ML20046C813
| ML20046C813 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 08/06/1993 |
| From: | Denton R BALTIMORE GAS & ELECTRIC CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9308120214 | |
| Download: ML20046C813 (54) | |
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BAtJIMORE GAS AND l ELECTRI 1650 CALVERT CUFFS PARKWAY. LUSBY, MARYLAND 20657-4702 ROBERT E. DENTON Vict PREssotNT NVCLEAR cNERGY (4io) reo-a ass August 6,1993 U. S. Nuclear Regulatory Commission Washington, DC 20555 ATI'ENTION:
Document Control Desk
SUBJECT:
Calvert Cliffs Nuclear Power Plant Unit Nos.1 & 2: Docket Nos. 50-317 & 50-318 Independent Performance Inspection of the Senice Water Systems Operation Performance The purpose of this letter is to inform NRC Staff that Baltimore Gas and Electric Company (BG&E) i will perform an independent performance inspection of the Service Water Systems Operation Performance at Calvert Cliffs Units 1 and 2. Further, BG&E proposes that this self. assessment be accepted as an alternative to the NRC Staff conducting a team inspection of the same subject area.
The performance inspection proposed by BG&E wiil be performed as described to the NRC Staff at '
the meeting held at NRC Region I headquarters on August 5,1993. The presentation material is included with this letter as Attachment (1). The performance inspection will be patterned after senice water team inspections conducted by the NRC Staff. Documents used will include Staff inspection reports and inspection guidelines. The inspection will specifically cover the scope of NRC Temporary Instruction 2515/118, ' Service Water Systems Operation Performance Inspection."
The inspection will be conducted under the supervision of our Quality Audits organization. The team will consist of six BG&E personnel and six experienced contractor personnel. The team will approximate the size and qualification of an NRC team. Resumes of the contractor team members are included as Attachment (2). Baltimore Gas and Electric Company members experience summaries are being prepared and will be available for review.
The performance inspection is scheduled for the period from August 9 - September 10,1993. There will be an entrance meeting on August 6 and a formal exit meeting on Friday, September 10,1993. A final report documenting the results of the inspection will be submitted to the NRC approximately November 1,1993. A schedule summary is provided as Attachment (3).
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Document Control Desk August 6,1993 Page2-Should you have any questions regarding this matter, we will be pleased to discuss them with you.
Very truly yours, f
i RED,RCG/ dim Attachments: As Stated cc:
D. A. Brune, Esquire J. E. Silberg, Esquire R. A. Capra, NRC D. G. Mcdonald, Jr., NRC T. T. Martin, NRC P. R. Wilson, NRC R. I. McLean, DNP.
J. IL Walter, PSC
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A'ITACHMENT (1) i i
PRESENTATION MATERIALS
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SERVICE WATER SYSTEMS OPERATION PERFORMANCE INSPECTION 8
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I Calvert Cliffs SWSOPI Project Presentation to NRC 8/5/93 Componerr: Coo ing Wa:er (CCW)
Service Wa:er (SRW) 1 Salt Water (SW) i SAFE I
FE OPERATION l
MATERIAL PERSONNEL CONDITION PROGRAMS S-1 1
4 1
.I Agenda
/=A I.
Opening Remarks R.P. Heibel II.
Calvert Cliffs W.E. Kemper SWSOPI Project III.
Independent SWSOPI R.P. Heibel Assessment IV.
Closing Remarks R.P. Heibel I
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Purpose and
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Background
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Purpose To inform the NRC of Calvert Cliffs' past, current and future SWSOPI related activities for consideration by NRC in light of the NRC's more recent SWSOPI initiatives.
Background
BG&E initiated SSFI process in 1987 as a Calvert Cliffs Continuous Improvement initiative.
Safety systems were selected based upon PRA reviews.
SSFIs completed on 3 other safety systems:
AFW ('87), LPSI('89), and EDS ('91).
In 1992 an independent SWS SSFI type inspection was scheduled for summer 1993.
S-3
Calvert Cliffs AN SWSOPI Project
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In 1992, an independent SWS SSFI type inspection was scheduled for summer 1993 as part of CCNPP's Continuous Improvement Program.
In February of 1993, the SWSOPI Project was established in response to continuing NRC and industry SWS concerns and to prepare for the independent SWS SSFI.
Project goal consistent with TI, that is:
. Ensure DB of SWS, CCW, and SW systems are consistently and accurately reflected in design documents.
. Ensure systems are operated and maintained consistent with design basis.
. Ensure systems are capable of performing their safety functions.
Interdepartmental project team matrixed to SWSOPI Project Manager.
S-4
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k SWSOPI Project
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ProjectActivities Mar Apr May Jun Jul Aug Sep Oct Establish Project Team
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Generate DBDs
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, me-a Validate DBDs m m :m m :e _ m m.
SelfAssessment m.m m.m_-
GL 89-13 Report um Ind S~WSOPI/SSFI m msm. _ -
Corrective Actions m7mmmm7:
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L Complete TI AN Coverage
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All TI Inspection Items were covered by SWSOPI Project Activities:
DBD Preparation, Review and Approval.
DBDs for SRW, CCW, and SW systems i
were prepared. This entails consolidating appropriate design and licensing bases information to support both safety and key I
operational functions.
DBD Validation. Performed as pa
Self-Assessment. A programmatic self-assessment to ensure CCNPP processes are sufficient to identify and correct deficiencies and operational problems in a timely manner.
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SWSOPI AN Project & Tl 4
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1 TI2515/118 Inspection Items Activities 3.01 3.02 3.03 3.04 3.05 DBD adf Generation gi DBD bee abe ac abc b
Validation hij k gh ehjl Self cdf bde dfg ae Assessment fghi ik de S-7
4-Self Assessment A\\
Methodology
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An SSFI " vertical assessment technique."
8 week on site effort.
Assessment team comprised of 1 BG&E and 5 full time and 3 part time contractor (UESC) personnel.
Five functional areas reviewed:
. Mechanical Systems Engineering Design and Configuration Control
. Operations
. Maintenance
. Surveillance and Testing
. Quality Assurance and Corrective Actions.
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Assessment Team /
st Qualifications M _\\
Assessment Team BG&E Assessment Coordinator Peter Penn BG&E Project Manager Mike Stephens UESC Team Leader Brian Debs UESC Mechanical Design Rick McAdams UESC Mike Lane UESC Dave Gruber UESC Operations / Testing Frank Mulcahy UESC Maintenance Ted Carter UESC Gene Preston UESC Quahfications Previous NRC employment experience.
Previous plant SSFI experience.
Previous SWSOPI experience.
Previous NRC SWSOPI experience.
SRO experience.
Previous SSOMI experience S-9
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NRC SWSOPI AN Criteria & Scope 4
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Inspection Scope Temporary Instruction (TI) 2515/118 allows for implementation latitude.
Preliminary NRC criteria under development for granting licensees reduced scope NRC SWSOPIs.
Criteria Gooc. SALP rating (a 2 or better)
Good SWS operating performance history Recently conducted SWS self-assessment that meets TI guidance.
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Criteria A\\
Satisfaction
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CCNPP has a SALP rating of 2 or better in all areas and had a 2 or better in its previous SALP.
Historically BG&E has been proactive in responding to performance problems with its '
SWS.
CCNPP has performed a host of SWS improvement activities over the last few years.
Additionally, CCNPP has completed a self-assessment which meets TI Guidance, and An independent BG&E SWSOPI assessment is scheduled to commence on August 9.
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i Good SWS AN Performance
/_ A
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Performance improvement initiatives.
l' Good material condition:
. SW piping and valve replacements.
. Good chemistry on closed syste-ms.
. Degradation is minimized / controlled.
Normal corrective action system via Issue Reports is effective.
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Major SWS s:_
Improvements
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Activities
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'91
'92
'93
'94 Scrape Intake c==
c:s HX Test Program um=== =
HX Retest Program
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Walkdowns e
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UFSAR Review era DB Reconstitution c~""
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U1 SW Piping / Valves Rpled cra era U2 SW Piping / Valves Rpled U-l U7
=a m:5 Clean /Insp Undrgnd Piping Single Failure Analysis
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Clamtrol Trial m:
- SWSOPI Project
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Procedures Review
-m Corrective Actions
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Self Assessment AN Conclusions 4
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t The assessment team has concluded that the plant has taken many actions necessary to ensure that the SRW, CCW, and SW systems are capable of performing their safety functions and are operated and maintained in a manner consistent with their design bases.
Issues discovered during this assessment have been incorporated into the BG&E corrective action system (irs /PDRs) and screened for:
. operability,
. reportability, and
. safety significance S-14
Summary
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CCNPP has taken a very proactive approach to NRC and industry concerns, especially in the SWS area.
TI 2515/118 was completely covered once by the SWSOPI Project activities and will be covered again by the independent SWSOPI Assessment.
CCNPP has a SALP rating of 2 or better in each functiona: area.
Recent experience with CCNPP SWS has resulted in good operating performance.
CCNPP has an effective corrective action process.
CCNPP will continue to implement SWS improvements.
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Recommendations 4= \\
Consider utilizing the efforts of the SWSOPI Project self-assessment and the upcoming independent SWSOPI/SSFIin lieu of performing a NRC SWSOPI.
Consider participating in the upcoming independent SWSOPI.
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Independent SWSOPI
/EN Schedule
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Pre-Inspection meeting (Kick-off) 8/6/93 Week 1 - Commence Inspection at CCNPP 8/9/93-8/13/93 Week 2 - In-Office Review of Documentation 8/16/93-8/20/93 Week 3 - Resume Inspection at CCNPP 8/23/93-8/27/93 Week 4 - In-Office Review of Documentation 8/30/93-9/3/93 Week 5 - Final Week at CCNPP/ follow-up of 9/7/93-9/10/93 outstanding concerns and questions.
" Informal" Exit Meeting on Site (team members 9/10/93 and SWSOPI project response group).
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Independent SWSOPI
/EN Schedule (Cont'd) 4
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Weeks 6 & 7 - Ogden prepares draft report to 9/13/93-9/24/93 BG&E. BG&E team develops report input for inclusion into final collection ofissues.
Week 8 - Final planning and development 9/26/93-9/28/93 of Findings, Recommendations, Issue Reports, and Program Deficiency Reports (PDRs).
" Formal" Inspection Exit Meeting with 9/28/93 Management on-site.
Inspection Report finalized, assembled no later than 10/28/93 by BG&E Team Leader, reviewed and issued with associated Findings, Recommendations, Issue Reports, and PDRs (as appropriate).
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Background &
/EN Focus / Scope 4
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Background
Ogden has been contracted by BG&E to support a SWSOPI of the Salt Water, Service Water, and Component Cooling Water Systems and the Calvert Cliffs Nuclear Power Plant.
Focus / Scope The scope of the inspection includes the following systems:
Service Water System Salt Water System Component Cooling Water System S-19
Inspection
/EN Methodology 4
A
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The inspection is based on the SWSOPI objectives defined in NRC TI 2515/118, " Service Water Systems Operation Performance Inspection" Additional guidance for the concerns listed in TI 2515/118 will be provided by Ogden's SWSOPI Critical Attributes Matrix (CAM),
and BG&E /Ogden Inspection Plan and Checklist for the SWSOPI.
guidance to topical areas of review, priority of review areas, and references to topics that have become issues or concerns at other plants during previously conducted pilot SWSOPIs.
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Areas of A\\
Review 4
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Verify SWS is capable of fulfilling its thermal and hydraulic performance requirements and is operated consistent with its design bases.
CCNPP's response to and implementation of Generic Letter 89-13 Review of system design bases to ensure consistent application of bases through design output and operating documents.
Adequacy and documentation of testing programs.
Maintenance / modification activities to implement and satisfy design and regulatory requirements.
Quality Assurance and Corrective Actions.
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Inspection 2
Team Members
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Inspection Team BG&E Inspection Coordinator /
R.J. DeAtley BG&E QA & Corrective Actions Odgen Team Leader /I&C S.F. Kobylarz Ogden Mechanical Design P.J. Lindsay Ogden J. S. Gray BG&G Mechanical Design /QA Support L. D. Smith BG&E Mechanical Maintenance R.W. DeNight, Jr Ogden R. W. Conklin BG&E Surveillance Testing J.S. Fuoto Ogden Operations T.S. White Ogden P.D. Naley BG&E E&C Maintenance / Electrical V.J. Suchodolski Ogden
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Quahfications Previous plant SSFI experience (including SWS).
Previous NRC SSFI and M1 experience.
Previous SSOMI experience.
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' ATTACHMENT (2)
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i RESUMES OF CONTRACTOR INSPECTION TEAM MEMBERS t
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Q u alific a tio n s a n d Background for t
1 Ogden Environmental and E n e rgy S e r v i c e s C o, In c.
"T e c h n i c a l Sp e c i a li s t s
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A ssisting in th e B G&E Service Wa ter System Op era tion al P e rfo rm a n c e In sp e c tio n i
08/05/93 i
STANLEY F. KOBYLARZ, P.E.
EDUCATION B.S., Electrical Engineering, Lehigh University,1977 i
Drexel University, Courses in Electrical Power Engineering,1979 PROFESSIONAL AFFILIATIONS Registered Professional Engineer, Commonwealth of Pennsylvania,1978 Institute of Electrical and Electronics Engineers
SUMMARY
OF QUALIFICATIONS Mr. Kobylarz has 20 years of electrical engineering and design experience with architect-engineer and consulting firms serving the power generation industry. He has conducted 5.hty Systern Functional Inspections (SSFis) and Safety System Outage Modification !nspections (SSOMis) for both the USNRC and commercial utilities, has participated on a SALP review team and an assessment team of an SSFI/SSOMI program for USNRC, and has performed design reviews and engineering assessments lige for restart and recovery activities for Department of Energy reactor facilities and the Tennessee Valley Authority (TVA). He has over 11 years of experience in supervising engineering activities associated with new construction projects, plant modifications, electrical systems analysis, and design reviews and inspections.
Mr. Kobylarz is experienced in performing assessments of design basis documentation and configuration control activities at nuclear powa ststions, as well as inspections and assessments of the programs, facilities, and affectiveness of plant maintenance
_t activities.
PROFESSIONAL EXPERIENCE Ogden Environmental and Energy Services Co., Inc.
1987 - present a
Manager, Power Engineering. Mr. Kobylarz is responsible for the staffing and conduct of design, engineering, design review, and related engineering and consulting activities j
in Ogden's Blue Bell, PA, office. He previously served as Chief Electrical Engineer, i
providing guidance and direction to the electrical engineering staff. He has i
participated on numerous SSFI teams _as an electrical design reviewer having conducted SSFis at Robinson, Monticello, Cooper, D. C. Cook (2), Calvert Cliffs (2),
Fermi 2, Palo Verde, Browns Ferry, Susquehanna, Surry, Farley, South Texas Project, and Grand Gulf; an Operational Safety Team inspection (OSTI) at Crystal River; Safety i
System Design Confirmations at Palisades (2); Electrical Distribution System Functional Kobylarz - 1 s
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7 Assessments and Inspections (EDSFA/EDSFI) at Calvert Cliffs (Team Leader), Big Rock Point, and North Anna; and EDSFl Readiness Audits and Reviews at D. C. Cook and V. C. Summer. He has also performed SSOMis at Calvert Cliffs Units 1 and 2.
Mr. Kobylarz also performed safety system design reviews for Pilgrim and for the Department of Energy "N" reactor, Hanford, and recovery planning for the "K" reactor, Savannah River. He participated on a USNRC team that reviewed the effectiveness of the utility-sponsored SSFl/SSOMI program at Diablo Canyon, and conducted a review and evaluation of electrical engineering and design for the 1989 SALP at Waterford 3.
Mr. Kobylarz assisted TVA as an independent member on a Bechtel SMART Team that reviewed the Electrical issues Program for the restart of Browns Ferry Unit 3.
Mr. Kobylarz participated on team Maintenance inspections at Calvert Cliffs and Palo Verde, and assisted Susquehanna in their preparations for an NRC Maintenance inspection. He also reviewed the adequacy of the design basis documentation for Alabama Power Company and Consumers Power Company during safety system func-tional assessments and design basis confirmation reviews, respectively.
Mr. Kobylatz is currently Project Manager of a comprehensive EDSFl support program for American Electric Power's Cook Nuclear Plant, which includes preparing system technical notebooks, design basis documents, and engineering analyses for the plant's g
electrical systems.
United Engineers & Constructors, Inc.
1974-1987 Supervising Electrical Engineer (Washington Public Power Supply System, Nuclear Project No.1). Mr..Kobylarz supervised the electrical design and engineering for WNP Unit 1, a 1200-MWe pressurized water reactor generating station, Hanford Reserva-tion, WA, and was responsible for reviewing and evaluating licensing requirements such as NUREG-0800, ATWS, Regulatory Guide 1.97, and Appendix "R" and imple-menting required design changes in the discipline. As discipline supervisor, he was in charge of approximately 15 engineers and designers.'
Public Service Company of New Hampshire (Seabrook). Mr. Kobylarz provided tech-nical review and direction for the electrical plant design modification group activities at the Seabrook Station site.
Tennessee Valley Authority (Watts Bar 1 & 2). Mr. Kobylarz performed calculations and evaluations of motor breakdown kilowatt requirements, assisting TVA engineering in the Watts Bar di'esel generator loading analysis.
Tennessee Vcliey Authority (PIUS Reactor Evaluation Study). Mr. Kobylarz was responsible for the design review of the electrical and process system interface design for an ASEA-ATOM SECURE-P type reactor power generating station as part of the Kobylarz 2
PIUS Reactor Evaluation Study on the cost and licensability to construct a SECURE-P plant in the United States.
Ente Nazionale Per L'Energia' Electtrica (ENEL). Mr. Kobylatz checked electrical equipment design calculations for sizing the station battery and uninterruptible power supply (UPS), station auxiliary transformers, standby diesel generators, motor control centers and power distribution centers for a 980-MWe pressurized water reactor generating station, acting as a consultant to ENEL for their national energy plan.
