ML20071P149
| ML20071P149 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 08/02/1994 |
| From: | CAROLINA POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML20071P139 | List: |
| References | |
| PROC-940802, NUDOCS 9408090170 | |
| Download: ML20071P149 (171) | |
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O BRUNSWICK NUCLEAR PLANT THREE-YEAR BUSINESS PLAN PERFORMANCE IMPROVEMENT INITIATIVES & PROJECTS O
Update V O
9408090170 940802 PDR ADOCK 05000324 PDR p
BRUNSWICK NUCLEAR PLANT THREE YEAR BUSINESS PLAN O
PERFORMANCE IMPROVEMENT INITIATIVES & PROJECTS TABLE OF CONTENTS 4
I.
PERFORMANCE IMPROVEMENT INITIATIVES Initiatives Summary Initiatives Plans II.
PROJECTS q(_/
Category I & II Projects List Projects Summary Category I Projects Plans Category II Projects Plans Small Projects O
,/)
INDEX OF ACTIVE INITIATIVES U
INITIATIVE NO.
TITLE SPONSOR TY101 Integrated Planning & Scheduling B.
Helme TY102 BNP Integrated Scheduling and Three-G.
Honma Year Plan Administration TY103 Corrective Maintenance Backlog G.
Barnes Reduction TY104 Business Planning Improvements J.
Martin TY105 Inventory Control J.
Ferguson TY201 Effective Performance J.
Ferguson 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 C.
Heath TY206 Develop and Implement Brunswick R. Johnson
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Facility Improvements TY301 Improved Procedure Control and C. Lewis 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.
Lewis TY309 Improve Management of Regulatory R,
Lopricre
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Commitments TY401 Site Communication Plan M.
Harritt TY501 Preventive / Predictive Maintenance C.
Pardee Program Improvements TY502 Corrosion Preventive Maintenance C.
Pardee TYS05 Cooling Water Reliability Program C.
Pardee TY506 Plant Engineering Program Upgrade C.
Pardee
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TYS07 Inservice Inspection and Inservice C.
Pardee Testing Improvement Program
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INITIATIVE Q
NO.
TITLE SPONSOR TY510 Develop and Implement Preservation B.
Deacy Program to Upgrade Material Condition TYS11 ALARA Initiatives, Source Term J. Gawron Reduction TY512 Environmental and Chemistry Program J.
Gawron Improvements TY601 Human Performance J.
Cowan TY602 Reactor Vessel Internals E.
Willett Preservation TY607 Improve BNP's Competitive Position J. Martin D.
McCloskey TY604 Reduce Regulatory Burden R.
Lopriore i
TY605 Improve Refueling Outage Management J.
Cowan INDEX OF DELETED INITIATIVES i
+
(
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INITIATIVE NO.
TITLE SPONSOR TY106 Outage Length Reduction U1/U2 Outage Managers TY207 Nuclear Revision Control System C.
Lewis 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 TY503 Design Basis Reconstitution Program B.
Grazio TY504 Equipment Data Base System (EDBS)
B. Grazio TYS08 AC Source Improvement Project B. Grazio TY509 Management of Temporary and C.
Pardee Substandard Conditions TY513 Megawatt Improvement Projects C.
Pardee TY514 Improve Plant HVAC Systems C.
Pardee fs TYS15 Fire Protection Upgrade Project C.
Pardee r
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O INITIATIVES SUhih1ARY EXECUTIVE
SUMMARY
INTRODUCTION Improved performance continues at Brunswick as the BNP Three-Year Business Plan reaches the mid-point of its implementation schedule. Continued improvements are being realized in the areas of planning, scheduling, and commitment achievement; human performance; work
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processes; communications; and system reliability and material condition.
PLAN ACCOMPLISHMENTS Saccessful performance indicators noted since the May 4,1994 update include 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 smooth and successful restart of Unit 2 from the recent refueling outage.
Four initiatives have been identified as task complete since the last update. They include O
initiatives TY201, Effective Performance Management / Total Quality; TY204, Establish "World Class Performance" Culture; TY301, Improved Procedure Control and Content; and TY305, Clearance Process Improvements. The next phase of these task complete initiatives is to implement self-assessment effectiveness reviews.
Additional performance improvements are being realized from five (5) initiatives that are still being implemented and are not task complete. A continued downward trend in the corrective maintenance backlog is being realized as a result of implementing initiative TY103, Corrective Maintenance Backlog. A management succession plan has been developed through 1998 and management rotation is being realized as a result of initiative TY205, Supervisory / Management Improvements. Implementation of initiative TY202, Training Improvements has resulted in the following: Development of Advanced Radiation Worker Training; enhanced operator teamwork in simulator training and plant operational activities; implementation of a technical training mock-up; Establishment of the Training Advisory Board; and improved operations, technical, and support training through line organization training involvement. Implementation of initiative TYS10, Develop and Implement Preservation Program to Upgrade Material Condition has been acceleran:C and is projected to complete in 1995, approximately two years ahead of schedule. Progress continues on initiative TY206, Develop and Implement Brunswick Facility Improvements. The Master
' Facilities Plan has been developed and changes to the plan are managed by the Project Review Group (PRG) and Three-Phase Authorization processes. Construction has been completed on several facilities including the Technical and Administrative Center (TAC),
O Snubber Repair and Hot Calibration Shop, E&RC Laundry and Chemical Storage Facility,
Sewage Treatment Facility, Tool Decontamination Facility, and Irw-Level Weste Storage Facility. Construction of the Hands-On Training Facility, Operations / Maintenance Support Building, and Technical Support Center / Emergency Operations Facility (EOF) is in progress and nearing completion.
Brunswick's ability to self-assess continues to improve and a mid-year " normal business" self-assessment resulted in improvements to three (3) initiatives to achieve the desired objectives.
Initiative TY303, Improve BNP's Ability to Identify and Correct Problems was enhanced to develop corrective actions for the timeliness of ACRs, improve ACR information exchange
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across functional lines, and to place more focus on less consequential (precursor) events.
i Enhancements to initiative TY501, Preventive / Predictive Maintenance Program Improvements, will focus on adopting a Reliability Centered Maintenance (RCM) Program, reducing the existing preventive maintenance (PM) tasks, developing standard preventive maintenance activities, reducing short term preventive maintenance manpower needs, and RCM evaluations of all PM tasks in progress. Improvements to initiative TY511, ALARA Initiatives, Source Term Reduction include the incorporation of an aggressive correction action study for achieving successful 1995 decontamination and directing management focus to the area of environmental / radiological control.
In addition, six (6) new initiatives were added to the plan:
TY601, Human Performance; TY602, Reactor Vessel Internals Preservation; TY603, Improve BNP's Competitive Position; TY604, Reduce Regulatory Burden; and TY605, Improve Refueling Outage Management.
CURRENT STATUS Sixteen (16) of the forty (40) initiatives identified in the original BNP Three-Year Business Plan are ongoing, eleven (11) initiatives are task complete, and thirteen (13) initiatives have-been closed and superseded by other projects or work processes that are achieving the desired improvements. Three (3) initiatives have been augmented to ensure the desired results are obtained and that the initiative is effective. Five (5) new initiatives have been initiated to address areas of management focus.
FUTURE FOCUS 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.
l Management of the BNP Three-Year Business Plan to ensure trends of continuous
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improvement are maintained will continue. Aggressive self-assessment activities will be used to assess the effectiveness of the initiatives and to ensure successful performance is realized.
Modifications to existing initiatives, or the 6 'lopment of new initiatives will occur as areas requiring improvement are identified.
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INITIATIVES STATUS SUM 3fARY (40 Original Initiatives)
INITIATIVE TITLE STATUS TY101 Integrated Planning & Scheduling Initiative is task complete. Task closure documentation has been provided.
Effectiveness self-assessment scheduled.
TY10'2 BNP Integrated Scheduling and Initiative is task complete. Task closure Three-Year Plan Administration documentation has been provided.
Effectiveness self-assessment scheduled.
TY103 Corrective Maintenance Backlog Five (5) tasks remain ongoing. Initiative Reduction scheduled to task complete in 1995.
TY104 Business Planning Improvements Initiative is task complete. Task closure documentation has been provided.
Effectiveness self-assessment scheduled.
TY105 Inventory Control Four (4) tasks remain ongoing. Initiative scheduled to task complete in 1995.
TY106 Outage Length Reduction Initiative closed per August,1993 update to Three-Year Plan. Works scope is being performed under Strategic Issue, Outage Management. Initiative TY605 has been established to cover this issue.
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TY201 Effective Performance Mgmt/ Total Initiative is task complete. Task closure Quality documentation is in process. Effectiveness self-assessment scheduled.
TY202 Training Improvements Eight (8) tasks remain ongoing. Initiative scheduled to task complete in 1995.
TY203 Utilization /Imer-Unit Support Initiative is task complete. Task closure documentation has been provided.
Effectiveness self-assessment scheduled.
TY204 Establish "World Class Performance" Initiative is task complete. Task closure Culture documentation is in process. Effectiveness self-assessment scheduled.
TY205 Supervisory & Management One (1) task remains ongoing. Initiative Development scheduled to task complete in 1994.
TY206 Develop and Implement Brunswick Three (3) tasks remain ongoing. Initiative Facility Improvements scheduled to task complete in 1994. Master j
Facilities Plan has been developed and is being implemented. Additions, changes, and deletions to Master Facilities Pian are managed through PRG.
TY207 Nuclear Revision Control System Initiative closed because scope is currently covered within the action plan developed by
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Nuclear Business Operations (NBO) in their 1
(O response to NAD Assessment C-SP-93-03.
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l INITIATIVE TITLE STATUS l
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TY208 Integrated Computer Support Initiative closed per August,1993 update to i
Three-Year Plan. This scope of work is included in an NGG initiative to reorganize and establish computer and telecommunications organizational consistency among the three nuclear sites.
1 TY301 Improved Procedure Control and Initiative is task complete. Task closure 4
Content documentation is in process. Effectiveness self-assessment scheduled.
TY302 Improving the Modification Process Two (2) tasks remain ongoing. Initiative scheduled to task complete in 1995.
TY303 Improve Ability to Identify and Mid-year self-assessment determined further Correct Problems actions are required to obtain desired results.
Additional tasks incorporated to ensure desired j
effectiveness.
TY304 Backlog Reduction Initiative is task complete. Task closure documentation is in process. Effectiveness self-assessment scheduled. Backlog priorities and targets have been established and will be tracked via in-house management and tracking processes.
O TY305 Clearance Process Improvements Initiative is task complete. Task closure v
doeurnentation is in process. Effectiveness self-assessment in progress.
TY306 Health Physics Program initiative closed per August,1993 update to Improvements
'Ihree-Year Plan. Initiative tasks identified under other initiatives, programs, or existing in-house processes.
TY307 Implement / Augment BNP Local Area Initinive closed per August,1993 update to Network inree-Year Plan. Work scope is being performed in coordination with the corporate plan for installing company-wide LANs.
TY308 Centralized Document Control Two (2) tasks remain ongoing. Initiative Program scheduled to task complete in 1995.
TY309 Improve Management of Regulatory Initiative is task complete. Task closure Commitments documentation is in process. Effectiveness self-assessment scheduled.
TY310 Assess Implementation of SAT ltems Initiative closed per August,1993 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 task complete. Task closure p
documentation has been provided.
Q Effectiveness self-assessment scheduled.
INITIATIVE TITLE STATUS TY501 Preventive / Predictive Maintenance Mid-year self-assessment determined further Program Improvements actions are required to obtain desired results.
Additional tasks incorporated to ensure desired effectiveness.
TYS02 Corrosion Preventive Maintenance Two (2) tasks remain ongoing. Initiative scheduled to task complete in 1995.
TY503 Design Basis Reconstitution Program initiative closed per August,1993 update to Three-Year Plan. Work scopes identified under projects B0018A, B0019A, BNT622, G0017A, and 05644A.
TY504 Equipment Data Base System (EDBS)
Initiative closed per August,1993 update to Three-Year Plan. Work scope is identified under project F0025C.
TYS05 Cooling Water Reliability Program Seven (7) tasks remain ongoing. Initiative scheduled to task complete in 1995.
TY506 Plant Engineering Program Upgrade Three (3) tasks remain ongoing. Initiative scheduled to task complete in 1995.
TY507 Inservice Inspection and Inservice Three (3) tasks remain ongoing. Initiative Testing Improvement Program scheduled to task complete in 1995.
TYS08 AC Source Improvement Project Initiative closed per August,1993 update to Cs) s Three-Year Plan. Work scope is identified under project G0110A.
TY509 Management of Temporary and Initiative closed per August,1993 update to Substandard Conditions 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 Preservation One task remains ongoing. Five-Year Painting Program to Upgrade Material Plan has been developed and implementation Condition accelerated. Initiative scheduled to task complete in 1995. Additions, changes, and deletions to plan are managed through PRG.
TY511 ALARA initiatives, Source Term Mid-year self-assessment determined further Reduction actions are required to obtain desired results.
Additional tasks incorporated to ensure desired effectiveness.
TY512 Environmental and Chemistry One (1) task remains ongoing. Initiative Program Improvements scheduled to task complete in 1994.
TYS13 Megawatt Improvement Projects Initiative closed per August,1993 update to Three-Year Plan. Work scope is being performed through internal resources and processes, d
TY514 Improve Plant HVAC Systems Initiative closed per August,1993 update to Three-Year Plan. Work scope is being i
performed through internal resources and processes.
INITIATIVE TITLE STATUS V
TY515 Fire Protection Upgrade Project Initiative closed per August,1993 up6te to Three-Year Plan. Work scope is being performed through internal resources and processes.
NEW INITIATIVES INITIATIVE NO.
TITLE TY601 Human Performance TY602 Reactor Vessel Internals Preservation TY603 Improve BNP's Competitive Position TY604 Reduce Regulatory Burden TY605 Improve Refueling Outage Management mU l
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Brunswick Performance Improvement Initiative n o.,
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Corrective Maintenance Backlog 12/92 TY103 Reduction Strategy:
To develop and implement management processes for corrective maintenenace backlog to both eliminate the current backlog and maintain manageable levels in the future.
Impact / Benefits:
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.
c)
Ensure timely repair of plant equipment to sustain good plant material condition.
d)
Enhance the corrective maintenance work process allowing effective utilization of manpower.
O s a ser:
r rriority George Barnes Medium
Corrective Maintenance Backlog Reduction - TY103 1994 1995 1996 1997 Description Action Sponsor J lF%!lAhtlJ lJ lAlSl0lNlD JlFlMlAlMlJlJlAlSl0lNlD J lF ftlAhtlJ lJ lAlSl0lNlD J lF ftlAlMlJ lJ lAlSlOjNlD TY103 - 1 E Develop and implement an improved Bob IIelme 74 p y/// p gl trouble tag / minor maintenance process.
TY103 - IF Determine appropriate cycle 9 backlog Neal Gannon 74 y/ w /g pys y/g g yg g;7A (WR-JO) reduction goal to be attained by June 1995.
TY103 - 2A Reduce existing Unit 2 Corrective George Barnes g
Maintenance Backlog and achieve goal established by the Unit 2 Plant Manager.
TY103 - 2B Reduce existing Unit I Corrective Neal Gannon yg yg y/ M z yg ygg yg gyz sy/A Maintenance Backlog and achieve goal established by the Unit i Plant Manager.
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O Corrective Maintenance Backlog Reduction - TY103 1994 1995 1996 1997 Description Action Sponsor J lFlMlAlMlJ lJ lAjSl0lNlD JlFlMlA}MlJlJlAlSl0lNlD J lFlMlAlMlJ l J lAlSl0lNlD J lFlMlAlMlJ l J lAlS l0lNlD TY103 - 3A Evaluate performance and implement George Barnes necessary actions for effective corrective backlog management.
TY103 - 3B Provide necessary staffing to achieve George Barnes ypppggMMpp p sfy p M M pfy m Unit 2 outage corrective maintenance goals per the outage schedule.
TY103 - 3C Provide necessary staffing to achieve Neal Gannon VMsppppsm Unit I outage corrective maintenance goals per the outage schedule.
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TY103 - 4A Evaluate and implement work process Bob Helme improvements to enhance scheduling and work implementation.
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Brunswick Performance Improvement Initiative
Title:
Ori gin:
Number:
Inventory Control 12/92 TY105 Strategy:
To effectively reduce and control the materrial inventory while supporting plant needs for replacement parts and other material.
Impact / Benefits:
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a)
Entture accuracy in the storage of material.
b)
Improved cycle inventory process accuracy in numbers of stored items.
c)
Reduced amount of inventory dollars.
d)
Improved automation techniques for inventory control.
sr= w r:
rrierny:
John Ferguson Medium
Inventory Control - TY105 1994 1995 1996 1997 Description Action Sponsor J lFjMlA}MlJ lJ lAlSl0lNlD JlFlMlAlMlJlJlAlSl0lNlD JlFlMlAjMlJlJlAlSlOjNlD JlFlMlAlMlJlJlAlSl0lNlD T(105 - 5A Complete the implementation of the John Ferguson W M M /A second barcoding segment.
TY105 - SC Complete the second segment of the John Ferguson ty/g y// M M g4 100% inventory.
TY105 - 8D Complete the third segn.ent of the John Ferguson V M g y3 74 yz yA 100% inventory.
TY105 - 8E Complete the final segment of the John Ferguson Wgyyg/MMA 100% inventory.
TY105 - 9A Modify procedures for inventory John Ferguson WMgj control improvements.
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v Inventory Control - TY105 1994 1995 1996 1997 Description Action Sponsor J lF htlAhtlJ lJ lAlSl0lNlD J lFhtlAhij J lJ lAlSl0lNlD JlFlMlAlMlJlJlAlSlOlNlD JlFhtlAhtlJlJlAlSl0lNjD TY105 - 17A Complete evaluation for removing R. White
- ygrgeggy; 154 account for tools.
TY105 - 18A Vendor stocking program is R. Stroud g
implemented for appropriate items (insulation, paint, steel, etc.).
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Brunswick Performance Improvement Initiative Titlet Otagint Numbert Effective Performance Management 12/92 TY201 Strategy:
Improve performance in the areas of safety, production, and cost by effective utilization of human resources.
This initiative fully implements Effective Performance Management (EPM) at Brunswick.
,O Impact / Benefits:
a)
Clear expectations in support of the mission are established for each employee.
b)
The expectations and employee performance are peiodically reviewed to ensure that the expectations support the mission and that performance meets expectations.
c)
Employee development plans are developed and reviewed such that each employee may develop to maximum potential.
f O
Sycaso r:
Priority John Ferguson High
Effective Performance Management - TY201 1994 1995 1996 1997 Description Action Sponsor J lF%ilA%flJ lJ lAlSlOlNjD J lF%1lA%1lJ lJ lAlSlOlNl0 J lF jMlA%1lJ lJ lAlSl0lNlD J lF%1lA%tlJ lJ lAl5l0lNlD TY201 - 7B Development Plans for Section John Ferguson M
Managers are complete.
TY201 - 7C Development Plans for Unit Managers John Ferguson are complete.
TY201 - 7D Development Plans for Supervisors John Ferguson are complete.
TY201 - 7E Development Plan for All Employees John Ferguson is complete.
TY201 - 7F lacorporate Development Plan results John Ferguson yggggggygggggggy,p;y,j into Assessment Program.
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Brunswick Performance Improvement Initiative
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Titler Origint Numbers (a~)
Training Improvements 12/92 TY202 strategy:
Implement training upgrades that will develop and sustain a highly qualified plant staff by the following a)
Identifying areas of training weakness.
b)
Improving the use of the Systematic Approach to Training.
c)
Providing additional training to key personnel.
d)
Improved use of industry standards as bases for training programs.
e)
Specifically upgrading the following training programs:
Engineering Support Non-Licensed Operator Hands-On Craft Personnel
'N Impact / Benefits:
a)
Well trained and highly-qualified workforce.
b)
Improved individual employee development.
c)
Sustaining a high-level of technical qualification for supervisors and managers, d)
An efficient and effective training process.
e)
Maintain accreditation of training programs.
f)
Assure 100% pass rates on NRC License Exams, g)
Achieve significant improvement in line ownership, involvement, and oversight of training, h)
Significant improvement in the SRO level systems knowledge by supervisors and managers.
Spnsort Priotsty:
Keith Ahern High
Training Improvements - TY202 1994 1995 1996 1997 Description Action Sponsor J lF %1lAlMlJ lJ lAlSl0lNlD J lFhtlAlMlJ lJ lAlSl0lNlD J lF %tlA%1lJ lJ lAlSl0lNjD JlFlP1lAlMlJlJlAlSlO]NlD TY202 - 12A Upgrade non-licensed operator Mike Williams
- yg y g gs y s gg yg 7/g 5y, training programs for Auxiliary and Radwaste Operators. Thb includes job and task analysis and development of qualification cards and lesson material.
TY202 - 131 Develop lesson plans and conduct Cecil Gurganus
- ygyM M M g7M s,74/g w s p p p M 7/A hands-on training for maintenance craft personnel.
TY202 - 14U Develop, validate, and approve Mike Williams yg/g y/g ygg y p s y p f7z Simulator Guides for use during simulator training.
TY202 - 15A Develop and provide performance Paul Mazzola yggygyg/gr7ggygyzygyA based Emergency Response Organization initial and refresher training.
TY202 - 15Q Develop and provide an Advanced Mike Williams
- 54yggyzyzygegygeg744ysg5pysgyggyMgy, Systems Training Course for managers.
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O Training Improvements - TY202 1994 1995 1996 1997 Description Action Sponsor J lF htlA%flJ lJ lAlSl0lNlD J lF %1lA%flJ lJ lAlSl0lNlD J lF %tlA%1lJ lJ lAjSlOjNlD J lFhtlA%1lJ lJ lAlSlOlNlD TY202 - 18A Improve the implementation of the Keith Ahern
'ss/pssppsg e
Systemr. tic Approach to Training to meet INPO criteria and upgradejotVtask analyses and task-to-training matrices for accredited programs.
TY202 - 33A Conduct stafTmg and instructor Keith Ahern yppep/psspA training assessments as described in the Corporate Improvement Initiatives.
TY202 -34F Develop a prioritized list and procure Cecil Gurganus c/ p s p s s p y p p s p s s pfyp p s z hands-on training mock-ups and models.
TY202 - 38A Complete the plant simulator Bill Geise g/pppppppppppysppjj upgrade program.
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Brunswick Performance Improvement Initiative f
Ticies Crigin Number Establish "world class Petormance" 12/92 TY204 j
culture j
i Strategy:
Establish a culture in which World-Class performance is the highest priority and where continuous improvement is way-of-life.
Impact / Benefits:
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a)
Organizational structure and staffing aligned to support the vision of World-Class performance, b)
Consistent and continuous communication of the new culture and business direction providing the focus for all business activities.
c)
Development and execution of a plan for effective use of human resources.
G(V sponsor
- resorsey, Dennis McCloskey High
Establish "World Class Perf'ormance" Culture - TY204 1994 1995 1996 1997 Description Action Sponsor JlF%1lA%1l3lJlAjSl0lNlD J lF %1lA%1]J lJ lAlS jOlNlD JlF%tlA%tlJlJlAlSl0lNlD J lF%1lAhtlJ lJ lAlSl0lNlD TY204 - 3 A Management and employees will be Galen Jones y
provided the results of the employee survey.
TY204 - 4A The results of the employee survey Dennis McCloskey M
will be analyzed and new initiatives w-ill be developed based on the analysis.
TY204 - 1I A Develop a iluman Dennis McCloskey gepggyA Resource / Organizational Development Plan.
TY204 - 12A Managers training will be conducted Pat Jordan syg yfyg w A for the lluman Resource / Organizational Development Plan.
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Brunswick Performance Improvement Initiative Titler OrJglas h rt
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Supervisory and Management Development 12/92 TY205 N
strategy:
This initiative will implement the following Corporate Improvement Initiatives:
Supervisory Assessment Center Supervisory Development Program Management Development and Succession Planning Impact / Benefits:
a)
Provide a consistent assessment process to assist in the selection of motivated, high-performing individuals for supervision.
1 b)
Provide supervisory training to incumbent supervisors.
c)
Enable the site organization to fill planned and unplanned vacancies with well-prepared supervisors and managers.
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1 sponsort priority:
Chris Heath High
Supervisory and Management Development - TY205 1994 1995 19 %
1997 Description Action Sponsor J lFlMlA%1lJ lJ lAlSlO[NlD J lFlMlAhtlJ lJ lAlSl0lNlD J lF%1lA}MlJ lJ lAlSl0lNjD J lF %1lAhtlJ lJ lAlSlOINlD TY205 - 10C High-Potential non-managers will Bowin Lindgren
- py//gyffA be identified for selected positions.
TY205 - 10D Development plans will be drafted Section Managers
- yzyzyzygggfa and discussed with high-potential non-managers and supervisors.
ap 1 TY205 MPP S
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Brunswick Performance Improvement Initiative A
rar2.,
- origin, numo.r, N_,
Develop and Implement Brunswick 12/92 TY206 Facility Improvements Strategy:
Improve the overall condition of Brunswick facilities by:
a)
Designing and constructing the following new facilities:
Operations / Maintenance Building Single Point Access Facility Technical Training Facility Snubber Repair and Hot Calibration Shop Technical and Administrative Center (TAC Building) j 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 U grade p
Paint and Sandblasting Facility
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Warehouse "C" Renovation
(,,)
Site Paving - Asphalt Paving of Stoned Areas 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, i
i 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.
O Sponsot Priothtyr Roy Johnson High
- -m m
- -.ma
-m-- m-
Develop and Implement Brunswick Facility Improvements - TY206 1994 1995 1996 1997 Description Action Sponsor J [F htlA htlJ lJ lA!S l0 lN ID J lF KilA htlJ lJ lA lS l0lN !D J IF hilA hilJ lJ JAlS IOlN ID J lF ht(A htlJ lJ lA lS lO N ID TY206-2A - Remove Trailers and Temporary Bob Deacy
-sw Buildings TY206-1I A - Implement the Master Site Factilities Roy Johnson te os:> -
Plan TY206 - 41 A Renovate Tool Decontamination Bob Deacy acs -
Room, Material Storage Facilty, and Administrative i
Annex.
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Brunswick Performance Improvement Initiative Titiet Origin:
Numbert t
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.
Impact / Benefits:
O 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.
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- rriorley, Carol Lewis Medium
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Improved Procedure Control and Content - TY301 1994 1995 1996 1997 Description Action Sponsor JlF%1lA%1lJlJlAlSl0lNlD J lFlMlA%1lJ lJ lAlSl0lNjD J lF lMlA}MlJ lJ lAlSl0lNlD J lF %1lAlMlJ lJ l AlSl0}NlD TY301 - 10A Fullimplementation of the new Carol Lewis
- y,y g r////A procedure control process.
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Brunswick Performance Improvement Initiative
Title:
Ottgla:
Nuaber:
i Improving the Modification Process 12/92 TY302 Strategy:
Improve the plant modification process to reduce the overall investment of both human and financial resources and to prcvide timely response for needed modifications.
1 Impact / Benefits:
O 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.
i 3,,,
r:arsey:
Bob Grazio High
Improving the Modification Process - TY302 1994 1995 1996 1997
.-escription Action Sponsor J lF hflA bllJ lJ lAlS lOlNID J lF htlA hflJ lJ IAlS LOIN lD J lF hflA htlJ lJ lAIS l0lN lD J lF htlA hflJ lJ. AlS !O N ID TV302 - 6E Complete orientation training for Paul Cafarella incumbent engineers involved in the design process-l TY302 - 6F Complete position specific Paul Cafarella training for incumbent engineers invch ed in the design process.
i Pm 1 TY302.MPP
Brunswick Performance Improvement Initiative fre2.,
- origin, nu.o.r, Improve Ability to Identify and Correct 12/92 TY303 Problems 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 l
Program.
Improve the Corrective Action Program through the following l
actions:
l
\\
l l
a)
Improve training l
b)
Establish effective sub-programs c)
Implement effective trending and tracking.
d)
Place more focus on less consequential (precursor) events tracking and trending e)
Improve process for exchanging ACR information across functional lines l
k Impact / Benefits:
a)
An established culture of continuous improvement, b)
Clear and consistent management direction enforcing the expectation for effective self-assessment and the accountability for effective corrective action.
c)
Early identification of problems, by responding to precursor events and findings identified through self-assessment.
d)
Management attention focussed on areas needing improvement.
e)
Accurate identification of the root causes of problem areas.
f)
Decreased number of plant events and violations.
g)
Effective application of lessors learned at other plants, worldwide.
s a or,
- priorsey,
\\
s Rich Lopriore High
Improve Ability to Identify and Correct Problems - TY303 1994 1995 19 %
1997 Description Action Sponsor J lF %ilA%tlJ lJ lAjSl0lNlD JlF%1lA%1lJlJlAjSl0lNlD JlF%11AlMlJlJlAlSl0lNlD JlF%1lA%1lJlJlAlSl0lNlD TY303 - 111 Perform a self-assessment on the Bruce Altman
- ygygyA effectiveness of the self-assessment progra.n.
TY303 - IJ Perform a self-assessment based on Bruce Altman y
the results of the 1993 SALP Report.
TY303 - 2L Revise PLP-04 to require key CAP Bruce Altman y
corrective actions followup effectiveness reviews; reinforce cross functional area ACR owner responsibilities; improve ACRinvestigation response times; document Level III ACR causes.
TV303 - 31 Perform annual self-assessments of Bruce Altman 7,7,74 74 7p&r/7#4 744YA7#4Y4YM4'M7#4747MAYMM7#/M/////#//M///// M M M M M M //h CAP program to confirm proyess and adjust goals.
TY303 - 3K Improve the efficiency of the CAP Bruce Altman y p p4 y g g gd computer program by adding improvement area tracking feature, creating ability to produce 5 standard trend reports; and improving system response time by 25%.
I Page1 TY303 MPP O
L-___ _ _ _ _ _ - - - - - - - - - - - - _.. _ _
i
O O
O Improve Ability to Identify and Correct Problems - TY303 1994 1995 1996 1997 Description Action Sponsor JjFlMlAlMlJlJlAlSl0lNlD J lFlMlAjMj J lJ lAlSl0lNlD JlFlMlAlMlJlJ{AlSjolNlD J lFlMlAlMlJ lJ lAlSlOjNlD TY303 - 3L Improve the effectiveness of CAP Bruce Altman g
subprograms by implementing a Desktop Guide to provide guidance to reinforce management i
expectations that trend analysis and reporting is performed as required and is consistently applied.
~TY303 - 4A Combine all site observations, Bruce Altman wegwssssszysssssp/m inspections, surveillances, self-assessments, etc.
into a relational database that will form an l
cffective diagnostic tool for improving plant human performance g
TY303 - 4B 1mplement electronic data entry and Bruce Altman g,ysszwpjypsz processing of Adverse Condition Reports (ACRs) l l
l TY303 - 4C Develop mechanisms to facilitate the Bruce Altman wszwppj exchange of ACR information across functional lines and prompt action on issues that cross functional boundaries.
Page 2 TY303.MPP
1 Brunswick Performance Improvement Initiative i
n eles crista:
Numbert Clearance Process Improvements 12/92 TY305 Strategy:
4 Evaluate the current clearance process against the best practices at world-class plants.
Develop and implement imprevements to maintain protection for both personnel and equipment and to streamline the clearance process.
i 1
l 3
Impact / Benefits; a)
Improved margins of personnel and equipment safety through the use of a well understood and practiced clearance process, b)
Increased efficiency of the work management process
-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.
a I
N " '*!'
Prietity:
John Titrington High f
i
Clearance Process Improvements - TY305 1994 1995 1996 1997 Description Action Sponsor J lFlMlAhtlJ lJ l AlSl0lNlD J lFlMlAlMlJ l J lAlSl0lNlD JlFlMlAhtlJlJlAlSl0lNlD JlF%1lAlMlJlJlAlSl0lNlD TY305 - I A Implement necessary procedure John Titrington y
changes resulting from the team evaluation of clearance process improvements.
TY305 - 2A Complete necessary training on the John Titrington g
improved clearance process and implementing procedures.
Pagej TY305.MPP
Brunswick Performance Improvement Initiative ti tle s origsa:
Numbert
(
Centralized Document Control Program 12/92 TY308 strategy:
Evaluate the current document control process against the needs of the plant.
Develop an improved program, train personnel, and implement the improved program.
O Impact / Benefits:
v 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.
r.
(
sp.sa so r :
Friority:
Carol Lewis Medium l
Centralized Document Control Program - TY308 1994 1995 19 %
1997 Description Action Sponsor J lFlMjAlMlJ lJ lAlSl0lNlD J lFlM]A%1lJ lJ lAlSl0lNlD JlF%1lA%1lJlJlAlSl0lNlD J lF%il A%1} J lJ lAlSl0lNlD TY308 - 1B Evaluate drawing control, procedure Carol Lewis
- yzepgeyy,ys;cyppgy;j control, vendor manual control, and mod package control areas of the document control program.
TY308 - 6A Adequately train site personnel in the Carol Lewis
- y,yzyggggA use of the document control program (RMP-003).
TY308 - 7A Fully implement the improved Carol Lewis
- yggsppsg document control procedures (RMP-003).
TY308 - 9A Train site personnel and implement Carol Lewis wypspyypppA sitewide administrative procedure for document control. OAP-008.
Page1 TY308.MPP i
Brunswick Performance Improvement Initiative
Title:
' Origin:
Number:
Preventive and Predictive Maintenance 12/92 TYS01 Program Improvements 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.
[s,/
Impact / Benefits:
a)
An optimized Preventive Maintenance Program which performs the right work at the correct time to improve equipment performance and reliability.
1 b)
Reduced overall maintenance costs by eliminating redundant tasks or those tasks which add no value, c)
Reduced challenges to operation by providing more reliable plant equipment.
d)
Provide consistent and trended data for use in Preventive and Predictive Maintenance Programs.
O Sponsor:
Priority:
Chip Pardee High
Preventive / Predictive Maintenance Program Improvements - TY501 1994 199s 1996 1997 Description Action Sponsor J lF htlA K1lJ lJ lAIS }O N ID J lF htlA bt!J lJ lAlS l0lNlD J lF htlA htlJ lJ lAlS hlN]D J lF h1lAbllJ lJ lAls DN[D TY501 - 2B Complete a self-assessment of the Mark Varno O
Preventive Maintenance optimization process.
TY501 - 4C Complete optimization of 8 total Mark Varno 4
prioritized systems.
TYS01 -4D Complete optimization of14 total Mark Varno 4
prioritized systems.
TY501 - 4E Complete optimization of 20 total Mark Varno 4
prioritized systems.
Pm 1 gg ypp O
l
(,
(~3 s
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)
a Preventive / Predictive Maintenance Program Improvements - TY501 l
1994 1995 1996 1997 Description Action Sponsor J lF htlA htlJ lJ lA lS IO N jD J lF htlA htlJ lJ lAls %IN lD J lF htlA htlJ l3 lA jS DlN lD J lF htlA htlJ lJ lAlS l0lN ID TY501 - 4F Complete optimization of 26 total Mark Varno prioritized systems.
TY501 - SA Incorporate optimized PM tasks Mark Varno 2i into existing PM program (e.g. procedures).
TY501 - 5B Incorporate optimized PM tasks Mark Varno 4
into existing program - 2 pilot systems.
TY501 -SC Incorporate optimized PM tasks Mark Varno 4
into existing program for 6 more systems (8 to date).
Page 2 TY5ol.MPP
Preventive / Predictive Maintenance Program Improvements - TY501 1994 199s 1996 1997 Description Action Sponsor J lF htlA htlJ lJ lAlS l0 lN lD J lF htlA htlJ lJ lAlS lO $ lD J lF htlA htlJ lJ lAlS l0 lN lD J lF htlA htlJ lJ lAlS 10 N [D TY501 - SD Incorporate Optimized PM tasks Mark Varno
+
into existing program for 6 more systems (14 to date).
TYS01 - SE Incorporate optimized PM tasks Mark Varno into existing program for 6 more systems (20 to date).
TY501 - 6A Develop Predictive Maintenance Mark Varno
+#7As
- wrwu co M Program.
TYS01 - 6F Implement Predictive Mark Varno
- aumaw el Maintenance Program self-assessment action plan.
Pm 3 TY501.MPP I
oV Preventive / Predictive Maintenance Program Improvements - TY501 1994 199s 1996 1997 Description Action Sponsor J lF htlA htlJ lJ lA lS lOlNlD J lF h(lA h(l1lJ lAlS )OlNlD J lF htlA h(lJ lJ lAlS l0 %IlD J [F bilA htlJ lJ lAlS )O lNID TY501 -6G Integrate Preventive and Mark Varno B ~ +4 zAnemnnzwedyl j
Predictive Maintenance Programs to create Predictive-Driven Preventive Maintenance tasks.
TY501 - 7A Maintenance PM procedure Mark Varno wwb+ewswe4#Mwesyw<resw wmeer '< ###:i revisions and planning.
TY501 - 8A Identify and implement Mark Varno w ays w40,e +w@ w$1 initaitives to achieve near-term PM reductions.
t TY501 - 8B Develop standard PM activities Mark Varno that allow for more consistent and accelerated reliability centered maintenance (RCM) i studies as described in this initiative.
i I
i Page 4 TY5ol.MPP
Preventive / Predictive Maintenance Program Improvements - TY501 1994 1995 1996 1997 Description Action Sponsor J lF htlA htlJ lJ lAlS l0lNlD J lF htlA htlJ lJ lA IS lOINlD J lF hflA htlJ lJ lA jS l0lNID J lF btlA bllJ lJ lAls l0lNlD TYS01 - 8C Initiate reviews of PMs as Abrk Varno t+
c1 scheduled for scope and gri:J1 cities that art:
appropriate. Integrate mio the proposed Reliability Centered h aintenance (RCM).
TY501 - 8D Consolidate the vibration data Mark Varno tw M es el collection and analysis to facilitate overall program to simplify trending and eliminate redundancy.
TY501 -SE Benclunark Predictive hhrk Varno 0m% ve44
&l Maintenance Programs and incorporate lessons learned from industry leaders.
TY501 - 8F Revise the procedures governing Mark Varno be
- WW J1 site preventive maintenance practices to reduce the resources required to correct PM deficiencies.
^
TY5ol.MPP
Brunswick Performance Improvement Initiative rse2.
ortvas numbert U
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.
()
smo ur s rriors e y:
~'-
Chip Pardee High
l Corrosion Preventive Maintenance - TY502 1994 1995 1996 1997 l
Description Action Sponsor J lFlMlA lMl J l J lA lS lOlNlD J lF lMlA jMl J l J l A lS l0lNlD JlFlMlAlMlJlJlAlSlOjNjD J lFlMlA%1lJ lJ lAlSl0lNlD l
TY502 - 1 A Develop and implement a Corrosion Ken Fennell rygyzegggp/ppggj Preventive Maintenance Program to maintain plant ma crial condition from the effects ofcorrosion.
TY502 - 6B Provide engineering support for Hal Pitts r.vggygp;ggj cleaning and inspection of storm drains: prepare study based on results.
Page1 TY502.MPP O
Brunswick Performance Improvement Initiative
(
n u.,
orin~
rwa s Cooling Water Reliabi1ity Program 12/92 TY505 strategy:
Evaluate the best practices at world-class plants.
Develop and implement a program which will preserve cooling water systems from the effects of erosion and corrosion.
Systems to be included are:
the Circulating Water System, the Reactor Building Closed Cooling Water System, the Turbine Building Closed Cooling Water System, and the Service Water System.
Impact / Benefits:
a)
Reduced potential for through-wall leaks resulting from erosion or corrosion.
b)
Improved cooling water system material condition.
c)
Long-term reliability and lesser maintenance costs.
O naur; rrioriev
'k M Chip Pardee High
Cooling Water Reliabiility Program - TY505 1994 1995 1996 1997 Description Action Sponsor JlFlMlAlMlJlJlAlSl0lNlD J lFlMlAlMlJ lJ lAlSl0lNlD J lF%1lA%1lJ lJ lAlSl0lNlD J[FlMlAlM[J{JlAlSl0lNjD TY505 - 2B Develop a written procedure to define Ken Fennell g
the program at BNP.
TY505 - 3 A Determine the scope of piping to be Ken Fennell yp,yppp,j included in the program for UI cooling water systems.
TY505 - 3B Implement corrective actions as Don Eng E7,y/A detennined by the inspections of Unit I cooling water systems TYS05 - 3C Complete design of corrective actions Bob Grazio and provide engineering support during implementation ofcorrective actions from Unit I cooling water system inspections.
Pay 1 TY505.MPP
O O
O-Cooling Water Reliabiility Program - TY505 1994 1995 1996 1997 Description Action Sponsor JlF%ilAhtlJlJlAl5l0lNlD J lF%ilAhtlJ lJ lAlSl0lNlD JlF%1lAhtlJlJlAlSlOlNlD J lF%1lAlMlJ lJ lAlSl0lNk 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 g
and provide engineering support during implementation ofcorrective actions from Unit 2 cooling water system inspections.
TY505 - 4E Perform ultrasonic testing (baseline) of John Langdon g
identified piping for Unit 2 cooling water systems.
i i
1 i
Page 2 TY505.MPP r--.
., --~
Brunswick Performance Improvement Initiative es
(\\~s')
f2tJ':
ors,1a, mm,,
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.
Impact / Benefits:
(V"'}
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.
("
smauer usariey:
\\-
Chip Pardee High
Plant Engineering Program Upgrade - TY506 1994 1995 1996 1997 Description Action Sponsor J lFlMj A %1l J l J l AlS l0lNlD J lF %1l AlMl J l J l AlS l0lNlDJ lF %1lAhtlJ lJ lAlSl0lNlD JlF%1lAlMlJlJlAlSl0lNlD TY506 - 9A Sustain specific interim contractor Chip Pardee ggypsypxgypsypy,;
assignments in needed engineering program areas j
while minimizing the need for continuing contractor support.
l TYS06 - 17A Incorporate lessons learned from the Chip Pardee Technical Support improvement Program into l
Nuclear Engineering Department.
TY506 - 18A Perform a self-assessment of the Chip Pardee g
efTectiveness ofimprovements in Plant Engineering (Technical Support and NED).
Page1 TY506.MPP O
J' I
Brunswick Performance Improvement Initiative
(
riele:
'oris ta s m&ars Inservice Inspection and Inservice 12/92 TY507 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.
(O/
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.
sumso r t priori t y:
,b, Chip Pardee High
Inservice Inspection and Inservice Testing Improvement Program - TY507 1994 1995 1996 1997 Description Action Sponsor J lF%1lAlMlJ lJ lAlSl0lNlD JlF%1lAlMlJlJlAjSl0lNlD J lFlMlA%1lJ lJ lAlSl0lNlD J lFlMlAlMlJ lJ lAlSl0lNlD TY507 - 1B Perfonn a self-assessment ofISUIST Jerry Crider g
j i
improvements and develop a plan for corrective actions.
TY507 - IC Perform a self-assessment of ISI/IST Jerry Crider improvements and develop a plan for corrective acticns.
TYS07 - 3 A Review / revise ISI/IST program Jerry Crider g
implementing test procedures.
TY507 - 12A Update the ISUIST programs for the Jerry Crider gwsMp/,MMpA third interval using the latest edition of the code.
Page1 TY507.MPP
^
O W-
Brunswick Performance Improvement Initiative N
ries.,
- origin, nue.r, Develop and Implement Preservation 12/92 TYS10 Program to Upgrade Material Condition Strategy:
Develop and implement a program to upgrade the material condition of the 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.
Impact / Benefits; a)
Higher standards of material condition, b)
A professional plant environment promoting performance excellence.
c)
Fewer errors resulting from wrong system / wrong unit mistakes.
Sponsor t
- priority, Bob Deacy Medium
Develop and Implement Preservation Program to Upgrade Material Condition - TY510 1994 1995 1996 1997 Description Action Sponsor JlF%1lAlMlJlJlAlSlOjNlD J lF %1lA%tlJ lJ lAlSl0lNlD JlFlMlA%1lJlJlAlSl0lNlD J lI'%1lA%1lJ lJ lAlSl0lNlD TY510 - 3 A Implement the Five-Year Preservation Bob Deacy ygg yz yg yg gg gggyz ygggggggyggggg ggggypg Program to Upgrade Material Condition.
Page1 TYS10.MPP
Brunswick Performance Improvement Initiative Titiet
'Origiar Numbers ALARA Initiatives, Source Term 12/92 TYS11 Reduction I
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.
b
" O Impact / Benefits:
a)
Reduced site exposure to world-class levels of less than 500 person-REM, annually.
b)
Reduced dose from plant systems and equipment through chemical decontamination and hydrolasing to reduce contamination levels, t
I i
sponsors ersoritys Jackie Gawron Medium
ALARA Initiatives, Source Term Reduction - TY511 1994 1995 I996 1997 Description Action Sponsor J lF htlAhi}J lJ lA jS ]O $ lD J lF htlA htlJ lJ lAlS }OlN ID J lF bilA htlJ lJ {AIS l0lN jD J lF hila htlJ lJ lAlS lO NlD TY511 - IC Develop and implement a Chemical Jackie Gawron
- wc1 Decontamination Plan for Unit 2 Residual Heat Removal and Reactor Recirculation Systems.
TYS11 - II implement a Chemical Jackie Gawron w
Decontamination Plan for Unit 1 Reactor Recirculation System.
TYSil - 8A Complete the evaluation and make Scott Watson llfar o -
41 recommendations for zine and ECP Probe additions.
TYSI1 - 8B Consolidate and implement mock-up Jackie Gawron is o4 o
training for dose reduction purposes.
Pm 1 TY511.MPP
O O
O ALARA Initiatives, Source Term Reduction - TY511 1994 1995 1996 1997 Description Action Sponsor J lF hflA htlJ lJ lAlS lO N[#J [F htlA bllJ lJ lAlS lOIN jD J lF hfIA htlJ lJ lAlS jolNlD J IF hiIAhtlJ lJ lAIS l0 $lD TY511 - 8C Complete recommendation for Scott Watson F-ese 944 "v"w M:1 hydrogen water chemistry management strategy.
TY511 - 8D Approve the BNP Dose Reduction Jackie Gawron I+ s e W71 Plan for 1995.
TYS11 - 8E Complete evaluation and make Scott Watson
[%s den @w <- %#esW meusi recommendations for reactor recirculation pipe decontamination.
TY511 - 8F Implement robotics for remote work in Jackie Gawron Iw+ qw ass 9p.;ce,.azee high radiation areas.
Page 2 TYS11.MPP
ALARA Initiatives, Source Term Reduction - TY511 1994 1995 1996 1997 Description Action Sponsor J lF bllA htlJ lJ lA lS h N !D J [F hilA htlJ lJ lA lS hlN lD J lF hilA htlJ lJ lAlS h lN lD J jF htlA htlJ lJ lAlS hlNlD l
TY511 - 8G Implement decontamination and dose Jackie Gawron ly
- q reduction strategy for 1995.
Pms3 TYS11.MPP
Brunswick Performance Improvement Initiative O
Ti tle
'Origiar Humber:
Environmental and Chenistry Program 12/92 TYS12 Improvements strategy:
Evaluate best practices at world-class plants. Develop plans and implement measures to upgrade our existing programs.
1 Impact / Benefits:
a)
Optimum chemistry is maintained in plant systems and equipment
\\
ensuring long-term plant life.
j
\\
\\
b)
Discharges to the environment are minimized and world-class l
performance parameters are achieved.
l l
1' i
l b)/
S]vmur:
pgjorgey:
Jackie Gawron Medium
Environmental and Chemistry Program - TY512 1994 1995 1996 1997 Description Acrion Sponsor J lF %tlAlMlJ lJ jAlSl0lNlD JlF%1lAlMlJlJlAlSl0lNlD JlFlMlAlMlJlJlAlSl0lNlD J lF%1lA%1lJ lJ lAlSl0lN}D TY512 - 4A Develop and implement a program to Sue Fitzpatrick
- yg y p,yg y/g y p s ygepj reduce liquid radwaste.
I i
i I
l Page 1 TY512.MPP
Brunswick Performance Improvement Initiative
- rtese, orista, umr,
(;
Human Performance 8/94 TY601 Strategy:
Develop and implement an action plan that fully addresses inconsequential errors and near misses due to human performance in the cortrol of equiprace evolutions, and ensures long-term and sustained human perforcance 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 implemented in conjunction with the BNP Corrective Action Program enhancements (Initiative TY303, Improve Ability to Identify and Correct Problems), to ensure effective human performance improvements are realized.
O Impact / Benefits:
a)
Fewer inconsequential errors which are deemed to be precursors to significant events b)
Reduced O&M and Capital Costs c)
Improved plant availability and reliability d)
Reduced outage durations O
- sponsor, prioricy, John Paul Cowan High
Human Performance - TY601 1994 1995 1996 1997 Description Action Sponsor J lFlMlA%1lJ lJ lAlSl0lNlD J lF htlA%1lJ lJ lAlSl0lNlD JlF%IlA%1lJlJlAlSl0lNlD J lFlM]A%1lJ lJ lAlSlOjNlD TY601 - 1 A Increase work force invoviement in Clay Warren / Bill Levis rg yg y/geg ygeza developing methods for improving performance through direct involvement with Iluman Performance Group, in root cause analysis, and corrective action development.
TY601 - IB Improve work force awareness of Clay Warren / Bill Levis rgyzyggyzyggyz y/4 human performance trends.
TY601 - IC Expand self-check techniques.
Clay Warren / Bill Levis rg yg y/A TY601 - ID Use EPM processes to modify Clay Warren / Bill Levis rg //4g yg yz yzygggggy/ggyzyp/gy/pg behavior.
Page 1 TY601.MPP MW i
g g
V
'd b3J Human Performance - TY601 1994 1995 1996 1997 Description Action Sponsor J {F %1lA%fl3 lJ lAlSl0lNlD J lF %1lA%1lJ lJ lAlSlOjNlD JlF%1lAlMlJlJlAlSlOlNjD J{FlMlA%1lJlJlAlSl0lNlD i
TY601 - IE Improve work force capability Clay Warren / Bill Levis reyssggyg5pygygyggsy/g5pyfyfygyz through broad based training.
l Page 2 TY601.MPP w_____-________-__________-_________-__-______-____-____-____________---___---_
_ _ _ - _ _ _ _ _ _ - _ _ _ ~
Brunswick Performance Improvement Initiative ts a,
- ortsia, numbers
)
Reactor Vessel Internals Preservation 8/94 TY602 Strategy:
Recent industry events associated with cracking of reactor internal components asssociated with crackine
.f reactor internal components -
shrouds, jet pump beams, shroud hea-alts, etc. necessitated an aggressive analysis and evaluation to develop and integrate strategy for preserving the BWR internals and ensuring plant and public safety.
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 e)
Provides mitagation and repair technologies for the most cost effective means to preserve reactor internals.
l Impact / Benefits:
a)
Reduced number of outages and outage durations b)
Reduced OLM and Capital Costs t' h N_.)
ss-n.or,
- orioriey, Ed Willett High j
i
Reactor Vessel Internals Preservation - TY602 1994 1995 1996 1997 Description Action Sponsor J lF %1lAlNilJ lJ lAjSl0lNlD J lF %1lA%1lJ lJ l AjSl0lNlD J lF %1lA%1lJ lJ lAlSlOlNlD J lFlh1lA%1]J lJ lAlSl0lNlD TY602 - 1 A Perform engineering analysis to Vaughn Wagoner tyg g yg eg y s gea determine internal components essential to safety and production, scope, and frequency of inspections needed, and flaw evaluation methods.
TY602 - IB Review current inspection techniques Vaughn Wagoner tygeg f g py s ssfyMssgea e
for improvements in detection capabilities and time to perform, and identification of new/ improved techniques needed to address all components identified.
TY602 - 1C Review mitigation and repair Vaughn Wagoner EygessszygesssMMMgmwges szwsggyMz technologies for most cost effective means to preserve reactor internals.
Page 1 TY602.MPP G
e 1
Brunswick Performance Improvement Initiative
[]'
- riese, orsysa,
- wuneer, Q,,/
Improve BNP's Competitive Position 8/94 TY603 Strategy:
Develop and implement strategy for achieving world class cost performance.
Impact / Benefits:
a)
Reduced O&M and Capital costs b)
Increased customer satisfaction c)
Improved Brunswick competitive edge O
I
)
- sponsor, prioriere Jim Martin / Dennis McCloskey High
Improve BNP's Competitive Position - TY603 1994 1995 19 %
1997 Description Action Sponsor J lF bilA hflJ lJ lA lS l0 lN lD J lF hlIA htlJ lJ lA lS DIN jD J lF hi(A bllJ lJ lAlS hlN lD J [F bllA htlJ lJ lAlS D $ lD TY603 - l A Implement " Materials Process John Ferguson im
.1 Redesign" dated May 1994 reducing issue stations and related stafling levels.
TY603 - 1B Aggressively manage the capital John Cowan (PRG) li - -
program (post 3-year recovery plan) to keep expenditures below 2.8 mills /KWII. Only authorize projects that are costjustified, or required by regulation.
TY603 - IC Educate stalTas to BNP's cost Jim Martin b-
me
-?
' - w psition relative to the competition by means of periodic all-hands meetings or use of printed materials (e.g. Monday Memo).
TY603 - ID Establish a process that will Jol" Cowan (NMC) 14 =
identify services that may be performed more economically by contract services, targeting if possible tasks performed exclusively by certain units or sub-units.
Pne1 TYE03.MPP
O O
O Improve BNP's Competitive Position - TY603 1994 1995 1996 1997 Description Action Sponsor J lf hflA bflJ lJ IAlS lO NID J lF htlA htlJ lJ lAlS lO $ lD J lF hila bflJ lJ lAlS lOlN ID J lF htlA ht]J lJ lAlS IOlNID TY603 - IE Provide Nuclear Managers Janet Crews tw6 nine M Conunittee with cost of senice information for those tasks that may be performed by contractors.
TY603 - IF Review NMC contract senices Rich Lopriore/Denny Hicks IA - 5:n set target groups and determine if there are any regulatory or training constraints for these tasks that would call into question economic viability.
TY603 - IG Perform an analysis of cost John Cowan S
benefit of contracting designated work tasks utilizing data provided by Contract Senices, Regulatory Affairs, and Training.
TY603 - lH Perform a team effort to develop John Cowan FG"i the BNP staffing plan thru calendar year 1999.
l Page 2 TY603.MPP
Improve BNP's Competitive Position - TY603 1994 1995 1996 1997 Description Action Sponsor J lF htIA htlJ lJ lAlS h N lD J IF htlA htlJ lJ lAlS }OIN lD J IF htlA htlJ lJ lAlS 10 N lD J [F htlA htlJ lJ lAIS l0lN !D TY603 - II Develop and maintain succession John Cowan p se nw*
m-
+m s1 we -
and developmental plans.
TY603 - 1J Provide assistance as required to Bo Lindgren (HR) th
%meu
=
m -
implement and maintain the BNP succession and career development plans.
TY603 - IK Ensure attendance of appropriate Denny Hicks i:-
r@
Anw -
personnel at Business Concepts Training Workshop.
Pme3 TY603.MPP
Brunswick Performance Improvement Initiative figjet Origin Numbert Reduce Regulatory Burden 8/94 TY604 Strategy:
Implement the Regulatory Burden Reduction Program at Brunswick. The program encompasses identifying and prioritizing opportunities to reduce the cost of compliance with regulatory requirements and commitments with balanced consideration of plant safety, reliability, ecocomics, 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.
(
Impact / Benefits:
a)
Elimination of unnecessary work b)
Reduction in O&M and Capital costs c)
An enhanced ability for management to make sound business decisions based on balanced consideration of plant safety, reliability, economics, and protection of the environment d)
Improved efficiency and consistency in plant work practices e)
Reduced outage costs / schedules Os spottsor t Prictityt Rich Lopriore High
Reduce Regulatory Burden - TY604 1994 1995 1996 1997 Description Action Sponsor JlF%1lAlMlJlJlAjSl0lNlD JlFhtlA%1lJlJlAlSlOlNlD J lF %1lA%1lJ lJ lAlSl0lNlD JlF%1lA%1lJlJlAlSl0lNlD TY604 - 1 A Suppon '95 outage (BI 10RI)
Rich Lopriore wp p p s s pfa cost / schedule reduction acitivities: e.g. MSLRM Scram / Isolation Function Elimination; Eliminate ILRT; Increase MSIV leakage.
TY604 - IB Implement regulatory burden reduction Rich Lopriore r y,y s,y p pps/ spa issues: Increase surveillance intervals from 30-90 days; implement hand geometry; increase turbine valve surveillance intervals; CAD system downgrade to non-safety related.
TY604 - IC Support reliability and operational Rich Lopriore wsfys/yppspessfysga flexibility improvements by eliminating unnecessary /burdensom regulatory items:
E!iminate EPA power supply testing..., increase EDG surveillance reqwement flexibility, extend remote shutdown p mel..
TY604 - 1D Implament additional burden reduction Rich Lopriore ypppMMpaz items in 1996 which, vill result in savings of > =
$500,000.
Page1 TY604.MPP
Brunswick Performance Improvement Initiative Ti t le:
Orlgin:
Number:
Improve Refueling Outage Management 8/94 TY605 Strategy:
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.
Impact / Benefits:
b a)
Reduced outage durations b)
Reduced O&M and Capital Costs c)
Longer plant runs d)
Reduced site exposure I
4
%..)
Sponsor:
Priorityi John Paul Cowan High
Improve Refueling Outage Management - TY605 1994 1995 1996 1997 Description Action Sponsor JlFhtlA%1lJlJlAlSl0lNlD J lF%1lAlMlJ lJ lAjSl0lNlD J lF htlA%1lJ lJ lAjSl0lNlD J lF htlAhtlJ lJ lAlSl0lNlD TY605 - I A Develop a standard defmition and Clay Warren / Bill Levis rypppga priority spem for performing on-line corrective and preventive maintenance.
TY605 - 1B Provide a scheduling tool and Clay Warren / Bill Levis gyzyppam reporting process that meets the needs of all work g groups. Establish schedule products for each work ! I group's review and approval.
TY605 - 1C Develop a manageable outage Clay Warren / Bill Levis vppyssgm schedule with milestones, effective buy-in, and status capability. Distribute preliminary outage schedule for review with milestones for Bl10RI.
TY605 - ID Develop plans for outage resources Clay Warren / Bill Levis swppsam including parts, manpower and cardination activities. Distribute histograms for resource requirements, parts required list and milestone schedule.
Page 1 TY605.MPP
- - - - - - - - - - - ' - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - ^ ~ ~ - - - - - - - - - - - -
mU bs b,
Improve Refueling Outage Management - TY605 1994 1995 1996 1997 Description Action Sponsor JlF%ilA%1lJlJlAjsl0lNlD JlF%tlA%tlJlJlAjSl0lNlD J lF%tlAhtlJ lJ lAlSl0lNlD J lFhtlA%tlJ lJ lAlSl0lNlD TY605 - IE Identify outage mods and projects Clay Warren / Bill Levis wpm early enough to allow for detailed planning.
TY605 - IF Enhance scope control process by Clay Warren / Bill Levis wpa revising BSP-35 to clearly identify responsibilities relative to emergent items (ie: daily review of WRJO's for outage impact).
TY605 - 1G Provide early involvement of the Clay Warren / Bill Levis wpm Planning (work packages) Organization in the scope identification process.
TY605 - 2A Ensure future outage contracts have -
Clay Warren / Bill Levis wpppsam incentive clauses to improve contractor performance and outage success.
Page 2 TY605.MPP
Improve Refueling Outage Management - TY605 1994 1995 1996 1997 Description Action Sponsor JlF%1lA%1lJlJlAjSlOlNlD JlF%1lAhtlJlJlAlSl0lNlD J lF %1lAhtlJ lJ lAlSl0lNlD JlF%tlA%1lJlJlAlSl0lNlD TY605 - 2B Evaluate the procurement of Clay Warren / Bill Levis tygypppfgypA improved reactor servicing tools and/or existing equipment upgrades to support shorter refueling outages.
TY605 - 2C Key outage personnel will visit and Bill Levis tgepgy,g/A observe other utilities during the performance of planned "Short Duration" refuel outages this fall so that industry best practices can be incorporated I
into future outages.
I TY605 - 2D Evaluate routine preventive Clay Warren / Bill Levis '
Egg /hyggggA maintenance perfo:med during refueling outages that does not require an outage for performance to reduce the number of PMs scheduled.
TY605 - 2E Evaluate / implement Clay Warren / Bill Levis gggggA recommendations for improvement from INPO's recently completed outage review visit.
Page 3 TY605.MPP
f-Improve Refueling Outage Management - TY605 1994 1995 1996 1997 Description Action Sponsor JlFlMlA%1lJlJlAlSl0lNlD J lF%1lA%1lJ lJ lAlSl0lNlD JlF%1lA%1lJlJjAlSlOjNlD JlFhtlA%1lJlJlAlSl0lNlD TY605 - 2F Set aggressive preplanning milestones Clay Warren / Bill Levis y
that ensure site resourcu have adequate preparation time for outage activities. Issue at least one year prior to the outage start per BSP-35 guidelines.
TY605 - 2G Maximize preoutage work by Clay Warren / Bill Levis vas/sa performing extensive reviews and challenges of all outage projects. (Example: U2 RIIR Valves)
TY605 - 211 Prestage/ package materials required George Warriner vs/s///ay///A for outage activities in specific locations prior to the outage so that material availability can be validated.
TY605 - 21 Complete pre-outage training to Clay Warren / Bill Levis y////// M //ay///A all-hands on the outage schedule along with the weekly stand-down meeetings to encourage ownership and communications among site employees.
Page 4 TY605.MPP
l Improve Refueling Outage Management - TY605 1994 1995 19 %
1997 Description Action Sponsor J lF %1lA%1lJ lJ lAlS j0lNlD J lF%1lA%1lJ lJ lAlSl0lNlD JlF%1lAlMlJlJlAlSlOlNlD J lF%1lA%1lJ lJ lAlSl0lNlD TY605 - 23 Adopt a policy that all significant John Cowan
- yggyp pgl projects and modifications will require PRG approval to be implemented in refueling outages to ensure manageable work scope and minimal potential to extend outage duration.
TY605 - 3A Utilize PLP-25 (Self-Assessment) to Clay Warren / Bill Levis m yj yA perform a post-outage assessment of B21 IRI Refueling Outage within 60 days of outage completion.
TY605 - 3B Perform project critiques on all major Clay Warren / Bill Levis projects implemented uring Unit 2 refuel outage with emphasis on every cycle repeat projects.
TY605 - 3C Document lessons learned from Clay Warren / Bill Levis v474rgsya B211RI and assign a responsible Unit Manager to resolve items needing corrective action prior to UI spring '95 outage.
Page 5 TY605.MPP m
w w
w
, - ~
p (y
v V
d Improve Refueling Outage Management - TY605 1994 1995 1996 1997 Description Action Sponsor J lF%ilA%1lJ lJ lAlSl0lNlD J lFlMlA%1lJ lJ lAlSl0lNlD J lF%1lAlMlJ lJ lAlSl0lNlD J lFlMlA%1lJ lJ lAjSl0lNlD TY605 - 3D Examine post-outage critiques from Clay Warren / Bill Levis y
other utilities recognized by INPO as having superior programs that document outage lessons learned.
TY605 - 3E Continue active participation with Clay Warren / Bill Levis ;y p p s /gg ygg yg y s zygg y p 4p gg yp M M M4 y///fy p p/////// s p 47// M /// M M ///// p //4 BWR Owners Group Outage Mangement Committee to ensure that improvements in industry outage performance are considered for Brunswick Station.
TY605 - 3F Continue to encourage use of outage Clay Warren / Bill Levis :rfgyMMsss,yzyp,/s p s/s p s,ys p p M M M // p / s / pM // M M s / s // M g self-assessment forms by all site personnel to capture good practices and areas for improvement.
Page 6 TY605.MPP
PROJECTS LISTING PROJECT #
PROJECT TITLE HV AC UPGRADE (FAIM #A0001666)
SIMULATOR CORE THERMAL UPGRADE (FAIM #I000(M54)
SIMULATOR INSTRUCTOR STATION (FAIM #10000453)
TURBINE ROTOR REPLACEMENT (FAIM #10000621 & 10000623)
- 009171 EMERGENCY RESPONSE FACILITY ISOLATION SIGNAL - GROUP 10 00918A REACTOR VESSEL WATER LEVEL INSTRUMENTATION UPGRADE 00925F APPENDIX R. THERMOLAG FIRE WRAP ISSUE
- 01538 A SERVICE WATER SYSTEM PIPING PHASE III
- 01757A PROCESS COMPUTER REPLACEMENT
- 02164A CORE THERMAL UPRATE
- 02317A REPLACE SHAFT DRIVEN OIL PUMP FOR REACTOR FEEDPUMP TURBINE WITH MOTOR DRIVEN PUMP (S) j 02549A SCREENWASH PUMP UPGRADE O
V
- 04(M2A SEISMIC QUALIFICATION OF EQUIPMENT-NUREG 1030 04830A MAINTAIN THE BSEP ENVIRONMENTAL QUALIFICATION PROGRAM 05092A REACTOR BUILDING INSTRUMENT RACK REPAIR / UPGRADE 05307A DC BATTERY LOAD STUDY 05644A AC VOLTAGE DROP ANALYSIS 05806A RADWASTE EFFLUENT RELEASE LINE REPLACEMENT 05892A EFFECT OF ELECTRICAL SYSTEM VARIATIONS ON TURBINE GENERATOR TORSIONAL RESPONSE
- 05983A BATTERY ROOM ANNUNCIATOR ALARM INVESTIGATION 06156A HIGH PRESSURE COOLANT INJECTION-REACTOR CORE ISOLATION COOLING HIGH STEAM FLOW 06202A OFF-GAS DRAIN TANKS RESERVOIR M650A REACTOR PRESSURE VESSEL THERMAL CYCLING EVALUATION
%729A DREDGE SPOILS DISPOSAL
- 07148A REPLACE HPCI, RCIC AND RPS TOPAZ INVERTERS 07208A REMOVE / REPLACE OBSOLETE BAILEY RECORDERS 07438A REPLACEMENT OF OFF-GAS RADIATION MONITORING RECORDERS
- 07627A EDG GOVERNOR REPLACEMENT 1
1 Q
PROJECTS LISTING PROJECT #
PROJECT TITLE 07848A REACTOR BUILDING ROOF VENT
- 07862A REPLACE LIGHTING AND COMMUNICATIONS UNINTERRUPTIBLE POWER SUPPLY 08262A DRYWELL COOLERS LOSS OF COOLING ACCIDENT LOCKOUT OVERRIDE
- 08893A CONTAINMENT PENETRATIONS
- 12420A CONTROL BLDG HVAC CONDENSATE DRAIN REPAIR
- 13447A TURBINE UPGRADE
- 13533A THERMOLAG PROJECT
- 1367] A ECCS SUCTION STRAINERS 31856B FIRE BARRIER UPGRADE 80203A DIESEL GENERATOR FUEL OIL LEVEL 81401A FLOOR DRAIN FILTER RETROFIT 84489B 480-AC MOTOR PROTECTION MODIFICATION p
84587A RADWASTE SAMPLING SYSTEM UPGRADE
- B0014A EMERGENT STRUCTURAL ISSUES B0018A PIPING DESIGN TURNOVER PROGRAM B0019A DESIGN BASIS RECONSTITUTION BNT622 BNP PLANT BUILDING STEEL G0015A SMALL MODS G0017A DC VOLTAGE PROFILE STUDY
- G0024A INVESSEL CORE SPRAY PIPING REPAIR
- G0029A FEEDWATER SPARGER CRACKING ISSUE G0050A SERVICE WATER TASK G00503 DIESEL GENERATOR SERVICE WATER SUPPLY AND DISCHARGE PIPING REPLACEMENT
- G0058A TURBINE UPRATE G0075A LOCAL POWER RANGE MONITOR CABLE REPLACEMENT IN DRYWELL G0083A INSTRUMENT AIR COMPRESSORS ALARM AND AIR PRESSURE SETPOINTS G0096A FUEL POOL GIRDER TENDON INSERVICE INSPECTION
- G0110A ELECTRICAL DISTRIBUTION ADEQUACY /GDC-17
- G0140A UPGRADE SECURITY COMPUTER AND CARD READER l
2
OU l
PROJECTS LISTING PROJECT #
PROJECT TTTLE
- G0180A 125/250 VDC BATTERY GROUND DETECTION IMPROVEMENTS G0193A REFRIGERANT REPLACEMENT UNIT I & UNIT 2 G0218A MAKE TEMPORARY POWER FEEDS PERMANENT
- G0249A TORUS LINER PRESERVATION
- G0251A IlYDROGEN WATER CIIEMISTRY M0066A REFUEL BRIDGE UPGRADE
- M0121E PROVIDE THERMAL OVERLOAD PROTECTION FOR AC MOTOR OPERATED VALVES P0057.B SERVICE WATER AND CIRCULATING WATER INTAKE AREA ENHANCEMENT P0057E IIOTSIDE-COLDSIDE WALKDOWN REPAIRS
- R0123A CilEMICAL DECON
- R0123M SPENT FUEL POOL COOLING ASSIST-PIPING & PENETRATIONS
- Indicates project change from May 4,1994 update.
O 3
PROJECT CATEGORIZATION v
Category I - Commitments Represents projects that are necessary to comply with an explicit written obligation to a regulatory agency and any implicit actions resulting from these obligations. Changes to Category I projects will be approved by the Vice President, BNP in accordance with PLP-26, " Establishment of Commitments to Regulatory Agencies."
Catenary II - Non-Commitments Represents other business related projects / modifications. Changes to Category II projects will be approved in accordance with the Nuclear C
Generation Group Manual,303-05, Three Phase Project Approval and Authorization Process.
