ML20134M278

Independent Corrective Action Verification Program

ML20134M278
Person / Time
Site:	Millstone
Issue date:	02/14/1997
From:	NORTHEAST NUCLEAR ENERGY CO.
To:
Shared Package
ML20134M269	List: B16256, Forwards Millstone Nuclear Power Station,Unit 2 Independent Corrective Action Verification Program ML20134M278
References
PROC-970214, NUDOCS 9702200172
Download: ML20134M278 (269)

Text

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Millstone Nuclear Power Station, Unit No. 2 Independent Corrective Action Verification Program (ICAVP)

Section 1 Q Statement of Work O seervervise7

U. S. Nucl: r R:gulatory Commission B16256/Att: chm:nt 1/ Suction 1/Page 1

(] Millstone Nuclear Power Station - Unit No. 2 Independent Corrective Action Verification Pogram (ICAVP)

Section 1: Statement of Work A. Backaround l

Currently, all three Millstone Units are shut down, placed on the NRC's " Watch l List," and cannot restart until authorized to do so by the Nuclear Regulatory '

Commission (NRC). Because of long-standing concerns involving configuration management, corrective actions, and oversight effectiveness, the NRC has i expanded their inspection and enforcement activities at Millstone Station by )

increasing resident and regional inspections, establishing a Special Projects l Office, planning for an Operational Readiness Team Inspection, and requiring a l Manual Chapter 0350 restart assessment.  !

On August 12, 1996, the NRC met with Northeast Utilities (NU) in a public  ;

meeting at NRC Headquarters in Rockville, Maryland. The NRC stated that their inspections and NU's internal audits had identified several issues of concern at Millstone Station, namely:

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Configuration (Design) Control, Implementation of Corrective Actions for known problems, Implementation of Quality Assurance requirements (Oversight), and Compliance with the conditions of the Operating Licenses and NRC regulations.

Based on these findings, the NRC has determined that it is necessary to ensure that: (1) NU's programs to correct design control deficiencies at Millstone Units 1,2, and 3 are effective, and (2) identification of degraded and non-conforming conditions and implementation of corrective actions are satisfactory, and can effectively preclude repetition of these deficiencies in the future. Accordingly, the NRC now requires an independent corrective action verification of the adequacy and results of the programs currently being implemented by NU that are directed at resolving existing design and configuration management issues.

This vuification will consider the adequacy of NU's efforts to establish appropriate design bases and design controls, including translation of the design bases into operating procedures and maintenance and testing practices, verification of system performance, and implementation of modifications since issuance of the original facility licenses.

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U. S. Nucirr R:gul tory Commission B16253/ Attachment 1/Section 1/Page 2

(]) The NRC has directed NU to obtain the services of an organization, independent of NU and its design contractors, to conduct a multi-disciplinary review of l Millstone Units 1,2, and 3. This review is to provide independent verification l that, for selected systems, NU's Configuration Management Program (CMP) has identified and resolved existing problems, documented and utilized the licensing and design basis, and established programs, processes and procedures for i effective configuration management in the future. This review must be comprehensive, incorporating appropriate engineering disciplines, such that the NRC and the public can be confident that NU has been thorough in the identification and resolution of its design and licensing basis issues.

B Scope and Plan Reauirements In all respects, the Independent Corrective Action Verification Program must satisfy the Confirmatory Order issued by the NRC on August 14,1996, and to meet the requirements of the NRC's ICAVP Oversight inspection Plan dated j December 19, 1996. The NRC's Confirmatory Order and ICAVP Oversight l Inspection Plan are enclosed.

The ICAVP will provida a comprehensive examination of the design development and implementation for a selected uample, such as a system or portion of a (m) system as directed by the NRC. It will include onsite verification, on a sampling l basis, of the design and configuration management process since initial issuance of the unit's operating license. ,

The ICAVP will be conducted by an independent third party contractor for NU.

The review team must be comprised of a qualified engineering staff, based on experience and technical credentials. All members of the team, as well as the contractor, must demonstrate financial and organizational independence from NU. In determining independence and qualifications, the primary focus will be on the individuals that will comprise the team. The independence and qualifications of the contractor and members of the audit review team will be reviewed and approved by the NRC prior to contract award.

As indicated in the NRC's Confirmatory Order, Northeast Utilities has committed to undertaking an ICAVP that will include:

. Conducting an in-depth review of selected systems which will address control of the design and design basis since issuance of the operating license for Millstone Unit 2.

. Selecting systems for review based on risk / safety based criteria similar to those used in implementing the Maintenance Rule (10 CFR 50.65);

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(] . Developing and documenting a review plan that will provide assurance that the quality of results of NU's problem identification and corrective action l programs on the selected systems is representative of and consistent with that of other systems i

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. Preparing procedures and schedules for parallel reporting of findings and recommendations by the ICAVP team to both the NRC and NU; and

. Preparing procedures for the ICAVP team to comment on NU's proposed  ;

resolution of the findings and recommendations. 1 The contractor will be responsible for developing a detailed ICAVP that will subsequently be reviewed and approved by the NRC prior to its implementation.

The scope of the plan will encompass a review of modifications to selected systems  ;

since initial plant licensing and must include, in addition to the above attributes, the following elements for the selected systems:

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. A review of engineering design and configuration control processes.

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. Verification of current, as-modified plant conditions against design basis and I licensing basis documentation.

p d . Verification that design and licensing basis requirements are translated into appropriate operating procedures, and maintenance and test procedures.

. Verification of system performance through review of specific test records and/or observation of selected testing on particular systems.

. Review of proposed and implemented corrective actions for NU-identified design deficiencies.

. Review of descrepancies identified and corrective actions taken to prevent recurrence of design deficiencies.

The third-party review will help NU demonstrate to the NRC and the public that when NU's Configuration Management Program is completed, NU will have thoroughly identified design and configuration control problems, corrected the design and documentation issues, and demonstrated that Millstone Unit 2 can be restarted with confidence. Deficiencies in this regard will be identified and reported by the independent verification consultant to both NU and the NRC.

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[ The ICAVP will be a multi-discipline review that will address, as a minimum, areas such as mechanical, electrical, civil, structural, and instrumentation and i control for the systems selected. The ICAVP may include such details as

checking or performing sample calculations; however, the emphasis should be j on the systematic management of the total design process and the adequacy of NU's Configuration Management Program (CMP).

I The process will examine facets of the design management process for a limited j sample of systems as selected by the NRC from initial full-power licensing to j present. This may be modified by the NRC to be responsive to unique conditions 4

for a particular Millstone Unit, or known or suspected generic problems, and in l response to suggestions of the Connecticut Nuclear Energy Advisory Council l j (NEAC). l The evaluation will start with development of a logic or flow network of the design process. Each functional entity within the design organization will be l identified. For each of these entities, internal and external design interfaces which involve transmittal of design information will be specified. From this network, critical design areas or areas with the least tolerance for error will also p be identified. Within each of the design entities, the specific procedures for the V verification and transmittal of design information will be reviewed for i

l conformance with NU's overall Quality Assurance program, and to identify i specific weaknesses in the design process. Based on the results of the review i and the identification of critical design areas, a specific sample such as a system or portion of a system will be evaluated.

In examining design modifications to a system or structure and its specifications, the evaluation will focus on topics such as:

(a) Validity of design inputs and assumptions, l

(b) Validity of design specifications,  ;

(c) Validity of analyses, (d) Identification of system interface requirements, (e) Potential synergistic effects of changes, (f) Proper component classification, O (9) aevisioa cootroi.

4 1 U. S. Nuclear Rcgulatory Commission B16256/ Attachment 1/Section 1/Paga 5 lQ (h) Documentation control, (1) Verification of as-built conditions (j) Validity of testing, and F

(k) Other attributes as determined by NU and the ICAVP consultant, subject to NRC oversight and approval.

! In addition, the ICAVP review will address programmatic areas. For example,

! classification of systems and components, design verification records, interface control and interdisciplinary review, consistency with the Final Safety Analysis Report (FSAR), non-conformance's and corrective actions, and audit findings and resolutions will be sampled during the review process.

i D. NRC Oversicht 1

The NRC is expected to provide close oversight of activities being performed by j the ICAVP consultant. Specifically, the NRC Staff will:

i e Approve the qualifications and independence of the ICAVP consultant, v organization, and team proposed.

. Select systems and/or subsystems for the ICAVP review.

. Assess resolution of ICAVP findings and recommendations.

. Conduct parallel inspections; audit calculations; and review corrective i action implementation for selected systems.

NRC restart oversight inspections (MC 0350) and the ICAVP

independent reviews are parallel and independent efforts.

Conditions / actions required for restart will be determined by the NRC Staff and approved by the Commission.

The NRC Staff will be periodically briefed on ICAVP program results and findings by NU and/or the ICAVP consultant.

l Procedures for effecting this requirement shall be developed by the ICAVP consultant in conjunction with NU.

The NRC Staff will be afforded access to ICAVP consultant J

records and information at all reasonable times.

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Criteria to accept results or to reduce or expand the sample size used for the ICAVP will be developed by the ICAVP consultant in conjunction with NU, and subject to review by the NRC Staff.

Proposed criteria are enclosed.

The ICAVP consultant and NU will maintain a strictly independent i communications protocol. Requests for information will be written.

Phone calls and face-to-face meetings must c:onsider the l requirements of the NRC, who will monitor the inieractions to l assure independence. Use of reasonable Information rechne' available to the NRC and public, will be used.

E. Additional Information n The ICAVP review will not be initiated until NU believes that design and l licensing basis deficiencies are identified for the necessary population of i

systems outlined by the NRC in the Confirmatory Order and in public meetings.

The ICAVP consultant and team will be afforded unescorted access to the Millstone Unit being reviewed, and associated incilities. Team personnel must be able to meet NU's and the NRC's requirements for unescorted access to vital i areas. Also, work done by it e ICAVP consultant must be in accordance with lO tneir annrovee o^ ero9 rem.

The ICAVP consultant selection will largely be based on the probable l effectiveness in demonstrating to the NRC and public that the consultant.is highly qualified, technically competent, and capable of performing a truly independent, objective, and comprehensive review.

i The project manager / lead for the ICAVP consultant will represent the ICAVP company in meetings and presentations to NU, the NRC, and the public. The ICAVP consultant should anticipate significant and frequent interactions with these entities.

The proposal considered the likely existence of an executive level oversight panel to which the ICAVP team would communicate with and keep informed of l

activities and results.

l The following are general attributes that NU and the NRC consider in selecting / approving the ICAVP consultant, respectively:

Financial and Organizational Independence Experience in Design Review Activities / Nuclear Plant Design 3

Availability / Depth of Human and Other Resources l

Technical Experience of Human Resources I

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'ateraa' o"aiitv ro9 e ram ^=se== meat Credentials of Key Project Personnel

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Ability to Make Regulatory Judgments on Findings and Recommendations NRC Experience Level of Corporate interest

{ NU used a Kepner-Tregoe decision analysis methodology to select the ICAVP )

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Q ICAVP Procurement Methodology i

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.Section 2: ICAVP Procurement Methodoloav Backaround As directed in the NRC's August 14,1996 Confirmatory order, Northeast Utilities is committed to the Independent Corrective Action Verification Program (ICAVP) as an appropriate step in the Millstone 2 unit's restart plan. Because of the conditions surrounding this situation, it is recognized that the selection of the supplier for the ICAVP must be accomplished with the utmost objectivity, and that all aspects of the selection be documentable. Therefore, the company has decided to utilize the Kepner-Tregoe Decision Analysis process to make the supplier selection, and has retained the services of a Kepner-Tregoe professional to assist in the structuring of the selection.

Kepner-Treaoe Decision Analysis (DA) Process in the 1950's, Drs. Charles Kepner and Benjamin Tregoe were employed by the Rand Corporation. Their assignment at the time was to help automate the decision making in use by Air Force missile launch officers in the defense of the country during the co'd war. In practice, however, many officers used hunches and intuition, and the quality of their decisions was relatively poor. Subsequently, Kepner and Tregoe spent signsicant time in the business environment to understand how successful decisions were being made. They then articulated their findings into a " process" that could be treasferred and replicated by others.

The most common pitfalls in decision making they discovered were that people became emotional about alternatives, and they failed to consider the risks around choices. The DA process addresses these weaknesses by first focusing on the pe; poses of the decision, and lastly understanding the possible adverse consequences around what appears to be the best alternative (s).

Application of the DA Process to the Millstone 2 ICAVP Procurement The " purpose" of this procurement is to " Select an ICAVP Supplict." Using Kepner-Tregoe's facilitation, NU then developed criteria that defined the ideal candidate supplier to accomplish the ICAVP in c competent, comprehensive and independent manner.

The criteria were further refined into " Essential Criteria" and " Additional Criteria."

Essential criteria are aspects of the selection that must be present for the candidate O sunniier to be eiioibie to nerform tne project. if e criterion is not met. ine sunniier wiii not be further considered to perform this effort. Additional criteria are measures by

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f which eligible candidates can be directly compared to determine which one appears to )

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By making these selection entena visible to candidate suppliers, as well as all other ,

concerned parties, the intentions of the procurement should be clear and direct.  !

Further, once the supplier proposals are received, the application of the selection  !

criteria to the various elements of each proposal will surface the important data and will rationally highlight the strongest candidate supplier.

When the best candidate (s) are identified, the project team will work to assess the possible adverse coneaqrrce5 vi tim cand;dcte(=) This step will ensure that results can be ma . aged and that the project can be accomplished effectively, with confidence of Le public and NRC staff, and in full compliance with the NRC's Confirmatory Order.

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Section 3 Q Proposed Evaluation Criteria for the ICAVP Procurement 1

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Section 3: Proposed Evaluation Criteria for the ICAVP Procurement Essential Evaluation Criteria The following criteria must be met or the bidder was considered nonresponsive to the )

Request for Proposals:

. Suppliers must be independent of NU and NU's design contractors.

. Project team must have technical capabilities in the following areas:

Electrical Engineering Instrumentation and Control Engineering Mechanical Engineering 4 -

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Structural Engineering  !

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Nuclear Plant Maintenance Probabilistic Risk Assessment Design and Licensing Basis Documentation at Commercial Nuclear Plants

. Project team members must meet the following NRC criteria as enumerated in the NRC's Confirmatory Order dated August 14,1994:

i No financial interest in NU or its affiliates No prior involvement in design reviews for NU Not the Engineer of Record or Architect-Engineer for the unit evaluated I Additional Evaluation Criteria The following additional criteria were considered as part of the overall evaluation of the contractor's capability to conduct the ICAVP in accordance with NRC requirements.

The evaluation assessed the proposal most likely to provide a credible, comprehensive, and independent review acceptable to the NRC and the public:

Contractor The following supplier attributes were considered in evaluating capability to conduct O the ic^ve:

U. S. Nucl=r Rrgulatory Commission B16256/Attrchm:nt 1/Szction 3/Page 2 (3 i

. Level of corporate commitment to this project l

. Related experience in design and licensing reviews (design and configuration l l

management, or safety evaluations) and design verification programs Project Leader i

. Project team leadership experience and capability that can accomplish a high .

quality verification. Example attributes that will be considered-  !

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Managerial level within the contractor's organization Credentials, such as education, industry committees, publications 4 Experience, including tec".nical, managerial, and regulatory 1 Communication experience and skills, including technical knowledge and public speaking experience l Project Team

. The following project team capabilities and experience will be considered:

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Experience with similar projects j Other relevant experience, including utility, regulatory, and nuclear design 1 Depth of human resources available in terms of quality and quantity Project Plan

. The effectiveness of the ICAVP project plan in meeting the requirements of the NRC's Confirmatory Order  !

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. The capability of the Information Technology systems proposed (e.g., electronic bulletin board) for use in exchanging information under NRC and public review

. The detail of the plan for organizing, directing, and controlling project resources and activities

. The plan for conducting verification activities openly with joint reporting to the NRC and NU, and subject to public review l l

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Attachment 1 Millstone Nuclear Power Station, Unit No. 2 Independent Corrective Action Verification Program (ICAVP)

Section 4 Proposed ICAVP Criteria for J

t Acceptance of Findings and Expansion of Sample Size i

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Section 4: Proposed ICAVP Criteria for Acceptance of Findinas and Expansion of Sample Size Acceptance criteria to determine the program elements to be covered by the ICAVP scope, to determine when a finding may be considered acceptable and not subject to further review, and to determine whether the sample needs to be expanded shall be established by the ICAVP contractor and approved by the NRC prior to initiating the ICAVP reviews. As a minimum, the criteria shall assure that the following requirements are met for satisfactory ICAVP completion: j Proaram Elements to be Covered by ICAVP Scope

. Configuration Management

. Corrective Action

. Commitment Management l . FSAR update

. 10CFR 50.59 evaluations and conduct of safety evaluations

• Procedure changes

'O Proposed Criteria for Acceptance of Findinas not Subject to Further Review 1

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. No new findings are identified which would have resulted in a shutdown if the unit had been in operation

. No findings are identified in which plant modifications, procedure changes, or operational setpoints would have created an unreviewed safety question or would have significantly degraded a safety margin

. No systematic or programmatic deficiencies are noted in NNECO's assignment, prioritization, or implementation of corrective actions

. All other findings, if new, are a result of program or process deficiencies or weaknesses which have already been identified by NNECO and are being formally tracked and addressed as part of the MP2 corrective action program

. There is reasonable assurance that the plant is now maintaining conformance to its licensing basis l

Criteria for Sample Expansion

. Where findings fall outside of the above acceptance criteria, the sample size may be expanded to provide at least the same level of confidence as the sample being expanded

. Where findings fall outside of above acceptance criteria but are contained within a specific technical or programmatic area, sample expansion may be confined to that technical or programmatic area

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. The collective significance of multiple findings, none of which falls outside of the above acceptance criteria, should be evaluated to determine whether a sample I

expansion is appropriate t

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, independent Corrective Action Verification Program (ICAVP) i Section 5: Proposed ICAVP Communications Protocol Guidelines All communications and reporting will be done openly and made available to all parties.

Parties include the NRC, the ICAVP Contractor, and NNECO (the Principals), and the Connecticut Nuclear Energy Advisory Council (NEAC), the Connecticut DEP, and the public. Communication processes and distribution lists for ICAVP material will be described in the NNECO Project Instruction being prepared for the ICAVP process.

Meetings for conduct of the ICAVP will have representation of the NRC, ICAVP, and

NNECO, as well as other interested participants. Public meetings shall be held i regularly to provide information on the progress and results of the ICAVP and an opportunity to comment on the process. The guidelines for the communications

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l protocol and reporting requirements for the ICAVP are:

I . Reports - Monthly progress reports and a final report from the ICAVP Contractor are  ;

required. Such reports will be issued concurrently to the NRC and NNECO.

Reports will be made available to all participants. Draft reports may be made l available, if appropriate, for open comments by the parties.

O O . Meetinos - Meetings involving interchanges between the parties will be held as j necessary and required. As a minimum, however, these will include:

Weekly working and progress meetings. These meetings are to facilitate understanding among the parties of the issues arising during the ICAVP process and to promote discussion of information to assist the ICAVP reviewers to

, conduct their work in an efficient manner. Attendees include representatives of 1

the ICAVP, NRC, and NNECO, and other interested parties. Meeting summaries will be available to the parties within one week of the meeting and will include information requests and written material exchanged at the meeting.

Monthly program review and status meetings. These meetings are intended to provide overall program status, interim findings, and discussion for representatives of the parties. These rneetings will be open to the public for observation and, following the program review / status discussions, provide an l opportunity to comment and give input. Meeting summaries will be available to the parties within two weeks of the meeting and will include information requests i and written material exchanged at the meeting.

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U. S. Nuciser Regulatory Commission B16256/ Attachment 1/Section 5/Page 2 O . Teleconferences - Teleconferences will be arranged on a case-by-case basis to facilitate information requests and exchanges. All such teleconferences will be '

noticed to the parties via E-Mail (Bulletin Board or Web Site). All teleconferences will be documented in Telecon memos to be available to the parties within one week ,

of the telecon. i i

E-Mail - An electrcaic Bulletin Board System (BBS) will be set up by the ICAVP  !

Contractor for use by designated representatives of the parties to formally transmit information requests and answers to quest;ons. The parties will be provided access to this BBS for observation. Public access to the system will be by a computer

! station located at the local public document room (and Waterford Town Library, if l practicable). All BBS messages will be recorded, retained, and available for subsequent review.

. Correspondence - Routine correspondence and reports shall be in accordance with '

the distribution established in the NRC-approved ICAVP review plan and will become part of the ICAVP records.

. Distribution - Distribution of all communication media will be formalized as part of ,

the ICAVP review plan which is approved by the NRC. The distribution will ensure i parallel and direct reporting of all information to and from the ICAVP participants p and designated representatives of the State and the public. All written and s

electronic communication will be issued and controlled by the ICAVP, NRC, and NNECO project managers, with copies to each of the project managers and/or Project Directors. All ICAVP communications will be made available for public j review at the NNECO local public document room and Waterford Town Library.

Independent Oversiaht Team (IOT)

In order to provide additional confidence that the ICAVP is performed competently, objectively, and independently, an IOT will be established to monitor and oversee ICAVP activities. The IOT will be established to ensure that the ICAVP meets all of the process requirements and objectives specified in the NRC's Confirmatory Order, including review and approval of the ICAVP contractor's work plan, protocol, independence and qualifications of project personnel, and decision making as work progresses. The IOT scope may be applied to the Millstone site.

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O O O SECTION 6 INDEPENDENT CORRECTIVE ACTION VERIFICATION PROGRAM Contractor Selection Attributes This section lists the attributes used in selecting an ICAVP contractor. Since NNECO's evaluation methodology has not changed from that used for the Millstone Unit 3 ICAVP contractor selection, the company attributes listed herein are also the same as those used for the Millstone Unit 3 selection process with the exception of changes made based upon the latest Parsons Power Group proposal. These changes have been shown in the attached figures as bolded print.

- - - . - - . _ _ _ - - - - - - - - - - - - - - - - - - - - - _ - _ - . - - - _ _ - - - - - , - - - - - - - - - - - - - - - - - . - - - - - - - - , - - - , - . - - - - - - - - - - - - _ - - - - _ - - , - - - - _ _ - - - - - - , . _ _ - -_--_u w-

O O O Figure 1-1 INDEPENDENT CORRECTIVE ACTION VERIFICATION PROGRAM Contractor Selection Attributes ESSENTIAL CRITERIA COMPANY A COMPANY B COMPANY C Supplier must be independent of Northeast Utihties . Was not involved in the onginal design of any . Was not involved in the onginal design of any . Was not invo8ved in the original desgn of (NU) and NU's design contractors of the Millstone units. of the Millstone units. any of the Millstone units.

. Has revenues of over $100M per year, with . Has revenues of over $200 milhon per year, . Has revenues of over $900M per year, revenues of approximately 5218K of non- but has received approxirnatey $707 with approximate revenues of about $6 nuclear work from NU in the last ten (10) thousand revenues from the NU nuclear rnillion from NU in the last ten (10) years.

years. organization in the last ten (10) years. The revenues from NU Nuclear are orly 5460 K over ten years or approximately

$46 K per year.

. Not on the Approved Vendor List (AVL) . Was removed at one point from the Approved . Was removed at one point from the Approved Vendor List (AVL) for inactivity. Vendor List (AVL) for inactrvity

. Owns and controls no stock nor has any . Owns and controis no stock nor has any . Owns and controls no stock nor has any financialInterest in NU or any of its financialinterest in NU or any of its financialinterest in NU or any of its subsidianes. subsidsanes. subsidianes.

. If awarded this work, will not provide market . Pending restnctions on future work. . If awarded this work, will not market semees to Millstone 3 for one year following services to MiHstone 2 for one year the completion of the ICAVP. following completion of the ICAVP Project

G n U P)

C U Figure 1-2 INDEPENDENT CORRECTIVE ACTION VERIFICATION PROGRAM Contractor Selection Attributes ESSENTIAL CRITERIA COMPANY A COMPANY B COMPANY C Project team members must meet the following NRC criteria as enumerated in their Confirmatory Order dated August 14,1996:

• No financial irwestment in NU or its affiliates. . Each team member is to sign a 'confhet of . Each team member is to sign a " conflict of = Each team member is to sign a *confict of interest

• statement documenting their tack of interest" statement documenting their lack of interest" statement documenting their lack of e No prer b,c,wse-a in design reviews for potential conthet including any financial potenbal conflict including any financial potential conf!ct including any financral NU. interest in NU. interest in NU. interest in NU.

. Au proposed *eam members have been

• AR proposed team members have been e A5 preposed team members have been screened to ensure that they have no pnor screened to ensure that they have no pnor screened to ensure that they have no prior involvement in design renews for NU. b,C. .. . A in design revevs for NU. involvement in design rewews for NU.

O O Figure 1-3 INDEPENDENT CORRECTIVE ACTION VERIFICATION PROGRAM Contractor Selection Attributes ESSENTIAL CRITERIA COMPANY A COMPANY B COMPANY C The project team must have technical capabilit:es The project team mus' have technmal capabilities The project team must have techncal capabilites The project team must have techncal capabilites in the following areas: in the following areas' in the following areas: in the followmg areas:

e Electrical engineenng . Electrical engineenng . Elec+' ilengineenng . Electncal engineering e instrumentation and Control engineenng e instrumentation and Control engineenng . Instrumentaten and Control engineenng . Instrumentation and Contml engineenng e Mechanical engineenng . Mechanical engineenng . Mechancal engineenng . Mechanical engineenng e Civil engineenng . Civil engineenng . Civil engineenng . Civil engineenng e Structural engeW . Structural engineenng . Structural engineenng . Structural engineenng e Nuclear plant operations . Nuclear plant operations . Nuclear plant operatens . Nuclear plant vyciabis e Nuclear plant maintenance . Nuclear plant maWenance . Nuclear plant maintenance . Nuclear plant maintenance e Probabikste nsk assessment . Probabihstic nsk assessment . Probabiliste risk assessment . Probabihstic risk assessment e Desgn and licensing basis documentation at . Design and Icensing basis documertation at . Design and licensing basis documentation at . Design and l~c ensing basis documentation at commercial nuclear plants commercial nuclear plants commercial nuclear plants commercial nuclear plants

nm Om Os Fig:re 1-4 INDEPENDENT CORRECTIVE ACTION VERIFICATION PROGRAM Contractor Selection Attributes ADDITIONAL CRITERIA COMPANY A COMPANY B COMPANY C Project Plan e The effectrveness of the ICAVP project plan The plan involves the following steps: The plan involves the fonowmg major steps: . The plan involves the folicwing phases in in rneeting the requirements of the NRC's - Establish logistics (smaq point team) - Develop pro #.ocol series:

Confirmatory Order. - Develop detailed plan / submit for NRC - EstatWish the ICAVP Oversight Team - Startup and detailed project approval. - Obtain current documerfs management plan development

- Evaluate candidate systems using risk- - Develop ICAVP project manual - SystemVerification significant weighting factors - Mobilize and train project team - Finalreportissuance

- In paraNet, develop and document a - Select /;cw. 64 systems sample plan for choosing system - Perform revwws attributes. - Findengs and proposed resolutions

- Finalreport

. The capability of the information technology . Not discussed . A public bulletin board will be established to . The plan descusses an anbcipated use of systems proposed (e g., electronic bulletin promote broad communications. electronic information transfers, as wed as a board) for use in exchanging information focus on communscations protocol.

under NRC and public review.

. The plan for conducting verification activities . Minimaldiscussion on protocol . A protocol plan is descussed which describes . A protocol plan cWailed which discussed openty with joint reportog to the NRC and f,U interfaces between ICAVP, NNECO, NRC, ICAVP, NNECO, NRC, and public interfaces and subject to public review. and public.

e The detail of the plan for organizing, . Perform reviews using vertical slice and . The plan wiH use the project director, deputy . The plan proposes to use a vertical slice direchng, and controlling project resources limited horizontal slice app vadies; and director, and intemal review committee .i.cu.4v,vyy in evaluating fue n,&,. ;;;,

and activites. assess for effectiveness /iewimiiei 4 chairman to jointty plan ard implement the through design, operations, maintenance, corrective a~tions, project. testing, and quality considershons.

. The plan contains the most detail of the three proposals received

( (~h ("

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V N Figure 1-5 INDEPENDENT CORRECTIVE ACTION VERIFICATION PROGRAM Contractor Selection Attributes ADDITIONAL CRITERIA COMPANY A COMPANY B COMPANY C Contractor Oraanization The following attnbutes will be considered in evaluating the capabihty to conduct the ICAVP.

e Level of corporate w,n.nm na a to the . President of the company has indcated . Proposed protect director is a senior vice . A Vice President wiH lead the IOT.

project. commitment by way of his personal cover president and owner. Project manager is also letter to the proposal, he will be on the ICAVP a vice president. A member of the proposed Advisory Board Independent Review Committee also is also an owner.

e Related experience in design and licensing . Has performed over 200 site implementation . Performed on IDVP at Hope Creek. . Has developed 12 DBD programs.

revews (design and configuration audits of TMl fixes, numerous emergency management, or safety evaluations) and exercises (15), NRC Maintenance Rule . Performed Vertcal Sice Reviews (Diagnostic . Has performed seven SSFis, and 35 nuclear design venication programs. Inspections,, worked with NRC to review Evaluations) at Salem 2 and Watts Bar Unit pant large scope PRAs.

seve e accident management guidelines of 1.

the four NSSS vendors, and provided team . Related projects include: An Augmented members to 50 SSF1-type inspections. . Corporate expenence includes the design of Systems Review and Test Program, a MIS 13 BWRs 14 PWRs,1 HTGC,1 liquid for design transfer, a Design Control sodium reactor. Program Procedure, a Design Baseline Venfcation Program, and a Configuration Management issues Review.

. Original designer on 16 nuclear units.

. Over $210 milhon in revenue due to power . Over 5927 million in annual revenue in 1995 related work in 1995. and 1996

. Provide services in 27 states and 3 foreign countnes

. Substanhal expenence in configuration . Significant experience reviewing existing . Has developed methods for process management regulatory comphance and programs and facihties, analyzing problems modeling and analysis of design change licensing support, technical evaluations, (50.59 reviews), development of conceptful modifcations, maintenance work control, and preparation of DBDs and PRA. designs, dr.Jeima of procurement fire protection.

specircations, detailed design, engineenng and installation guidance.

O C O Figure 1-6 INDEPENDENT CORRECTIVE ACTION VERIFICATION PROGRAM Contractor Selection Attributes ADDITIONAL CRITERIA COMPANY A COMPANY B COMPANY C Protect Leader Project team leadership experience and capability that can acccmphsh a high quahty verification.

Example attnbutes that will be considered include:

e Managenal Level vnthin the contractor's . Currently not employed by the company. . Proposed project manager is a career . Proposed project director is a Vice organization. Proposed project leader reached the level employee of the company. He was admitted President of vice president with the company, and also to ownership in 1986 and currently is a senict had roles in project management and vice president and project director. . Has 25-yea-s expenence in the nuclear corporate quakty assurance. He was with the industry; involved in engineering, desegn, company for 13 years and left in 1987. construction, operations, and management assessment, both domestic and international.

. Assisted IAEA in nuclear plant technical support documentation.

e Credentials such as education, industry . Pnor responsibihties included: Manager of . Member of the NElIndustry Strategic committees, and pubicatens. Plant Design and Engineenng. Director of Advisory Council and the Supplier Structural Design, and containment vessel Working Group on International Nuclear design and seismic analysis. Safety programs.

. Expenence, including technical, managerial, . Related expenence includes Project and regulatory. Director fct the Watts Bar Vertcal Sice Review (VSR) project. Also has managed t efforts at domestic and foreign nuclear plants, as well as vanety of focsil plants. i e Communcation's expenence and skills, . Recognized industry leader and senior offcial . Holds BS and MS degrees in Civil including technical knowledge and pubhc of US DOE. Engineenng speaking. . Is a professional engineer in 13 states.

. He was with the DOE for four years, on . Is a member of a variety of industry trade projects that involved weapons systems and groups and serves on many committees con 7:ercial nuclear R&D work.

. Spent four years in the Princeton Plasma . Has authorized several related articles for . Is a member of severalindustry groups.

Physics Laboratory. industry journals.  ;

. Has conducted press interviews and . Holds BS and MS degrees in Civil . Consultant to GPU Nuclear's discussions with interest groups. Has given Engineenng. Is a professional engineer in 13 10CFR50.54(f) Management Oversight Testimony before Congress and worked with states. Team for TMI-1 and Oyster Creek local elected offcials.

. Has a BS in Civil Engineering, and a MS in . Is a member of a vanety of industry trade Mechanical Engineenng; is a professional groups and serves on many committees.

Engineer in Cat!fomia.

. Has authonzed several related artcles for industry journals.

m em o O C)

Figure 1-7 INDEPENDENT CORRECTIVE ACTION VERIFICATION PROGRAM Contractor Selection Attributes ADDmONAL CRITERIA COMPANY A COMPANY B COMPANY C Protect Team The following project team capabilites and expenence will be considered:

e Education of team members. Includes a four-level team with a project . Includes a four-level team with a project . Includes a four-level team with a project e Expenence with similar projects. director , deputy project director, QA director, venfcation team manager, quality director, deputy project director, quality manager, four functional team leaders, and assurance manager, four functional team assurance manager, five functional 30 team members. teaders, and 22 team members. teams, and 39 team members e Other relevant expenence, including utility, regulatory, and nuclear design.

e Depth of human resources available in terms . The project director reports intemalty to the . The proposal inc!udes an Intemal Review . The protect director reports to the of quality and quantity. senior vice president - project operations. Committee, and a suggestion that an company President.

independent oversight team be established after the project is begun. . The team includes an advisory panel of recognized industry experts, and an oversight panel composed of former regulatory, industry, and local personnel,

. There is an advisory board, which includes . The team includes 12 MS degrees,3 MBA the chairman / president of the company, and degrees,1 PhD,19 Professional Engineers, a consultant. and 2 SROs.

. All but one team member have at minimum a . The team members have t% experience and . The core team includes 12 MS degrees,6 college degree and 27 have advanced capabildies relevant to the project. PhD degrees,23 professional engineers, degrees. and at lea 13 former SROs.

. The team members have expenence and . The team averages 23 years expenence . The team members have the expenence capabilites relevant to the project. and capabilities relevant to the project

. The team averages 31 years of experience. . The Project Director is a Senior Vce . The team averages over 25 years of President who reports to an Executive Vce experience.

President.

O O O Figure I-8 INDEPENDENT CORRECTIVE ACTION VERIFICATION PROGRAM Contractor Adverse Consequences COMPANY A COMPANY B COMPANY C Advisory board hsts only the company . Proposal doesn1 discuss plan for possible . Proposed project director is not employed by CEO/ President, and one outside consultant substituton of team members. the company.

(whose resume is not included in the proposal). It suggests that other members Resolved for Millstone Unit 2; Project will be named later. Director is now a Corporate Officer.

. No mention is made of plans for an electronic . Project plan proposed to accomplish key bulletin board. activites in series rather than para!!el which creates questionable efficiencies.

Resolved for MP2; Project plan is samlar to Millstone Unit 3

. Proposed project director is not a company employee.

. Project plan and reporting protocol aren't addressed in much detail.

. Proposal doesn't discuss plan for possible substitution of team members.

.p Docket No. 50-336 v B16256 Attachment 1 Millstone Nuclear Power Station, Unit No. 2 Independent Corrective Action Verification Program (ICAVP)

Enclosure 1 Q Contractor Selection Attributes NRC Independent Corrective Action Verification Program Oversight inspection Plan For Millstone Nuclear Power Station Units 1,2, and 3 O February 1997 1

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, MILLSTONE l

INDEPENDENT CORRECTIVE ACTION VERIFICATION PROGRAM OVERSIGHT INSPECTION PLAN l

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Submitted by:

&w&

Eugene V. Imbro

k. /$ M9f.-

Deputy Director, ICAVP Oversight Approved by:

luL.R-William D. Trave %, Director ixth Date #

Special Projects Office O

Attachment

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i MILLSTONE '

INDEPENDENT CORRECTIVE ACTION VERIFICATION PROGRAM I OVERSIGHT INSPECTION PLAN h I. BACKGROUND On August 14. 1996, the Director of the Office of Nuclear Reactor Regulation I (NRR) established a team to provide regulatory oversight of the Millstone Independent Corrective Action Verification Program (ICAVP). The charter directs that an ins)ection program be developed to oversee the ICAVP in a manner similar to tlat outlined in NRC Inspection Manual Chapter (MC) 2535.

" Design Verification Programs." for Independent Design Verification Programs (IDVP). The team will be composed of inspectors from headguarters, regional offices (other than Region I) and contractors with specialized design expertise. The team's efforts are to be coordinated with the MC 0350. " Staff Guidelines for Restart Approval." process.

II. INSPECTION OBJECTIVE The objective of NRC's oversight of the ICAVP for the Millstone units is to ensure that the review conducted by the ICAVP contractor is effective.

performed in a manner independent of the licensee and its design contractors.

and performed by qualified individuals. The oversight is to be comprehensive.

incorporating appropriate engineering discipline and operational reviews, such that the NRC can be confident that Northeast Nuclear Energy Company (NNECO) has been thorough in identification and resolution of design deficiencies and configuration control problems for the Millstone units.

III. INSPECTION METHODOLOGY The inspection of the ICAVP will be conducted in a manner similar to the IDVP.

as outlined in NRC MC 2535. However. the MC 2535 inspection will be modified because the ICAVP will address the adequacy of the original design, design modifications. and control of the design and design bases since issuance of the initial o>erating license. where the IDVPs were conducted prior to the issuance of tie initial operating license. The ICAVP. conducted by an independent contractor, will be similar to inspections described in Inspection Procedure (IP) 93801. " Safety System Functional Inspections." and MC 2530. i

" Integrated Design Ins j current configuration,pection Program." in that the ICAVP will review theincluding th not been modified. and the modifications made since issuance of the initial operating license to determine that the systems conform to their licensing bases and will be capable of performing their intended function.

The NRC's oversight of the Millstone ICAVP for each unit will provide confidence that the licensee's configuration management corrective action l programs have been effective. This inspection plan is based on the NRC's i understanding of the licensees activities and will be modified. as necessary.

to reflect new information. Millstone Unit 3 is currently scheduled to be the lead plant for the ICAVP. The scope and methodology for the inspection of the ICAVP for Units 1 and 2 may be adjusted based on insights gained from the Unit j

3 inspection and the licensee's proposed programs for those units.

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-IV. INSPECTION CONDUCT l.

The NRC's ICAVP oversight staff will perform a number of tasks to ensure that the licensee's configuration management corrective action programs, and the ICAVP. have been effectively implemented. These tasks include the (1) review

, and approval of the contractor, and individual contractor specialists.

i selected by the licensee to perform the ICAVP: (2) review and approval of the contractor's audit plan for performing the ICAVP: (3) independently assessing the licensee's implementation of its configuration management corrective action programs: (4) assessing the performance of the ICAVP contractor's implementation of the ICAVP: (5) monitoring the contractor interactions with the licensee as specified in the approved comunication protocol to ensure continued independence from the licensee: and (6) evaluating the adequacy of the licensee's corrective actions, and their implementation. including corrective actions developed in response to the ICAVP contractor's findings and recomendations, and the findings from the NRC's ICAVP oversight. In  !

arfonning these tasks. a number of inspection and oversight activities will I a performed as described below. Detailed inspection guidance for the NRC's  ;

ICAVP oversight staff will be  !

aspects from MC 2530. ML 2535, and prepared IP 93801. that incorporates the applicable

1. Review and approve the selection of the contractor to perform the ICAVP.

PURPOSE: To ensure that the contractor selected to perform the ICAVP is.

technically and financially independent of the licensee, the NSSS vendor, and the architect-engineer (AE): and technically capable of effectively performing the ICAVP.

O ACTIVITIES: To complete this task the NRC's ICAVP oversight staff will

(/ perform the following:

a. Review the information provided by the licensee and the selected '

contractor to determine whether the contractor has any financial interest or had any technical involvement with the design or construction of the subject Millstone unit.

b. Verify that the contractor has adequate technical and managerial qualifications to conduct the ICAVP.

c. Verify that the individual specialists have the appropriate technical background to participate in the ICAVP. The evaluation will include interviews, as well as a review of individual resumes and certifications.

d. Verify that the individual s3ecialists have no financial interest in NNECO the NSSS vendor, or t1e AE for the subject Millstone unit.

e. Verify that the individual specialists have had no prior involvement with the subject Millstone unit.

2. Review and approve the ICAVP audit plan submitted by the ICAVP contractor.

PURPOSE: To ensure that the ICAVP contractor's audit plan accomplishes the objectives of the August 14, 1996, confirmatory order. includes a sufficient scope and depth, and provides sufficient guidance and instructions to its specialists to effectively implement an assessment of the capability and

' effectiveness of the licensee's configuration management corrective action programs at identifying and addressing licensing-bases deficiencies.

ACTIVITIES: To complete this task, the NRC's ICAVP oversight staff will perform the following:

a. Review the contractor's ICAVP audit plan to ensure it employs a three-tier approach for assessing the licensee's effectiveness at identifying and correcting licensing-bases deficiencies that includes:

Tier 1: A vertical-slice system review method for the approximately four systems similar to the guidance provided in IP 93801 and MC 2530.

Tier 2: A' review of accident mitigation systems that assesses critical design characteristics to ensure that the systems and components can perform their specified safety functions.

This activity requires the NRC's ICAVP oversight staff to review and ap3 rove the critical design characteristics proposed by tie ICAVP contractor.

Tier 3: A review of examples from the various processes used by the licensee to change the facility design or change the characteristics, procedures. or practices for maintaini.ng.

operating, testing, and training on safety or risk significant systems, structures, and components.

b. Review the contractor's ICAVP audit plan to ensure it has sufficient depth to enable the contractor to:

(1) Verify that the licensee's design engineers have sufficient technical guidance to perform assigned engineering functions.

(2) Verify for the selected systems, that the regulatory requirements, and licensing-bases are correctly implemented in specifications, drawings, calculations, and procedures and that systems can perform their specified functions.

(3) Verify that the updated Final Safety Analysis Report (FSAR) accurately reflects the current licensing bases. current plant configuration and operational characteristics of the unit for the selected systems.

(4) Verify that the analyzed facility configuration in the design bases is consistent with the current plant configuration and operational characteristics of the unit for the selected systems.

(5) Verify that the correct licensing-bases information has been reflected in the responsible engineering, maintenance, and operations procedures.

(6) Verify that system design changes have not invalidated preoperational and startup acceptance testing.

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.. ~ -- . .. - - - - - ~ . - - . . - . - - - - - . _ . . -

t l (7) Verify that design controls, as ap) lied to the original design.

have also been applied to design c1anges. including permanent modifications, temporary modifications, procedure changes. and -

' t(c any other processes the licensee uses to change the

configuration or operation of the facility. l j (8) Verify the adequacy of the licensee's corrective actions and assess the effectiveness of the licensee's implementation of the

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corrective actions developed as part of the CMP and in response i to the ICAVP findings.

I (9) Define the contractor's review and inspection schedules for NRC

planning.

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c. Verify that the procedures and review plans developed by the ICAVP i contractor have sufficient administrative and technical instructions and guidance to its specialists to enable them to implement the ICAVP ,

! audit plan as approved by the NRC staff, including: '

(1) Instructions for documenting and reporting observations, findings. and recommendations in a manner consistent with the i August 14, 1996. confirmatory order.

(2) Providing coments to the NRC on the licensee's recomended

! corrective actions in response to the ICAVP observations, j findings and recomendations.

(3) Instructions for communicating with the licensee that are lO j

co">4ste"t ~4t" the co-"#4c t4o" arotecei deve1oPee < r the process.

'd. Review the ICAVP contractor's proposed system selection criteria. The August 14, 1996, order states that the ICAVP audit plan, which the licensee must provide to the NRC before implementation, must describe risk / safety based criteria for selection of systems for review,

e. Select approximately three systems to include within the scope of the ICAVP contractor review. In selecting these systems, the staff will consider the ICAVP contractor's proposed criteria. Also considered by the NRC for system selection are the (1) system's risk significance:

(2) system's design and operating characteristics: (3) number and complexity of changes to the system; and (4) number of previously identified deficiencies and operating problems. In addition, to address public concerns with system selection, the staff will offer to a third party, such as the Connecticut Nuclear Energy Advisory Council (NEAC), the opportunity to select one other system using any method that they deem appropriate.

3. Independently assess the effectiveness of the licensee's performance of its configuration management corrective action programs and performance of the ICAVP contractor in the implementation of its audit plan.

PU0, POSE: To provide the NRC with an independent assessment of the licensee's ability to identify and resolve licensing-bases deficiencies; and assess the 5-

effectiveness of the ICAVP contractor in verifying that the licensee has identified and addressed licensing-bases deficiencies as intended by the confirmatory order.

ACTIVITIES: To complete this task, the NRC's ICAVP overught staff will.

perform the following activities to assess the ICAVP contractor's Tiers 1. 2.

and 3 reviews and provide the NRC will an independent assessment of the licensee's performance:

a. The NRC ICAVP oversight staff will perform a vertical slice review of two systems. One of the reviews will be on a system within the scope of the Tier 1 (vertical-slice) system reviews of the ICAVP contractor.

The second review will be of a system outside the scope of the ICAVP Tier 1 system reviews. The vertical slice reviews performed by the NRC's ICAVP oversight staff will include a review of design calculations and analyses for both the unmodified portions of the original system configuration and design modifications, system walkdowns, review of procedural controls for modifying or changing the facility operational characteristics. The vertical slice review will verify that:

(1) The current configuration is accurately reflects the licensing-bases. including the updated FSAR.

4 (2) The calculations and analyses were performed using recognized and acceptable analytical methods.

(3) The assumptions made in any calculations or analysis supporting the change are technically sound.

gl (4) The results of calculations or analysis supporting the unmodified portions of the original configuration and design changes are reasonable (based on engineering judgement) for the scope of the change.

(5) The licensee considered the effect of a change on design margins and the design changes received the appropriate level of engineering and management review during the design phase and prior to implementation.

(6) The licensee considered the effect of a change on pre-operational, startup. or system baseline acceptance test results.

(7) Design changes were accomplished in accordance with the licensee's approved procedures.

(8) Design changes are accurately reflected in operating, maintenance, and test procedures, as well as in training materials.

(9) Proposed design changes, subsequently cancelled, were not replaced by procedural changes that imposed excessive burdens on plant operators.

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b. In performing the vertical slice review, the NRC's ICAVP oversight staff will conduct in-plant system walkdowns for the two systems  !

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reviewed. The walkdowns will be performed in accordance with specific inspection guidance based on IP 93801 and MC 2535. The walkdowns will '

be multi-disciplinary reviews including, as a minimum, areas such as ,

mechanical systems, mechanical components, electrical xwer, civil and j structural design, and instrumentation and control. T1e walkdowns will l be used to:

(1) Verify adequate control of onerational procedures, maintenance procedures,testandsurveilTanceprocedures,operatortraining, and control of the plant simulator configuration.

(2) Verify that the current configuration is consistent with the licensing bases at the level of detail contained in piping and instrumentation diagrams (P& ids) or system flow diagrams, piping isometric drawings electrical single-line diagrams, and emergency, abnormal, and normal operating procedures. This includes:

(a) Verification of the licensing-bases information contained in the updated FSAR and docketed correspondence.

(b) Verification that the analyzed configuration is consistent I with the current plant configuration. 1 (c) Verification that equipment location and identification numbers are as indicated on the P&lD or process flow diagram.

O and equipment name plate data is consistent with design specifications and analyses.

i (d) Verification that the location of pipe supports, snubbers, and other pipe restraints is consistent with design specifications and piping stress analyses. i (e) Verification that divisional separation of safety-related systems, structures and components, seismic II/I, and other topics addressed by the licensee's hazards analyses are reflected in the current plant configuration.

(3) During the walkdowns, the team will also take note of modifications that appear to have been recently completed.

These modifications will be screened to assure adequate documentation exists and will be included in further review.

c. The NRC's ICAVP oversight staff will select two postulated accidents analyzed in the accident analysis section of the FSAR and independently i review the critical characteristics of the systems relied upon to mitigate the consequences of the selected accident scenarios to assess the ICAVP contractor's Tier 2 review. The oversight staff will ensure that the systems can perform their safety function (s) specified to mitigate the selected FSAR accident scenarios, and that the ICAVP contractor has thoroughly verified the critical characteristics for the systems associated with the selected accident scenarios.

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d. The NRC's ICAVP oversight staff will select samples from each of the change processes within the scope of the ICAVP Tier 3 review, both reviewed by the ICAVP contractor and not reviewed by the contractor, to ensure that the contractor's review was effective in identifying s)ecific and programatic design process control deficiencies. For g

t1ose samples reviewed by the ICAVP contractor include an evaluation of the validity of:

(1) The ICAVP contractor's review methods for assessing the changes.

(2) Any assumptions made by the ICAVP contractor in its review of the changes.

(3) Any independent calculations or analysis performed by the ICAVP contractor during its review of the changes,

e. Verify that NRC comments and recomendations provided to the ICAVP contractor on the scope of the ICAVP were effectively implemented or otherwise satisfactorily resolved.

f. The NRC's ICAVP oversight staff will review the findings and obse vations made by the licensee during the implementation of the configuration management corrective action ]rograms and the ICAVP contractor to determine whether the oversig1t staff's reviews have identified any licensing-bases deficiencies that were not identified by the licensee or the ICAVP contractor.

4. Assess the continued independence of the contractor and its specialists during implementation of he ICAVP.

, PURPOSE: To ensure that the ICAVP contractor maintains an adequate level of independence from the licensee during conduct of the ICAVP.

ACTIVITIES: The NRC's ICAVP oversight staff will control and monitor the interactions between the ICAVP contractor and the licensee as specified in the cc=unication protocol. To perform this task the NRC's ICAVP oversight staff shall perform the following activities:

a. Control and monitor meetings and verbal comunication between the ICAVP contractor and the licensee. Ensure that reasonable efforts are made to allow observation by the designated Connecticut NEAC observers or their alternates.

b. Review the written questions posed by the ICAVP contractor to the licensee and the written replies by the licensee.

5. Assess the adequacy of the licensee's corrective actions, and their implementation, in response to the findings of licensee conducted programs (e.g., CMP), the ICAVP contractor's findings and recommendations, and the findings of the NRC's ICAVP oversight staff.

PURPOSE: To provide the principal input into the NRC's assessment of the ability of the licensee to maintain the licensing bases of the subject unit in the future.

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ACTIVITIES: The NRC's ICAVP oversight staff will review the licensee's

! corrective actions resulting from its configuration management review, the

, ICAVP contractor's review, and the NRC's ICAVP oversight staff activities.

This part of the inspection will be conducted after the ICAVP contractor has completed its review of the selected systems, including the corrective actions for issues previously identified by the licensee or its other contractors, and

the corrective actions for issues identified by the ICAVP oversight staff.

The staff will interface closely with the Millstone Restart Panel during this

! phase to ensure each deficiency has been appropriately resolved. To complete this task the NRC's ICAVP oversight staff will perform the following:

! a. Review the licensee's design-related corrective actions for tha cycter

within the scope of the ICAVP Tier 1 review to assure that

1 (1) The root cause(s) of and causal factors associated with the' j issue have been identified.

(2) The specific deficiency has been resolved.

< (3) The applicability of the deficiency to other systems, and I programmatic and operational aspects not reviewed by the ICAVP j contractor has been addressed.

l (4) The corrective actions have been adequately documented.

i (5) Those corrective actions required to be implemented prior to restart have been completed, and that those not completed are p ad uately justified and acceptable to the ICAVP oversight sta f.

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b. Ensure the results of the ICAVP, including all observations, findings, and recomendations made by the ICAVP contractor, and open items established by either the ICAVP contractor or the NRC staff, have appropriately been addressed by the licensee's corrective actions and that those corrective actions have been completed.

c. Review the comments from the ICAVP contractor submitted to the NRC as required by the order regarding the corrective actions proposed by the licensee to resolve or address the ICAVP contractor's findings and recomendations. Verify that the licensee has considered the ICAVP findings and recommendations in the development of its corrective actions,

d. Evaluate the overall results and conclusions of the ICAVP contractor to detemine whether the licensee's configuration management corrective action programs were effective in:

(1) Providing the licensee with a clear understanding of the licensing and design bases of the subject unit.

(2) Providing confidence that the configuration of the unit under review is in accordance with the updated FSAR NRC regulations, and other commitments.

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l (3) Providing confidence that the licensee's configuration '

management rograms. if prope ly implemented, will maintain the I subject Mil stone unit's comp 1ance with its licensing basis. g; V. ICAVP OVERSIGHT TEAM COMPOSITION  :

i The NRC ICAVP Oversight Team will include the following:

Deputy Director. ICAVP Oversight . . . . . . . . . . . . E. Imbro. NRR/SP0 Branch Chief. ICAVP Oversight . . . . . . . . . . . . . L. P11sco. NRR/SP0 Operations Inspectors ................ J. Nakoski, NRR/SP0 A. Gody RIV/DRP Mechanical Systems Inspectors ................ (2 minimum)

Electrical Power Systems Inspectors ............. (2 minimum)

Instrumentation & Control .................. (2 minimum)

Piping / Structural ...................... (2 minimum) s VI. DELEGATION OF RESPONSIBILITIES ulation has delegated to the The SeniorDirector of Service Executive the Office (SES) of Manager Nuclear responsib Reactor Re$e for the staff oversight of the Millstone ICAVP. the authority to approve changes to the initial ICAVP h,

audit plan, within the scope of the August 14, 1996, confirmatory order, and to modify this inspection plan as necessary to ensure adequate oversight of the licensee *s ICAVP audit plan. Changes to the ICAVP audit plan proposed by the licensee that are in conflict with the confirmatory order shall be ,

approved by the Director of NRR.

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v Docket No. 50-336 B16256 i

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j Attachment 1 i

Millstone Nuclear Power Station, Unit No. 2 Independent Corrective Action Verification Program (ICAVP)

Enclosure 2 August 14,1996 Confirmatory Order Establishing the Independent Corrective Action Verification Program For Millstone Nuclear Power Station Units 1,2, and 3 O reerverv1997

. pa nt y & UNITED STATES

,ig

( j NUCLEAR REGULATORY COMMISSION

(-) e $ WASHINGTON, D.C. 30866 4 001

***** August 14, 1996 i

Mr. Ted C. Feigenbaum Executive Vice President and Chief Nuclear Officer Northeast Nuclear Energy Company c/o Mr. Terry L. Harpster *

Director - Nuclear Licensing Services l'.0. Box 128

Waterford, CT 06385

SUBJECT:

CONFIRMATORY ORDER ESTABLISHING INDEPENDENT CORRECTIVE ACTION VERIFICATION PROGRAM (EFFECTIVE IMMEDIATELY) - MILLSTONE NUCLEAR POWER STATION, UNITS 1, 2 AND 3

Dear Mr. Feigenbaum:

On August 12, 1996, the Nuclear Regulatory Commission (NRC) staff met with the staff of Northeast Nuclear Energy Company (NNECO) regarding programmatic weaknesses in design and configuration control at Millstone Nuclear Power

' p Station, Units 1, 2, and 3. The NRC staff noted that NRC inspections and V NNECO internal audits since 1991, have identified numerous configuration (design) control failures, failures to implement corrective actions for known problems, failures to implement quality assurance requirements and failures to comply with the terms and conditions of the operating licenses for all th e Millstone plants. The NRC staff also noted that there have been indicatio of weaknesses in the NRC's oversight of the operation of the Millstone plan .

Accordingly, the NRC staff stated the need for an independent review to verify the adequacy of NNECO's efforts to establish adequate design bases and design controls, including translation of the design bases into operating procedures and maintenance and testing practices, verification of system performance, and

implementation of modifications since issuance of the initial facility operating licenses.

By letter dated August 13, 1996, NNECO submitt .1 its plan and commitments for such an independent review. NNECO's commitments included details regarding the scope of the independent review team's effort as described in the enclosed Order. Based on the magnitude of the failures at the Millstone units noted above, the NRC believes that NNECO's commitments must be confirmed by Order.

Therefore, the NRC is herewith issuing the enclosed Confirmatory Order Establishing Independent Corrective Action Verification Program (Effective

Immediately). This Order states that the selection of the members of the Independent Corrective Action Verification Program (ICAVP) team and the team's plan for conduct of its reviews will be subject to NRC staff approval. In

, evaluating the independence of each team member, factors the NRC staff will m

Mr. Ted C. Feigenbaum O O

consider will include, but not be limited to, whether the individual has prior

! involvement in design reviews for the licensee and whether the individual has any financial interest in Northeast Utilities. The Order also confirms the

, licensee's commitments regarding the scope of the ICAVP review.

i In its letter of August 13, 1996, NNECO agreed that it would not take any Millstone unit critical until the Commission approves restart of the unit. As 4

the staff noted during the meeting on August 12, 1996, the staff will follow the process outlined in the NRC's Inspection Manual Chapter 0350 to evaluate

' the licensee's actions directed toward resolving issues prior to restart of each unit. Conditions and/or actions the Commission may require of NNECO for j restart will be the subject of future correspondence.

I Please contact me if you have any questions or require further information on

this matter.

Sincerely, 3 MD William T. Russell, Director Office of Nuclear Reactor Regulation

! Docket Nos. 50-245, 50-336 l and 50-423

Enclosure:

Order j cc w/ encl: See next page i

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T. Feigenbaum Millstone Power Station, Northeast Utilities Service Company Unit Nos. 1, 2 & 3 ny . p, 3 wl. .

cc: c0 d Mr. P. D. Swetland, ResidentICA Lillian M. Cuoco, Esq. Inspector Senior Nuclear Counsel n ....

Millstone Nuclear Power Staf}'on.,..,h. '

Northeast Utilities Service Company c/o U.S. Nuclear Regulatory

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P.O. Box 270 Commission j Hartford, CT 06141-0270 P.O. Box 513

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Niantic, CT 06357  ; ],.

C' Mr. D. B. Miller, Jr.

Mr. Kevin T. A. McCarthy, Director Senior.Vice President Monitoring and Radiation Division h Nuclear Safety and Oversight e furt-Department of Environmental Northeast Utilities Service Company Protection P.O. Box 270 79 Elm Street Waterford, CT 06141-0270 Hartford, CT 06106-5127 Mr. E. A. DeBarba Mr. Allan Johanson, Assistant Vice President - Nuclear Tedhnical Director Services Office of Policy and Management NortheastUtilitiesServiceCo$Nng,l. .

Policy Development and Planning P.O. Box 128 Division Waterford, CT 06385 O 80 Washington Street Hartford, CT 06106 Mr. F. C. Rothen Vice President - Nuclear Work Services Mr. S. E. Scace, Vice President Northeast Utilities Service Company Nuclear Reengineering Implementation P.O. Box 128 Northeast Utilities Service Company Waterford, CT 06385 P.O. Box 128 Waterford, CT 06385 P. M. Richardson, Nuclear Unit Director ,

Millstone Unit No. 2 Mr. W. J. Riffer Northeast Nuclear Energy Company Nuclear Unit Director P.O. Box 128 Millstone Unit No. 1 Waterford, CT 06385 Northeast Nuclear Energy Company P.O. Box 128 Charles Brinkman, Manager Waterford, CT 06385 Washington Nuclear Operations ABB Combustion Engineering Regional Administrator 12300 Twinbrook Pkwy, Suite 330 Region I Rockville, MD 20852 U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 First Selectmen Town of Waterford Hall of Records -

200 Boston Post Road O Waterford, CT 06385 4

-. . - - - - - - . . - - . - _ _ _ _ - - _ - _ _ - . _ _ - . . = - . - . - . - - - _ . _ -

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. M. H. Brothers, Nuclear Unit Director

, Millstone Unit No. 3 Northeast Nuclear Energy Company

! k P.O. Box 128 Waterford, CT 06385 i

Burlington Electric Department c/o Robert E. Fletcher, Esq.

4 271 south Union Street 4

Burlington, VT 05402

. Mr. M. R. Scully, Executive Director

Connecticut Municipal Electric '

i Energy Cooperative ,

1 30 Stott Avenue

Norwich, CT 06360 Mr. William D. Meinert

Nuclear Engineer j Massachusetts Municipal Wholesale Electric Company i P.O. Box 426 i Ludlow, MA 01056 2 Ernest C. Hadley, Esq.

1040 B Main Street 1 P.O. Box 549 l

West Wareham, MA 02576 Mr. John Buckingham Department of Public Utility Control Electric Unit 10 Liberty Square New Britain, CT 06051 O

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UNITED STATES NUCLEAR REGULATORY COMMISSION In the Matter of )  !

) Docket Nos. 50-245, 50-336, l

) and 50-423 i NORTHEAST NUCLEAR ENERGY ) License Nos. DPR-21, DPR-65, i COMPANY ) and NPF-49 I

)

(Millstone Nuclear Power Station )

Units 1, 2, and 3) )

' CONFIRMATORY ORDER ESTABLISHING INDEPENDENT CORRECTIVE ACTION VERIFICATION PROGRAM (EFFECTIVE IMMEDIATELY)

I  !

Northeast Nuclear Energy Company (Licensee) is the holder of Facility I i

4 Operating License Nos. DPR-21, DPR-65, and NPF-49 issued by the Nuclear Regulatory Commission (NRC or Commission) pursuant to Title 10 of the Code of j federal Regulatfons (10 CFR) Part 50 on October 31, 1986,' September 26, i 1975, and January 31, 1986 respectively. The licenses authorize the operation I of Millstone Units 1, 2 and 3 in accordance with conditions specified therein. i 4

All three facilities are located on the Licensee's site in Waterford,'

Connecticut.

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On August 21, 1995, as supplemented August 28, 1995, the NRC received a I petition under 10 CFR 2.206 which requested that NRC shut down Millstone Unit

' Millstone Unit I was issued its provisional operating license on October 7, 1970 and commenced operation on March 1, 1971. This unit received O. a full term operating license on October 31, 1986.

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I and take enforcement action based upon alleged violations of NRC i requirements related to operation of the spent fuel pool cooling systems and I refu.eling practices. On November 4,1995, the Licensee shut down Millstone l Unit I for a planned 50-day refueling outage. During the fall of 1995, an NRC

investigation of licensed activities at Millstone Unit 1 identified potential f violations regarding refueling practices and the operation of the spent fuel l pool cooling systems of Millstone Unit 1. On December 13, 1995, the NRC d

i issued a letter to the Licensee requiring that it inform the NRC, pursuant to i

{ Section 182a of the Atomic Energy Act of 1954, as amended, and 10 CFR i

l 50.54(f), with regard to Millstone Unit 1, of the actions it would be taking l to ensure that future operation of that facility would be conducted in f accordance with the terms and conditions of the plant's operating license, the Commission's regulations, including 10 CFR 50.59, and the plant's Updated l Final Safety Analysis Report (UFSAR).

On February 20, 1996, the Licensee shut down Millstone Unit 2 when both l trains of the high pressure safety injection (HPSI) system were declared inoperable due to the potential to clog the HPSI discharge throttle valves during the recirculation phase following a loss-of-coolant accident (LOCA). l On February 22, 1996, the Licensee issued Adverse Condition Report (ACR) 7007 )

- Event Response Team Report, which describes in detail the underlying causes for numerous inaccuracies contained in Millstone Unit l's UFSAR. Those causes, as determined by the Licensee, include the following: 1) errors and omissions in the original 1986/87 UFSAR; 2) failure of the administrative control programs to address fully NRC requirements; 3) failure of the Licenst i to implement fully those administrative programs; 4) a pattern of failure of ,

Licensee management to correct identified weaknesses and risks associated with l

1

j n the UFSAR and design bases; and 5) failure of Licensee oversight to identify this pattern to management, the significance of the pattern itself, or the ineffectiveness of corrective actions to prevent its recurrence. The report acknowledged that, due to the nature of these identified causes, the potential existed for the presence of similar configuration management problems at Connecticut Yankee and Millstone Units2' and 3.

In response to the Licensee's ACR 7007 and the NRC's own ongoing inspections, evaluations and investigations, on March 7, 1996, the NRC issued a letter to the Licensee requiring that it inform the NRC, pursuant to Section 182a of the Atomic Energy Act of 1954, as amended, and 10 CFR 50.54(f), with 4

regard to Millstone Unit 2, of the actions it would be taking to ensure that future operation of that facility would be conducted in accordance with the terms and conditions of the plant's operating license, the Commission's regulations, including 10 CFR 50.59, and the plant's UFSAR. The letter stated that this information was to be submitted no later than 7 days prior to the Unit's restart (prior to criticality) from its current outage. The Millstone  !

Unit 2 letter also described findings the NRC had made in recent inspections of that facility which suggested that significant operability and design concerns remained, including the HPSI issue identified above, as well as inadequate containment sump screen mesh and a flawed post-accident containment hydrogen monitor design.

On March'7, 1996, the NRC also issued a 50.54(f) letter to the Licensee regarding the Millstone Unit 3 plant, which was then operating at full power.

In that letter, the NRC noted that it did not have an inspection history at Millstone Unit 3 that revealed design deficiencies similar in number and nature to that of Millstone Units 1 and 2. Nonetheless, the NRC concluded

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O that it required additional information, within 30 days of the date of the letter, including the Licensee's plans and actions to address the implications of ACR 7007 for Millstone Unit 3, as well as the Licensee's plans and schedules to ensure that future operation of the unit would be conducted in i

accordance with the Commission's regulations, the terms and conditions of the  !

operating license, and the facility UFSAR.

Following the March 7 letter, the NRC conducted a special inspection at Millstone Unit 3 that identified design and other deficiencies similar to those reported in ACR 7007 and by the NRC at the other Millstone units. On i

March 30, 1996, Unit 3 was shut down after it was determined that containment isolation valves for the auxiliary feedwater (AFW) turbine-driven pump were inoperable due to the valves' noncompliance with NRC requirements. Shortly thereafter, while still shut down, the Licensee discovered that the facility had been operating in a condition outside its design basis due to the .

Licensee's failure to adequately address design temperature conditions in the stress calculations for the Containment Recirculation Spray System (RSS)

]

piping and supports. Both of these deficiencies had existed for over ten years, since initial operation of the facility. All three Millstone Units remain shut down.

On April 4, 1996, the NRC issued a second letter to the Licensee, pursuant to 10 CFR 50.54(f), with regard to Millstone Unit 3, similar to those issued for Millstone Units 1 and 2. The letter described programmatic issues and design deficiencies identified during the NRC's ongoing special inspection of the plant that were similar in nature to those present at Millstone Units 1 and 2. These included the inoperability of the turbine-driven AFW pump during startup and shutdown, the failure to remove plastic shipping plugs from

.. *i 6 Rosemount transmitters, the failure to correct a degraded non-safety battery, I 4

inadequate control of the modification of the service water system, and the potential for introduction of foreign material into the containment sump. In addition, the letter noted Licensee-identified design deficiencies in the AFW containment isolation valves and RSS that had existed for more than 10 years.

As in the case of the Millstone Unit 1 and 2 letters, as described above, the Licensee was required to provide the NRC, no later than 7 days prior to the Unit's restart, with information necessary to assure the NRC that the plant will be operated in conformance with the terms and conditions of the plant's operating license, the Commission's regulations, including 10 CFR 50.59, and the plant's UFSAR.

On May 21, 1996, pursuant to 10 CFR 50.54(f), the NRC issued a letter to the Licensee requiring specific information regarding design and configuration l deficiencies identified at each of the Millstone units as well as a detailed description of the Licensee's plans for completion of the work required to respond to the NRC's letters of December 13, 1995, March 7, 1996, and April 4,

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1996. The NRC required this information to be submitted within 30 days of the date of the letter for the first unit that the Licensee proposed to restart and not later than 60 days prior to the Licensee's proposed restart for the remaining Millstone units. '

Based upon the Licensee's assessment of the extent and scope of identified design control problems at Millstone Station, the Licensee decided to focus its near-term efforts on restart of Millstone Unit 3. In a letter dated June 20, 1996, the Licensee responded to the NRC's May 21, 1996, letter and informed NRC that Millstone Unit 3 would be the first Millstone unit the Licensee proposed to restart. In Attachment I to its June 20 response, the O

. Licensee listed 881 design and configuration deficiencies identified since issuance of ACR 7007 and entered into the Licensee's Deficiency Review Team Report database as of June 13, 1996. The Licensee designated 378 items to be corrected prior to restart of Millstone Unit 3. The Licensee determined that the items it had designated for correction prior to restart, if not corrected, could impact upon operability of required equipment, raise unreviewed safety questions, or indicate discrepancies between the plant's UFSAR and the as-built plant or operating procedures.

In the June 20 letter, the Licensee also described its own Configuration Management Plan (CMP), intended to provide reasonable assurance that the future operation of Millstone Units 1, 2, and 3 will be conducted in accordance with the terms and conditions of their applicable operating licenses, UFSARs and NRC regulations. The CMP includes efforts to understand licensing and design basis issues which led to issuance of the 50.54(f) letters and actions to prevent those issues' recurrence. Additionally, the Licensee described its CMP objective to clearly document and meet the units' licensing and design basis requirements, and its intention to ensure that adequate programs and processes exist to maintain control of licensing and design basis requirements.

On July 2,1996, the Licensee supplemented its June 20, 1996 response to NRC's May 21, 1996 50.54(f) letter. The Licensee provided additional information on Millstone Unit 3 deficiencies previously reported, identified revisions to its plans and committed to complete a review to identify and correct, as necessary, Millstone Unit 3 UFSAR deficiencies prior to restart.

The Licensee reported a substantial increase in the total number of identified design and configuration management discrepancies (1187 items), and an

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increase in those proposed by the Licensee for corrective action prior to restart (597 items).

. As the Licensee's own submissions and NRC inspections indicate, significant design control deficiencies and degraded and non-conforming conditions have been identified at Millstone Units 1, 2 and 3. The staff has identified three major types of design control problems which exist at all three Millstone plants. Specific examples of deficiencies at each plant in each of the categories are provided below.

1. Errors in Licensino/Desian Basis Documentation The NRC identified errors in the UFSARs for Millstone Units 1, 2, and 3. For example, at Millstone Unit 3, the protective relay settings and calculations for 4kv safety-related motor feeders were not set consistent with the UFSAR. At Millstone Unit 2, the 1

( UFSAR indicated that certain non-essential loads of the reacter i s building closed cooling water (RBCCW) system inside containment were automatically isolated during a sump recirculation actuation signal when in fact the associated isolation valves received no automatic isolation signal. Additionally, the RBCCW flow rates assumed in the accident analyses were non-conservative with  !

respect to the actual system flow rates. l In addition, the NRC found instances of modifications that were completed without implementing required revisions to the UFSAR.

For example, the Licensee revised the Millstone Unit 3 Technical Specifications (TS) in January 1995 to change the testing frequency of the auxiliary feed pumps from monthly to quarterly, but did not update the UFSAR to reflect the change.

At Unit 1, the Licensee failed to perform and document a safety evaluation for an electrical separation deficiency associated with a feedwater regulating valve interlock. This deficiency was not corrected and constituted a change to the design of the facility as described in the UFSAR. Also, the Licensee's assessment of the need for upgrades to the intake structure ventilation system was inadequate. Specifically, insufficient heat removal capability existed under several postulated scenarios.

At Unit 2, the NRC found that the UFSAR had not been updated to reflect that the intake structure design temperature could not be met following a loss of non-vital exhaust fans.

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1 Furthermore, while the Millstone Unit 3 UFSAR documented that the design bases for the containment heat removal systems had been

established in accordance with specific general design and code

! criteria, portions of these systems were found to violate certain

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analytical stress considerations. Specifically, the recirculation i spray system (RSS) pipe supports inside containment were not i

designed to withstand a single failure of a supporting service water train. Also, both the RSS and quench spray systems were

found to contain pipe supports for which ASME Code stress

! allowables would se exceeded during design basis accident

, temperature conditions within the Unit 3 containment building.

2. Failure to Translate Desian Bases to Procedures and Hardware i

The NRC found instances where the Licensee did not adequately

translate design basis information into procedures, practices, i hardware and drawings. For example, at Millstone Unit 1, the

! reactor pressure assumed as an initial condition in the accident i analyses was exceeded during reactor power operation. At Unit 3, l a modification that installed the service water intake structure i

sump pump called for specific periodic testing, but such testing was never performed. In another case at Unit 3, prelubrication of the AFW pump was not performed every 40 days as required by the vendor.

As noted in the NRC's letter of December 13, 1995, at Millstone Unit 1, the Licensee's core offload practices were not consistent with the Unit's UFSAR. Specifically the heat load assumptions were not maintained as a result of full core offloads performed sooner than the required delay time after reactor shutdown.

Also at Unit 1, measures established to ensure that the design bases were satisfied for control room habitability were not adequate in that the means for maintaining viable self-contained breathing apparatus capability for each person in the control room were not translated into procedures. In addition, the Licensee failed to translate the design bases for the Unit I standby gas treatment system (SGTS) into design specifications, and failed to perform comprehensive pre-operational testing of the SGTS to ensure that it met its design specifications.

At Millstone Unit 2, the Licensee failed to adequately update the surveillance requirements to reflect modifications to contact positions in the anticipated transient without scram (ATWS) mitigating system actuating circuitry. Also at Unit 2, the procedure requirements for the time of initiation of hydrogen monitoring following a LOCA were not consistent with the licensing and design bases.

In addition, there were a number of instances where the original O design basis was inadequate or the original installation was

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} incorrect. For example, at Units 2 and 3, the Licensee failed to l remove plastic shipping plugs from Rosemount transmitters prior to j installation, notwithstanding the vendor's instructions which  !

required those plugs' replacement with stainless steel plugs. At '

, Unit 2, the NRC found that nuclear instrumentation and post-LOCA

, hydrogen monitors were not single-failure proof.

! At Millstone Unit 2, the Licensee's inspection of the containment

! sump screen mesh revealed that debris larger than the size i specified in the design basis could pass through with potential

{ adverse consequences to the operability of the emergency core

! cooling systems. The NRC also identified that the post-accident

containment hydrogen monitor design at Millstone Unit 2 was flawed

! in that insufficient sample flow would be available at low

containment pressures when the monitor must be operable.

Also at Unit 2, when it was found that postulated failures of the non-vital intake structure ventilation systems could cause the j intake structure ambient temperature to exceed the design basis, j the Licensee did not perform appropriate evaluations relative to i the design basis before concluding that no modifications to i equipment or the design basis were needed.

3. Inadeaunte Enaineerina and Modifications

! The NRC identified a number of instances in which a modification 1 l was not installed in accordance with the design, a modification i was inadequate, or a modification was based on incorrect design  ;

l assumptions. In one example at Millstone Unit 1, the Licensee

failed to maintain the design bases for the loss of normal power j (LNP) logic. Specifically, a modification resulted in a single i

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failure vulnerability of the LNP logic that would have prevented both smergency power sources from properly starting and sequencing  !

. the rega..cd loads. The Licensee also revised the Unit 1 maximum

spent fuel pool temperature through an amendment to the Technical 4 i Specifications but failed to evaluate the impact of the change on i the SGTS.

At Millstone Unit 2, both trains of service water were rendered inoperable when the strainer backwash line froze due to an ,

! undocumented modification that extended the backwash line through l an opening under the wall to a point just outside the intake

structure.

e i Also at Millstone Unit 2, the NRC identified that both trains of 1 the post-accident sampling system have been inoperable since the steam generator replacement modification because higher containment pressures would have delayed taking a containment sample for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. -

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!  : AtMillstoneUnit3,theLicenseepreparedamodificationpacka$efor the high j relied on incorrect design assumptions because a previous  !

modification had revised the design. In addition, the Licensee i , had no approved calculation to demonstrate the adequacy of the i station blackout diesel generator battery at Millstone Unit 3.

! Although the Licensee's own programs, such as the CMP, are intended to 1 correct existing and prevent future def'iciencies at the facilities, I have

concluded that these programs by themselves are not sufficient, given the l Licensee's history of poor performance in ensuring complete implementation of 1

i corrective action for both known degraded and non-conforming conditions and )

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past violations of NRC requirements. In addition, the magnitude and scope of j i

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the design and configuration deficiencies currently being identified indicate l multiple significant failures to comply with NRC regulations (e.g., 50.59, 50.71(e),etc.) The Licensee's history of poor performance, coupled with the l

! magnitude and scope of its failure to maintain and control conformance of i i Millstone Units 1, 2, and 3 to their design bases, require resolution prior to plant restarts.

The extent and duration of the deficiencies identified also indicate in3ffective implementation of the Licensee's oversight programs, including the NRC-approved quality assurance (QA) program. EMactive oversight activities I should have identified and led to corrective measures for design control .

deficiencies. One conclusion of ACR 7007 was that the Licensee's oversight I organizations (Review Boards, Quality Assessment Section (QAS), Independent 1 Safety Engineering Group, and Operating Experience) did not identify the pattern of Millstone Unit 1 UFSAR discrepancies to management; nor did they I identify the significance of the pattern, or the effectiveness of corrective actions to prevent recurrence. In a July 2,1596 letter to the NRC, the O

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/] Licensee provided the preliminary findings of an independent Root Cause Evaluation Team chartered to determine the causes for these oversight fail.ures. The team found that there was no history of escalating issues effectively and that QAS operated in an environment that did not lend itself to resolution of QAS-identified problems. Such findings of program weaknesses that represent poor oversight functions are not recent. It is apparent that the Licensee was aware of significant weaknesses in its oversight functions as early as 1991 and took no effective actions to correct those weaknesses. The Licensee's Performance Task Group Final Report, issued in September 1991, and Procedure Compliance Task Force Final Report, issued in October 1991, identified significant programmatic weaknesses affecting configuration management that either went unnoticed or were not corrected by the Lict;nsee Q oversight functions.

C/ It is necessary to ensure that the Licensee's programs to correct design control failures at Millstone Units 1, 2 and 3 are effective and that identification of degraded and ncn-conforming conditions and implementation of corrective actions are satisfactory and can effectively preclude repetition of these failures. For this reason, the NRC requires an independent verification of the adequacy of the results of the programs currently being implemented by the Licensee which are directed at resolving existing design and configuration management deficiencies. Accordingly, the Commission in this Order directs the Licensee to obtain the services of an organization, independent of the Licensee and its design contractors, to conduct a multi-disciplinary review of Millstone Units 1, 2, and 3. The review is to provide independent verification that, for the selected systems, the Licensee's CMP has identified and resolved existing problams, documented and utilized licensing and design

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bases, and established programs, processes and procedures for effective i

configuration management in the future. This review must be comprehensive, incorporating appropriate engineering disciplines, such that the NRC can be confident that the Licensee has been thorough in identification and resolution of problems.

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! III On August 12, 1996, a transcribed meeting was conducted between the l

Licensee and the NRC staff regarding this matter. In response to the staff's ,

concerns, the Licensee subsequently submitted a letter dated August 13, 1996, i 1

! in which it agreed and committed to take a number of actions with respect to Millstone Units 1, 2, and 3. Specifically, the Licensee committed to have an independent team conduct an Independent Corrective Action Verification Program

. (ICAVP) at Millstone Units 1, 2, and 3. The Licensee committed that the corrective action verification program will include: (1) conduct of an in-depth review of selected systems which will address control of the design and t 4 design basis since issuance of the operating license for each unit; (2) l 7

selection of systems for review based on risk / safety based criteria similar to j those used in implementing the Maintenance Rule (10 CFR 50.65); (3) t l development and documentation of an audit plan that will provide assurance l 4

that the quality of results of the Licensee's problem identification and corrective action programs on the selected systems is representative of and consistent with that of other systems; (4) procedures and schedules for parallel reporting of findings and recommendations by the ICAVP team to both the NRC and the Licensee; and (5) procedures for the ICAVP team to comment on

O,-5 the Licensee's proposed resolution of the findings and recommendations. The Licensee also committed to the scope of the ICAVP review, encompassing modifications to the selected systems since initial licensing, including: (1) a review of engineering design and configuration control processes; (2) verification of current, as-modified plant conditions against design basis and licensing basis documentation; (3) verification that design and licensing bases requirements are translated into operating procedures, and maintenance and test procedures; (4) verification of system performance through review of

specific test records and/or observation of selected testing of particular f systems; and (5) review of proposed and implemented corrective actions for l Licensee-identified design deficiencies.

I find that the Licensee's agreements and commitments as set forth in i

its letter of August 13, 1996 are acceptable and necessary.

V In view of the foregoing, I have determined that public health and safety require that the Licensee's agreements and commitments in its August 13, 1996 letter be confirmed by this Order. The Licensee has agreed to this action. Pursuant to 10 CFR 2.202, I have also determined, based on the significance of the matters described above, as well as on the Licensee's consent, that the public health and safety require that this Order be immediately effective.

IV Accordingly, pursuant to Sections 103, 104, 161b, 1611, 161o, 182 and 186 of the Atomic Energy Act of 1954, as amended, and the Commission's regulations in 10 CFR 2.202 and 10 CFR Part 50, IT IS HEREBY ORDERED,

(~ EFFECTIVE IMMEDIATELY, THAT:

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1. The Licensee shall implement an Independent Corrective Action Verification Program (ICAVP) for each Millstone Unit to confirm that the plant's physical and functional characteristics are in conformance with its

licensing and design bases. The ICAVP review shall begin after the Licensee has completed the problem identification phase of the CMP, including the

activities of the QA organization. The ICAVP shall be performed and completed

] for each Unit, to the satisfaction of the NRC, prior to the Unit's restart. l f ,

2. The ICAVP is to be conducted by an independent verification team I whose selection must be approved by the NRC. The ICAVP team shall provide j input on its findings on an ongoing basis concurrently to both the Licensee and the NRC. The ICAVP team shall also periodically provide to the NRC its comments on the Licensee's proposed resolution of the team's findings and

! recommendations.

3. The ICAVP team shall provide for NRC review and approval, prior to j implementation, a plan for the conduct of the team's review. The plan must j describe (a) the conduct of an in-depth review of selected systems' design and design bases since issuance of the facilities' operating licenses; (b) risk / safety based criteria for selection of systems for review; (c) a

[ description of the audit plan to provide assurance that the quality of results I of the Licensee's problem identification and corrective action programs on the j selected systems is representative of and consistent with that of other systems; (d) procedures and schedules for parallel reporting of findings of i the ICAVP team to both the NRC and the Licensee; and (e) procedures for the ICAVP team to comment on the Licensee's proposed resolution of the team's findings and recommendations. The scope of the ICAVP effort shall encompass all modifications made to the selected systems since initial licensing, and 1 O 4

+. ...  ;

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i j shall include: (1) . review of engineering design and configuration control

processes, (2) verification of current, as-modified conditions against design and Jicensing basis documentation, (3) verification that the design and j licensing bases requirements have been translated into operating procedures,

! and maintenance and test procedures, (4) verification of system performance through review of specific test records'and/or observation of selected testing, and (5) review of proposed and implemented corrective actions for 1

licensee-identified design deficiencies.

4. The Licensee shall provide written replies to.the Regional Administrator, Region I and the Director, Office of Nuclear Reactor i Regulation, addressing ICAVP team findings and recommendations discussed in I

.; reports made pursuant to item 3(d) above. The Licensee's written replies to ICAVP team findings and recommendations shall include a statement of agreement jO or disagreement with reasons for each ICAVP finding or recommendation, and of i the status of implementation of corrective actions. Subsequent written

) replies shall be made until all corrective actions are implemented.

The Director, Office of Nuclear Reactor Regulation, may, in writing, 1

i relax or rescind this order upon demonstration by the Licensee of good cause.

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The Licensee has, as described above, consented to the issuance of this j Order and waived its right to request a hearing. Thus, any person adversely affected by this Order, other than the Licensee, may request a hearing within i 20 days of its issuance. Where good cause is shown, consideration will be given to extending the time to request a hearing. A request for extension of l

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time must be made in writing to the Director, Office of Enforcement, U.S.

Nuclear Regulatory Commission, Washington, D.C. 20555, and include a statement of good cause for the extension. Any request for a hearing shall be submitted to the Secretary, U.S. Nuclear Regulatory Commission, ATTN: Chief, Docketing and Service Section, Washington, D.C. 20555. Copies of the hearing request shall also be sent to the Director, Off' ice of Enforcement, U.S. Nuclear

] Regulatory Commission, Washington, D.C. 20555, to the Assistant General 1

Counsel for Hearings and Enforcement at the same address, to the Regional l

}

Administrator, NRC Region I, 475 Allendale Road, King of Prussia, PA 19406-I 1415, and to the Licensee. If such a person requests a hearing, that person i

l shall set forth with particularity the manner in which his interest is l adversely affected by this Order and shall address the criteria set forth in i

10 CFR 2.714(d).

}

If a hearing is requested by a person whose interest is adversely affected, the Commission will issue an Order designating the time and place of any hearings. If a hearing is held, the issue to be considered at such j hearing shall be whether this Confirmatory Order should be sustained.

l In the absence of any request for hearing, or written approval of an

extension of time in which to request a hearing, the provisions specified in Section IV above shall be final 20 days from the date of this Order without further order or proceedings. If an extension of time for requesting a hearing has been approved, the provisions specified in Section IV shall be i

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final when the extension expires if a hearing request has not been received. .

AN ANSWER OR A REQUEST FOR HEARING SHALL NOT STAY THE IMMEDIATE EFFECTIVENESS

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1 0F THIS ORDER.

FOR THE NUCLEAR REGULATORY COMMISSION B

I William T. Russell, Director

' Office of Nuclear Reactor Regulation j Dated at Rockville, Maryland this 14th day of August, 1996 3

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I Docket No. 50-336 -

O 816256 l

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Millstone Nuclear Power Station, Unit No. 2 l Independent Corrective Action Verification Program (ICAVP) I i Millstone Unit No. 2 Response to information Requested by the NRC Staff Concerning the Selection of the ICAVP Contractor -

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U. S.' Nucl cr R:gulatory Commission I B16256/ Attachment 2/Page 1  ;

O miiistone Nuciear Power Station - unit No. 2  !

j independent Corrective Action Verification Program (ICAVP) l 4

Millstone Unit No. 2 Response to information Reauested by the NRC Staff i Concernina the Selection of the ICAVP Contractor I I

1. How was the financial and organizational independence of Parsons Power from NU and NU's design contractors verified? What criteria were used to establish j

independence and what information was reviewed?

j Corooration The NRC stated that the selected ICAVP Contractor shall have:

. . No financial involvement with NU, and

. No current involvement at the Unit being reviewed.

i' The Parsons Power Group President has provided a letter affirming independence.

Parsons has also required each of its subcontractors to provide a letter affirming their l independence.

4 O in their proposal, Parsons indicated that they own and control no stock, nor have any U other financial interest in Northeast Utilities or its subsidiaries. A check of NU records i 1 has confirmed this statement.  !

l Further, Parsons is doing no current work at Millstone Unit 2, nor at any other Millstone Unit.

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The magnitude of work at NU over the years is a small fraction of the revenues that  !

they have received from other sources. Recognized in 1995 and 1996 by " Engineering News Record" as the largest design firm in the United States with total annual billings

of over $927 million ($100 million power related), Parsons' financial success will not be

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dependent on the value of the ICAVP project. A listing of the work done by Parsons for NU is enclosed. Note that most of the Parsons work for NU over the past decade was j in support of the NU Fossil / Hydro, and Transmission and Distribution (T&D) groups.

i Parsons has earned a reputation as a world class architect engineering firm. Parsons

! and their predecessors have designed 16 nuclear power plants. They will not risk their

! reputation to do anything inconsistent with the NRC's Order.

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U. S. Nucl:ar Regulatory Commission B16256/Attachm:nt 2/Page 2

] Team The NRC also stated in its Confirmatory Order, that the team members of the ICAVP Organization shall have:

. No financial involvement with NU, and

. No prior involvement at the Unit being reviewed. )

To assure independence as required, NU reviewed each resume of the members of the team proposed, and determined that no individual proposed has any past experience at Millstone in design or licensing basis work. In one case, an individual performed inspection work at Millstone Unit 1, but the work is not in conflict with activities to be performed on the ICAVP for Unit 2.

l Further, Parsons has established a Conflict of Interest form that each team member must sign, indicating independence from NU, Bechtel (the Architect Engineer for Millstone Unit 2), and ABB/ Combustion Engineering, the Nuclear Steam System Supplier (NSSS) for Millstone Unit 2.

2. What are the details of the previous work performed by Parsons at Millstone Unit n 2? How will the program audit plan compensate for those specific technical

() areas where Parsons has performed previous work?

Enclosed is the listing of work previously performed by Parsons and their predecessors. The Parsons Project Management Plan will preclude team members from reviewing work that they previously performed. If ICAVP review efforts require review of a prior Parsons project deliverable, the NRC and NNECO will be notified.

3. Will you restrict future work which Parsons Power may seek to perform?

NU's Contract for the ICAVP will include the following language:

"Notwithstanding any other provision of this contract, during the term of and for a period of twelve (12) months after completion of the Independent Corrective Action Verification Program at the Millstone site, Parsons will be precluded from performing work, at Millstone, on developing corrective actions which the NRC requires Northeast Utilities to perform as a direct result of the ICAVP program." As a result of our intended time table for resolving discrepancies, this restriction will effectively exclude Parsons from correcting deficiencies that they have identified, or that other ICAVP contractors have identified.

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U. S. Nucirr R:gul: tory Commission B16256/Attachm:nt 2/Page 3

4. What action will you take to address substitution of project team members should that become necessary?

Parsons will be required to provide a formal project instruction (procedure) to be approved by the NRC, that will govern the process for substituting and adding personnel to the ICAVP project team, when required. This project instruction will include wording such as the following:

. New personnel are required to have the technical background and experience to I perform the functions required of them in the ICAVP. These personnel will be accepted by the Parsons Project Director, and submitted to the NRC for review.

. That new or substitute personnel will also be required to meet the same independence criteria as the original team proposed.

It is recognized that team members may have to be replaced because of unforeseen circumstances. Further, since the NRC will pick the systems to be reviewed, the proper balance or mix of the team may have to change. For example, if the reviews are heavily weighted on electrical systems or equipment, more electrical engineers or designers may be required, while other disciplines reduced.

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5. What process is used at Parsons to handle Differing Professional Opinions (DPOs) among their staff?

. The most likely source of Differing Professional Opinions will be related to:

-- lCAVP scope limitations

-- the identification and wording of Discrepancy Reports

- acceptance of NU resolution of Discrepancy Reports

. The Parsons management team will be cognizant of the sensitivity of these issues and obtain complete input from team members before making decisions. DPOs can be escalated to the Parsons Power Group President and the QA Manager for resolution. They can bring additional technical resources to bear on an issue, if required. Also, Parsons personnel will be afforded access to the NU Employee Concerns Program, as will the Independent Oversight Team for Employee Concerns. Parsons will be required to provide a formal Project Instruction to be approved by the NRC that will govern the process for resolution of differing professional opinions (DPOs).

• Team members, of course, have the right to bring issues to the NRC if they believe

() it is necessary to do so.

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Attachment 2

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Millstone Nuclear Power Station, Unit No. 2 I Independent Corrective Action Verification Program (ICAVP) 4 3

Enclosure 1 i

Proposed ICAVP Contractor (Parsons Power)

.i Summary Of Work Performed At Northeast Utilities s I l

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i O February 1997

U. S. Nucic:r R gulatory Commission B16256/Attachm:nt 2/Enclosuro 1/Page 1 Millstone Nuclear Power Station - Unit No. 2 Independent Corrective Action Verification Program (ICAVP)

MILLSTONE UNIT 2 PROPOSED ICAVP CONTRACTOR (PARSONS POWER)

SUMMARY

OF WORK PERFORMED AT NORTHEAST UTILITIES Work Performed Durina or After 1986 (10 years)

For the 10 year period beginning in 1986, Parsons Power Group has performed approximately $5,008,000 worth of business with NU. These activities do not impact the NRC's definition of independence in the Confirmatory Order and none of the personnel engaged in the above work are proposed for the ICAVP. The Parsons Power Group is a combination / merger of Parsons Construction, C.T. Main, and Gilbert

/ Ccmmonwealth Associates. The following is a summary of these activities:

Work Performed As Parsons Power 1995 ($261,000) F/H** Conducted environmental and engineering studies in New Hampshire for the NU Fossil / Hydro Group.

This work involved the identification of creosote deposits and analysis of remediation options for the Winnipesaukee River in Laconia, NH in a cooperative effort with Energy North. This work does not involve Seabrook Station or any other NU nuclear facility.

Work Performed As Gilbert / Commonwealth 1994 ($2,000) NG* Material expediting services at the Sulzer Bingham Facility for the Connecticut Yankee plant.

1992 ($48,000) NG* Criteria for selection of small bore erosion / corrosion piping inspection and Independent Review of flow accelerated piping corrosion at Millstone Units 2 & 3.

(Subcontract to Altran Corporation).

1992 ($63,000) NG* Flow Chart Mapping of the Configuration Management processes at the Connecticut nuclear plants.

1992 ($38,000) NG* Flow Chart Mapping of High Energy Line Break evaluation processes for the Connecticut nuclear O gients.

U. S. Nucinar Reguletory Commission B16256/Attachm:nt 2/Enclosura 1/Paga 2 i l

1992 ($78,000) NG* Flow Chart Mapping of Motor Operated Valve -

processes for the Connecticut nuclear plants.

1990 ($162,000) NG* Provided a check s!alve maintenarice and review program for Millstone Units 1 and 2, and Connecticut Yankee. I 1989 ($264,000) F/H** Performed a Life Extension Study for the Norwalk Harbor Station, a fossil-fueled electricity generating station.

1984 ($69,000) NG* QA Services at Millstone Unit 1, Unit 2, Unit 3, and Connecticut Yankee under a five year contract.

Work Performed As Parsons Main 1993 ($41,000) F/H" Engineering services for a FERC Part 12 safety  ;

inspection at a hydro facility in Scotland, CT.  ;

1989 ($452,000) F/H** Engineering services for the closure of surface O impoundment's for the NU Fossil / Hydro Group.

1987 ($728,000) T& D *** Provided engineering and design work for the NU j Transmission and Distribution (T&D) group for a 115 l KV line not associated with Millstone or Connecticut

~

Yankee.

Work Performed As C.T. Main 1991 ($441,000) T& D*** Material procurement for reconstruction of a 115 KV Line for the NU Transmission and Distribution group.

1990 ($54,000) F/H** Provided Technical Services to the NU Fossil / Hydro group.

1989 ($717,000) T&D"* Provided engineering design and siting services required to rebuild two 115 KV lines for NU's Transmission and Distribution (T&D) group.

1989 ($109,000) F/H" Engineering services to prepare a five year FERC safety inspection and report for the Scotland, CT i hydro facility.

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U. S. Nuclecr R:gulatory Commission B16256/Attachm:nt 2/Enclosuro 1/Paga 3 4

l 1988 ($1,154,000) F/H" Provided engineering and design services for waste water treatment facilities and equalizing basins for the Fossil Hydro Group's Devon, Middletown, and

Montville stations.

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1987 ($296,000) F/H" Design services for Equalization Basins at the j Fossil / Hydro groups Norwalk Harbor ststion.

1 1986 ($31,000) F/H" Engineering analysis and cost estimate for a i

combined cycle dual energy facility for NU's Fossil / Hydro group.

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' The breakdown of work by NU aroup is

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Nuclear Group 460,000 i Fossil / Hydro 2,662,000 1

Transmission and Distribution 1.886.000 j 5,008,000 iO 3

Thererore. the work nerrormee re eer oas <or the " cieer orove is e emeii vert or ineir overall work for NU, and when taken in context of a company that does over $900

Million annually ($100 Million power related), the overall work for NU is small, and q would not affect independence of the corporation doing the ICAVP for Millstone Unit 2.

i Nuclear Group Fossil / Hydro i Transmission and Distribution i

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_ -. ~ __ . - _ - _ . - - - _ . - _ . _ _ . _ _ _ . - _ _ . __. - __.-m MT.5ONS POWER GROUID INC. a comtunaten of Gilbert / Commonwealth and Parsons Main ' i 1

W. Kendall Burkhart, P. E., President 2675 Morgantown Road

• Reading. PA 19607 * (610) 855 2466 Fax: (610) 855-2190 l L i

. 5 January 24,1997 l Mr. R. Jeb DeLoach {

Executive Assistant -Ndelear i Northeast Utilities Service Company l Millstone Nuclear Power Station Rope Ferry Road  !

Waterford, CT 06385-2623  :

t

Dear Mr. DeLoach:

t This letter will serve to confirm that Parsons Power Group Inc. (Parsons Power) meets the l independence criteria required in Inquiry No. AWT-106 for Millstone Unit 2 activities. Parsons ,

Power meets the requirements to have no financial interest in Northeast Utilitics, its affiliates or l design contractors, and have no prior involvement in design reviews for Northeast Utilities' Millstone nuclear units. Furthermore, we were not the Engineer of Record or the Architect-l Engineer for Millstone Nuclear Power Station Unit No. 2.  !

Very truly ,

/

IJ W. Ken ur l

WKB/kmb  !

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E mansONS t

CONFLICT OF INTEREST FORM PARSONS POWER: MILLSTONE 2-ICAVP INFORMATION CONCERNING POTENTIAL CONFLICT OF INTEREST Independent Corrective Action Verification Program (ICAVP) for Millstone Nuclear Power Station Unit #2 located in Waterford. Connecticut (Program Name)

(Name)

My participation in the Independent Corrective Action Verification Procram (ICAVP) for Millstone Nuclear Power Station Unit #2 located in Waterford. Connecticut. does ( ) does not ( ) involve situations or relationships of the type set forth below. In particular, I have ( ) do not have ( ) direct previous involvement with design or design review activities at the plant that I will be reviewing and have ( ) do not have ( )

conflicting roles which might bias myjudgment in relation to my work for this assignment. In addition:

1. ( ) I have not been previously employed by the Applicant to do similar design work.

( ) Ihavebeenpreviouslyemployedbythe Applicant.

(State the nature of the employment.)

2. ( ) I do not own or control significant amounts of Applicant stock.

(State amount and nature of ownership.)

( ) I own or control significant amounts of Applicant stock.

(State the nature of the ownership.)

3. ( ) Members of my present household are not employed by the Applicant.

( ) Members of my present household are employed by the Applicant.

(State the nature of the employment.)

4. ( ) My relatives are not employed by the Applicant in a management capacity.

( ) My relatives are employed by the Applicant in a management capacity. I (State the nature of the employment.)

5. ( ) I do not have any financial or other potential relationship in the Applicant that might cause a conflict ofinterest in this assignment.

( ) I do have financial or other potential relationship in the Applicant that might cause a conflict ofinterest in this assignment.

(State the nature of the conflict.)

I understand that I will be precluded from participation should an item be identified and evaluated as a conflict of interest for the Millstone 2 ICAVP.

I in the above statements, the " Applicant" is constmed to mean the applicant (Northeast Utilities System). the j architect-engineer (Bechtel) , or the NSSS vendor (Combustion Encineerine) for the Millstone Nuclear Power Station Unit W2.

O Signature Date l

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d PROJECT PERSONNEL EXPERIENCE, EDUCATIONAL and PROFESSIONAL CREDENTIALS (Continued)

Pro _iect Centrols Planner' Scheduler 22 ABA I&C Engmeer Senior Control Sys. 26 US Aerospace Engineering Engineer Professional Engineer I&C Engineer Control Sys. Engineer 30 MBA BSME Professional Engineer I lectrical Engineer Electrical I ngineer 25 Bs Physics liVAC Engineer Lead IIVAC Engineer 28 MS Engineering Science BSME Professional Engineer Structural Engineer Supervising Engineer 13 PhD Engineering Mechanics MSCE BSCE Professional Engineer Walkdown Lead, Mechanical Designer 31 Mechanical Design, USAF Mechanical Mechanical Drafting TC Electrical Engineer Electrical Engineer 30 BSEE Professional Engineer

Structural Engineer Structural Engineer 28 MS Structural Materials BSCE Professional Engineer l Technical Editor Technical Editor 24 BSME l

Professional Fngineer l Lead Engineer, Electrical . Senior Project Engineer 20 BSEE 1&C Systems l Lead Engineer, Mechanical Senior Mechanical 35 BSME Systems Engineer Professional Engineer Operations Operations Consultant 29 US Electronics EnE i neermg Senior Reactor Operator Professional Engineer Procurement Procurement Consultant 19 MBA MSME BSME Professional Engineer j

Walkdown Lead. Electrical lead Designer 23 Voc. Tech. Drafting i Flectrical l&C I&C Engineer Senior Control Systems 34 Al Electronic (MS equiv)

Engineer A2 Electrical Eng (BS equiv) '

Professional Engineer Lead Engmeer, Project Vice President Major 25 MSME Support Projects BSME Professional Engineer

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l Configuration Management Configuration 23 PhDBusiness Admin Consultant Management Consultant MBA BSNE Senior Reactor Operator Certificd Level til NDE  !

Certified Kepner Tregoe course leader l

Summary

Core team includes 6 PhD degrees,12 MS degrees,23 Registered Professional Engineers, and at least 3 former licensed Senior Reactor Operators. The core team averages about 25.5 years experience.

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l PROJECT PERSONNEL  !

EXPERIENCE, EDUCATIONAL and PROFESSIONAL CREDENTIALS Project Role Parsons Title Yrs Experience Degree / Certification Nuclear Engineer Project Manages 26 BSNE a

Quality Assurance Manager Company 25 AS Quality Lead Auditos/ Examiner level!!! Mechanical Examiner Mechanical Engmeer trad Engineer 28 BSME

Deputy Director Project Manager 20 BS, Marine Engineering

, KAPL Reactor Eng School Professional Engineer Information Services Librarian 23 MS Library Science i BS Education / Library Science

] Electrical Engineer Electrical Engmeer 24 BSEE Professional Engineer Mechanical Engineer - Project Engineer 28 MENE DBE Analysis MS Engineering Science DS Engineering Science j Professional Engineer j Civil Engineer Cisil Consultant 27 PhD Engineering Mechanics MSCE BSCE Professional Engineer Project Director Vice President Nuclear 25 BS Physics Services Fquipment Qualification FQ Pgm Coordinator 16 BSCE Mechanical Engineer Mechanical Engineer 25 MSNE g BSME

\ Operations /1.icensing Operations Consultant 30 Senior Reactor Operator Lead Engineer, Process Principal Consultant 18 MSNE Models and Operational BS Engineering Physics Analysis Professional Engineer Risk Assessment Risk Assessment 30 PhD I ng's / Applied Science Consultant MS Engineering BS Physics Professional Engineer ,

MechanicalIngmeer Lead Engineer 33 ASME I BSME Professional Engineer Mechanical Engineer Piping Engineer 38 MME BSME Professional Engineer Lead Enpneer, l.icensing Senior Nuclear Licensing 24 MSNE and Risk Amsment Engineer BS Physics Certified Lead Auditor Mechamtal Engmeer Mechanical Engineer 16 BSME Professional Engineer Senior Reactor Operator Liectrical Engineer Liectrical Engineer il MS Engineering Management BSEE Professional Fngineer Mechanical Engineer Senior Mechanical 34 PhD Engineer MSME BSME Professional Engineer Risk Assessment Risk Assessment 24 PhD Nuclear Engineering Consultant MSNE BSNE r

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Project Leads a

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MProject Director Over 25 years of experience in nuclear power plant design, engineering, constmetion and operations and management assessments, both domestic and international. As Vice President of Nuclear Services, responsible for all nuclear utility service support worldwide including project wrformance and development. Served internationally in senior management positions as 3egional Manag directors of fore,er, Project Director, Manager of Engineering, and as a member of the boards o ign subsidiaries.

EXPERIENCE: PARSONS POWER (formerly Gilben/ Commonwealth) since 1981 1997 to Present Vice President Nuclear Services - Responsible for all facets of Parsons Power Nuclear Services to clients worldwide.

1996 to Present Director Nuclear Programs - Responsible for all company nuclear industry programs and clients, domestic and international.

1991-95 Director Nuclear Project Operations - Responsible for all nuclear projects performed domestically and internationally, valued up to $40 million annually. Involved with senior U.S. utility executives in planning for restructuring of nuclear utility organizations and processes.

1990 Performed performance assessments for nuclear utilities, evaluating management practices and programs.

1989 Engineering Manager, TVA Sec uoyah Nuclear Plant Restan - Responsible q for day-to-day management of the project office in Tennessee for this Q $20 million project. Major activities meluded electrical and instrumentation modification package development, simulator and control room design reviews, and pro 225 engineers. ject control engineering activities for a staffof110 to 1987-88 Director Intemational Projects; Cairo, Egypt - Responsible for all ongoing company power projects in the Middle East including:

Commissioning / Warranty Phase for 4x150 MW oil-fired units, i Abu Sultan.

Mechanical Design for Daelim Construction on 300 MW Shoubrah El Khemia oil-fired unit.

500 kV Substation and Protective Relay Replacement; Cairo to Aswan.

National Energy Control Center Automation Upgrade, warranty support.

Project Manager - Egyptian Electricity Authority (EEA), Gas Turbine Combined Cycle Conversion, Talkha Power Station - U.S. AID funded Owner's Engineer / Construction Management Consultant; served as advisor to the EEA Deputy Chairman.

Served as Director of Gilbert Associates Middle East Ltd., a joint Egyptian-U.S. engineering services company.

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Persare Power Grow 824612-11004 Pagei

1 1986-87 Director Intemational Projects; Harare, Zimbabwe - Project Director -

Responsible to the Ministry of Energy for National Energy Study and Generation Plan 1986-2010. U.S. and United Nations Development Program funded project.

Project Director - Zimbabwe Electricity Supply Commission, Hwange 7 &

8 Conceptual Design and Study for 2x220 MW coal-fired units - Funded by U.S. Trade and Development Agency. Responsible to the General Manager of Generation.

1983-85 Project Manager - South African Electricity Supply Commission (ESCOM) l Quality Assurance Consulting and Engineerm, g/ License S Contract, Koeberg Nuclear Power Station (two units) - Responsible the first expon

?roject of the French Nuclear Consonium. Support was provided at the 3SCOM Corporate Office in Johannesburg, on site near Cape Town, in Paris, France, and from Reading, Pennsylvania.

Quality Assurance tasks included quality inspection, programmatic monitoring, operations / maintenance evaluations, development and qualification oflocal material suppliers. Engineering assignments included staff augmentation in senior engmeer and licensing positions; maintenance department development; health physics and radiation protection consulting; records management program assistance and evaluations; A detailed horizontal slice program to evaluate field construction, field V changes, engineering evaluations, design changes, and configuration management control based upon the scope of the U.S. NRC Bulletin 79-14.

Manager, Engineering and Suppon Services, Gilben Associates South Africa (Pty) Ltd. - Responsible for the formation, staffmg, training, and management of the engineering deoanment of this South African subsidiary. The primary focus of tais effort was to provide ESCOM with a source of South Africa nationals to suppon the engineering requirements of Koeberg.

1981-83 Manager, Production Improvement Section - Responsible for the management of the Gilben/ Commonwealth field service organization.

Major plant betterment programs included Gilben/ Commonwealth CUE computerized main'.enance management system, plant efficiency and performance studies, preventive and predictive maintenance programs, and nuclear plant preservice and inservice inspection.

1971 80 U.S. Navy Administrative support staffin Bureau of Naval Personnel supponing Director, Naval Nuclear Power Programs, and Deputy Vice Chief of Naval rations for Submarines. Responsible for development and passage of 1 islation on military personnel compensation programs and submarine technical issues. Prepared legislation and provided testimony and issue resolution: Office of Joint Chiefs of Staff, Office of Management &

Budget, and House and Senate Armed Services Committee.

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Nuclear submarine officer responsible for nuclear plant operations, maintenance and training. Chief Engineer - Completed two assignments which included operational periods and plant overhauls. Successfully

' completed a $100 million nuclear plant refueling / conversion overhaul which included steam generator tube plugging. Supervised the first waterbome steam generator inspection and tube plugging assignment.

1 Completed the planning and technical implementation of a two-year,

$300 million refueling overhaul. Prepared and delivered two, one-hour 4

training sessions per week for three years.

1971-72 Assigned to military support staffin New York City for the U.S.

Ambassador to the United Nations. Special assignments included assistance on maritime issues in Southeast Asia and Taiwan.

EDUCATION: B.S., Physics / Oceanography, U.S. Naval Academy,1971 Engineering Economics Studies, George Washington University,1980 ,

M.B.A. Studies, St. Joseph's University, 1981-83 The Executive Program, The Darden School, University of Virginia,1990 SOCIETIES: American Nuclear Society  ;

President, Northeast Pennsylvania Chapter,1994-96 '

Nuclear Energy Institute, Corporate Representative Nuclear Strategic Issues Advisory Committee ,

, Nuclear Suppher Working Group (d PUBLICATIONS: " Outage Management Planning Techniques," American Nuclerdociety, Philadelphia Chapter,1982.

" Preventive and Predictive Maintenance Techniques," South African Society of Mechanical Engineers,1983.

" Computerized Maintenance Management," Vector Magazine,1983.

" Predictive Maintenance Management, Parts I and II," Systems Magazine, April and May 1983.

" Maintenance Management Programs," South African Society of Mechanical Engineers,1984.

"Why Computerize Your Preventive Maintenance Program," Mainterance Management Convention, South Africa,1985.

LANGUAGES: Spanish, Arabic, French, German, Russian (all tourist level) s24612 11004 Fase 3

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O Deputf Project Director-O 4

Over twenty years of experience in the design, operation, testing and maintenance of nuclear and '

a fossil power generating plants. As Manager, Life Cycle Services, responsible for analysis, development and performance of Parsons Power's License Renewal, Aging / Lifetime  !

Management, Plant Improvement and Decommissioning programs. Previous positions included

] design basis engineer, configuration management, modification engineer, pre-operational test director, shift supervisor, operations engineer, maintenance engineer and training engineer.

a EXPERIENCE: PARSONS POWER (formerly Gilbert / Commonwealth) since 1988 4

1991 to Present Manager, Life Cycle Services - Responsible for the analysis, development and performance of Parsons Power's License Renewal, Aging / Lifetime i

Management, Plant Improvement, and Decommissioning programs.

i Responsibilities include strategic planning, detailed technical approach development, resource / capability development and task management.

Task Manager - Westinghouse, Westinghouse Owner's Group (WOG), Life Cycle Management / License Renewal Program - Responsible for technical

! direction of Gilbert / Commonwealth activities associated with development i of task scope descriptions for the program plan, consultation on Integrated l

^ Plant Assessment (IPA), analysis of Life Cycle Management / License Renewal (LCM /LR) information management requirements, and i preparation of system and commodity technical report guidelines. Provided 4

p operations and maintenance practices evaluations, Time Limited Aging V Analysis, and aging analysis / management reviews for WOG-EPRI Generic Technical Reports for RHR system, motor operated valves, check valves, heat exchangers, reactor vessel /RCS supports, containment, reactor vessel, class I piping, and pressurizers. I Task Manager - Sandia National Labs - Responsible for the development of

an industry Aging Management Guideline (AMG) for tanks and pools.

AMG identified design information, analyzed aging degradation, and evaluated industry aging management / maintenance practices for tanks and ,

spent fuel storage pools. AMGs are part of U.S. Department of Energy (DOE) Plant Lifetime Improvement Program (PLIM).

Task Manager - Korea Power Engineering Company - Plant Lifetime

' Management (PLIM) study - Three-year economic and technical feasibility study for extended operations of the KORI-l nuclear plant in Korea.

i Responsible for Phase II planning, economic evaluation, technology assessment, and establishing the scope (screening) of KORI-l systems, structures, and components. PLIM technical reports developed for reactor

! vessel, reactor intemals, reactor coolant pump, RCS nozzles, Pressurizer, i Control Rod Drive Mechanisms, Containment I&C Cables, RCS piping, d

Containment, and Turbine Generator.

Task Manager - Westinghouse - Palisades Reactor Vessel Annealing.

n Responsible for the technical direction of Parsons Power activities ij b associated with NRC Thermal Annealing Request (TAR), thermal characterization of reactor vessel insulation, biological shield wall concrete

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Ci-analysis, ex-vessel instrumentation system, internals characterization and shielding design, temporary reactor cavity HVAC design, and selected construction activities.

Task Manager - Westinghouse - Annealing Demonstration Project.

l Responsible for design, installation, and operation of ex-vessel i instrumentation system and associated data reduction. Also responsible for constmetion activities to prepare site and containment building for annealing operations.

' Task Manager - Consumers Power - Big Rock Point Nuclear Plant -

Supported development of Big Rock Decommissioning Plan, options study, and cost estimate for NRC submission. Prepared decommissioning plan i

sections and supporting evaluations for reactor vessel, reactor vessel internals, steam dmm, primary coolant system, control rod drive system, and reactor cleanup system. Options studies included packing / cutting

, details, resource requirements, and integrated scheduling.

Task Manager - Wisconsin Electric Power Company, Point Beach Nuclear l

Station - Responsible for the development of the License Renewal Project '

Management Plan. Project also included organizational readiness reviews and material assessments for major components and systems.

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'V Task Manager - South Carolina Electric & Gas Company, V.C. Summer Nuclear Station - Responsible for program planning and development of the maintenance rule program. Performed plant system screening, participated i as member of expert panel, developed plant / system performance criteria, integrated maintenance mle program to Reliability Centered Maintenance program, and developed integrated information system.

Task Manager - Electric Power Research Institute - Responsible for engineering and cost data portion of the Gilbert / Commonwealth portion of the ALWR site selection and environmental criteria project. Served as design consultant for Tennessee Valley Authority (TVA), ALWR site selection and environmental study.

Consultant - Prepared and conducted the following workshops:

Ontario Hydro - Life Cycle Management Strategies Korea Power Engineering Company - Life Cycle Management Florida Power Corporation - License Renewal South Carolina Electric & Gas Company - Maintenance Rule Implementation U.S. Department of Energy - Decommissioning and Deactivation Strategies Consumers Power Company - Big Rock Decommissioning Planning.

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Consultant - General Electric Nuclear Energy - Provided life cycle l component considerations and maintenance mle implementation perspectives to support the General Electric (GE) Life Cycle Study for Chubu Electric.

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Task Manager - Pennsylvania Power & Light Company, Susquehanna Station - Technical review and detailed enhancement recommendations of design standard GDS-10 " Life Assessment of SPLEX Components."

Consultant, Industry Initiatives / Assistant Technical Program Chairman -

l l ANS License Renewal Topical Meeting, Participant in IAEA pilot studies on aging management, Participant NUMARC AHAC on Maintenance Rule and License RenewalIntegration 1988-91 Program Manager - Gilbert / Commonwealth Design Basis Program -

' Program manager for all Gilbert / Commonwealth design basis projects.

Prepared the Gilbert / Commonwealth corporate design guide for Design Basis Documents and provided Gilbert / Commonwealth's input to design basis committees / activities at ANS, NUMARC and NIRMA. Member of senior consultant team for TVA, Watts Bar Start-up Design Basis Strategy.

Developed General Public Utilities, Three Mile Island Design Baseline Pilot and program procedures for Baltimore Gas & Electric-Calven Cliffs

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' Nuclear Power Plant Design Basis Consolidation Program. Performed design basis verification of Davis-Besse feed and bleed system upgrades.

Assigned as senior consultant and reviewer for the following DBD projects:

Tennessee Valley Authority, Watts Bar Florida Power Corporation, Crystal River, Unit 3 General Public Utilities, Three Mile Island, Unit 1 Baltimore Gas & Electric Company, Calvert Cliffs Nuclear Power Plant South Carolina Electric & Gas Company, V.C. Summer Nuclear Station Philadelphia Electric Company, on Peach Bottom Atomic Power Station and Limerick Generating Station.

Program Manager - Gilbert / Commonwealth Configuration Management -

Lead engineer for Philadelphia Electric Company (PECo) Configuration Management Issues Review Team responsible for drawing change review, modification evaluation, maintenance of design bases, design interface reviews, modification acceptance testing and as-built programs. Provided resolution of PECo restart design issues. Also performed Waterford 3 NUCLEX assessment for design base documents,50.59 review and related configuration management issues. Configuration management audit / assessment lead at Cleveland Electric Illuminating Company, Perry Plant and Baltimore Gas & Electric Company, Calvert Cliffs Nuclear Plant.

Developed Rochester Gas & Electric Vendor Manual Upgrade Program and l f- lead assessment team. Served as senior consultant for Public Service

( Electric & Gas I&C Vendor Documentation Upgrade Projects, i

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1982-88 Imoell Corooration. Fort Worth. Texas Group Lead Engineer - Hot Functional Test Sequence Coordinator -

Responsible for procedure development, design interface reviews, sequence preparations and operations compatibility review. Also responsible for the following technical specification surveillance test procedures: 18-Month Diesel Testing (Loss of Offsite Power, Safety Injection, Time Response, Load Run); Rx Trip and Safety Injection TADOTs; Containment Isolation; Containment Spray Actuation; 6.9 kV Power Supply Testing; Time Response Testing; and Control Room HVAC. System engineer for switchyard and seismic monitoring.

i Modification and Performance Engineer - Group leader responsible for development, preparation, review and conduct of electrical and I&C surveillance and design modification testing at 1150MW Westinghouse PWR. Surveillance procedures included, but were not limited to, Diesel &

Blackout Sequence, Rx Trip /ESFAS Time Response, Integrated Safety Injection and Control Room HVAC. Special engineering assignments included containment leakage test director and program coordination, modification review and closeout SAR/SER Compliance Review, IE Bulletin 85-03 (Motor Operated Valves) response, technied specification

, ESFAS ad Appendix "J" enhancements, station operating / administrative e

procedure review and preparation, security testing, sys'em analysis and i k configuration / design basis follow for NSSS and balance of plent systems.

Section XI responsibilities for containment isolation valves, special pump i performance tests (spray, RHR, service water), pressure testing and procurement document review.

Senior System Test Engineer - Responsible for start-up testing on NSSS and balance of plant systems at 1150 MW Westinghouse PWR. Test director for Integrated Leak Rate Test ILRT), Local Leak Rate Testing LLRT), Hot Functional Testing (HFT), Solid State Protection System Test and IE Bus Diesel Load Group Assignment (including ESF response timing). Prepared, conducted and reviewed preoperational tests, including ILRT, LLRT and IE Bus Diesel Load Group Assignment. NSSS-auxiliary sub-group leader for the following systems: spent fuel pool cooling / cleanup, service water, component cooling water, containment spray, safety cranes, leak rate testing, containment, fb.. aandling and vessel servicing equipment.

1977-82 General Electric / Knolls Atomic Power Labs. Schenectadv. New York Shift Supervisor - Senior supervisor in prototype plant responsible for conducting and supervising power plant operations and evaluations, including training and drills, testing, maintenance, repairs, outages and emergencies. Interfaced with engineering and craft support groups.

Reported to the plant manager and supervised approximately 100 operators, engineers and trainees. Supervised major plant operations, including cold start-up, integrated plant hydrostatic and leak rate testing, nuclear 824612-11004 Page 4

l instrument alignments / calibration, breaker-valve response timing, engineering safeguards testing and physics-thermal hydraulic te.iting.

Operations Engineer - Shift supervisor engineer responsible for assisting the shift supervisor (duties described above) and acted as relief during his absence. Responsible for in-service inspections and audits, plant and station

' support systems, maintenance and outage coordination / follow-up, plant start-up testing and system design evaluation.

Maintenance Engineer - Project engineer responsible for plant operation problems relating to maintenance and repair, outages, plant modifications,  !

system design evaluation and scheduling. As materials engineer prepared i and reviewed repair procedures, subcontracts, design evaluations and changes. Major design projects included, but were not limited to, site service water upgrade, radwaste management for zero discharge, work administration and reporting system, acid addition system restoration, j engineering safeguards system evaluation, energy conservation modifications and steam dump restart. Prepared plant conditions and test documents for plant outages and assisted with critical path analysis and

planning.

Training / Operations Engineer - Qualified nuclear operations watch engineer L with responsibilities for plant operations and training. Prepared and conducted training sessions, hands-on training and seminars on mechanical, electrical, instrumentation and integrated plant operations / design. Assisted shift supervisor during plant start ups, testing, outages and special training evolutions. Completed extensive theory and operations qualification program at top of class.

1973-77 United States Merchant Marine Acadgmy Marine Officer - Engineering, maintenance and operations experience on oil fired boiler and diesel power propulsion systems on merchant vessels.

EDUCATION: B.S., Marine Engineering / Minor Physics, United States Merchant Marine Academy,1977 KAPL Reactor Engineering School, General Electric,1977 Additional Courses:

Project Engineer Workshop, Gilbert / Commonwealth Development Center, Gilbert / Commonwealth Mastering Business Development, Gilbert / Commonwealth Microsoft Word, Gilbert / Commonwealth dBase III, Gilbert / Commonwealth Word Perfect, Gilbert / Commonwealth Excel, Gilbert / Commonwealth 3 Lotus 1-2-3, Gilbert / Commonwealth DOS, Gilbert / Commonwealth

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O-REGISTRATION: Professional Engineer - Texas (1986), Pennsylvania (1988)

Third Assistant Engineering License Steam and Diesel Vessels - USCG SOCIETIES: American Nuclear Society:

Technical Program Chair - Annual ANS Meeting,1995 Chairman - National Program Committee Vice Chairman - Committee for New Constmetion Vice Chairman - Power Division Executive Committee Member, Professional Engineering Exam Committee Nuclear Information and Records Management Association a , Chairman, