ML20117E168

Proposes to Conduct self-assessment at Facility to Examine Effectiveness of Engineering Activities & Programs & Controls Established for Identification,Resolution & Prevention of Problems.Assessment Encl.Encl Withheld

ML20117E168
Person / Time
Site:	Waterford
Issue date:	05/14/1996
From:	James Fisicaro ENTERGY OPERATIONS, INC.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML19355D151	List: ML20117E168
References
W3F1-96-0075, W3F1-96-75, NUDOCS 9605150486
Download: ML20117E168 (20)

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, En egy Operations,Inc.

Killona. LA 70066 Tel 504 739 6242 s J. Fisicato a tord W3F1-96-0075 A4.05 PR May 14,1996 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555

Subject:

Waterford 3 SES Docket No. 50-382 License No. NPF-38 Proposed Self-Assessment  ;

1 Gentlemen: 1 in accordance with the NRC's program to permit self-assessment alternatives to NRC team inspections, Entergy Operations, Inc. proposes to conduct a self-assessment at Waterford 3 to examine the effectiveness of engineering activities, and programs and controls established for the identification, resolution and prevention of problems. The objective of the assessment is to evaluate engineering activities using the guidance of NRC Inspection Procedure (IP) 37550,

" Engineering," to identify strengths, weaknesses, and areas for further improvement.

Based on our discussiorts with the NRC Region IV staff, we understand that the staff concurs with the self-assessment option as an alternative to a full scope engineering inspection.

Attachment 1 outlines the objective, scope, general approach, schedule, level of effort, and team qualifications. Attachment 2 provides the details of the assessment plan and Attachment 3 includes the resumes of most of the assessment team members. Please note that this is a preliminary list that will be revised to add additional team members as indicated. Remaining team members will be identified and resumes not included will be forwarded by May 23,1996.

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Proposed Self-Assessment W3F1-96-0075 Page 2 May 14,1996 i

We appreciate the opportunity to participate in the self-assessment program.

Should you have any questions or require additional information, please contact me at (504) 739-6242 or Don Vinci at (504) 739-6370.

Very truly yours, ames J. Fis to i Director Nuclear Safety l JJF/RTK/tjs Attachment cc: L.J. Callan (NRC Region IV)

C.P. Patel (NRC-NRR)

, R.B. McGehee l N.S. Reynolds l NRC Resident inspectors Office l

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, Attachm:nt 1 W3F1-96-0075 Page 1 of 2 ASSESSMENT OVERVIEW OBJECTIVE The objective of this self-assessment is to examine the effectiveness of Waterford 3 engineering activities; to recognize strengths and identify opportunities for improvement. The guidance provided in USNRC IP 40501 will be used so that this  !

assessment can be performed as an altern&tive to a full-scope NRC inspection.

l SCOPE The Waterford 3 engineering assessment will be conducted using USNRC IP 37550, 1 This procedure was used to develop the assessment plan provided in Attachment 2.

The assessment will include evaluation of the following areas / activities:

1. General engineering capabilities

2. - Design and configuration control

3. Involvement / responsiveness in site activities

4. Identification / Resolution of technical problems

5. _ Effectiveness of the independent safety engineering group (ISEG) function APPROACH The assessment will be accomplished by performing an in-depth vertical evaluation of a significant safety system, the Emergency Diesel Generators, and a horizontal review of other selected engineering activities on either a system or process basis.

The in-depth evaluation will emphasize verification of selected design / licensing bases, configuration centrol and system capabilities while the horizontal review will provide a broader look at engineering involvement / responsiveness in site activities and general engineering capabilities.

SCHEDULE The assessment is scheduled for July 22-August 2,1996. A report of the completed assessment will be provided to the NRC Regional Administrator no later than August 30,1996. Additionally, Waterford 3 would welcome an opportunity to meet with the NRC staff to review the results of the assessment. We would anticipate being prepared for this meeting in the latter half of August 1996.

, 1 Attachm:nt 1 W3F1-96-0075 Page 2 of 2 LEVEL OF EFFORT The assessment team will be composed of approximately eight team members plus a team leader. The level of effort is expected to be approximately 640 man-hours of direct inspection.

TEAM QUALIFICATIONS The team consists of experienced technical personnel with expertise in their area of assignment. The resumes of most of the team members are included in Attachment ,

3. Please note that this is a preliminary list that will be revised to add additional i team members as indicated. Remaining team members will be identified and resumes not included will be forwarded by May 23,1996.

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. . Attachtm:nt 2 W3F1-96-0075 i

Page 1 of S j SELF-ASSESSMENT PLAN P

METHODOLOGY The self-assessment will be conducted using a performance based combination  ;

of vertical and horizontal reviews. The established Entergy Operations self-assessment process will be used to conduct the assessment and produce the assessment report.

The vertical review will be used to evaluate engineering effectiveness by reviewing the operational performance capability of the Emergency Diesel Generators. This willinclude a multi-discipline review of selected engineering elements of the system to verify that the engineering performed supports the design basis requirements. The following items will be included as part of this effort:

1. Assessing selected design basis functional requirements.

2. Assessing the adequacy of design and configuration changes.

3. Assessing selected surveillance and post maintenance testing activities.

4. Assessing engineering's capability to identify and resolve problems. j The horizontal component of the assessment will be used to provide a broader -

l review of engineering activities outside the selected system. The following items  ;

will be included as part of this effort:

1. Assessing the effectiveness of the Waterford 3 engineering organization to identify, evaluate, and resolve problems by reviewing the resolution of selected operationalissues.

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2. Assessing the overall effectiveness of the engineering organization in providing maintenance support for such activities as troubleshooting, corrective, and planned maintenance support.

3. An evaluation of the effectiveness of the system engineering function I

to improve and maintain system material condition, trending component performance, and operations support.

4. Assessing engineering work backlog.

5. Assessing the adequacy of selected design and configuration changes, either completed or awaiting installation, and a review of

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temporary alterations to ensure engineering properly supported

implementation of the changes in accordance with approved procedures.

6. Assessing the effectiveness of the independent review functions of the Independent Safety Engineering Group (ISEG).

7. Assessing the use of risk analysis to support operations and maintenance activities.

8. Assessing the effectiveness of engineering communications with, and involvement in operational and maintenance technical issues.

The assessment will be accomplished through a review of relevant design, procurement, installation, maintenance, testing, and corrective action

documents; walkdowns of the Emergency Diesel Generators; and interviews with

! cognizant personnel. Potentially generic issues will be identified and l appropriately pursued across system boundaries.

b i' DETAILED PLAN 1

. Vertical Evaluation b

1. Design and Configuration Control j

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a. Review licensing and design basis documents for the selected system to

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ideritify the functional requirements for the system during normal,

^ abnormal and accident conditions. For the selected functional requirements (team leader to select during assessment preparation) l determine if (1) the design basis is in accordance with the licensing

commitments and regulatory requirements, (2) the design basis,

! analyses, and associated design output documents such as facility L drawings, and procurement specifications are correct, and (3) if the installed system and components are tested to verify that the design bases have been met.

b. Review a sample of safety-significant design changes and temporary modifications for the EDG system and evaluate these changes to verify conformance with the applicable implementation and testing

requirements.

! c. Review the modification configuration and determine if the drawings, l l which reflect the as-built design and installation match the current  ;

L design documents and licensing requirements of the facility. Also l l ensure that plant drawings were either revised and distributed or legibly 4

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marked-up, on an interim basis, to show all changes relating to the plant modification.

d. Determine if the modified system is capable of functioning as specified

by the current design documents and licensing requirements for the j facility, and that 10CFR50.63 Station Blackout, Reg Guide 1.97, and

, SPDS have not been compromised.

e. Determine if the modifications implemented have introduced any unreviewed safety questions and if a 10 CFR 50.59 review or safety evaluation was appropriately documented.

j f. Review the modification packages to ensure that all changes to the

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support elements have been made, including maintenance requirements

! . and procedures, operating procedures, training documentation and training programs, periodic testing, and procurement documentation and specifications.

2. Surveillance and Testing For the selected system, evaluate several technical specification (TS) surveillance and ; ast maintenance tests performed since January 1995, to verify that the tests and surveillances are adequate to demonstrate continued operability.

a. Review and evaluate the technical adequacy of the selected TS surveillance procedures and post maintenance tests.

b. Verify that the system testing adequately ensures that the system will operate as designed under postulated accident conditions. Verify that the surveillance test procedure acceptance criteria are adequate to demonstrate continued operability.

c. Review the component history files, looking for indications of adverse trends or recurrent test failures.

d. Review the inservice test records for pumps and valves in the selected safety system for technical adequacy.

e. Determine if design engineering and system engineering personnel contribute to test procedures and if they review test results.

f. Determine if post maintenance testing for maintenance activities were correctly scoped and implemented.

, Att chm::nt 2 W3F1-96-0075 Page 4 of 6

3. Identification / Resolution of Technical Problems Associated with the EDG System.

a. The assessment team will select a sample of issues, problems, and self-assessments occurring since January 1995, for detailed analysis to assess engineering's ability to identify and correct problems.

Operational events, testing, or maintenance activities (such as temporary repairs or troubleshooting activities).

Equipment deficiencies requiring safety evaluations or operability determinations.

Procedural adherence deficiencies.

Audits.

Repetitive equipment deficiencies.

Other events or issues that may indicate weaknesses.

b. The problems selected above will be evaluated to determine engineering effectiveness in performing the following:

Initialidentification and characterization of the problem.

Proper assignment of priority and elevation of problems to proper level of management for resolution.

Root-cause analysis.

Evaluation of adverse trends or repetitive conditions.

Disposition of any operability /reportability issues and interim resolutions.

Implementation and timeliness of corrective actions.

Expansion of the scope of corrective actions to include applicable related systems, equipment, procedures, and personnel actions.

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.,' , Attachmant 2 I W3F1-96-0075 Page 5 of 6 1 Horizontal Evaluation

1. General Engineering Capabilities - ,

Through a review of selected operational issues evaluate the capability of  :

the engineering organization in the following areas:  !

a. Assess engineering involvement in site activities, particularly in the i resolution of technicalissues,

b. Evaluate the effectiveness of communications within Engineering, and  ;

with other departments such as Maintenance and Operations.

c. Evaluate the extent of backlogged engineering work.

2. Design and Configuration Control  ;

Review selected design and configuration change engineering products I (design changes, temporary alterations, Spare Parts Equivalency l Evaluations, calculations, etc.) in accordance with the criteria noted in Items 1.b-f of the vertical evaluation section:  ;

i (Specific items will be selected by the team leader during the assessment preparation)

3. Identification / Resolution of Technical Problems Review a sample of recent technical problems in accordance with the -

guidance of items 3.a-b of the vertical evaluation section. -

4. Maintenance and Operations Support -

Evaluate the effectiveness of the engineering organization in providing maintenance support for such activities as troubleshooting, corrective and preventive maintenance support, and use of risk analysis to support operations and maintenance activities, i

a. Review selected corrective and preventive maintenance activities for safety significant components performed since January 1995.

Determine the level of engineering involvement in planning the )

maintenance activity. Discuss with relevant maintenance personnel to I determine if sufficient engineering support was provided.