Electrical Engineer (Washington Public Power Supply System, Nuclear Project No.1).
l Mr. Kobylarz was responsible for electrical design and implementation of reactor (NSSS), engineered safety features, and non-NSSS safety-related control systems. He supervised the preparation of single-line and electrical schematic diagrams, and was responsible for procurement coordination with the related motor control equipment contractor. He was also responsible for the electrical design of the main control room panels and auxiliary equipment, and was the liaison electrical engineer on the Control Room Human Factors Task Force for the main control room. Mr. Kobylarz was responsible for the layout of the 480-volt plant distribution system, including preparation of single-line diagrams and control schematic diagrams.
lise Kobytarz - 3
STUART M. KLEIN, P.E.
EDUCATION B.S., Pennsylvania State University,1960 PROFESSIONAL AFFILIATIONS Registered Professional Engineer, Commonwealth of Pennsylvania
SUMMARY
OF QUAllFICATIONS Mr. Klein's diverse experience spans over 31 years of engineering design in such areas as nuclear power plant systems and mechanical equipment design, industrial mechanical design, design review, and project management. He has more than 12 years of nuclear power plant project assignments while employed with a major architect engineering firm. His work has included the detailed design of mechanical systems with assignments of increasing supervisory and management responsibilities.
He has participated in numerous design inspections (SSFI) with the NRC as well as utility-sponsored SSFl programs. Mr. Klein was responsible for the development of studies related to configuration management controls at operating nuclear plants for the NRC and continues efforts in these areas to support the nuclear power industry.
PROFESSIONAL EXPERIENCE Ogden Environmental and Energy Services Co., Inc.
1984 - present Mr. Klein is responsible for overseeing and directing the activities related to mechanical engineering design and design review of power plant process systems.. In addition, he has served as a consultant to the Nuclear Regulatory Commission and participated in the design review of numerous safety-related nuclear plant systems, including inspections at FitzPatrick (Service Water System Operational Performance Inspection), Palisades, Crystal River, D. C. Cook, Calvert Cliffs, Fermi 2, Farley, and Palo Verde (SSFI), and Dresden (SSOMI). He has participated as Lead Mechanical reviewer for an SSFl of the Engineered Safety Features, Control Room and Fuel Handling Area Ventilation Systems at D. C. Cook and during a SSOMI of the Control Room HVAC System at General Public Utilities' Oyster Creek Nuclear Power Plant.
Mr. Klein developed a training program for the NRC on vertical-slice inspection techniques used in SSFis which he presented at the NRC Regional Offices and NRC Headquarters. Recently, he has also participated as the mechanical reviewer in a utility-initiated EDSFl of the service water system at Clinton' Nuclear Power Plant in which the HVAC, fuel oil storage and transfer, and the service water system were the primary areas of review. He participated as lead mechanical reviewer in a mock inspection of the emergency service water system for NYPA at FitzPatrick Nuclear Klein - 1
Power Plant. This inspection was conducted in preparation for the forthcoming NRC Service Water Operational Performance inspection (SWOPI). Mr. Klein also performed an evaluation of the Calvert Cliffs Nuclear Power Plant safety-related salt water pumps.
Mr. Klein was involved in the detelopment of studies related to configuration management at operating nuclear plants for the NRC. The results of these efforts have been published by the NRC in NUREG/CR-5147, " Fundamental Attributes of a Practical Configuration Management Program for Nuclear Plant Design Control." He has provided support and consultation to the NRC and utilities (Arizona Public Service and Consumers Power Company) in the development of Design Basis Documents. He has served as Design Basis Program Coordinator directing all activities related to the development of Palo Verde Nuclear Generating Station Design Basis Documents for Arizona Public Service. Mr. Klein has also written and served as Project Manager to develop Design Basis Documents for several safety-related systems at Fermi 2 Nuclear Plant.
United Engineers & Constructors, Inc., 1972-1984 Supervising Engineer. Mr. Klein had lead responsibility for the Mechanical Group, Site i
Support Engineering for the Seabrook Nuclear Power Station. Activities included work in all areas of the plant, both safety-related and the balance of plant systems, e.g.,
main steam, circulating water, feedwater systems, and related auxiliary systems. Mr.
Klein's personal responsibilities included directing the work of the engineers and designers; reviewing and approving drawings, documents, and specifications for plant modifications; and, in general, supporting the construction and start-up efforts to complete the Scabrook project.
During this period, Mr. Klein originated the system designs for the safety-related station service water system and a number of other cooling systems, e.g., the component cooling water system. He completed extensive trade-off studies to determine optimum system concepts, equipment sizes and parameters for wet and dry cooling towers, heat exchangers, pumps, etc. He developed final detail designs and directed procurement activities associated with these systems. Much of the conceptual work for these activities was described in a paper entitled " Emergency Shutdown Cooling Towers - Considerations in the Evolution of an Optimum Tower Design," which was published in Nuclear S_afe_ty.
Mr. Klein appeared before the NRC Staff to substantiate the design of essential cooling water systems.
Westinghouse, Bettis Atomic Power Laboratory, 1969-1972 Senior Design Engineer. Mr. Klein was responsible for the design of nuclear reactor plant fluid systems for NIMITZ class nuclear aircraft carriers. He conducted design analysis to assure successful hydraulic and thermal performance of the systems.
Klein - 2
4 United Aircraft Corporation, 1963-1969 i
Design Engineer. Mr. Klein was responsible for the design of aircraft propeller systems and components, pitch change machanisms, and blade retention systems.
He also designed aircraft air inlet control systems, hydraulic actuators, and servomechanisms. He was involved in design tradeoff studies to determine optimum control configurations.
North American Aviation, Inc., 1962-1963 Research Engineer. Mr. Klein was invc!ved in the design of the engine actuation system for the Saturn ll Space Vehicle.
United Aircraft Corporation, 1960-1962 f
Development Test Engineer. Mr. Klein was responsible for the development testing of jet engine fuel control systems and hydro mechanical feedback control servo-mechanisms. He also was involved in the development testing of precision control system components, e.g., flapper control valves, servo controlled linear throttle valves, linkages, pressure control valves, and force balance systems.