O
CATEGORY I & II PROJECTS LISTING PID COMMITMENT NUMBER PROJECT TITLE CATEGORY l
009171 EMERGENCY RESPONSE FACILITY ISOLATION SIGNAL - GROUP 10 1
00918A REACTOR VESSEL WATER LEVEL INSTRUMENTADON UPGRADE I
00925F APPENDIX R. DIERMOLAG FIRE WRAP ISSUE I
01538A SERVICE WATER SYSTEM PIPING PHASE III I
04042A SEISMIC QUALIFICABON OF EQUIPMENT-NUREO 1030 1
05092A REACTOR BUILDING INSTRUMENT RACK REPAIR / UPGRADE I
05614A AC VOLTAGE DROP ANALYSIS I
06156A IllGil PRESSURE COOLANT INJECDON REACWR CORE ISOLATION COOLING 111-1 4
STEAM FLOW 13533A TilERMO-LAG FIRE WRAP ISSUE I
B0014A EMERGENT STRUCTURAL ISSUES I
B0018A PIPING DESIGN TURNOVER PROGRAM I
B0019A DESIGN BASIS'RECONSITTUTION I
BNT622 BNP PLANT BUILDING STEEL I
G0017A DC VOLTAGE PROFILE FIUDY I
G0024A INVESSEL CORE SPRAY PIPING REPAIR I
C/XT29A FEEDWATER SPARGER CRACKING ISSUE I
G00501 DIESEL GENERATOR SERVICE WATER SUPPLY AND DISCHARGE PIPING I
REPLACEMENT G0096A FUEL POOL GIRDER TENDON INSERVICE INSPECTION I
G0110A ELECTRICAL DISTRIBlmON ADEQUACY /GDC 17 I
G0140A UPGRADE SECURITY COMPUTER AND CARD READER I
M0121E PROVIDE DIERMAL OVERLOAD PROTECTION FOR AC MOTOR OPERATED VALVES I
P0057E IlOTSIDE-COLDSIDE WALKDOWN REPAIRS I
i I
J D
v 1
~
j
("
O CATEGORY I A 11 PROJECTS LISTLNG 1
l PID COMMITMENT NUMBER PROJECT TITLE CA1TGORY
)
IIVAC UPGRADE (FAIM #A0001666)
II l
SIMULATOR CORE TilERMAL UPGRADE (FAIM #1000N54)
II
)
SIMULATOR INSTRUCTOR STATION (FAIM #10000453)
Il TURBINE ROTOR REPIACEMENT (FAIM #10000621 & 10000623)
II Ol757A PROCESS COMPlTTER REPIACEMENT II l
021MA CORE THERMAL UPRATE II 02317A REPLACE SilAFT DRIVEN OLL PUMP FOR REACTOR FEEDPUMP TURBLNE WITH II l
MOTOR DRIVEN PUMP (S) l 02349A SCREEN WASH PUMP UPGRADE II M830A MAINTAIN THE BSEP ENVIRONMENTAL QUALIFICA110N PROGRAM II 1
05307A DC BATTERY LOAD SIUDY II 05806A RADWASTE EFFLUENT RELEASE LINE REPLACEMENT II l
05892A EFFECT OF ELELTRICAL SYSTEM VARIATIONS ON TURBINE GENERATOR TORSIONAL II
RESPONSE
05983A BATTERY ROOM ALARM INVESI1GATION II 06202A OFF-GAS DRAIN TANKS RESERVOIR II 06650A REACIDR PRESSURE VESSEL 11IERMAL CYCLING EVALUATION 11 06729A DREDGE SPOILS DISPOSAL U
07148A REPLACE HPCI RCIC AND RPS TOPAZ INVERTERS II 07208A REMOVE / REPLACE OBSOLETE BAILEY RECORDERS II 07438A REPLACEMENT OF OFF-GAS RADIATION MONITORING RECORDERS 11 07627A EDG GOVERNOR REPLACEMENT II 07848A REACTOR BUILDING ROOF VENT 11 07862A REPLACE LIGHTING AND COMMUNICAT10NS UNINTERRUFIIBLE POWER SUPPLY Il l
08262A DRYWELL COOLERS LOSS OF COOLING ACCIDENT LOCKOUT OVERRIDE II 08893A CONTAINMENT PENE'IRATION II 12420A CONTROL BLDG HVAC CONDENSATE DRAIN REPAIR II 1
13447A 1URBINE UPGRADE II 1367tA ECCS SUCTION STRAINERS II 31856B FIRE BARRIER UPGRADE II 80203A DIESEL GENERATOR FUEL OIL LEVEL II
(
81401A FLOOR DRAIN FILTER RETROFIT II 84489B 480-AC MOTOR PROTECTION MODIFICATION Il 2
CATEGORY I & Il PROJECTS LISTLNG r%
('d)
PID COMMITMENT NUMBER PROJECT TITLE CATEGORY l
84587A RADWA5TE SAMPLING SYSTEM UPGRADE Il
]
00015A SMALL MODS II G0050A SERVICE WATER TASK Il G0058A TURBINE UPRATE D
00075A LOCAL POWER RANGE MONITOR CABLE REPLACEMENT IN DRYWELL 11 G0083A INSTRUMENT AIR COMPRESSORS Il G0180A 125/250 VDC BATTERY GROUND DETECTION IMPROVEMENTS U
G0193A BNP REFRIGERANT REPLACEMENT II G0218A MAKE TEMPORARY POWER FEEDS PERMANENT II G0249A TORUS LINER PRESERVATION Il G0251A HYDROGEN WATER CHEMISTRY 11 M0066A REFUEL BRIDGE UPGRADE 11 P0057B SERVICE WATER AND CIRCULATING WATER INTAKE AREA ENHANCEMENT U
R0123A RECIRCULATING SYSTEM DECONTAMINA110N D
R0123M SPENT FUEL POOL COOLING ASSIST-PIPING & PENETRATIONS II OV
)
- d 3
_ _~
MAJOR PROJECTS EXECUTIVE
SUMMARY
l INTRODUCTION Brunswick Nuclear Plant (BNP) continues to make improvements in the areas of system reliability, material condition of the plant, and management oversight of projects. These improvements directly contributed to the smooth and successful startup and operation of both units, and ensure long-term and sustained improvements in plant performance.
Management control of projects has improved with the implementation of the first phase of the Master Pajects Plan (MPP). The MPP provides a decision makmg tool for management and the Plant Review Group (PRG) in selecting and scheduling projects for the development of the long range plan and budget. Phase II of the MPP, scheduled for completion by the end of 1994, will provide linkage and timing of project benefits to goal achievement; show impact project decisions on the budget; labor requirements and our plant performance.
]
Additionally the MPP will provide indicators of priority and urgency; and communicate regulatory implications.
PLAN ACCOMPLISILMENTS Twelve projects have been completed for both units since the May 1994 update of the BNP Three-Year Business Plan including: remote shutdown panel vessel level indication, feedwater control system replacement, condenser water box air removal system upgrade, replacement of residual beat removal system valves, reactor vessel level 4
reference leg backfill modification installation, diesel generator starting and control air moisture removal, jet pump beam replacement, secondary containment atmospheric monitor and steam leak detector upgrades, CAD subsystem divisional separation, reactor vessel core shroud modification, and control room annunciator and control switch relocations (HED modifications). Additionally, the material condition of the service and circulating water intake structure, instrument racks, hydrogen water chemistry system, and several HVAC systems was upgraded.
CURRENT STATUS On-line projects currently in progress include the Unit 1 four day tank level, radwaste permanent power, Unit 1
& 2 DC ground detections, security computer upgrade Unit 1 on-line emergent structural repairs, conventional service water pump replacement, Unit 1 supplement spent fuel pool cooling piping installation, Unit 1 girder tendon inspection, and the operation work area upgrade, in addition, planning is in progress to support the B110R1 outage scheduled in the Spring of 1995.
FLTTURE FOCUS -
The future focus is the completed implementation of Phase II of the MPP, ensuring total cost and scheduling integration to be used as a tool for management and PRO to ensure trends of continuous improvements are LG'i-improved plant performance, and ensures plant safety.
maintained. BNP management is committed to ongoing plan implementation that is result based, focuses on 1
-~-
l l
l l
SUMMARY
OF COMPLETED WORK:
Twelve (12) projects were completed; ten (11) as planned, one (1) earlier than planned.
PROJECT #
PROJECT TITLE CAT.
EXPLANATION 00912D Replace Rosemount Transmitters 1
Project completed as planned.
00925A Remote Shutdown Panel Level Indication I
Project completed as planned 06249A Diesel Generator Start & Control Air I
Project completed as planned.
Moisture Removal G0010A Replace E11-F003A-B & F0024A-B with I
Project completed earlier than Globe Valves planned.
G0051A Secondary Containment Atmospheric I
Project completed as planned.
Monitor Modules and Steam Leak Detection i
System Upgrade G0156A Provide CAD Subsystem Divisional I
Project completed as planned.
Separation G0237A Reactor Water Level Reference Leg I
Project Completed as planned.
Continuous Backfill S0033B Control Room Upgrade I
Project completed as planned.
04688A Feedwater Control System Replacement 11 Project completed as planned.
05429A Water Box Air Removal System Upgrade II Air removal system completed i
in both units as planned.
12984A Jet Pump Beam Replacement 11 Project completed as planned G0250A Reactor Vessel Core Shroud Modification II Project completed as planned.
f)-
V 2
i PROJECTS CANCELLED:
Ten (10) projects included in the previous business plan update have been cancelled by the PRG due to issues being resolved through routine maintenance and engineering support, or other existing processes. Also, some projects have been cancelled because improved maintenance has eliminated the need for the design change.
Four (4) of the cancelled projects were identified as under evaluation in the May 4,1994 submittal.
PROJECT #
TITLE CAT.
EXPLANATION Chi 2A Upgrade Replacement Equipment to I
Remaining activities to be NUREG 0588 Category I Requirements performed by routine maintenance activities.
G0119A Reactor Recirculation Valve Upgrade I
Evaluation determined modification is not necessary.
The hydraulic locking issue occurs only when the valve is in the safe (closed) position.
Existing procedural guidelines are sufficient to address this issue.
01536A Restore Cathodic Protection for Intake II Project will be accomplished Structure by maintenance activities.
p 03484A HPCI Room C02 System Alarm II To be addressed via the Q
Industrial Safety Process.
04031A Residual lleat Removal Head Spray Project will be accomplished Removal by Engineering Decommission Package.
04963A Reactor Water Cleanup Pump II Project will be a direct replacement.
06094A Cooling Upgrade for Drywell, Reactor II Evaluation determined cooling Building, and Fuel Pool upgrade at the project level is not required. Enhancements to the system are being handled under other projects.
08341A RPV Shell Temperature Monitoring II Project will be evaluated Hermocouple Cable Replacement through the Engineering Evaluation Process.
F0025C Equipment Database System II Remaining work will be completed via routine work process and EDBS program enhancements.
j P0074A Anti Foulant Coatings in Circulating Water II Project will be accomplished System by Engineering activities.
v 3
PROJECTS UNDER EVALUATION
(],7 Sixteen (16) projects are undergoing further evaluation. Four (4) projects from the May 4,1994 projects list are being re-evaluated. Seven (7) projects remain under evaluation from the May 4 update. Five (5) additional projects are being evaluated.
PROJECT #
TITLE CAT.
EXPLANATION B0060A Miscellaneous Structural Steel I
Scope for Phase I is complete.
Upgrade Additional scope being identified under BNT622.
G0159A RPV Invessel Irradiated Specimens I
Define scope of project and submit to PRG 04699A Salt Water Transfer Pump II Redefine scope of project and submit to Replacement PRG.
05503A Replace 1-5A Feedwater Heater II Redefine scope of project and submit to PRG.
06407A Improve Refuel Floor Fire II Redefine scope of project and submit to Detection Access PRG.
06661A Traversing In-Core Probe System II Redefine scope of project and submit to Upgrade PRG.
07197A Ten Year Inspection of II Evaluate alternative methods of Recirculation Pump Motors performing inspection and submit to
[
PRG.
s 07250A Eliminate Source and Intermediate II Define the impact on plant operations Range Monitor Noise Spikes and submit to PRG.
08048A Setpoint Control Program II Redefine scope of a study and submit to PRG.
31377B Spent Fuel Pool Repair II Redefine scope of project and submit to PRG.
77443A Phase II Spent Resin Transfer II Study being performed to address System deficiencies in Spent Resin transfer system and to propose solutions to PRG.
e4849A Electrical Fire Pump Control II Redefine scope of project and submit to PRG.
B0078A Emergency Fire Dunper Position II Redefine scope of project and submit to PRG.
G0105A Thermal-Ilydraulic Instability II Define scope of project and submit to PRG.
~
G0161A Bus Duct Cooling Fan Modification II Define scope of a study and submit to Unit Two PRG.
M0187A Building Penetration Leakage II Define project scope and submit to
)
PRG.
s 4
1
PROJECTS RESCIIEDULED:
Twelve (12) projects have been rescheduled since the May 4,1994 Three-Year Business Plan update.
PROJECT #
TITLE CAT.
EXPLANATION 01538A Service Water Piping Phase III I
Original scope and schedule unchanged; new scope added and scheduled for completion June 1996.
G0096A Fuel Pool Girder Tendon Inservice I
Original schedule July 1995; new Inspection schedule December 1994.
G0140A Upgrade Security Computer and I
Schedule change due to integration Card Reader with Hand Geometry Access System
)
project.
M0121E Provide Thermal Overload 1
Original schedule May 1996; new Protection for AC Motor Operated schedule is B212R1 refueling outage, Valves June 1996, which is consistent with the existing commitment.
Ol757A Process Computer Replacement II Original schedule June 1994; new schedule November 1994.
02317A Replace Shaft Driven Oil Pump for II Original schedule was B211Rl; new Reactor Feed Pump Turbine with schedule is B212RI refueling outage, Motor Driven Pump (s)
June 1996.
'b/
05983A Battery Room HVAC II Original schedule was May 1994; new schedule December 1994.
07148A Replace HPCI, RCIC & RPS Topaz II Original schedule May 1996; new Inverters schedule June 1996.
J 07438A Replacement of Off-Gas Radiation II Original schedule December 1998; new Monitor Recorders schedule December 1999, 12420A Control Buildirig IIVAC Condensate II Original schedule June 1994; new Drain Repair Study Phase schedule October 1994.
31P56B Fire Barrier Upgrade II Original schedule June 1994; new schedule December 1994.
G0249A Torus Liner Preservation 11 Schedule change from Oct 1995 to B212R1 refueling outage, June 1996, reflects new outage schedule.
l i
J 5
PROJECTS ADDED:
(
Six (6) projects have been added to the business plan.
PROJECT #
TITLE CAT.
021MA Core Thermal Uprate II 07627A EDG Governor Replacement II 08893A Containment Penetration 11 13447A Turbine Upgrade II 13533A Thermo-Lag Fire Wrap Issue 1
13671A ECCS Suction Strainers II OG OV J
0
?
EMERGENCY RESPONSE FACILITY ISOLATION SIGNALS - GROUP 10
/%
L 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. Ilowever, 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 B110R1 and Unit 2 during B212RI. The successful installation of the Group 10 containment isolation signals would meet the requirements of NUREG 0737, Supplement 4
1, paragraph V.
II.
EVALUATION Schedule Index: 8 - There are no appreciable nuclear safety implications for this project. This initiative would provide additional information to the operators on the status of the instrument air containment isolation valves during scenarios involving reopening of main steam isolation valves and containment venting. It would also provide information on the status of containment integrity 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 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.
Other Considerations: In order for this work to be accomplished, it must be scheduled during an outage and coordinated with other projects that may have an interface with 009171. Ilowever, 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.
i Ill.
CONCLUSION Relative to other projects, this project has a lower Scheduling Index. Ilowever, this project will be completed because the Group 10 containment isolation signal indicators are required to be located in t'ie ERFIS per NUREG 0737 and to meet the NRC commitment date.
a IV.
STATUS The !mplementation Phase has been approved by the Plant Review Group for Unit 1. The Unit 2 plant moduication has been approved. Unit I plant modification is in the approval cycle.
PID 009171 Category I 9
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l V.
TARGET COMPLETION Unit i Bl10 Unit 2 B212 l
PROJECT MANAGER CRAIG MARCH PID 00917[
1 O
t 9
1 I
i APPENDIX R THERMO-LAG FIRE WRAP ISSUE 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 perform their intended fire protection function. CP&L has placed fire watches as compensatory measures in the areas containing this material until the material can be successfully tested or upgraded to provide the appropriate protection.
NUMARC has provided industry direction by coordinating this issue with the NRC and performing an industry testing program.
This 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 The NRC !ssued 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 configuration to determine to best possible option for resolution of the Thermo-Lag issue. This could inclade elimination of the Thermo-Lag through changes in CP&L's Safe Shutdown Methodology, rerouting the circuits, upgrading the existing Thermo-Leg or replacing the Thermo-Lag with a different fire wrap material.
(
The Test Program will consist of configurations not bounded by the current NUMARC Testing Program. This included large junction boxes. The Testing Program and Project Study will be performed in parallel to streamline the final resolution and implementation.
III.
CONCLUSION This project will continue to ensure resolution of Thermo-lag issues.
IV.
STATUS Project has been study phase approved by Plant Review Group.
V.
TARGET COMPLETION The response to Generic Letter 92-08, Supplement 1 outlined that CP&L wou'd provide an integrated schedule within 90 days of NUMARC completing their testing program which is currently scheduled for September of 1994.
PROJECT MANAGER STEVE IIARDY PID 00925F f
PID 00925F Category I w++-r
SERVICE WATER SYSTEM PIPING PIIASE III O
I.
PURPOSE AND SCOPE This project upgrades the Service Water (SW) pumps for long term seismic qualification, with self-lubrication, and with improved thrust bearings. This SW pump modification eliminates the need for the SW lube water pumps, which will eventually be removed. The success criterion of this project is that no unit forced outagu or plant deratings will be attributable to the SW system and the pumps meet long term seismic integrity. Also, the Reactor Building Closed Cooling Water (RBCCW) SW supply piping on both Units will be replaced in B110R1 and B212RI. The scope of this project includes replacement of those piping areas known to have corrosion damage.
II.
EVALUATION Schedule Index: 32 - This project moderately improves the availability of the SW system and therefore reduces the probability of core damage or containment 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, which requests relaxation of required performance testing of the SW lube water pumps. Seismic upgrade 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 operations and maintenance of the SW system and reduces the maintenance and testing requirements for the 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.
l' Related Standards: ISI testing of the SW lube water pumps will be eliminated and therefore simplify testing requirements of the SW system. This will close the relief request PR-05 on the SW lube water pumps, which is currently a commitment to the NRC. The 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.
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. The RBCCW/SW supply piping will be replaced in B110R1 and B212RI.
^
o:C PID Ol!38A Category I
V.
TARGET COMPLETION November 1994 for the committed portion of this project.
December 1995 for ripout of the Lube Water System.
June 1996 for RBCCW SW Supply Pipe Replacement PROJECT MANAGER CIIRIS IIUGHES PID 01538A O
O
SEISillC QUALIFICATION OF EQUIPMENT - NUREG 1030 V
l.
PURPOSE AND SCOPE Methods to analyze the adequacy of equipment to withstand seismic events have changed in the years since the Brunswick Nuclear Plant was designed and constructed. Because of these changes in methodologies, the seismic margins of older equipment are unknown. NRC resolution of Unresolved Safety Issue (USI)
A-46, " Seismic Qualification of Equipment in Operating Nuclear Power Plants", is promulgated in NRC Generic Letter 87-02 and requires all utilities whose plants are not qualified to current criteria to evaluate their electrical and mechanical equipment required for hot shutdown for adequate seismic qualification.
The Seismic Qualification Utility Group (SQUG), of which CP&L is a member, developed general implementing guidance for performing the reviews. NRC approved the use of this guidance in a Safety Evaluation Report dated May 22,1992. In addition, the NRC issued Generic Letter 88-20, " Individual Plant Examination for External Events (IPEEE) for Severe Accident Vulnerabilities". The generic letter requested each licensee to conduct an examination to establish the effects of seismic events, internal fires, high winds, floods, transportation, and nearby facility accidents. Licensees are also to confirm that there are no comparable plant-unique external events being er.cluded from examination.
The purpose of this project is to implement the resolution of USI A-46 by analyzing the seismic adequacy of Brunswick electrical and mechanical equipment required to accomplish and maintain the plant in a hot safe shutdown condition for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. Also included in the scope of this project are the evaluation of out-liers and the scoping of modifications to address any deficient conditions found during the effort. The final product will be a report documenting the results of the review, including identification of deficiencies that may require correction. The seismic portion of the IPEEE will be performed under this project using a seismic margins methodology that screens components according to safety importance and seismic capacity
{
against a peak ground acceleration of 0.03g. The option to perform a Probability Risk Assessment (PRA) will be maintained by gathering sufficient data for component fragility calculations.
This screening process will be performed concurrently with the US! A-46 program. Assurance that safety-related electrical and mechanical equipment can perform their intended functions during and following a seismic event or identification of corrective actions to resolve deficient conditions will constitute successful completion of this project. Further assurance of successful completion will be evidenced by NRC review and acceptance of Brunswick Nuclear Plant's implementation of USI A-46.
II.
EVALUATION Schedule Index: 30 - This project could have a significant impact on future analyses of external events.
All plant systems could be affected by a seismic event and severe consequences could result if equipment is not assured of meeting the specified qualification criteria. This results in a significant impact on the core damage frequency due to seismic events (1.0 x 32). Verifying seismic qualification will require inspection and system walkdowns in radiation areas and result in exposure to workers. This exposure will not be made up by any ALARA benefits afforded by the project over the lifetime of the plant, therefore resulting in a negative ALARA scaling factor (-0.2 x 9).
Economic Aspects: The project requires a short-term investment to conduct 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 Category I
Other Considerations: The project will be performed t*'er the guidelines of the General Implementing Procedure (GIP) developed by SQUG. NRC approvas of the procedure has been obtained. After the study is completed, a report will be prepared and submitted to NRC by June 30,1995 that documents the results and describes the schedule for correcting any deficiencies identified during the review. Mangins for the plant with respect to seismic events as required for the IPEEE analysis will also be established under this project.
III.
CONCLUSION Because the methods used to seismically qualify safety-related 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. The NRC has expressed its concerns on this issue and recommended actions to be taken by licensees in Generic Letter 87-02. SQUG, of which CP&L is a participant, submitted and received approval from the NRC on generic implementing guidance for reviewing seismic qualification of equipment.
CP&L plans to complete and document the SQUG and related IPEEE reviews by June 30,1995.
IV.
STATUS The inspections have been completed in Unit 2 and evaluations of equipment is ongoing. Inspections in Unit I will be performed on line and during outage B1IORI.
V.
TARGET COSIPLETION June 1995 for both Units.
PROJECT MANAGER CHUCK RAINES PID 04042A i
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l REACTOR BUILDING INSTRUMENT RACK REPAIR / UPGRADE I.
PURPOSE AND SCOPE The original scope of this project addressed the Residual Heat Removal (RHR) instrument racks located on the.17' level of the Reactor Buildings. These instrument racks were rusting and needed to be repaired or replaced to prevent further degradation which could lead to a condition adverse to quality and safety. Pre-Startup work activities replaced three racks, and installed additional seismic restraints on five racks in each u
unit to support long term operability. All identified pre-startup work items have been successfully completed in Unic 1 and Unit 2. An engineering Study is in progress to determine the baseline corrosion of the five remaining instrument racks in each Unit on the.17 levels, and develop a plan for any corrective actions identified by this Study.
Success for this project will be the completion of any actions required to maintain the long term seismic qualification on Ul/U2 instrument racks located in the Reactor Building -17' level, and to determine the means required to ensure that the rack mounted components will withstand a Design Basis Event.'
II.
EVALUATION Schedufe Index (SI): 14 - The Si is composed of the nuclear safety, unit availability, and ALARA categories. For nuclear safety there is a moderate improvement in the availability of systems of high importance (0.5 x 32). Unit availability has been increased since some instrument racks were repaired or replaced to maintain the plant in an operational condition conducive to quality and safety (0.2 x 12). There is a moderate negative impact on the ALARA category because work on these instrument racks resulted in approximately 18 man rem dose range (-0.5 x 9).
Economic Aspects: The expected benefits of this project are the improved material condition and reliability of the Reactor Building Instrument Racks. Additional benefits received will be reduced long term maintenance costs due to lower maintenance on the stainless steel instrument racks.
Related Standards: This project directly relates to the Work Management Policy for material condition.
Action will be taken to remove and control the reoccurrence of corrosion at the cosmetic stage.
Other considerations: Any additional work identified for this project will have to be accomplished during
~ outages. It will be necessary to coordinate this project with other RHR refurbishment and painting projects during these outages.
111. CONCLUSION It is important for the material constion of the power plant not to degrade to the point where conditions could become adverse to both quality and safety. Therefore this project will be completed as scheduled to ensure the scismic qualification for the Reactor Building Instrument Racks is maintained.
IV, STATUS Project has been study phase approved by the Plant Review Group. Study is nearing completion and appears that rack replacement will not be necessary with increased level of maintenance.
V.
TARGET COMPLETION May 1996.
O PROJECT MANAGER LARRY WALTON d'
Category I j
i
)
p AC VOLTAGE DROP ANALYSIS
("
I, PURPOSE AND SCOPE l
Existing design basis calculations for the Brunswick Alternating Current (AC) electrical distribution system have been found, in some cases, to be unavailable or inadequate. The AC Voltage Drop Analysis project l
has been undertaken to establish current, readily accessible AC electrical distribution system design basis calculations. Calculations to bc pavided include load factor studies, control loop calculations, voltage / load flow / fault current calculations, caole ampacity (amperage capacity) calculations, emergency diesel generator loading calculations, grounding calculations, the fast bus transfer study, and a vaiidation of the computer code used for voltage drop analysis (in accordance with NRC Branch Technical Position PSB-1). 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 AC distribution system, and provide a basis to support future modifications and 10 CFR 50.59 safety evaluations. In the event of a proposed change to the AC distribution system, documentation will be easily accessible to allow identification of potential equipment overloading, over or under voltage situations, non-selective tripping ofovercurrent protective devices, excessive fault currents, cmergency diesel generator overloading, or other design issues. The 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 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 p
system. Because of the low impact on this system of high risk significance, a 0.2 nuclear safety scaling
\\
factor is assigned (0.2 x 32). This 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 preparation and engineering evaluation.
