ML20196J797
| ML20196J797 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 03/08/1988 |
| From: | Gridley R TENNESSEE VALLEY AUTHORITY |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| NUDOCS 8803150060 | |
| Download: ML20196J797 (21) | |
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TENNESSEE VALLEY AUTHORITY 5N 157B Lookout Place MAR 081988 U.S. Nuclear Regulatory Commission ATTN:
Document Control Deck Washington, D.C.
20555 Gentlemen:
In the Matter of
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Docket Nos. 50-327 Tennessee Valley Authority
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50-328 SEQUOYAHNUCLEARPLANT(SQN)-APPENDIXRRESOLUTIONREVIEWTEAMQUALIFICATI0hS c' )/
In response to a verbal request from Rex Westcott of your staff, TVA is providing the resumes for the Appendix R Resolution Review Team as; enclosure 1.
Three of the team members have significant experience with the SQN Appendix R program.
The other two team members have significant experience with nuclear systems analysis.
The team members were chosen to provide a balanced and objective review of the Appendix R concerns.
In particular, the team cembers with Appendix R experience provided a multidisciplined core as well as a thorough understanding of the SQN Appendix R program.
The nuclear systems analysts provided a strong systems overview focused on the key nuclear safety aspects of Appendix R.
In addition, TVA is providing, in enclosure 2, the resumes of three consultants used'by TVA during the review of the Appendix R concerns.
If you have questions, please telephone M. R. Harding at (615) 870-6422.
)
Very truly yours, TENNESSEE VALLEY AUTHORITY R.
ridley, Di ctor Nuclear Licens ng and Regulatory Affairs Enclosures cc:
see page 2 4
G803150060 88030s fDR ADOCK 05000327
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An Equal Opportunky Employer
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-i Mr.
K.,P.
Earr, Acting Assistant Director if(
for Inspection Programs TVA Projects Division U.S. Nuclear Regulatory Comission Region II 101 Marietta Street, NW, Suite 2900 l
Atlanta, Georgia 30323 1
Mr. G. G. Zech, Assistant Director i
for Projects TVA Projects Division i
U.S. Nuclear Regulatory Comission one White Flint, North 11555 Aockv111e Pike Rockville, Maryland 20852 i
Sequoyah Resident Inspector l
Sequoyah//.uclear Plant i
2600 Igou Ferry Road Soddy Daisy, Tennessee 37379 P
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s sv ri NAME:
Frank Albert Koontz, Jr.
i m-TITLE:.
Assistant Chief Nuclear Engineer
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GRADE:
M-7
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B.S. Engineering (with Honors) Purdue Ohiversity, 1973
. q M.S. Nacicar Engineer, Purdue University, 1977
'l 'N Gradate Courses in Computer S:.' ence, P:trdue. University,1977.
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EXPERIENCE:
h June 1986 to Assistant Chief Nuclear Engineer Tennessee Valley Authority Present i
Served as Group Head for the Analysis. snd Plant Support group of the Nuclear Engineering Branch (NELD.., Manager of four staff specialist.: and five sections incledig aadiation 4
Protection, Ttermal Hydraulic and Severe Adident Anaiysis, Environmental Control. Radwaste Engineering, and Prdbabilistic
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Risk Assessment. Group dutica include nuclear analyns anch engineering review associated wi?.h NSSS systems, core melt calculations, contaitant int.egrity AGWA, radwaste system design, and plant decommissiot.ing.
Served as NEB Sequayah design baseline' progrt n sponsor i;nr all systems under branch responsibility. Served as memLor of EPRI Safety Analysis Task Force.
Represented TVA in closure phase of the Industry Degraded Core Rulemaking (IDCOR) progra,u. Responsible for branch automated data processing (ADP) budget in excess of $1 x
million.
fi October 1984 Supervisor of the Radiation Protection Section. Te.nessee to June 1986 Valley Authority Directed engineers in the preparation ot' shielding analyses.
radiation monitoring systems design, design basis accident source term analyses, offsite dose analyses for FSAR preparation, and equipment qualift:ation integrated normal /accidant dose analyses including preparation of radiation dose "maps."
Directed engineers in performing and documenting as low as is reasonab*,.y achievable (ALARA) walkdowns from the design perspective.
Responsible for radiation monitoring system enginn e efforts on Sequoyah
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design baseline program with objective of regenerating der ign basis.