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i PAUL J. LINDSAY j
EDUCATION B.S., Mechanical Engineering, Villanova University,1989 EPRI Workshop, Monitoring Equipment Environments During Nuclear Plant Operation,1990 EPRI Seminar, Service Water Systems Reliability improvement Seminar,1993 PROFESSIONAL AFFILIATIONS Engineer in Training (EIT), Pennsylvania American Nuclear Society, Member National Society of Professional Engineers, Member
SUMMARY
OF QUALIFICATIONS Mr. Lindsay is experienced in design, design review, and technical auditing. He is i
familiar with regulatory requirements and has conducted numerous in-depth technical reviews of nuclear safety-related equipment. He has worked on design-related.
projects and has been responsible for preparation of design calculations, drawings, and other design documents associated with key nuclear power plant mechanical systems. He is co-author of EPRI NP-7189, " Review of Polyimide insulated Wire in Nuclear Power Plants," and has developed software and methodology for calculating internal flood heights in nuclear plant critical areas in support of utility INPO SOER 85-5 evaluations.
PROFESSIONAL EXPERIENCE Ogden Environmental and Energy Services Co., Inc.
1989 - present Senior Engineer. Mr. Lindsay is currently supporting the design basis reconstitution effort at American Electric Power Service Corporation (AEPSC) as task leader for the D. C. Cook Nuclear Plant Auxiliary Feedwater System Design Basis _ Document.
Mr. Lindsay supported New York Power Authority's James A. FitzPatrick Plant following their NRC service water system operational performance inspection (SWSOPI). He assisted in the management and scheduling of service water related commitments and activities resulting from the SWSOPI, Generic Letter 89-13, and other service water system inspections..in addition, h.e performed numerous design-
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related' tasks, including Single Failure Analyses, irt support of this effort.
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Mr.'Lind' ay supported t'he design bssis rec'onstitution' effo'rt at AEPSC as lead s
technical reviewer for the design basis documents (DBDs) for the control room and Lindsay - 1 1
engineered safety features ventilation system, for which he reviewed the development of the documents and their technical quality.
Mr. Lindsay was in charge of Ogden's site support to AEPSC for an NRC Electrical Distribution System Functional Inspection (EDSFI) at D. C. Cook. He directed the Ogden team that reviewed all electrical distribution related operating, emergency, abnormal, surveillance, and maintenance procedures; the validation of procedures through plant walkdowns; and the resolution of open items generated from the effort. He supported D. C. Cook through their NRC inspection as a member of their EDSFI response team.
Mr. Lindsay served as lead mechanical engineer on the EDSFl team for Calvert Cliffs and for the EDSFI Readiness Audits for D. C. Cook and V. C. Summer; as a member of the Safety System Functional inspection team for the diesel generators at Peach Bottom; and in Southern Company Services' mechanical design basis review of the diesel generator support systems at Farley. In these efforts, he reviewed and assessed mechanical documentation supporting the design of the emergency diesel generators (EDGs), the EDG support systems, and portions of the HVAC systems serving areas housing safety-related electrical equipment. He reviewed plant modifications, licensing commitments, quality assurance, and incorporation of design requirements into testing and operating procedures.
In other EDSFl preparation efforts, Mr. Lindsay reviewed several OPPD " white papers" and prepared system technical notebooks for Quad Cities and Zion. In a programmatic EQ assessment at Palo Verde, he reviewed material control, procurement engineering, warehouse, and stores procedures; design changes; and quality control procedures to assure that EQ requirements were met.
Mr. Lindsay was principal author of a 1-day system assessment training course presented at Commonwealth Edison. The course included discussions on vertical-slice and other inspection techniques, design bases and documentation, industry experience, and common design deficiencies.
Mr. Lindsay supported the design basis reconstitution effort at Fermi 2. He developed the high pressure coolant injection (HPCI) and the mechanical diesel generator system DBDs and reviewed all supporting calculations. He served as Assistant Project Manager for the HPCI DBD project, directing development of the document. He also confirmed that adequate design requirements, component param-eters, design drawings, and specifications were identified to assure satisfaction of system function and performance.
Mr. Lindsay participated in the high and moderate energy line break analyses of Calvert Cliffs as part of Baltimore Gas & Electric's SOER 85-5 internal flooding evaluation. He developed software and methodology for calculating flood heights in plant compartments housing safety related equipment, performed the necessary calculations contained in ANSI 56.11 for flood evaluation, prepared design drawings, Lindsay - 2 4
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' conducted walkdowns, and evaluated flood impact on Q-list equipment required for safe shutdown.
Mr. Lindsay evaluated the use of polyimide wire insulation in nuclear power plants for the Electric Power Research Institute (EPRI). This assignment included review of industry and laboratory research experience in both nuclear and non-nuclear
- applications, review of nuclear qualification testing of polyimide wire to IEEE Stds j
323 and 317, identification and review of polyimide insulation manufacturing processes, determination of peculiar characteristics of the insulation system, and
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identification of failure mechanisms that could cause problems in nuclear applications.
PUBLICATIONS G. J. Toman and P. J. Lindsay, Review of Polyimide Insulated Wire in Nuclear Power Plants, Electric Power Research Institute, EPRI NP-7189, February 1991.
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VICTOR J. SUCHODOLSKI EDUCATION B.S., Electrical Engineering, Villanova University,1990 Bussmann Overcurrent Protection Seminar,1990 PROFESSIONAL AFFILIATIONS Engineer in Training, Pennsylvania American Nuclear Society, Member Institute of Electrical and Electronics Engineers Eta Kappa Nu, Electrical Engineering Honor Society PROFESSIONAL EXPERIENCE Ogden Environmental and Energy Services Co., Inc.
1988 - present Senior Engineer. Mr. Suchodolski is assisting American Electric Power's D. C. Cook plant in its post-Electrical Distribution System Functional Inspection (EDSFI) efforts.
4w Prior to the EDSFI, he had. reviewed all of the 4-kV and emergency diesel generator (EDG) electrical calculations. He has performed an EDG steady-state loading calcula-tion and has developed 4-kV and EDG electrical systems draft design basis documents (DBDs).
Mr. Suchodolskiis currently developing the case studies to be used for voltage drop / load flow and short circuit analyses using the DAPPER (Distribution Analysis for Power Planning Evaluation and Reporting) and A_ FAULT software programs. He is also performing calculations which establish the thermal damage limits of auxiliary -
electrical system motors, transformers, and cables.
