approved or disapproved, (3) approved design changes and implementation status are recorded and reported throughout the life of the plant which (4) results in the accurate implementation of design output information into the physical configuration of the plant, and (5) into selected plant configuration documents specifying operations, maintenance, testing, installation, procurement, and training requirements.
B.2 Design Bases:
Information which identifies the specific functions to be performed by a structure, system, or component of a facility, and the specific values or ranges of values chosen for controlling parameters as reference bounds for design. The values may be (1) restraints derived from generally accepted "state of the art" practices for achieving functional goals, or (2) requirements derived from analysis (based on calculation and/or experiments) of the effects of a postulated accident for which a structure, system, or component must meet its functional goals.
(10CFR50.2 Definitions).
B.3 Design Bases Training Package: A set of documents which are developed for the purpose of training individuals in the Design Bases area, which include, but is not limited to the following:
- 1) Lesson Plans
- 2) Handout Materials
- 3) Examinations
- 4) Other Material used in Training B.4 Independent Review: A method of verifying process, procedure or task results by a party other than the one conducting the event. The reviewer may or may not be from an external organization.
B.5 Key Parameters Values: Those design bases parameters, and actual test values, which directly correlate to conforming capability of the system, component structure or topical issue to perform its design bases functions.
B.6 Margins: The difference between the actual operating point or failure point and the technical specification minimum operating, licensing, or the theoretical design point for a system, component or structure.
B.7 Non-safety Function:
Those system, structure, or topic issue functions that support the generation of electrical power and other functions not related to nuclear safety.
- 3 B.8 NRC Inspections/Surveys: As discussed in Section I. Introduction of this DBD Program Plan, related NRC acronyms used within the DBD industry are:
o SSFI-Safety System Functional Inspection, o SSOMI-Safety System Outage Maintenance Inspection, o EDSFI-Electrical Distribution System Functional Inspection, o DVI-Design Verification Inspection, and o DET-Diagnostic Engineering Team B.9 Open Items:
Those items that are discovered during the performance and evaluation of the design bases document that are discrepant and require correction.
B.10 Operable - Operability: A system, subsystem, train, component, or device shall be OPERABLE or have specified function(s), and when all necessary attendant instrumentation, controls, electrical power, cooling or seal water, lubrication or other auxiliary equipment that are required for the system, subsystem, train, component, or device to perform its function(s) are also capable or performing their related support functions(s).
(Reference Technical Specifications, e.g., Unit 1,Section I, 1.0 Definitions).
B.11 Safety Functions:
Those system, structure or topical issue functions that directly or indirectly support one or more of the following plant nuclear safety performance goals:
- 1) Maintain reactor coolant pressure boundary integrity.
- 2) Provide capability to shutdown the reactor and maintain the safe shutdown condition.
- 3) Prevent or mitigate the consequences of accidents which could potentially result in off-site exposures comparable to 10CFR Part 100 guidelines.
The term "safety related" applies to the prevention or mitigation of the consequences of postulated accidents that could cause undue risk to the health and safety of the public. Important-to-safety relates to "plant safety".
B.12 Validation:
Authentication of selected sets of information or determination that a process is being carried out in accordance with approved guidelines or procedures.
APPENDIX C GUIDELINE LISTING OF REFERENCE SOURCES I. Design Disclosure Documents: documentation that provides information and data needed to translate engineering concepts into structures, systems and components, e.g.:
o Drawings, Note:
An Analyses document o P&I Diagrams, that "define items...
o Calculations, and engineering concepts...",
o Specifications may also represent a Design Disclosure Document.
These data must be the "documents of record" and so authorized as Design Disclosure Documents.
II. Design Bases Reference Documents: documentation in addition to Design Disclosure Documents that were used in evaluating technical options, provided clarifying analysis, or provided additional definition during or subsequent to the development and establishment of the Design Bases of record, e.g.:
o Safety Analysis Reports (SARs):
including Preliminary (PSAR), Final (FSAR), Updated Final Safety Reports (UFSARs), and related documentation such as, NRC SAR Questions and Licensee Answers (SAR Q&AS), (SONGS, Unit-1 was Final Engineering Report and Safety Analysis FSA, now UFSAR),
o Fire Hazards Analysis (FHA), Environmental Impact Report (EIR),
Emergency Preparedness Plan (EPP), and the Physical Security Plan (PSP) and associated Q&As, o Safety Evaluation Reports (SERs): prepared by the NRC, including SEP related NRC correspondence and SEP related Licensee prepared analyses and responses.
o Systematic Evaluation Program (SEP): reports and correspondence (Note, SEP's are only applicable to early vintage nuclear facilities, such as SONGS Unit-1, as designated by the NRC),
o Operating Licenses/Technical Specifications:
including previous revisions related to the Design Bases evolution, o NRC Regulatory Guides and NRC Reports (NUREGs),
- C2 o Code of Federal Regulations, Title 10 (10 CFR):
such as Part 50, (10 CFR 50) Appendix A - Criteria - General Design Criteria, Criterion 1 through 64, o Codes and Standards:
such as American Society of Mechanical Engineering ASME Codes and other related codes and standards used in the development of the design bases and/or referenced within the Design Disclosure or Design Bases References Documents, o NSSS Supplier/Equipment Manufacture/A-E Design Manuals and related design bases of record and associated reference documentation, o NRC Commitment Correspondence/Documentation: related to the previously listed Design Disclosure and Design Bases Reference Documentation, are candidate sources for review and evaluation in the development of a DBD program.
III.
Other reference materials:
such as the System Descriptions, normal and emergency procedures and programs, etc., are design/process/program implementing documents that in some cases are integral to DBD development.
These documents are not deemed to be Design Disclosure nor Design Bases Reference Documentation. Extractions from these documents will be annotated within the DBD when they are referenced in DBDs to provide clarification or to demonstrate implementation, on a case by case basis.
IV.
Refer to NES&L 25-1-1 and 25-2-1 Quality Procedures for the detail list of Source Reference Documentation Categories used by the DBD Section to manage and record DBD reference documentation.
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