ML20079B081
| ML20079B081 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 12/14/1994 |
| From: | Public Service Enterprise Group |
| To: | |
| Shared Package | |
| ML20079B079 | List: |
| References | |
| PROC-941214, NUDOCS 9501050099 | |
| Download: ML20079B081 (193) | |
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{{#Wiki_filter:- -- s CP&L DEC141994 ( Carolina Power & Ught Company Roy A. Anderson PO Box 10429 Vice President Southport NC 28461 '+ Brunswick Nuclear Plant 910 457-2496 SERIAL: BSEP 94-0513 United States Nuclear Regulatory Commission ATTENTION: Document Control Desk Washington, DC 20555 BRUNSWICK STEAM ELECTRIC PLANT, UNIT NOS.1 AND 2 DOCKET NOS. 50-325 & 50-324/ LICENSE NOS. DPR-71 & DPR-62 - UPDATE OF BRUNSWICK NUCLEAR PLANT THREE-YEAR BUSINESS PLAN Gentlemen: This letter provides to the NRC staff an update of Carolina Power & Light Company's (CP&L) " Brunswick Nuclear Plant Three-Year Business Plan." The plan was last updated by letter dated August 2,1994 (BSEP 94-0297). A (") This update reflects accomplishments through November 30,1994 and documents the current status of the BNP Three-Year Business Plan initiatives and projects. Enclosure 1 provides a summary of this BNP Three-Year Business Plan update. Enclosure 2 provides the BNP Three-Year Plan update. Please refer any questions regarding this letter to Mr. R. P. Lopriore at (910) 457-2212. Sincerely, A. Anderson KAH/ Enclosures cc: Mr. S. D. Ebneter Mr. P. D. Milano Mr. C. A. Patterson The Honorable H. Wells, Chairman - North Carolina Utilities Commission /^\ 9501050099 941214 PDR I I ADOCK 05000324 l PDR l 2
ENCLOSURE 1 O: BRUNSWICK STEAM ELECTRIC PLANT, UNITS 1 AND 2 NRC DOCKET NOS. 50-325 & 50-324 OPERATING LICENSE NOS. DPR-71 & DPR-62
SUMMARY
OF BNP THREE-YEAR BUSINESS PLAN UPDATE Introduction The Brunswick Nuclear Plant (BNP) Three-Year Business Plan consists of improvement initiatives and projects which support BNP's objective of continuously improving performance to achieve "world class" results. in December,1992, BNP established the Three-Year Plan to support achievement of "world class" performance. In December 1993, the BNP Three-Year Business Plan was developed to ensure alignment with the budget process, more accurately reflect the , strategic plan, and eliminate ambiguity of regulatory commitments, as well as facilitating management of emergent issues, outage schedule changes, and ongoing management involvement in plan implementation. , Controlled processes have been implemented to ensure that any changes to the BNP Three-Year Business Plan are carefully evaluated based on a balanced consideration of plant safety, reliability, and economics. Additions, deletions, and changes to the plan initiatives are approved by the Vice-President, Brunswick Nuclear Plant, in accordance with the guidance established under Initiative TY102, BNP Integrated Scheduling and [m') Three-Year Plan Administration. Management oversight of the projects reflected in the BNP Three-Year Business Plan is provided by the Plant Review Group (PRG). The PRG is chaired by the Plant General Managers and includes management from key site functions. The PRG reviews projects in accordance with the CP&L Nuclear Generation Group Guideline for Three-Phase Project Evaluation and Authorization. The Three-Phase Project approach includes study, design, and implementation phases. PRG review and concurrence must be obtained prior to implementation of each phase. This process ensures ongoing assessment of the relative safety significance of existing and emerging issues, project scope changes, priorities, schedules, and costs. . Plan Accomplishments A's previously noted, the BNP Three-Year Business Plan consists of improvement initiatives and projects that support the Brunswick Nuclear Plant's objective of continuous improvement. Both initiatives and project accomplishments are updated herein. Since the August 1994 update, six additional initiatives are task complete. t " assessments have been completed for the eleven initiatives reported as task ..umplete. Ten of the eleven self-assessments indicate that the initiatives have been effective in achieving the desired results, and the initiatives are ready for closure, o in addition to the initiatives discussed above, five projects have been completed since the El-1
August 1994 update. Completed projects include drywell loss of cooling accident lockout , . override, diesel generator oil level annunciator, and 480-volt vital motor control center '
- V rework.
. Plan Status .
This plan update documents the current status of the initiatives and projects which comprise the BNP Three-Year Business Plan. Changes to initiatives and projects resulting ; from BNP management review, along with the associated change justifications,' are documented in the plan. -
. Eleven of the forty initiatives identified in the original BNP Three-Year Plan are ongoing.
' Ten initiatives have been closed, six are task complete and awaiting self-assessments, and thirteen have been closed based on being superseded by other projects or work processes.
Five initiatives which were developed in 1994 are also ongoing. Several projects are being worked, including the Unit 1 supplemental fuel pool cooling . , project, instrument air compressor upgrade, fuel pool girder tendon inspections, and DC ground detection. In addition, considerable effort is ongoing to support projects scheduled for implementation during the Spring,1995 Unit 1 refueling outage. Conclusion i BNP Three-Year Business Plan implementation continues to be managed to ensure that improvement trends continue. Plan implementation continues to be result drive, focusing on improving methods and supporting plant priorities. Future focus remains on completing - assessments of the task complete initiatives, j The Brunswick Three-Year Business Plan continues to support accomplishment of the Brunswick Nuclear Plant mission of making electricity in a safe, reliable, economic, and ; environmentally sound manner. e i a i I E1-2 f m,..y. - p , ,, r- _ _ .cy -..
ENCLOSURE 2 (-~ ') 's BRUNSWICK STEAM ELECTRIC PLANT, UNITS 1 AND 2 NRC DOCKET NOS. 50-325 & 50-324 OPERATING LICENSE NOS. DPR-71 & DPR-62 BNP THREE-YEAR BUSINESS PLAN DECEMBER 14,1994 o O 8 V E2-1
l BRUNSWICK NUCLEAR PLANT TIIREE-YEAR BUSINESS PLAN PERFORMANCE IMPROVEMENT INITIATIVES & PROJECTS l I O : l Update VI O
BRUNSWICK NUCLEAR PLANT THREE YEAR BUSINESS PLAN. PERFORMANCE IMPROVEMENT INITIATIVES & PROJECTS TABLE OF CONTENTS I. PERFORMANCE IMPROVEMENT INITI ATIVES Initiatives Summary Initiatives Plans -
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- 11. PROJECTS O -
Projects Summary ; Category I Projects Category II Projects i 1
I I INDEX OF ACTIVE INITIATIVES ' _)) L INITIATIVE NO. TITLE SPONSOR TY101 Integrated Planning & Scheduling B. Helme TY102 BNP Integrated Scheduling and Three- R. Lopriore Year Plan Administration TY103 Corrective Maintenance Backlog G. Barnes Reduction TY104 Business Planning Improvements J.-Martin TY105 Inventory Control J. Ferguson TY201 Effective Performance B. Lindgren Management / Total Quality TY202 Training Improvements K. Ahern TY203 Utilization / Inter-Unit Support J. Titrington TY204 Establish "World Class Performance" D. McCloskey Culture TY205 Supervisory & Management Development B. Lindgren TY206 Develop and Implement Brunswick R. Johnson
,o Facility Improvements
' ) k/ TY301 Improved Procedure Control and C. Patterson Content TY302 Improving the Modification Process B. Grazio TY303 Improve Ability to Identify and R. Lopriore Correct Problems TY304 Backlog Reduction R. Lopriore TY305 Clearance Process Improvements J. Titrington TY308 Centralized Document Control Program C. Patterson TY309 Improve Management of Regulatory R. Lopriore Commitments TY401 Site Communication Plan M. Harris j t TYS01 Preventive / Predictive Maintenance C. Pardee Program Improvements TY502 Corrosion Preventive Maintenance C. Pardee TY505 Cooling Water Reliability Program C. Pardee TYS06 Plant Engineering Program Upgrade C. Pardee 1 TY507 Inservice Inspection and Inservice C. Pardee i Testing Improvement Program V ' 1
l l 1 I
/~'S INITIATIVE
( ) \~/ NO. TITLE SPONSOR , 1 TY510 Develop and Implement Preservation B. Deacy 1 Program to Upgrade Material l Condition 1 TYS11 ALARA Initiatives, Source Term J. Gawron i Reduction ' TY512 Environmental and Chemistry Program J. Gawron Improvements TY601 Human Performance J. Cowan TY602 Reactor Vessel Internals E. Willett Preservation TY603 Improve BNP's Competitive Position J. Martin D. McCloskey TY604 Reduce Regulatory Burden R. Lopriore TY605 Improve Refueling Outage Management J. Cowan INDEX OF DELETED INITIATIVES m ( I INITIATIVE \- NO. TITLE SPONSOR TY106 Outage Length Reduction U1/U2 Outage Managers TY207 Nuclear Revision Control System C. Patterson TY208 Integrated Computer Support D. Reid TY306 Health Physics Program Improvements J. Gawron TY307 Implement / Augment BNP Local Area D. Reid Network TY310 Assess Implementation of SAT Items J. Cowan TYS03 Design Basis Reconstitution Program B. Grazio TY50d Equipment Data Base System (EDBS) B. Grazio TY508 AC Source Improvement Project B. Grazio TY509 Management of Temporary and C. Pardee Substandard Conditions TYS13 Megawatt Improvement Projects C. Pardee TY514 Improve Plant HVAC Systems C. Pardee p-~s TYS15 Fire Protection Upgrade Project C. Pardee
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-StBecJtY OF INITIATIVE CHANGES U (Since August 2, '1994 Update) -
INITIATIVE NO. TITLE DESCRIPTION OF CHANGES TY103- Corrective Maintenance. Accelerated complete date Backlog Reduction for one task TY201 Effective Performance Initiative / Task Sponsor Management change TY205 Supervisory and Management Initiative / Task Sponsor Development change TY206 Develop and Implement Task Sponsor Change. Added Brunswick Facility seven (7) facility upgrades Improvements to the Master Facilities Plan. Deleted construction of the Single Point Access Facility from the plan TY305 Clearance Process Added four new tasks Improvements TY308 Centralized Document Extended complete date for Control Program one task and accelerated complete date for one task TYS07 Inservice Inspection and Extended start / complete Inservice Testing dates for one task Improvement Program TY604 Reduce Regulatory Burden Task Sponsor change TY605 Improve Refueling Outage Task Sponsor change Management O
i M INITIATIVES
SUMMARY
.) EXECUTIVE
SUMMARY
l INTRODUCTION ! Improved performance continues at Brunswick as the BNP Three-Year Business Plan i approaches the final year of its three year implementation schedule. Continued .;
. improvements are being realized in the areas of planning, scheduling' and commitment j achievement; work processes; communications; and system reliability and material condition. i o
PLAN ACCOMPLISHMENTS ; Successful performance indicators noted since the August 2,1994 update include completion i of the Brunswick facility improvements, continued upgrades in the material condition of the
- plant, a continued decline in backlog reductions for both units, the successful operation of both units, and the achievement of an all-time Brunswick generation record of 9,917,239 hours.
1 Six initiatives have been identified as task complete since the last update.- They include initiatives TY103, Corrective Maintenance Backlog Reduction; TY205, Supervisory and O Management Development; TY206, Develop and Implement Brunswick Facility Improvements; TY506, Plant Engineering Program Upgrade; TY510, Develop and Implement Preservation Program to Upgrade Material Condition; and TY512, Environmental and Chemistry Program Improvements. . The next phase of these task complete initiatives is to implement self-assessment effectiveness reviews. Self assessment effectiveness reviews have been performed on the eleven initiatives reported ; as task complete in the August 2,1994 update. The self-assessments for ten of the initiatives indicate the results have been effective and that the initiatives can be closed. Follow-up assessments will be performed on these initiatives by the Nuclear Assessment Department (NAD) in the spring of 1995. The self-assessment on initiative TY305, Clearance Process ; Improvements revealed that additional actions are required to obtain the desired results of this ! initiative. The initiative has been augmented to include the actions necessary to ensure its - effectiveness and the changes are reflected in this update. . t CURRENT STATUS
.i Eleven (11) of the forty (40) initiatives identified in the original BNP Three-Year Plan are l
- ongoing, ten (10) have been closed, six (6) are task complete and awaiting self-assessments, I and thirteen (13) have been closed and superseded by other projects or work processes that ;
p are achieving the desired improvements. The five Business Plan initiatives developed in 1994 l
- (,) are currently ongoing. ,
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(]. FUTURE FOCUS . \,1 BNP management is committed to an ongoing plan implementation that is results based, -! focuses on improving work processes and performance, and safely supports plant priorities. Managem:nt of the BNP Three-Year Business Plan to ensure trends of continuous improvement are maintained will continue. Aggressive self-assessment activities will continue to assess the effectiveness of the initiatives and to ensure successful performance is realized. Modifications to existing initiatives, or the development of new initiatives will occur as areas requiring improvement are identified. 4 J O I i I b V
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W INITIATIVES STATUS
SUMMARY
h.. -(40 Original Initiatives) I INITIATIVE TITLE STATUS- i TY101 Integrated Planning & Initiative is closed. .; Scheduling TY102 BNP Integrated Scheduling Initiative is closed. I and Three-Year Plan l Administration . l TY103 Corrective Maintenance Initiative is task complete. . Task l Backlog Reduction ' complete documentation is in ; progress. ! i TY104 Business Planning Initiative is closed.' l Improvements -
.i TY105 Inventory Control Two (2) tasks remain ongoing. ]
Initiative scheduled to task complete ! in 1995. ! i TY106 Outage Length Reduction Initiative closed per August,1993 O update to Three-Year Plan.' Works scope is being performed under. Strategic Issue, Outage Management. i Initiative TY605 has been established ! to cover this issue. l TY201 Effective Performance Initiative is closed. Mgmt/ Total Quality l TY202 Training Improvements Five (5) tasks remain ongoing. ! Initiative scheduled to task complete in 1995. , i TY203 Utilization / Inter-Unit Support . Initiative is closed. l TY204 Establish "World Class Initiative is closed. ! Performance" Culture I i TY205 Supervisory & Management Initiative is task complete. Task i Development- complete documentation is m , progress.
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TY206 Develop and Implement Initiative is task complete. Task i Brunswick Facility complete documentation is in .; Improvements progress.
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hv INITIATIVE . TITI E STATUS
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TY207 Nuclear Revision Control Initiative closed because scope is-System currently covered within the action plan developed by Nuclear Business ; Operations (NBO) in their response to NAD Assessment C-SP-93-03. ; TY208 Integrated Computer Support Initiative closed per August,1993 j update to Three-Year Plan. This ; scope of work is included in an NGG j 2 initiative to reorganize and establish ' ' computer and telecommunications organizational consistency among the ~! three nuclear sites. ! i TY301 ' Improved Procedure Control Initiative is closed. i and Content l TY302 Improving the Modification Two (2) tasks remain ongoing. ! Process Initiative scheduled to task complete l in 1995. i t TY303 Improve Ability to Identify Five (5) tasks remain ongoing. ! and Correct Problems Initiative scheduled to task complete i in 1995. l TY304 ' Backlog Reduction Initiative is closed. l
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TY305 Clearance Process Self-assessment has determined } Improvements further actions are required to obtain [ desired results. Additional tasks have ; been incorporated to ensure desired . i effectiveness. TY306 Health Physics Program Initiative closed per August,1993 Improvements update to Three-Year Plan. Initiative tasks identified under other initiatives, programs, or existing in-house l t processes. TY307 Implement / Augment BNP Initiative closed per August,1993 local Area Network update to Three-Year Plan. Work ; scope is being performed in coordination with the corporate plan , for installing company-wide LANs. ; TY308 Centralized Document Control One (1) task remains ongoing. Program Initiative scheduled to task complete ; in 1995. l
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INITIATIVE . TITLE STATUS-TY309 Improve Management of Initiative is closed. Regulatory Commitments
' TY310 Assess Implementation of SAT Initiative closed per August,1993 Items update to Three-Year Plan. Staff Assistance Team (SAT) improvements are incorporated in BNP self-assessment, strategic planning, and business planning processes.
TY401 Site Communication Plan Initiative is closed. TY501 Preventive / Predictive Eleven (11) tasks remain ongoing. Maintenance Program Initiative scheduled to complete in Improvements 1995. TY502 Corrosion Preventive Two (2) tasks remain ongoing. Maintenance Initiative scheduled to task complete in 1995. TY503 Design Basis Reconstitution Initiative closed per August,1993 Program update to Three-Year Plan. Work. scopes identified under projects O. B0018A, B0019A, BNT622, G0017A, and 05644A. TY504 Equipment Data Base System Initiative closed per August,1993 (EDBS) update to Three-Year Plan. Work scope is identified under project F0025C. TY505 Cooling Water Reliability Three (3) tasks remain ongoing. Program Initiative scheduled to task complete in 1995. TY506 Plant Engineering Program Initiative is task complete. Task Upgrade complete documentation is in progress. TY507 Inservice Inspection and Two (2) tasks remain ongoing. Inservice Testing Initiative scheduled to task complete Improvement Program in 1996. TY508 AC Source Improvement Initiative closed per August,1993 Project update to Three-Year Plan. Work scope is identified under project G0110A.
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( INITIATIVE TITLE STATUS TY509 Management of Temporary Initiative closed per August,1993 and Substandard Conditions update to Three-Year Plan. Work scope is being addressed through the implementation of a Temporary Modification Identification and Control Program, internal resources, and existing programs. TY510 Develop and Implement Initiative is task complete. Task Preservation Program to complete documentation is in Upgrade Material Condition progress. Y511 ALARA Initiatives, Source Seven (7) tasks remain ongoing. Term Reduction Initiative scheduled to task complete - in 1995. : TY512 Environmental and Chemistry Initiative is task complete. Task Program Improvements complete documentation is in i progress. TY513 Megawatt Improvement Initiative closed per August,1993
- Projects update to Three-Year Plan. Work scope is being performed through internal resources and processes.
TY514 Improve Plant HVAC Systems Initiative closed per August,1993 update to Three-Year Plan. Work scope is being performed through internal resources and processes. , TY515 Fire Protection Upgrade Initiative closed per August,1993 Project update to Three-Year Plan. Work scope is being performed through internal resources and processes. BUSINESS PLAN INITIATIVES . INITIATIVE NO. TITLE TY601 Human Performance : TY602 Reactor Vessel Internals Preservation l l TY603 Improve BNP's Competitive Position l TY604 Reduce Regulatory Burden TY605 Improve Refueling Outage Management
t i Brunswick Performance Improvement Initiative nue, oriusa, mmr, .{. p )' Corrective Maintenance Backlog 12/92 TY103 -! Reduction' ^ Strategy: ! i To develop and implement management processes for corrective j maintenenace backlog to both eliminate the current backlog and ! maintain manageable levels in the future.
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Impact / Benefits: O a) Elimination of the current corrective maintenance backlog -{' within three years. b) Establishment of the optimum staffing levels in the maintenance organization to effectively manage corrective maintenance. t c) Ensure timely repair of plant equipment to sustain good .t plant material condition. d) Enhance the corrective maintenance work process allowing ; effective utilization of manpower. l I i f t Sponsora Prhorityt George Barnes Medium- l f y n . . , =
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G V; g Corrective Maintenance Backlog Reduction - TY103 - im im im im Description Action Sponsor ITrNkNIJIJ kisDNp J FNkN!Jls kis DNp 1 F N k Nisis k s N p J FNkMislJ kis DNp TY103 - 04 A Evaluate and implement work process Bob Helme w improwments to enhance scheduling and work implementation. ; TY103 - 4B Evaluate and implement improvements to the George Barnes trEwswarran At-ms%2erM&A fornet, control, and technical content of maintenance -! procedures. l TY103 - 05 A improve the technical - non-technical format George Barnes ve/F##MMent+samreaweesurfaw of maintenance procedures s Page 2 TY103.MPP v .- -- . . . - . - e.. . . - ,w, .,-, , .. - . - + e - -,.m. .-~ . e. .- . - -w-.-s-m ...------w-a .
Brunswick Performance Improvement Initiative-m> , . w,u. - 1. Inventory control 12/92 TY105
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i Strategy: To effectively reduce and control the materrial inventory while supporting plant needs for replacement parts and other material.
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Impact / Benefits: - a) Ensure accuracy in the storage of material.
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b) Improved cycle inventory process accuracy in numbers of stored items. I c) Reduced amount of inventory dollars. d) Improved automation techniques for inventory control. I ( sponsors John Ferguson erwrur, Medium
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a Impact / Benefits: a) Elimination of the current corrective maintenance backlog within three years. b) Establishment of the optimum staffing levels in the i maintenance organization to effectively manage corrective t maintenance. i c) Ensure timely repair of plant equipment to sustain good ! plant material condition. t d) Enhance the corrective maintenance work process allowing effective utilization of manpower. . l 1 sponeere Priorityt George Barnes Medium
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Corrective Maintenance Backlog Reduction - TY103 1994 1995 1996 1s97 Description Action Sponsor JFMkMyDk$ ND JFMkMppkk N JFMkMypkkpND JFMkMypk$DNp TY103 - ole Develop and implement an improved trouble Bob Helme M4-w x1 l tag / minor maintenance process. i I l I i i TY103 - OIF Determine appropriate cycle 9 backlog Neal Gannon l9w we - 4 mi (WR-JO) reduction goal to be attained by June 1995. ! TY103 - 2A Reduce existing Unit 2 corrective maintenance George Barnes E backlog and achieve goal established by the Unit 2 Plant Manager. ! TY103 - 2B Reduce existing Unit i corrective maintenance Neal Gannon e4wu c essess n1 backlog and achieve goal established by the Unit 1 Plant Manager. l TY103 -3 A Evaluate performance and implement necessary George Barnes es actions for effective corrective backlog management. I l TY103 - 3B Provide necessary staffing to achieve Unit 2 George Barnes e em l outage corrective maintenance goals per the outage schedule. l l l TY103 - 3C Provide necessary staffing to achieve Unit 1 Neal Gannon t* W wae%su m outage corrective maintenance goals per the outage schedule. l
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Corrective Maintenance Backlog Reduction - TY103. 1994 1995 1996 1997 Description Action Sponsor J FNkHIJIJ klspND J FMkMlslJ kis DNp JykikHijlskkpkp i F kak MiJis k k p k b TY103 - 04A Evaluate and implement work process Bob Helme S improvements to enhance scheduling and work j implementation. ; i TY103 - 4B Evaluate and implement improvements to the George Barnes F#amewerce"mer.swegweme format, control, and technical content of maintenance ! procedures. l TY103 - 05A Improve the technical - non-technical format George Barnes mewzwst!*WAw#sM:reers#Xes1 of maintenance procedures. e Page 2. TY103.MPP
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TY105 j l Strategy: ; i To effectively reduce and control the ma*.errial inventory while supporting plant needs for replacement parts and other material. I t i ( l l i Impact / Benefits: i
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r a) Ensure accuracy in the storage of material. l f b) Improved cycle inventory process accuracy in numbers of j stored items. i i c) Reduced amount of inventory dollars. I d) Improved automation techniques for inventory control. { t l i i semm: rrserny, John Ferguson Medium t i I
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k b n ( Brunswick. Performance. Improvement Initiative ; 1 [' . Titter orietar sumbero l r $ Effective Performance Management 12/92 - TY201 .i V- i Strategy: 'l i Improve performance'in the areas of safety, production, and cost by l effective utilization of human resources. This initiative fully [ implements Effective Performance Management (EPM) at Brunswick. f
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b Impact / Benefits: L f a) Clear expectations in support of the mission are f established for each employee. I b) The expectations and employee performance are peiodically ! reviewed to ensure that the expectations support the { mission and that performance meets expectations. l t c) Employee development plans are developed and reviewed such that each employee may develop to maximum potential, { I i l l i sponsor, erserieyu Bowin Lindgren High
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Effective Performance Management - TY201 l 1994 1995 1996 1997 Descriptior. Action Sponsor JlF%fjA%1JlJlAlSl0lNlD J lF %flA%1lJ lJ lAlSl0lNlD JjF%1lA%IlJlJjAlSl0lNlD JlF%1lA%1lJlJjAlSlOjNlD 3 TY201 - 7B Development plans for section Bowin Lindgren 7JA] managers are complete. TYNI - 7C Development plans for unit managers Bowin Lindgren are complete. TY201 - 7D Development plans for supervisors are Bowin Lindgren M complete. TY201 - 7E Development plans for all employees Bowin Lindgren are complete. [ _ . Pg 1 _ TY201.MPP
c, , (v- v v Effective Performance Management - TY201 1994 1995 1996 1997 Dewription Action Sponsor J lF%1] Ahi} J lJ lAjSl0lNjD J[F%1]Al%IjJlJlAlSl0lNlD JlF%1lAlMlJlJlAlS]OlNjD J lF%1lAhtlJ lJ lAlSl0lNjD TY201 - 7F Incorporate Development Plan results Bowin Lindgren :gysszeysfygyfyzggA into assessment program. Page 2 TY201.MPP
f Brunswick Performance Improvement. Initiative nue, () p oT w a, seas.e, Training Improvements 12/92 IY202. Strategy: l l Implement _ training upgrades that will develop and sustain a highly ; qualified plant staff by the following: 1 t a) Identifying areas of training weakness.
- b) Improving the use of the Systematic Approach to Training.
c) Providing additional. training to key personnel. - Li d) Improved use of industry standards as bases for training ; programs. , 1 e) Specifically upgrading the following training programs: l 1 Engineering Support i Non-Licensed Operator ' Hands-On Craft Personnel
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Ir@act/ Benefits: '
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f a) Well trained and highly-qualified workforce. , I b). Improved individual employee development. , e c) Sustaining a high-level of technical qualification for supervisors and managers. i d) An efficient and effective training process. .{ e) Maintain accreditation of training programs. f) Assure 100% pass rates on NRC' License Exams, i g) Achieve significant improvement in line ownership, involvement, and oversight of training. l l h) Significant improvement in the SRO level systems knowledge by supervisors and managers. 5p0,10016 PTiOT4tyI
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Keith Ahern High
Training Improvements - TY202 1994 1995 1996 1997 Description Action Sponsor JlFhtl Aft lJlJlAlSl0lNlD JlF%1lA%1lJlJlAlSl0lNlD JlFhtlA%1lJlJlAlSl0lNlD J lF %tlA%1lJ lJ lAlSl0lNlD TY202 - 12A Upgrade non-licensed operator Mike Williams ysss,ygggypsga training programs fbr Aaxiliary and Radwaste Operators. This includesjob and task analysis and development of qualification cards and lesson material. TY202 - 13I Develop lesson plans and conduct Cecil Gurganus yp p p p ,y yg e g y,yg yj:yfygggggyzyzygyg y hands-on training for maintenance craft personnel. TY202 - 14U Develop, validate, and approve Mike Williams y/yg g ys y p p p p g yg Simulator Guides fbr use during simulator training. TY202 - 15A Develop and provide performance Paul Mazzola yggyp psygygyggy,y,gg based Emergency Response Organization initial and refresher training.
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U J. . . s Training Improvements - TY202 1994 1995 1996 1997 Description Action Sponsor J lFhtlAhtlJ l.8 lAl5lOjNlD J lF%1lAhtlJ lJ lAlSjOjNjD JlFhtlA%f]JlJlAlSl0lNlD JlF%1lA%1lJlJlAlS[OlNlD TY202 - 15Q Develop and provide an Advanced Mike Williams yp p p s s ,yp p y s g.;y p p p M M / s p fz Systems Training Course for managers. TY202 - 18A Improve the implementation of the Keith Ahem y p p //// M M / g y/A Systematic Approach to Training to meet INPO criteria and upgrade job / task analyses and task-to-training matrices for accredited programs. TY202 - 33A Conduct staffing and instructor . Keith Ahern gypsyssssag training assessments as described in the Corporate improvement Initiatives. , 4 TY202 -34F Develop a prioritized list and procure Cecil Gurganus - y s g y/ s p p pz yz yz yggysgyspapaz hands-on training mock-ups and models. i
' Page 2 TY202 MPP ~ ~. _ _ . . . _ , _ _ _ _ . _ . _ . . . - - . . - . - . - _ - - - _ - - . _ _ _ . _ _ . _._..,-...,_-.:...._...__. . , . . . . . . . - . . . . . . . - . . _ - . . _ _ _ . . . . . . . . . _ . _ . .
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- [ ,2 .:s y-l Brunswick Performance Improvement Initiative -
l Titlet Origlas Numbers O Establish "World Class Performance" Culture
'12/92 TY204
.i Strategy: '
t l Establish a culture in which World-Class performance is the_ highest ! priority and where continuous improvement is way-of-life. , t
'i i
Impact / Benefits: , i I a) organizational structure and staffing aligned to support j the vision of World-Class performance, f b) Consistent and continuous communication of the new culture and business direction providing the focus for all business activities, i c) Development and execution of a plan for effective use of , human resources. l l 'I Sponsora Priority 2* 3 Dennis McCloskey High t I w
s - - Establish "World Class Performance" Culture - TY204 1994 1995 1996 I997 Description Action Sponsor J 1FptlAhtlJlJ l Als jolNjD J jr ht[AhtlJ j J lAlsjolNjD J lF ptl AhtlJ lJ lAlSl0lNlD J jFlhijAftj l j J l AlSl0lN[D TY204 - 3 A N1anagement and employees will be Galen Jones 3 provided the results of the employee survey. TY204 - 4A The results of the employee survey Dennis hicCloskey 974 y3 w ill be analyzed and new initiatives will be deseloped based on the analysis. 1Y204 - 1I A Develop a iluman Dennis hicCloskey ygy,y,y,yj Resource' Organizational Development Plan. TY204 - 12A hianagers training will be conducted Pat Jordan yzyz5yzeze2 for the iluman Resource /Organir.ational Development Plan. Pg 1 _ TY204.MPP
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t Brunswick Performance Improvement Initiative T4thes Oripla t Numberr ., Supervisory and Management Development- 12/92
) TY205 Strategy:
This initiative will implement the following Corporate Improvement
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Initiatives: I i Supervisory Assessment Center Supervisory Development Program Management Development and Succession Planning [ i f Impact / Benefits: I a) Provide a consistent assessment process to assist in the selection of motivated, high-performing individuals for i supervision. b) Provide supervisory training to incumbent supervisors, c) Enable the site organization to fill planned and unplanned vacancies with well-prepared supervisors and managers. l CponEOft PriO!3tyt Bowin Lindgren High f
. -i Supervisory And Management Development - TY205 1994 1995 1996 1997 Ikscription Action Sponsor J lF %1lAhtl3 lJ lAlSl0lNlD JlFftlA%1lJlJlAlSjOlNjD J [F %1lAhtlJ lJ lAlSl0lNlD J lF%llA%1lJ lJ lAlSl0lNlD TY205 - 10C liigh-Potential non-managers will be Bowin Lindgren yg yz yg g identified for selected positions.