Mr. Suchodolski is skilled in the evaluation of process system pump / motor performance requirements and motor-operated valve (MOV) power and control design.
He recently assisted American Electric Power during their NRC Generic Letter 89-10 MOV inspection.
Mr. Suchodolski served as Senior Electrical Reviewer, AC Systems, for the mock EDSFI conducted at Nine Mile Point 2 and the pre-EDSFI walkdown at Prairie Island.
This review included ac system calculations, specifications, procedures, drawings, and -
vendor information. These inspections assessed the ability of the safety-related.ac -
elect'rical sy' stems to perform their intended safety functions.
Suchodolski - 1
Mr. Suchodolski reviewed the Class 1E ac electrical system calculations and procedures in a Safety System Functional Inspection (SSFI) at Peach Bottom Atomic Power Station.
Mr. Suchodolski served as electrical maintenance reviewer of Calvert Cliffs' electrical maintenance program in an SSFI of the Class 1E ac and de electrical systems. He previously supported the high and moderate energy line break analyses of Calvert Cliffs as part of BG&E's SOER 85-5 internal flooding evaluation.
Mr. Suchodolski supported the de electrical system design basis reconstitution effort at Detroit Edison's Fermi 2 plant. His responsibilities included development of the contents of the dc electrical system DBD, review of design calculations, and identification of system and component requirements.
Mr. Suchodolski supported EDSFl preparation efforts for' Commonwealth Edison's Quad Cities, Dresden, and Zion Stations through the assessment of design calcula-tions and the preparation of system technical notebooks.
He developed an Environmental Qualification binder on NAMCO limit switches for Pennsylvania Power & Light's Susquehanna Plant.
Mr. Suchodolski evaluated maintenance and surveillance data for testing of a failure model for Brookhaven National Laboratory. He classified failure data into different N
levels of component degradation; the components included auxiliary feedwater pumps, saltwater valves, and various motors.
In addition, Mr. Suchodolskiidentified environmental qualification parameters for Kapton insulation and developed a database for EPRl; supported the development of eight Fermi 2 DBDs.by organizing and leading the document retrieval effort at the utility's offices; established a database for tracking references for work on Fermi 2 design basis documents; developed a computer program to_ determine the required size of safety-related batteries per IEEE Std 485; and developed an open items database for functional system description reviews at Alabama Power Company.
Mr. Suchodolski is responsible for electrical, mechanical, and nuclear CAD / CAM design and maintenance; database creation, programming, and manipulation; spread-sheet organization, coding, and maintenance; network support; and hardware, soft-ware, and communications installations. He maintains a working knowledge of current software systems, including database spreadsheet, word processing, graphics, CAD / CAM, and desktop publishing systems.
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General Motors Acceptance Corporation (GMAC) Mortgage Company-1987-1988 PC Programmer. Mr. Suchodolski programmed on IBM Personal Computers in dBASE 111 Plus and Lotus 1-2-3; installed and maintained all hardware, software, and communications devices; and developed benefits programs and reports.
Electronic Data Systems, 1985-1987 PC Programmer / Technician. Mr. Suchodolski developed various database systems on -
personal computers, and provided maintenance, installation, training, and technical
- support for numerous users.
I Colonial Mortgage Service Company,' 1983 - 1985 PC Programmer. Mr. Suchodolski was involved in projects on an IBM Personal Computer and programmed in dBASE Ill Plus and IBM Basic.
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i ROBERT W. DeNIGHT, JR.
EDUCATION B.S., Mechanical Engineering, Virginia Polytechnic Institute & State University,1990 PROFESSIONAL AFFILIATIONS American Society of Mechanical Engineers Engineer in Training (EIT)/1990/ Virginia
SUMMARY
OF QUAllFICATIONS Mr. DeNight provides engineering services for nuclear utility design-related projects.
He is familiar with nuclear plant design and has participated in several technical audits of nuclear plant systems. Mr. DeNight has experience in maintenance, trouble-shooting, and liaison engineering related both to nuclear plant and shipboard reactor systems. He has also performed design stress analyses, piping minimum wall calculations, and developed component maintenance overhaul procedures.
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PROFESSIONAL EXPERIENCE
'MM Ogden Environmental and Energy Services Co., Inc.
1993 - present Engineer. Mr. DeNight is supporting Entergy Operations' Grand Gulf Nuclear Plant calculation assessment program. In this effort, he is responsible for reviewing design-related calculations'for various safety-related systems.
Mr. DeNight has participated as the maintenance reviewer for a Safety System Functional inspection (SSFI) of the low pressure core spray and reactor core isolation cooling systems at Grand Gulf. He was responsible for the review and assessment of the effectiveness of the preventive and corrective maintenance programs, maintenance records and associated documentation, and component failure trending.
Mr. DeNight participated as mechanical design reviewer in an SScl of the main.
feedwater system at Philadelphia Electric Company's Peach Bottcm Nuclear Generating Station. He reviewed and assessed mechanical documentation supporting the design of the feedwater and condensate pumps, MOVs, and feedwater heaters.
He was also responsible for review of plant modifications, licensing commitments, and incorporation of design requirements into testing and maintenance procedures.
He has a working knowledge of CAD and the computer languages' Fortran and Basic.
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Newport News Shipbuilding 1990-1993 Mr. DeNight served as a mechanical engineer in an industrial environment. He performed design work of shipyard tooling and stress analysis of piping. He wrote corrective and preventive maintenance instructions for various shipboard reactor systems. He also performed troubleshooting activities when system discrepancies were discovered. He held confidential restriction data clearance and was radiation
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worker qualified.
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JOHN S. FUOTO, P.E.
EDUCATION 1972, B.S., Mechanical Engineering (With Distinction), Clarkson College of
- Technology (now Clarkson University)
Additional Training: 1983, introduction to Microprocessing / Microcomputers; 1982, r
Design Review Training Course; 1982, ASME Code Familiarization Course; 1981, ALARA Awareness Seminar; 1975, Nuclear Heat Transport and Reactor Design; 1973, Zion Nuclear Power Station Simulator Course PROFESSIONAL AFFILIATIONS Registered Professional Engineer - Pennsylvania (1979), Maryland (1991), Virginia (1991), District of Columbia (1991)
American Nuclear Society
SUMMARY
OF QUALIFICATIONS Mr. Footo has 20 years of experience in design basis development, analysis, safety spq assessment, configuration management, licensing, operational readiness, program
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assessment, quality assurance, emergancy procedure development, technical specifications, plant testing, and procedure development and implementation in the commercial nuclear power industry. Mr. Fuoto is familiar with Calvert Cliffs Nuclear Power Plant design and licensing basis, operating procedures, and personnel.
PROFESSIONAL EXPERIENCE Ogden Environmental and Energy Services Co., Inc., Fairfax, VA 1987 - present Manager, Projects Department,1988-Present. Performed Safety System Functional Assessment for BWR-6 in the area of operations and surveillance testing. Acts as Management Reviewer of the Calvert Cliffs Regulatory Commitment Management Project (RCMP). In that capacity, performed a review of the licensing basis for the Calvert Cliffs Service Water System Scenario document presently being developed.
Project Manager of Calvert Cliffs EAL Upgrade Project. In that capacity, has reviewed and is familiar with AOPs and EOPs. Developed and trained Baltimore Gas & Electric (BG&Ei angineering personnel on Calvert Cliffs-design criteria and safety-related classificatio'ns as part of conti?iuing training progra'ms. Directed Ogden support for @e BG&E Performance Improvement Plan (PIP) for Calvert Cliffs Nuclear Power Plant. Assisted in the implementation and presentation of BG&E's Commitment implementation Assessment (CIA) Project.
Fuoto - 1
c Manager, Systems Engineering Division, 1987-1988. Member of team performing j
an assessment of Technical Safety Appraisals and Design Reviews of Department of Energy (DOE) facilities, including comparison with other safety appraisal mechanisms and recommending improvements. Led evaluation of Limerick 2 readiness for operation in the areas of engineering, design, and analysis including utility, vendor, and architect-engineer programs.
international Energy Associates Limited, Fairfax, VA 1985-1987 Senior Consultant, Technical Services Unit. Developed Technical Specification Guideboo'K for the Republic of China Atomic Energy Council. Project included survey of European, Canadian, Japanese, and U.S. practices, improvement efforts, and use of probabilistic risk assessment.
Westinghouse Nuclear Technology Div., Monroeville, PA 1972-1985 Engineer; Senior Engineer. Directed vendor efforts on application of Owners Group Emergency Response Guidelines to both an early vintage Westinghouse (San Onofre Unit 1) and a Combustion Engineering-designed (Maine Yankee) nuclear power plant.
Developed and reviewed FSAR sections for updating to meet requirements of Regulatory Guide 1.70, developed Tehenical Specification changes, and performed safety evaluations. Provided analytical, licensing, and on-site technical support for North Anna Unit 2 and Sequoyah Unit 1 speciallow-power natural circulation tests.
Developed control and protection system functional design changes, technical specification changes, and emergency procedure changes necessary to support Millstone 3 loop-out-of-service operation.
AWARDS Westinghouse General Manager's Excellence Award,1979,1980 PATENTS Patent No. 4,231,328, " Automatic Feedwater isolation System," Co-holder SELECTED PUBLICATIONS
" Bases for Post-Ac'cident Source Term and Dose Estimation," Philadelphia Electric Company, Revrsion 0, July 1991.
Methodology for Development of Emergency Action Levels NUMARCINESP-DO7, April 1990.
Fuoto - 2
Lessons Learned Notebook, DOE /ID-10193, April 1988.
" Hydrogen Mitigation System for N-Reactor - Analysis and Regulatory Review,"
IEAL-R/87-23, December 1987.
Severe Accident Issue Resolution Process, DOEllD-10172, October 1987.
" Review and Assessment of the Technical Aspects of the Sale / Leaseback of Beaver Valley 2," IEAL-R/87-96, September 1987.
" Development of a Policy for the Use of PRA in the Deployment of Advanced LWRs and for Addressing Severe Accident Considerations," International Conference on Probabilistic Safety Assessment and Risk Management, August / September 1987.
Role of Probabilistic Risk Assessment for Advanced LWRs, DOEllD-10173, August 1987.
" Component Cycle Monitoring System," ANSI Topical Meeting on Computer Applications for Nuclear Power Plant Operation and Control," September 1985.
" Maine Yankee Procedures Generation Package Plant Technical Guidelines," May 1985.
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TERRY S. WHITE P
EDUCATION B.S., U.S. Naval Academy,1980 U.S. Naval Nuclear Power School,1987 b
SUMMARY
OF QUALIFICATIONS Mr. White has 10 years of engineering experience, including commercial and naval nuclear power plants. He has participated as project manager, team leader,.and technical reviewer in numerous design inspection activities and is experienced in using the SSFl vertical-slice techniques. He has exte'nsive engineering inspection experience as a member of utility and NRC SSFI teams and of the distinguished Navy Board of Inspection and Survey. Mr. White's qualifications also include operation and maintenance of power plant equipment while a Navy Engineering Officer, experience in the area of configuration management, and significant experience in training development for a nuclear utility.
PROFESSIONAL EXPERIENCE hiM Ogden Environmental and Energy Services Co., Inc.
i 1988 - present Senior Engineer. Mr. White is the discipline head for performance-based inspec-tions. He also serves as a mechanical system design reviewer and maintenance program reviewer on utility and NRC-sponsored Safety System Functional inspec-tions (SSFis) and El6ctrical Distribution System Functional inspections (EDSFis).
He has participated in SSFis at Maine Yankee (Yankee Atomic), Trojan (Portland -
General Electric), Peach Bottom (Philadelphia Electric), Palo Verde (Arizona Public Service), and Davis-Besse (Toledo Edison). As an NRC team member, he reviewed.
Maine Yankee's component cooling water system. He reviewed the' control building HVAC systems at Trojan and the injection mode of low pressure coolant'-
injection system at Fermi 2. He was a discipline leader in the mechanical and maintenance areas of electrical system SSFis at Peach Bottom and Palo Verde and of.a high pressure service _ water SSFl at Peach Bottom. In each SSFI, he developed and implemented inspection plans, demonstrated a working familiarity _-
with regulatory requirements, and conducted in-depth technical reviews of nuclear safety-related equipment.