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'Julh61982to Supervisor of the Severe Accident Analysis Section, Tennessee Octoder 1984 Valley Authority q
h, (Specialworkinggroupconvertedtosectionstatus.
Performed s\\
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supervision of section personnel.
Served on IDCOR containment I l Expert Risview Group (ERG).
Directed and assisted in the s
1 preparation of probabilistic risk assessment (PRA) consequence x^
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analyses and Sequoyah IbCOR reference plant dhalysis using the MAAP
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and CRAC2 computer codes.
Reviewed and provided direction to the NRC Severe Accident Sequence Analysis (SASA) programs on Browns Ferry and Bellefonte.
3 August 1931
.%elear Engineer Tennessee Valley Authority t.o July 1982
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lead etgineer for special working group. Technical supervision respvv il.ility for nine engineers in areas of:
thermal hydraulic analysis, including small break loss of coolant accident; anticipated transients without scram; waterhammer and safety / relief valve discharge loads; system transient analysis; and degraded core consequence analysis, including fission product transport and hydrog6n generation.
Responsible for a:onitoring and critiquing s
industry activities in computational analysis of design basis accidents and degraded core accidents. Activities related to RELAP4, RELAP5, REPIPE, RETRAN, MARCH 2, KESS, and other codes.
Projects include ATWS analysis and probabilistic risk assessment consequence analyses.
January 1981 Nuclear Engineer, Tenr.essee Valley Authority August 1981 Technical supervisor over several engineers and engineering aides in area of computational analysis. Members of post-TMI Combustion Engineering Owners Group analysis subcommittee.
Supervised and trained personnel in qualitative / quantitative studies of primary system, secondary system, heat transfer, fluid flow, and external har.ards analysis for design and FSAR preparation.
Evaluated PWR Ovnees group activities on small 1.OCA, inadequate core cooling, etc.
Septembu 1978 Nuclear Engineer, Tennessee Valley Authority to Januaty 1981 Performed, and directed engineers of a lower grade, in the analysis of hydrogen generation, secondary system blowdown and force load calculations. Assisted in the development of hydrogen mitigative systems and in resolution of licensing issues, includine evaluations of flame propagation burn characteristics, oilution effects, and equipment survivability.
Represented TVA in RETRAN users group.
Performed torus pool heatup calculations and force loadings on jet pump beams to resolve BWR concerns.
Provided computer expertise for others in group and branch on CDC services r.nd IBM inhouse machines.
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' May 1975 to Nuclear. Engineer. Tennessee. Valley Authority August 1976 Performed calculations as summer work student.
Examined hazards due to natural gas pipeline rupture by application of code previously coauthored for gas diffusion, detonation, thermal 1
radiation, and peak overpressure following a pipeline accident.
Prepared and executed RELAP4 models of various piping systems.in PWR and BWR plants as part of safety reviews.*' Checked vendor analyses and prepared FSAR revisions.
I January 1976 Research Assistant. Purdue University to August 1977 Performed research for the Nuclear Regulatory Commission on liquid metal fast breeder reactor safety. Assisted others in research on cladding relocation, bubble growth, and drop fragmentation.
Performed, documented, and analyzed experiments on LMTBR transition phase accident.
Explored use of microwaves for volumetric heating simulation of two component pool boiling.
August 1971 to Nuclear Co-op Student Tennessee Valley Authority l
August 1975 i
Performed work assignments of varying level of sophistication including fluid flow, heat transfer, and shielding analyses.
Prepared computer programs and converted existing subcompartment pressurization and containment analysis and studies of the performance of Mark III containment vent clearing behavior.
Performed shielding calculations using point kernel approximations for various source / shield configurations within the plant.
Calculated containment pressure / temperature response following inadvertent containment spray. Assisted in preparation of FSAR
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material and computer analyses using RELAP3.
LICENSES OR CERTIFICATIONS:
American Nuclear Society American Society of Mechanical Engineers Association for Computing Machinery IEEE Computer Society National Computer Graphics Association 4
Registered Professional Engineer, Tennessee #017372 I
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RESUME t
NAME:
Robert H. Bryan, Jr.
TITLE:
Senior Engineering Specialist I
GRADE:
M-6 EDUCATION:
BSNE, University of Tennessee l
EXPERIENCE:
June 1986 to Senior Engineering Specialist Tennessee Valley Authority Present Serve as technical and administrative advisor to the Analysis and Plant. Support Group of the Nuclear Engineering Branch.