TY205 - 10D Development plans will be drafted Section Managers yg gyz yz yggy m and discussed with high-potential non-managers and supervisors. _ PT1 , TY205.MPP
Brunswick Performance Improvement Initiative rs n e, orsusae n=e.1, {"' } Develop and Implement Brunswick Facility Improvemente 12/92 TY206 Strategy: Improve the overall condition of Brunswick facilities by: a) Designing and constructing the following new facilities: Operations / Maintenance Building Permanent Warehouse Facility Technical Training Facility Snubber Repair and Hot Calibration Shop Technical and Administrative Center (TAC Building) Tool Decontamination Room Sewage Treatment Plant Clean Trash Monitoring Building b) Upgrading the following facilities: Main Storeroom HVAC and Power Supply for Hot Shop CRD Room Upgrade Control Room Upgrade Service Building Upgrade TSC/ EOF Building Upgrade Paint and Sandblasting Facility Warehouse "C" Renovation (} ( ,/ Site Paving - Asphalt Paving of Stoned Areas Clean Maintenance Building Upgrade Employee Recognition Room Human Resource Area TAC Building Upgrades Fire House In-Process Center Paving / Landscaping Outside Protected Area c) Disposing of trailers and temporary buildings. d) Constructing a Radiation Controlled Area (RCA) with a single-point Access. e) Develop and execute a Master Facilities Plan. Impact / Benefits: a) Centralize plant organizations and equipment to improve communications, operational effectiveness, and worker efficiency. b) Improve radioactive material control and streamline plant access. c) Improve the quality of life of workers. d) Create a professional industrial site appearance. e) Upgrade training capabilities. f) Increase sewage treatment capacity. g) Provide adequate material storage space. h) Provide office space in permanent facilities for all CP&L employees. ( 9lw%do, t 97 i OT , t y l Roy Johnson High
Develop And Implement Brunswick Facility Improvements - TY206 1994 1995 1996 1991 Description Action Sponsor J lF %tlA%1lJ lJ lAlSl0lNlD J lF %1lA%1lJ lJ l AlSl0lNlD J lFlh1]A%flJ lJ lAlS[OlNlD J lF%1l4%1lJ j J lAlSl0lNlD TY206 - 2 A Remove Trailers and Temporary Dennis McCloskey ygy,gypygyzyppygg Buildings TY206 - 11 A Implement the Master Site Facilities Roy Johnson y s g sy s s z w,yz yg e; Plan TY206 - 4i A Renovate Tool Decontamination Dennis McCloskey yg gfyg yj gy/g gfg yg yj Room, Material Storage Facility, and Administrative Annex.
, Page1 , _ ~ TY206.hsPP :
Brunswick Performance Improvement Initiative-TitJes Origint Numbers 5
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Improved Procedure Control and Content 12/92 TY301 Strategy: , Develop and implement a comprehensive procedure control process to ; more efficiently manage Plant Operating Manual procedures by establishing a hierarchy and an efficient change process to_ improve ' plant procedures. T Impact / Benefits: I a) A uniform process for the development, change, and overall control of Plant Operating Manual procedures. b) An efficient process for executing expedient changes to incorrect or inadequate procedures, thereby stimulating identification of problems and encouraging procedural' adherence. i
,p Cponscre PThortCYt \ Carol Lewis Medium I
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t A n 5 9 l J t e 9 1 l l J 1 n % o l A C j l Nt F d J n j D N A l l l 0 S o r 4 l l A J 1 9 t n 9 1 l l J A y PM - o l 1 A zy C l A 1 g e F y r l J g y u d e r o n c s o o n sr r o p t e t P S a n P d o o! it r e A C c a v o r p I m w e n e ht f o n i o t t a n e m s. e s lp e c imorp ll l u o F r t n A o n 0 c i o 1 e r t - ip u r 1 d c 0 e s 3 c e Y or D T p l
l Brunswick-Performance' Improvement-Initiative l fJtJWJ' Origlas Wusibers . l
\,% Improving the Modification Process -12/92 TY302 j Strategy:
Improve the plant modification process to reduce the overall investment of both human and financial resources and to provide timely response for needed modifications. I i I i Impact / Benefits: 1 a) Improved efficiency in resource utilization for design activities to ultimately result in a 25% design cost reduction, b) Reduced design time.for small modifications and setpoint changes to less than 6 weeks and less than 3 weeks, respectively. J i
****' enois ty, Bob Grazio High l
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Improving The Modification Process - TY302 1994 1995 1996 1997 Description Action Sponsor J (F bt h htl1lJ lAlS h $ lD J IF htlA b!lJ lJ lAlS hlN lD J lF htlA bilJ lJ lAIS lN!D J lF htlA bilJ lJ lA lS lN lD TY302 - 6E Complete orientation training for Paul Cafarella $ incumbent engineers invohrd in the design process. i i TY302 - 6F Complete position specific training for Paul Cafarella I incumbent engineers invohrd in the design process. j i P-1 - TY302.MPP
r b Brunswick Performance' Improvement Initiative ~ re ue, ors,2a, number, i Qj Improve Ability to identify and Correct 12/92 TY303 ; Problems i Strategy: Develop and implement a self-assessment program that results in
- critical evaluation of plant processes and products. Develop and ;
implement a root cause analysis process strengthened by improved' training, line organization involvement, increased management oversight, and feedback from the Operations Experience Feedback Program. Improve the Corrective Action Program through the following actions: a) Improve training b) Establish effective sub-programs c) Implement effective trending and tracking. d) Place more focus on less consequential (precursor) events tracking l and trending e) Improve process for exchanging ACR information across functional lines km Impact / Benefits: l a) An established culture of continuous improvement. b) Clear and consistent management direction enforcing the expectation for effective self-assessment and the 1 accountability for effective corrective action. , c) Early identification of problems, by responding to precursor events and findings identified through self- l assessment. d) Management attention focussed on areas needing improvement, e) Accurate identification of the root causes of problem areas. l f) Decreased number of plant events and violations. g) Effective application of lessons learned at other plants, worldwide. Sponsor Priorityr
\ Rich Lopriore High
Improve Ability To Identify And Correct Problems - TY303 1994 1995 1996 1997 Description Action Sponsor JlFptlAhtlJlJlAlsl0lNlD JlF%ilA%ilJlJlAlSl0lN[D J {F %1lA%1lJ lJ lA[S jolNlD J lF %IlA%tl J lJ lAlS[OlNlD 1Y303 - Ill Perform a self-assessment on the Bruce Altman 7pg/jj effectiveness of the self-assessment program. TY303 - 1J Perform a self-assessment based on the Bruce Altman g results of the 1993 SALP Report. I i TY303 - 2L Revise PLP-04 to require key CAP Bruce Altman g corrective actions followup elTectiveness reviews; reinforce cross functional area ACR owner responsibilities; improve ACR investigation response times; document Level Ill ACR causes. l TY303 - 31 Perform annual self-assessments of Bruce Altman 7,zwnyngswgwggggggggggggg7gggggyzgz9m///ggg CAP program to confirm progress and adjust goals. l l _ Psap 1 - TY303.MPP
O O Improve Ability To Identify And Correct Problems - TY303 1994 1995 1996 1997 Description Action Sponsor Jjr%lA%tjslJlAISl0lNlD J lF%tlA% lJ lJ lAlSl0lNjt) J lF %1lA%IlJ lJ lAlSlOjNjD JlF%IlA%tlJlJlAlSl0lNlD TY303 - 3K Improve the efficiency of the CAP Bruce Altman geygggyfy///xgj computer program by adding improvement area tracking feature, creating ability to produce 5 standard trend reports; and improving system response time by 25%. TY303 - 3L Improve the effectiveness of CAP Bruce Altman. subprograms by implementing a Desktop Guide to provide guidance to reinforce management expectations that trend analysis and reportmg is performed as required and is consistently applied. TY303 -4A Combine all site observations, Bruce Altman w//fyAp///fy/7///gw/AN ////z inspections, surveillances, self-assessments, etc. into ~ a relational database that will form an effective diagnostic tool for improving plant human performance. t-i TY303 - 4B Implement electronic data entry and Bruce Altman g p yg g efz w fy//z eyA w x< ! processing of Adverse Condition Reports (ACRs) i L 1 b Page 2 TY303.MPP 9
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Improve Ability To Identify And Correct Problems - TY303 1994 1995 1996 1997 Description Action Sponsor J lF%tlA%1} J lJ lA]S JOlNjD J lF%1lA%1lJ lJ lAlSl0lNlD JlF%1lA%1lJlJlAlSjOlNlD J lF htlA%1lJ j J lAlSl0lNjD TY303 - 4C Develop mechanisms to facilPate the Bruce Altman gyfy,2;97tR53J exchange of ACR information across functional lines and prompt action on issues that cross functional boundaries. f 1 Page 3 . gypp ff
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m , Brunswick Performance: Improvement Initiative ~. 74 es., - orsvin, n e.r,
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- p' Clearance Process Improvements 12/92 TY305 Stra'tegy; r Evaluate the current clearance process against the best practices at ~f world-class plants. Develop and implement-improvements to maintain f protection for both personnel and equipment'and to streamline che t
clearance process. , .
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i i L Impact / Benefits: :;. i a) Improved margins of personnel and equipment safety through the use of ; a well understood and practiced clearance process. I b) Increased efficiency of the work management process through the use of an effective and streamlined clearance process. c) Clear definition of the authority for equipment manipulation. d) Improved utilization of manpower through the planning and use of ! master clearances. i i < O - John Titrington High
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Clearance Process Improvements - TY305 1994 1995 1996 1997 Description Action Sponsor 3yphyppu$ pnp Jypkppuk$ pnp jyphyppupppp 3yphyppupppp TY305 - I A Implement necessary procedure changes John Titrington D , resulting from the team evaluation of clearance process -! improvements. j ! TY305 - 2A Complete necessary training on the improwd John Titrington O l clearance process and implementing procedures. t i TY305 - 08A Conduct assessment of clearance process and John Titrington 1. _ i ewnts TY305 - 08B Revise procedure to incorporate lessons John Titrington E learned.8 ( TY305 - 08C Conduct training on clearance preparation, John Titrington y l research requirements, and process revision. l l TY305 - OSD Perform follow-up self-assessment on John Titrington Irr=d clearance process. l l t 1
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TY305.MPP l
I Brunswick Performance Improvement Initiative ~ titJet Origin s . Numbers Centralized Document Control Program' 12/92 TY308
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Strategy:. . Evaluate the current document control process against the needs of the plant. Develop an improved program, train personnel,1and implement the improved program. 1 l i Impact / Benefits: a) High confidence that superceded revisions to documents are not used to operate or maintain the plant. b) Improved efficiency in the work management process, c) Complete and strict management of controlled documents by a central organization. d) Effective management of document libraries with clear and understandable rules for their use, e) Continued improvement through the use of an internal audit program. O smoor, resorny, Carol Lewis Medium
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Centralized Document Control Program - TY308 1994 1995 1996 1997 Description Action Sponsor J lF %tl Aft lJ lJ lAlSl0lNlD J lF htlAhtlJ lJ lAlSl0lNlD JjF%tlA%1l1lJlAlS[OlNlD J lF%1lA}NtlJ lJ l4lSl0lNjD TY308 - 111 Evaluate drawing control, procedure Carol Patterson 97MMysgyymzg;pysfygea control, sendor manual control, and mod package control areas of the document control program. I 308 - 6A Adequately train site personnel in the Carol Patterson ysfysfya use of the document control program (RMP-003). TY308 - 7A l'ully implement the improved Carol Patterson ysfymeya document control procedures (RMP-003). l TY308 - 9A Tra n site personnel and implement Carol Patterson ymgyp;yssga; sitewide administrative procedure for document control, OA P-008. l l l l l _ Pge1 _ TY308 MPP
Brunswick Performance Improvement Initiative TJ tle t O *0719sas ! Numbers Preventive and Predictive Maintenance 12/92 Program Improvements TYS01 Strategy: Evaluate our programs against best practices at world-class plants . Reconstruct the bases for Preventive Maintenance tasks and frequencies and ensure that the work we perform effectively supports the mission. Develop and implement a Predictive Maintenance Program to proactively evaluate equipment conditions through the use of infrared thermography, and vibration analysis. Impact / Benefits: a) An optimized Preventive Maintenance Program which performs the right work at the correct time to improve equipment performance and reliability. b) Reduced overall maintenance costs by eliminating redundant tasks or those tasks which add no value. c) l Reduced challenges to operation by providing more reliable plant equipment. d) Provide consistent and trended data for use in Preventive and Predictive Aaintenance Programs. Sponsor: Practity: Chip Pardee
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High _ _ _ _ _ . - _ . _ . _ _ _ _ _ . _ _ _ _ _ - - - - - - - - - - - - - ~
Preventive / Predictive Maintenance Program Improvements - TY501 1997 1995 I 1996 1994 J lr bilA bij J lJ IAis !OlN lD J IF bl(A ht1J lJ lAls 10IN [D 1 [F b1lA htlJ lJ lAls 10 NID Action Spcnsor i fr btIA btlJ lJ lAls l0 N [D Description TY501 - 2B Complete a self-assessment of the Mark Varno 0 i I Preventive Maintenance optimization process. Mark Varno $ TY501 - 4C Complete optimization of 8 total prioritized systems. Mark Varno $ TY501 - 4D Complete optimization of 14 total prioritized systems. Mark Varno TY501 - 4E Complete optimization of 20 total , prioritized systems. i t Pama 1 6
O O O Preventive / Predictive Maintenance Program Improvements - TY501' 1994 1995 1996 1997 Description Action Sponsor J lF htlA bllJ lJ {AlS l0 lN lD J lF bllA htlJ lJ lAlS lO N lD J lF btlA htlJ lJ lAlS hlN lD J lF bth htlJ lJ lAls l0 NlD TY501 - IF Complete optimization of 26 total Mark Varno $ prioritized systems. TY501 - 5 A Incorporate optimized PM tasks into Mark Varno b We - or nent<Ms spw em eul existing PM program (e.g. procedures). TYS01 - 5B Incorporate optimized PM tasks into Mark Varno $ existing program - 2 pilot systems. , i TY501 - SC Incorporate optimized PM tasks into - Mark Varno $ l existing program for 6 more systems (8 to date). ! l Page 2 TY501.MPP _ _ . _ . _ . . _ _ . . _ . . _ . . _ . ~ . _ - , _ . . _ , . . . . . _ . _ _ _ . . . _ _ _ . - .
y Preventive / Predictive Maintenance Program Improvements - TY501 1994 1995 1996 1997 Description Action Sponsor J IF htlA htl1 lJ lA lS lO N lD J lF htlA ht lJ lJ lAlS $)lN jD J lF $1lA htlJ lJ lA lS l0lN ID J lF htlA b1lJ lJ jA lS lO]N [D TY501 - SD incorporate Optimized Phi tasks into h1 ark Varno $ existing program for 6 more systems (14 to date). i TY501 - SE incorporate optimized PA1 tasks into h1 ark Varno $ existing program for 6 more systems (20 to date). TY501 -6A Develop Predictive Alaintenance h1 ark Varno en - m egi ; Program l [ F ! TY501 -6F 1mplement Predictive hiaintenance h1 ark Varno - 91 Program self-assessm:nt action plan. l
- TV501.MPP
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O C O Preventive / Predictive Maintenance Program Improvements - TY501 1994 1995 1996 1997
- Description Action Sponsor J lF btlA bflJ lJ jAIS lO b lD J lF btlA bt}J j J lAlS l0lNlD J }F btlA btlJ IJ lA lS l0 lN jD J lF btlA btlJ lJ lAlS lOlNlD TY501 - 6G Integrate Preventive and Predictive Mark Varno in % ~ @< - ~ < ~ - <M Maintenance Programs to create Predictive-Driven Preventive Maintenance tasks.
TY501 - 7A Maintenance PM procedure resisions Mark Varno j*@oamew Me@&ee-me de*;t e zmwM and planning. TY501 - 8A identify and implement initiatives to Mark Varno ty?egy rie<cuww2emea:sw d achieve near-term PM reductions. l 1 TY501 - 8B Develop standard PM activities that Mark Vane Q allow for more consistent and accelerated reliability centered maintenance (RCM) studies as described in this initiative. l t~ r. l l' . I Page 4 TY501.MPP
Preventive / Predictive Maintenance Program Improvements - TY501 1994 1995 1996 1997 Descrip; ion Action Sponsor J IF htlA htlJ lJ lAls 10 NlD J lF htlA htlJ lJ lAIS DlN jD J lF htlA htlJ lJ lA lS lOlN lD J lF htlAhtlJ {J lAls )ON!D TY501 - 8C Initiate resiews of PMs as scheduled Mark Varno 15 - n1 for scope and periodicities that are appropriate. Integrate into the proposed Reliability Centered Maintenance (RCM). I i l 5 i I TY501 - 8D Consolidate the vibration data Mark Varno Imer " c1 collection and analysis to facilitate overall program ! to simplify trending and eliminate redundancy. TY501 - 8E Benchmark Predictive Maintenance Mark Varno M #wM - :vi Programs and incorporate lessons learned from I I industry leaders. TY501 - 8F Resise the procedures governing site Mark Varno Is +- :vem "] preventive maintenance practices to reduce the i resources required to conect PM deficiencies. l 3 i 1 - t I i g Pg5 - TYSO1.MPP W W _
Brunswick Performance Improvement Initiative i
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( rJt2 , 'origine number, Corrosion Preventive Maintenance 12/92 TY502 Strategy: Evaluate the best practices at world-class plants. Develop and implement a program which will prevent declining material condition resulting from corrosion. , Impact / Benefits: { Plant equipment material condition will be preserved by replacing or properly preserving components with proper coatings.
- Kponsor Priori tyi Chip Pardee High
rm+ Corrosion Preventive Maintenance - TY502 1994 1995 1996 1997 Description Action Sponsor J lF htlA%1lJ lJ l Al5lOlNlD J lF %1lA%1lJ lJ lAlSl0lNlD JlF%1lAhtlJlJlAl5l0lNjD JlF%1lA%1]JlJlAlSl0lNlD TY502 - 1 A Develop and implement a Corrosion Ken Fennell rMEM4MMMM4MGM Preventive Maintenance Program to maintain plant material condition from the effects of corrosion. TY502 - 6B Provide engineering support for IIal Pitts rggega cleanir.g and inspection of storm drains: prepare study based on results. 4
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i 1 1 Brunswick Performance Improvement Initiative (3 n u., w as., - ,, Cooling Water Reliability Program 12/92 TYS05 i Strategy: , Evaluate the best practices at world-class plants. Develop and f implement a program which will preserve cooling water systems from , the effects of erosion and corrosion. Systems tio be included are: I the Circulating Water System, the Reactor Building Closed Cooling Water-System, the Turbine Building Closed Cooling Water System, and the Service Water System. t i i i O : i Impact / Benefits: '
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a) Reduced potential for through-wall leaks resulting from erosion or corrosion. ' b) Improved cooling water system material condition, i c) Long-term reliability and lesser maintenance costs.
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1 l spoesort Prior 2tyt
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Chip Pardee High ;
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l Cooling Water Reliability Program - TY505 1994 1995 1996 1997 Description Action Sponsor J lF%1lA%1lJ lJ l4lSlO'NlD JjF%1lA%IlJlJlAlS[OlNlD J jF %1lA%IlJ lJ l AlSl0lNlD J lF%1lA%1lJ j J lAlSl0lNlD TY505 - 2B Develop a written procedure to define Ken Fennell g the program at BNP. l l TY505 - 3A Determine the scope of piping to be Ken Fennell gwgwawa included in the program for Ul cooling water systems. l l TY505 - 3B Implement corrective actions as Don Eng determined by the inspections of Unit I cooling l water systems. l TY505 - 3C Complete design of corrective actions Bob Grazio and provide engineering support during - implementation of corrective actions from Unit I cooling water system inspections. Py 1 TYS0$ M-P l , _
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O 1 O O Cooling Water Reliability Program - TY505 1994 1995 1996 1997 Description Action Sponsor 1lF%1lA%1lJlJlAjSl0lNlD J lF%1]A%1lJ lJ lAlSlOlNlD JlF%1lA%1lJlljAlSlOjNlD J lF%1lA%1lJ lJ lAlSl0lN[D TY505 - 3E Perform ultrasonic testing (baseline) of John Langdon identified piping for Unit I cooling water systems. TY505 - 4C Complete design of corrective actions Bob Grazio
- and provide engineering support during implementation of corrective actions from Unit 2 l cooling water system inspections.
l TY505 - 4E Perform ultrasonic testing (baseline) of John Langdon g identified piping for Unit 2 cooling water systems. 4 i Page 2 TYS05 MPP I
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-l Brunswick Performance Improvement Initiative
. n u., w,u, - ,,
. Plant Engineering Program Upgrade 12/92 TYS06 Strategy:
Evaluate best practices at world-class plants and develop and implement a program to upgrade Plant Engineering based on these best practices and the intent of INPO. Good Practice TS-413, Use of System Engineers. .]
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a Impact / Benefits: vb a) Improved performance and reliability of systems and equipment. b) . Improved Plant Engineering performance in the areas'of material condition, outage management, and management of engineering backlogs. c) Increased job satisfaction through increased responsibility, _ accountability, and technical knowledge. d) Improved technical knowledge / experience of systems engineers, thereby ! broadening the capabilities and flexibility of engineering personnel. i spa m sa ritorny-Chip Pardee High i
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Plant Engineering Program Upgrade - TY506 1994 1995 19 % 1997 Description Action Sponsor JjF%tlA%lJjjjAlsl0lNjD J lFlMlA%1lJ lJ l AlSl0lNlD J lF %1lA htlJ lJ lAlSl0lNjD JlF%1l4%tlJlJlAlSl0lNlD TY506 - 9A Sustain specific interim contractor Chip Pardee yg e,y g g ge s g g g g g egg assignments in needed engineering program areas w hile minimizing the need for continuing contractor support. TY506 - 17A Incorporate lessons learned from the Chip Pardee r4/4/4V4V/74V/744V4 Technical Support improvement Program into Nuclear Engineering Department. TY506 - 18A Perform a self-assessment of the Chip Pardee effectiveness ofimprovements in Plant Engineering (Technical Support and NED).
. Py 1 _ TYSOS.MPP
Brunswick Performance Improvement' Initiative nues oristas mee.r . ! Inservice Inspection and Inservice 12/92 TYS07 Testing Improvement Program Strategy: Evaluate best practices at world-class plants and develop and implement a ; program to upgrade the Inservice Inspection (ISI) and Inservice Testing ; (IST) Programs. Evaluate needs and implement necessary improvements in training, test equipment, and system configuration to support this upgrade. I Impact / Benefits: a) High-confidence of compliance with ASME Section XI and 10CFR50 requirements. b) Improved efficiency of ISI/IST activities thereby eliminating un-necessary resources, radiation exposure, and costs. q spon.or, eriority, h _ Chip Pardee High
Inservice Inspection and Inservice Testing Improvement Program - TY507 1994 1995 1996 1997 Description Action Sponsor JlFfthfqJlJhlsphlD JlFf thf1lJlJ hlSlOhjD JlFfthhtlJjJlAlSjohlD JlFftl Aft lJlJhlsjohjD TY507 - 1D Perform a self-assessment of ISI/IST Jerry Crider y improvements and des clop a plan for corrective actions. TY507 - IC Perform a self-assessment of ISI/IST JerryTrider g improvements and develop a plan for corrective actions. TY507 - 3 A Review / revise ISI/IST program implementing Jerry Crider g test procedures. l l TY507 - 12 A Update the ISI/IST programs for the third Jerry Cnider yp;ygggfygggg41 interval using the latest edition of the code. l l l l l 1 Py 1 , TYSOTMPP
i Brunswick Performance Improvement Initiative
. Titlet .'Origine Numberr
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Develop and' Implement Preservation . 12/92 TYS10 , A . Program to Upgrade Material Condition Strategy: f i Develop and implement a program to' upgrade the material condition of the I plant by coating floors, walls, ceilings, and equipment. A system and unit separation color-coding scheme should be included. Note: Protective coating of inaccessible or near inaccessible areas will be reviewed by management on a room by room basis. 4 i e f Impact / Benefits: , ( 4 a) Higher standards of material condition. b) A professional plant environment promoting performance excellence. ; I c) Fewer errors resulting from wrong system / wrong unit mistakes. i F i l spannor a priorsty: , Bob Deacy Medium t
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Develop and Implement Preservation Program To Upgrade Material Condition - TY510 1994 1995 1996 1997 Description
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Action Sponsor JlF%1lAhtlJlJlAlSlO[\ D,J jFp1lAbtlJlJ lAlSl0lNlD JlFhtlA%1lJlJlAlSl0lNlD JlF%1lAp1lJlJlAlSl0lNlD TY510 - 3A Implement the Five-Year Preservation Bob Deacy gggggsppggggy,gggggypp,gggyggggg Program to Upgrade Material Condition. Pgy 1 _ TYS10.MPP
Brunswick Performance Improvement Initiative racle, "orJrin, museer, ALARA :nitiatives, Sourt t Term 12/92 - TYS11 - Reduction Strategy: Develop plans and implement measures to reduce the total absorbed dose. Implement-activities to decontaminate necessary systems'and components to reduce the dose source. ! Develop an aggressive corrective' action study for achieving successful source term reduction, which places management focus on the areas of environmental and radiological control; HWC management strategy; robotics for high dose area; implementation of BNP dose reduction plan, and continuous' training for dose reduction, i i 5 Impact / Benefits: a) Reduced site exposure to world-class levels of less than-500 person-- REM, annually. I b) Reduced dose from plant systems and equipment through chemical ; decontamination and hydrolasing to reduce contamination levels, i l l
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ssensor, priertry: ( Jackie Gawron Medium
ALARA Initiatives, Source Term Reduction - TY511 1994 1995 1996 1997 Description Action Sponsor JjF%1lA%IlJlJlAj5l0lNlD J lF p1lAf tl1lJ lAlSlOlNlD JlF%fl Aft lJlJlAlSlOjNlD JlF%1} Aft lJlJlAlSl0lNjD TY511 - IC Des elop and implement a Chemical Jackie Gawron 7/pA] ( Decontamination Plan for Unit 2 Residual lleat l Removal and Reactor Recirculation Systems.
~TY511 - 11 Implement a Chemical Jackie Gawron -
Decontamination Plan for Unit 1 Reactor Recirculation System. TY511 - 8A Complete the evaluation and make Scott Watson ggfjyppgepA recommendations for zinc and ECP probe additions. TY511 - 8B Consolidate and implement mock-up Jackie Gawron gyppsyppA training for dose reduction purposes.
,-m. Pge1 _ TYS11.MPP
O O O - 1' ALARA Initiatives, Source Term Reduction - TY511 1994 1995 1996- 1997-Description Action Sponsor J lF%1lAhtlJ lJ lAlSl0lNlD J lFhtlA%1lJ lJ lAlSl0lNlD J lFhtlA%1lJ lJ lAlSl0lNjD JlFhtlA%1lJlJlAlSl0lNlD TY511 - 8C Complete recommendation for Scott Watson v p/ p ,y// p p g vf74 y// p p A i hydrogen water chemistry management strategy. , i i t TY511 - 8D Approve the BNP Dose Reduction Jackie Gawron y/pp/sy,j Plan for 1995. TY5ll - 8E Complete evaluation and make Scott Watson vp,yppppgrps/7/spp/ppp/pp,yg recommendations for reactor recirculation pipe - decontamination. TY511 - 8F Implement robotics for remote work in Jackie Gawron gygeg y/g ysgep p p pfyyp p pj; high radiation areas. Page 2 TYS11.MPP _.__m _ _ _ _ _ _ _ _.._.______m.._ _ _ . _ _ _ _ _ . , _ . _ . __ . _m______.______._____.--u
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. Brunswick Performance Improvement Initiative O -
Environmental and Chemistry Program 12/92' TYS12 Improvements Strategy: Evaluate best practices at world-class plants. Develop plans and implement measures to upgrade our existing programs. Impact / Benefits: a) Optimum chemistry is maintained in plant systems and equipment ensuring long-term plant life, b) Discharges to the environment are minimized and world-class performance parameters are achieved. s p oor, reurur, O Jackie Gawron Medium
D P l P j N M. O 2 l 1 S b l Y j A T 7 J 9 l 9 J 1 l l M _ w l A l M F l J l D l N l 0 S l l A 6 J 9 l 9 J 1 l l M l A M 2 j F l 1 J 5 D Y l l N T l l 0 S
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Brunswick Performance Improvement Initiative ' f %' TA tle s Origint 2, umbers .
)I Human Performance 9/94' TY601 Strategy: '
Develop and implement an action plan that fully addresses inconsequential arrors and near misses due to human performance in the control of equipment ; evolutions, and ensures long-term and sustained human performance improvements in plant equipment mispositioning. Recent Unit 2 (B2110R1) outage self-assessment indicates the number'of. consequential plant occurrences due to human performance problems have - declined, but that improvement is needed in the area of near misses and occurrences, specifically in the control of equipment evolutions. The corrective action plan identified in this initiative will be i implemented in conjunction with the BNP Corrective Action Program- l enhancements (Initiative TY303, Improve Ability to Identify and Correct Problems),-to ensure effective human performance improvements are realized. Impact / Benefits: a) Fewer inconsequential errors which are deemed to be precursors to ; significant events l b) Reduced O&M and Capital Costs ' c) Improved plant availability and reliability d) Reduced outage durations i l l l Stuttsor o Priority: ,. John Paul Cowan High i
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k. Human Performance - TY601 1994 1995 1996 1997 Description Action Sponsor J [F htlAhtlJ l1l AlSl0lNlD J lF ptlAhtlJ lJ lAlSl0lNlD JlFftlA%tlJlJlAlSl0lNlD J lF %1lA%1lJ lJ lAlSl0lNjD TY601 - I A Increase work force involvement in Clay Warren / Bill Levis yppfypsygyggj developing methods for improving performance through direct involvement with liuman Performance Group, in root cause analysis, and corrective action development. TY601 - 1B Improse work force awareness of Clay Warren / Bill Levis ygygggpygygyppa human performance trends. l TY601 - 1C Expand self-check techniques. Clay Warren / Bill Levis yggp;yA l l t 1 TY601 - 1D Use EPM processes to modify Clay Warren / Bill Levis vggyzyggyfypppggyppgeygygysgyzyj behavior. 1 1 g _ PT1 , TY601.MPP
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l l I Brunswick Performance _ Improvement Initiative fitjes Oriflas Numbers 3O Reactor Vessel Internals Preservation 8/94 .TY602 Strategy: Recent industry events associated with cracking of reactor. internal components assaociated with cracking of reactor internal components - shrouds, jet pump beams, shroud head bolts,..etc. necessitated an aggressive analysis and evaluation to develop and integrate strategy for preserving the BWR internals and ensuring plant and public safety, i Develop and implement a' comprehensive Reactor Vessel Internals Preservation Program that includes the following components: a) Performs engineering analysis to determine internal components , essential to safety and production; ! b) Determines scope and frequency of needed inspections; . c) Identifies flaw evaluation methods; d) Reviews current inspection techniques for improvements in detection capabilities and identifies new/ improved techniques required to address all identified components; and A e) Provides mitagation and repair technologies for the most cost , effective means to preserve reactor internals. l I Impact / Benefits:
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a) Reduced number of outages and outage durations + 1 b) Reduced O&M and Capital Costs I l u
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t sponsoro rssorieys Ed Willett High i I i - ., . , - - , _ , - . + . - -. , . - . - - , . -
Reactor Vessel Intemals Preservation - TY602 1994 I995 I996 I997 Description Action Sponsor JlF%1lAlMlJlJlAlSlOjNlDIlF%IjAlMlJlJlAlSjOjNlD J lF htlA%flJ lJ lAjS jOlNlD J lF htlA%tlJ lJ lAlSlOjNlD TY602 - 1 A Perform engineering analysis to Vaughn Wagoner rMF/MMMMA determine internal components essential to safety and production, scope, and frequency ofinspections needed, and ibw evaluation methods. l TY602 - 1Il Review current inspection techniques Vaughn Wagoner rWFMvMF/MMMMMMA l for improvements in detection capabilities and time l to perform, and identification of new/ improved techniques needed to address all components identified. l TY602 - IC Review mitigation and repair Vaughn Wagoner VM/MMMMM fy M M ///g p/ p //// p/Mfy////7pMp/M/2 technologies for most cost effective means to preserve reactor internals. 1 1 f l _ E - N.E
J Brunswick Performance. Improvement Initiative j n firJes- origsas msnbere
-{ Improve BNP's . Competitive Position 8/94 17603 l
l Strategy: l t Develop and implement strategy for acMxving world class cost performance.- l i c a l F
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f i I A h Impact / Benefits: l v
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a) Reduced OEM and Capital costs b) Increased customer satisfaction c) Improved Brunswick competitive edge t i I h 3 i f spennor, eraarter< l Jim Martin / Dennis McCloskey High
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Improve BNP's Competitive Position - TY603 1994 8995 19 % 1997 Description Action Sponsor JIFptlA%tl1l1ltjsl0lNlD JlF%1lA%1lJl1lAjSlOjNlD J lF %1l A%1lJ lJ lAlSl0lNlD J lF %1l Aft lJ lJ l AlSl0lNlD TY603 - 1 A Implement "htaterials Process John Ferguson [7A7459 y ,yg g555j Redesign
- dated 51ay 1994 reducing issue stations and related staffing levels.
