ML18031B251
| ML18031B251 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 07/07/1986 |
| From: | Crisler H, Stapleton J, Weinhold J TENNESSEE VALLEY AUTHORITY |
| To: | |
| Shared Package | |
| ML18031B250 | List: |
| References | |
| 2492A, PROC-860707, TAC-00018, TAC-18, TAC-62258, NUDOCS 8703250029 | |
| Download: ML18031B251 (25) | |
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I, July 2, 1986 Revision 0 DESIGN BASELINE AND.VERIFICATION PROGRAM BROGANS FERRY NUCLEAR PLANT P
Preparers Approved by:
Project Engine r wlilri Si e Director Manager Project Engineering X >p~J Jk~PP'anager Engineering Assurance Director Division of Nuclear Engineering
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~ ~ 0 a DESIGN BASELINE AND VERIFICATION PROGRAM TABLE OF CONTENTS Section ~Pa e 1 .0 Introduction ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ (~ ~ ~ ~ i~ ~ ~ ~ ~ ~ ~ o ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 1 2 .0 . Objective..............;............................
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Scope ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 3 3.1 Pre-Restart Phase 3.2 Post-Restart Phase 4.0 Descrxptxon of Program................................. 5 4.1 Interim Change Control......................;. 5 4.2 Design Criteria/Design Basis................. ~ 6 .
4.3 System Malkdown/Test.......................... 6 4 4 Evaluation of ECN and Other System Changes.... 6 4,5 System Evaluations and Corrective Actions..... 7 5.0 Program Implementation................................. 8 5.1 0 rganlzatlon ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ o'ooi ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 8 5.2 Schedule.................. o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ t ~ ~ ~ 8 6 .0 Program Documentation.................................. 9 6.1 Program Procedures............................ 9 6.2 Program Interfaces........................,... 9 6.3 F anal Report..........'..............".....;.... 9 Attachment A System List Attachment B Conceptual Plan for Design Baseline and Verification Program 2492A
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'r DESIGN BASELINE AND VERIFICATION PROGRAM 1;0 INTRODUCTION The Browns Ferry Design Baseline and Verification Programwill be used to provide the required level of confidence that the plant is ready for restart.
This program has been developed by the Division oi Nuclear Engineering to reconcile design control issues described in several evaluations and audits as follows:
o Comprehensive review of the existing program.
o Studies/evaluations performed by TVA and others.
o Interviews of key personnel within the TVA organization.
o Two reviews performed by Gilbert/Commonwealth (G/C) at Sequoyah.
o The corporate evaluation conducted by INPO.
Experience gained during the development 'of the Design Baseline and verification program' for .Sequoyah Nuclear Plant has been factored into the development of this program. Results from the implementation of the SON program will. be available in order to consider adjustments to the BFN program as results may dictate.
The implementation of this program has been structured into two distinct phases. The purpose of this structuring is to allow for an early as
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practical decision on restart and to facilitate the completion of activities necessary to meet the overall program objectives subsequent to any restart decision.
- 2. 0 OB JECTIVE The objectives of this program are:
To verify the adequacy of the plant modifications since operating license (OL) made to the systems, or portions thereof, required to mitigate design basis events and to provide for safe shutdown of the plant.
To provide confidence that these modifications are supported by engineering analysis and documentation.
o To provide confidence that these modifications are made in conformance with licensing commitments.
The essential elements of the overall program are as follows:
o Verification of actual plant configuration.
Reconciliation to engineering design documents including supporting calculations and design criteria.,
o Reconciliation to'the FSAR, licensing commxtments, and technical specifications.
+o Performance of Safety Evaluation Reports and Unreviewed Safety Question Determinations (USQDs) for the system configuration.
Issuance of revised key plant drawings which are essential for operations.
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These program objectives will be met in two phases. The pre-restart phase=of this program will be devoted to compiling data from tests and walkdowns ~ performing system safety evaluations. implementing and testing required restart modifications with corresponding changes to control room drawings, defining actions to resolve document discrepancies, and preparing a report documenting the results for DNE management approval.
The post-restart phase will include implementation of the remaining modifications to the systems not required for restart, completion and revision of the design criteria documentation including the criteria to support the post-restart modifications, completion of system safety evaluations not required for restart, implement corrective actions to other safety systems as required, formal revision of control room drawings (i.e. configuration control drawings), and issue post-restart design change supplements (DCSs}.