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b. Evaluate how Waterford 3 ensures the operability of equipment for  !

systems such as ATWS, SBO, SPDS and RG 1.97 instrumentation that are not covered by TS but are installed in accordance with commitments and are important to the safe operation of the plant,

c. Assess whether probabilistic risk assessment considerations were made i when removing components from service for planned maintenance. I l

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Attachm:nt 2 VV3F1-96-0075 Page 6 of 6

d. Assess whether Operations has been supported with timely and thorough review of technical problems (e.g., review operations work around !ist and determine if engineering issues are being addressed in a timely manner).

5. ISEG Function Effectiveness Evaluate the overall effectiveness of the independent safety engineering function by reviewing a sample of ISEG reports issued since January 1995.

a. Assess if reports are thorough and of appropriate breadth and depth.

b. Determine if appropriate recommendations are provided.

c. Determine if recommendations are responded to/ implemented in a timely manner.

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6. System Engineering Function Evaluate the effectiveness of the system engineering function to trend and maintain system material condition, and provide operations and maintenance support.

a. Review the role of the system engineers and their knowledge of system requirements and plant design basis. i

b. Review the system engineers involvement in system activities; including planned maintenance, modifications, surveillance testing, condition reports, and nonconformances.

c. Review system engineering effectiveness in trending and monitoring system performance.

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ATTACHMENT 3 l

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, , Attachmsnt 3 W3F1-96-0075 Page 1 of 1 WATERFORD 3 ENGINEERING AND TECHNICAL SUPPORT SELF-ASSGSMENT July 22-August 2,1996 l ASSESSMENT TEAM 4

Team Leader:

Jerry Roberts, Entergy Operations, Director Nuclear Safety and Licensing Team Members: i Phillip Wagner, Contractor Jeff Wright, Grand Gulf, Mechanical Design Engineering Supervisor Clyde Little, ANO, Mechanical Engineer, Technical Assistant to Design Director Drew Bottemiller, Grand Gulf, Superintendent, Plant Licensing ,

Larry Phillips, Grand Gulf, Senior l&C Design Engineer Dan Dormady, River Bend, Manager System Engineering TBD (EDG System Engineer)

TBD (Electrical Design Engineer) l Assessment Coordinator:

Tom Smith 1

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• .n JERRY C. ROBERTS ,

Director, Nuclear Safety & Licensing i

EXPERIENCE .

f ENTERGY OPERATIONS,INC.

March 1994 Director, Nuclear Safety & Licensing, Corporate Headquarters. Reports to the Vice-President,

. Operations Support - Echelon, and is responsible for directing the licensing staffin actisities pertaining to monitoring and providing analysis on new and long-term generic issues, pro-active participation with the NRC and industry to achieve the resolution of generic issues, facilitating consistency on selected regulatory issues, providing short-term staff support, and coordinating j Entergy Operations interface with NUMARC. In addition, is responsible for directing Corporate .

Quality Assurance and Nuclear Assessment functions. The Corporate Quality Assurance function insures that corporate activities performed for the sites are carried out in accordance with Quality Assurance requirements. The Nuclear Assessment function seeks to ensure excellent performance ,

in the safe operation of Entergy's nuclear stations through performance based assessments. These -

assessments are designed to measure operating plant performance against criteria of excellence (not regulatory compliance).

Sept.1991 Afanager, Plant Afaintenance, Grand Gulf Nuclear Station. Reports to General Manager, Nuclear Operations - GGNS, and is responsible for the safe, efficient, and cost-effective implementation of all plant maintenance activities in accordance with appropriate procedures and regulatory ,

requirements to enable maximum power generation and plant availability.  ;

July 1988 Afanager, Performance andSystem Engineering, Grand Gulf Nuclear Station. Reports to the GGNS General Manager, and is responsible for the safe, efficient, and cost-etTective implementation of all plant engineering activities in accordance with appropriate procedures and  !

regulatory requirements to enable maximum power generation and plant availability.