Related Standards: The applicable Work Management Policy is design documentation.
Other Considerations: This project is related to B0019A, Design Basis Reconstitution, and G0110A, Electrical Distribution System Adequacy /GDC17. The 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 NRC Inspection Report 91-09 by December 31,1992. The calculations being developed presently either do not exist or need improvement.
Ill.
CONCLUSION This project will be completed as part of the design basis reconstitution effort. This project will provide a basis for ensuring operation of the plant within the design basis.
IV.
STATUS This project is design phase approved.
V.
TARGET COMPLETION December 1994.
PROJECT MANAGER TERRY BOWMAN PID 05644A 1
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HIGH PRESSURE COOLANT INJECTION / REACTOR CORE ISOLATION COOLING I.
PURPOSE AND SCOPE Resolve problem of inaccurate High Pressure Coolant Injection (HPCI) and Reactor Core Isolation Cooling (RCIC) instrument readings caused by instrument piping vapor pockets. This project originated from LER
- 1-88414 involving inadequate steam leak detection setpoints and the affect the loop seals had on these setpoints. The modification is to eliminate the loop seal.
II.
EVALUATION This project ensures proper HPCI/RCIC steam leak detection.
III.
CONCLUSION This project will be resolved as scheduled.
4 IV.
STATUS The Unit 1 plant modification has been completed. The Unit 2 Plant Modification (PM 88-022) was deleted form the B211R1 Outage. Measurements taken during the B211R1 will be used in an engineering evaluation that willjustify canceling this project.
V.
TARGET COMPLETION Unit 1 Complete v
Unit 2 B211R1 PROJECT MANAGER PAUL FLADOS PID 06156A i
l O
PID 06156A Category I
TIIERMO LAG FIRE WRAP ISSUE I.
PURPOSE AND SCOPE (3
b)
The purpose of this project is to develop options for a long-term solution to the Thermo-Lag fire wrap issue for BNP.
The NRC has issued several Information Bulletins, Notices and a Generic Letter concerning the failures of Thermo-Lag 330-1 material to perform their intended fire protection function. CP&L has placed fire watches as compensatory measures in the areas containing this material until the material can be successfully tested or upgraded to provide the appropriate protection.
NEI has provided industry direction by coordinating this issue with the NRC and performing an industry testing program.
The Thermo-Lag 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.
IL EVALUATION The 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 three phase plan. The three phases include an Option Development Phase, Test Plan Phare and a Implementation Phase.
The Option Development Phase will review each Thermo-Lag configuration to determine the best possible option for resolution of the Thermo-Lag issue. This could include elimination of the Thermo.
Lag through changes in CP&L's Safe Shutdovm Methodology, rerouting the circuits, upgrading the f^
existing Thermo-Lag, replacing the Thermo-Lag with a different fire wrap material, and enhancing the defense in depth measures.
The Test Plan Phase will consist of configurations not bounded by the current NE! Testing Program.
The scope of these configurations will be confirmed during the Option Development Phase and should include large junction boxes. NEI has identified that junction box testing will be considered a generic industry issue and may envelop some or all of CP&L's configurations.
III.
CONCLUSION The Option Development Phase will provide a detailed approach to resolving the Thermo-Lag issue at BNP. The remaining phases of the project will continue based on plant approval to ensure resolution of Thermo-Lag concerns.
IV.
STATUS The Project has been approved by the Plant Review Group to proceed with the Option Development Phase. Option development is approximately 60% complete.
V.
TARGET COMPLETION CP&L's response to Generic Letter 92 08, Supplement I committed to providing an integrated schedule within 90 days of NEl completing their testing program which is currently anticipated to be complete in the third quarter of 1994. Option Development is 60% complete.
PROJECT MANAGER STEVE IIARDY
\\.s PID 13533A PID 13533A Category I
EMERGENT STRUCTURAL REPAIRS k'
l.
PURPOSE AND SCOPE BNP initially responded to the pipe support issues of IEB 79-14 in 1979 and 1980. The 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 79-14 to provide enhancements to pipe supports needed in order for them to meet original design requirements.
Other work not related to IEB 79-14 has been added to this project. Examples of such emergent items are fire protection support upgrades, HVAC support upgrades, conduit support upgrades and resolution of STSI structural deficiencies identified by EWRs. These deficiencies require either verification of structural support seismic qualification or implementation of structural reinforcements or repairs that meet seismic requirements.
The Drilled-In Anchor Sampling Programs have been initiated as a result of NRC Notice of Deviation in inspection Report (IR) 92-14. The Unit I and Unit 2 plant mods have been completed.
The Emergent Structural Modifications will be considered successful when all plant structures and supports with seismic qualifications or other safety related design criteria are found to conform consistently to those requirements over the remaining life of the plant. The level of emergent structural work will decline, and work on structural supports should be primarily the result of inspections or walkdowns and EWR resolutions. Scope for modification to conduit supports in the Unit I drywell, and STSI repairs have been issued into PM 93-029 and will be performed during outage Bl 10RI. An Emergent Structural Modification for each unit should remain in-place for repair of other structural deficiencies identified as STSI.
/~N) 11.
EVALUATION Schedule Index: 51 - This project is intended to assure the seismic qualification or requalification of supports for Category I and Category 11 structures and safety systems. This project exceeds the scope of the current nuclear safety Probabilistic Risk Assessment (PRA) model. Nevertheless, a special seismic review was performed by the CP&L PRA Group to assess the significance ofidentified structural support deficiencies. This assessment indicated that the structural support corrective actions included 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 meet seismic requirements. Potential also exists for personnel ha7ards due to failed supports, primarily during an earthquake (0.2 x 29). As a result of this project, continued upgrades and plant inspections, system walkdowns, ard maintenance practices will provide additional general enhancements to the plant (0.2 x 8).
Economic Aspects: This project has financial impacts due to the commitment to perform repairs to STSI structures and supports that must be seismically qualified.
Related Standar is: This project is primarily related to the Work Management Policy for maintaining plant material conditions within design and licensing requirements.
Other Considera: ions: 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 NRC commitment will continue past the commitment date, into outage B110RI.
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PID B0014A V
Category I
III.
CONCLUSION This project assures continued compliance with regulatory requirements, primarily STSI seismic support requirements. The impacts on safety and plant system availa'oility are significant and aggressive implementation is warranted.
IV.
STATUS Com.mitment to complete Unit 2 and Unit common STSI supports per letter NLS-93-136 was met during outage B211RI. Structural repairs will be performed on-line in 1994 and during outage BI10R1 in 1995.
PM 93-029 Approved for implementation in 1994 - 1995.
PM 91-011 Approved for implementation in 1994-1995.
PM 91-041 Implementation complete, mod closecut in 1994.
PM 93-030 Approved for implementation in 1994 and 1995.
PM 92-082 Implementation complete, mod closcout in 1994.
PM 92-083 Implementation complete, mod closcout in 1994.
V.
TARGET COMPLETION PM 93-029 December 31,1995 PM 91-011 December 31,1995 PM 91-041 December 30,1994 PM 93-030 December 31,1995 PM 92 082 December 31,1994 PM 92-083 December 31,1994 PROJECT MANAGER CHUCK R.AINES PID B0014A l
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3 PIPING DESIGN TURNOVER PROGRAM A
I.
PURPOSE AND SCOPE Some BSEP design drawings 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. The Piping Design Turnover Program is locating, packaging, and turning over to CP&L the UE&C pipe stress and pipe support calculations for Brunswick. CP&L is reviewing the calculations that are safety related and, where needed, upgrading 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.
The Piping Design Turnover Program will result in over 5000 revised piping-suppon drawings. In addition, over 400 piping isometric drawings and supporting calculation packages will be provided. The BNP Piping Design Control organization will integrate data into existing plant information systems (NRCS and EDBS) and will establish procedures to assure continued integrity of design information. Following project completion, an audit will be conducted to verify the consistency among related drawings, calculations, and the as-buileplant configuration. Also the administrative procedures for plant modifications will be updated to ensure continued maintenance of design basis documents.
II.
EVALUATION Schedule Index: 11 - This project has resulted in the changeout or modification of over 400 piping s'ipports for safety systems. Of the 400 piping supports affected, about 200 involve the RHR system, 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 (3
performance is considered to be low. However, because the RHR and service water system are high V
contributors to theoretical are melt frequency, a nuclear safety scaling factor of 0.2 is assigned (0.2 x 32).
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). The potential for increased efficiency in future design activities results in a significant plant enhancement (0.5 x 8).
Economic Aspects: The compiled design documents will improve efficiency in developing future modifications and in conducting operability evaluations. Long term maintenance of the affected piping design bases will be incorporated as a routine 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 staffing and are adequate to support long term requirements. Therefore, the net long term impact of this project is a reduction in BNP costs.
Related Standards:
The applicable Work Management Policy for this project concerns design documentation.
Other Considerations: This type of documentation problem resulted in NRC IEB 79-14. Final closecut 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.
O)
/
PID B0018A Category I
III.
CONCLUSION This 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 M ANAGER SUSAN VANN PID B0018A O
h DESIGN BASIS RECONSTrivrION i'
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. The project includes the collection and consolidation of design basis information from the Architect / Engineer (UE&C), the NSSS supplier (General Electric), and from CP&L licensing, regulatory compliance, and engineering files. This compilation includes the review and turnover of applicable historical correspondence and calculations related to system / component design and regulatory requirements or commitments. The scope of this effort includes capturing data for Brunswick systems and generic issues. All information will be sorted and stored in a computer database to enhance retrievability and control The NRC has shown a high level of interest in plant design basis reconstitution. This project meets the guidance of NUMARC 90-12, " Design Basis Program Guidelines." The 1992 NRC policy statement on design basis information indicates that a generic letter will be issued requesting a description of all licensee programs and that the SALP process will be modified to include assessment 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 maintain the option of plant life extension beyond the current license expiration through the license renewal process. The project is expected to uncover potential discrepancies which must be evaluated. A programmatic approach to identify, confirm, prioritize, track, and close out each discrepancy has been developed. Once completed, the design basis for safety related systems, structures and components at Brunswick will be clearly established, easily retrievable, and fully controlled.
II.
EVALUATION Schedule Index: 24 - This project will resolve any discrepancies that arise as a result of the design basis
/]
reconstitution effort. Since the PRA model directly depends on the quality of plant design documentation, V
such discrepancies could invalidate important PRA assumptions and could impact calculated core damage frequency. Plant modifications to resolve discrepancies are expected to represent a moderate improvement to safety (0.5 x 32). The project should significantly reduce research time on modifications and engineering evaluations and analyses. The identification and disposition of potential discrepancies also represents a plant enhancement (1.0 x 8).
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 part of this project. Ongoing resource savings are expected in the future, due to reduction of time spent on modification and engineering 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. The original NRC commitment date to complete the Brunswick Design Basis Reconstitution Project was December 1993; however, after further defining the work scope, the 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 Efforts on this project will continue due to the importance of accurate and useful design basis documentation.
b PID B0019A V
Category I
IV.
STATUS This project is approved by management.
V.
TARGET COMPLETION Regulatory committed validations December 1995.
Total project December 1996.
PROJECT MANAGER PAUL CAFALLERA PID B0019A O
l O
BNP PL, ANT BUILDING STEEL ID U
I.
PURPOSE AND SCOPE The purpose of the BNP plant building steel verification program is to cloac out the Notice of Deviation in NRC Inspection Report (IR) N-14. Licensee Event Report (LER) 1-88-35 and Unresolved Item (UI) 89-18-02 identified an overstrres condition in one beam in each Reactor Building. In response, in 1990, CP&L began walkdowns of n ".cellaneous steel in the Reactor Building outside the drywell, under project B0060A, As-Buik Verification of Miscellaneous Steel. In early 1992, in response to IR 92-14, CP&L expanded the program to include drywell platform steel (because of similarities with miscellaneous steel design and construction); this program is being accomplished in two phases. The Phase I Program consists of engineering walkdowns of miscellaneous steel inside the drywell, in the reactor building, and autside the drywell to categorize each steel member and connection as adequate or requiring further action. Those requiring further action were evaluated using restart criteria. The Phase II Program consists of analysis of representative platform sections in the drywell and in the Reactor Building outside the drywell using UFSAR criteria, documentation and verification of miscellaneous structural steel. The walkdowns associated with Phase I and the majority of Phase II have been completed.
Walkdowns and analyses performed to date have shown that, despite occasional minor construction variances, construction of miscellaneous steel in the Reactor Building outside the drywell is generally of good quality and none of the variances adversely affect safe plant operation. In the event that repairs or modifications are required, such work will be completed under the scope of projects B0060D and B0060E.
The success criteria for this prograin are that the structural steel affected by the program will satisfy the design requirements of the 1978 Edition of the AISC Specification for the Design, Fabrication, and Erection of Structural Steel Buildings, consistent with the Brunswick Plant Updated FSAR and that there fq will be greater assurance that plant drawings accurately reflect current as-built conditions.
V 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 likelihood that a seismically-induced failure of a structural member could damage 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). The 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 in significant worker dose even though steps (such as the use of photographs) have been taken to minimize the accumulated dose for the project effort (-l x 9). The added confidence in structural steel design margins and in the currency of design drawings and calculations, and the contribution these make to the efficiency of the modification process, represent a moderate plant enhancement (0.5 x 8).
Economic Aspects: This 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. The 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: The Work Management Policies for material condition and design documentation apply to this program.
(
PID BNT622
'v Category I
Other Considerations: Walkdowns and photographs in the drywell require a plant outage to accornplish and were given priority attention during the forced Unit I and 2 outages. The evaluation portion of the Phase 11 Program will begin in late 1994, with the scheduled completion to be in December,1995.
j III.
CONCLUSION The Phase ! Program is complete, as are the walkdowns for the Phase 11 Program. A minimal amount of walkdowns may still be required for selective platforms to determine actual locations of large piping attachments.
IV.
STATUS This project requires design phase approval by the Plant Review Group.
V.
TARGET COSIPLETION December 1995.
l PROJECT MANAGER SUSAN VANN PID BNT-622 O
O
1 DC VOLTAGE PROFILE STUDY j
I.
PURPOSE AND SCOPE 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 undertaken to establish current, readily accessible DC electrical distribution system design basis calculations. Calculations 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 accessible to demonstrate whether a proposed change to the DC distribution system will cause overloading of components. The 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. The 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). This 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 A
enhancement,0.5 x 8).
t 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 preparation.
Related Standards: The applicable Work Management Policy is design documentation.
Other Considerations: The calculations being developed are required by the NRC and presently either do not exist or are not in a usable form for the Brunswick units. The original NRC commitment date (12/30/90) for completing this project was missed. This project is now scheduled for completion at the end of December 1994 based on its relative priority to other projects. This 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 This project was approved by management.
V.
TARGET COMPLETION December 1994.
PROJECT M ANAGER TERRY BOWMAN PID G0017A PID G0017A Category I
FEEDWATER SPARGER CRACKING ISSUE b
V I.
PURPOSE AND SCOPE NUREG-0619 requires frequent non-destructive examination (NDE) of the Feedwater (FW) nozzle blend radius regions and visual examination of the FW spargers to monitor potential crack growth in the vessel cladding. Both units are currently committed to examining the spargers every outage. As a result of such inspections, feedwater sparger cracking has been found.
The Unit I and Unit 2 sparger replacement scope includes removal and replacement of existing spargers, safe-ends, and portions of FW piping in the drywell. Both units will have the cladding removed from the FW nozzle blend radius regions. The spargers are cracking around the flow holes and around the circumferential welds which attach the sparger arms to the tee. During outages that are prior to sparger replacement, interim repairs may be performed to capture potential loose pieces in place. Prior to the interim repairs, as applicable, the regularly scheduled NDE will first be performed on the FW spargers, nozzle weld areas, and IGSCC susceptible weld joints. The success criteria for this project are the presence of no cracks (as determined by NDE/UT) and extended operation of both units without FW sparger problems.
II.
EVAL UATION Schedule Index: 22 - Replacing the FW spargers is expected to reduce the potential for a breach of the Reactor Coolant Pressure Boundary (RCPB) and a Loss of Coolant Accident (LOCA). The likelihood of breaching the RCPB and causing a LOCA event is based on nuclear grade piping having no pre-existing flaws exceeding allowable limits. Therefore, this initiative is assessed to have a significant impact to a moderately important system, the RCPB (0.5 x 32).
(g)
Additionally, this project is a plant enhancement; it provides marginally improved unit availabihty and results in some ALARA benefits. This modification would constitute a plant enhancement in that it would considerably reduce the maintenance and inspection requirements of NUREG-0619 on the FW nozzle inner blend radius (0.2 x 8). There is a increased potential for a significantly longer unit down time from failed FW sp trgers if they are not replaced. Therefore, unit availability is expected to improve (0.2 x 12).
Also, reducing the frequency of liquid penetrant inspections of the feedwater nozzle blend radius would reduce by sixteen hours the outage critical path time required to perform the examination. Reducing the inspection requirements would represent significant man-rem savings, although the actual FW sparger replacement work would expend approximately 190 man-rem for each unit. Radiation dose for each in-vessel inspection is approximately 7.9 nun-rem and, given the estimated reduction in the inspection frequency, when a savings of approximately twenty inspections is realized, a net ALARA savings would result (0.2 x 9).
Economic Aspects: The expected benefits of this modification will be derived through personnel radiation exposure reductions, net unit availability increase, and savings due to reduced maintenance and inspections.
It is expected that the baseload cost of FW sparger maintenance and inspections will be significantly reduced after replacement.
Related Standards: This project impacts the Work Management Policy regarding material condition.
p PID G0029A
(
Category I l
4
l Other Considerations: This modification can only be performed during a refueling outage, with a complete core offload. A contingency plan for repairs to the Unit I spargers is being prepared for outage B110RI.
FW sparger replacement is scheduled for outage B212RI. It is estimated that at least three weeks of outage critical-path time is required to replace FW spargers. Decontamination of FW piping and the vessel should be performed prior to work to reduce exposure during FW sparger replacement. Unit 2 spargers were procured in 1982 and are available for installation (modification is required to accept new safe-end design).
Unit i equipment will be ordered if replacement is deemed necessary.
III.
CONCLUSION Implementation of this project will reduce the frequency of inspections required by NUREG-0619. Unit reliability will be improved because of the reduced likelihood of FW sparger failure. There is a marginal benefit in ALARA savings and improved unit availability. However, the benefits are difficult to quantify.
The July 1991 NRC commitment to evaluate the FW low flow controller evaluation per NUREG-0619 was met in June 1991.
IV.
STATUS Evaluation of the material condition of the Unit i spargers shows replacement may not be necessary.
Unit I spargers will be repaired or replaced, as necessary, based on inspection of their material condition and engineering evaluations during the B110R1 outage.
Replacement of Unit 2 spargers is planned for outage B212Rl.
V.
TARGET COMPLETION O
Unit 1 Outage B110RI.
Unit 2, Outage B212RI.
]
PROJECT MANAGER CIIUCK RAINES PID G0029A 9l
\\
DIESEL GENERATOR SERVICE WATER SUPPLY AND DISCHARGE PIPING REPLACEMENT 1.
PURPOSE AND SCOPE in order to meet requirements resulting from NRC Generic Letter 89-13, CP&L has undertaken a number ofinitiatives regarding inspection and testing of service water piping and components. The service water I
lines for the diesel generatorjacket water heat exchangers have a history of high maintenance due to piping through-wall leaks. These leaks result from cement lining failure at weak spots or from erosion and corrosion of the piping. Leaks, eroded welds, and missing cement lining indicate that the piping is in a degraded condition. The potential for this piping becoming inoperable is of significant concern because of the stringent operability requirements for the diesel generators, which require service water for cooling.
during operation. In order to eliminate high ongoing maintenance costs, CP&L has chosen to undertake a major program to replace large portions of the service water system piping with new piping to improve resistance to salt water corrosion and bio-fouling.
The purpose of this project is to replace 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 throttle service water flow to the diesels in order to balance flow to other equipment cooled by the service water system.
Successful completion of the proposed modifications would be evidenced by the absence of corrosion and through-wall leaks in system piping and improved cooling water flow to other system loads.
II.
EVALUATION l
Schedule Index: 30 - Replacing the service water piping reduces maintenance and improves system reliability, thereby moderately improving the availability of the emergency diesel generators. Throttling of
('
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 maintaining a significant margin of cooling flow to the emergency diesel generators. The 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 availability and would prevent or minimize the potential for forced outages due to failures of the service water system or inoperability of the emergency 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 significant plant enhancement (1.0 x 8).
Economic Aspects: Analyses show that no significant cost savings are achieved by performing the installation in a dual-unit outage. The project 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 increasing cost ofinspection and repair caused by the deteriorating piping.
Related Standards: The Work Management Policy on material condition is applicable to this project.
f Other Considerations: This project is an element of the Long Range Plan to significantly improve the reliability and performance of the service water system. It is also consistent with the Emergency Diesel
}
Generator Enhancement Strategy goal to minimize out-of service time and improve reliability. Installation must be performed during plant operation as well as over a series of outages.
In letter NLS-92-136, CP&L documented commitments from a meeting with NRC on May 12,1992,and PID G0050J
\\
Category I
answered questions from an NRC letter dated April 27,1992. Commitment number 15 from enclosure 4 of NLS-92-136 was given in response to the NRC question.
III.
CONCLUSION To meet established commitments, this project will be completed as scheduled. This project is an element of the Long Range Plan for the service water system and is consistent with the Emergency Diesel Generator Enhancement Strategy goals.
IV.
STATUS This project has been implementation phase 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 in Bf10RI.
V.
TARGET COMPLETION Plant Mod 91-070. December 1995 Plant Mod 91-071 - December 1995 Plant Mod 91-072 - June 1997 PROJECT MGR.
CHRIS Hf!CHES PID G0050J O
O
FUEL POOL GIRDER TENDON IN-SERVICE INSPECTION L
PURPOSE AND SCOPE Each of the four spent fuel pool girders contains twelve pairs of post-tensioned tendons that serve as primary tension reinforcement for the girders. This project resulted from an NRC inspection report item that has been closed, but further work was initiated to address long term BNP inspection requirements for the fuel pool girders. Potential problem areas to be addressed include:
- loss of pre-stress force of the fuel pool girder tendons,
- loss of grease from the tendon anchorage grease caps, and
- corrosion of girder tendons.
More specifically, this project is to evaluate 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 properties of the tendon wires, the potential for corrosion, and the effects of cyclical loading. The information previously available (i.e., design calculations, specifications, and industry literature) did not indicate that design margins were reduced or compromised; however, there are unknowns that could not be addressed by analysis. Nevertheless, it is felt that the important unknowns wi;l not impact the design margin to current standards. At present, there is no inspection program for fuel pool girders.
The scope of this project 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.
Tendon sample wires will be tesV and and analyzed for acceptability. Upon completion ofinspection and p
testing, data analysis will be done. It is anticipated that a routine inspection and testing program with a
\\
periodicity of three to five years will be put in place following the analysis.
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. The long term success of this project will be dependent on the ability of the inspection program to control the tendon material condition and to anticipate problems.
II.
EVALUATION Schedule Index: 16 - This inspection and testing 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 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).
Economic Aspects: This is no direct economic gain from thir inspection and testing program. The project i
expenditure is a charge for economic-loss risk reduction. If a degraded condition is found upon inspection j
and testing, correcting the problem early could save many times the inspection and testing cost by avoiding expensive repairs.
Related Standards: This project impacts Work Management Policies for material condition and for management oversight and corrective actions. The inspection and testing is in line with the standard to ensure that adverse conditions, excluding those that are self revealing, shall be selfidentified an average of 90% of the time.
l O
v PID G0096A Category I
~
Other Considerations: The original NRC commitment date for completion of this project, December 31,
?986, was not met. The effort is now scheduled for completion by December 31,1995.