9 1Y603 - lB Aggressively manage the capital John Couan (PRG) cryg,;;c97x/g9;;77,y,ygggygyy,ygmygmygg/pgS$9;5SS97pyxSygggy,y,9;59597p,yg,y;5 program (post 3-year recos ery plan) to keep expenditures below 2.8 mills /KWii. Only authorize projects that are costjustified, or required by regulation. TY603 - lC Educate statias to BNP's cost position Jim h1artin c/pg/yyx/gpyyyggy/gygg;5597p,/ppppg59py/yyg97xmyA;S97p p ygS9pyyg59;yg/g relatise to the competition by means of periodic all-hands meetings or use of printed materials (e.g. hionday hiemo). TY603 - ID Establish a process that will identify John Cowan (Nh1C) regggjyxyge; services that may be performed more economically by contract services, targeting if possible tasks performed exclusively by certain units or sub-units. Page1 TYE031 APP g
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d L.) LJ Improve BNP's Competitive Position - TY603 1994 1995 19 % 1997 Description Action Sponsor J lF %1l A%1lJ lJ lAlSlOjNjD J lF bllA%1]J lJ lAlSl0lNlD J lF ftl4%1]J lJ l AlSl0lNjD J lF ftlA%1lJ lJ lAlSl0lNjD TY603 - IE Provide Nuclear Managers Committec Janet Crews rygggypppg3 with cost of service information for those tasks that may be performed by contractors. TY603 - IF Review NMC contract services target Rich Lopriore/Denny 11 rpysygygyggggg groups and determine if there are any regulatory or training constraints for these tasks that would call into question economic viability. lY603 - IG Perform an analysis of cost benefit of John Cowan g contracting designatea woik tasks utilizing data provided by Contract Services, Regulatory Affairs, and Training. TY603 - Ill Perform a team cfTort to develop the John Cowan 11NP stafTing plan thru calendar year 1999. Page 2 TY603.MPP
Improve BNP's Competitive Position - TY603 1994 1995 1996 1997 Description Action Sponsor J lF%1]AhtlJ lJ l AlSl0lNlD JlFftlAhtlJlJlAlSl0lNlD J lFhtlA%1lJ l J lAl5lOjNlD JlF%1lA%1lJlJlAlSl0lNlD TY603 - l1 Develop and maintain succession and John Cowan yg,yypysyg ygyx9ppy,ypsy,ygynyggg,y,y,y,yyp,9;yy, ppg,y,ygypysyyygggyp; developmental plans. _TV603 - l3 Provide assi;tance as required to Bo Lindgren (H.~*) y,y;y,ygggyggggy,ysyppyy,97,yppg(,ygg,,;9;yggyyy,y,yg, g;97,yyy,y,ygyggy,yg implement and maintain the BNP succession and career development plans. TY603 - IK Ensure attendance of appropriate Denny llicks yg 97pgegyg yfy p p y,yg 97p p yg yg yz personnel at Business Cancepts Training Workshop. Pg3 _ TY603_MPP
-l Brunswick Performance Improvement Initiative
. - m ,.. o,w,, , -, \
,_f Reduce Regulatory Burden 8/94 TY604 i
Strategy: ! Implement the Regulatory Burden Reduction Program at Brunswick. The i program encompasses identifying and prioritizing opportunities to reduce , the cost of compliance with regulatory requirements and commitments with balanced consideration of plant safety, reliability, economics, and protection of the environment. Develop and implement action plans to realize identified cost saving targets for the selected opportunities. The program will be implemented in a manner that maximizes near-term success and' cost savings which facilitates maintenance of a focused and positive NRC interface. O Impact / Benefits: l' f I i a) Elirrination of' unnecessary work ) b) Reduction.in OEM and Capital costs c) An enhanced ability for management to make sound business decisions l based on balanced consideration of plant safety, reliability, economics, and protection of the environment d) Improved efficiency and consistency in plant work practices l l e) Reduced outage costs / schedules i l l 1
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spcmsetr PrJoshtys w Rich Lopriore High
Reduce Regulatory Burden - TY604 1994 1995 1996 1997 Description Action Sponsor ipht hipphlsphp JKhihpipp lsphp Jlrhthhipphlsphp JlrpihbqJphlsphp TYM14 - 1 A Support '95 outage (B110R1) cost / schedule George Ilonma pggyjfg/,gggzge,3 reduction acthities: e.g. MSLRM Scram / Isolation Function Elimination; Eliminate ILRT; increase MSIV leakage. TY604 - 1B !mplement regulatory burden reduction issues: George lionma rp7#/Ke7MWE/2We7z1 Increase surveillance intervals from 30-90 days; implement hand geometry; increase tmtine valve surveillance intervals; CAD system downgrade to non-safety related. TY604 - 1C Support reliability and operational flexibility George lionma rggg/pmgfgpz:pppp,gy,p2 improvements by climinating unnecessary /burdensom regulatory items: Eliminate EPA power supply testing.. , increase EDG surveillance requirement flexibility, extend , remote shutdou n panel.. l I l TY604 - 1D Implement additional burden reduction items in George llor.ma :2>7/pfg//p///////p/) 1996 w hich n ill result in savings of > = $500,0(x).
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' Brunswick Performance Improvement Initiative :l J
, . ,f% - TJ tJe s origina Numbers l
}{ L yrove Refueling Oucage Management. 8/94 TY605 -- }
l Strategy: j Develop and implement an outage preparation and implementation program ' designed to continually. reduce BNP outage lengths through the application , of industry experience and improved performance.
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'i Impact / Benefits: !
a) Reduced outage durations b) Reduced O&M and Capital Costs >
, c) Longer plant runs l
d) Reduced site exposure , I; k I f P i scannora ersernya ! John Paul Cowan High
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Improve Refueling Outage Management - TY605 1994 1995 1996 1997 Description Action Sponsor J iFlMlA%1lJ lJ lAlSlOjNjD J lF %1lA%1lJ lJ l AlSl0lNjD J jF%1lA%tlJ lJ lAlSl0lNlD J lF%1lA%1lJ lJ lAlSl0lNlD TY605 - 1 A Develop a standard definition and Clay Warren / Bill Levis rpysy/gyg7,yj priority sytem for performing on-line corrective and preventive maintemnce. TY605 - 1B ProvMe a scheduling tool and Clay Warren / Bill Levis tggyz yg gyg y4;y,4 reporting process that meets the needs of al; tork groups. Establish schedule products for each work group's review and approval. TY605 - IC Develop a manageable outage schedule Clay Warren / Bill Levis r$pyg ygg ys yjgegj with milestones, effective buy-in, and status capability. Distribute preliminary outage schedule for review with milestones for B110RI. TY605 - ID Develop plans for outage resources Clay Warren / Bill Levis pygge yggyzys:py,j including parts, manpower and coordination activities. Distribute histograms for resource requirements, parts required list and milestone schedule. _ P, age 1 _ TY605.MPP
fn (~) f'p V w. M ' Improve Refueling Outage Management - TY605' 1994 1995 1996 1997 Description Action Sponsor
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JlF%tlA%11slJlAjSIOjNjD J jF %1lA%1lJ lJ lAlSlOlNlD JlF%1lA%1lJlJlAlS[OlNlD JlF%1lA%tlJlJlAlSlOjNjD TY605 - 1 E Identify outage mods and projects Clay Warren / Bill Levis yppfa early enough to allow for detailed planning. . - TY605 - IF Enhance scope centro! process by Clay Warren / Bill Levis , revising BSP-35 to clearly identify responsibilities relative to emergent items (ie: daily review of WRJO's for outage impact). TY605 - IG Provide early involvement of the Clay Warren / Bill Levis ypppA Planning (work packages) Organization in the scope identification process. TY605 - 2A Ensure future outage contracts have Clay Warren / Bill Levis r4&7Ev#A3Vad incentive clauses to improve contractor perforraance and outage success. 4 Page 2 . TY605.MPP
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Improve Refueling Outage Management - TY605 1994 1995 19 % 1997 Description Action Sponsor JlFhtlAfijJlJlAlsl0lNlD J lF %1lA%1)J lJ lAlSlOjNlD JlFhtjA%1lJlJlAl slo lNjD JlF%1lA%1lJlJlAlSl0lNlD TY605 - 2B Evaluate the procurement ofimproved Clay Warren' Bill Levis wgggygyga reactor servicing tools and'or existing equipment upgrades to support shorter refueling outages. TY605 - 2C Key outage personnel will visit and Bill Levis pyzy////g observe other utilities during the perfomiance of planned "Short Duration" refuel outages this fall so that industry best practices can be incorporated into future outages. TY605 - 2D Evaluate routine preventive Clay Warren / Bill Levis gypygggA maintenance performed during refueling outages that does not require an outage for performance to reduce the number of PMs scheduled. TY605 - 2E Evaluate / implement recommendations Clay Warren / Bill Levis gyzy/A l for improvement from INPO's recently completed outage review visit. g Page 3 TY605.MPP
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Improve Refueling Outage Management - TY605 1994 1995 1996 1997 Description Action Sponsor J lF%1lA%1lJ lJ lAlSl0lNlD J lF %llA%IlJ lJ lAlSl0lNlD J lF %Il A%1lJ lJ lAlSlOlNlD JlF%IlA%IlJlJlAjSjolNl0 TY605 2F Set aggressive preplanning milestones Clay Wauentill Levis g that ensure site researces has e adequate preparation time for outage aovities. Issue at least one year prior to the outage stat per BSP-35 guidelines. TY605 - 2G Maximize preoutage work by Clay Warren / Bill Levis yzpyg gy M A performing extensive reviews and challenges of all outage projects. (Example: U2 RIIR Valves) 1Y605 - 211 Prestage/ package materials required Dennis McCloskey py/fyMMAwzpyA for outage activities in specific locations prior to the outage so that material availability can be validated. 1Y605 - 21 Complete pre-outage training to Clay Warren / Bill Levis przyzygmyggvmg1 all-hands on the outage schedule along with the weekly stand-down meetings to encourage ou nership and communications among site , employees. Page 4 : TY605.MPP - - _ - - . . - . . _ , - . _ - _ _ - . . . . - - . . ~ , . ~ . _ . ...-.-. _. - - ...,-:..--,- -- . - - - .:.---.-,.--..,,.- .. ~ - . . . - . - . . - . . . . . - --.
Improve Refueling Outage Management - TY605
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1994 1995 19 % 1997 Description Action Sponsor J lFpthptp p hlslOjNlD J jrp1hhiplJ hlSlOjNlD 1jF%1h%tlJlJlAlSj0!NjD J lF ptlAhtlJ lJ hlSl0lNlD TY605 - 2J Adopt a policy that all significant John Cowan py;y,p;pm l projects and modifications will require PRG approval to be implemented in refueling outages to ensure manageable work scope and minimal patential to extend outxe duration. TY605 - 3A Utilize PLP-25 (Self- Assessment) to Clay WarrencBill Levis tggyfm perform a post-outage assessment of B211RI Refueling Outage within 60 days of outage completion. lTY605 - 3B Perform project critiques on all major Clay WarrenBill Levis , . ';*ojects implemented during Unit 2 refuel outage with emphasis on every cy cle repeat projects. TY605 - 3C Document lessons teamed from Clay WarrenBill Lesis t:py,p;p;,ypA B211RI and assign a responsible Unit Manager to resohe items needing correctise action prior to Ul spring 95 outage. Page 5 TY605.W-P j
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O O O Improve Refueling Outage Management - TY605 1994 1995 t996 1997 Description Action Sponsor J lF %1l4%1lJ lJ lAjSlOjNjD JlFptlA%1lJlJlAlSl0lNjD J lF%tl Apt lJ lJ lAlSl0lNlD J lF %flA%llJ lJ lAlSl0lNlD TY605 - 3D Examine post-outage critiques from Clay Warren / Bill Levis @ other utilities recognized by INPO as having superior programs that document outage lessons learned. i TY605 - 3E Continue active participation with Clay WarreWBill Levis y//sssaysp//,m y s p / s s // s p / s / s y//,y s /,y s sssf/ss/s/ssz llWR Owners Group Outage Management Committee to ensure that improvements in industry outage performance are considered for Brunswick Station. TY605 - 3F Continue to encourage use of outage Clay Warren l Bill Levis 7sx/p g g /s s s,m y//4 7 m //x yxA y g A;9/,ygggg,7xyxy/gy/gssS7g/ZS self-assessment forms by all site personnel to capture good practices and areas for improvement. e Page 6 TY605.MPP
e q g MAJOR PROJECTS
/m i-d* EXECUTIVE
SUMMARY
INTRODUCTION i Bnmswick Nudear Plant (BNP) continues to make improvements in the areas of system reliability, matenal condition of the plant, and management oversight of projects. These impmvements ensure long-term and sustained improvements in plant performance. PLAN ACCOMPLISHMENTS Five projects have been completed for both units since the August 19M update of the BNP 'Ihree-Year Business Plan including: drywell coolers loss of cochng accident lockout override, diesel generator oil level annunciator, and 480 volt vital motor contml center. Studies are complete on reactor buildirg instrument rack repair / upgrade and Phase II of spent resin transfer system, and the physical work will be completed as minor mods. CURRENT STATUS On-line projects currently in progress include the Unit I supplemental spent fuel pool cooling permanent piping and penetrations, instrument air compressor upgrade, Unit 2 battery room HVAC, DC ground detection, and
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O) fuel pool girder tendon inspections. In addition, planrung is in progress to suppon the B1IORI outage scheduled for the Spring of 1995. FUTURE FOCUS The future focus is the timely accomplishment of all the L110RI refueling outage projects / mods mejor milestones and the completed implementation of Phase II of the Master Projects Plan, ensunng total cost and scheduhng integration to be used as a tool for management and Plant Review Gmup (PRG) to ensure trends of continuous improvements are maintained. BNP management is committed to ongoing plan implementation that is result based, focuses on improved plant performance, economic viability, and ensures plant aafety. O 1
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SUMMARY
OF COMPLETED WORK: . Five (5) projects were completed, since the August 1,1994 'Ihree Year Plan Update
' PROJECT # PROJECT TITLE CAT. EXPLANATION '
05092A- Reactor Building Instrument Rack I. ESR 9400406 initiated fx ,; Repair / Upgrade minor mod for permanent .> repair. 08262A Drywell Coolers loss of Cooling Accident H Physical work complete. t Lockout Override 77443A Phase II Spent Resin Transfer System H Study performed to address l' deficiencies in Spent Resin ; transfer system. ESR 9400434 i initiated for Minor Mod to s implement fix. 80203A Diesel Generator Oil level Annuncintor H Physical work complete.
- 84489B 480 Volt Vital MCC Rework H Physcial work complete.
T k l r i t 5 e i a t e-2
PZOJECTS CANCELLED: Nine (9) projects have been cancelled since the August 1,1994 Three Year Plan Update. PROJECT # PROJECT TITLE CAT EXPLANATION
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i) 06156A High Pressure Coolant Injection. I The Unit I plant modification Reactor Core Isolation Cooling 111- has been completed. The Unit Steam Flow 2 Plant Modification (PM 88-022) was canceled. An engineering evaluation has shown it is not necessary. G0159A RPV Invessel Irradiated Specimens I 'Ihis project will be incorporated into the routine projects of Technical Support. 05892A Effect of Electried System Variations H New rotors are to be on Turbine Genen . tor Torsional torsionally matched upon Response installation. 06107A Improve Refuel Floor Fire Dctection H Safety aspect of this issue is Access placed with the Loss Prevention Grcup. If any action is required an ESR will be generated. , 07438A Replacement of Area Radiation II Replacement of recorders no Monitoring Recorders longer necessary. EDP 93-005 removed 1(2)-D22-RR-R600 & 601 recorders.
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07848A Reactor Building Roof Vent H Scope will be performed under G0015A (Small Mod program). G0075A Local Power Range Monitor Cable H Unit I completed and Unit 2 Replacement in Drywell has been cancelled. The spiking phenomenon that had been taF e place has now been corrected on Unit 2 through the performance of IV curves on a regular basis and the removal of the LPRMs that were most prone to spike. G0161A Bus Duct Cooling Fan Modification II Technical Support evaluated Unit Two the existing systems in use and determined that the appropriate measures are in place that eliminate the need for this modification. Based on this evaluation. Canceled October 1994. M0187A Building Penetration Leakage H Transferred to the Minor Mod Program, ESR 9400055
. initiated.
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PROJECTS UNDER EVALUATION f,. Nine (9) projects are undergoing further evaluation: (d \ PROJECT #
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SPONSOR / TITLE CAT. EXPLANATION PRQJECT MANAGER 04699A Chris }{ughes Salt Water Transfer II Redefine scope of project and Pump Replacement submit to PRG prior to June 1995. 05503A Bob Jernigan Replace 1-SA II Redefine scope of project and Feedwater Heater submit to PRG prior to June 1995. 06661A Craig March Traversing In-Core II Redefine scope of project and Probe System submit to PRG prior to June Upgrade 1995. 07197A Bob Jemigan Ten Year Inspection II Evaluate alternative methods of Recirculation of performing inspection and Pump Motors submit to PRG prior to June 1995. 07250A Dan Moore Eliminate Source II Detine the impact on plant and Intermediate operations and submit to PRG Range Monitor prior to June 1995. Noise Spikes 08048A Terry Bowman Setpoint Control II Redefine scope of a study and (,,Q) Program submit to PRG prior to June 1995. 31377B Chuck Raines Spent Fuel Pool II Evaluation to complete Repair December 1994. t 84849A Bunk Hewett Electrical Fire Pump II Redefine scope of project and Control submit to PRG prior to June 1995. I B0078A Craig March Emergency Fire II Redefine scope of project and Damper Position submit to PRG prior to March 1995.
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- FROJECTS RESCHEDULED:
i g Eight (9)' projects has been rescheduled since the August 1.1994 Three Year Plan Update. !
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D PROJECT # TITLE CAT. EXPLANATION -l G0096A~ Fuel Pool Girder Tendon Inservice I Sample expansions have extended the - Inspection implementation schedule completion from December 1994 to .hy 1995. G0017A DC Voltage Profile Study I 9 of 11 calculatmns are scheduled to complete end of 1994. Preliminary calculational iterations have been ! performed on the 2 remaining. . Study. l has been extended from December . 1994 to December 1995. l 1 1000453 Simulator Instructor Station II Simulator outage scheduled for November / December 1994 for testing. l Final installation May 1995.' Target . ! completion revised from December . 1994 to June 1995. ;
.L 058% A Radwaste Effluent Release Line II . Small Project Listing >
Reroute moved from December 1996 to - December 1995. > 12420A Control Building HVAC Condensate ' II Study is in NED review. Forecast } Drain Repair PRG presentation rescheduled from , October to mid-Dember 1994. 81401A Floor Drain Filter Retrofit II Design of. mod is on hold. until ESR , 94-0226 investigates the use of current technology. Extended from December 1994 to April 1995.
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84587A Radwaste Sampling' System Upgrade II Project is important to properly monitor reactor water chemistry and completion 4 date has accelerated from July 1996 to December 1995. , G0058A Turbine Uprate II Unit Two target completion has extended from August 1994 to - December 1994 due to data being collected at 100% power and { performance of control and stop valve i testing at higher power levels. Unit i One completion is still targeted for June 1995. G0193A BNP Refrigerant Replacement II Study has been extended from August i 1994 to December 1994. e
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4( L PROJECTS ADDED: Six (6) projects have been added since the August 1,1994 Three Year Plan Update. PROJECT # TITLE CAT. ; B0060A Miscellaneous Structural Steel Upgrade I G0105A 'Ihermo Hydraulic Stability Issues I-13629A Control Blade Pins and Rollers Replacement II 13676A Supplemental Spent Fuel Pool Cooling Assist (Purchase of II Equipment) 13695A Increase MSIV Allowable Leakage II 13863A 10CFR73 Compliance . Vehicle Intrusion II O e 6
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.- CATEGORY I PROJECTS LISTING l PID ' COMMITMENT NUMBER - PROJECT TITLE -CATEGORY 1-009171 EMERGENCY RESPONSE FACIUTY ISOLATION SIGNAL
- GROUP 10
*00918A REACTOR VESSEL WATER LEVEL INSTRUMENTATION UPGRADE I 00925F APPENDIX R.1NERMOLAG RRE WRAP ISSUE I 01538A SERVICE WATER SYSTEM PIPING PHASE III I
'04042A I SEISMIC QUAUFICA110N OF EQUIPMENT-NUREG 1030 l I~
*05644A AC VOLTAGE DROP ANALYSIS 1
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*B0014A EMERGENT STRUCTURAL ISSUES I B0018A PIPING DESIGN TURNOVER PROGRAM i
B0019A DESIGN BASIS RECONSTITimON I~
'B0060A MISm f-ANEOUS STRUCTURAL STEEL UPGRADE I .,
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*BNT622 BNP PLANT BUILDING bitiEL
*G0017A DC VOLTAGE PROPILE STUDY I
*G0024A INVESSEL CORE SPRAY PIPING REPAIR I
*G0029A PEEDWATER SPARGER CRACKING ISSUE I
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*G00501- DIESEL GENERATOR SERVICE WATER SUPPLY AND DISCHARGE PIPING l REPLACEMENT
'G0096A PUEL POOL GIRDER TENDON INSERVICE INSPECTION I
*G0105A THERMO HYDRAULIC STABILITY ISSUES I 1
*G0110A ELECTRICAL DISTRIBUTION ADEQUACY /GDC-17
'G0140A UPGRADE SECURITY COMPUTER AND CARD READER I I
*M012 tE PROVIDE THERMAL OVERLOAD PROTECTION IUR AC MOTOR OPERATED VALVES 1
P0057E HOTS!DECOLDSIDE WALKDOWN REPAIRS I I
- ' Indicates project change from August I,1994.
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f'] EMERGENCY RESPONSE FACILITY ISOLATION SIGNALS - GROUP 10 , /
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I. PURPOSE AND SCOPE This project addresses the need to add the Group 10 containment isolation signals to the Emergency Response Facility Information System (ERFIS) displays. The primary containment logic functions to ensure that the appropriate containment isolations occur in response to abnormal plant conditions. The Group 10 containment isolation signals should be remotely indicated at the Emergency Response Facility as required by NUREG 0737, Supplement 1, paragraph V. These isolation signals will also be added to the ERFIS (SPDS) display in Unit I and Unit 2 control rooms. This NUREG was implemented at BNP by the establishment of the ERFIS system. However, during the initial installation of the ERFIS system, the signals from the Group 10 isolation valves, which isolate the normal pneumatic supply to the reactor vessel drywell, were not included in the work scope. To satisfy the requirements of NUREG 0737 Supplement 1, the Group 10 isolation valves must be added to the ERFIS system. The project is under design and is planned for installation for Unit I during B110RI and Unit 2 during B212RI. The successful installation of the Group 10 containment isolation signals would meet the requirements of NUREG 0737, Supplement 1, paragraph V. II. EVALUATION Schedule Index: 8 - There are no appreciable nuclear safety implications for this project. This initiative I would provide additional information to the operators on the status of the instrument air containment isolation valves dunng scenarios involving reopening of main steam isolation valves and containment venting. It would also provide information on the status of containment integnty during events involving core damage and containment release. A nuclear scaling factor of 0.2 was assigned to this project based on low impact to the instrument air system and improved ability to monitor the status of containment [] V integrity during a severe accident. The plant will be enhanced with the addition of the Group 10 Containment Isolation valves which will aid the operators performance in verifying plant conditions (0.2 x8). Economic Aspects: After installation of the Group 10 signals to ERFIS, there are no additional costs for this project. Related Standards: This project relates to the Work Management Policy on operating parameters because it improves the operators' ability to monitor plant conditions. l Other Considerations: In order for this work to be accomplished, it must be scheduled during an outage l and coordinated with other projects that may have an interface with 009171. However, the display and ! database development can be accomplished during non-outage time periods. In order to address its ! commitments to NRC, CP&L has committed to complete this project. IIL CONCLUSION Relative to other projects, this project has a lower Scheduling Index. However, this project will be completed because the Group 10 containment isolation signal indicators are required to be located in the i ERFIS per NUREG 0737 and to meet the NRC commitment date. IV. STATUS The Implementation Phase has been approved by the Plant Review Group for Unit 1. The Unit 2 plant modification has been approved. Unit I plant modification is in the approval cycle. (n A PID _00917,I Category I m
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V. ' TARGET COMPLETION : - Unit 1 B110 Unit 2 B212 PROJECT MANAGER CRAIO MARCH PID 009171 1 l
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. /% . REACT,OR VESSEL WATER LEVEL INSTRUMENTATION UPGRADE 1 ) L PURPOSE AND SCOPE his project will provide the inadequate core cooling instrumentation required by NUREG 0737.
The modification covers the installation of two new cold reference legs, lines B217013 and B21-7014 and two new condensate chambers. De new reference legs will tie into existing level transmitters B21-LT-N026A and B21 LT N026B which are used for wide range reactor water level measurements.
%e remaining project scope is to relocate variable restriction orifices closer to the pnmary containment penetrations to reduce transient pressure spikes in the sensing lines.
II. EVALUATION Schedule Index: 30 - Dis project is an NRC commitment and improves the accuracy of the reactor water level indicating system. Economic Aspect: Dere are no expected continuing or baseload costs nor any maintenance savings associated with this project. Other Considerations: Dis modification will ensure compliance with Supplement 1 of NUREG 0737 Section U.F.2. III. CONCLUSION his project is a regulatory commitment to ensure compliance with NUREG 0737. IV. STATUS De regulatory commitment was met with the installation of the cold reference legs and condensing - chambers in 1989. Since the remaining work does not affect operability of the system or fulfillment of the commitment and is not cost beneficial, a field revision will be issued to delete the remaining scope of work. V. TARGET COMPLETION December 31,1994 - Issue field revision and close ned. PROJECT MANAGER CRAIG MARCH PID 00918A PID 00918A Category I '
. g. _ APPENDIX R THERMO-LAG FIRE WRAP ISSUE h)
I. PURPOSE AND SCOPE The NRC has issued several Information Bulletins, Notices and a Generic Letter concerning the failures of Thermo-Lag 330-1 material to perfcrm their intended fire protection function. CP&L has placed fire watches as compensatory measures in the areas containmg this material until the material can be successfully tested or upgraded to provide the appropriate protection. NUMARC has provided industry direction by coordinatmg this issue with the NRC and performing an industry testing program. His material is located in the Control, Reactor, Service Water and Diesel Generator Buildings. The configurations range from small conduit wraps to large junction box enclosures. II. EVALUATION ne NRC issued a revision to Generic letter 92-08 requesting additional information concerning ' CP&L's configurations and plans for resolution of this issue. CP&L provided a response to this request on 2/14/94 outlining a plan to perform a Project Study and Testing Program. The Project Study would review each configrtion to determine to best possible option for resolution of the Thermo-Lag issue. This could include elimmarion of the Thermo-Lag through changes in CP&L's Safe Shutdown Methodology, rerouting the circuits, upgrading the existing nermo-Lag or replacing the Hermo-Lag with a different fire wrap material. The Test Program will consist of configurations not bounded by tue current NUMARC Testing Program. His included large junction boxes. The Testing Program and Project Study will be performed in parallel to streamline the final resolution and implementation. III. CONCLUSION His project will continue to ensure resolution of nermo-lag issues. IV. STATUS Project has been study phase approved by Plant Review Group. V. TARGET COMPLETION The response to Generic I.etter 92-08, Supplement 1 outlined that CP&L would provide an integrated schedule within 90 days of NUMARC completing their testing program which is currently scheduled for September of 1994. PROJECT MANAGER STEVE HARDY PID 00925F O L PID 00925F Category I
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. _ SERVICE WATER SYSTEM PIPING PHASE III
( c i 1 U I. PURPOSE AND SCOPE i 1 nis project upgrades the Service Water (SW) pumps for long term seismic gaalification, with , self-lubrication, and with improved thrust beanngs. His SW pump modification eliminates the need for I the SW lube water pumps, which will eventually be removed. De success criterion of this project is that no unit forced outages or plant deratings will be attributable to the SW system and the pumps meet long i term seismic integrity. Also, the Reactor Building Closed Cooling Water (RBCCW) SW supply piping on ' both Units will be replaced in B110R1 and B212RI. De scope of this project includes replacement of l those piping areas kn-)wn to have corrosion damage. I II. EVALUATION 9 Schedule Index: 32 - His project moderately improves the availaoility of the SW system and therefore reduces the probability of core damage or contamment release (0.5 x 32). The probability of a SW system train being out of service is included in the PRA and the project is judged to have a moderate positive impact on SW system availability. It eliminates the need for ASME Section XI Relief Request PR-05, N which requests relaxation of required performance testing of the SW lube water pumps. Seismic upgrade
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and self-lubrication changes to the SW pumps will reduce the potential personnel safety hazards resulting from high SW pump maintenance (0.2 x 29). Finally, this project contributes to improvement in the 1 operations and maintenance of the SW system and reduces the maintenance and testing requirements for 1c SW system; therefore, this project is considered an important plant enhancement (0.5 x 8). Economic Aspects: The expected benefits of this project are future savings due to reduced maintenance ; requirements and, therefore, increased unit availability. Related Standards: ISI testing of the SW lube water pumps will be climinated and therefore simplify testing requirements of the SW system. His will close the relief request PR 05 on the SW lube water puraps, which is currently a commitment to the NRC. De outage-associated work of this project has been planned, scheduled, and carefully integrated with all other major SW projects. Other Considerations: Upgrading SW pumps (and removing the SW Lube Water system) can be accomplished without an outage because of the redundancy of the SW system. Upgrades to the SW pumps are critical to meeting the NRC commitment date which are scheduled to be completed November 1994. i III. CONCLUSION Eliminating the SW lube water system reduces ISI testing requirements and some Technical Specification considerations. This project will continue to ensure the service water pumps have long term seismic qualification, are designed for self-lubrication, and are backfitted with improved thrust bearings. IV. STATUS Projects have been design and implementation phase approved by the Plant Review Group. Currently seven of ten service water pumps are complete. De RBCCW/SW supply piping will be replaced in B110R1 and B212RI. ( , L PID 0153SA Category I
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V. TARGET COMPLET10N . I'- November 1994 for the committed poruon of this project. December 1995 for ripout of the Lube Water System. June 1996 for RBCCW SW Supply Pipe Seplacement PROJECT MANAGER CHRIS HUGHES PID 01538A I I' i t i 4 l r f I I e
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. SEISMIC QUAIRICATION OF EQUIPMENT - NUREG 1934 V i I. FURPOSE AND SCOPE !
i Methods to analyse the adequacy ofequipment to withstand seimuc events have changed in the years since -l the Brunsmck Nuclear Plant was designed and w ;.-W. Because of these changes in =ie*W. - j the seerne margms of older equipment are unknown. NRC resolution of Unresolved Safety Issue (USI) ; A-46, "Seimnic Qpaldication of E; 6 -at in Operatag Nuclear Pcner Plana", is pmmulgated in NRC Genenc letter 87-02 and requires aB utihees whose plans are not qualdied to current entma to evaluate 3 their elecincal and =='=?=1 --;- , =^ requeed for hot shuulown for adequate seeme q "'- d=- l The Seismic Qp=1#ie='m Utility Group (SQUG), of which CP&L is a member, dr.d.,,4 genemi ; imp'- =-- -- guidance for i, L.. g the revums. NRC appemed the use of this gnwimace in a Safety j Evaluation Report dated May 22,1992. In addition, the NRC immed Generie letter 88-20, " Individual . Plant Examination for External Euena (IPEEE) for Severe Acculent Vulne dih M. %c genenc lener - , requested each Loensee to conduct an exarrunanon to estabbsh the effects < f seirnir evens, internal fuen, high wmds, floods, transportanon, and nearby facihtyA T h ve a'u to confrm that there- ! are no m.,. ed,le plant-umque extemal ew:nm being excluded fiera exams .en.