1987-1988 Afanager, Plant Afodification & Construction, Grand Gulf Nuclear Station. Promoted to (Acting)

Manager, Plant Modification and Construction in April 1987. In June was promoted to Manager, i Plant Modification and Construction. Reported to the GGNS Site Director, and was responsible for planning, scheduling and implementing major maintenance and modification activities during both outage and non-outage periods at GGNS. This included installation and documentation of

• all modification work activities; maintenance of the interface with Plant Staff and NPE for outage activities; coordination of all assigned work activities such as modifications, major maintenance activities, retests, etc., being performed during outage and non-outage periods; and establishment and implementation of all Design Changes at GGNS. Also served as Duty Manager and Emergency Director for the GGNS General . Manager.

1978-1987 e Technical Assistant to Afanager, Plant Support, Grand GuliNuclear Station. As the Technical Assistant to Manager, Plant Support, reported to the Manager, Plant Suppon and assisted in his day-to-day duties. Such duties are associated with Technical Support, Warehousing and Security.

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. TechnicalSupport Superintendent, Grand Gulf Nuclear Station. Reported to the Manager, Plant Operations, responsible for Results Engineering, Reactor Engineering, Shift Technical l Advisors, and Startup Test Group. Special assignments have included Manager, RPD of Technical Specification rewrite. Routine responsibilities include coordinating suneillance program / implementation and approval of surveillance procedures. Reporting to RF01 Outage Director also substituted for Backshift Outage Manager Obtained NRC SRO License, GGNS, Unit No. I License Number 20487 on 10/19/86.

. StartupManager/ Superintendent, Grand Gulf Nuclear Station. Reported to the General Plant l Manager / Manager Plant Operations, responsible for closeout of Phase I systems punchlist (including applicable testing, maintenance and design change activities), Phase 11 systems l completion and testing, and implementation of power ascension test program. During this l time provided support to Technical Engineering Organization by overseeing DCP approval, implementation and close out process and coordinating System Engineering functions during surveillance rewrite program.

. Startup Supervisor, Grand Gulf Nuclear Station. Reported to the Startup Manager, l

responsible for supenision of the preoperational and acceptance test programs and preparations for the Power Ascension Test program. Responsibilities included the i coordination of testing activities to meet the project schedule, approval of test procedures, l coordination with Bechtel-CfO, and coordination with plant staff for operations and I mamtenance suppon.

. Assistant Startup Supervisor, Grand Gulf Nuclear Station. Reported to the Startup l Supenisor. Provided assistance to the Startup Supenisor in the supenision of preoperational and acceptance test programs and coordination of day to day operations and maintenance l

support.

l . Group Leader, Grand Gulf Nuclear Station. Reported to the Startup Supenisor. Prosided i assistance to the Startup Supenisor in the supenision of preoperational and acceptance test programs and coordination of day to day operations and maintenance support.

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. Startup Test Supervisor, Grand Gulf Nuclear Station. Organized and issued Plant Startup Mamtal and participated in its writing; design review and correction ofliquid and solid radioactive waste systems; preparation ofliquid and solid radioactive waste systems, and containment integrated leak rate test preoperational test procedures; review of construction and acceptances of radioactive waste building and facilities; general engineering suppon to other Startup Test Supenisors and their systems.

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INGALLS SillPBUILDING 1974 Radiological Engineer. Responsible for the following duties to support the refueling and ,

overhaul of nuclear submarines: Man-Rem Reduction Engineer; Radiological Work and l 3

Management / Organization Auditor; wrote and approved decontamination procedures, radioactive waste packing procedure, and radioactive liquid processing system design and operating manual; had overall radioactive liquid processing engineering responsibilities; wrote shipyard radiation emergency plan; engineer for performance of and approval of I

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Jerry C. Roberts Page 3 of 3  !

i detailed radiation shield survey results (lead on two submarine data reduction supervisor on one).