'the group consists of five sections responsible for radiation protection, thermal hydraulic and severe accident analysis, i
environmental control, radwaste engineering, and probabilistic risk assessment. Required to have total cognizance of the Group's activities.
In addition serve as project manager for major engineering programs on main steam line break, containment isolation, and severe accident issues.
Provide j
independent assessments of the Sequoyah baseline program.
Represent TVA on Babcock and Wilcox and Westinghouse Owners Groups.
Serve as a member of the NUMARC Containment Issues Task Group.
September 1982 Supervisor Nuclear Analysis Section. Tennessee Valley l
to June 1986 Authority Managed a section of engineers in the preparation of analyses in the areas of thermodynamics, heat transfer and fluid flow.
Responsible for developing pressure and temperature time j
histories for equipment qualification to high energy line i
breaks, analyses of design basis accidents for FSAR preparation and response to NRC issues, containment response a
to pipe breaks and equipment failures, waterhammer, 1
safety / relief valve discharge loads, thermal response of structures and components to thermal loads, fluid system design and heat exchanger performance. Developed a major 4
program for determining the response of the Bellefonte NSSS to a wide range of accidents and transients and verifying the adequacy of the newly developed operator guidelines.
Responsible for completion of the Mark I Torus Program.
Served on various utility owners groups and served as chairman of the Babcock and Wilcox Analysi9 Committee.
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December 1979 to Nuclear Engineer, Tennessee Valley Authority September 1982 Lead engineer for the Nuclear Analysis Group.
Technical supervisory responsibility for engineers in the areas of containment analysis, general heat transfer and fluid flow l
evaluations, and hydrogen production and behavior during degraded core events. Responsible for the development of the MONSTER containment analysis code and new heat transfer routines for evaluating the effects of steam line breaks inside containment. Directed the preparation and review of FSAR material related to containment performance 4
and reactor coolant system response to design basis accidents. Represented TVA before the NRC, ACRS, and in international meetings.
August 1973 to Nuclear Engineer, Tennessee Valley Authority December 1979 Performed analyses in the areas of heat transfer, fluid flow, subcompartment pressurization, and containment pressure and temperature response. Responsible for determining containment isolation and leak rate testing design requirements for TVA nuclear plants. Responsible for the preparation, review and defense of TVA licensing submittals in the areas discussed above.
June 1972 to Summer Student, Tennessee Valley Authority September 1972 Assigned to Colbert Steam Plant Performance Section.
Performed routine surveillance of plant system to assure i
q that operational limits and performance objectives were a
met.
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POSITION Plant Operating Review Staff: Manager NAME John Henry Sullivan, Jr.
FORMAL EDUCATION North Carolina State University BSNE 1977 BSME 1977 Certificates:
Registered Professional Engineer in Tennessee Shift Technical Advisor NDE Leak Rate Examiner EXPERIENCE (DATES, POSITION, EMPLOYERS)
July 1986 to present: TVA, Manager, Plant Operating Review Staff, Sequoyah Directs the activities of the Plant Operations Review Staff (PORS).
Initiated the. staffing of the section with competent supervisors and engineers.
Investigates noted problem areas or special events on request of the plant manager or PORC.
Assesses the cause of the event and recommends corrective action or assesses effectiveness of ongoing corrective action. Responsible for the maintenance'and tracking of Potential Reportable Occurrences (PR0s) and their disposition via evaluation of reportability in accordance with 10 CFR 50.72,10 CFR 50.73, 10 CFR 20, 10 CFR 21, and 10 CFR 73.71.
Ensures proper preparation of Licensee Event Reports (LER) for plant manager's signature in accordance with NUREG 1022 (including Supplement I and Supplement 2).
Ensures proper preparation of nonroutine special reports as required by technical specifications for the plant manager's signature. Directed the onsite program for handling all conditions adverse to quality received from the design organizations, including preparation / approval of all safety evaluations and determining reportability. Ensured proper coordination and preparation of technically involved USQDs when requests are made by plant sections.
Coordinates Technical Specification Interpretation Committee meetings.
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February 1985 to July 1986: Supervisor, Regulatory Engineering Section, i
Sequoyah Directed the section and completed the staffing of the section with competent individuals. Prepared draft licensing submittals and l
forwarded to the Licensing Branch for submittal to NRC.