%e pup di propet is to implement the resolunon of USI M6 by analy mg the sewnic adequacy
{ of Brunsmck d_aical and =~h=ab=1 equipment requaed to =----- ;'4 and mamtam the plant in a hot safe shutdown condition for 72 hours. Also included in the scope of this pmpect are the eveluation of out- j liers and the scopung ofnwwitie= ems to address any deficient conditions found during the effort. %e final -l pmduct wiB be a report t-:---- = ting the resula of the review, sieludmg ideneine=*m of' '- - - - that { may require conection. De sewnic portion of the IPEEE wiB be i L..a under this project using a _l seismic magpns methodology that screens componene according to safety L..,,,,.w.a and seuruc capacity agamst a peak gmund ac2; ; of 0.03g. De option to perform a Probability Risk Assemment (PRA) ; will be maintained by gathenng sufliment data for- --, = _--t fmgibty calculations. i His m -g pmcess wiB be performed concunently with the USI A 46 program. Assurance that ~! safety related electncal and =='==1 equipment can perform their intended funcnons duiing and l following a semnic event or V-- T=E=, ofcorreenve acnons to resolve riencient conditions will constitute l successful completion of this pmject. Further assurance of =ree=#ul cara-t-e aa win be evalenced by NRC ! review and acceptana of" dk Nuclear Plant's ; --/=- ==--- d USI M6. II. EVALUATION l e a Schedule Index: 30 - his project could have a agndicant impact on future analyses of extemal events. l AD plant systems could be affected by a newrue event and severe consequences could result if equipment is not assured dmeenng the specified quahfication criteria. His resula in a last impact on the core ; damage frequency due to seimnic events (1.0 x 32). Venfying neuruc qualification wiH require L gsics and system walkdowns in radianon areas and result in expo ure to workers. his exposure will not be made i up by any ALARA benefits affonled by the project c e a t lifetime of the plant, themfore resulting in a j negative AIARA scaling factor (-0.2 x 9). { Economic Aspects: Ae project requires a short-term investment to condxt component inspections and walkdowns, with no identified positive or negative economic benefits extending beyond the completion of ; the project. Related Standards: The Work Management Policy on material condition of the plant is applicable to this Project. PID 04042A s Category I i
Other Considerations: The project wiD be performed under the guidelines of the General Implementing Pmeedure (CIP) developed by SQUG. NRC appmval of the procedure has been obtained. After the study is completed, a repon wiD be prepared and submitted to the NRC that documents the results and describes the schedule for conectmg any deficiencies identified during the review. Margins for the plant with respect to sessmic events as required for the IPEEE analysis will also be established under this pmject. III. CONCLUSION Because the methods used to seismicaDy qualify safety rrlated systems were not as capable as current methodologies, plant systems will be reviewed to assure the capability to perform their functions during and after a seismic event. %e NRC has expressed its concerns on this issue and recommended actions to be taken by licensees in Generic I.etter 87-02. SQUG, ofwluch CP&L is a participant, submitted and received approval fmm the NRC on generic implementmg guidance for reviewing seismic quahfication ofequipment. IV. STATUS ne CP&L implementation program addresses the requuements ofboth USI A 46 and IPEEE, and includes combined walkdowns that rmrumize manpower %=m. cats and impact on the plant. He CP&L implementation of the SQUG program is tmcked under Brunswxk FACTS Item Numbers 92B9307 and 92B9308. Unit 2 walkdowns began in theJanuuy 1994 prior to the refueling outage, and continued through the outage. Walkdowns are complete, and equipment anchorage evaluations and SQUG guideline compliance deterrrunation are ongoing. The walkdowns induded approx 2mately 850 Unit 2 and Common equipment componen:s. Unit I drywell and MSIV pit walkdowns were conducted during the Summer of 1993. Unit I on-line walkdowns began in the Fall of 1994. For these items the equipment anchorage evaluations and SQUG guideline compliance determmation are ongoing. Walkdowns are stiD required for approxunately 80 items. He items still requiring walkdowns include control room cabinets, and battery and cable spread room components. Preparations are underway to complete these walkdowns. V. TARGET COMPLETION
%e IPEEE commitment is based on CP&L letter number NIS 92-285, dated October 15,1992. The target submittal date for the IPEEE analysis was given asjune 30,1995. He walkdowns stiD pending for Unit 1 items include specific IPEEE components such as control room cabinets P601, P606, P622, P623, XU-3, XU-27, XU-28, XU-51, XU-53, XU-56, XU.65, XU-66, XU-67, XU-68, XU-75, and XU-79 (and components mounted inside these cabinets). In order to meet this date the remauung items wiD require on-line walkdowns.
An NRC letter dated November 23,1992 provides the Brunswick Safety Evaluation addresang USI A-46 and addresses the submittal dates, which are tied to the completion of specific refueling outages (reference letter NLS-92-252). He USI A-46 commitment is based on report submittal 120 days after the completion of Unit I refueling outage B110RI.The refueling outage for Unit 1 is scheduled to end on hby 25,1995. Based on this, the USI A-46 submittal is due on September 22,1995. PROJECT MANAGER CHUCK RAINTE PID 04042A O
i b .h LAC VOLTAGE DROP ANALYSIS I b lL PURPOSE AND SCOPE ' Exisdag design basis calculations for the Brunswick Alternating Current (AC) electrical distribution system l have been found,in some cases, to be unavailable or inadequate. De AC Voltage Drop Analysis project 1 has been undenaken to establish cunent, readily accessible AC electncal distribution system design basis calculations. Calculations to be provided include load factor studies, control loop calculations, voltage / load - flow / fault current calculations, cable ampacity (amperage capacity) calculations, emergency diesel generator static and dynamic loading calculations, the fast bus transfer study. De 1991 electrical distribution system - functionalinspection reaffirmed the need to upgrade or develop cenain calculations which are a pan of this project. Once complete, this project will document the capability of the present AC distribution system, l and provide a basis to support future modifications and 10 CPR 50.59 safety evaluations. In the event of : a proposed ' change to the AC distribution system, documentation will be easily accessible to allow i identification of potential equipment overloading, over or under voltage situations, non-selective tripping i of overcunent protective devices, excessive fault currents, emergency dieselF .h overloading,orother l design issues. De ability to quickly and accurately respond to design basis issues which may arise during an audit will be greatly enhantwl j f IL EVALUATION ! Schedule Index: 10 - Upgrade or development of design basis calculations is not expected to have a !' substantial effect on AC distribution system design or operation. However, the project includes additional calculations to establish diesel generator loading profiles. A more detailed analysis of the diesel generator load profile could result in procedural or hardware changes that would enhance the reliability of the EDG l system. Because of the low impact on this system of high risk significance, a 0.2 nuclear safety scaling a factor is assigned (0.2 x 32). Dis project should have no appreciable effect on personnel safety, unit : availability, unit capacity, or ALARA, but should reduce research time on modifications and engineering evaluations and analyses (plant enhancement. 0.5 x 8). ! t Economic Aspects: Once this project is completed, no continued costs are anticipated. Ongoing resource j savings are expected in the future, due to reduction of time spent on modification preparation and engineering evaluation. Related Standards he applicable Work Management Policy is design documentation. ! Othe.1 Considerations: his project is related to B0019A, Design Basis Reconstitution, and G0110A, ; Electrical Distribution System Adequacy /GDC17. De original NRC commitment for this project was to complete analysis of MCC system selectivity by October 3,1988. In 1991, an additional commitment was , made to respond to NRCInspection Repon 91-09 by December 31,1992. He calculations being developed ; presently either do not exist or need improvement. ! i IIL CONCLUSION I his project will be completed as part of the design basis reconstitution effort. his project will provide i a basis for ensuring operation of the plant within the design basis. IV. STATUS , This project is design phase approved. ; PID 05644A Category I
V. TARGET COMPLETION December 1995 t PROJECT MANAGER Mike Terry PID 05644A
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i EMERGENT STRUCTURAL REPAIRS 3 i~/ I. PURPOSE AND SCOPE BNP initiaDy responded to the pipe support issues ofIEB 7914 in 1979 and 1980. He Emergent Structural Repair project was initiated in 1986 to address other structural repairs for supports and miscellaneous steel used in the plant. In 1988, the project incorporated additional response to IEB 7914 to provide enhancements to pipe supports needed in order for them to meet original design requirements. Other work not related to IEB 7914 has been added to this pmject. Examples of such emergent items are fue protection suppon upgrades, HVAC support upgrades, conduit suppon upgrades and resolution ofSTSI structural deficiencies identified by EWRs. %ese deficiencies require either verification of structural suppon seismic qualification or implementation of structural reinforcements or repairs that meet seismic requurments. The Drilled-In Anchor Sampling Pmgrams was initiated as a result of NRC Notice of Deviation in Inspection Repon (IR) 9214. He Unit I and Unit 2 plant mods have been completed. He Emergent Structural Modifications will be considend successful when aH plant structures and suppons with seismic qualifications or other safety related design altena are found to conform consistently to those requurments over the remammg life of the plant. The level of emergent structural work has declined and work on stmctural suppo:ts is now pnmarily the result ofinspections or walkdowns and EWR resolutions. Scope for modification to conduit supports in the Unit I drywell, and STSI repain have been issued into PM 93-029 and will be performed during outage Bl10RI. An Emergent Structural Modification for each unit should remam in-place for repair of other structural deficiencies identified as STSI. i p\ V II. EVALUATION Schedule Index: 51 - His project is intended to assure the setsrruc qualification or re-qualification of suppons for Category I and Category 11 structures and safety systems. His project exceeds the scope of the current nuclear safety Probabilistic Risk Amessment (PRA) model. Nevenheless, a special seismic review was performed by the CP&L PRA Gmup to amess the significance ofidentified structural suppon deficiencies. This assessment indicated that the structural suppon conective actions induded in this project have a high impact on reducing the risk of core damage (1.0 x 32). Unit availability is also impacted directly (1.0 x 12) since structural supports have been found in the plant that do not nueet seismic requirements. Potential also exists for personnel hazards due to failed suppons, primarilly during an earthquake (0.2 x 29). As a result of this project, continued upgrades and plant inspections, system walkdowns, and maintenance practices will provide additional general enhancements to the plant (0.2 x 8). Economic Aspects: 'Gis project has financial impacts due to the commitment to perform repain to FTSI structures and suppens that must be seismicaEy qualified. Related Standards: This project is primarily related to the Work Managernent Policy for maintaining plant material conditions within design and licensing requurments. Other Considerations: CP&L has met the commitment to the NRC to complete IEB 79-14 pipe support work by the end of outage B211RI. In addition, work under this project not related to the NP.C commitment wiB continue past the commitment date,into outage Bl10RI. A ! ) PID B0014A Category I l
I ne remaining scope in PM 91-011 was redewed by a Structural Review Team including personnel from Operations, Tech Support, Maintenance, NED and the Projects Group. Twenty five items require structural repair. Fourteen other supports can be accepted as-is, although ensung design calculations will ( require revision to accept as-is. PM 91-011 will be performed on-line in 1994 and during B110RI. - Remarung scope in PM 93-030 will be performed on-line in Unit Two during 1994. III. CONCLUSION This pmject assures continued compliance with regulatory requurments, prunarily STSI seismic support requirements. %e impacts on safety and plant system availability warrant implementation. IV. STATUS Commitment to complete Unit 2 and Unit common STSI supports per letter NIS93-136 was met during outa5e B211R1. Structural repairs will be performed on-line in 1994 and during outage B110R1 in 1995. PM 93-029 Approved forimplementation in 1994 - 1995. PM 91-011 Approved forimplementation in 1994-1995. PM 91-041 Implementation complete, mod doseout in 1994. PM 93-030 Approved for implementation in 1994 and dosecut in 1995. PM 92-082 Implementation complete, mod doseout in 1994. PM 92-083 Implementation complete, mod dosecut in 1994.
- 4. TARGET COMPLETION PM 93-029 December 31,1995 PM 91011 December 31,1995 PM 91-041 December 30,19M PM 93-030 December 31,1995 PM 92-082 December 31,1994 PM 92-083 December 31,1994 PROJECT MANAGER CHUCK RAINES PID B0014A O.
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M l l 1 6 y PIPING DESIGN TURNOVER PROGRAM ' i I l I. PURPOSE AND SCOPE . Some BSEP design drawmgs and calculations have been found to differ from the as-built condition of ' piping and related equipment in the plant. One of the primary causes of this problem is incomplete- ; turnover of detailed design information from the architect / engineer, ne Piping Design Turnover Program
' is locateg, packaging, and turnmg over to CP&L the UE&C pipe stress and pipe support calculations for - l Brunswick. CP&L is reviewing the calculations that are safety related and, where needed, upgradmg :
them. Where safety related design calculations are missing, they are being recreated. Also, some plant walk-downs are being conducted where needed to verify drawing information. i ne Piping Design Turnover Program will result in over 5000 revised piping-support drawags. In . ! addition, over 400 piping isometric drawags and supporting calentarian packages will be provided. The BNP Piping Design Control organientian. will integrate data into existing plant information sysicas (NRCS ; and EDBS) and will establish procedures to assure contmuod integrity o' design information. Following ; project completion, an~ audit will be conducted to verify the consistency among related drawings, -l calculations, and the as-built plant configuranon. Also the admmierrative procedures for plant modifications t will be updated to ensure continued mameenance of design basis documents. !
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H. EVALUATION Schedule Index: 11 - his project has resulted in the changeout or modification of over 400 piping i supports for safety systems. Of the 400 piping supports affected, about 200 involve the RHR system, j including RHR service water. In most cases, these piping supports were adequate for their basic function, ; but they were not fully qualified. Thus, the actual impact of this project on RHR and service water system i _ performance is considered to be low. However, because the RHR and service water system are high j contributors to theoretical core melt Aq y, a nuclear safety scaling factor of 0.2 is assigned (0.2 x 32). q If design basis issues are not resolved, unit availability concerns could arise (0.2 x 12). Some personnel ! radiation exposure is incurred during walkdowns (0.2 x 9). De potential for increased efficiency in future desi n activities results in a significant plant enhance =e= (0.5 x g). j Economic Aspects: De compiled design darnments will improve efficiency in developing future modifications and in conducting operability evaluations. Imag term .. .' - .. of the affected piping . design bases will be incorporated as a routme part of plant work that is already funded and staffed. The related data base management and design control activities are also already part of the routine plant work and staffmg and are adequate to support long term requirements. Derefore, the net long term impact of this project is a reduction in BNP costs. Related Standards: De applicable Work Management Policy for this project concerns design documentation. Other Considerations: Dis type of documentation problem resulted in NRC IEB 79-14. Final closcout of IEB 79-14 issues and resolution of NCR S-86-021 are dependent on this project. The service water lubricating water and service water diesel generator supply and return systems are not within the scope of the NRC commitment. These systems are currently being modified and/or replaced; consequently, the associated design packages, prepared by CP&L, contain current design documentation.
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PID B0018A Category I 4 l l
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III. -CONCLUSION
" Ibis project will proceed as scheduled due to the importance of having accurate design basis documentation ,
readily available. IV. STATUS This project has been approved by management. V. TARGET COMPLETION December 1994. PROJECT MANAGER SUSAN VANN PID B0018A O
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. l DESIGN BASIS RECONSTITUTION -
I. PURPOSE AND SCOPE -
. CP&L has undertaken the Brunswick Design Basis , Reconstitution Project to structure the design bases and calculations / analyses applicable to the plant systems and generic issues. De project includes the collection ' ;l
' and consolidation of design basis infonnation from the ArchitectC - (UE&C), the NSSS supplier i (General Electric), and from CP&L licensing, regulatory compliance. and engineering Ales. His ;
compilation includes the review and turnover of applicable historical wm--- '-- and calculations
, .j related to system / component design and regulatory requirements or connutments. De scope of this effort includes captunng data for Brunswick systems and genenc issues. All information will be sorted and stored in a computer database to enhance retrievability and control. De NRC has shown a high level of ' i interest in plant design basis reconstitution. His project meets the guidance of NUMARC 90-12, ' Design j Basis Program Guidelines." De 1992 NRC policy statement on design basis information indicates that a -l' generic letter will be issued mquesung a description of all licensee programs and that the SALP process will be modified to include ===e== ment of licensee design basis programs. The current CP&L program is ;
sufficient to meet all anticipated regulatory standards. Additionally, design basis control will be necessary to maintam the option of plant life artensian beyond the cunent hosese expiratios through the license renewal process. De project is expected to uncover potential discapancies which nest be evaluated. A programmatic approach to identify, confirm, prioritise, track, and close out each b.gf has been ! developed. Once completed, the design basis for safety related systems, structures and components at - -l Brunswick will be clearly established, casily retnevable, and fully controlled. ; i II. EVALUATION l Schedule Index: 24 - This project will resolve any L.,, ;es that arise as a result of the design basis I reconstitution effort. Since the PRA model directly depends on the quality of plant design stacumentarian , - l such discrepancies could invalidate important PRA assumptions and could impact calculated core damage l frequency. Plant modifications to resolve A des are expected to represent a moderate improvement 'l to safety (0.5 x 32). De project should significantly reduce research time on modifications and ; engineenng evaluations and analyses. De identification and disposition of potential A.,, sies also ; represents a plant enhancement (1.0 x 8). i Economic Aspects: Once the upgrades of this project are complete, maintenance of design bases will be :) part of routine and are not considered as a pan of this project. Ongoing resource savings are expected in j the future, due to reduction of time spent on modification and engineenng evaluation preparation. Related Standards: The applicable Work Management Policy is that for design documentation. Other Considerations: Writing of design basis documents was completed as scheduled in December 1993. Validation is expected to be completed by December 1995. Resolution of discrepancies is expected to continue through 1995 and 1996. De original NRC commitment date to complete the Brunswick Design l Basis Reconstitution Project was December 1993; however, after further defining the work scope, the I completion date was extended to December 1996. AC system and DC system calculation reconstitution ! efforts are covered in projects 05644A and G0017A, respectively. III. CONCLUSION
~l Efforts on this project will continue due to the importance of accurate and useful design basis I documentation. l PID B0019A j Category 1 )
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IV. STATUS This project is approved by management. O V. TARGET COMPLbTION Regulatory commined validations December 1995. Total project December 1996. PROJECT MANAGER PAUL CAFALLERA PID B0019A i Oll l, O
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MISCELLANESUS' STEEL VERIFICATICN AND REPAIRS.- q
-L ' PURPOSE AND SCOPE ].
De purpose of prgect B0060D/E'is to make necessary repairs or modfications, if any, to BNP M; r-II-= Steel as a nsult of engineering evaluations in project BNT 622 BNP Plant Building Steet. j . . l In early 1992, to address issues in the Notice of Deviation in NRC T& Report (IR) 92-14, CP&L1 expanded the scope of rrancellmeous steel evalumnons to include drywell platform steel hac=== of sinalarities _ with - - >!- =i steel design and construenon. %e =-,= E' evaluation esort is closely tied to this l project and is described separately under project BNT-622, BNP Plant Building Steel. l 1 IL ' EVALUATION l Schedule Index: 3 No nuclear safety problems have been found to date and none are expeted. -i Nevertheless, even though the likelihood that a seurucally-induced failure of a structural member could'. j damage a safety related system is wry amate, such a failure would dect a safety funcuan of high 1 i 1..p r.cc (0.2 x 32). %e added con 6dence in structural meel demgn magpns and in the currency of - design drawings and enleal=% and the contribution these make to the edicaency of the r--:9- =-'= ' - process asy.wi .; a gibci..; plant ' =------- -t (0.5 x 8). His project is not expected to afect unit . i availability or tanit capacity. l Economic Aspects: This project is required to provide the assurance that allaa aa steel meets the. : demgn requiremenu in the updated FSAR. Once --- ;i '. this project will nault in ne#ble continued l financial costs. ;
'l Related Standants: %e Work M.r%wt Policy for matenal condition applies to this project. j III. CONCLUSION ;
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Completion of B0060D/E is d.,a ad at on the BNT-622 evalumnons. Le Phase II walkdowns have been l completed. No operability issues were id-ah %e BNT-622 Phase II evaluations will start in late 1994 and complete by 12/31/95. Repain to miscellaneous steel - ;--- -ts as a result ofBNT-622 evaluations are not anticipated. .If npairs are deemed -ry, B0060D/E will retum to PRG for funding consideration. IV. STATUS PM 92-076 Unit 1, Project to return to Project Review Gmup when scope for BNT-622 is defmed. PM 92-077 Unit 2, Project to return to Project Review Group when scope for BNT-622 is defined. V. TARGET COMPLETION PM 92-076 December 31,1995. PM 92-077 December 31,1995. I PROJECT MANAGER CHUCK RAINES PID B0060A ) Category I l 1
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G BNP PLANT BUILDING STEEL ( ) I. PURPOSE AND SCOPE he purpose of the BNP plant building steel venScation program is to dose out the Notice of Deviation in NRC Inspection Report (IR) 92-14. Iicensee Event Report (LER) 188-35 and Unresolved Item (UI) 89-18 02 identined an oventress condition in one beam in each Reactor Building. In response, in 1990, CP&L began walkdowns of miscellaneous steel in the Reactor Building outside the drywell, under project B0060A, As. Built Veri 5 cation of Miscellaneous Steel. In early 1992, in response to IR 92-14, CP&L expanded the program to indude drywell platfonn steel (because of amilarities with Weheous steel desgn and construction); this program is being accomplished in two phases. %e Phase I Pmgram consists of mgkag walkdowns of miscellaneous steel inside the drywell, in the reactor building, and outide the drywell to categorize each steel member and connection as adequate or requinng funher action. Rose requinng further action were evaluated using restart criteria. Le Phase II Progrr.n consists of analysis of representative platform sections in the drywell and in the Reactor Building cr .tside the drywell using U13AR criteria, documentation and veri 6 cation ofmiscellaneous stmenu21 steel. 7 tie walkdowns associated with Phase I and the majority of Phase II have been completed. Walkdowns and analyses performed to date have shown that, depa: occasional minor construction variances, construction of miscellaneous steel in the Reactor Building ..utside the drywell is generally of good quality and none of the variances advenely affect safe plant ope ation. 'In the event that repain or modi 6 cations are required, such work will be completed under the scope of pmjects B0060D and B0060F. The success criteria for this program are that the structural steel affected by the pmgram will satisfy the design requurments of the 1978 Edition of the AISC Specification for the Design, Fabrication, and Erection of Structural Steel Buildings, conastent with the Bninswick Plant Updated FSAR and that there will be
; greater assurance that plant drawings accurately reflect current as-built conditions.
(O II. EVALUATION Schedule Index: (-13) - No nuclear safety problems have been found to date and none are expected; the purpose of this program is to verify that building steel meets design requirements in the updated FSAR. Nevertheless, even though the 11elAuvi that a seismically-induced failure of a stmetural member could damaSe a safety.related system is very remote, such a failure could have an impact on a safety system function of high importance (0.2 x 32). He walkdowns necessary to implement the program will greatly increase the chance that a worker could be injured due to a fall or falling objects (-0.5 x 29) and will result 4 in significant worker dose even though steps (such as the use of photographs) have been taken to rnirdmize l the accumulated dose for the project effort (-l x 9). he added conEdence in structural steel design margins and in the ctmency of design drawings and calculations, and the contribution these make to the ef5ciency of the modification pmcess, represent a moderate plant enhancement (0.5 x 8). Economic Aspects: his two-phase program has been undertaken to provide assurance that building steel meets design requirements in the updated FSAR. Once completed, this program will result in negligible continued financial costs. He updated drawings and calculations resulting from the program will make subsequent plant modifications, which relate to or interface with structural steel, easier and quicker to complete. Related Standards: he Work Management Policies for material condition and design documentation apply to this program. PID BNT622 Category I
DC VOLTAGE PROFILE STUDY L PURPOSE AND SCOPE , l Existing design basis calculations for the Brunswick DC electrical distribution system have been found,in ( } .some cases, to be unavailable or inadequate. The DC Voltage Profile Study has been undenaken to V establish current readily accessible DC electrical distribution system design basis calculations. Calculations : I to be provided include those to establish battery loading, DC distribution system voltage, battery charger sizing, DC system fault current and coordination, and DC system cable amperage capacity. The 1991 electrical distribution system functional inspection reaffirmed the need to upgrade or develop certain ; calculations which are a part of this project. Once complete, this project will document the capability of the present configuration and loading, and provide a basis to support future modifications and 10 CFR 50.59 safety evaluations. For a proposed change to the DC distribution system, documentation will be easily i accessible to demonstrate whether a proposed change to the DC distribution system will cause overloading ) of components. De ability to quickly and accurately respond to design basis issues which may arise during . an audit will be greatly enhanced. IL EVALUATION Schedule Index: 10 - Upgrade or development of design basis calculations is not expected to have a substantial effect on DC distribution system design or operation. However, the project includes additional calculations to analyze battery loading profiles. De results of these calculations could lead to procedural or hardware changes that would increase the plant's ability to withstand station blackout. A nuclear scaling factor of 0.2 is assigned because of this potential low impact on core damage frequency (0.2 x 32). His project should have no appreciable effect on personnel safety, unit availability, unit capacity, or ALARA, but should reduce research time on modifications and engineering evaluations and analyses (plant enhancement. 0.5 x 8). Economic Aspects: Once this project is completed, no continued costs are anticipated. Ongoing resource savings are expected in the future due to reduction of time spent on modification and engineering evaluation g preparation. Related Standards: he applicable Work Management Policy is design documentation. Other Considerations: The calculations being developed are a commitment to the NRC and presently either do not exist or are not in a usable form for the Brunswick units. He NRC commitment date for completing this project was rescheduled based on the need to perform additional, more detailed analyses for 2 of the 1I calculations. This project is now scheduled for completion at the end of December 1995. His project is related to B0019A, Design Basis Reconstitution. IIL CONCLUSION The DC Voltage Profile Study will proceed as scheduled to provide a basis for future modifications and safety evaluations of the DC electrical distribution system. IV. STATUS Of the 11 calculations,9 are scheduled for completion at the end of 1994. Preliminary calculational iterations have been performed on the 2 remaining calculations (Unit I and Unit 2 DC Voltage Drop Studies) and are scheduled for completion at the end of December 1995. V. TARGET COMPLETION December 1995. PROJECT MANAGER KEN KEY PID G0017A A)
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l PID G0017A Category I
INVESSEL CORE SPRAY PIPING REPAIR I. PURPOSE AND SCOPE Plant Mod 91-043 installed stainless steel brackets across the top and bottom of the Loop A Core Spmy (V) Tee-box to piping header. %e brackets were installed to provide strength to the headers in the event the existmg crack grows to a length that could causejoint failure. Seal welds are needed since the wetted crevice condition at the existing bracket welds could result in IGSCC of the welds. Exception number 1 to PM 91-043 was wntten to pedorm the following additional tasks:
- 1. Perfonn seal welds on brackets.
- 2. Pedonn liquid penetrant exammation of the welds.
II. EVALUATION In letter NLS 91303, CP&L provided the results of visual exanunations of the invessel core spray piping and spargen for Unit 2 performed during the Reload 9 outage (B210R1). nese inspections were . pedormed in accortlance with NRC Bulletin 8013, dated May 12,1980. His submittal also described i repairs of a crack indication on the north core spray line. He crack indication on the north com spray line was repaired by reinforcing the piping using underwater welding techniques to weld a bracket assembly to the core spray piping. He bracket assembly coven the cracked tee-box location and consists of an upper and lower bracket welded acros the piping arna and tee-box. He brackets provide full structural integrity of the piping, ewn if the crack indication were to grow l to 360 degrees. In addition, the bracket material and weld filler material are both resistant to Intergranular ! Stress Corrosion Cracking (IGSCC). Following the repair, a remote visual exammation of the bracket ; welds was pedarmed which assured the welds to be of acceptable quality for at least one egle of operation. ! Since a vessel drain down was not perfonned, a Liquid Penetrant (LP) exammation of the bracket welds , p could not be performed. )
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In the NLS 91-303 submittal, CP&L initially committed to pedonn an LP examination of the bracket assembly welds and application of seal welds to the bracket assemblies during Unit 2 reload outage B211R 1. The seal wekis are intended to clinunate the potential for crevice corrosion crackmg developing under the i brackets. In a Safety Evaluation dated January 14, 1994, it was concluded this modification would l maintain full structural integrity and support continued operability of the core spray line. With letters BSEP 93-0222 and BSEP 94-0042 CP&L has committed to complete the seal welds and liquid penetrant exanunations during Unit 2 Outage B212RI. j III. CONCLUSION Carohna Power & Light Company curnntly plans to exanune the exisung bracket assembly welds and seal weld the open ends of the brackets during the Unit 2 reload outage B212RI. The work is to be pedormed while the vesselis drained down during the B212R1 outage. ) l IV. STATUS I i Design to implement the seal welds and LP examination is scheduled for release April 1,1995. Implementation will be pedormed during outage B212RI. Project is implementation phase approved by Plant Review Group. V. TARGET COMPLETION May 1996. f) PROJECT MANAGER CHUCK RAINES V PID C0024A PID C0024A Category I
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x FEEDWATER SPARGER CRACKING ISSUE I. PURPOSE AND SCOPE The feedwater spargen are inspected in acconlance with NUREG-0619. Dese inspections monitor cracking in the nozzle blend radius inside the reactor vessel and cracking on the spargers themselves. Crackmg has been identified in l j both Units at the sparger flow holes and cirrufererntial welds. Additionally, the longitudinal seam weld on each Unit J 2 tee has han cracking identified. %e spargen are not safety related but could generate loose parts in the vessel. Lis project ongmally involved a replacement of spargers in both Units as well as the safe-ends, cladding on the blend radius, and a portion of piping m, the drywell. hw has re-evaluated the technical requurments for the sparger replacement and determined that a reasonable justification exists to support continued use of the spargers for the remauung design life of the Units. This plan will be presented to the NRC and consists of the followmg: If cra develops m the nozzle blend radius, the crack will be evaluated and repai:rd if necessary. Cracking in the spargen will be monitored in accordance with NUREG.0619 and repaired as necessary. Fogineenng Evaluations will be developed each RFO tojustify continued use of the spargen. If a repair is needed, contmgency plans will be developed and ; implemented in the appmpriate RFO. Unit I has three Inconel 82 welds on each of the four feedwater lines. Rese welds are m' spected in accordance with NUREG.0313. he origmal sparger replacement pmject would have removed these welds fmm the system and the contsponding inspection. Rese welds wdl remam m the augmented inspection pmgram and, if a crack develops, a weld overlay will be applied as a repair. II. EVALUATION BWR's have experienced crackmg in the nozzle blend radius and at the flow holes on the spargen. NUREG-0619 was issued recguiring liquid penetrant (LP) mspections of the blend radius at various frequencies depending on the configuration. Most utiht es have aced their spargen with a design that has top mounted flow nozzles. Also, dunng replacement the stainless steel clad in the blend radius was often removed. BNP has operated both units with the onginal spargen. Additionally, BNP ias modi 5ed the hydmgen injection system to pemut injection rates up to 100 V) SCFH. The affects of this higher rate on the undad surface had not been pmviously evaluated by GE. The first interference sparger designs, loose fit (installed at other plants), did not vide adequate protection against bypass leakage and lead to cracking. Unit 2 has a tight interference fit sparger. ie welded thermal sleeve to safe-end design, installed in Unit 1, pmvides bypass flow protection but intmduced a weld that could not be in-service inspected. This weld may be susceptible toIn ular Stress Conosion Crackmg (IGSCC) by the crevice corrosion mechanism But, no welded thermal sleeve to e-end spar 5ers designs have leaked or failed to date. Clad crackmg in the blend radius is initiated by high cyde thennal fatigue. %ermal stresses come fmm bypass leakage at the thennal sleeve to safe-end joint. Cold feedwater trickles on the lower portion of the blend radius oscillating side. to-side at 0.1 to 1.0 Hz. His altemating " hot" to " cold" fluid generates a surface stress which is sufficient to initiate and gmw cracks in the dadding approxunately 0.25" deep. At 0.25" deep the thennal induced stresses at the crack tip are sufficiently low such that crack pmpagation due to bypass leakage stops and cychng the RPV takes over. (Acconting to GE, the KKM plant in Sweden has operated with spargen sunilar to Unit 2 and has monitored leakage of approxunately 4 gpm since 1989; no cracking has developed m the blend radius dadding). Once a crack has developed, another mecharusm continues to grow the crack from the 0.25" depth. Vessel heat-up/ cool-down generates base metal stresses in the nozzle. %ese stresses are not sufficient to initiate a crack but are capable of drivmg existing cracks well into the base metal. The deepest crack reported by Utihties has been 1.5" induding the 3/8" daddmg thickness, Nine Mile Point 1 - 1976. (This crack was subsequently removed by grinding with no weld repair required). Removing the dadding exposes the carbon steel vessel material which has a higher coefficient of thermal conductivity and higher resistance to thermal fatigue. A second problem with the sparger designs is flow hole cracking During start-ups and dunng low feedwater flow conditions the coolant stratifies in the sparger. Colder feedwater lays in the bottom of the sparger while hot RPV PID G0029A Category I [m) v
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4 i r - ;4 DIESEL GENERATOR SERVICE WATER SUPPLY AND DISCHARGE PIPING REPLACEMENT
/ s I. PURPOSE AND SCOPE In onier to meet requirements resulting from NRC Generic letter 89-13, CP&L has undertaken a number j ofinitiatives .cdhg inspection and tesung of service water piping and a-q- =ts. He service water i lines for the diesel generatorjacket water heat exchangers have a history ofhigh maintenance due to piping ,
through-wall leaks. Rese leaks result from cement lining failure at weak spots or from emaion and , concsion of the piping. Ieaks, emded welds, and missing cement lining indicate that the piping is in a : degraded condition. De potential for this piping W- -Q inoperable is of signi6 cant concem because of ; the sinngent operability requirements for the diesel ger .; , which require service water for coohng ; during operation. In order to I = high ongoing maintenance costs, CP&L has chosen to undenake a major program to replace large portions of the service water system piping with new piping to unprove j resistance to salt water corrosion and bio.fouhng. i The purpose of this project is to replace the exisang cement-lined carbon steel serwce water piping to and from the diesel genemtorjacket water heat exchangers with copper. nickel piping. Also this pmject will thmtde service water flow to the diesels in order to balance Bow to other equipment cooled by the service water system. I Successful completion of the y.vya d. modi 6 cations would be evidenced by the absence of conosion and through-wall leaks in system piping and improved coohng water flow to other system loads. ! \ II. EVALUATION ; Schedule Index: 30 - Replacmg the service water piping reduces maintenance and unproves system l p reliability, thereby moderately impmving the availability of the sr 3mcy diesel generators. Thmtding of l
\'j the service water flow to the diesels ir.d.a ;dy increases the flow to other safety- related coolers and l I
components that are served by the service water system while maintauung a signi6 cant margm of coohng flow to the emergency diesel generators. De result is a moderately positive impact on nuclear safety (0.5 x 32). Impmved piping materials would reduce the maintenance required to maintain service water system availability and would prevent or mmuruze the potential for forced outages due to failures of the service . water system or inoperability of the sr swg diesel generators, resulting in a moderate impact on plant availability (0.5 x 12). Replacement of service water system piping would result in less frequent repair activities, more reliable system operation, and improved maintenance, providing a signi6 cant plant enhancement (1.0 x 8). Economic Aspects: Analyses show that no signi6 cant cost savings are achieved by pdu..u.ug the installation in a dual-unit outage. ne pmject reduces the probability of a forced dual-unit outage that might result due to service water unavailability impacting diesel generator operability. Long term costs will be reduced because improved piping materials will eliminate the ina.g cost ofinspection and repair ; caused by the deteriorating piping. .j Related Standards: The Work Management Policy on matenal condition is applicable to this pmject. Other Considentions: his project is an element of the Long Range Plan to significantly impmve the ! reliability and performance of the service water system. It is also consistent with the Emergency Diesel j Generator Enhancement Strategy goal to nunmuze out.of-service time and improve reliability. Installation l . must be perfonned during plant operation as well as over a series of outages. , l In letter NIS.92 136, CP&L documented commitments from a meeting with NRC on May 12,1992,and PID G0050J ;
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FUEL POOL GIRDER TEND' ON IN SERVICE INSPECTION
# I. PURPOSE AND SCOPE Each of the four spent fud pool girden contains twelve pain of post-tensioned tendons thst sene as pnmary tension reinfortement for the girden. His project resulted from an NRC inspection repon item that has been doned, but further work was initiated to address long tenn BNP inspection requirnnents for the fuel pool girden. Potential pmblem areas to be addressed indude:
- loss of pre-stress force of the fuel pool ginier tendons, !
- loss of grease from the tendon anchorage grease caps, and
- corrosion of girder tendons.
More specifically, this pmject is to enluate the long-term capacity of the girders as a result of the installation of high density fuel racks in the fuel pool, the effects of fuel pool water temperature on the material propenies of the tendon wires, the potential for corrosion, and the effects of cyclical loadtng De information previously available (i.e., design calculations, specifications, and industry literature) did not indicate that design margms were reduced or compromised; however, there are unknowns that could not be addressed by analyns. Nevertheless, it is feh that the important unknowns will not impact the design margm to current standards. At present, there is no inspection program for fuel pool girders. The scope of this pmject involves writing and implementing a specification and procedure to inspect a percentage of the tendon sample wires, samples of tendon lubricant, and visible areas of girder concrete. 1 Tendon sample wires will be tested and and analyzed for acceptability. Upon completion ofinspection and l ('~' testing, data analyns will be done. It is antidpated that a routine inspection and testing program with a (,)i periodicity of three to five yean will be put in place following the analysis. I l l This project will initially be considered successful when the fuel pool girder tendon inspection requirements have been identified in the short term and the immediate inspections and adjustments have been implemented. %e long term success of this project will be dependent on the ability of the inspection l program to contml the tendon material condition and to anticipate problems. II. EVALUATION Schedule Index: 16 - This inspection and tesung pmject is not expected to affect nuclear safety (0 x 32). I Without the inspection and testing to verify the design basis assumptions for the pool with high density storage racks, there may be personnel safety implications from the potential degradation of the fuel pool support girder strength (0.5 x 29). Also, since the original design assumptions could potentially be no longer appropriate and in need of correction, this project represents a plant enhancement (0.2 x 8). l Economic Aspects: his is no direct economic gain from this inspection and testmg program. The project expenditure is a charge for economic-loss risk redetion. If a degraded condition is found upon inspection and testmg, conecting the problem early could save many times the inspection and testing con by avoiding expensive repairs. Related Standanis: his project impacts Work Management Policies for material condition and for management oversight and corrective actions. O PID G0096A Casegory I
__ ~ O FEEDWATER SPARGER CRACKING ISSUE V I. PURPOSE AND SCOPE The feedwater en are inspected in accordance with NUREG-0619. These ins nonle blend us mside the reactor vessel and crackmg on the spargen Crackingthemselves.pections has been identified in monitor crac both Units at the sparger flow holes and circuferemtial welds. Additionally, the longitudinal seam weld on each Unit 2 tee has had crackm' g identified. The spargen are not safety related but could genente loose pans in the vessel. His project ongmally involved a replacement of spargen in both Units as well as the safe-ends, dadding on the bl radius, and a ponion of piping in the drywell. NED has re-evaluated the technical requirements for the spa replacement and determined that a reasonable justification exists to suppon continued use of the spargers remauung design life of the Units. his plan will be presented to the NRC and consists of the following: If crackmg develops m the nonle blend radius, the crack will be evaluated and repaired if necessary. Cracking in th be monitored in accordance with NUREG.0619 and repaired as necessary. Engineenng Evaluations wil each RFO tojustify continued use of the spargers. implemented in the appropriate RFO. If a repair is needed, contingency plans will be developed and Unit I has three Inconel 82 welds on each of the four feedwww lines. %ese welds are m' spected in accordance with NUREG-0313. The ongmal sparger replacement project would have removed these welds from the system an corresponding m' sp.ection. Rese welds will remam in the augmented impection progmm and, if a crack dev weld oveday will be applied as a repair. II. EVALUATION BWR's have experienced crackmg in the nozzle blend radius and at the flow holes on the spargen. NUREG-0619 issued requinng configuration. liquidhave Most utihties penetrant (LP) inspections of the blend mdius at various frequencies dependmg on t replacement the stainless steel dad aced theirspargen with a design that has top mounted flow nonles. Also, during O original spargers. Additionally, BNP in the blend radius was often removed. BNP has opented both units with the SCFH. The affects of this higher rate on the undad surface had not been pressou He fint interference sparger designs, loose fit (installed at other p! ants), did not pro ide adequate pr bypass leakage and lead to cracking Unit 2 has a tight interference fit sparger. %e welded thermal sleeve to saf This weld may be susceptible to Intergrannular Stress Conosion Cmcdesign, mstalled i (IGSCC) by the crevice conosion mechanmn. But, no welded thermal sleeve to safe.end spargers desi6ns have 1. or failed to date. Clad cracking in the blend radius is initiated by high cycle thermal fatigue. %ermal stresses come fmm at the thermal sleeve to safe-endjoint. Cold feedwater trickles on the lower portion of the blend rudius oscul to-side at 0.1 to 1.0 Hz. This ahemating " hot" to " cold" fluid genemtes a surface stress which is sufficient to initiate and gmw cracks in the dadding approxunately 0.25" deep. At 0.25" deep the thennat induced suesses at the crack tip are sufficiently low such that crack propagation due to bypass leakage stops and cycling the RPV takes over of approxunately 4 gpm since 1989; no cracking has developed m the blend r Once a crack has developed, another mechamsm continues to grow the cmck from the 0.25" depth. Vessel hea up/ cool-down generates base metal stresses in the nozzle. These stresses are not sufficient to initiate a crack but are capable of dmmg existing cracks well into the base metal. ne deepest crack reponed by Utilities has been 1.5" I induding the 3/8" cladding thickness, Nine Mile Point 1 - 1976. (This crack was subsequently removed by grindm no weld repair required). Removing the cladding exposes the carbon steel vessel material which has a hig of thermal conducuvity and higher resistance to thermal fatigue. A second problem with the sparger designs is flow hole aucking. During stan-ups and dunng low feedwater flow conditions the coolant stratifies m the sparger. Calder feedwater lays in the bottom of the sparger while hot RPV PID G0029A Category I E
B i I coolant flows over the outside of the sp r. m %e thermal the holes stresses and exhibit a jagged at tha path. sideSevem!drilled d flow utilities ted flow holes have is experi and gmw cracks. %e cmcks are radialflow hole cracking. %e practice at othe nozzi ij ti n rates on the nozzle blend d a concern has recendy been mised with regards to the elevated hy rogen n ec o bstly,if radius the cladding is removed. Plants which have removed cladding or w operated at myection rates of 100 SCFH jd and erosion in this an:a has notent, determined the potential for erosion /cormsion and, using engineenng u gem muAhg life of the plant. h f ration of the Units Schedule inder 11 - Evaluating and repainng the feedwater spargers will not affect t e sa (0 x 32). This project is not a plant enh=r ment in that maintenance and inspection 12). Radianon dose fmm replacement will be added or removed (0 x 8). %ere is a direct benefit to unit ava a is expected to avoid up to a 12 day critical path extension for each Unit (0.5 xid d bu was esumated to be 226 man-Rem. Ein exposure will be avo e approximately 80 man-Rem, partially offsets the benefit l (0.5ill be x 9). incuned when weld Fronomic Asocets: - Maintenance and inspection costs will remam as-is. Additiona costs wthe ovedays or sparger repairs are required. Dis will be more than offset ~oactive waste will not replacements,appmxunatelytenfold. Additionally,alargevolumeof pipe, safe-ends, spargers, and equipment). a refueling outage. Development of altemate O. ther Considerations: - he repairs can only be implemented dLP ' uce the estimated dose exp on the ID. te ection techniques for the nozzle blend radius may i significantly' id lines.
%e NRC will evaluate the technical merit of this appmach to NUREG.0619 an BNP commitment to replace Unit 2 spargers must be revised.
III. CONCLUSION fd zzles will-Sufficient technicaljustification exists which demonstrates that cracking in the bl both Units with the not exceed desip margms for the rematrung life of Unit 1 or Unit 82 exisang feedwater spargen does not affecti theh safe operation of the plants or systems l ement. exposure can be avoided and radwaste trununized by not perform ng t e rep ac IV. STATUS klength The material condition of the spargers h has been evaluated in the previou h ID. NED will develop and present to f were noted at the flow holes,f and i the ctrtumferential cracks s owe nn the NRC inJanuary 1995 the technical basis for not per onn ng t e b 1994. This Development of the weld overlay design f ll and plant modification for Un mspecuon, evaluation, and repair as needed approach, as opposed to u sparger r the PRG for both Units. V. TARGET COMPLETION Unit 1, Outage BillRI i RFO's. Unit 2, Outage B212RI Future repairs to the spargen and weld ovedays will be addressed as eme PROJECT MANAGER PID G0029A CHUCK RAINES e
~ '
. . __ _, ~. . _ . -- . . ..
DD '
;w LDIESEL GENERATOR SERVICE WATER SUPPLY AND DISCHARGE PIPING REPLACEMENT E L- PURPOSE AND SCOPE In iader to meet requirements resulting fmm NRC Generic letter 89-13, CP&L has undertaken a number ofinitiatives .vur., inspection and testing of service water piping and --;-----ts. He service water.-
lines for the diesel p_.wrjacket water heat rol.r.r . have a history ofhigh maintenance due to piping i through-wall leaks. Dese leaks result frum cement lining failure at weak spots or from eromon and-conusion of the piping. Izaks, emded welds, and mining cement lining indicate that the piping is in a degraded condition. %e potential for tMs piping l- <c- - - inoperable is of-(, ht concem because of the stnngent operability requirements for the diesel generators, wiuch require service water for coohng during operation. In order to " -- = high ongoing maintenance costs, CP&L has chosen to undertake ; J a major progmm to replace large portions of the service water system piping with new piping to improve resistance to salt water corrosion and bio.fouhng.
%e purpose of this pmject is to seplace the existing cement-lined carbon steel service water piping to and from the diesel generatorjacket water heat exchangers with copper. nickel piping. Also this project will thmtde service water flow to the diesels in order to balance flow to other equipment cooled by the service water system.
Successful completion of the ymyo.ed modihcations would be evidenced by the absence of conesion and through-wall leaks in system piping and improved coohng water flow to other system loads. IL EVALUATION Schedule Index: 30 - Replaang the service water piping reduces maintenance and improves system q reliability, thereby medm.;dy improving the availability of the cam mcy diesel gcr.e.w. nrotthng of Q the service water flow to the diesels moderately increases the flow to other safety related coolers and components that are served by the service water system while maintairung a 45 ..;f.cr.i.t margin of coohng flow to the ea~emcy diesel ger %e result is a moderately positive impact on nuclear safety (0.5 x 32). Improved piping materials would reduce the maintenance required to maintain service water system avadability and would prevent or nurumize the potential for forced outages due to failures of the service water system or inoperability of the m.~.mcy diesel gccm. , resulting in a moderate impact on plant avadability (0.5 x 12). Repl-nent of service water system piping would result in les frequent repair activities, more reliable system operation, and improved maintenance, providing a_ significant plant ' enhancement (1.0 x 8). i Economic Aspects: Analyses show that no significant cost savings are achieved by perim. .g the I installation in a dual-unit outage. He project reduces the probability of a forced dual-unit outage that might result due to service water unavailability irr.ps.cdr.g diesel 8 enerator operability. I.ong term costs will l be reduced because irrproved piping materials will eliminate the increanng cost ofinspection and repair caused by the deteriorating piping. l I Related Standards: He Work Management Policy on material condition is applicable to this project. I Other Considerations: his project is an element of the I.ong Range Plan to significantly improve the i reliability and performance of the service water system. It is aho consistent with the Emergency Diesel { Generator Enhancement Str3tegy goal to nurumize out of-service time and improve reliability. Installation ; must be performed during plant opemtion as well as over a series of outages. In letter NLS-92-136, CP&L documented commitments fmm a meeting with NRC on May 12,1992,and PID G0050J j Casegory I- ] I n
l answered questions from an NRC letter dated April 27,1992. Commitment number 15 from enclosure 4 of NIS-92-136 was given in response to the NRC question. III. CONCLUSION To meet established commitments, this project will be completed as scheduled. 'Ihis project is an element of the Iaig Range Plan for the service water system and is connstent with the Emergency Diesel Generator Fnbncement Strrq goals. IV. STATUS
'Ihis project has been implementaticxi phue approved by the Plant Review Group. Unit I and Unit 2 supply piping and valves were tied into D/G 3 and D/G 4 in B211RI. Tie-ins to D/G 1 and D/G 2 will be completed by B1IORI. Design Engineenng has committed the approval of 91-072 by 12/94.
V. TARGET COMPLETION Plant Mod 91-070 - December 1995 Plant Mod 91071 - December 1995 Plant Mod 91-072 -June 1997 PROJECTT MGR. CHRIS HUGHES PID G0050J O e
e FUEL J"OOL GIRDER TENDON IN-SERVICE INSPECTION l
\ j I. PURPOSE AND SCOPE Each of the four spent fuel pool girden contains twelve pairs of post-tensioned tendons that serve as primary tension reinforcement for the girden. His project resulted from an NRC inspection report item that has been dosed, but further work was initiated to address long term BNP inspection requirements for the fuel pool girders. Potential problem areas to be addressed indude:
- loss of pre-stress force of the fuel pool girder tendons,
- loss of grease from the tendon anchorage grease caps, and
- conosion of girder tendons.
More specifically, this project is to evaluate the long-terrn capacity of the girders as a result of the installation of high density fuel racks in the fuel pool, the effects of fuel pool water temperature on the material properties of the tendon wires, the potential for conosion, and the effects of cyclical loadmg The , information previously available (i.e., design calculations, specifications, and industry literature) did not indicate that design marpns were reduced or compuuumi, howeser, there are unknowns that could not be addrersed by analysis. Nevertheless, it is felt that the important unknowns will not impact the design marpn to current standards. At present, there is no inspection program for fuel pool girders. He scope of this project involves writing and implementing a specification and procedure to inpect a , percentage of the tendon sample wires, samples of tendon lubricant, and visible areas of ginier concrete. Tendon sample wires will be tested and and analyzed for acceptabdity. Upon completion ofinspection and testmg, data analysis will be done. It is anticipated that a routine inspection and testmg program with a Q) (_ periodicity of three to five years will be put in place following the analysis. This project willinitially be considered successful when the fuel pool girder tendon inspection requirements have been identified in the short term and the unmediate inspections and adjustments have been implemented. The long term success of this project will be dependent on the ability of the inspection program to contml the tendon material condition and to anticipate problems. II. EVALUATION Schedule Index: 16 - This inspection and testmg project is not expected to affect nuclear safety (0 x 32). Without the inspection and testing to verify the design basis assumptions for the pool with high density storage racks, there may be personnel safety implications fmm the potential degradation of the fuel pool support girder strength (0.5 x 29). Also, since the origuul design assumptions could potentially be no longer appmpriate and in need of correction, this project represents a plant enhancement (0.2 x 8k Economic Aspects: This is no direct economic gain fmm this inspection and testing program. He project expenditure is a charge for economic-loss risk reduction. If a degraded condition is found upon inspection and testmg, correcting the problem early could save many times the inspection and testing cost by avoiding expensive repain. Related Standards: nis project impacts Work Mmagement Policies for material condition and for management ovenight and conective actions. () PID G00PV. Category .
Other Considerations: The enginal NRC commitment date for completion of this project, December 31, . 1986, was not met. The effort is scheduled for completion by December 31,1995. III. CONCLUSION Because this project yields a signi6 cant benefit in economic-loss risk reduction, it will be accomplished as scheduled. IV. STATUS Inspections are currently in progras and are scheduled to complete in 1994. Sample expansions have extended the implementation schedule completion. This in tum will cause the vendon final report to delay until February 1995. V. TARGET COMPLETION February 1995. l i k PROJECT MGR. CHRIS HUGHES PID G0096A l 9 i O l
'k
. PUR OSE AND CO E Thennal hydraulic instability oscillations have been detected at some BWRs, potentially causing core local thermal limits to be exceeded for short durations. As a result, there is some potential of localized fuel j damage under some conditions if this phenomenon is not adequately controlled. De purpose of this project ']
is to increase safety margins relative to BWR thermal hydraulic instability by implementing.the BWR l Owner's Group (BWROG) Stability Committee's enhanced option'lA solution. Generic-modification j technical development and the associated licensing of the modification are accomplished through the BWROG and GE. Development and licensing specific to BNP will be completed under this project, which , will eventually involve detailed engineering, material procurement, and installation. De success criterion ; for this project is that the modification and implementation adequately address the concerns regarding thermal hydraulic instability margins such that the risk of fuel damage during future operations is r minimized, t II. EVALUATION Schedule Index: 13 - A nuclear safety scaling factor of 0.2 has been selected based on the design alternatives under consideration (0.2 x 32). nis project is also a plant enhancement in that it is expected , I to help operators manage plant conditions more effectively when the plant is operating in some configurations. His improved control will help operators avoid inadvertent entry into the unstable thermal [ hydraulic region, thus avoiding unknown localized core conditions and minimizing the potential for unit - i shutdowns to investigate (0.2 x 12). f Economic Aspects: Following project completion, routine maintenance costs wili tikely increase. However, l p the project and continuing increased rnaintenance costs will be somewhat offset by the reduced potential ! ( for shutdows.s due to thermal hydraulic instabilit'j. 1 i Related Standards: This project impacts the Work Management Policies on material condition and operating l parameters. Other Considerations: NRC issued Generic Letter 94-001, which required all BWR Owners to install
- hardware modifications to address thermal hydraulic instabilities. CP&L has committed, in a September 9,1994 respoonse, to the NRC that we willinstall the BWROG enhanced option IA solution by the 1996 - ,
refueling outages. l III. CONCLUSION CP&L has issued a purchase order to General Electric for the development of the enhanced option lA l hardware. General Electric is currently building the proto-type hardware and is proceeding with licensing the hardware with the NRC. His project will proceed as planned assuming GE licensing and product development remains on schedule. , b PID COIO5A Category I
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i i IV. STATUS G, Project has been Design phase approved by the Plant Review Group. V. TARGET COMPLETION December 1997 PROJECT MANAGER CRAIG MARCH PID G0105A 1 1 l l
- O1 1 i
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ELECTRICAL DISTRIBUTION SYSTEM ADEQUACY:~GDC-17 I. PURPOSE AND SCOPE As pan of the Integrated Action Plan (IAP) that responded to the NRC Diagnostic Evaluation Team (DET) report of September 1939. Item Di pmvided for a rt< valuation of the Bmnswick electrical distribution system for comphance with 10 CFR 50, Appendix A, General Design Criterion 17 (GDC-17). This criterion requires that the plant emergency systems be able to respond to a loss of coolant accident and a coincident loss of all on site sources of AC power by having one source of off site electrical power immediately available. Also required is a second source of off site power that would be avadable in time to preclude exceeding fuel thermal limits. For Brunnvick, this first source of off site power to each unit is pmvided through the respective startup stuohary transfonner (SAT). The second sourte of off site power is provided by back feeding thmugh the unit auxiliary transformer (UAT), which takes several hours to accomplish. BNP and the NRC have agreed that BNP should enhance the off-site electrical distribution system to meet the current interpretation of GDC-17. This enhancement requires a faster way of pmviding the second off site source if needed. In addition to GDC17 comphance, additional concems being addressed for the AC electrical distribution system include long term adequacy of switchyard voltage to meet emergency bus voltage requuements.. Also the non-segregated bus ducts for each unit's existing SAT Y-windings will be upgnded to meet curnnt system ampacity requurments. Successful completion of G0110A will result in electrical distribution system design ahematives that meet the cunent interpretation of GDG17. IL EVALUATION () The study has resulted in three pmjects for each Unit, nowin various phases of design and implementation. The three pmjects are; the replacement of the SAT-Y Wmding non segregated bus duct with higher ampacity equipment, the installation of the Generator No lead Disconnect Switches to enhance the electrical dismbution system to meet the cuntnt requuements of GDG17 and the installation of Voltage Regulators to control the E Bus Voltage Level under conditions of heavy Grid load. IIL CONCLUSION The studies have resulted in the following actions: A. Installation of the Non Segregated Bus Duct in 1994 (Unit 2) and 1995 (Unit 1). B. Design is in progress for the Generstor No Ioad Disconnect Switch for installation in 1995 for Unit I and 1996 for Unit 2. This installation includes logic changes to simplify the prtx:ess of moving into UAT backfeed. *Ihis work will result in an enhanced electrical distribution system that meets the cunent interpretations of GDG17. C. Authorization has been approved to Design Voltage Regulators to control E Bus Voltage levels. Installation completion is forecast in 1997 (Unit 2) and 1998 (Unit 1) to conform with the system load forecast. This addn:sses the issue of the long tenn adequacy of Switchyard Voltage to meet E bus voltage requirements. PID G0110A \s Category I l
IV. STATUS The parts of this overall project are in various stages of app:mst tlutragh the Plant Review Group. V. TARGET COMPLETION Unit 2 Non Seg Bus Duet Replacement . Complete PCN G0110C 1994 1995 Unit 1 Non Seg Bus Duct Replacement PCN G0110B PCN G0110F 1995 Unit i Generator NLDS Unit 2 Generator NLDS PCN G0110G 1996 PCN G0110H 1998 Unit i Voltage Regulators 1997 Unit 2 Voltage Regulators PCN G01101 PROJECT MANAGER DAN MOORE PID G0110A O O
g3 UPGRADE SECURITY COMPUTER AND CARD READER V I. PURPOSE AND SCOPE i
. i Most of the equipment that makes up the Brunsmck security system has been in place since ongmal plant construction. Developments in the dengn and use of such equipment have evolved such that new l equipment and systems are avadable which prende higher reliability and would substantially reduce the types of failures cunently +-k. cad. %cse failures resultin potential secunty problems and require large ,
amounts of resources to -..ym z and correct. Additionally, the unique design of the Brunswick system is no longer fully supported by the ongmal vendor. Because fadures can affect large pomans of the secunty system and because troubleshooang must currently be done at the component level, failures can result in , delays for plant access. His represents an econonne risk should fadures occur dunng busy outage penods. Failures could require additional manrung of access points until r-y repass are effected. De upgraded system equipment -larw has been finahzed with system hardware and software demgn ' cunently in pmgress. Le Security Access Control system is being upgraded with .f == =t of the security host - ;-.w., consoles, multiplexors, card readers, and Hand Geometry readers. De upgrades I will conast of industry standard fault tolerant computers ----- M-=L- to distributed in4a multiplexors via high speed Eber optic communication links. A majonty of the Eber optic cables, planned a for and pulled during previous security = m=--s will be used for the d,l~ar commurucanon link. . s During installation of the multiplexors and the rnonitored devices, secunty --ep -- '-y guard pm-..d i will be required. New access cards will be prepared on the upgnded Polaroid Photo ID system for all badged pm a.ca. Additionally, trairung ofcomputer, rnaintenance, and security ym-c.a will be required. j t System performance, maintenance, spare parts avadabihty, and the reduced rehance on contractor software I
~
support will greatly impmve the security system. Following ia- 11-eand an initial trial period, reportable events due to failuns of the card reader access control subsystem should decrease to less than one third of , that of the three previous years. ; i II. EVALUATION Schedule Index: 8 - This project should have no apprecable effect on nuclear s4ety, perioru:el safety, unit availability, unit capacity, or ALARA. A high plant enhancement scahng factor is assigned because the expected reduction in security events and reduced numance to all badged ym.m.d will result in higher ! system reliability (1.0 x 8). l Economic Aspects: Increased security system reliability and reduced maintenance and prm.mm.at effort for individual repair and routine activities should result. Reliance on contractors for software support will be ehmmated. Security, technical, and computer software staff time, along with ir rgm.st attention ! following failure events, should be signi6cantly reduced. He nuisance impact of access control failures and ! security events on all badged pm~roa should decrease. Addition of the Hand Geometry function to this l i project will pmvide for significant cost reductions in Security labor, and enhance the access control functions of the overall system. ; 1 Related Standards: ne applicable Work Mana6ement Policy is material condition. j 1 Other Considerations: The schedule for completion of this project was provided to the NRC staffin an exemption request submitted onJuly 29,1994. PID G0140A Category I l 1
. - _ ,. ._ I
III. CONCLUSION Although the schedule index is relatively low, this project is important. Failure of the card reader control subsystern could have a major impact on plant access and require expensve and labor intensive compensatory action. IV. STATUS Project has been implementation phase approved by the Plant Review Group. Design is now scheduled for completion in Novernber 1994. The factory acceptance test for the new computer hardware / software system was completed in September 1994. Implementation is scheduled to begin in November 1994, followmg release and appmval of the desgn package. Fmal system acceptance and availability mra are scheduled for completion inJune 1995. V. TARGET COMPLETION June 1995 PROJECT MGR. LARRY WALTON PID G0140A O M O !
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l l 1
-l
% PROVIDE THERMAL OVERLOAD PROTECTION FOR AC MOTOR OPERATED VALVES '
).
I. PURPOSE AND SCOPE
- Thermal owedoed proteccon for valve actuator motors addeses one part of the overaB program to upgrade j the opersoonal reliability a motor operated valves (MOV). 'Ihermal overloads are used to protect the actuator motors from ---ve electrical cunent, especinDy in the case where the MOV is stuck (either shut j or open) and the motor does not have enough pcmer to overcome the pmblern. Wahaut thermal owedoed pmiection, when the valve is stuck, the motor starener cumans remam high, severely damagmg the moeor wmdings and rnalung manual operanon of the valve the only opman.