Prepared and conducted training ofinstrument operators, data recorders, and data reduction personnel for performance of shield survey. l GEORGIA POWER COMPANY ';

1974-1978 . Test Engineer - Responsible for resiew of systems in order to set instrumentation calibration, logic checks, and functional checks, and functional checks. Review and approval of completed data packages. '

. Preoperational Test Engineer -for completion of local leak rate testing to complete containment integrated leak rate test; developed and performed functional and logic checks of emergency diesel generator systems. -

e FuelLoading Engineer - Alternated between refueling floor and control room to direct and verify fuelloading operations.

. Startup Engineer -for initial criticality through five to ten percent power testing.

EDUCATION 1974 Mississippi State University, Stark 3ille, MS.

B.S. Nuclear Engineering l

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THOMAS H. SMITH JR. 1 Senior Oversight Specialist Nuclear Safety And Licensing i

Experience l 1982 - Present Louisiana Power and Limht/Enterav Operations 1991- Senior Oversight Specialist, Nuclear Safety and Licensing (Assessments). Responsible for planning, scheduling, and leading performance based assessments of activities / processes at all Entergy Operations facilities. Was Acting Manager of the Assessment Group during the formative stages of assessment process development from October 1992 to February 1994. The EOI assessment process has been recognized by others in the industry, INPO and NRC as a superior process. Over 160 assessments have been conducted since the inception of the process.

t 1988-1991 PlantEngineeringSuperintendent, Waterford3. Directed the activities and was responsible for System Engineering, Reactor Engineering and Performance, and Chemistry; a department of approximately 60 engineers'and technicians. Established and staffed the initial system engineering program. Waterford 3  :

performance steadily improved during this period.

1985-1987 Maintenance Superintendent, Waterford 3. Directly supervised the l Electrical, Mechanical and I&C Assistant Superintendents and a small group of maintenance engineers in the management of a departmcat of approximately 160. Led the maintenance department  ;

in the transition from startup support to operational plant l maintenece. Responsible for all plant corrective and preventive maintenance. Achieved a good maintenance record with steady improvements. First plant refueling outage completed successfully.  ;

i 1984-1985 SupportEngineeringSupervisor, Waterford3. Supervised thirteen engineers. Responsible for the final preparation of the Technical Specification, the Equipment Qualification program, the Preservice and Inservice Inspection program and various major surveillance test activities.

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I 1982-1984 Startup Engineer, Waterford 3. Completed startup testing of assigned systems. Shift Test Director for Hot Functional Testing and Containment Integrated Leak Rate Test.

1978-1982 NucIcar Regulatory Commission Two years regional office based inspector, two years Senior Resident Inspector at an operating PWR facility.

Military U.S. Navy. Two nuclear submarine sea tours. Depanment Head on second tour.

Engineer Qualified.

l Education / Certifications i

Bachelor of Science, United States Naval Academy SRO Management Certification, Waterford 3 l

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i ROBERT J. WRIGHT PROFESSIONAL EXPERIENCE:

Engineering Supervisor, Mechanical / Civil Engineering (NPE), Entergy Operations, Inc., Grand Gulf Nuclear Station, Port Gibson, MS.

(1991-Present) Supervisor for the Mechanical Programs group. Responsible for managing the design activities of a technical staff of seven people in a broad spectrum of mechanical engineering programs and systems. Program areas include ASME Section XI, welding and coating special processes, and valve programs. System responsibilities include HVAC and diesel generator systems. Other assignments include performance of metalalurgical evaluations and resolution of containment design and testing issues. Responsible for implementation of Generic Letter 89-10 program for testing of motor operated valves. This program implements industry leading initiatives for minimizing cost and scope by use of valve grouping and PRA techniques.

Currently coordinating major update of ISI and IST 10 year programs. Responsible for developing an alternate design change program to allow valve packing changes with reduced cost and plant impact. Also served as Mechanical Group budget coordinator.