3.0 SCOPE 3.1 PRE-RESTART PHASE
-The detailed scope of the pre-restart phase is as follows:
o Unit 2, common systems, and portions of Unit 3 and Unit 1 systems required to support Unit 2 will receive first priority. The remaining Unit 3 systems will be considered immediately thereafter, and then the remaining Unit 1 systems will be considered.
o The systems or portions of systems covered by this program are listed in Attachment A. These systems were selected using the following rationale. To determine what system and portions of systems are required to mitigate FSAR Chapter 14 design basis accidents. The minimum set of systems or portions of systems that actually mitigate the event were identified by marked prints of the system flow diagrams and control diagrams. The results of th' pffort Mil't ho documented .in a'alculations package.
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o The drawings to be reviewed include the control room drawings depicting the systems listed in Attachment A.
o System walkdowns will be conducted to provide information to establish functional design acceptability of the systems and data, as required,.for input to engineering evaluations.
o The change documentation covered by this program includes ECNs, FCRs, TACFs, LDCRs, and NCRs/SCRs.
o The plant test information to be used. includes Pre-Operational Test results, Post-Modification Test results, Surveillance y ~
Instruction Program.
o The walkdown/test data will be compared to the licensing commitments and the design basis criteria for an engineering evaluati on.
o Complete the modifications required for restart.
o Revise control room drawings as required.
o Complete the evaluations of the selected safety systems.
o Issue USgDs for the selected safety systems and pre-start "
modifications.
o" Define-actions to resolve document discrepancies.
o Issue report on the results of the pre-start effort.
3.2 POST-RESTART The detailed scope of the post-restart phase is as follows-o Revise and issue drawings to obtain a single ! set of as-constructed configurations for control room drawings on the selected systems (configuration control drawings) prior to any post-restart modifications.
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0 o Change Control Board approval of non-restart modifications o Issue design change packages which were not required for pre-restart and complete the related modifications.
o Complete the evaluations of the remaining safety systems.
o Complete the design '
criteria/design basis.
o Complete other corrective actions resulting from the restart technical report.
o Issue final system USQD for each system affected by the post-restart modjfications.
4.0 DESCRIPTION
OF PROGRAM This program is broken down into five major program areas as follows:
o Interim Change Control' Design Criteria/Design Basis o System Malkdown/Test o Evaluation o ECN and Other System Changes o System Evaluations and Corrective Actions The details of when these activities are to be accomplished are shown in Attachment B.
The pre-restart phase will consist of engineering activities related to 3
I the five major program areas as necessary to achieve the level of confidence that the plant is ready to restart.
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I The post-restart phase will continue the engineering, activities to a point that complete engineering documentation and evaluations will be
'lg developed describing the final as-constructed configurations with supporting engineering technical justifications. The change control and management review procedures used during the pre-restart phase will also be in effect during the post-restart phase.
Acceptance criteria will be developed for specific technical issues.
Such criteria will be included in the individual procedures prepared for the implementation of this program. Upon issuance of these procedures, personnel will be trained in their areas of responsibility.
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An4 independent review vill be performed by Engineering Assurance on a surveillance basis of all engineering activities and documentation generated during the pre-restart phase.
4.1 INTERIM CHANGE CONTROL Interim Change Control Procedures are developed to control the change process during the design baseline and verification program and will remain in effect until long-term design control and configuration control program improvements are implemented. The interim procedures include implementation of the packaging concept for all modifications
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4 Change Control Board (CCB) is being, established to limit and I I
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control plant modifications. The CCB is to be staffed by senior personnel from Plant Management, Licensing, Division of Nuclear Engineering (DNE), and be chaired by the Site Director. The first priority of the CCB during the restart phase is to define, review, limit, and contxol all plant modifications required to be implemented prior'to restart of BFN and to stop all other changes to h
the selected systems.
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4.2 DESIGN CRITERIA/DESIGN BASIS Procedures are being developed to (1) define the licensing commitments review process and (2) control preparation of design criteria/design basis documents. These procedures will be used to perform the licensing .review process and prepare/compile design basis documentation.
4.3 SYSTEM VALKDOWN/TEST Procedures will be developed for system walkdowns to verify the configuration for pZ'ocess flow for mechanical and fluid systems.
For electrical and I8 C systems, test program results (Pre-operational tests, post-modification tests, surveillance instructions) vill be evaluated to establish proper function of modifications since OL. Each method used will be supported by documented logic to support the specific walkdown/test requirements. Dimensional or other data will be obtained, as required, for input to engineering dvaluations needed to technically justify the modifications..