III.
CONC 1.USION Because this project yields a significant benefit in economic-loss risk reduction, it will be accomplished as scheduled.
IV.
STATUS Project has been implementation phase approved by the Plant Review Group.
Inspections are scheduled for the 3rd & 4th quarters of 1994.
V.
TARGET COMPLETION December 1994 PROJECT MGR.
CilRIS flUGIIES PID G0096A O
O
ELECTRICAL DISTRIBUTION SYSTEM ADEQUACY /GDC-17 L
PURPOSE AND SCOPE As part of the integrated Action Plan (IAP) that responded to the NRC Diagnostic Evaluation Team (DET) report of September 1989. Item D1 provided for a re-evaluation of the Brunswick electrical distribution system for compliance 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 available in time to preclude exceeding fuel thermal limits. For Brunswick, this first source of off site power to each unit is provided through the respective startup auxiliary transformer (SAT). The second source of off site power is provided by back feeding through 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 providing the second off site source if needed.
In addition to GDC-17 compliance, additional concerns being addressed for the AC electrical distribution system include long term adequacy of switchyard voltage to meet emergency bus voltage requirements, and investigation into improving emergency diesel generator (EDG) Technical Specification (Tech Spec) restrictions through enhancements, which may include an additional on site emergency power source. Also the non-segregated bus ducts for each unit's existing SAT Y-windings will be upgraded to meet current system ampacity requirements.
Successful completion of G0110A will result in electrical distribution system design alternatives that meet the current interpretation of GDC-17.
OQ II.
EVALUATION The study has resulted in three projects for each Unit, now in various phases of design and implementation.
The three projects are; the replacement of the SAT-Y Winding non segregated bus duct with higher ampacity equipment, the installation of the Generator No Load Disconnect Switches to enhance the electrical distribution system to meet the current requirements of GDC-17 and the installation of Voltage Regulators to control the E Bus Voltage Level under conditions of heavy Grid load.
III.
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 Generator No Load Disconnect Switch for instal'
- in 1995 for Unit I and 1996 for Unit 2. This installation includes logic changes to simpt
.he process of moving into UAT backfeed. This work will result in an enhanced electrical discibution system that meets the current interpretations of GDC-17.
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 addresses the issue of the long term adequacy of Switchyard Voltage to meet ~
E bus voltage requirements.
D.
The study to explore the alternative of adding an additional on site emergency power source is continuing with completion expected by July of 1994.
O PID G0110A k/
Category I l
j
IV.
STATUS The parts of this overall project are in various stages of approval through the Plant Review Group.
V.
TARGET COMPLETION PCN G0110C 1994 Unit 2 Non Seg Bus Duct Replacement (Completed)
PCN G0110B 1995 Unit 1 Non Seg Bus Duct Replacement PCN G0110F 1995 Unit i Generator NLDS PCN G0110G 1996 Unit 2 Generator NLDS PCN Gol10H 1998 Unit i Voltage Regulators PCN G01101 1997 Unit 2 Voltage Regulators PCN G0110D 1994 Unit 1/2 Fif1h Diesel Study PROJECT MANAGER DAN MOORE PID G0110A O
O
UPGRADE SECURITY COMPUTER AND CARD READER I.
PURPOSE AND SCOPE Most of the equipment that makes up the Brunswick security system has been in place since original plant construction. Developments in the design and use of such equipment have evolved such that new equipment and systems are available which provide higher reliability and would substantially reduce the types of failures currently experienced. These failures result in potential security problems and require large amounts of resources to compensate and correct. Additionally, the unique design of the Brunswick system is no longer fully supported by the original vendor. Because failures can affect large portions of the security system and because troubleshooting must currently be done at the component level, failures can result in delays for plant access. This represents an economic risk should failures occur during busy outage periods. Failures could require additional manning of access points until necessary repairs are effected.
The upgraded system equipment selection has been finalized with system hardware and software design currently in progress. The Security Access Control system is being upgraded with replacement of the security host computers, consoles, multiplexors, card readers, and Hand Geometry readers. The upgrades will consist of industry standard fault tolerant computers communicating to distributed intelligence multiplexors via high speed fiber optic communication links. A majority of the fiber optic cables, planned for and pulled during previous security modifications, will be used for the multiplexor communication link.
During installation of the multiplexors and the monitored devices, security compensatory guard personnel will be required. New access cards will be prepared on the upgraded Polaroid Photo ID system for all badged personnel. Additionally, training of computer, maintenance, and security personnel will be required.
I
- q System performance, maintenance, spare parts availability, and the reduced reliance on contractor software Q
support will greatly improve the security system. Following installation and an initial trial period, reportable events due to failures of the card reader access control subsystem should decrease to less than one third of that of the three previous years.
II.
EVALUATION Schedule Index: 8 - This project should have no appreciable effect on nuclear safety, personnel safety, unit availability, unit capacity, or ALARA. A high plant enhancement scaling factor is assigned because the expected reduction in security events and reduced nuisance to all badged personnel will result in higher I
system reliability (1.0 x 8).
1 Economic Aspects: Increased security system reliability and reduced maintenance and procurement effort for individual repair and routine activities should result. Reliance on contractors for software support will be eliminated. Security, technical, and computer software staff time, along with management attention following failure events, should be significantly reduced. The nuisance impact of access control failures and security events on all badged personnel should decrease. Addition of the Hand Geometry function to this project will provide for significant cost reductions in Security labor, and enhance the access control functions of the overall system.
Related Standards: The applicable Work Management Policy is material condition.
Other Considerations: The schedule for completion of this project was provided to the NRC staff in an exemption request submitted on July 29,1994.
l n
l PID G0140A l
Category I
III.
CONCLUSION Although the schedule index is relatively low, this project is important. Failure of the card reader control i
subsystem could have a major impact on plant access and require expensive and labor intensive compensatory action.
IV.
STATUS Project has been implementation phase approved by the Plant Review Group. Design is scheduled for completion in August,1994. The Factory Acceptance Test for the new Computer hardware / software system is scheduled for September,1994, implementation is scheduled to begin in October,1994. Final system acceptance and availability runs are scheduled for completion in the 2nd quarter,1995.
V.
TARGET COMPLETION June 1995 PROJECT MGR.
LARRY WALTON PID G0140A 9
PROVIDE TIIERMAL OVERLOAD PROTECTION FOR AC MOTOR OPERATED VALVES s
I.
PURPOSE AND SCOPE Thermal overload protection for valve actuator motors addresses one part of the overall program to upgrade the operational reliability of motor operated valves (MOV). Thermal overloads are used to protect the actuator motors from excessive electrical current, especially in the case where the MOV is stuck (either shut or open) and the motor does not have enough power to overcome the problem. Without thermal overload protection, when the valve is stuck, the motor starting currents remain high, severely camaging the motor windings and making manual operation of the valve the only option.
The basis for not using thermal overload protection was the assumption that the use of protective devices (such as thermal overloads) having the capability to interrupt power to safety-related valves would increase the risk that the valves would not operate during accident conditions, assuming the protective devices themselves might malfunction and prevent valve operation. It was considered better to let a motor destroy itself while attempting to operate the valve. The current industry approach and NRC guidance (NUREG 1296, " Thermal Overload Protection for Electric Motors on Safety-Related Motor-Operated Valves") is to assure that motor overload protection is set and maintained in a manner that assures motor-winding protection and, also, avoids spurious valve operation. This approach allows resetting of electrical breakers and thus, allows another attempt by operating personnel to reposition the valve after the condition causing the stuck valve is corrected.
This project is primarily to install thermal overload protection for motor operated valve AC motors and to replace motor control cabinet breakers which have reached their environmental qualification end of life.
To support this project, collateral engineering work is needed to assure setpoint consistency and breaker coordination among the approximately 125 MOVs per unit. Also, once the new setpoints are established, 4
recalculation of the corresponding torque values is required for each valve actuator in order to a;sure that the valve can be operated under all design conditions without causing spurious thermal overload ac tuations.
All of the affected safety related MOVs and the associated breakers were identified using the Equipment Data Base System, assuring coverage of all of the applicable safety equipment. Examples of systems affected by this project include core spray (CSS), high pressure coolant injection (HPCI), reactor core isolation cooling (RCIC), reactor water cleanup (RWC), reactor building closed cooling water (RBCCW),
standby gas treatment (SGT), main steam (MS), and containment atmospheric control (CAC).
This project will be successful when the operational reliability of MOVs improves and valve actuator motors are no longer damaged under stuck-valve (stalled-motor) conditions.
II.
LVALUATION Schedule Index: 28 - This project is directly related to assuring the availability of several safety systems, including residual heat removal, service water, main steam, core spray, high pressure coolant injection, and reactor core isolation cooling (0.5 x 32). Since it has been determined that lack of overload protection has probably resulted in higher MOV motor failure rates at BSEP, this condition has most likely indirectly contributed to plant outages in the past. Consequently, unit availability is enhanced (0.5 x 12) through increased operational reliability of most of the safety-related MOVs. Likewise, this project provides potential plant enhancements (0.5 x 8) by reducing the level of corrective maintenance, post-maintenance testing, and MOV troubleshooting required for a large number of safety-related valves. This is particularly important due to the high impact such work has on outages. Finally, although the project itself will require some additional exposure to radiation during its implementation, reduced levels of MOV inspection, troubleshooting, and maintenance over the rest of the life of the plant are expected to compensate for this (0.2 x 9).-
(".
PID M0121E Category I
Economic Aspects: Improved plant availability and fewer actuator motor replacements are expected to compensate for the cost of this project. No long term additional costs are anticipated as a result of this project for maintenance except routine preventive maintenance.
Related Standards: This project directly is related to the Work Management Policy for material condition.
Other Considerations: The remaining thermal overload work will be accomplished before the completion of outages B110R1 and B212R1 to fulfill CP&L's commitments to the NRC. Also, this project is related to M01210, MOV Testing, which is a long term effort and does not directly impact the M0121E thermal overload work.
]
III.
CONCLUSION This project will be completed as scheduled during outages B110R1 and B212RI.
IV.
STATUS The Unit 1 projects for Bl10R1 have been implementation phase approved by the Plant Review Group.
The Unit 2 projects will require implementation phase approval by the Plant Review Group for future outage scope (8212RI). Unit PM's have been approved.
V.
TARGFT COMPLETION B110R1 (June 1995)
B212R1 (June 1996)
PROJECT MGR.
LARRY WALTON PID M0121E 1
MATERIAL CONDITION WALKDOWN I.
PURPOSE AND SCOPE
/^
t The purpose of this project is to identify, categorize, and repair plant material discrepancies not being addressed under other projects. Under this project, approximately 2000 discrepancies were identified during plant walkdowns. A list of detailed 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 material discrepancies on these lists have been further categorized, l
and the appropriate corrective actions will be taken. The plant's Technical Support Group and the Nuclear Engineering Department have evaluated and categorized all of the walkdown items. The lar;,est segment of ems is related to conduit and structural supports. Other discrepancies include mechanical maintenance f
items, fire hazards, and housekeeping issues. Some of the discrepancies can be resolved directly under the routine work request process. Those discrepancies requiring design and/or documentation changes are being accomplished under this project or under other appropriate projects such as PID B0014A, Emergent Structure Repair. The success criteria of this project are elevated inspection and material condition standards for the plant.
II.
EVALUATION 1
l Schedule Index: 17 - Walkdowns have identified discrepancies that could affect plant safety-related systems. Some of the approximately 2000 items may be operability concerns for safety-related systems.
For example, some of the discrepancies are cable tray and conduit supports for class 1E systems. Also, feedwater heater support problems were identified during the walkdowns. Therefore, this project has a j
positive effect on nuclear safety (0.2 x 32). During the comprehensive walkdowns, industrial safety l
deficiencies (including some fire hazards) were identified; correction of these will result in improved j
personnel safety (0.2 x 29). Raising the standard of the plant's comprehensive walkdown inspection l
program is an important contributor to upgrading and maintaining the material condition of the nuclear i
plant - a plant enhancement (0.5 x 8). Finally, performing the walkdowns will result in a person-rem expenditure with no future person-rem savings projected (0.2 x 9). The net expected benefits of this program are not readily quantifiable.
Related Standards: The applicable Work Management Policies are those for management oversight and corrective actions, material condition, and housekeeping.
j i
Other Considerations: This project augments the periodic inspections required by Administrative Instructions Al 96, "Drywell Inspection and PNSC Outage Prestartup Checklist Instruction," and AI 114, i
" Management Field Walkdowns."
III.
CONCLUSION nis 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, j
IV.
STATUS This project has been implementation phase approved by the Plant Review Group.
V.
TARGET COMPLETION December 1994.
l I
s I
PROJECT MANAGER STUART BYRD PID P0057E PID P0057E Category I I
t
e llVAC UPGRADE
(
I, PURPOSE AND SCOPE There are currently numerous open work items for the heating, ventilation, and air conditioning (HVAC) systems at Brunswick. 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 ductwork 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 by continual condensation. This duct requires replacement and insulation to preclude future condensation and corrosion. Also, many of the HVAC duct supports are either bent, missing, or loose.
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.
The Reactor Building supply fan vortex dampers are corroded and obsolete. This corrosion has caused damper binding and has tripped HVAC. D.c 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.
Successful completion of this project will result in increased HVAC system efficiency and reliability.
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 modeled in the PRA. Failure ofindividual 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, therefo e, judged that this project will result in an overall low positive effect on nuclear safety (0.2 x 32). HVAC systems in general provide support functions for many plant systems. The inability to cool certain plant areas, particularly the Reactor Building, could result in a loss of unit generation. During the summer months when the temperatures in the Reactor Building are elevated and a loss of Reactor Building ventilation occurs, a potential threat exists for a l'CIS Group 1 isolation on high temperature in the MSIV pit. Additionally, cooling con unents for safety related equiprnent (i.e., RhR Room Coolers) have a potential to place the plant in restitive LCOs. Therefore, this project has a low positive impact on unit availability (0.2 x 12). This project would therefore result in a low negative scaling fac.or for ALARA (-0.2 x 9).
Economic Aspects: The 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 d
Category II I
Other Considerations: There is an NRC commitment associated with a portion of this project - to complete the development of DR 90-0143 related to vortex dampers in the Reactor Building by December 31,1992. The DR will be completed on the committed schedule.
III.
CONCLUSION Work is complete on the 200 feet of the reactor building duct work in both units. 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 l
This project is implementation phase approved by the Plant Review Group.
l V.
TARGET COMPLETION December 1995.
PROJECT MANAGER HOWARD LINDSEY O
O a
SIMULATOR CORE-TIIERhlAL MODEL UPGRADE OG i.
PURPOSE AND SCOPE Replace the existing simulator core-thermal software model to improve training on core and vessel dynamics during start-up, transient, and accident conditions.
II.
EVALUATION The current simulator core-thermal model was developed for the existing ENCORE computer. The computation limitations of the ENCORE required a compromise in simulation accuracy and computer execution time requirements. This limits the accuracy and degree of training on many core and thermal conditions.
III.
CONCLUSION The approved simulator computer upgrade to a current technology SGI Challenge computer greatly reduces (M required compromise on execution time. This permits an upgraded core-thermal model which improves training in several areas:
A.
Nuclear instrumentation response during startup training; steady state and transient response during simulation of accident conditions; containment and radiation monitoring system performance under degraded core conditions; recirculation pump start transient and start logic failures; and provides for realistic demonstvion of thermal stratification during low flow conditions.
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B.
New capabilities have been added: Modeling of Boron stratification allows for demonstration of i
EOP guidelines for boron injection during ATWS conditions; addition of recirculation pump and jet pump cavitation; and permits modeling of individual instrument reference legs allowing for simulation of reference leg flashing, out-gassing, reference leg refill; and pressurization of reference leg with mis-operation of reference leg backfill system.
IV.
STATUS Project requires implementation phase approval by the Plant Review Group.
V.
TARGET COMPLETION June 1995.
PROJECT MANAGER WILLIAM GEISE PID O
FAIM 10000454 U
Category II
.~
e.
SIMULATOR INSTRUCTOR STATION / COMPUTER UPGRADE I.
PURPOSE AND SCOPE Reprace the 8 yer 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 means of development, testing, and instructing, without interfering with training on the main simulator.
II.
EVALUATION The outdated simulator computer system failures interrupt training and examinations increased training demand usage 1.as resulted in limited accessibility for scenario development, maintenance and certification testing.
III.
CONCLUSION An upgrade of the simulator computer to current technology, and the addition of extra instructor stations will address the problems above plus provide other benefits:
A.
Reduce reliance on contractor support e
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 Project has been approved for implementation by management.
Simulator outage is scheduled for November / December 1994 to enable installation and testing.
V.
TARGET COMPLETION l
December 24, 1994.
PROJECT MANAGER
. WILLIAM GEISE PID i
FAIM 10000453
~
=
Category fl
TURilINE IlOTOR REPLACE 31ENT 4
J I.
PURPOSE AND SCOPE The purpose of this project is to upgrade the turbine by replacing the LP-A and LP-B monoblock rotors on Unit I and LP-A on Unit 2.
II.
EVALUATION The rotor replacement extends the life of the turbine and potentially reduces the turbine valve testing f equency. The turbine upgrade is intended to improve the reliability and performance ;f the units.
III.
CONCLUSION CP&L will install the monoblock rotors. A study other turbine-related equipment upgrades is being performed under PID 13447A.
IV.
STATUS Unit 1 project is being prepared for implementation during outage B110Rl; Unit 2 is projected for implementation duriqg outage B212RI.
V.
TARGET COSIPLETION December 1996 PROJECT MANAGER DAN MOORE PID N/A FAISI 10000621 &
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FAIS110000623 Category II
PROCESS COMPUTER REPLACEMENT I.
PURPOSE AND SCOPE Brunswick's Honeywell 4010 process computers are the oldest installed and functioning reactor core monitoring computers in the United States. They were designed with technology which has become outdated and cannot be readily supported by the manufacturer. Also, technician trammg services and spare parts are no longer provided by Honeywell. Spare parts can be obtained at this time from third party sources; however, supplies are subject to depletion without notice. Although the many computer outages have not yet impacted the associated unit generation, their frequency has been rising, increasing the probability of startup delays or shutdowns.
The process computer's primary function, core monitoring, is currently dependent on and limited by the existing P1 software provided only by General Electric Corporation (GE). This software is less versatile and accurate than the variety of software now being written for DEC VAX (versus Honeywell) computers.
In addition, limitations in fuel vendor selection are caused by the core monitoring software being GE-specific and less efficient than other available software. These fuel vendor limitations are considered to be a major disadvantage of the present system. In addition, as more complex fuel is used in the reactor core, it becomes increasingly difficult to predict the effects of core power adjustments, resulting in slower reactor startups and power adjustments than would be possible with a more capable system. He existing process computer system does not have sufficient capacity to accommodate the upgraded software needed.
The basic scope of the plant process computer replacement (PPCR) project is to transfer the functions currently being performed by the existing process computer to a system that has greater hardware / software capability, expansion capability, reliability, and maintainability. The existing process computer functions will be upgraded to perform more advanced computing and monitoring using the latest computer graphic t
capabilities. The new hardware includes front-end data acquisition equipment, 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 existing Honeywell input / output (1/0) cabinets will remain, serving as the interface between the plant sensors and the new data acquisition system.
The new software includes the CPU's operating system licenses, data acquisition and data validation software, new core monitoring software, applications specific software, and system integration software that coordinates and monitors the entire system. Engineering services to support this project include providing documentation, testing, installation, training, conversion planning, and project management.
The testing and evaluation phase for the new system is extensive. After the new system's operation has been adequately verified, the existing Honeywell 4010 computer will be disconnected and removed using a phased approach. A long list of goals and success criteria have been established to confirm the adequacy of the new system. Abandonment and/or removal of the Honeywell process components will be a major milestone to indicate that important goals are being satisfied.
II.
EVALUATION Schedule Index: 13 - The process computer replacement is considered a non-safety related modification.
Although it can be argued that the equipment is not safety related, the dependence of operators on the system output may have safety implications during operation. It is reasonable to predict that the graphic display benefits and predictive capability of the new system (especiaUy 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). The reliability, availability, 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 increases with the old system (0.2 x 12). The
/9 PID 01757A V
Category 11
=
computer 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: The current 20 year old computer system can not last much longer without support from the vendor, so investment in a replacement is inevitable, ne largest probable economic benefit is that the new system is much less likely to delay return to service after a refueling outage because of process computer system failures. It has been estimated that such a failure would result in a one to seven day increase in startup time. Also important is that the new core monitoring software, which will not run on the old computer, will permit CP&L to purchase fuel from more than one nuclear fuel supplier, enhancing competitive pricing. Finally, upon project completion, long-term system maintenance costs are expected to be reduced somewhat due to the increased availability of spare parts.
Related Standards: This project is related to Work Management Policies for material condition, operating parameters, and management oversight and corrective action. The PPCR project will improve the reliability, availability, and maintainability of the process computer systems, allowing better operational control.
Other Considerations: Other improvements in the ability of operators to monitor and tune the operation of the plant require the installation of the new process computer system. It is anticipated that there will be measurable improvement in plant availability and net generation as a result of these additional enhancements.
111.
CONCLUSION Unit I and Unit 2 Process Computer System replacement has been accomplished, with Availability Runs in progress for both Unit systems. The process computer replacement will result in improved plant availability and allow better operational control.
IV.
STATUS Both Unit I and Unit 2 systems are in service (Partial Operability on both systems). His project is in final stages of system testing and availability runs.
V.
TARGET COMPLETION November,1994 PROJECT MANAGER LARRY WALTON PID Ol757A 1
l j
l l
O a
~.
.._~ -..
4 1
CORE TIIERMAL UPRATE i
I.
PURPOSE AND SCOPE This project will gain a 3.9 percent thermal power uprate (from 2436 MWt to 2531 MWt) by reducing unnecessary conservatisms in the core thermal-hydraulic analysis. Actual core design will not change, but higher power operation will be authorized. liigher full power operation will be achieved by using modified rod patterns. An increase in steam and feedwater flow through the corresponding systems and components will be achieved; however, no increase in core recirculation flow will be necessary Sufficient margins exist for turbine operation at greater steam flow. The BSEP generators are rated at 849 MWe. Currently, maximum power output for rated core thermal power is about 800 MWe, Generator rated output power is not expected to be exceeded. Other systems will be affected by thermal uprate, and analysis is necessary in the general areas of LOCA loads, increased decay heat, NPDES compliance, corrosion rate changes, setpoint changes, valve closure capability, blowdown pipe support loadings, and system performance at higher pressures. General Electric is preparing the safety analysis to demonstrate continued reactor safety.
A license amendment request will be submitted to NRC in order to enable operation at higher power.
CP&L is allowing for an 12 month review of the amendment request by NRC. Successful completion of this project will result in licensed operation at higher capacity with no decrease in safety or reliability.
II.
EVALUATION The goal of this project is a substantial increase in plant electrical capacity, Core thermal-hydraulic analysis will demonstrate continued nuclear safety at higher power, or no licensing submittal will be made.
1-liigher power level could increase the decay heat removal requirements following a plant trip. This i
increase in decay heat removal requirements would be small and therefore would not result in a significant l
effect on nuclear safety.
Economic Aspects: Costs of this project are partially offset by General Electric under the settlement agreement. Once complete, no appreciable additional funding will be necessary under this project, though 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 related to Work Management Policies for material condition and operating parameters.
Other Considerations: Project G0058A addresses turbine power uprate (increased steam throttling efficiency) and is thus related to core thermal uprate. These two projects are considered separately because the project interdependence is limited.
III.
CONCLUSION This project will increase unit capacity but is dependent on successful completion of a number of smaller projects and 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.
PID 02164A i
Category II i
i
~ - -,
n,,-
REPLACE SilAlT DRIVEN OIL PUh!P FOR REACTOR FEEDPUSIP TURBINE WITH SiOTOR DRIVEN PUMP (S)
I.