Prepared plant procedures to govern the activities of the section.
Established the Sequoyah operating experience review system.
Responsible for the onsite Final Safety Analysis Report update process, Technical Specifications l
changes process, Appendix R fire protection program, and evaluation of conditions adverse to quality received from the design engineering organization. Principal plant contact for interface with NRC-NRR activities. Maintain cognizance of Industry efforts by 4
supporting /providing membership in various owner group activities (WOG and AIF). Serve as Assessment Team Let. der in the Technical Support Center and recommend protective action fcr the general public during emergency exercise.
August 1984 to February 1985:
Project Manager, 10 CFR 50 Appendix R, Sequoyah Reassigned to direct.Sequoyah's reevaluation of compliance to 10 CFR 50 Appendix R. "Fire Protection." Directed a team of multidiscipline engineers through a complex program to satisfy a confirmation of action letter from NRC-RII and ensure compliance with the rule.
Submitted deviations from the rule to NRR for ap;roval.
Determined plant modifications required to meet the rule and provide the inhouse documentation to meet requirements.
Served as team leader during a week
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l long NRC team inspection of our compliance to Appendix R.
1 June 1984 to August 1984: Supervisor, Regulatory Engineering Section l
Filled this new position at Sequoyah.
Prepared job descriptions to staff the section with competent engineers.
Assigned responsibilities to senior level engineers. Directed the section in evaluating regulatory requirements to ensure compliance with existing or new requirements.
Served as the plant contact for various licensing activities including environmental qualification and Appendix R.
Directed the site program for evaluation of nonconforming reports j
received from the design organizations.
November 1983 to June 1984: Reactor Engineer, Chattanooga Prepared safety evaluations, unreviewed safety question determinations, and recommended corrective actions for identified problems and nonconforming conditions at the plants.
Prepared technical specification changes for Sequoyah.
Prepared submittals to NRC or.
licensing issues (NUREG 0737).
Interfaced with the owners Groups, Westinghouse, and NRC on various technical issues.
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' January 1982 to November 1983: Mechanical Engineer, Shift Technical Advisor (STA), Sequoyah Completed STA training, first in class and later taught portions of the class.
Involved in the operation, performance, and testing of a nuclear unit.
Performed core calculations, such as shutdown margin, estimated critical conditions, and thermal power.
Ensured compliance with technical specifications.
Knowledgeable of response to transients and accidents.
Provided advice to operations management concerning normal operations, transient and accident conditions.
When not on shift as an STA, performed the functions of the Senior Mechanical Test Engineer.
Supervised the NSS/ Ventilation group (group leader) and supervised the test section in the absence of supervisor. Acted as test director on specific tests, such as ECCS flow balancing and steam generator helium leak tests.
July 1979 to January 1982: Mechanical Test Engineer Seque, Prepared, performed, and supervised ASME XI pump and valve tests, 10 CFR 50 Appendix J containment isolation valve leak tests,' ANSI N510 filter system and ventilation tests, condenser air inleakage tests, and steam cycle performance tests.
Performed vibration analysis of rotating equipment. Supervised engineering aides and supervised the test section in the absence of the supervisor.
January 1978 to July 1979: Mechanical Construction Engineer, Sequoyah Directed the installation of mechanical components. Ensured compliance with QA requirements.
Performed hydrostatic pressure testing of completed systems.
Prepared design changes during the installation of systems and coordinated these changes with other groups.
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Norman D. Black, Jr.
l EDUCATION:
BSEE, University of Southwestern 1,ouisiana, 1962 f
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EXPERIENCE:
1970 to Electrical Engineer, Tennessee Valley Authority l
present i
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j Responsible for conduit, grounding and cabling design.
Experience with Watts Bar environmental qualification program.
Participated in the Sequoyah Appendix R program i
since 1984.
Several years' experience as a unit supervisor in the electrical design project.
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- l 1962 to 1970 Electrical Design Engineer, Boeing Corporation I
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RESUME i
NAME:
Jimy J. Pierce EDUCATION:
B.S. Electrical Engineering, Texas Tech University, 1973 Fire Science Technology Courses Roane State - 1975-76 EXPERIENCE:
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August 1986 Engineering Specialist, Tennessee Valley Authority I
to present I
Assigned to the Mechanical Engineering Branch (MEB) to serve as Appendix R Program Manager for the Division of Nuclear j
Engineering (DNE).