4.4 EVALUATION OF ECN AND OTHER SYSTEM CHANGES
>1*, I An evaluation of the ECNs initiated since OL and other system A
-, > -.1 changes such as NCR/SCR, TACF, LDCR, FCR will be performed in
~ ~ l preparation for the system evaluations. Procedures are being developed for the control of these processes and data is being assembled.
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Modification ECNs will be categorized into three groups: (1) fully implemented, (2) partially implemented, and (3) unimplemented. The partially implemented and unimplemented ECNs will be evaluated to determine if their implementation is required for restart. If yes, the completion of the design and modification is to be in accordance with the new interim change control procedures.
The evaluation of other control programs such as NCR/SCR, TACF, LDCR, FCR is intended to assure that appropriate correction actions have been taken and that all related documentation is in order.
4.5 SYSTEM EVALUATIONS AND CORRECTIVE ACTIONS The system evaluations are the focal point of all previous portions of the program. The results of previous verification and data gathering activities of. this program will be use'd to show that the modifications since OL to selected systems or portions of systems covered by this program fulfills its'unctional design requirements.
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phase will determine if the system will operate safely. This evaluation will be based upon an engineering evaluation with appropriate documentation. Recommended restart modifications
, I' derived from this evaluation will be reviewed by senior managers l
f ti within DNE. Final decisions will be documented.
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Actions required to resolve any discrepancies identified in the system evaluation and/or technical review will be taken. This may require modification to the plant configuration with cor"esponding drawing changes, design basis document changes, and/or licensing commitment changes.':- .
'he following items will be issued prior to completion of this program element for each system or portion thereof:
o Required Actions Summary o Safety Evaluation Report 4
o Configuration Control Drawings (CCDs) required for operations o Unreviewed Safety Question Determination (USQD) o Document Discrepancy Resolutions (including input for I ~
Operating Instructions, Technical Specifications, and FSAR) o Design Criteria/Design Basis The specific efforts to be accomplished during pre- and post-restart phases are shown in Attachment B.
5.0 PROGRAM IMPLEMENTATION
.k I 5.1 ORGANIZATION I
Organizational changes as described within the revised Corporate lt Y
Nuclear Performance Plan Volume I consolidate within DNE the F
responsibilities for preparing and approving modification packages that change the design and configuration of the plant and acquiring or creating, and maintaining the technical record of the facility and maintaining the record current with changes in the plant.
Consistent with these responsibilities for maintaining a design control program, DNE has taken the lead in order that the configuration. design control, and design basis program improvements will be implemented. The Change Control Board described in section
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~ g Within DNE, the project organization onsite vill provide the lead for program implementation. The Project Engineer vill interface with the Site Director as necessary. System Engineers are being assigned so that one'ngineer vill be responsible for coordinating all system evaluation '
.activities on their appropriate system or portion thereof. Senior level engineers are being assigned for each system to provide technical assistance and guidance to the system engineers.
5.2 SCHEDULE S conceptual plan shoving these activities and their interrelationship is presented in Attachment B.
6.0 'PROGRAM DOCUMENTATION
- 6. 1 PROGRAM PROCEDURES Procedures reguieqd to assign specific responsibilities, define methods, and establish documentation requirements vill be developed. Program procedures will'e issued to cover, as a minimum, the following subject areas:
o Change Control Board o Identification of Licensing Commitments o System Walkdovns o Test Evaluation for Electrical Components o Design Criteria/Design Basis o Packaging and Control of Walkdown/Test Documentati'on o Drawing Comparison Review o Interim Change Control Procedure o Performance of System Evaluations o Review of ECNs and Other Changes o Engineering Assurance Oversight Review o Design Change Supplement
6.2 PROGRAM INTERFACES The requirements and responsibilities for interface between the project organization and other organizations such as'he Division of Nuclear Quality Assurance, Engineering Assurance, the Nuclear Safety Review Board (NSRB); and the Plant Operations Review Committee (PORC) shall be established and documented.
6.3 FINAL REPORT The results and conclusions of the pre-restart phase, including supporting information, will be .documented in a final report for submissions to the Director, Division of Nuclear Engineering. The report will consider trending of deficiencies found during the
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implementation of the program in order to consider other corrective actions needed based on generic implications and also effects on other safety systems for post-restart consideration. Based upon 4 review of the report, the Director, Division of Nuclear Engineering, will determine if the stated objective of the program has been met;
.,or if additional actions are required.