'The basis for not using thermal overload prosecnon was the - , = that the use af pmeetz devices (such as thermal owedonds) having the capability to interrupt power to safety related wives would increase j the risk that the valves would not operate during accident condinons, assuming the proeectne devices ,
0 .u might malfuncnon and prevent valve opemnon. It was caa-le ed bener to let a motor destroy imelf while attempang to operate the valve. The cunent mdustry appmach and NRC guidance (NUREG l 1296, "Ihermal Overload 7,- d.r. for Beeme Motors on Safety Related Motor 4 perused Valves") is to r.asure that motor owedoed protecnon is set and maatamed in a manner that assures motorminding protection and, also, avomis spunous vahe operanon. 'Ihis appmach aBone resetang ofelecencal breakers _.: to sepa non the vahe afier the mndiaan e==ng I and thus, anows anadur attempt by operanng ;-. the smek vahe is w. 4. I e
'Ihis petgect is p.s. 4 to install themal owedoed protecnon for motor operated vahe AC motors and to -i replace motor contml cabinet breakers wluch haw reached their envuonmental q=14c=e== end dlife. j i
To support this propet, call =*eral engmeenng work is needed to asure setpoint --- -- y and breaker a L i . among the ayy.4. aly 125 MOVs per unit. Also, once the new setpouns are established, ,
, wealculanon of the .-rce.Lg torque wlues is required for each vahe actuator in ander to amure that .!
the vahe can be operated under au design conditions wnhaut cauung spurums thermal owedoed actuations. AB of the afected safety related MOVs and the -**d breakers were idenaGed using the Equipment . Data Base System, assuring coverage of all of the applicable safety e#- ; =^ Examples ofsystems afected l by this pmject mclude core spray (CSS), high pmmune coolant injecnon (HPCI), reactor core =Jaeion i i coohng (RCIC), reactor water cleanup (RWC), reactor buikhng clama<1 cochng water (RBOCW), standby gas treatment (SGT), main steam (MS), arel contamment atmospheric contml (CAC). q
'This project wiH be succe=#ul when the operational reliability of MO% improves and vahe actuator motors -l are no longer damaged under stuck-vahe (staBed-motor) conditions. l II. EVALUATION Schedule Indec 28. 'This project is drectly related to assunng the availability of several safety systems, including residual heat removal, semce water, main steam, core spray, high presure coolant injecnon, and ,
reactor core isolation coohng (0.5 x 32). Since it has been h...;..si that lack of owedoed protecnon has l pmbably resulted in lugher MOV motor faihue rates at BSEP, this condition has most likely i..Lwdy ; conmbuted to plant outages in the past. Consequently, unit availability is enh=aa <1 (0.5 x 12) through ! irw.i opemtional reliability of most of the safety related MOVs. Iikewise, this propet prtmdes potential i plant enhancements (0.5 x 8) by reducing the lewl of conective maintenance, post-maintenance testing, and ! MOV troubleshooting required for a larEe number of safety-related valws. 'This is paraculady imponant due to the high impact such work has on outages. Finally, although the project itself wiB require some additional ecym to radiation during its i...elsr.e.r.tation, reduced levels of MOV ;.--* , troubleshooting, and maintenance over the rest of the life of the plant are expected to compensate for this j (0.2 x 9). j PID M4121E C.s.g.ry I j 1 - _ .-- . . . . __ ~ . _ - . , _ - _ _ _-_ _ _ _ _ _ _
Economic Aspects: Impmved plant availability and fewer actuator motor replacements are expected to compensate for the cost of this project. No long tenn additional costs are anticipated as a result of this pmject for maintenance except mutine preventive maintenance. Related Standards nis project directly is related to the Work Management Policy for material condition. Other Considerations: ne remammg thermal overload work will be accomplished before the completion of outages B110R1 and B212R1 to fulfill CP&Ils comnutments to the NRC. Mso, this project is related to M01210, MOV Testing, wiuch is a long tenn effort and doer not directly impact the M0121E thermal overload work. III. CONCLUSION
%is pmject will be completed as scheduled during outages B110R1 and B212RI.
IV. STATUS The Unit I projects for Bl10R1 have been implementation phase approved by the Plant Review Group. Le Unit 2 projects will require implementation phase approval by the Plant Review Group for future outage scope (B212RI). Unit 1 Plant Modifications have been approved and work package plannmg is in Pmgress. V. TARCET COMPLETION B1IORI Gune 1995) B212RI Gune 1996) PROJECT MANAGER. LARRY WALTON PlD M0121E l l l l 1 0 l l
' MATERIAL CONDITION WALKDOWN . L l
I L PURPOSE AND SCOPE ne purpose of this project is to identify, categorize, and repair plant material discrepancies not being j addressed under other projects.' . Under this project, approrimanely 2000 discrepancies were identified .j during plant walkdowns. A list of detaded walkdown items in plant locations that are high radiation areas ' during plant operation (hot side) and a list of walkdown items in all other normally accessible areas (cold ~ ' side) have been developed. The plant matenal discrepancies on these lists have been further categotuod, and the appropnate corrective actio s vill be taken. De plant's Tachneal Support Group and the Nuclear ; Engineenns Dors i i have evaluated and categorized all of the walkdown items. De largest segment l ofitems is related to conduit and structural supports. Other Awes include mechamcal maintannare items, fire hazards, and housekeeping issues. Some of the A A can be resolved directly under j; the routine work request process. nose Ages requinns design and/or documentarwe changes are i being accomplished under this project or under other appropriate projects such as PID B0014A, Emergent i Structure Repair. De success criteria of this project are elevated inspection and matenal condition a standards for the plant. -1 IL EVALUATION ' a Schedule Index: 17 - Walkdowns have identified A r . des s that could affect plant safety-related systems. Some of the approxunately 2000 items may be operability concerns for safety-related systems. For example, some of the discrepancies are cable tray and conduit suppons for class IE systems. Also, . l feedwater heater support problems were identified during the walkdowns. Therefore, this project has a ; positive effect on nuclear safety (0.2 x 32). Dunng the w r.d.a ive walkdowns, industrial safety . deficiencies (including some fire hazards) were identified; correction of these will result in improved l personnel safety (0.2 x 29). Raising the standard of the piant's cory.J.a ive walkdown inspection ! program is an important contributor to upgradag and maintaining the matenal condition of the nuclear plant - a plant enhancement (0.5 x 8). Finally, performing the walkdowns will result in a person. rem j expenditure with no future person-rem savags projected (0.2 x 9). De net expected benefits of this :l program are not readily quantifiable. j Related Standards: The applicable Work h8= _ ^ Policies are those for management oversight and corrective actions, material condition, and h==%ing. { t Other Considerations: This project augments the periodic inspections required by Admmistrative , Instructions AI %, "DrywellInspection and PNSC Outage Prestanup Checklist Instruction," and AI 114, i
- Management Field Walkdowns."
i ID. CONCLUSION This project provides a process for identifying and resolving plant material discrepancies. This project was , initiated during the B108F9 and B210F6 outages and will continue until all identified walkdown work not ' covered by other projects is completed. IV. STATUS This project has been implementation phase approved by the Plant Review Group. V. TARGET COMPLETION December 1994.
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PROJECT MANAGER STUART BYRib PID P0057E , PID P0057E Category I I I l
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a A - _- -a&- , , n ---,- -s--4 a A _ _, 6 e i I t u 5 9 i I I h e e: 4 4 e I I h 4 h i t i e-r s l
CATEGORY 11 PROJECTS LISTING , 7 i
. PID COMMITMENT :
NUMBER PROJECT TITLE CATEGORY j i HVAC UPGRADE (FAIM #A0001666) 11 SIMULATOR CORE THERMAL UPGRADE (FAIM #10000454) 11 SIMULATOR INSTRUCTOR STATION (FAIM #10000453) 11 -
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TURBINE ROTOR REPLACEMENT (FAIM #10000621 & 10000623) 11
*01757A PROCESS COMPUTER REPLACEMENT 11 -
i' 02164A CORE THERMAL UPRATE 11 i
*02317A REPLACE SHAIT DRIVEN OIL PUMP POR REACTOR FEEDPUMP TURBINE % TIN MOTOR 11 ,
DRIVEN PUMP (S) 04830A - MAINTAIN THE BSEP ENVIRONMENTAL QUALIFICA110N PROGRAM II ;
'05983A BA1TERY ROOM ALARM INVESTIGATION 11
*06202A OFF-GAS DRAIN TANKS RESERVOIR 11 06729A DREDGE SPOILS DISPOSAL 11
*07148 A REPLAG HPCI, RCIC AND RPS TDPAZ INVER1ERS 11 !
t
*07208A REMOVE /REPLAG OBSOI.EIE BAILEY RECORDERS II ,
07627A EDG GOVERNOR REPLACEMEW 11 l l I
*07862A REPLAG LIGHTING AND COMMUNICATIONS UNINTERRUPTIBLE POWER SUPPLY 11
*12420A CONTROL BLDG HVAC CONDENSA1E DRAIN REPAIR II
*l3447A TURBINE UPGRADE II l
*13629A CONUtOL BLADE PINS AND ROLLERS REPLACEME!G !!
*13671 A ECCS SUCI10N STRAINERS 11
*13676A SUPPLEMENTAL SPENT PUEL POOL COOLING (PURCHASE OF EQUIPMENT) li f
*13695 A INCREASE MS!V ALLOWABLE LEAKAGE 11
*13863A 10CFR COMPLIANG - VEHICLE INTRUSION 11
'81401A FLOOR DRAIN FILTER RETROFIT 11 l
'84587A RADWASTE SAMPLING SYSTEM UPGRADE 11 j
*G0058A TURBINE UPRATE II
*G0180A 125/250 VDC BATTERY GROUND DETECT 10N IMPROVEMENTS II I
'G0193 A BNP REFRIGERANT REPLACEMENT II !
'G0249A TURUS LINER PRESERVA110N II .
*G0251 A HYDROGEN WATER CHEMIS11tY (9400377 ZINC INJECTION) II l
*M0066A REFUEL BRIDGE UPGRADE Il i
P0057B SERVIG WATER AND CIRCULA11NG WA1ER INTAKE AREA ENHANCEMENT 11 i
*R0123 A RECIRCULATING SYSTEM DECONTAMINATION 11 ,
i
*R0123M SPENT FUEL POOL COOLING ASSIST-PIPING & PENETRA110NS !! ;
- Indicates project change from August i. 4W4 update. h
" Category 11 Small Proje,ts hsted separately.
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$ HVAC UPGRADE I. ' PURPOSE AND SCOPE
'Ihere are currently numerous open work items for the heating, ventilation, and air conditioning (HVAC) {
systems at Bmaswick. Of these items, the highest priority work pertains to HVAC material upgrades in ( the Reactor Building and in the Control Building.' Noteworthy examples of material conditions requiring resolution under the scope of this project are listed below: Approximately 200 feet of Lx-vA in (100 feet in each Reactor Building) is corroded beyond repair. '! The corroded ductwork is located in the overhead area of the 20 feet elevation. This corrosion is caused t by continual corwi==non. This duct requires r=1-nt and insulation to preclude future l condensation and corrosion. Also, many of the HVAC duct supports are either bent, missing, or loose. l i The Control Building intake plenum base is corroded through wall in several places. The Control Building supply and return roll filters (sitewide) do not work properly and have to be '! manually advanced. Excessive leakage of unfiltered air occurs due to corroded media frames. 1 The Reactor Building supply fan vortex dampers are corroded and obsolete. 'Ihis corrosion has caused damper binding and has tripped HVAC. The supply fan discharge dampers have no rubber seals, therefore backflow through idle fan causes reverse rotation of fan blades and a possible fan breaker trip ; could result when the fan is started. j Successful completion of this project will result in increased HVAC system efficiency and reliability. l II. EVALUATION Schedule Index: 15 - Upgrading the material condition of HVAC systems at Brunswick will be a { significant plant enhancement (1.0 x 8). Concerning nuclear safety, HVAC systems are me.leled in the PRA. Failure of individual HVAC systems have the potential to fait plant systems. Individual system failures are generally not significant with respect to mitigation of accidents; however, the cumulative
]
effects of the degradation of HVAC systems could result in a negative effect on nuclear safety. It is, 1 therefore, judged that this project will result in an overall low positive effect on nuclear safety (0.2 x l 32). HVAC systems in general provide support functions for many plant systems. The inability to cool -l certain plant areas, particularly the Reactor Building, could result in a loss of unit generation. During 1 the summer months when the temperatures in the Reactor Building are elevated and a loss of Reactor - l Building ventilation occurs, a potential threat exists for a PCIS Group 1 isolation on high temperature in _j the MSIV pit. Additionally, cooling components for safety-related equipment (i.e., RHR Room Coolers) ' have O potential to place the plant in restrictive LCOs. Therefore, this project has a low positive impact on unit cvailability (0.2 x 12). This project would therefore result in a low negative scaling factor for .j ALARA t-0.2 x 9). I Economic Aspects: 'Ihe cost of this project will be offset by reduced long-term HVAC maintenance costs and longer, more reliable operation of systems cooled by these HVAC systems. Related Standards This project is primarily related to the Work Management Policy for material condition. This project will bring HVAC systems up to design conditions and ensure long-term reliability. O FAIM A0001666 Category II.
Other Consi(crations: There is an NRC commitment associated with a pordon of this project - to complete the development of DR 90-0143 related to vortex dampers in the Reactor Building by December 3L 1992. The DR will be completed on the committed schedule. IIL CONCLUSION Work is complete on the 200 feet of the reactor building duct work in one unit. Control building intake plenum is in implementation. Parts are on site. Roll filters are being replaced with pleated cartridge filters and is approximately 50% complete. The reactor building supply vortex and isolation dampers are being replaced. Design and procurement is complete. IV. STATUS
'Ihis project is implementation phase approved by the Plant Review Group.
V. TARGET COMPLETION December 1995. PROJECT MANAGER HOWARD LINDSEY O O '
5
- y. SIMULATOR INSTRUCTOR STATION / COMPUTER UPGRADE 4
;\ l r
L PURPOSE AND SCOPE t
' Replace the 8 year old Encore computer with a current technology SGI Challenge computer to improve simulator reliability. ;
Add 6 instructor stations / work stations to replace the 13 year old instructor station and provide independent t l means of development, testing, and instructing, without interfering with training on the main simulator. IL EVALUATION
'Ihe outdated simulator computer sy:: tem failures interrupt training and examinations f i
Increased training demand usage has resulted in limited accessibility for scenario development, maintenance l and certification testing. j III. CONCLUSION i An upgrade of the simulator computer to current technology, and the addition of extra instructor stations l will address the problems above plus provide other benefits: l A. Reduce reliance on contractor support i B. Potential for API reduction in 1995/1996 time frame ! C. New enhanced user-friendly instructor system will enable cross training of more instructors. IV. ' STATUS l Project has been approved for implementation by management. l Simulator outage is scheduled for November / December 1994 for testing. Final installation is scheduled for May 1995. j V. TARGET COMPLETION June 1995 PROJECT MANAGER WILLIAM GEISE PID FAIM 10000453 Category II
s SIMULATOR CORE-THERMAL MODEL UPGRADE l
.7 t
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. I. PURPOSE AND SCOPE 1
Replace the existing simulator core-thermal softwere model to improve training on core and vessel dynamics ! during start-up, transient, and accident conditions. , 4 , II. ' EVALUATION :
.i The current simulator core-thermal model was developed for the existing ENCORE computer. The j computation limitations of the ENCORE required a compsomise in simulation accuracy and computer execution time reqmrements. This limits the accuracy and degree of training on many core and thermal ,
conditions. III. CONCLUSION ,
'Ihe approved simulator computer upgrade to a current technology SGI Challenge computer gready reduces the required a,.i.y.vuJse mi execution time. 'Ihis permits an upgraded core-thermal model which improves training in several areas:
A. Nuclear instrumentation response during startup training; steady stste and transient response during simulation of accident conditions; containment and radiation monitoring system performance under i degraded core conditions; recirculation pump start transient and start logic failures; and provides for realistic demonstration of thermal stratification durmg low flow conditions. B. New capabilities have been added: Modeling of Baron stratification allows for demonstration of . EOP guidelines for boron injection during ATWS conditions; addition of recirculation pump and 3 jet pump cavitation; and permits modeling of individnal instrument reference legs allowing for l simulation of reference leg flashing, out-gassing, reference leg refill; and pressurization ofreference i leg with mis-operation of reference leg backfill system. l l IV. STATUS l Work in progress. Software integration will commence in December 1994; stand-alone testing in 1995 and installation in May 1995. , i V. TARGET COMPLETION j June 1995. . i PROJECT MANAGER WILLIAM GEISE PID l FAIM 10000454 Category II I i
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i TURBINE ROTOR REPLACEMENT I. PURPOSE AND SCOPE ne purpose of this project is to upgrade the turinne by replacmg the IP-A and IP.B monoblock rotors > on Unit I and LP-A on Unit 2. , II. EVALUATION ; He rotor replacement extends the life of the turbme and potentially reduces the turbine valve testmg ; frequency. De turbme upgrade is intended to improve the reliability and performance of the units. l III. CONCLUSION ! CP&L will install the monoblock rotors. A study of other turbine-related equipment upgndes is being perfonned under PID 13447A. { IV. STATUS i Unit 1 project is being prepared for implementation during outage B110Rl; Unit 2 is projected for ; implementation during outage B211RI. V. TARGET COMPLETION Unit 1 -July 1995 Unit 2 - December 1996 i PROJECT MANAGER DAN MOORE i PID 10000621 - Unit 1 10000623 - Unit 2 : i l i l l l I l FAIM I0000621 k I O FAIM I0000623 Category II l l
p , I b "' PROCESS COMPUTER REPLACEMENT I. PURPOSE AND SCOPE Bnnweck's hard 4010 process crmgmters are the oldest installed and fs ;L. g nector core monitanng computers in the Uruted States. %ey were dengned with technology which has become outdated and cannot be readdy supported by the manufacturer. Also, - - - training serwces and spare parts are no longer prowded by Hornwell Spare parts can be obtamed at this time from third party sources; ho=ver, appbm are mbject to '=rM= without nonce. Ahhough the many compmer outages
, have not yet :-;= W the -=>~i unit genersten, their frequency has been rising, mcmaang the probability of startup delays or shutdowns.
%e process computer's primary function, core is .; . , is -. .:f -h J--a on and hnnted by the enstmg PI software prowded only by General Electne Corporanon (GE). This soAware is less versatile and accurate than the vanery of software now being wntsen for DEC VAX (versus hard) computers. In addition, limitanons in fuel vendor h are caused by the core monitanng soAware being GFepecific and less Eri-e than other avadable soAware. These fuel wnder hastanons are conndemd to be a major disadvantage of the present system. In addition, as more complex fuel is used in the reactor core, it becomes ird 'y ddEcult to prechet the effeca of come power adjustments, ruulting in slower reactor startups and power adjustments than would be possible with a more capable system. He emstmg process computer system does not have -Erient capacity to - - - - - "- the upgraded soAware needed.
%e basic scope of the plant pmcess computer .-;' -- == (PPCR) project is to transfer the A e==
currently being pe.ifm..si. by the enstmg process computer to a system that has greater hardware / software capability, expansion e p.hm e y, rc.1, lief, and mamtamabibey. %e exmang pmcem --e funcoom will be upgraded to perform more advanced computing and monitoring using the latest computer graphic capabilities. De new hardware includes front-end data acquisition 4 :; =-; data links, high speed DEC network interfaces to existing VAX computers, additional VAX systems, special purpose interfaces for the existing plant data system, and new operator consoles. Only the ensang Hecard input / output (I/O)' cabinets will remam, serung as the interface bermen the plant sensors and the new data acquisition system. De new software includes the CPU's ep, .; g system licenses, data acxtuisition and data vahdation software, new core monitoring soAware, applications speedic software, and system ..,. . software that co u.stes and monitors the entire system. Engmeenng serwces to support this project include pmwding documentation, tesang,6..u.ea trauung, convenson planrnng, and project ..-+.gr.t. De testing and evaluation phase for the new system is extensive. After the new system's sp .;;oe has been adequately veri 6ed, the existing He.ard 4010 computer will be di e-~+~3 and removed using a phased approach. A long list of goals and success criteria have been a==hh=hed to confum the adequacy of the new system. Abandonment and/or removal of the Honeywell process -- ;--ats will be a major @=-_+ to indicate that lu.ymwnt goals are being satis 6ed. II. EVALUATION
. Schedule Index: 13 - De process computer replacement is considered a non-safety related =- ':"-cation.
Ahhough it can be argued that the equipment is not safety relata4 the dependence of Op, .;e.i, on the system output may have safety implications during operation. It is reasonable to pedict that the grapluc display benefits and predictive capability of the new system (especially as related to secondary plant process parameters) will reduce the frequency of secondary plant event sequence initiators (such as low condenser vacuum) relative to the frequency values considered in the PRA (0.2 x 32). Le reliability, avadability, and maintainability of the new system is expected to be much better than the previous system. As time goes on, the probability of unit downtime or startup delays mereases with the old system (0.2 x 12). Le PID 01757A Casegory II
ec,mputer replacement is viewed as a significant enhancement for the personnel who need to use it, resulting in a plant enhancement (0.5 x 8). Economic Aspects: he cunent 20 year old computer sptem can not last much longer without support from the vendor, so investment in a replacement is inevitable. he largest probable economic benefit is that the new system is much les likely to delay return to savice after a refueling outage because of process computer system failures. It has been enrim=+ dt hat such a failure would result in a one to seven day mcrease in startup time. Also important is that the new core monitanng software, which will not run on the old computer, will pemit CP&L to purchase fuel fnxn more than one nuclear fuel supplier, mhancing competitive pricing. Fmally, upon project completion,long-term system maintenance cons are expected to , be reduced somewhat due to the 6ad availabdity of spare parts. Related Standartis: his pmject is related to Work Mar +2nt Policies for material condition, operating parameters, and management oversght and conective action. The PPCR project will impmve the reliability, avadability, and maintamability of the procem mm sywems, allowing better operational contml. Other Considerations: Other unpmvements in the ability of operators to monitor and tune the operation of the plant require the installation of the new proces computer sptem. It is antidpated that there will be measurable improvement in plant avadability and net generation as a result of these additional enhancements.
- m. CONCLUSION Unit I and Unit 2 Proces Computer System replacement has been accomplished, with availability mns completed for Unit I and Unit 2 systems. Le pmcess computer replacement will result in impmved plant availability and allow better operational contml.
IV. STATUS Both Unit I and Unit 2 systems are in service (Panial Operability on both systems). Documentation anembly for final operability and closcout is in progress. V. TARGET COMPLETION November,1994 PROJECT MANAGER LARRY WALTON PID Ol757A O
)
1 E CORE THERMAL UPRATE 3i i j. L PURPOSE AND SCOPE - ,
'nis project will gain 3.9 percent thennal power uprate (from 2436 MWt to 2531 MWt) by reducing ;
na-<y conservatisms in the core thennal-hydraulic analysis. Actual core design will not change, but , higher power opershon will be authonzad. Higher full power operation will be actueved by using modified ! rod patterns. An increase in steam and feedwater flow through the w.._ , "5 sy=tama and components l will be achieved; however, no increase in core recirculahan flow will be -ry. Sufficient margins exist for turbme operation at a greater steam flow. The BSEP generators are rated at 849 MWe. currently, maximum power output for rated core thennal power is about 800 MWe. Generator rated output power is not expected to be exceeded. Other systems will be affected by thennal uprate, and analysis is . necessary in the general areas of LOCA loads, increased decay best, NPDES comphance, corrosma rate > changes, seapoint changes, valve closure capability, blowdown pipe support loadags, and system performanca at higher pressures. Ceneral Electric is prepanag the safety analysis to demonstrate contmuod , reactor safety. A heense amendment request will be submitted to NRC in order to enable operation at a . higher power. CP&L is allowag for a 12 month review of the =====l-* request by NRC. Successful - ! completion of this project will result in licensed operation at higher capacity with no decrease in safety or reliability. H. EVALUATION t The goal of this project is a substantial increase in plant electncal capacity. Core thermal-hydrauhc ! analysis will demonstrate continued nuclear safety at higher power, or no licensmg submittal will be made. , Higher power level could increase the decay best removal requirements followag a plant trip. This increase in decay heat removal regarements would be small and therefore would not result in a significant , effect on nucient safety. Economic Aspects: Costs of this project are partially offset by General Electric under the settlamaar . agreement. Once complete, no appreciable additional fundmg will be necessary under this project, though ' l additional revenue should be gained throughout plant life due to increased plant output. { Related Standards To the extent that it impacts productivity and efficiency, this project is most closely l related to Work Management Policies for material condition and operstag par ==atars. Other Considerations: Project G0058A addresses turbme power uprate (increased steam throttling l efficiency) and is thus related to core thermal uprate. These two projects are considered separately hac=uma the project interdepaadaace is limited. HL CONCLUSION This project will increase unit capacity but is dependent on successful completion of a number analyses. An unfavorable outcome of one or more of these subtasks could negate the benefits of the project. Because implementation of this project also requires a favorable licensing action from NRC, coordination with other licensing issues and initiatives is necessary. IV. STATUS The study phase has been completed and design phase has been authorized. l PID 02164A l Category II
V. TARGET COMPLETION Project implementation is targeted for B212 and Bill in 1996. PROJECT MANAGER KIM WILLIAMSON PID 02164A PID 02164A Category II ,
a r <
.I p REPLACE SHAFT DRIVEN OIL PUMP FOR REACTOR FEEDPUMP TURBINE WITH MOTOR ;
(v- ) DRIVEN PUMP (S) . I.' PURPOSE AND SCOPE' his projectis to assess and: 1 = t the installation of redundant motor driven oil pumps for the reactor ; feedwater pump turbines (RFFI). He RFFT main shaft driven oil pumps have been unruhable, with limited qm iaq range, and have had a dif5 cult and expensive repair and maintenance lustory. Due to the unreliable ope..i.. of the main shaft driven oil pumps, a single motor driven auxihary oil pump must - be continuously operated to mamtain RFFT oil system pressure requaements. He prior failure of a single ! motor driven ==hry oil pump resulted in the loss of car $100,000 in gc~eg revenue (18 hours of j reduced power). He r"- -- = A= , to concet this problem involves adding two new motor dnven oil pumps, one of which will replace the cunent motor dnven auxihary oil pump; the shaft driven oil pump : will be disabled. De =rer- of this project will be impnmd plant availability, capacity, and a reducnon in maintenance costs for the RFFTs. ,
' II. EVALUATION f
ScheduleIndex: 30 - ne prevention of pour reducnons due to failures in the present RFFT system and lost generation time will increase the unit capacity (1.0 x 10). %e plant will also be en6ar~1 by the ; improved maintenance and lower repair costs for the pmposed upgrade to the RFFT oil pumps (1.0 x 8). Nuclear safety is somewhat unproved with a more rehable faa.~ system wluch will reduce the potential
~ for a loss of fas.a.c transient (0.2 x 32). %e addition of the motor dnven auxihary oil pumps for the l RFFTs could prevent previous unit power reducnons associated with the pnsent system thus ir 4 4 unit availability (0.5 x 12).
Economic Aspects: %e economics ofisyl g a difEcult and expensive to maintain RFFT main shaft i driven oil system with a more rehable and easier to maintain oil system are positive. In addition to the savings in maintenance, there is also a savings in gc~ g capacity with irmwd reactor faw.m reliability Just one failure of the RFFT auxiliary oil system cost 18 hours of reduced gc.erdrq capacity ; or $100,000 oflost revenue. %e cost of ugi dig both units could be &c -.<---i=11yjusufied with the i prevention ofpotential lost gs~.-g revenue over the balance ofplant life. Iong term maintenance costs j would be reduced relative to the present RFFT oil system. j Related Sur.d d Replacmg the RWT oil pumps with a more reliable system would meet the Work ! Management Policy on matenal condition. This policy is met by maintauung and improving the reliability i and productivity of the Brunswick Nuclear Plant with a more reliable reactor fa.r.:er system. Other Considerations: Because this project requires the reactor feedwater system to be inoperable for the replacement of the RFFT oil pumps the work would have to be perimmed during an outage. P IIL CONCLUSION
%e project is scheduled to allow adequate time for design and outage plannmg %e replacement of the RFFT shaft driven oil pumps with motor driven oil pumps would result in increased plant capacity,- l availability and reduce the mainter.ance cost of the reactor feedwater system. Le added reliability of the 1 1
reactor feedwater system will also enhance the safety of the Bninswick Nuclear Plant. 1 5 I l PID 02317A l Casegory II i l I
--.nm y ,, , ,.e-
IV. STATUS Implementation ofUnit 1 is scheduled dudng the Bl10R1. Implementation ofUnit2 has been to B212RI. V. TARGET COMPLETION Unit 1 - B1IORI Unit 2 - B212R1 PROJECT hMNAGER BOBJERNIGAN PID 02317A O O I
n
.q MAINTAIN THE BSEP ENVIRONMENTAL QUALIFICATION PROGRAM h I. PURPOSE AND SCOPE
- The Brunswick Environmental Qualification (EQ) Program ensures continued compliance with 10 CFR' 50.49,the NRC environmental qualification rule. Since the establishment of the Brunswick EQ program, numerous and significant issues have arisen which have the potential to affect ponions of the program, i Some of these issues are ongoing. Review, evaluation, and revision of affected qualification &-> ===' ion i is =---y to ensure the quality of the EQ files and support contmued qualification of equipment. ; ;
Founeen Engineenng Work Requests (EWRs) have been specified at different times to address variol concerns. AU 14 of these EWRs are consolidated in this project. Additionally, other EQ issues will be addressed under this project. For example, resolution of Limitorque Motor Operated Valve issues and the establishment of an environm,ntal specification for plant harsh environment areas are two imponant initiatives. At the completion of this project, Brg.dk should have resolved each of the issues curre within the scope of this project and received faal NRC acceptance of each resolution. IL EVALUATION . Schedule Index:
- 10. If EQ activities identify necessary improvements to systems, structures or componenu, sogne contribution to nuclear safety may result. However, such improvements are unlikely and, should they occur, will have small overall impact on the reliability of systems important to plant risk (0.2 x 32). If any equipment upgrades result from EQ activities, a similar, small improvement may bi seen in plant availability (0.2 x 12). Maintenance of the EQ program reconis should make future ai of eq sipment easier (plant aah=aea-=a', 0.2 x 8). No appreciable effect is anticipated to personl unit capacity (EQ must suppon plant uprate, but does not detenmne it), or ALARA.