Provide program guidance and technical j
review and assistance to DNE organizations for Appendix R related issues.
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May 1982 to Electrical' Engineer. Tennessee Valley Authority August 1986 l
I Assigned to the Fire Protection Engineering Sect 1on in MEB.
i Primary responsibility consisted of compiling Appendix R
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analyses from various disciplines into formal report to NRC l
and to develop fire protection criteria to meet Appendix R requirements.
Developed deviation / exemption requests to Appendix R rules for Browns Ferry, Sequoyah, and Watts Bar
' Nuclear Plants. Developed fire protection criteria for fossil and hydro power plants.
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I April 1980 Electrical Engineer, Tennessee Valley Authority I
to May 1982 l
i Assigned to Electrical Wiring Section #4 on Bellefonte design f
project. Responsible for producing the interface wiring l
diagrams between TVA functional control and logic diagrams l
and Consolidated Control Corporation control cabinets (Solid j
State Control System). Also developed connection diagrams for the Process Computer System; Status, Environmental and j
Alarms Monitoring Systems; Reactor Protection System.
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LNCLOSURE 2 Resumes of Consultants 99 l
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MAR 8 '88 12:37 BLCP-R 202-857-9800
'PAGE.'01
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RESUME JAMES MICKAEL McGARRY, III 5910 Cedar Parkway Chevy Chase, Maryland 20815 P)one:
(301) 654-0792 PERSONAL DATA:
Born July 30, 1943; married, three children EDUCATION:
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Degree 1965 from University of Pennsylvania, B.S.
The Wharton School; majored in Economics LL.B. Degree.1969 from University of Virginia Admitted to District of Columbia Bar November 1969; admitted to Maryland Bar June 1972; admitted to U.S.
Supreme Court, July 1976 FORMER JOBS AND EXPERIENCEt
. Law Clerk to former Chief Judge
- Matthew F. McGuire, U.S. District Judge, Washington, D.C.,. 1969-1970 Assistant U.S. Attorney for the District of Columbia, 1970-1973 Partner, Conner & Knotts, 1747 Pennsylvania Avenue, N.W.,
Washington, D.C. 20006, engaged in the representation 1973-1976 of public and private utility clients, PRESENT POSITION:
Partner, Bishop, Cook, Purcell & Reynolds, 1200 Seventeenth 20036, continuing my
- street, N.W.,
Washington, D.C.
representation of public and private utility clients as well as pursuing other forms of litigation, 1977-present ACTIVITIES:
Member, American Bar Association Member, Public Utility Law Section of the American Bar Association Member, Lawyers Committee, Atomic Industrial Forum i
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MAR 8 ' 88 12:37 BLCP-R 202-857-9000 FHuh.dd
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Board of Directors, Wharton Club of washington Board of Direct' ors, University of Pennsylvania Club of Washington, D.C.
Board of Directors, Catholic Charities of"Archdiocese of Washington, D.C.
Member, Chevy Chase Club Member, Metropolitan Club PUBLICATIONS:
Author:
"The Nuclear Alternatives An Analysis of Paralysis,"
28 Nastings L J. 1209 (1977) c
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, t%R.'08 ' 88 12: 21 TENERA CORP LEThESDA P.2 L
RICHARD H. VOLlMER Vice President i
Education 1
B.S.
Physics, University of Notre Dame F
an==ary of Ibmarienca Mr. Vollmer has 34 years of management and technical experience with an amphasis on policy develo nuclear power plant issues. pment and program direction of significant At the NRC, he had major policy and program responsibility in all aspects of nuclear power regulation, including issuance of licenses, ordars, and enforcement actions; review of planning, plant designs and safety analyses; review of amargency QA, and environmental tions and implamenting criteria. programs; and development of regula-1
.He had technical responsibility for engineering, earth science, QA and environmental issues for plants under construction and in operation.
He chaired the NRC Piping Review committee whose recommendations to the Commission on leak-before-break and other important. aspects of piping design have led to major rulu relaxations.
His. work. with industry orr the BWR recirculation pipe cracking provided a path. for resolutica of. i.hs. 3rrohlum utthout plant shutdowns.
He had major responsibility in resolvig issues raiwnd by allegations of quality. problems, harassment and intimidation and i
interfacing with CI.
Prior to the NRC, Mr. Vollmer had extensive technical and management experience encompassing design and operation of nuclear power plants and research facilities.