PURPOSE AND SCOPE Ris project is to assess and implement the installation of redundant motor driven oil pumps for the reactor feedwater pump turbines (RFPT). The RFFT main shaft driven oil pumps have been unreliable, with limited operating range, and have had a difficult and expensive repair and maintenance history. Due to the unreliable operation of the main shaft driven oil pumps, a single motor driven auxiliary oil pump must be continuously operated to maintain RFPT oil system pressure requirements. The recent failure of a single motor driven auxiliary oil pump resulted in the loss of over $100,000 in generating revenue (18 hours2.083333e-4 days <br />0.005 hours <br />2.97619e-5 weeks <br />6.849e-6 months <br /> of reduced power). The recommendation to correct this problem involves adding two new motor driven oil pumps, one of which will replace the current motor driven auxiliary oil pump; the shaft driven oil pump will be disabled. The success of this project will be improved plant availability, capacity, and a reduction in maintenance costs for the RFPTs.
II.
EVALUATION Schedule Index: 30 - The prevention of power reductions due to failures in the present RFPT system and lost generation time will increase the unit capacity (1.0 x 10). The plant will also be enhanced by the improved maintenance and lower repair costs for the proposed upgrade to the RFFT oil pumps (1.0 x 8).
Nuclear safety is somewhat improved with a more reliable feedwater system which will reduce the potential for a loss of feedwater transient (0.2 x 32). The addition of the motor driven auxiliary oil pumps for the RFPTs could prevent previous unit power reductions associated with the present system thus increasing unit availability (0.5 x 12).
Economic Aspects: The economics of replacing a difficult and expensive to maintain RFPT main shaft driven oil system with a more reliable and easier to maintain oil system are positive. In addition to the savings in maintenance, there is also a savings in generating capacity with increased reactor feedwater reliability. Just one failure of the RFFT auxiliary oil system cost 18 hours2.083333e-4 days <br />0.005 hours <br />2.97619e-5 weeks <br />6.849e-6 months <br /> of reduced generating capacity or $100,000 of lost revenue. The cost of upgrading both units could be economically justified with the prevention of potentiallost generating revenue over the balance of plant life. Long term maintenance costs would be reduced relative to the present RFPT oil system.
Related Standards: Replacing the RFirr oil pumps with a more reliable system would meet the Work Management Policy on material condition. This policy is met by maintaining and improving the reliability and productivity of the Brunswick Nuclear Plant with a more reliable reactor feedwater system.
Other Considerations: Because this project requires the reactor feedwater system to be inoperable for the replacement of the RFPT oil pumps the work would have to be performed during an outage.
111.
CONCLUSION The project is scheduled to allow adequate time for design and outage planning. The replacement of the RFPT shaft driven oil pumps with motor driven oil pumps would result in increased plant capacity.
availability and reduce the maintenance cost of the reactor feedwater system. He added reliability of the reactor feedwater system will also enhance the safety of the Brunswick Nuclear Plant.
PID 02317A
' (
Category 11
]
IV.
STATUS Implementation of Unit I is scheduled during the B110RI. Implementation of Unit 2 has been rescheduled to B212RI.
V.
TARGET COSIPLETION Unit 1 - B210R1 Unit 2 - B212R1 PROJECT MANAGER DENNIS COOPER PID 02317A O
0
'I MAINTAIN TIIE BSEP ENVIRONMENTAL QUALIFICATION PROGRAM I.
PURPOSE AND SCOPE
'Ihe 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 portions of the program.
Some of these issues are ongoing. Review, evaluation, and revision of affected qualification documentation-is necessary to ensure the quality of the EQ files and support continued qualification of equipment.
Fourteen Engineering Work Requests (EWRs) have been specified at different times to address various EQ concerns. All 14 of these EWRs are consolidated in this project. Additionally, other EQ issues will be addrased under this project. For example, resolution of Limitorque Motor Operated Valve issues and the establishmcui of an environmental specification for plant harsh environment areas are two important initiatives. At the completion of this project, Bmnswick should have resolved each of the issues currently within the scope of this project and received final NRC acceptance of each resolutien.
1 II.
EVALUATION Schedule Index: 10 - If EQ activities identify necessary improvements to systems, structures or components, some 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 be seen in plant availability (0.2 x 12). Maintenance of the EQ program records should make future analysis of equipment easier (plant enhancement,0.2 x 8). No appreciable effect is anticipated to personnel safety, unit capacity (EQ must support plant uprate, but does not determine it), or ALARA.
Economic Aspects: This project addresses a number of discreet, one-time issues which have arisen relative to EQ. While the level of effort associated with EQ should decrease as these issues are resolved, other issues are likely to be identified in the future. Maintenance of the Brunswick EQ Program is an ongoing effort which must continue until final plant shutdown and deconunissioning (PCN 01657A accounts for this routine activity).
i Other Considerations: This overall program is required by 10 CFR 50.49. Power uprate will require some high energy line break reanalysis due to expected primary system pressure and temperature changes. The generation of an environmental specification will assure that power uprate parameters are well documented in the BNP EQ design basis.
III.
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 December,1994.
PROJECT MANAGER JIM MCPADDEN PID 04830A PID 04830A Category II
BATTERY ROO51 ANNUNCIATOR ALARSIINVESTIGATION
(
I.
PURPOSE AND SCOPE Several problems have been identified regarding ventilation of the Battery Room. A Temporary Condition exists for the Control Room annunciators for the ventilation fan flow switches due to spurious alarms during conditions of minimum design flow through the Battery Room. Other problems have been identified regarding the control of temperature in the Battery Room to assure that battery cell temperatures remain above the Technical Specification limits required to ensure that adequate battery capacity is available. The only indication to the operator that ventilation flow is not adequate is dropping Battery Room temperature, which indicates that bester elements have tripped due to overheating under the reduced flow. Because there is no remote indication for the status of the heater elements, confirmation of this condition requires an operator to spend 20 minutes climbing among the cables above the battery room to determine if the heater elements are energized. These deficiencies are symptomatic and point to the need for defming and achieving overall balance, control, and indication of ventilation flow through the Battery Room. This project will implement modifications to the air flow measurement system for the Battery Room that will provide accurate and reliable indication of battery room temperature in the Control Room, balance battery room ventilation flow to design requirements, eliminate spurious annunciation at low flow, and maintain battery room temperr.ture within normal operating range under all operating conditions. The success of this project will be evidenced by annunciation in the Control Room without spurious alarms and ventilation improvements that maintain temperatures in the Battery Room within the Technical Specification limits under all expected conditions.
II.
EVALUATION Schedule Index: 14 - Resolving the ventilation problems will simplify and streamline the ventilation O
controls for the Battery Room, eliminate spurious alarms, and decrease the extraneous work requests generated by low flow conditions in the ventilation system for the battery, thus providing positive impact on plant enhancement (! x 8). The intent of this project is to improve the availability of the station batteries by implementing ventilation controls to maintain temperatures in the Battery Rooma within the limits of the Technical Specifications. Since common cause failure of the batteries is a major contributor to failure of the DC Power System, improved monitoring of temperatures in the battery room is expected to have a moderate to high impact on DC Power System availability. Therefore, a nuclear scaling factor of 0.2 is assigned to this initiative (0.2 x 32).
Economic Aspects: The cost of implementing the modifications expected to result from this project will be recovered in reduced costs for extraneous maintenance and upkeep on the ventilation systems for the Battery Rooms.
Related Standards: The Work hfanagement Policy on material condition applies to this project.
Other Considerations: The existing Temporary Condition for ventilation flow annunciation will be cleared during the current dual-unit outage. However, this modification will not require an outage for implementation. A battery ventilation flow test was conducted in August 1992 to identify specific deficiencies in ventilation controls and instrumentation that require permanent design solutions to resolve.
I III.
CONCLUSION l
Based on the project information available at this time, the study for this project has already identified several benefit producing recommendations and, therefore, implementation will continue.
PID 05983A
\\
Category II i
IV.
STATUS O
Project has been implementation phase approved by the Plant Review Group, and scheduled for implementation in the 4th quarter,1994.
V.
TARGET COMPLETION December 31,1994.
PROJECT MANAGER DAN MOORE PID 05983A O
i 9
a
OFF-GAS DRAIN TANKS RESERVOIR
(
s I.
PURPOSE AND SCOPE The electrical level control and indication systems for the off-gas drain tank (OGDT) and its loop seal reservoir have had a history of problems that have initiated several incidents resulting in loss of main condenser vacuum. Some of these incidents have led to power reductions or reactor scrams. The control failures and other material deficiencies in the system are caused, in part, by the high humidity in the residual heat removal (RHR) room (17 foot elevation) where the OGDT is located. For example, the humidity causes corrosion of exposed carbon steel solenoid valve linkages, 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 leading to loss air ejector condensing capability and, thus, loss of condenser vacuum. Operator response to loss of vacuum incidents is hindered by the current indication and control system since determining whether this system is the cause is unusually difficult. This is because of the lack of remote and accurate level indications for the OGDT and loop seal reservoir. Also, to determine the level in the OGDT, the operator must enter a contaminated area and check the high level alarm annunciator.
Even if a high level is indicated, the operator must then try to start the OGDT pumps. Failure of the drain pump to start indicates a low level in the OGDT, leading to the conclusion that the loop seal reservoir level control system is causing a problem. Also, the high level alarm for the OGDT is also not reliable, since the alarm has failed to annunciate when the drain pump and level control malfunction. Other control and indication related deficiencies have been identified during investigations of loss of condenser vacuum incidents. The scope of the project includes installing 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 magnetic float type liquid level indicators (with remote annunciators), and modifying piping to eliminate hold-up points for condensate. These modifications
(
will provide more reliable level control to prevent water from backing up in the off-gas 30-minute hold-up line and will provide remote mechanical indication of water level in the off-gas drain tank. Successful implementation of this project will be evidenced by a reduction in loss of condenser vacuum events caused by the off-gas system and consistent, reliable level indication for the off-gas drain tank and the loop seal line reservoir.
11.
EVALUATION Schedule Index: 27 - Removing the potential for loop seal line blockage increases plant availability by reducing the potential for loss of condenser vacuum events that have resulted in reactor scrams (1.0 x 12).
The deficiencies being corrected hase 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). The reduced potential for the off-gas system to cause a loss of condenser vacuum event has a low positive impact on nuclear safety due to the improved availability 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 pos:tive impact on plant enhancement (0.5 x 8).
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 off-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 off-gas system.
Related Standards: The Work Management Policies on material condition and operating parameters are applicable to this project.
O PID 06202A Category 11
Other Considerations: This project includes modifications that must be implemented during an outage.
III.
CONCLUSION Problems with the off gas system drain tank valves and associated piping has, on several occasions, caused reactor scrams and power reductions. Implementing this project will correct system reliability deficiencies and will enhance the ability of the operator to determine system conditions. This project will be completed as scheduled or earlier, if feasible.
IV.
STATUS This project is currently scheduled in the B110RI. Design in progress.
V.
TAllGET COSIPLETION May 1996.
PROJECT MANAGER CRAIG MARCII PID 06202A O
I j
O
DREDGE SPOILS DISPOSAL L
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 ensuring that proper flow characteristics and capacities can be maintained.
III.
CONCLUSION This project is needed to maintain plant reliability.
IV.
STATUS Plant Review Group approved.
V.
TARGET COMPLETION December 1998.
O PROJECT MANAGER Martin Dalla-Pozza PID 06729A
[~'i -
PIL) 06729A t
Category II
i i
g REPLACE IIPCI, RCIC, AND RPS TOPAZ INVERTERS
(
l.
PURPOSE AND SCOPE The purpose of this project is to resolve the spare parts and reliability issues associated with Topaz inverters. Topaz inverters are presently used in a variety of systems for DC to AC conversion to allow control, logic and instrumentation functions to be performed with AC power. The installed models are no longer available and the original manufacturer will not refurbish the units. Additionally, replacement parts are unavailable. This has affected the availability of the high pressure coolant injution (HPCI) and reactor core isolation cooling (RCIC) systems. Initially, all component loads supplied by the HPCI and RCIC Topaz inverters will be removed. Then, the Topaz inverters and components will be replaced with a simplified DC to DC power distribution system. The function of all the system components originally supplied by the inverters will be the same. New DC HPCI and RCIC flow controllers will be procured.
New power supplies will be procured that will feed the remaining instruments aner the inverter loads are removed. The desired state at the completion of this project is to have available, in place of the obsolete Topaz inverters, reliable power supplies that are qualified for the environment to which they are exposed.
The success criterion of this project is the elimination of HPCI and RCIC systems unavailability due to the failure of the Topaz inverter.
II.
EVALUATION Schedule Index: 13 - This initiative moderately improves the availability of the HPCI and RCIC systems.
Flow control improvements do not have a major impact on HPCI or RCIC reliability. Based on the PRA model, the HPCI system is a system of relatively Irw importance. However, when combined with the RCIC system, the HPCI system is weighted higher. Therefore, a nuclear safety scaling factor of 0.2 was assigned D
to this initiative (0.2 x 32). Further, this initiative corrects the failure of Topaz inverters in the HPCI and
(
RCIC systems which has a potential for a loss of unit availability. The potential loss of unit availability would be most likely caused by entering a HPCI and/or RCIC inoperable LCO (0.2 x 12). Finally, this modification is a medium positive impact on plant enhancement in that it contributes to improvement in the maintenance and operations of the HPCI and RCIC systems (0.5 x 8). Maintenance work-arounds such as replacing individual components within Topaz inverters would be avoided, and the elimination of Topaz inverter failures would enhance system operation.
Economic Aspects: The estimated cost of the project includes the RCIC and HPCI modifications. The expected benefits of this project are the improved material condition and reliability of the RCIC and HPCI systems. The changes in the routine periodic maintenance costs as a result of this initiative are difficult to quantify. The maintenance cost will diminish but maintenance will clearly be required for the new equipment.
Related Standards: The Work Management Policy on material condition is applicable to this project.
Other Considerations: The critical short term work to be completed is the RCIC and HPCI Topaz inverter change out. Other related work is also in progress. The feedwater Topaz inverters are being removed under PID 04688A. The RCIC and HPCI steam leak detection system Topaz inverters are being replaced with a NUMAC digital system under PID G0051 A.
O PID 07148A (s/
Category 11
III.
CONCLUSION The RCIC and llPCI modifications will be implemented as scheduled. This initiative improves the availability of the RCIC and HPCI systems 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 project has been design phase approved by the Plant Review Group. Plant mod is in approval cycle.
V.
TARGET CO.\\1PLETION June 1996.
PROJECT MANAGER LARRY WALTON PlD 07148A l
O 1
l I
O
. ~. - - -
REMOVE AND REPLACE OBSOLETE BAILEY SR 1310 AND SR 1110 RECORDERS I. PURPOSE AND SCOPE Currently the BSEP control rooms have Bailey narrow range chart recorders which have been obsolete since 1974 and for which the spare parts are depleted. This project is currently replacing some of the recorders in the control rooms for both of the Brunswick Units. Some of the recorders have regulatory related operational requirements and are in need of parts which could impact plant operations. The d
installation of new recorders will help prevent plant operations from being impacted. Existing Bailey recorders are to be replaced with Leed & Northrup Speedomax models 131,132, or 133 narrow range chart recorders. Successful completion of this project would allow the Control Room operators to properly document important plant parameters which will allow continued plant operations and also reduce out of i
service recorders.
II. EVALUATION j
Schedule Index: 6 - The only categories are affected by this project are plant enhancement and unit availability. Changing out the existing recorders will enable the operator to have a more reliable means to diagnose off gas problems. Ilowever, this improvement will have no appreciable impact on nuclear safety (0 x 32). The plant would be enhanced with ensured indication of plant parameters and improved operator effectiveness (0.5 x 8). There is a potential for the plant availability to be reduced if those recorders required by regulatory considerations are out of service for lack of parts (0.2 x 12).
4 Economic Aspects: The cos' of routine maintenance and calibration of the recorders willlikely be reduced.
The expected benefits of the replacement of the obsolete Bailey recorders are reduced maintenance and improved operator performance.
Related Standards: Applicable Work Management Policies for this project are material condition and operating parameters. Having new long term (20 yrs) reliable recorders would meet the policy of continuously monitoring operating plant parameters.
Other Considerations: Some of the plant systems' recorders will need to be replaced during a plant outage l
because of their location in the Control Room and the importance of that system to plant operation. 'lhe stock of replacement parts for these recorders at the BSEP is depleted; therefore it is advisable to replace them at the scheduled dates.
III. CONCLUSION The project will continue at the scheduled rate and will be completed by November 1997. Replacement l
of the old recorders will prevent the possible loss of vital equipment during power plant operations.
IV.
STATUS Project requires design phase approval by the Plant Review Group.
V.
TARGET COMPLETION November 1997.
PROJECT MANAGER DAN MOORE l
l PID 07208A I
- j. h PID 07208A U
Category II
EDG GOVERNOR REPLACEMENT t
i V'
I.
PURPOSE AND SCOPE The 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.
II.
EVALUATION The existing governors are obsolete. Certified Class IE parts are no longer available to the vendor for rebuilding and recertifying existing governor Control Circuit Boards, Motor Opera'ted Potentioineters and Actuators. Parts will not be available in the event of failure. Future EDG operability may be impacted.
BNP Maintenance does not have the technical expertisc or the tool and facilities to overhaul or repair and recertify this equipment. Expected benefits are to reduce maintenance expense and to increase EDG reliability.
III.
CONCLUSION Proceed with the design to install new style governors ori cach Emergency Diesel Generator.
IV.
STATUS U
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 PID 07627A Category II
REPLACE LIGIITING AND COMMUNICATIONS UNINTERRUPTIBLE POWER SUPPLY L
PURPOSE AND SCOPE This project will replace the existing obsolete lighting and communications uninterruptible power supply (UPS) system with a more modern and maintainable system. The lighting and communications UPS system supplies 120/208V AC power to the plant paging and intercom system, the plant evacuation and fire alarm system, lighting in the Control Room and other critical areas, and the plant card reader and security system (e.g., the explosive entrance detectors and security computer system). The UPS system was originally installed in 1973 and ha become a significant maintenance problem due to normal equipment aging.
Support from the original manufacturer (Static Products Incorporated, now International Power Machines) has been declining and will continue to erode due to the unavailability of the spare parts for this obsolete equipment. In order to maintain the functions of the UPS system, it is crucial that the current hardware be replaced with a modern system for which part support is available.
The initial phase of the project identified the new system and vendor to replace the existing lighting and communication UPS system. The project will be successful if the UPS system maintenance costs are reduced and the system reliability is improved. Also, the equipment modernization process itself should not unnecessarily impact plant operations or personnel safety.
II.
EVALUATION Schedule Index: 23 - Plant lighting and the plant paging system are very important to successful operator actions during recovery from any potential accident. Since operator actions are critical in preventing and mitigating core damage, the replacement of the lighting and communications UPS impacts nuclear safety scaling factor (0.2 x 32). - Personnel safety is improved by this project due to the potential lost time accident that could occur if the evacuation and fire alarms were to be without power. Loss of plant communications could also have the potential for a lost time accident (0.5 x 29). There is also some potential for unnecessary radiation exposure if the plant intercoms and alarms are unavailable due to a loss of power (0.2 x 9).
Economic Aspects: The present system is obsolete and spare pants are becoming increasingly scarce. A new UPS will allow continued safe plant operation and will reduce maintenance costs as compared with the present installed system.
Related Standards: The Work Management Policy applicable to this project 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 sec sty or vital alarms.
This project is not outage dependent.
Ill.
CONCLUSION Installation of a new lighting and communications UPS system is needed to support continued efficient plant operational control. System maintenance costs for the current obsolete equipment will also be reduced.
This project will be completed as scheduled and will allow orderly modernization of the lighting and communications UPS system.
PID 07862A Category II l
~
CONTROL BUILDING IIVAC CONDENSATE DRAIN REPAIR STUDY PIIASE I.
PURPOSE AND SCOPE Inadequate insulation on ducts and inadequate drain line slope set up the condition for water to spill into the CB flVAC mechanical equipment room floor. This project will eliminate the standing water problem on the floor of the Mechanical Equipment Room.
II.
EVALUATION 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 identifies the cause(s) of water accumulation on the floor of the Mechanical Equipment Room and recommends appropriate corrective action (s).
IV.
STATUS Study has been compiled and is in NED review. Study presentation to the PRG is forecast for Mid-October following completion of preliminary plant reviews.
V.
TARGET COMPLETION Study completes October,1994.
PROJECT MANAGER Craig March PID 12420A i
l i
PID 12420A Category II f
i
_a
-~e
~
TURillNE UPGRADE
.C'i O
I.
PURPOSE AND SCOPE Contract authorization XS80380083 (LP Rotor Replacement) includes several modifications on turbine-related systems. This project was established to install these modifications, including replacement of turbine turning gear motors, installation of RFPT lube oil vapor extractors, installation of full flow lube oil filters, and replacement of RFPT govemors with electronic Woodward governors. As study phases are completed and approved on each modification, individual "sub-projects" will be established for the design phases.
II.
EVALUATION Econorr.
spects: These modifications are intended to correct current problems which requite excessive maintenance, difficulties in replacement of obsolete parts, and unreliable equipment.
Other Considerations: All of these modifications will require outages for installation.
III.
CONCLUSION These modifications are expected to provide decreased maintenance requirements and increased equipment reliability.
IV.
STATUS This project is currently in the study phase.
O V.
TARGET COMPLETION June 1997 PROJECT MANAGER Bill Biggs PID 13447A b)
Q PID 13447A Category II
l l
I ECCS SUCTION STRAINER i
I.
PURPOSE AND SCOPE l
The 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. The 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. The BWROG is currently performing testing to determine the extent of the project and recommend the solution to the long-term issue. The purpose of this project is to work with the BWROG in modeling the suction strainer performance specifically for Brunswick and implement a long-term solution for this issue.
II.
EVALUATION Economic Aspects: The project costs will depend on the final scope of work. The project is currently in the study phase. Modification requirements, if any, will be identified at the conclusion of the study phase.
Related Standards: This project supports the Work Management Policy of maintaining safety system availability and design basis requirements.
Other Considerations: If modifications are required as a result of the BWROG's recommendations and plant i
specific modeling, they will have to be accomplished during outages.
IIL CONCLUSION 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 j
requirements.
.j IV.
STATUS l
The PRG approved the study phase in July 1994.
V.
TARGET COMPLETION Study Phase - December,1994 I
PROJECT MANAGER J. E. Harrell PID 13671A I
l i
O PID 13671 A Category II
FLOOR DRAIN FILTER RETROFIT I.
PURPOSE AND SCOPE 4
Liquid radwaste processing was originally designed to be accomplished by two process paths, a floor drain system for " dirty" liquid waste and a waste collector system for " clean" liquid waste. A previous modification on the original floor drain filter system did not achieve the desired performance objectives and resulted in an inoperable floor drain filter. The inoperable condition of the floor drain filter leaves the waste collector system as the only path for processing liquid radwastes. Since the waste collector filter is designed for processing " clean" waste water, the presence of oil-containing water causes frequent changeouts of the waste collector filter elements that are costly and incur unnecessary expenditure of person-rem. The resin precoat is exhausted much more rapidly due to the current operating lineup, thereby generating extra costs and solid radwaste to ship off the site. Extended failures of the waste collector system could result in a dual unit shutdown because of an inability to process liquid radwaste.
The purpose of this project is to modify the floor drain filter to restore the filter to its original,' functional design. This will restore the floor drain system to service and provide separate paths for processing liquid radwastes, thereby improving the operation of the waste collector filters, reducing the frequency of filter changeouts, and providing an alternate path for processing all liquid radwastes in the event one of the systems becomes inoperable.
Successful completion of this project will be evidenced 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 frequency of element changeouts in the waste collector filter, p
IL EVALUATION Q
Schedule Index: 12 - Returning the floor drain filter to its original design will return the waste processing systems to their normal configurations and intended uses, provide redundancy in waste processing paths, and restore the ability to maintain cleanliness in the waste collector system, resulting in a significant plant enhancement (1.0 x 8). Returning the floor drain system to service reduces the possibility of a dual unit -
shutdown due to an inability to store or process radwaste for extended periods (0.2 x 12). This project will reduce the filter maintenance related radiation exposures caused by mixed stream processing (0.2 x 9).