Economic Aspects This project addresses a number of discreet, one-time issues which have ansen relati to EQ. While the level of eflort associated with EQ should decrease as these issues are resolved, other issues arc likely to be identified in the future. Mamtenance of the Brunswick EQ Program is an - effort which must continue until final plant shutdown and decommissioning (PCN 01657A accounts for routine activity). Other Considerations: " Ibis overall progract is required by 10 CFR 50.49. Power uprate will require! high energy line break reanalysis due to expected primary system pressure and temperature chang , generation of an environmental specification will assure that power uprate parameters are well documented in the BNP EQ design basis. IIL CONCLUSION Continuation of this project is necessary for compliance with 10 CFR 50.49, and the current schedule will ' be maintained. Four EWR's remain to be resolved this year. These EWR's include development of an EQ Specification, preparing revision to QDP-2 for test report traceability, revisions to QDP for Valcor SOV's, and revisions to Rosemount Transmitter QDP's. IV. STATUS ! This project has been design phase approved by the Plant Review Group. V. TARGET COMPLETION l December,1994. I PROJECT MANAGER JIM MCPADDEN PID 04830A PID 04830A Category II l
l l i
, BATTERY ROOM ' ANNUNCIATOR ALARM INVESTIGATION I. PURPOSE AND SCOPE-Several problems have been idennSed .3 14 vsl-b of the Battery Room. A Tm..yo.-y Condinen exism for the Connel Roorn annunaators for the ventilanon fan b switches due to spurious alarms during '
- conditions of muurnum dengn flow through the Battery Room.. Other y.o!.' have been identi6ed 4
.m 1.s the control of ;m..ym.;. ire in the Battery Room to assure that battery cell ;-..ym.; ares mnain above the Technical E-y-:b=E=. limia requimi to enmare that adequate battery capacity is av=i1=hle The' only L ':c=e, to the operator that ventilanon Sow is not adequate is dmpping Bauery Room wor s .; w , t which indicates that heater elements have inpped due to overheanng under the reduced flow. Rec =i= there !
is no remote indicanon for the status of the heater 3 - . i . of this condition requires an : operator to spend 20 minutes chmbmg among the cables above the battery rt.om to detemune if the heater ; elements are s mi. These d A M are 7 =p-- =+ and point to the need for de6nmg and 7 acluevmg overall balance, control, and ir hi -. of ventilation b through the Battery Room. This project ; will implement =- ':L=A=s to the air b measurement system for the Battery Room that will primde . accurate and rehable ir-1.c=eian of battery room ; y _ in the Control Room, balance battery mom j ventilation b to design 19 -.;., ehrmnate spunous annurici=*ian at low b, and maintain battery ; rt om ;morm.i.-s within normal orm.ousrange under all oym..;.4 conditions. The success of this project , will be evidenced by annunciation in the Contml Room without spunous alarms and ventilation uny.os.rs ts that maintam i ym.; w in the Battery Room within the Techrucal E-y:U=:en limits l under all expected condinons. ., II. EVALUATION i ScheduleIndex: 14 - Resolving the ventilanon problems will nmphry and streamhne the ventilation controls ; for the Battery Room, z :.=e spurious alarms, and decrease the extraneous work requests ger.m.;cd by ; low flow conditions in the ventilation system for the battery, thus prtmdmg positive impact on plant !' enhancement (! x 8). De intent of this pmject is to improve the avalability of the stanon batteries by implementing ventilation contmis to maintain worm.;.- in the Banery Rooms within the limits of the Technical Speci6 cations. Since commen cause failure of the batteries is a major contributor to failure of ( the DC Power System,improwd monitoring of woy in the battery room is expected to have a d moderste to high impact on DC Power System availability. %erefore, a nuclear scaling factor of 0.2 is . assigned to this initiative (0.2 x 32). Economic Aspects: The cost ofimplementing the ir-# =d== expected to result frorn this project will be I recovered in reduced costs for extraneous maintenance and upkeep on the ventilation systems for the Battery Rooms. , s Related Standards: The Work Management Policy on matenal condition applies to this project. Other Considerations: The exisung Temporary Condition for ventilation flow annunciation will be cleared during the cunent dual-unit outage. However, this modification will not require an outage for implementation. A battery wntilation flow test was conducted in August 1992 to identify specific deficiencies in ventilation contmis and instrumentation that require pennanent design solutions to resolve. III. CONCLUSION Based on the project information available at this time, the study for this project has already identiSed several benefit producing recommendations and, therefore, implementation will continue. PID 05983A Casegory II j
., ._ , . , . - . --- . - . . - ~ . . _ . . _ _ _ . _ - _ - . . - _ _ _ . - - - - - -
IV. STATUS Pmject has been implementation phase approved by the Plant Review Gmup with implementation currently m pmgren. V. TARGET COMPLETION December 31,1994. PROJECT MANAGER DAN MOORE PID 05983A O f l l 1 1 l l i
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i i GFF-GAS DRAIN TANRS RESERVOIR-v -
. I. PURPOSE AND SCOPE
. . 1 The electrical level contml and indication systems for the o& gas drain tank (OGDT) and its loop seal i reserwar have had a history of pmblems that have initiated several inadents resulting in loss of main !
condenser vacuum. Some of these incidents have led to power reduenons or reactor scrams. He contml . ) failures and other matenal M=:es in the system are c==a4 in part, by the high humidity in the ' , residual heat removal (RHR) room (17 foot elevanon) where the OODT is 1-= tad. For - la.the humidity causes conesion of exposed carbon steel solenoid valve hnkages, interfering with loop seal reservoir drain and makeup valve operation. Failure of these valves to operate properly will cause condensate to . , backup into the system, eventually lendmg to loss of air ejector % capabibty and, thus, loss of r condenser vacuum. Operator response to loss of vacuum inadens is hindmd by the current indicanon ; and control system since de.- g whether this system is the cause is unusually difficult, due to the lack ) ofmnote and accurate levelindications for the OGDT and loop seal reservesr. Also, to L.. e the level in the OGDT, the operator must enter a coni--- = ' area and check the high level alarm annunaa.or. ; Even if a high level is Mr=% the operator must then ny to start the OODT pumps. Failure of the druin - pump to start indicates a low level in the OGDT,lendmg to the conclusion that the loop seal reserwarlevel control system is cauang a problem. Also, the high level alarm for the OGDT is not rehable, since the i alarm has failed to annunciate when the drain pump level control system malfunction. Other control and : , indication related deficiencies have been identi6ed during invesaganens.cf loss of cc- ' vacuum j incidents. The scope of the project includes instalhng two float-type liquid drainers with associated piping ; ! in place of the electrical level control valves for the OGDT, installing a manual drain from the OGDT loop seal reservoir, replacing reed switch level indicators with ===-e Goet type liquid level indicators (with , remote annunciators), and modifymg piping to ? = hold-up points forc - '- - - % ese # -=*;ons will pmvide more reliable level control to prevent water from backing up in the off-gas 30-minute hold-up line and will provide mnote mach =61 indicanon ofwater levelin the o& gas drain tank. In the stack filter house, a local level indicator will be added and solenoid valves will be upgraded. Successful implementation . of this project will be evidenced by a reduction in loss of condenser vacuum events caused by the o5 gas j system and consistent, reliable level indication for the off-gas drain tank and the loop seal line resenoir. II. EVALUATION . I Schedule Index: 27 Removing the potential for loop seal li:e blockage increases plant availability by -! reducing the potential for loss of condenser vacuum events that have resulted in reactor scrums (1.0 x 12). The deficiencies being corrected have also caused power reductions at BNP in the past. Implementing this ; project has a positive impact on plant capacity by reducing the potential for such power reductions in the future (0.5 x 10). He reduced potential for the off-gas system to cause a loss of condenser vacuum event i has a low positive impact on nuclear safety due to the improved avadability of the condenser as a heat sink when decay heat removal is required (0.2 x 32). Correcting long-standing problems in the off-gas system for which special plant procedures were developed has a moderately positive impact on plant enhancement j (0.5 x 8). , , i' Economic Aspects: Reactor scrams and power reductions due to loss of condenser vacuum can result in one or two days of lost generating capacity each time the o5 gas drain tank and loop seal reservoir - , malfunction. Implementation of this project will have no substantial impact on the long term costs of system ; maintenance of the o5 gas syuem. Related Standards: The Work Management Policies on material condition and operating parameters are ! applicable to this project. i i I PID 06202A Category II ; i
,Other Consideradons: This project includes modifications that must be implemented dunng an outage.
III. CONCLUSION Problems with the off-gas system drain tank valves and assodated pipin6 h as, on several occasions, caused reactor scrams and power reductions. Implementing this project will correct system reliability deficiendes and will enhance the ability of the operator to determine sptem conditions. This project will be completed as scheduled or earlier, if feasible. IV. STATUS Unit One B110RI. Design in progress. Unit Two B212RI. Design in progress. V. TARGET COMPLETION May 1996. PROJFLT MANAGER CRAIG MARCH PID 06202A O O
DREDGE SPOILS DISPOSAL C/ I. PURPOSE AND SCOPE This project is required to ensure that proper methods and locations for the disposal of the spoil material are identified and prepared for the next dredging operation. Usage of any new spoil areas, or modifications to the existing areas, will require permit revision subject to the State of North Carolina and the Corps of Engineers approval. II. EVALUATION Dredging the intake canal is required approximately every five years to maintain design depth in the canal, thereby ensurmg that proper flow characteristics and capacities can be maintamed. III. CONCLUSION This project is needed to maintam plant reliability. IV. STATUS Plant Review Group approved. V. TARGET COMPLETION December 1998. O PROJECT MANAGER Martin Dalla-Pozza PID 06729A l l PID 06729A O\ Category II
E a s REPI. ACE HPCI, RCIC, AND RPS TOPAZ INVERTERS I. PURPOSE AND SCOPE ,
%e purpose of this pmpet is to resolve the spare parts and reliability imues asociated with Topaz inverten.
Topaz inverten are presendy used in a variety of systems for DC to AC con =rmon to allow contml, logic - and instrumemation functions to be Ar..d. with AC power. %e metaBed models are no longer available and the ongmal manufacturer will not nfurbah the units. Additmnally, replacement parts are unavailable. His has affected the availability of the lugh pressure coolant injecten (HPCI) and reactor core , isolation coohng (RCIC) systems. ImtinDy, aH - - ;-: -mt loads supplied by the HPCI and RCIC Topaz - mverters will be removed. %en, the Topaz inverters and components will be replaced with a simplified DC to DC power detribution system. De function of aH the system -2 = = ongmaDy supplied by the inverten wiH be the same. New DC HPCI and RCIC flow contmBen will be pmeund. New power supplies wiH be procund that will feed the remammg instruments after the inverterloads are removed. %e deared state at the - =p u-- of this pmpet is to have available,in place of the obsolete Topaz inverten, reliable power supplies that are quahfied for the envimnment to wiiich they are exposed. %e succes , criterion of this project is the 1..;..a e of HPCI and RCIC systems unavailability due to the faihue of the Topaz inverter. II. EVALUATION Schedule Index: 13. His initiative moderately improves the availability of the HPCI and RCIC systems. How contml improwments do not have a major impact on HPCI or RCIC reliability. Based on the PRA model, the HPCI system is a system ofrelatively low importance. However, when - --#+i with the RCIC , system, the HPCI system is mighted higher. Derefore, a nuclear safety scahng factor of0.2 was asigned ; to this initiative (0.2 x 32). Further, this initiative corrects the faihue of Topaz inverten in the HPCI and > RCIC systems wluch has a potential for a loss of unit availability. He potential loss of unit availability would be most likely caused by entenng a HPCI and/or RCIC inoperable ILO (0.2 x 12). Finally, this modification is a medium postive unpact on plant =h= -- =t in that it contributes to impmwment in the maintenance and opemtions of the HPCI and RCIC systems (0.5 x 8). Maintenance work.amunds such as replacmg individual components wnhm Topaz inverters would be avoided, and the ehnanation ofTopaz inverter failures would enhance system operation. Econonne Aspects: The =---W cost of the project includes the RCIC and HPCI moddications. The , expected benefits of this pmpet are the !...y.s.td material condition and reibbility of the RCIC and HPCI systems. %e changes in the mutine periodic maintenance costs as a result of this initiative are difficult to quantify. He maintenance cost will dmunsh but maintenance wiH clearly be required for the new equipment. Related Standards: ne Work Management Policy on material condition is applicable to this pmpet. Other Considentions: %e critical short term work to be completed is the RCIC and HPCI Topaz inverter change out. Other related work is also in progress. De feedwater Topaz inverten are being removed under PID 04688A. The RCIC and HPCI steam leak detection sptemTopaz inwrten are being replaced , with a NUMAC digital system under FID C0051A. ] 1 l PID 07H8A Category II ) I l
l lu. CONCLUSION 1he RCIC and HPCI modifications will be implemented as scheduled. This initiative improws the availability of the RCIC and HPCI systans and helps reach availability goals for those systems. It also will enhance the plant material condition by upgrading critical plant systems with components that are currently available. IV. STATUS This pmject has been design phase approved by the Plant Review Gmup. The Unit 1 Plant Mod is approved for implementation. Work package plamung for the Unit I mstaRation is in progress (B110R1 outage pmject). V. TARGET COMPLETION June 1996. PROJECT MANAGER IARRY WALTON PID 07148A O O L
f 'ic j l i 4 i
- N REMOVE AND REPLACE OBSOLETE BAILEY SR.ISIt'AND SR.I110 RECORDERS !
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L PURPOSE AND SCOPE Curmitly the BSEP control rooms heve Badey nanow range chart ncorders wluch have been obsolete since 1974 and for winch the spare parts are dal-art his project is cunently replacing some of the recordm
- in the control rooms for both of the Brunswick Units. Some of the recordm have regulatory related l cg.--dmal requimnents and are in need of parts which could impact plant operations. %e irw=Harirm j of new recorders will help prevent plant operations from being : j- M Existmg Badey i.e are to ;
t be replaced with Imd & Northrup Speedomax models 131,132, or 133 nanow range chart recorders. Successful P of this project would allow the Control Room w.;an to properly d- -- =i iv,.w.t plant p .ae which will allow canonued plant mm and also reduce cut d service i
. m .,-L a. ~
i IL EVALUATION Schedule Index: 6 - %e only categories are affected by this project are plant =h==- ct and unit avadability. Changmg out the exisang ,m.i.e will enable the operstor to have a more rehable means to diagnose off gas problems. However, this L.vem.em - will have no apprecable impact on nuclear safety - -l (0 x 32) he plant would be enhanced with enmued indication of plant parametm and improved op..w ! j effectiveness (0.5 x 8). Dere is a potential for the plant avadabdity to be miuced if those .m,.i.e required by regulatory consideranons are out of service for lack of parts (02 x 12). j e Economic Aspects: The cost ofroutine mamtenance and cah'bmtion of the recorders willlikely be reduced. 'f he expected benefits of the replacement of the obsolete Bailey recorders are reduced maintenance and ! improved operator perfmnance.
) Related Standards: Applicable Work Management Policies for this project are matenal condition and ,
operating parameters. Haviryg new long-term (20 yrs) reliable recorders would meet the policy of
]
continuously monitoring operating plant parameters. j
- $l Other Coraiderations: Some of the plant systems',m,.ai. will need to be replaced during a plant outage tr.:ause of theirlocation in the Control Room and the importance of that system to plant operation. He j l
stock of r7 ==nant 1 parts for these recorders at the BSEP is depleted; therefore it is advisabl:: to replace 1 them at the scheduled dates. i
)
1 III. CONCLUSION he pmject will continue at the scheduled rate and will be completed by November 1997. Replacement of the old recorders will prevent the possible loss of vital equipment during power plant operations. . IV. STATUS i Project design is complete. Project requires implementation phase appros31 by the Plant Review Group. V. TARGET COMPLETION November 1997 PROJECT MANAGER DAN MOORE PID 07208A PID 07208A ( Category II
EDG GOVERNOR REPLACEMENT v I. PURPOSE AND SCOPE ne existing governors on the Emergency Diesel Generators (EDG) are obsolete and are no longer available from the original or other supplier. Repair and rebuild of Brunswick spare governors is now possible on a limited parts available basis. Future repair of the governors by the vendor will not be available. The scope of this project is to replace the existing Class IE governors with new style Class IE digital control equipment. 1 IL EVALUATION l The existing governors are obsolete. Certified Class IE parts are no longer available to the vendor for l rebuilding and recertifying existing governor Control Circuit Boards, Motor Operated Potentiometers and Actnators. Parts will not be available in the event of failure. Future EDG operability may be impacted. BNP Maintenance does not have the technical expenise or the tool and facilities to overhaul or repair and recertify this equipment. Expected benefits are to stduce mamtenance expense and to increase EDG reliability. IIL CONCLUSION Proceed with the design to install new style governors on each Emergency Diesel Generator. IV. STATUS O The Unit I and Unit 2 projects are design phase approved by the Plant Review Group. V. TARGET COMPLETION May 1996 PROJECT MANAGER Dan Moore PID 07627A eb O PID 07627A Category II
i gm REPLACE LIGHTING AND COMMUNICATIONS UNINTERRUPTIBLE POWER SUPPLY
)
(V) L PURPOSE AND SCOPE His project will replace the existmg obsolete lighting and communications unintemiptible power supply , (UPS) system with a more modem and maintainable system. he lighting and communications UPS system l i supplies 120/208V AC power to the plant paging and intercom system, the plant evacuation and fire alarm l system, lighting in the Control Room and other critical areas, and the plant card r:ader and security system (e.g., the explosive entrance detectors and security computer system). The UPS system was origmally installed in 1973 and has become a significant maintenance problem due to normal equipment aging. l Support fmm the ongmal manufacturer (Static Products Incorporated, now Intemational Power Machines) has been dechnmg and will continue to emde due to the unavailability of the spare pr.rts for this obsolete equipment. In order to maintain the functions of the UPS system, it is crucial that the cunent hardwate be replaced with a modem system for which part support is available.
%e initial phase of the project identified the new system and vendor to replace the exisung lighting and communication UPS system.ne project wG be successful if the UPS neem maintenance costs are reduced and the system reliability is improved. Also, the equipment modermzation process itself should not unnecessarily impact plant operations or pm~rmd safety.
II. EVALUATION bchedule Index: 23 - Plant lighting and the plant paging system are very important to successful operator actions during recow:ry from any potential accident. Since operator actions are critical in preventing and mitigating core damage, the replacement or the lighting and communications UPS impacts nuclear safety p scaling factor (0.2 x 32). Personnel safety is impmved by this project due to the potential lost time accident h that could occur if the evacuation and fire alarms were to be without power. Ioss ofplant communications could also have the potential for a lost time accident (0.5 x 29). There is aho some potential for unnecessary radiation exposure if the plant intercoms and alarms are unavailable due to a loss of power (0.2 x 9). Mnomic Aspects: ne present system is obsolete and spare parts are becoming increasingly scarce. A new UPS will allow continud safe plant operation and will reduce maintenance costs as compared with the present installed system. Related Standards: he Work Management Policy applicable to this pmject is plant material condition. Other Considerations: Because of the importance of the UPS system, it is critical that replacement of this equipment is done in a manner that will not have any adverse impacts on plant security or vital alarms. His project is not outage dependent. IIL CONCLUSION Iristallation of a new lighting and communications UPS system is needed to support continued efficient plant : operational contml. System maintenance costs for the current obsolete equipment will also be reduced. ! his project will be completed as scheduled and will allow orderly modemization of the lighting and i communications UPS system. i i l i l PID 07862A !
\ Category-II 1
IV. STATUS Unit 2 implementation is complete. 'Ihe Unit i Design package is in the review cycle. Unit 1 implementation is presently scheduled for November 1995. "Ihe Unit I implementation is under evaluation by Plant Management for completion in 1994. V. TARGET COMPLETION Unit 2 - November 1994 Unit 1 - November 1995 PROJECT MANAGER LARRY WALTON PID 07862A O 1 i O 1
I P i es CONTROL BUILDING HVAC CONDENSATE DRAIN REPAIR l f (- I. PURPOSE AND SCOPE l Inadequate insulation on ducts and inadequate drain line slope set up the condition for water to spill into ' the CB HVAC mechanical equipment room floor. This project will elimmate the standing water problem , on the floor of the Muh=ir=1 Equipment Room. l II. EVALUATION i t Standing water on the floor of the mechanical equipment room has no safety impact but does degrade the material condition of the plant. III. CONCLUSION ! Prepare a Study that identiSes the cause(s) ofwater accumulation on the floor of the Mechanical Equipment Room and recommends appropriate conective action (s). L IV. STATUS Study has been compiled and is in NED review. Study presentation to the PRG is forecast for Mid- l December followmg completion of p1--ry plant reviews. t V. TARGET COMPLETION Study completes December,1994. O PROJECT MANAGER Craig March - PID 12420A I l i l 1 l PID 12420A Category II
X TURBINE UPGRADE - -U I. FURPOSE AND SCOPE Contract authonzation XS80380083 (LP Rotor Rep!=-- =t) includes several m~hdons on turtane- ; related systems. His project was estabbshed to install these n= 'T- -dons, including rmle-=mt of turbme l turning gear motors, installation of RFFT lube oil vapor extractors, u=r=11=da s of full flow lobe oil Sters,- and rmle*==t ofRWT govemors with electronic Woodward governors. As study phases are completed j and approved on each modacation, individual "sub- projects" will be established for the design phases. ! IL EVALUATION Economic Aspects: These modifications are intended to conect current problems which require excessive , maintenance, diEculties in replacement of obsolete parts, and unrehable equiprnent. Other Considerations: All of these modifications will require outages for installation. III. CONCLUSION
%ese modacations are expected to provide decreased maintenance requirements and irmed equipment ,
reliability. , t IV. STATUS ! The " Replacement Turinne Tunung Gear Motor" project was approved by Plant Redew Group and will be installed in the B110R1 and B212R1 outages. (This sub-project has moved to the Design Phase for Unit One and the project manager is Dan Moore.) Evaluation of RFT lube oil vapor extractors is in progress. Installation of the full flow lube oil Sten was disapproved by Plant Review Group because of high cost; contract cancellation is in progress with General Eectric. Altemasive (non-General Eectric) lube oil Stration systems are being evaluated. Evaluation of the replacement of RFFT govemors with Woodward electronic govemon is in Progress. V. TARGET COMPLETION . June 1997 PROJECT MANAGER Bill Biggs/ Dan Moore PID 13447A , PID 13447A Category II
m () CONTROL BLADE PINS & ROLLERS REPLACEMENT I. PURPOSE AND SCOPE he purpose of this pmject is to remove a major contributor of radioactive Co.60 from the plant. He goal is to reduce radiation doses. He scope of this project is the removal of upper pins and rollers from all origmal equipment control blades in Unit 1. Le rollers will be replaced by buttons which are inserted into the hole rmnining after the emstmg rollers are " punched out". Although the project is currently approved for Unit I only, the intention is to perform this work on both units. He expansion of this project to include Unit 2 will be considered prior to the next Unit 2 refueling outage (B212R2.) II. EVALUATION This project will remove the upper pins and rollen fiom the m2ining 103 original equipment control blades in Unit 1. It has been Mm=W by the BNP ALARA staff that the upper pins and rollers (of both ; units) arr the cause of 28% of the current site doses; the contribution from each unit is estimated to be appronmately one-half of this value. The removal of upper pins and rollen will lead to reduction of site dose by 28% within 5 6 years (as Co.60 curnntly in the plant is depleted and the source for replentslung it has been reduced). O An EESY analysis for Unit I was performed to quantify the benefit for replacing upper pins and ro!!en. V Based on the rate of $10,000 per penon-rem, a net present value of $5,287,700 was calculated. The , assoczated benefit-cost ratio is 2.88, with payback occumng within 4 years. Implementation of this project requires handling of control blades; appmxunately 12 houn per control I blade will be required. Plaruung for refueling window activities willinclude this work and will be conducted to muumtze potential for outage critical path extension. If unacceptable refueling window schedule impact is anticipated, consideration will be given to perfomiing some or all of this work in outage Bl11R1 vice l B110RI. III. CONCLUSION nis project will eliminate the lagest source of CA in Unit One and lead to reduced personnel dose. IV. STATUS This project is in the implementation phase and is approved by the Plant Review Group. l V. TARGET COMPLETION December 1997 PROJECP MANAGER BILL BIGGS PID 13629A O , Category II 13629A 1
-i
; ECCS SUCTION STRAINER -i L PURPOSE AND SCOPE :
ne purpose of this project is to resolve the ongoing concerns relative to the potential for post-LOCA debris l plugging of ECCS suction strainers in BWRs. De NRC has issued Bulletin 93-02, Supplement I which , requested utilities complete certain near-term actions and support the BWROG's project for long-term , resolution of this issue. De BWROG is currently performing testing to determme the extent of the project ! and recommend the solution to the long-term issue. De purpose of this propet is to work with the BWROG in modeling the suction strainer perforrnance specifically for Brunswick and implement a long. ! term solution for this issue. j II. - EVALUATION : Economic Aspects: The project costs will depend on the final scope of work. De project is currently in l the study phase. Modification requirements,if any, will be identifad at the conclusion of the study phase. Related Standards: his project supports tim Work Management Policy of maintaining safety system availability and design basis requirements.
-l Other Considerations:1f modifications are required as a result of the BWROG's recommendations and plant ~ i specific modeling, they will have to be accomplished during outages. j III. CONCLUSION i 9
The recommendations of the BWROG and the plant specific modeling of suction strainer performance will determine the type and the extent of modifications, if any, to ensure compliance with long-term cooling [ requirements. IV. STATUS The PRG approved the study phase in July 1994. V. TARGET COMPLETION Study Phase to complete March 1995. PROJECT MANAGER J. E. HARRELL PID 13671A PID 13671 A Category II l.
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SUPPLEMENTAL SPENT FUEL POOL CO3 LING ASSIST (PURCHASE OF EQUIPMENT) I. . PURPOSE AND SCOPE f'N (f Currendy, the spent fuel pool coohng system is not capable ofpnwhng decay heat removal from a full core'
' off-load until app.-. dy 32 days after plant shutdown. The RHR system must in operation.
l f during a signi6 cant ponion of the outage in onier to pnmde coohng to the spent fuel l The Supplemental spent Fuel Pool rwLng Symem (SSFPCS) may be used as an alternative to RHR l Coohng for removing heat from the Spent Fuel Pool (SFP). 'Ihe system has been mzed to accommodate heat loads associated with a full core off-load, such that on Day 10 of the outage when used in - -- r=h : with the regular Spent Fuel Pool Cochng System, the SFP Lv.iae can be maintamed at or below 125 degrees. This capability results in substantial cost savings, allows parallel dans which nault in reducing - ' outage time up to 3 weeks. ; i
'Ihe scope of this study is to determme the feasibility to make the w.p.7 HeatNh=agm, Pumps, and 1 Coohng Towers which are attached to the existing Supplemental Spent Fuel Poo! Cooling symem into l pennanent plant equipment. l I
IL EVALUATION i
'Ihis project will detemune ifit is rnore economically feasible for Brunenck to purchase, maintain, and operate the 6.p..l mstalled i vendor equipment used for the SSFPC System , or to continue to lease :
the equipment and rely on vendor supplied p.cd for the operation of the symem. ; A key assumption is it will be required to take the RHR symem out of semce for maintenance, or perform
- a chemical decon of the recirculanon piping. Use of the SSFPC system will make it han-Gal to :
perform these activities earher in the outage. l Altematives Considered:
- 1. Install an independent SSFPC System, pnmary and secondary, on each unit. .
- 2. Installir kg.de.r.t pnmary coohng systerm and a -,..d-ry coohng system common to both units. ;
- 3. Obtain a single set of equipment that will be used on the unit in an outage. !
- 4. Should all or part of the synem be innalled permanently or should it remain a w..y,,r.dly installed {'
system used during outages (mechanically and eleenically). . 1 III. CONCLUSION ; Without this project vendor supplied equipment and p ~r.d for egr.Ger. of the Supplemental Spent Fuel {
. Pool Cooling System will continue to be used. 1994 cost for installation, operation and removal of SSFPC j
system was $672,000. j i IV. STATUS ! Prehnunary study has been completed and is being reviewed by Project Manager. ! V. TARGET COMPLETION l Study phase completion targeted for November,1994. Results will be presented to the' Plant Review Group. : i l PROJECT MANAGER CHUCK RAINES PID 13676A J PID 13676A Category II
a 4 l 1 i j INCREASING MSIV ALLOWABLE LEAEAGE t' ;- I. FURPOSE AND SCOPE The purpose is to change the technical speedication to increase MSIV allowable leakage fmm 11.5 SCFH to 100 SCFH, in order to reduce valve maintenance and radianon exposure dunng outages. The scope includes calculations, seurruc walkdowns, molution ofidentdied pmblems, and development of a technical speedication change for submittal to the NRC. IL. EVALUATION . f i Schedule Index: 25. Calen1=nans are required for the .T cMcgical dupersion factors, and control room, ; TSC/ EOF and EAB/LPZ radiation doses. Seisme walkdowns of the - " and main steam piping j are required tojudge if these systems are Mr.ny rugged. " A._ identified will have to be resolved , by calculations, repain and =~ime-h 'Ihe techrucal -;=T=F-on change will have to be developed along with a safety renew, and submined to the NRC. 'Ihe NRC comments will have to be resolved. . ; i III. CONCLUSION This pmject provides the information to submit a heense amendment request to the NRC for Brunswick's Unit 1 & 2. i IV. STATUS This project is in the study phase. l i V. TARGET COMPLETION f . s j Study to be completed 12/31/94. ! PROJECTT MANAGER CHUCK RAINES\WENDELL*IRIPLETT .j PID 13695A ; l f i o 4 2 i e I P PID 13695A ; Category IF I l l l l
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((3)- 10CFRis COMPLIANCE VEHICLE INTRUSION ; I. PURPOSE AND SCOPE 10CFR73 (Revision dated 8-194) requires the addition of vehide barriers for two reasons: l I) Limit the use of vehides to gain proxunity to plant vital areas.
- 2) Establish a safe stand-oE distance for explosive laden vehides to protect vital equipment.
II. EVALUATION
'The objective is to constmet a vehide banier at the appropriate safe stand-of distance which will ensure compliance with 10CFR73. ;
III. CONCLUSION The rule became effective in August 1994. Implementation plans are to be submitted in February 1995 and I implementation doscout is required by Febmary 1996. IV. STATUS Currently in Study Phase. ; V. TARGET COMPLETION Milestone Schedule Start Complete Study 8-15-94 11 22 94 ! Design Il 23-94 6 2-95 Implementation 6 5-95 2 28-96 PROJECTT MANAGER MARTIN DALLA-POZZA PID 13863A a 4 1 PID 13863A [V9 Category II i j
I i G PLOOR DRAIN FILTER RETROFIT - U 1 I. PURPOSE AND SCOPE ' i Liquid radwaste processag was ongmally designed to be accomplished by two process paths, a floor drain - system for'diny" liquid waste and a waste calle'ar system for ." clean" liquid waste. A previous modafication on the original floor drain fiher system did not achieve the desired mio. objectives and resulted in an inoperable floor drain Alter.1 The ;-- d'= candivian of the floor drain filter leaves the i waste collector system as the only path for processag liquid radwastes. Since the waste calle'ar fHier is "l designed for processing fclean" waste water, the presence of oil.cantaimar water causes frequent 1 changeouts of the waste canartar fHier elements that are costly and incur unnarenancy e g-- * , of . ~ '! person-rem. 'Ibe resin precoat is exhausted much more rapidly due to the current operatag lineup, thereby ! generating extra costs and solid radweste to ship off the site. sinnandad fauures of the waste collector ! system could result in a dual unit shutdown because of an inabihty to process liquid radwaste. ; The purpose of this project is to modify the floor drain filter to restone the futer to its ongmal, funcuonal j design. This will restore the floor drain system to service and provide separate paths for processing liquid ; r radwastes, thereby L r.mi the operanon of the waste collector filters, reducing the frequency of filter ! changeouts, and providag an alternate path for processmg all liquid radwastes in the event one of the j systems becomes inoperable. ; i Successful - ---g'='= of this project will be evulanced by demonstrated ability to process all liquid radwaste through either the floor drain system or the waste collector system and by a reduction in the
% i.cy of element changeouts in the waste collector fiher.