This included work on boiling and pressurized light water systems and liquid metal reactors.
He was a consultant for the AEC on reactor operator licensing activities.
1 1987 " Present Vice President, TENERA, L.P.
Responsible for development and implementation of programs in the Management Services Division to support utility management needs in the following areast operational performance improvement, rate case hearings and 4
prudency reviews, and evaluation of organizational effectiveness and corporate strategy on regulatory issues.
1968 - 1987 Deputy Director - Office of Nuclear Reactor Regulation, NRC.
Responsible for the technical and policy direction of regulation of nuclear power l
plants including review of applications for cps.and l
OLs, implementation of requirements arising from j
generic safety issues, issuance of orders and other plant requirements, and licenses and amendments.
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. MAR,'00 '88 12:22 TEfCRA CORP BETHESDA p,3 l
RICHARD M. VOLU(ER Vice. President Page 2 1968 - 1987 (continued)
A principal in the development of NRC policy, regulatory positions, and technical requirements, Mr.
Vollmer met frequently with the Commission, Congress, utility exacutives, and the public and press.
At time of license issuance, he assumed principal role in resolving technical issues, allegation of plant deficiencies and interfacing with the Office of Investigations.
i Deputy Director - Office of Inspection and Inforcement, NRC.
Responsible for the technical and policy direction of the NRC's policies and programs for regional operations, inspection programs, emergency planning, nuclear vendor programs and quality assurance, and enforcement.
Director - Division of Engineering, NRC.
Responsible for directing the NRC's technical review of nuclear i
power plant issues in the engineering earth sciences,
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r.. ::. +. 0A.3 End environmental disciplines.
Mr. Vollmer
- pr.ovided nanagement and technical leadership in
. developing licensing documents and testimony to support licensing decisions before Hearing Boards and the Commission.
He took personal charge of certain difficult licensing reviews and technical issues such as BWR pipe cracks, fire protection, environmental qualification, and technical and quality allegations which threatened to delay licensing.
Director - TMI-2 Program Office, NRC. Responsible, in the year following the accident, for developing and l
implementing programs and policies to assure long-term safe shutdown and operation benign to the public and environment.
This included review and approval of licensing programs, development of inspection 1
programs, and policy on the clean-up operation.
Assistant Director - Division of operating Reactors, NRC.
Responsible for directing technical review and licensing activities associated with all currently 1
operating reactors in plant systems, physics and core reloads, electrical and IEC, and the NRC's systematic evaluation program.
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OTENERA
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'. MAR 08 '88 12:23 TENERA CORP BETKESDA P.4 RICHARD H. VOLIMER Vice President Page 3 1968 - 1987 (Continued)
Assistant Director - Site Safety, NRC.
Responsible for directing technical review and preparation of regulatory guidance in accident analysis, radiological assessment, health physics, and plant affluent treatment.
Mr. Vollmer was leader of the NRC's Liquid Pathway Study which evaluated transport, interdiction, and consequences of severe accident release into the liquid pathway at various types of plant sites.
Chief - Quality Assurance Branch, NRC.
Responsible for licensing reviews of QA programs, conduct of operations, and pre-op test programs for plants in construction and operation.
Developed initial Standard Review Plans and regulatory guides in these areas and initiated the Standard Technical Specifica-tion program, setting forth content and format and developing four standard Tech Spec models.
Technical Coordinator and Project Manager - NRC.
Managed licensing reviews for several operating reactor projects and coordinated technical ccview for operating reactors and operator licensing function.
1962 - 1968 Supervisor - Test Analysis and operations, Atom!.cs International.
Responsible for developing and implementing test prograns for SNAP ground test reactors and evaluation of test results.
Activo in review of a broad range of safety issues for AI's reactor facilities.
Consultant to AEC as operator license examinar for power and research reactors.
1958 - 1962 Supervisor - Physics and Critical Experiments, Allis-Chalmers.
Directed critical facility operations and test program for a BWR superheat design, trained operators, and directed physics design and evaluation.
Developed innovative techniques for measuring physics parameters peculiar to a reactor having a central superheat (void) region.
1952 - 1958 Senior Physicist - AMF Atomics.
Responsible for nuclear core calculation for power reactor lattices and for heavy and light water research reactors.
Directed start-up of foreign and domestic research reactors.