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Revision 0 6/26/86 ATTACHMENT A UNIT 2 BASELINE SCOPE A.l Unit 2 Restart Scope System
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'I Main Steam MSIV and SRV portion only Condensate (HPCI) Portion from CST to HPCI and RCIC Systems Reactor Feed Water Reactor water level pressure and drywell pressure measurement. Check valves and piping immediately adjacent to drywell Boiler Drains & Vents Blowdown Systems 10 Primary containment portion only Auxiliary Boiler 12- Secondary containment portion only Fuel Oil Entire system RHR Service Water 23 Entire system Raw Cooling Water 24 Secondary containment portion only Raw Service Water 25 Secondary containment portion only "HP Fire -'Protection Systera 26 Secondary containment portion only Condenser Circ.
Mater System 27 Vacuum Breaking system only Portable Water Distribution System 29 Secondary containment portion only Ventilating System 30 Portions associated with D/G Building Rooms, Primary Containment, RHR Cooleres,.and C S Coolers Ai'r Conditioning System 31 Portions associated with Shutdown Board Rooms, Main Control Rooms, Battery Board Rooms, Auxiliary Instrument Rooms, and Emergency Pressurization System Control Air System 32 Entire system Service Air System 33 Primary/Secondary containment portions only Vacuum Priming System .34 Secondary containment" portion 5, interactions '
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~Setem ID Gland Seal Water 37 Secondary containment portion only C02 Storage Fire Protection and Purging System. 39. Entire system Station Drainage 40 Secondary containment portions only e <<h Sampling 6, Water Quality System 43 Portions of systems required for containment isolation Building Heating System 44 Secondary containment portions only Feed Mater Control System 46 Interaction only Turbo Generator Control System 47 Turbine control valve fast closure portion Sodium Hypochloride Distribution System 50 Interaction only Demineralizer Backwash Air System Secondary containment portion only Stand By Liquid Control System 63 Entire system except for pump test loop
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B. Beating g Ventilation System 64 Entire'ystem Standby Gas Treatment Systemr Entire system Off Gas System 66 Interaction only h
Emergency Equip.
Cooling Mater System 67 Entire system Reactor Mater Recirc.
System 68 Piping for seismic and pump controls Reactor Rater Cleanup System 69 Area temperature monitoring equipment, isolation valves and water discharge system Reactor Bldg. Closed Cooli~ Mater System Entire system ee't Reactor Core Isolation
<<olin'ystem Entire system h qh h h
Revision 0 6/26/85 System
~Sstem ID High Pressure Coolant Injection System 73 .. Entire system Residual Heat Removal System 74 -, Entire system .
Core Spray Cooling System 75 Entire system Containment Inerting System 76 Entire system Radwaste System 77 ~ Liquid and gaseous subsystems. Solid radwaste will be reviewed for interaction
'2 Fuel Pool Cooling 6, Demineralizing Pool 78 Fuel cooling portions Fuel Handling and Stor. 79 Storage racks, refueling bridge interlocks, fuel pool structural integrity and functional integrity of refueling bridge Standby-Diesel Gen..
System Entire system Containment Atmospheric Dilution System Entire system Control Rod Drive System 85 Scram portion only Diesel Starting Air System 86 Entire system Radiation Monitoring System 90 Main Steam Line, Reactor Building Vent, Drywell and Control Room Isolation RMS Neutron Monitoring 92 Entire system Incore Probe 94 Entire system Reactor Protection 99 Entire system Electrical Systems All
'I Revision 0 6/26/86 A.2 Supporting References Title RIHS Number Common Mechanical Seismic Class .I B22 860206 101 Systems to Support Unit 2 Operation and Safe Shutdown Electrical Equipment Required B43 860206 912 To Support Unit 2 Restart Units 1 6 3, L Common I S C Systems B43 860203 920 To Support Unit 2 Operation Communications and Electronic Securi ty B43 860203 934 Requirements for Unit 2 2492K
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CONCEPTUAL PLAN DESIGN BASELINE 8 VERIFICATION
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PROGRAM BROWNS FERRY NUCLEAR PLANT UNIT 2 PRONAU FUff RCSFARF COUPLETE CORRECTIVE ClIGINCERIWtf ACFINfS TO fPORf OTHER SAFElY SYS ~ ~
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