Economic Aspects: Retrofitting the floor drain filter will redcce the routine costs of cleaning the waste collector system to remove oil impurities that the system was not designed to handle it.
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 in inoperability of the floor drain filter causes all liquid radwaste to be processed through the waste collector system, which is designed to process only " clean
- radwaste, and causes increased costs for maintenance and cleaning of the 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 more days. Restoring the floor drain filter to its original design offers immediate economic and material benefits, so this project will be implemented as scheduled.
f PID 81401A i
\\
Category II
)
RADWASTE SAMPLING SYSTEM UPGRADE
/O I.
PURPOSE AND SCOPE The BSEP radwaste sample system monitors some of the major sources of potential reactor water impurities, including the condensate demineralizers and processed mak'eup water. The radwaste sampling system has experienced several long term and repetitive problems. Many sample points have been plugged for years. Conductivity recorders normally track as many as 7 variables, but they print data on only 8%
of the chart paper range, making data analysis difficult. In addition, conductivity monitor failures cause the plant to enter LCOs frequently. In 1989, INPO issued finding CY.1-1, stating, in part:
"The conductivity monitors and recorders for the condensate filters and demineralizers located in the radwaste control room do not provide information useful for controlling the operation of the systems. Also, the radwaste demineralizer conductivity monitor has been inoperable for several years. The operators do not have indication when the demineralizer resin is exhausted and when impurities are sent to the waste sample tank. "
This project will be successful when the upgraded system is in place and fully operable; E&RC staff have accurate chemistry data to work with; and more proactive chemistry, filter, and resin management is demonstrated.
II.
EVALUATION Schedule Index: 15 - The plant is significantly enhanced by allowing plant personnel the ability to monitor critical chemistry parameters as well as prevent continual maintenance on obsolete equipment (1.0 x 8).
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 monitors identified 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 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. This potential causes a minor concern for loss of unit availability (0.2 x 12). Although this
(
project will significantly improve the ability to monitor chemistry of important makeup water supply systems, there is insufficient evidence to indicate that improvements in water quality of important safety systems would result in significant reduction of corrosion or other beneficial effects that might improve nuclear safety (0.0 x 32).
Economic Aspects: Due to radwaste processing costs and current chemistry practices, this project is expected to result in a cost savings of $2.8 million over the remaining life of the plant. General plant maintenance costs are expected to be somewhat lower following completion of this project.
Related Standards: 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. The FSAR states that the temperature of samples undergoing in-line analysis is designed to be maintained automatically at 77 degrees F ( + or - 1 degree ). Technical specification limits are given at 25 degrees C (77 degrees F). The temperature is controlled at the sample station by the chiller system, which has been very unreliable. The INPO finding CY.1-1 is being tracked by FACTS Numbers 89B0905, 89B0906, and 90B1031. Closure of the INPO finding has been rescheduled several times. Most of the work can be done while the units are on line. Addition or tie-in of some sample points, especially from the condensate system, may require an outage. A presently recommended option involves radwaste sample station -
replacement with a station prefabricated off site by a vendor. If this option is accepted, off site fabrication time must be scheduled between design approval and installation.
)
PID 84587A Category II
III.
CONCLUSION This project is important to proper monitoring of reactor water chemistry and will be completed as scheduled. The conditions warranting action have been present since 1985 and resulted in a 1989 INPO finding that is still open.
IV.
STATUS Project is design phase approved by the Plant Review Group.
V.
TARGET COSIPLETION July 1996 PROJECT MGR.
CllRIS HUGHES PID 84587A O
0
l l
TURBINE UPRATE gb I.
PURPOSE AND SCOPE i
This project improves BSEP efficiency by reducing main turbine throttling losses. The BSEP turbines have i
four inlet valves 'o tl e first stage. When operated in full admission, each of the four valves throttle equally to control steam flow to the turbine. In partial are admission, two or three of the valves operate wide open at full power and control is obtained by throttling the remaining valve (s). Partial arc admission is more efficient at full power (for the same steam flow and reactor power) because throttling losses are less.
Operation in partial arc admission results in more uneven stresses than operation in full are admission. The High Pressure Turbines in both units have been modified to strengthen the High Pressure Rotors for l
operation in partial arc operation.
Unit 2 was converted to partial arc admission during the fall of 1991. During subsequent operation, turbine oscillations due to control problems at high power necessitated a 75% power operation limit. These problems were addressed and corrected. Unit 2 is now in three admission partial arc operation and has demonstrated successful operation during the last run. Minor remaining controlissues are being addressed.
Turbine output is affected by a number of factors, including circulating water temperature, but preliminary estimates are that conversion to partial are admission has resulted in about 1.5% increase in turbine output.
This project included feedwater flow nozzle calibration testing to verify actual feedwater flow to the reactor.
II.
EVALUATION The feedwater flow nozzle calibration test resulted in a decrease of power output in Unit 2 and an increase of power in Unit 1.
Unit 2 performance testing indicates that the increased power output attributable to partial arc operation is about 8.5 MWe. It is expected that the conversion of Unit I will also produce about 1.5% increase in power output. These increases are significant in that additional power output is achieved without increases in fuel or operating expense.
Economic evaluations show that the project is very beneficial. The evaluations will improve as the Low Pressure Rotors (with improved efficiency) are installed. The Low Pressure Turbine contribution to improved efficiency have now been included in these economic evaluations as the low pressure rotors are not a part of this project.
This project is most closely related to the Work Management Policy for material condition, particularly with regard to optimizing plant productivity.
This project to uprate the turbines is related to the core thermal uprate, PID 02164A The nuclear safety and licensing considerations are more significant for core thermal uprate. These two projects are considered separately because of their different natures.
i PID G0058A
(
Category II l
111.
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 August 1994.
IV.
STATUS The Unit 2 project is implementation phased approved and the Unit I project is design phase approved by the Plant Review Group.
V.
TARGET COMPLETION August 1994 Unit 2 June 1995 Unit i PROJECT MANAGER DAN MOORE PID G0058A O
O
125/250 VDC BATTERY GROUND DETECTION IMPROVEMENTS b
I.
PURPOSE AND SCOPE Electrical ground detection problems on the 125/250 VDC electrical system have delayed startup and have consumed hundreds of man-hours in repairs and alternative measures to detect and isolate (locate) grounds.
The primary cause of these problems is that the 125/250 VDC electrical system ground detectors are inaccurate, unreliable, and obsolete. Repairs to the detectors are costly and difficult to perform since the repairs are performed at the component level and replacement parts are difficult to obtain. Frequent maintenance on ground detectors also increases the potential for creating circuit problems and increases general degradation of the detectors' circuit boards. Deficient and inaccurate control room annunciations have resulted in the need for ground readings to be taken manually on each shift. In addition to these hardware problems, the lack of a firm design basis for the setpoints of the detectors results in numerous man-hour expenditures to trace and isolate grounds that may be oflittle importance.
This project will provide a technical basis for the ground detection system requirements and will establish reasonable and maintainable annunciation serpoints. The scope of this project also includes researching industry ground detection systems to identify and select the most suitable system. Selection criteria will include maintuance, annunciation, and ground isolation considerations.
Successful completion of this project includes developing a valid setpoint design basis, which is to be accomplished by evaluating the electrical operating values for various DC components and by reviewing industry standards, BSEP system configuntion, and the associated PRA implications. The success of the system upgrade will ultimately be measured in terms of man-hours saved on isolating grounds and repainng failed detectors, by a decrease in false control room annunciations, and by a significant increase in the probability of the detectors remaining calibrated.
R II.
EVALUATION Schedule Index: 20 - Although AC electrical power is 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 offsite AC electrical power (station blackcut). Improved ground detection techniques providing real-time detection and more rapid location of system faults provides more assurance that the DC system will supply power to vital equipment when required, resulting in some positive impact on nuclear safety (0.2 x 32).
A major reason for identifying and removing electrical grounds is to provide safe working conditions for personnel and to ensure proper and safe operation of plant electrical equipment. Therefore, improving the reliability of ground detection assists operators in assuring that no unnecessary conditions exist to endanger personnel or plant equipment (0.2 x 29). Improved ground detection and isolation techniques will reduce the effort needed to identify and correct sources of electrical grounds, resulting in a moderate plant enhancement (0.5 x 8). Finally, the capability to more efficiently establish th source of a ground will reduce plant radiological area entries needed to perform ground detection, reduc ng the personnel radiation exposure currently expended in performing this activity (0.2 x 9).
Economic Aspects: Upgraded ground detection has substantial potential economic benefits. Upgrading of the ground detection system should alleviate the potential for delayed startup due to problems with detecting and isolating DC grounds. The costs that can be saved are evidenced by the approximately 1000 man-hours spent on such activities during a delayed startup of Units I and 2 in 1991. In addition, the need to perform manual ground detection could be removed, resulting in additional cost savings and improved productivity.
Related Standards: The Work Management Policies applicable to this study are material condition, design O
PID G0180A Category 11
i l
i documentation, and operating parameters.
Othcr Considerations: None III.
CONCLUSION Because of the significant benefits this project is expected to yield, it will be accomplished as scheduled.
IV.
STATUS Project has been implementation phase approved by the Plant Review Group. Plant mod is in approval cycle.
V.
TARGET COMPLETION December 1994 PROJECT MGR.
DAN MOORE PID G0180A O
9
IINP REFRIGERANT REPLACEMENT I.
PURPOSE AND SCOPE This project is currently in the study phase to assess one of the potennalimpacts on BNP of the Clean Air Act. Federal law now supports the United Nations protocol to gradually phase out production of chlorofluorocarbons (CFC) refrigerants by the year 2000, but this date could be moved up (by presidential directive) to as early as 1995. The objective is to protect the Earth's ozone layer. Current CFC production is limited to the level produced in 1986. Under current law, this level will be reduced by 20 percent in 1993,50 percent in 1995, and 85 percent in 1997, with production of new CFCs ending entirely no later than the year 2000. Manufacturers have indicated that production will end in 1995, regardless of federal law. The U.S. Clean Air Act also bans intentional venting of CFCs as of July 1,1992.
Enforcement of this law is the responsibility of the Environmental Protection Agency (EPA). The primary refrigerants used in BNP cooling systems are CFCs, so the availability of replacement refrigerants will be increasingly important as CFC production is restricted and terminated. Also, maintenance on cooling systems is already more difficult due to the venting restriction. The initial objective of this project is to identify and evaluate the impacts of using alternate refrigerants in the affected plant systems. Once the study phase has been completed, plant physical modifications must be developed acd carried out expeditiously. The project may include increasing near term inventories of CFC refrigerats in plant storage as physical plant adjustments are planned and carried out. The relative refrigention cycle effectiveness of alternate refrigerants will very likely impact cooling system design capabilitie,, requiring equipment changes. In particular, this project addresses Turbine Building chillers, Drrwell chillers, Control Building chillers, Augmented Off-Gas (AOG) Buildmg filter chillers, and the Training Building simulator chillers. Other plant equipment, vehicles, and buildings are also affected. This project will be successful if all refrigerant related Clean Air Act constraints are implemented without impacting plant operations.
II, EVALUATION Schedule Index: 12 - Tnis project does not impact any systems important in preventing core damage (0.0 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 reft -rants as the phasecut of CFC production continues. The worst case situation could involve plant shu.a,wn due to inadequate cooling system capacity, but this would be a gradual and controlled management action. Although no outage has yet resulted from this Clean Air Act requirement, this is a strong possibility requiring immediate action.
Economic Aspects: The cost of CFC refrigerants is expected to increase significantly as the supply of CFCs is reduced and as Federal excise taxes on CFCs are increased to discourage CFC use. D-ferral of this study and the resultant modifications could eventually lead to increased procurement co.ts and operating restrictions (including plant shutdown), but this would be gradual and dependent on avail tbility 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 for regulatory compliance (nonNRC) and material condition. Impacts on maintaining material condition involve a fundamental design change for plant cooling systems. Therefore, to maintain design capabilities (functional requirements), forward-looking design evaluations and timely cooling system modifications are required.
/3 PID G0193A V
Category II
Other Considerations: The CFC issue affects all CP&L facilities. For CP&L nuclear plants, this project will be addressed systematically, thus avoiding possible limitations or restrictions 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 absorbers is reduced, resulting in higher radiation release levels.
III.
CONCLUSION CP&L will pursue this study and any resulting hardware modifications. Complete and timely chiller system design capacity validations (using alternative refrigerants) are needed. Where system hardware upgrades or other rnodifications are needed to critical chiller systems, their vigorous implementation will be required.
IV.
STATUS Study phase has been approved by Plant Review Group.
V.
TARGET CONIPLETION Complete the study phase in August 1994.
PROJECT M ANAGER DENNIS COOPER PID G0193A O
@1
TORUS LINER PRESERVATION b'uJ I,
PURPOSE AND SCOPE The 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.
This project includes draining, inspection. and preservation of the Unit 2 Torus. Inspections will include UT measurements of the liner at previously tested location and pit depth measurements to quantify the localized corrosion rate.
II, EVALUATION The key assumption is the liner will not last the life of the plant due to localized pitting corrosion. This assumption is based upon the results obtained from underwater inspections on the Unit I torus liner.
Conditions are expected to be similar for the Unit 2 liner. The reason for excluding the vapor zone from the preservation project is that it is not subject to localized pitting corrosion, and that it will last the remainder of plant life in their present condition.
Ill.
CONCLUSION The torus liner will be refurbished during the next two refueling outages.
Preservation began on Unit 2 Torus during the B211R1 refuel outage and is approximately 50% complete.
IV.
STATUS The project has been implementation phase approved by the Plant Review Group.
V.
TARGET COMPLETION Unit 1 - H110R1 Unit 2 - B212RI PROJECT MANAGER STUART BYRD PID G0249A l
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PID G0249A
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Category II l
i IIYDROGEN WATER CIIE3flSTRY 1
[U I.
PURPOSE AND SCOPE i
i Upgrade the Units 1 & 2 Ilydrogen Water Chemistry systems to allow the systems to inject enough hydrogen to provide full core suppression of Intergranular Stress Corrosion Cracking (IGSCC) for short periods of time for evaluation of possible future continuous full core suppression injection (referred to a high injection rate, or about 3 ppm of 112 in feedwater). Actual anticipated operating injection rates in the near future are expected to be substantially lower (referred to as moderate injection rates, or 1.2-1.6 ppm of 112), however, due to anticipated need for shielding not yet installed on the moisture separator reheaters (MSRs). In addition, it is possible that the desired effects of full core suppression of IGSCC in the vessel may be obtainable through the use of moderate injection rates coupled with other emerging technologies (e.g., noble metal coatings).
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 concentration in the reactor water.
2)
Prevent extended outages and costly in-vessel component repairs and/or replacements (such as the Unit I shroud repair), due to IGSCC.
II.
EVALUATION See project scope and purpose.
III.
CONCLUSION Industry testing has indicated that this project as described will provide full suppression of IGSCC at a
" liveable" radiation level however, it has not been proven over an extended period of time in an operating plant.
' 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. 100scfm testing remains.
V.
TARGET COMPLETION December 1994.
PROJECT MANAGER CRAIG MARCli PID G0251 A D
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G PID G0251 A Category II l
1
REFUEL BRIDGE UPGRADE
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I.
PURPOSE AND SCOPE Refuel bridge upgrades in both units are required in order to increase reliability and safety during outage critical path defueling and reloading. Malfunctions of various refuel bridge equipment have resulted in outage delays.
This project upgrades or replaces the refuel bridge equipment having the most number of failures. For example, this project replaces the mast assembly, platform drive system, control systems, air compressor, and hose take up reels with more reliable equipment. Also, the main hoist motor is being refurbished, the load cells are being replaced with solid state strain gauge type load cells with a continuous digital readout.
Several other reliability enhancements are being made in the compressed air system. Obsolete positioning equipment will be removed.
The major part of the work has been completed. The remaining work is to incorporate lessons learned in both Units.
This project will be successful when outage delays due to refuel bridge equipment malfunctions and failures are eliminated.
II.
EVALUATION Unit availability is affected due to refuel bridge failures extending outage critical paths. Refueling operations are outside the limitations of the PRA model since the current model does not consider plant shutdown conditions.
OV Nevertheless, refueling accidents are analyzed in the FSAR and are important to nuclear safety. Since the refuel bridge is used in refueling operations with heavy loads over the core and fuel pool, nuclear safety is impacted directly. Personnel safety is also directly impacted due to hoist reliability concerns. A reduction in personnel exposure to radiation is expected due to reduced maintenance requirements in the associated radiation areas. This project is a plant enhancement since it replaces obsolete equipment and reduces maintenance requirements.
Economic Aspects: Costs due to outage delays and maintenance requirements will be significantly reduced by this project.
Related Standards: This project is related to Work Management Policies for material condition and outage management.
Other Considerations: This project does not require an outage to accomplish the physical modifications but does require an outage for in core testing. This project addresses work on Unit I under PCN M0066A and, under PCN M0067B, the work on Unit 2.
III.
CONCLUSION The overall benefits of this upgrade project are significant in that due to improved reliability of the equipment, delays are expected to be reduced during critical path activities of defueling and reloading.
This project will be accomplished as scheduled.
[d PID M0066A
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Category II
IV.
STATUS Project is implementation phase approved by the Plant Review Group.
V.
TARGET COMPLETION Unit 2 July 1994 Unit 1 June 1995.
PROJECT MANAGER DAN MOORE PID M0066A i
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SERVICE AND CIRCULATING WATER INTAKE AREA ENIIANCEMENT g
L PURPOSE AND SCOPE This is a comprehensive project to restore the material condition of the Service Water System (SWS) and Circulating Water System (CWS) intake areas and structures. The purpose of the SWS is to provide water from the Cape Fear River for lubrication and cooling of equipment in the Turbine Building, Reactor Building, Diesel Generator Building, Chlorination 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 for the main condenser. Due to the relatively humid and corrosive saltwater environment, the physical plant areas and equipment associated with these systems require continued upkeep and preservation. The project includes such work as upgrades to corroded steel structural components, platforms, conduit, cable trays, and handrails; piping repairs and replacement; general repairs to non-corrosive components; refurbishment of instrumentation and control systems; and general area improvements. The objectives of this project are to correct current material problems in the intake areas and to establish effective inspection and maintenance programs that prevent future, significant deficiencies.
The success criteria for this project are that the specified restoration work is completed as planned and that the associated equipment and general areas are returned to a corrosion-free condition.
II.
EVALUATION Schedule Index: 30 - 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 O
availability. Since the SWS is designed to cool critical safety system components directly and can be cross-V 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. Consequently, 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 current conditions from developing into a future concem 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 area facilities are frequently and readily identified as deteriorated, and these conditions are an indication of inadequate maintenance (0.5 x 8).
Economic Aspects: 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.
Other Considerationn 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.
[d PID P0057B Category 11
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III.
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 failures would be identified during normal operations and would primarily affect unit availability and capacity. Therefore, from a nuclear safety perspective, refurbishment and continued maintenance of these facilities is considered 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.
V.
TARGET COMPLETION 92-103 December 1995.
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December 1995.
PROJECT MANAGER CHRIS fiUGHES PID P0057B O
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REACTOR RECIRCULATION SYSTEM CIIEMICAL DECONTAhlINATION I.
PURPOSE AND SCOPE Chemical decontamination of reactor recirculation system (RRS) is currently performed every refueling outage due to the proven and immediate dose savings which will result. The RRS is the largest single contributor to drywell dose rates during outages. The RIIR and RWCU systems have a lesser impact on site total exposure such that chemical decontamination of these systems will be performed initially and not planned to be repeated in near term subsequent years. Dose rates and exposures from these systems will be monitored such that follow-up decontaminations can be planned as necessary.
II.
EVALUATION This project is expected to save 240 person-rem.
III.
CONCLUSION This project will be accomplished as scheduled.
IV.
STATUS The B211R1 outage portion of this project is complete. The remaining work involves disposal of waste resin. The resin has been sampled and will be disposed of when the sample results are received. This should be done by October 1994.
V.
TARGET COMPLETION Ongoing PROJECT MANAGER JAY TERRY PID R0123A PID R0123A Category II.
I SPENT FUEL POOL COOLING ASSIST - PIPING & PENETRATIONS I.
PURPOSE AND SCOPE 1
Currently, the spent fuel cooling system is not capable of providing cooling for a full core offload until
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approximately 32 days after shutdown; therefore, the Residual lleat Removal (RHR) system must remain in operation during significant portions of outages which require full core off-load in order to provide adequate cooling. This requirement inhibits RHR system maintenance and prolongs outages. Temporary beat exchangers and cooling towers can be used to supplement the existing spent fuel cooling system and accomplish this cooling function, allowing increased flexibility for RilR maintenance. Since a core offload can be accomplished in about 10 days, the supplemental cooling capability can save about 22 days of outage time. The scope of this project is to install permanent auxiliary fuel pool cooling system penetrations, piping, and valves in the Unit i Reactor Building. 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 SSFPC equipment is performed by project R01231.
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I II.
EVALUATION l
1 Schedule Index: 18 - The use of permanent piping significantly improves the viability of using an alternate spent fuel pool cooling system. This allows RilR system maintenance flexibility during outages; this l
minimizes the length of refueling outages, increasing unit availability (1.0 x 12). Permanently installed piping minimizes the need to install and remove temporary system piping, reducing radiation exposure (0.5 l
x 9). The use of permanent piping and the increased avellability of the RHR system without extensive temporary cooling system setup work constitute a plant enhancement (0.2 x 8).
Economic Aspects: The use of permanent piping for supplemental spent fuel pool cooling is more cost effective than the use of temporary piping. Overall, the use of the alternative cooling system for spent fuel cooling allows increased RHR system maintenance and decontamination flexibility, significantly reduchg the length of refueling outages.
Related Standards: This project is related to Work Manageinent Policies for human resources and outage management.
Other Considerations: The scope of this project is limited to the installation of permanent piping and valves for the supplemental cooling system.
III.
CONCLUSION This project will significantly increase the viability 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. The savings are significant, so this project will be completed as scheduled.
IV.
STATUS Design is complete and installation will start in August 1994. Project is implementation phase approved by the Plant Review Group. Prefabrication of piping and supports is 60% complete.
V.
TARGET COMPLETION December 1994 PROJECT MANAGER CHUCK RAINES
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PID R0123M PID R0123M Category 11
O SMALL PROJECT LISTING PID TARGET NUMBER PROJECT TITLE COMPLETION 00918A REACTOR VESSEL WATER LEVEL INSTRUMENTATION UPGRADE 12/94 02549A SCREEN WASil PUMP UPGRADE 12/94 05307A DC BATTERY LOAD STUDY 12/94
- 05806A RADWASTE EFFLUENT RELEASE LINE REROUTE 12/96
- 05892A EFFECT OF ELECTRICAL SYSTEM VARIATIONS ON TURBINE 12/95 GENERATOR TORSIONAL RESPONSE
- 06650A REACTOR PRESSURE VESSEL THERMAL CYCLING EVALUATION 12/94
- 07438A REPLACEMENT OF OFF-GAS RAD MONITOR RECORDERS 12/99 07848A REACTOR BUILDING ROOF VENT 12/94 08262A DRYWELL COOLERS LOCA OVERRIDE 12/94 08893A CONTAINMENT PENETRATIONS 06/96 p
31856B FIRE BARRIER UPGRADE 12/94
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80203A DIESEL GENERATOR OIL LEVEL ANNUNCIATOR 12/94 84489B 480 VOLT VITAL MCC REWORK 12/94 G0015A SMALL MODS 12/96 G0024A INVESSEL CORE SPRAY PIPING REPAIR 05/96 G0050A SERVICE WATER TASK ACTIVITIES 12/94 G0075A LOCAL POWER RANGE MONITOR CABLE REPLACEMENT 12/95 G0083A INSTRUMENT AIR COMPRESSORS 12/94 G0218A MAKE TEMPORARY POWER FEEDS PERMANENT 12/95
- These projects require design and implementation phase approval by the Plant Review Group. Other projects are design and implernentation phase approved.
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