1/88 OTENERA
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RICHARD H. VOLLER Vice President Page 4 1952 - 1958 (Continued)
As a physicist with DuPont at Argonnq National Laboratory and the Savannah River Plant, conducted l
experiments for' development of the first submarine reactor core (Nautilus) and for core designs for production of weapons materials.
sencial Achiaverants
~ l Meritorious service Award, USNRC Member of Executive committee, International Association for Structural Mechanics in Reactor Technology Invited Principal speaker, Nuclear Safety Research Association, Tokyo, Japan e
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I.i STEVEN R. Wi!TSETT OK Lead Senior Engineer Plant Engineering Division RESPONSIBILITY Mr. Whitsett is a Lead Senior Engineer in the Fire Protection group of the Plant Engineering Division at Impell Corporation's Southeast Regional office.
He is an Impell certified Project Engineer with the responsibility for project technical direction, budget, and schedule.
RELATED EXPERIENCE Hr. Whitsett has over 15 years of experience with supervision, operation, maintenance, and testing at naval and commercial pressurized water reactors, specializing in electrical distribution and fire protection.
This experience includes six years as a Navy Nuclear Power Instructor and operator qualification on four different PHR plant designs.
Fire Hazards Analysis Project Engineer for a Thermo-lag reduction effort at Commanche Peak Steam Electric Station.
This project identified alternative methods to the use of fire protection wrap to protect equipment required for safe plant shutdown in the event of a fire.
This project was highly successful with significant financial savings recomended to the client.
Project Engineer during a Fire Hazards Analysis at the Westinghouse Fuel Fabrication Facility.
This evaluation identified recommendations to improve the fire protection features and capabilities at the plant.
Project Engineer for an Electrical Circuit Analysis Data Base validation effort for Houston Lighting and Power's South Texas Project.
Mr. Whitsett was present during the NRC Appendix R Audit and provided direct support in the electrical area of i
evaluation.
Lead Electrical Engineer for an Appendix R Analysis for California Edison.
He was Lead Electrical Engineer, responsible for the circuit identification and analysis phase at the project.
In addition, he was involved with the identification at the Safe Shutdown Systems and equipment for the construction of a component level logic diagram for safe shutdown. He also worked in support of the breaker coordination and high impedance fault analysis.
Mr. Whitsett was also involved in the completion of a Fire Hazards Analysis Update for Rancho Seco.
In this assignment, his responsibilities included:
i Coordination of the commitment tracking aspect of the project.
This work 1
l encompassed identification of all fire protection related licensing i
commitments, tracking of open items and providing recommendations for closeout j
of these items where required.
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hStev'enR.Whitsett Page 2 Evaluation of the loss of safe shutdown :omponents as they relate to overall system function.
This task also included incorporating these effects into the update of the Fire Hazards Analysis.
Origination and revision of fire protection related surveillance procedures to ensure compliance with the olant technical specifications.
Project Engineer, developed a format and procedure for an Appendix R Time and Hanpower Analysis which has become the standard for Southern California Edison.
This analysis is part of the material which supports the feasibility of manual actions required to support Appendix R compliance.
Appendix R Inspection Mr. Whitsett has significant experience in the areas of Appendix R Pre-audits and NRC Appendix R Inspections.
He has participated in four Appendix R Pre-audits.
During these pre-audits, Hr. Whitsett evaluated the plant's ability to comply with the electrical, emergency lighting, communications and safe shutdown procedural requirements of Appendix R.
As part of the Impell team involved in support of power plants during NRC Appendix' R Inspections, Mr. Whitsett has represented a number of utilities in conversations with the NRC reviewers.
EMPLOYMENT HISTORY Lead Senior Engineer, Impe11 Corporation, July 1987 to present.
Impel.1 Corporation, January 1985.
U.S. Navy, January 1973 to January 1985.
Hr. Whitsett qualified as Engineer Officer of the Hatch and Engineering Hatch Supervisor and was responsible for the maintenance and operation of power plant systems including electrical distribution and generation systems.
In addition, Hr.
Hhitsett was a Naval instructor responsible for technical training on plant 1
operations on fire fighting and damage control.
EDUCATION B.S., New York State University U.S. Naval Nuclear Power Training SFPE Techniques of Quantitative Fire Hazards Analysis REGISTRATION AND PROFESSIONAL SOCIETIES National Fire Protection Association, Industrial Section Defense Fire Protection Association j
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