II. EVALUATION i
?
t Schedule Index: 12 *==ia= the floor drain fiher to its original design will return the waste processing ' systems to their normal configurations and intendad uses, provide i= '= i=y in waste processing paths, 'i and restore the ability to maintain clemnhneen in the waste collector system, resulting in a significant plant 'l enhancament (1.0 x 8). Retunung the floor drain system to service reduces the possibility of a dual unit j shutdown due to an inability to store or process radwaste for e=**ndad periods (0.2 x 12). This project will l reduce the filter maintenance related radianan exposures caused by mixed stream processing (0.2 x 9). 'i Economic Aspects: Retrofining the floor drain filter will reduce the rouune costs of cleanmg the waste j collector rystem to remove oil impurities that the system was not designed to handle it. ; i Related Standards: The Work Management Policy applicable to this project is material condition. '!' Other Considerations: The modification does not require an outage to implement. III. CONCLUSION ! l In inoperability of the floor drab filter causes all liquid radwaste to be processed through the waste ! collector system, which is desi, .i to process only " clean" radwaste, and causes increased costs for ! maintenance and cleamng or a waste collector system. Additionally, the lack of redundant processing ! paths presents a potential for forcing unit shutdown if the waste collector system is inoperable for three or l more days. Restoring the floor drain filter to its original design offers immediate economic and material l benefits, so this project will be implemented as scheduled. j ~ I PID 81401A Category II , j t a
._.____.__ ___ _ _ O
IV. STATUS Design of the Floor Drain Retrofit mod is on hold until ESR 94-0226 investigates the use of current technology radioactive waste processing skids. These skids can apparently process waste water with a mmimum of effluent release and at a lower cost than the precoatable filters of the retrofit mod. V. TARGET COMPLETION April 20,1995 PROJECT MANAGER CRAIG MARCH PID 81401A O O
- e. RADWASTE SAMPLING SYSTEM UPGRADE
)
I. PURPOSE AND SCOPE he BSEP radwaste sample system monitors some of the major sources ofpotential reactor water impurities, including the condensate demmerahzen and prud makeup water. He radwaste sampling system has expaienced several long term and repetitive pmblems. Many sample points have been plugged for years. Conductivity recorden normally track as many as 7 vanables, but they print data on only 8% of the chan paper range, makmg data analysis ddlicult. In addition, conductivity monitor failures cause the plant to enter IEOs frequently. In 1989,INPO issued fmding CY.l.1, stanng,in pare "The conductivity moniton and recorden for the condensate filten and deminerahzers located in the radwaste control room do not provide information useful for contmiling the operation of the systems. Also, the radwaste deminerahzer conductivity monitor has been inoperable for several years. The operaton do not have indication when the demineralizer resin is ev6e~i and when impurities are sent to the waste sample tank." This project will be successful when the upgraded synem is in place and fully operable; E&RC staff have accurate cherrustry data to work with; and more pmactive cherrustry, filter, and resin management is demonstrated. The project plan is to install new, modular, pnmary and secondary cooler sample racks; a new 10 ton chiller unit; and associated electmnics on the panel and in the Radwaste Contml Room. The design and location of these components is such that maintenance will be facilitated. II. EVALUATION Schedule Index: 15 - The plant is significantly enhanced by allowing plant personnel the ability to monitor Q critical chenustry parameters as well as prewnt continual maintenance on obsolete equipment (1.0 x 8). Cf Completion of this project is expected to result in a net savings of 16.3 person-rem (0.5 x 9). Of the four chloride intrusion moniton identi6ed in technical specifications, two are made inoperative by failure of the sample chiller. If the other two are out of service, then the unit must be brought to hot shutdown within 12 hours. This potential causes a minor concem forloss of unit availability (0.2 x 12). Although this project will significantly improve the ability to monitor chenustry ofimponant makeup water supply synems, there is insufficient evidence to indicate that improvements in water quality ofimportant safety systems would result in significant reduction of conesion or other beneficial effects that might impmve nuclear safety (0.0 x 32). Economic Aspects: he EESY net present value for this project calculated to be positive. Related Standants: The Work Management Policies applicable to this project are material condition and operating parameters. Other Considerations: Sample temperature is a critical parameter for accurate analysis. We FSAR states that the temperature of samples undergoing in-line analysis is designed to be maintained automatically at 77 degrees F ( + or. I degree ). Technical specification limits are given at 25 degrees C (77 degrees F). The temperature is controlled at die sanple station by the chiller system, which has been very unreliable. The INPO finding CY.l.1 is being tracked by FACTS Numben 89B0905, 89B0906, and 90B1031. Closure of the INPO finding has been rescheduled several times. PID 84587A V Categorfil l
l III. ' CONCLUSION This project is important to pmpedy monitor reactor water chemistry and will be completed as December 1995. The conditions warranting action have been present since 1985 and resulted in a 1989 INPO findmg that is still open. IV. STATUS Project is design phase approved by the Plant Review Group. V. TARGET COMPLETION December 1995 t PROJECT MGR. CHRIS HUGHES PID 84587A O O'
i i! l TURBINE UFRATE
' ~ .! l L 1 I. FURPOSE AND SCOPE l l
His project unproves BSEP eEciency by reducing man tudane 0.4 4 ames. %e BSEP turbes have four inlet valves to the fast stage. When operated in full adminion, each of the four valves throede equally j to control steam Bow to the turbine. In pamal are adrnusion, two or three of the valves operate wide open 1!
. at full power and control is obtained by 0.4g the remairang valve (s). Parnal are adminion is rnare . !
j L efEcient at full power (for the same m== Sow and mactor power) be== 0.4.s losses are less. Operation in pamal are adnussion resuhs in more uneven stmmes than ., e.. in full arc =<l=w=anL%e t High Fremure Tudanes in both units have been n-Wd o sinngthen the High Pressure Rotors for ! operation in pamal are vi~.ir ;
't Unit 2 was converted to pamal are admanion during the fall of 1991. Dunng subsequent c.im.;ws., turbe ;
a=<,Ilarians due to control problems at high power necessitated a 75% power c.i~.;k,r. limit. % ese _i problems were addressed and u .d Unit 2 is now in three admuman partial am c,j~.;ks. and has i W succesful operanon during the last run. Mmor remanung control imues are being addressed Turbme output is affected by a number offacton, E--L- E-g aAq water k ..,~.; rc, but prehminary esumates are that conversion to parnal are adrmasion has resulted in about 1.5% inaense in turtune output. This project included feedwater flow nonle calibration testing to verify actual far.;cr flow to the reactor. ! II. EVALUATION y De faw.; - flow nanle calibration test resulted in a decrease ofpower output in Unit 2 and an increase 1 of power in Unit 1. Unit 2 performance testing indicates that the irad power output attributable to pamal arc operation ; is about 8.5 MWe. It is expected that the converson of Unit I will also produce about 1.5% increase in power output. Dese increases are agru6 cant in that additional power output is aclueved without increases !' in fuel or c.pc.-.; g expense. Economic evaluanons show that the project is very ba Ari=1- he evaluations will improve as the Low ! Presure Roton (with impmved eEcimey) are installed. He low Pressure Turinne contribution to ~ improved ef5ciency have now been included in these economic evaluations as the low pressure rotors are ; not a part of this project. his project is most closely related to the Wort Management Policy for matenal condition, particularly with l regard to optimmng plant productivity. i his project to uprate the turbmes is related to the core thermal uprate, PID 02164A. %e nuclear safety [ and licensing considerations are more agm6 cant for core thermal uprate. Dese two projects are considered i separately because of their different natures. , 7 i i PID G0058A j O- Category II ; t r
III. CONCLUSION The Unit I project will be completed as scheduled to substantially increase turbine capacity. The Unit 2 project is complete with two exceptions. Data is being collected and evaluated at the 100% power level to resolve a minor control problem. In addition, tests to enable the performance of control and stop valve testing at higher power levels is scheduled to complete in November 1994. IV. STATUS The Unit 2 project is implementation phased approved and the Unit I project is design phase approsed by the Plant Review Group. V. TARGET COMPLETION December 1994 Unit 2 June 1995 Unit I ( PROJECT MANAGER DAN MOORE PID G0058A O O
y f 7r f l 125/250 VDC BATTERY GROUND DETECTION IMPROVEMENTS
- 1. rvarosE AND SCOPE ,
'l
'i Electrical ground detecuan problens on the 125/250 VDC electncal symem have delayed startup and have : i conmuned hundreds ofman-hours in repaus and attemative measures to detect and isolate (locate) grounds. :
The pnmary cause of these problems is that the 125/250 VDC elecincal syman ground detectors are l irm4 urwehable, and obsolete. Repaus to the detectan are coady and ddEcult to perfonn since the j repaus are p J-...d. at the -a--;==e level and ry: -- =r parts are ddEcult to obtain. Frequent ' rnaintenance on ground detectors also inaenses the'potennal for creating circuit pd'-- -- and increases i general degradanon of the t s..' circuit boards. De6cient and inaccumte cor. trol mom annuncianons : have resulted in the need for ground readmgs to be taken rnanually on each shifL . In addition to these , ;j 1 hr.rc problems, the lack of a fum demgn basis for the setpoints a the detectors results in numerous' I man-hour expendituns to trace and isolate gmunds that may be dlitde . y--..ce. j t This project will pnmde a techrucal basis for the ground ya ,,i- system requurments and will ==hli=h j re orde and .. .; h ble annunaanen setpoints. 'Ihe scope of this project also includes researching i industry ground detection systems to idennfy and select the most suitable system. Sat ~~~ criteria will j include maintenance, annunannon, and gmund inal= nan canaderanons. 1 Successful completion of this project mcludes dca,,, g a valid setpoint dengn basis, winch is to be ! accomphshed by evaluanng the electrical v.d.g values for vanous DC --;=---- and by reviewing . ! industry mandards, BSEP system c Gc.a. and the ==ari=*~1 PRA : ;M== The success of the l system upgrade will ultimately be ..~ J in terms of man-hours saved on isolanng gmunds and repainng ! failed detectors, by a decrease in false control mom annunaanons, and by a egndicant increase in the
- probability of the detecton remauung calibrated.
II. EVALUATION , l Schedule Index: 20 - Although AC electncal poweris used for most safety-related equipment, DC power is used for certain safety related equipment and instrumentation in the event of a loss of all onsite and cKnite ! AC electrical power (stanon blackout). Improved gmund detection techruques pnmdmg real-time detection . .j and more rapid location of symem faults provules more mammnce that the DC symem will supply power to .j vital equipment when required, resulting in some positiw impact on nuclear safety (0.2 x 32). A major reason for identifymg and removmg electrical grounds is to provule safe working conditions for p .a and to ensure pmper and safe ci~. . of plant electncal equiprnent. 'Iherefore, improving the reliability l ofground detection amists es.; in assuring that no ur'- - --y conditions exist to endanger p~...el j or plant equipment (0.2 x 29). Improved gmund rl**ard= and i=al=% techniques will reduce the effort ' l needed to identify and conect sources of electrical grounds, resu; ting in a moderate plant enhancement (0.5 j x 8). Finally, the capability to more efEciently =t=hh=h the source of a ground will reduce plant radiological I area entries needed to perform ground detection, reducing the p~..a radiation exposure cunently expended in ped-.-.g this activity (0.2 x 9). Economic Aspects: Upgraded ground detection has substantial potential economic benefits. Upgradmg of the ground detection system should alleviate the potential for delayed startup due to problems with detecting , and isolating DC grounds. 'Ihe costs that can be saved are evidenced by the appmximately 1000 l man-hours spent on such activities during a delayed startup of Units I and 2 in 1991. In addition, the i need to perform manual ground detection could be removed, resulting in additional cost savings and improved productivity. PID G0lSOA Casegory II l
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4 Related Standanic The Work Management Policies applicable to this study are material condition, design , documentation, and operating parameters. Other Considerations: None III. CONCLUSION Because of the significant benefits this project is expected to yield, it will be accomplished as scheduled. IV. STATUS Unit One complete. Unit Two in progress. V. TARGET COMPLETION December 1994 PROJECT MGR. DAN MOORE PID G0180A O i
I BNP REFRIGERANT REPLACEMENT 7 V ). I. PURPOSE AND SCOPE His project is curnntly in the study phase to - one of the potential impacts on BNP of the Clean Air Act. Fedem! law now supports the United Nations protocol to gradually phase out production of chlorofluorw !~ (CFC) dim-.ts by the year 2000, but this date could be moved up (by presidential duective) to as early as 1995. %e objective is to protect the Earth's ozone layer. Cunent CFC production is limited to the level produced in 1906. Under curnnt law, this level will be reduced by 20 percent in 1993,50 percent in 1995, and 85 percent in 1997, with production o(new CICs endmg entirely no later than the year 2000. Manufacturen have i IWe~l hat t production will end in 1995, regardless of federal law. De U.S. Clean Air Act also bans intentional wnting ofCFCs as offuly 1,1992. Enforcement of this - law is the responsibility of the Environrnental Protection Agency (EPA). He pnmary .dQm-.ts used in BNP coohng systems are CFCs, so the availability of rent-~nent .d bm .ts will be irm Jgly impcutant as CFC production is restricted and imu--wi. Also, maintmance on coohng systems is already more difficult due to the venting restriction. %e initial objective of this project is to identify and evaluate the impacts of unng attemate .26m-.t in the affected plant systems. Once the study phase has been completed, plant physical modifications must be developed and camed out expeditiously. He project may include irm sg near term inventories of CFC .dbu-.ts in plant storage as physical plant adjustments are planned and canied out. The relative refngeration cyde effectiveness of attemate .dQmwts will very likely impact celing systan design capabilities, requiring equipment changes. In particular, this project addresses Turbine Building chillen, Drywell chillers, Control Building chillers, Augmented Off-Gas (AOG) Building filter chillers, and the Traming Buildmg simulator chillers. Other plant equipment, vehicles, and buildings are also affected. his project will be successful if all .abm-.t related Clean Air Act constraints are implemented without impacting plant operations. II. EVALUATION
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Schedule Index: 12 - His project does not impact any systems important in preventing core damage (0.0 j x 32). Nevertheless, failure to comply with and anticipate the effects of the regulation would have a major ; impact on unit availability (1.0 x 12). Much of the impact depends on the availability of alternative j refrigerants as the phaseout of CFC production continues ne worst case situation could involve plant l shutdown due to inadequate cooling system capacity, but this would be a gradual and contmiled l management action. Although no outage has yet resulted from this Clean Air Act requirement, this is a j stmng possibility requiring immediate action. 1 Economic Aspects: The cost of CFC .J6m ats is expected to inacase significantly as the supply of CFCs is ieduced and as Federal excise taxes on CFCs are increased to discourage CFC use. Deferral of this study and the resultant modifications could eventually lead to irum ed procurement costs and opm.img j restrictions (including plant shutdown), but this would be gradual and dependent on avadability and conservation of CFCs. No significant long term impact is expected after required studies and modifications are completed. Related Standards: This study is primarily related to Work Management Policies forregulatory compliance (non-NRC) and material condition. Impacts on maintauung material condition involve a fundamental design change forplant coohng systems. Derefore, to maintain design capabilities (functional requurments), forward-looking design evaluations and timely cooling system modifications are required.
) PID C0193A j Category II
Other Considerations: 'Ihe CFC issue affects all CP&L facilities. For CP&L nuclear plants, this project will be addressed systematically, thus avoiding possible limitations or restdctions on the use of cooling ' systems affecting equipment important to safety or basic plant operational requirements. In addition to impacts on the operation of electronic equipment, loss of cooling system operation can impact the capabilities of other systems. For example, with the loss of AOG cooling, the efficiency of the charcoal absorben is reduced, resulting in higher radiation release levels. III. CONCLUSION CP&L will punu: this study and any resulting hardware modifications. Complete and timely chiller system design capacity validations (using altemative refngennts) are needed. Where system hardware upgrades or other modifications are needed to entical chiller systems, their vigorous implementation will be required. IV. STATUS Study phase has been approved by Plant Review Gmup. V. TARGET COMPLETION Complete the study phase in December 1994. PROJECT MANAGER MARTIN DALIA-POZZA PID G0193A O l 1 l l O I
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- y. I i
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. TORUS, LINER PRESERVATION
[%i I. PURPOSE AND SCOPE ne purpose of this project is to complete preservation of the torus liner and components. Successful . completion of this project will help ensure that the liner will maintain integrity for the life of the plant.- - his project includes draining, inspection, and preservation of the Unit I and Unit 2 To:us. Inspections will include UT measurements of the liner at previously tested locauon and pit depth measurements to quantify i the localized cormsion rate. ; II. EVALUATION f i The key assumption is the liner will not last the life of the plant due to localized pitting corrosion. His assumption is based upon results obtained fmm underwater inspections on the Unit I torus liner and B211R1 Unit 2 data. Portions of the vapor zone are included from the preservation project once the vapor zone is not subject to localized pitting corrosion. 6 IIL CONCLUSION ne toms liner will be refurbished during the next two refueling outages. Preservation began on Unit 2 Torus during B211R1 and is approximately 50% complete. IV. STATUS ne project has been implementation phase approved by the Plant Review Group. V. TARGET COMPLETION l
- Unit 1 - B110R1 I Unit 2 - B212R1 ;
I PROJECT MANAGER BOB JERNIGAN PID G0249A i I i I i PID G0249A l Category II 1 ~
.1
l 1
-j . p. HYDR,.
O GEN WATER CHEMISTRY > r ; L PURPOSE AND SCOPE 'l
. i Upgrade the Units 1 & 2 Hydrogen Water Chemistry systems to allow the systems to inject enough i hydrogen to provule full core suppression of Intergranular Stress Corrosion Cracking (IGSCC) for short j periods of time for evaluation of poss%1e future raar-nus full core suppression igiectico (referred to a j high injectum rate, or about 3 ppm of H2 in feedwater). Actual anticipated operating injection rates in the ,
near future are expected to be substantially lower (referred to as moderate injecuan rates, or 1.2-1.6 ppm _. of H2), however, due to anticipated need for shielding not yet installed on the moisture separator reheaters j (MSRs), in addition, it is possible that the desired effects of full core suppression of IGSCC in the vessel j may be obtainable through the use of moderate injecuce rates coupled with other emerging technologies ' ; (e.g., noble metal coatings).- l Project Objectives or Goals and Expected Benefits: ;
- 1) Mitigate IGSCC in susceptible material in the reactor vessel and attached piping by controlling the ;
electrochemical potential (ECP) and dissolved oxygen concentranon in the reactor water. l
- 2) Prevent extended outages and costly in-vessel component repairs and/or replacements (such as the .t Unit I shroud repair), due to IGSCC. !
H. EVALUATION j l See project scope and purpose. HI. CONCLUSION i Industry testing has ide='~t that this project as described will provule full supprenion of IGSCC at a l
- liveable" radiation level however, it has not been proven over an extended period of time in an operating }
Pl ant. Based on the above, the scope of the original project has been reduced from a continuous 100 scfm ' injection rate to a continuous 40 scfm rate with provisions for short duration 100 scfm runs. IV. STATUS ' Implementation phase and initial testing is complete. 100sefm testing remains. ', Because of the elevated personnel doses due to hydrogen injection into feedwater, cobalt reduction options i are being evaluated. 'Ibese include replacement of upper control blade pins & rollers, installation of . passive depleted zinc injection systems, and proactive replacement of highWt valves / valve seats. V. TARGET COMPLETION j December 1994, for original project scope. ; PROJECT MANAGER CRAIG MARCH , PID 00251A i O . PID G0251A I Category II ! i s
R ' n UNIT 1 ZINC INJECTION - b I. PURPOSE AND SCOPE i,/ Project Desenption: his project includes the installation of a General Electric passive zine injection l . system (GEZIP). The GE contract authorization will include depleted zine oxide pellets for the initial load plus the estimated requirement for pellets for two years of operation. In addition to installation of . , the GEZIP skid, the project includes installation of approximately 200 feet of small-bore piping, valves, .j and supports (connections to feedwater and condensate piping) and installation of a 1 ton jib crane ! (hinged monrail with chain fall) over the GEZIP skid. 1 IIL CONCLUSION Key Assumptions and Risk Assessment: (1) ne anticipated benefits of zine injection, including significantly reduced (future) decon l requirements, are based on starting-up Unit I with the GEZIP skid in operation after a successful j decon. If the decon during the installation outage is unsuccessful, the anticipated benefits of zinc injection will be decreased during the succeeding cycle. (2) here is concern that the addition of zinc may make future decons of piping more difficult; < ongoing GE and VECTRA testing should verify that this concern is unwarranted (completion of testing is anticipated mid-December 1994). , 1 Alternatives Considered: Several alternatives for dose / cobalt reduction have been considered. Options ! included: (1) decon each outage; (2) replace upper pins & rollers with decreased decon requirements; (3) install zine injection with decreased decon requirements; and (4) install zinc injection gin replace upper pins & rollers with decreased decon requirements. The chosen option is the last of the four above. q
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4 (Note that the project alternatives considered are in addition to the replacement of high-cobalt valves / valve seats. His practice is integral to the maintenance practices and plant modification practices for the Brunswick Plant. Also, the alternative of accelerated replacement of all remaining original control blades was briefly considered but discarded due to significant cost and marginal improvement over upper pins & rollers replacement.) Consequences of Non-Authorization: Since it is anticipated that the use of a zine injection system will decrease the deposition of Co-60 in the piping oxide film, non-authorization of this project will result in higher personnel doses than would otherwise be anticipated. II. EVALUATION Project Objectives or Goals and Expected Benefits: Zinc injection provides reduction in shutdown drywell dose rates by reducing the Co-60 content in the piping oxide film. Reduction of shutdown drywell dose rates should lead to the elimination of some outage pipe decons; these decons cost =700K per outage and 2-3 weeks of outage time. , IV. STATUS Implementation Phase authorized by the Plant Review Group. V. TARGET COMPLETION Implementation 11/94-12/96 (he Unit 1 zine injection system will be started up at the conclusion of the B110R1 outage in spring 1995; however, the project will be held open pending the fulfillment of performance guarantees being negotiated with GE.) PROJECT MANAGER Bill Biggs PROJECT NUMBER 9400377 PID 9400377 Cateeory II
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.I REFUEL BRIDGE UPGRADE i I.- PURPOSE AND SCOPE.
Refuel bridge upgrades in both units am required in order to increase reliability and safety during outage - ! r critical path defueling and reloadmg. Malfunctions of various refuel bridge equipment have resulted in -
- outage delays. +l t
%is project upgrades or nplaces the refuel bndge equipment having the most munber of failuns. For - l example, this pmject replaces the mast assembly, platform drive system, control systems, air -.y. , f 6 and home take up reels with more rehable equipment. Also, the main hoist motor is being idu.b;.l.4 the ;
load cells are being replaced with solid state strain gauge type load cells with a continuous digital readout. - 4 Several other reliability -- *---- --=ts am being made in the om.y. /. air system. Obsolete positiorung equipment will be removed. He major part of the work has been -- 31:l %e .- --- rg work is to liw A lessons leamed in : both Units. This project will be successful when outage delays due to refuel bndge equipment ==1 Mons and failures
^l are E ' . .=:.=;'.
i IL EVALUATION )
'l Unit avadabdityis affected due to refuel bridge failures e= 4:rg outage critical pr.ths. Refueling operanons are outside the limitations of the PRA model since the curant model does not' consider plant shutdown ;
conditions. ; Nevertheless, refuehng nccidents are analyzed in the FSAR and are Lu ~s-it to nuchar safety. Since the . f refuel bridge is used in refuehng w i-w with heavy loads over the core and fuel poal, nuclear safety is , j j impacted directly. Personnel safety is also duectly L. ==1 due to hoist reliability concems. A reduction in p~.md exposure to ;=hbiis expected due to reduced maintenance mquirements in the assocated j radiation amas. His project is a plant enhancement since it replaces obsolete equipment and reduces mainteru.nce requvements. Economic Aspects: Costs due to outage delays and maintenance requvements will be Q :L==tly reduced ; by this pmject. Related Standards: his project is related to Work Mria,-..#. sit Policies for matenal condition and outage ) management. [ Other Considerations: His project does not require an outage to accomplish the physical modifications i but does require an outage forin core tesang. This project addresses work on Unit I under PCN M0006A ! and, under PCN M0067B, the work on Unit 2. i IIL CONCLUSION
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The overall benefits of this upgrade project are significant in that due to improved reliability of the I equipment, delays are expected to be reduced during citical path activities of defueling and reloading. This : project will be accomplished as scheduled.
]
h A/ PID M0066A Casegory II I l I i
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IV. ' STATUS Project is implementation phase approved by the Plant Review Group. V. TARGET COMPLETION Unit 2 July 19M - Complete Unit 1 June 1995. PROJECT MANAGER DAN MOORE . PID M0066A I O 1 1 O o
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k ; i SERVICE AND CIRCULATING WATER INTAKE AREA ENHANCEMENT I. PURPOSE AND SCOPE This is a comprehensive project to restore the mrJerial condmon of the Service Water System (SWS) and Circulatmg Water System (CWS) intake areas and structures. The purpose of the SWS is to provide water . from the Cape Fear River for lubncation and cooling of eqmpment in the Turbine Building, Reactor
- Building, Diesel Generator Building, Chlonnation System, and the CWS. The SWS supplies a nuclear header and a conventional header. The purpose of the CWS is to provide water from the Cape Fear River : I for the main condenser. Due to the relatively humid and corrosive saltwater environment, the physical plant areas and eqmpment associated with these systems require continued upkeep and y. .veion. The project -
includes such work as upgrades to corroded steel structural components, platforms, conduit, cable trays, and j handrails; piping repairs and replacenent; general repairs to non-corrosive components; refurbishment of i
, instrumentation and control systems; and general area improvements. The objectives of this project are to correct cunent material problems in the intake areas and to establish effective inspection and maintenance j programs that prevent future, significant deficiencies. l l
The success criteria for this project are that the specified restorstion work is completed as planned and that the associated equipment and general areas are returned to a corrosion-free condition. ; II. EVALUATION seb Ante ind This project is largely a plant enhancement, but it also affects other attributes. ! Enhancement of the SWS intake area will improve the system's availability in the event of an accident. If . this project is not completed and the intake area not maintained on a continuing basis, the increased - probability of a single SWS train being out of service would have a moderate impact on overall SWS ! availability. Since the SWS is designed to cool critical safety system components d rectly and can be cross- ! connected to the residual heat removal system in an emergency to provide additional reactor core flooding capability, this system is very important to nuclear safety. C-a -tly, this project provides moderate improvement in the availability of a highly important core-damage protection system (0.5 x 32). Corroded platforms and handrails are potential sources of personnel injury; therefore, this project will avoid cunent conditions from developing into a future concern in this area (0.2 x 29). Unit availability could be affected, but the gradual nature of the degradation and the general ability to make temporary repairs make this a low
- impact (0.2 x 12). Problems in the CWS can lead to loss of flow to the main turbine condenser, requiring turbine shutdown or loss of thermal efficiency (0.2 x 10). In addition, the SWS intake ares facilities are frequently and readily identified as deteriorated, and these conditions are an indication of inadequate maintenance (0.5 x 8). j Economic Annects! Long-term maintenance of these facilities will require additional annual expenditures above previous maintenance efforts. Thus, the base maintenance program will be expanded in parallel with these improvements in order to meet this obligation.- Failure to maintain this equipment could lead to more extensive SWS and CWS problems, and potential damage of equipment cooled or served by these systems.
Qther considerations Even though each unit has its own SWS and CWS, the intake facilities are common to both units and will require outage work to accomplish some of the electrical work, especially for controls. It is expected that a significant portion of the structural work can be done with the units in operation. , Nevertheless, some of the structural work may also be more readily accomplished during outages. l i i PID P0057B
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IIL CONCLUSION Failure to maintain control of the material condition of the SWS and CWS facilities could lead to system failures requiring plant shutdown. Deterioration of the intake structure and associated equipment is usually gradual enough that any resultant system failuru would be identified during normal operations and would primarily affect unit availability and capacity. i berefore, from a nuclear safety perspective, refurbishment and continued maintenance of these facilities is tensidered to be mandatory but not urgent. Nevertheless, since continued deterioration of these facilities could result in unit shutdowns, this project is being implemented as scheduled. IV. STATUS This project has been implementation phase approved by the Plant Review Group. This project is approximately 80% complete. E V. TARGET COMPLETION l 92-103 December 1995. 93-021 December 1995. i PROJECT MANAGER CHRIS HUGHES l PID P0057B l l O i
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I REACTOR RECIRCULATION SYSTEM CHEMICAL DECONTAMINATION (,.__) v' I. PURPOSE AND SCOPE
- Chemical decontammation of the Reactor Coolant Recin ulation system (RCR) is currently performed each -l refueling outage due to the proven and immediate dose mings which will result. He RCR is the largest I single contributor to drywell dose rates during outages. Decontaounation is performed with the use of I chemical solvents. He solvents are injected into the RCR system, heated, and brought into contact with j the contaminated oxide film present inside the piping. %e contanunation is then removed with the solvent and disposed of. He RHR and RWCU systems have a lesser impact on total site exposure. Chemical decontarrunation of these systems was gifm..d initially and not planned to be repeated in near term i subsequent years. Dose rates and exposures frorn these systems will be monitored such that follow-up decontammations can be planned if necessary.
II. EVALUATION Chemical decontanunation during outage B110R1 is expected to save 146 person-rem. Chemicd decontanunation of RCR pipire in outages B212RI and B111R1 is included in the BNP Master Project Plan for 1995. III. CONCLUSION Chemical decontammation is an established dose reduction techrsque at BNP. This program will be i implemented as scheduled. IV. STATUS O Decontanunation will be performed during outage B110RI. Chemical decontammation will be performed as part of a new multi-site contract. Decontamination services will be provided by a single vendor as part of the contract. %e contract is currendy it. the bid process, and will be approved prior to implementation in BIIORI. # V. TARGET COMPLETION y Ongomg project in Unit One and Two. PROJECT hMNAGER CHUCK RAINES PID R0123A i t i r FID R0123A ; Category II I l l l
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I <~ s SPENT FUEL POOL COOLING ASSIST - PIPING & PENETRATIONS
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I. PURPOSE AND SCOPE Currently, the spent fuel cooling system is not capable of providmg cooling for a full core offload until appmximately 32 days after shutdown; therefore, the Residual Heat Removal (RHR) system must armam in operation during significant portions of outages which require fuH core off-load in orar to pmvide adequate cooling. His requirement inhibits RHR system maintenance and prolongs outages. Tuuyorary heat exchangers and cooling towers can be used to supplement the existmg spent fuel cooling system and accomplish this cooling function, allowmg increased flexibility for RHR maintenance. Since a core offload can be accomplished in about 10 days, the supplemental cooling capability can save about 22 days ofoutage time. He scope of this pmject is to instaB pennanent auxiliary fuel pool coohng system penetration.s, piping, and valves in the Unit 1 Reactor Buikling. Unit 2 installation is complete. When this project is completed, the permanent piping may be connected to supplemental spent fuel cooling equipment during refueling outages. Installation and operation of the SSITC equipment is pedormed by project R01231. H. EVALUATION ScheduleIndex: 18. He use of permanent piping significantly improves the viability ofusing an altemate spent fuel pool cooling system. His aHows RHR system maintenance flexibility during outages; this minimizes the length of refueling outages, ira. rig unit availability (1.0 x 12). Permanently installed piping rrurumizes the need to install and remove temporary system piping, reducing radiation exposure (0.5 x 9). He use of pennanent piping and the increased availability of the RHR system without extensive temporary cooling system setup work constitute a plant enhancement (0.2 x 8). Economic Aspects: %e use of pennanent piping for supplemental spent fuel pool cooling is more cost effective than the use of tuuyerary piping. Overall, the use of the altemative cooling sptem for spent fuel (V) cooling allows increased RHR system maintenance and decontanunation flexibility, significantly reducing the length of refueling outages. Related Standards his project is related to Work Management Policies for human resources and outage management. Other Comiderations: %e scope of this project is limited to the installation of pennanent piping and valves for the supplemental cooling system. ID. CONCLUSION Eis project wiB significantly increase the viabili- of using supplemental cooling of the spent fuel pool, allowing reductions in the length of refueling outages as a result of not having to operate the RHR system for this purpose. He savings are eignificant, so this project will be completed as scheduled. IV. STATUS Design is complete and installation in Unit I has started Pmject is implementation phase approved by the Plant Review Group. Work in progress with a scheduled completion date of 12/29/94. V. TARGET COMPLETION December 1994 CIRJCK RAINES pl s PROJECT MANAGER PID R0123M w/ PID R0123M Category II
t O CATEGORY II SMALL PROJECT LISTING l FID TARGET l NUMBER PROJECT TITLE COMPLETION : 02549A SCREEN WASH PUMP UPGRADE 12/94 ; 05307A DC BATIERY LOAD FIUDY 12/94 t
*05806A RADWASTE EFFLUENT RELEASE LINE REROUTE 12/95 06650A REACTOR PRESSURE VESSEL DIERMAL CYCLING EVALUATION 12/94 1 08893A CONTAINMENT PENEIRATIONS 0696 ,
31856B PIRE BARRIER UPGRADE 12/94 . 80203A DIESEL GENERATOR OIL 12 VEL ANNUNCIATOR 12/94 i i 84489B 480 VOLT VITAL MCC REWORK 12/94 00015A SMAllMODS 12/96 l 00050A SERVICE WATER TASK ACITVITIES 12/94 G0083A INSTRUMENT AIR COMPRESSORS 12/94 00218A MAKE TEMPORARY POWER FEEDS PERMANENT 12/95
- Indicates project change from August 1,1994 update.
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