(1989-1991) NSSS Design Engineer responsible for resolving design issues related to emergency core cooling systems. Performed analysis to resolve licensing inues related to fuel pool cooling system design. Presented analysis results to the Nuclear Regulatory Commission and was successful in removing issue from RF04 scope. Directed contractor activities for various RF04 design effons. Performed as Project Engineer for reactor vessel recovery task force during ,

RF04.

(1988-1989) Project Engineer for alternate shutdown cooling system design. Developed conceptual design and prepared scoping document for budget approval. Coordinated multi-discipline design and scheduling. Developed specifications for equipment procurement. Directed the work performed by Architect / Engineer for task specific analyses. Presented design to the Nuclear Regulatory Commission and received approval for use. Supported field implementation.

(1986-1987) Project Engineer for cooling tower upgrade. Performed analysis to determine cause of loss of performance. Developed specification for modifications to upgrade thermal performance, bid negotiations and evaluations, and selected turn-key vendor for contract award.

Performed field engineering functions during construction. Upon completion, performed thermal performance testing which verified performance exceeded design requirements.

(1984-1986) System Engineer for various systems in Balance of Plant Group. Responsible for design of fire protection, fire detection, and domestic water systems. Directed task force that reviewed station fire protection design. Coordinated Mechanical Group work scope for NRC Appendix R audit which resulted in no findings. Developed a Fire Hazards Analysis and administrative procedures to review design changes for impact on the fire protection program.

Developed a working knowledge of NFPA codes.

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OTHER EXPERIENCE:

Supervisor, M. P. Gibson Co., Jackson, MS 1 (1979-1981)

Planned and supervised daily assignments of construction work force performing commercial structural foundation repair.

EDUCATION AND TRAINING:

Mississippi State University, Mississippi State, MS B. S. Degree - Mechanical Engineering (December 1983)

Cum Laude Entergy Operations, Inc. SRO Certification Training - 1990 PROFESSIONAL MEMBERSHIPS:

Registered Professional Engineer - Mississippi l

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DANIEL (DAN) T. DORMADY Manager, Performance and System Engineering, RBS EXPERIENCE ENTERGY OPERATIONS,INC.

January 1996 Afanager, Performance andSystem Engineering, River Bend Station. Reports directly to the Director, Engineering, and also to the General Manager, Plant Operations. Responsible for the direction of the Reactor Engineering, System Engineering, Thermal Performance, and Process Computer groups. Member of the Facilities Review Committee.

April 1994 Afanager, Afechanical/CivilEngineering, River Bend Station. Reported to the Director, Engineering. Responsible for direction of all mechanical and civil design engineering functions including the development of plant design changes.

July 1993 Technical Assistant reporting to the Director, Design Engineering, Waterford 3. Responsibilities included project management of Waterford's power uprate feasibility study and decommissioning cost estimate update to the PSC.

June 1991 Sr. Evaluator at the Institute of Nuclear Power (INPO) on loan from Waterford 3. Responsible for performing evaluations and assistance to the nuclear industry in the maintenance and outage areas. Performed twenty visits to US nuclear plants.

August 1989 Superintendent, Afechanical Afaintenance, Waterford 3, Reported to the Maintenance Superintendent. Responsible for direction of all mechanical maintenance functions and plant housekeeping. During this period an INPO 1 rating was received.

July 1988 Supervisor, Afaintenance, Waterford 3. Reported to the Mechanical Maintenance Superintendent.

Responsibilities included planning and scheduling and plant housekeeping.

December 1987 Engineering and tecimical roles at Waterford 3  !

1986 Consultant to Waterford 3 in configuration management. j 1985 Consultant to Southern Company Services at Plant Vogtle. i EBASCO SERVICES,INC. I i

1981 Engineering and technical positions on the Waterford 3 Project.

EDUCATION 1981 Rensselaer Polytechnic Institute, Troy, New York B. S. Mechanical Engineering (1998) Louisiana State University, Baton Rouge, Louisiana Masters of Business Administration i

1987 Registered Professional Engineer in Louisiana 1

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