Mr.. White has significant experience in preparing for and conducting EDSFis. As team leader, he supported Commowealth Edison's EDSFl preparation efforts at their BWR and PWR stations. This effort involved review of calculations, evalua-tion of technical responses to NRC concerns, and assessment of design basis -
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a documentation for system technical notebooks. He has also participated in EDSFI activities for various facilities, including Wolf Creek and Nine Mile Point 2.
Mr. White has supported a diverse range of utility projects. He provided system engineering expertise to environmental equipment qualification projects for Baltimore Gas & Electric and Tennessee Valley Authority. He was a maintenance reviewer for safety system design confirmations at Consumers Power's Palisades Plant and for an emergency diesel generator SSFl for Toledo Edison. He was a team member of an electrical and l&C maintenance team inspection for NRC Region il at McGuire. He supported Arizona Public Service in a maintenance inspection at Palo Verde and has been a consultant to South Carolina Electric and Gas on its internal SSFl program. He was a member of a team that reviewed internal flooding concerns at Baltimore Gas & Electric's Calvert Cliffs. Mr. White was responsible for the development of the 125/250.Vdc design bases documents for the Quad Cities and Dresden Stations. In addition, Mr. White developed various training documents for Commonwealth Edison site technical staff.
U.S. Navy 1980- 1988 Engineer-in-Training. Mr. White was one of seven naval officers selected for training in the operation and maintenance of naval nuclear power plants. He has
-g naval operational experience with a PWR plant with two main propulsion turbine generators, two main propulsion motors, two ship service turbine generators, two ship service motor generators, and the various auxiliary equipment necessary to support this plant. His maintenance experience includes use of RCM and maintenance trending techniques.
Assistant to Admiral J. Bulkeley, President Navy Board of Inspection & Survey.
Mr. White coordinated and managed the day-to-day operation of ship inspections.
This effort included conducting operational testing of shipboard engineering systems on all classes of naval surface vessels. He was responsible for reviewing maintenance program documentation and maintenance procedures and for walking through selected maintenance procedures with maintenance personnel to identify -
weaknesses in the procedures or in the adequacy of technical training. He also reviewed ship and equipment design documents to verify contractor compliance with government-designated building specifications.
Engineering Officer. Mr. White was responsible for the operation and maintenance of naval propulsion equipment, including one LM2500 gas turbine engine, two ship service turbine generators, air conditioning units, distilling systems, and various auxiliaries required to support this equipment.
Anti-Submarine Warfare Officer. Mr. White supervised 25 technicians in operation and maintenance of sonar, missile, and torpedo systems. A significant portion of this assignment was an overhaul, during which he ensured quality control requirements were met and he developed field changes.
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i ATTACHMENT (3) t 1f SERVICE WATER SYSTEMS OPERATION PERFORMANCE INSPECTION SCHEDULE
SUMMARY
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Background &
AN Focus / Scope
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Background
- - Ogden has been contracted by BG&E to support a SWSOPI of the Salt Water, Service Water, and Component Cooling Water Systems and the Calvert Cliffs Nuclear Power Plant.
Focus / Scope The scope of the inspection includes the following systems:
Service Water System Salt: Water System Component Cooling Water System
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Inspection A\\
Methodology
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A The inspection is based on the SWSOPI objectives defined in NRC TI 2515/118, " Service Water Systems Operation Performance Inspection" A'dditional guidance for the concerns listed in TI 2515/118 will be
. provided by Ogden's SWSOPI Critical Attributes Matrix (CAM),
'and BG&E /Ogden Inspection Plan and Checklist for the SWSOPI.
guidance to topical areas of review, priority of review areas, and references to topics thathave become issues or concerns at other plants during previously conducted pilot SWSOPIs.
Areas of As Review
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Verify SWS is capable of fulfilling its thermal and hydraulic performance requirements and is operated consistent with its design bases.
CCNPP's response to and implementation of Generic Letter 89-13
~ Review of system design bases to ensure consistent application of bases through design output and operating documents.
Adeq'uacy and documentation of testing programs.
Maintenance / modification activities to implement and satisfy
. design and regulatory requirements.
Quality Assurance and Corrective Actions.
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Inspeetion
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Team Members A
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Inspection Tearn BG&E Inspection Coordinator /
R.J. DeAtley BG&E
.QA & Corrective Actions Odgen Team Leader /I&C S.F. Kobylatz Ogden Mechanical Design P.J. Lindsay Ogden J. S. Gray BG&G Mechanical Design /QA Support L. D. Smith BG&E Mechanical Maintenance R.W. DeNight, Jr Ogden R. W. Conklin BG&E Surveillance Testing J.S. Fuoto Ogden Operations T.S. White Ogden P.D. Naley BG&E E&C Maintenance / Electrical V.J. Suchodolski Ogden
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Qualifications Previous plant SSFI experience (including SWS).
Previous NRC SSFI and MI experience.
Previous SSOMI experience.
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Schedule
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Pre-Inspection meeting (Kick-off) 8/6/93 Week 1 - Commence Inspection at CCNPP 8/9/93-8/13/93 Week 2 - In-Office Review of Documentation 8/16/93-8/20/93 Week 3 - Resume Inspection at CCNPP 8/23/93-8/27/93 Week 4 - In-Office Review of Documentation 8/30/93-9/3/93 Neek 5 - Final Week at CCNPP/ follow-up of 9/7/93-9/10/93 outstanding concerns and questions.
"Infonnal" Exit Meeting on Site (team members 9/10/93 and SWSOPI project response group).
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Independent SWSOPI AN Schedule (Cont'd)
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Weeks 6 & 7 - Ogden prepares draft report to 9/13/93-9/24/93 BG&E. BG&E team develops report input for inclusion into final collection ofissues.
Week 8 - Final planning and development 9/26/93-9/28/93 of Findings, Recommendations, Issue Reports, and Program Deficiency Reports (PDRs).
" Formal" Inspection Exit Meeting with 9/28/93 Management on-site.
Inspection Report finalized, assembled no later than 10/28/93 by BG&E Team Leader, reviewed and issued with associated Findings, Recommendations, Issue Reports, and PDRs (as appropriate).
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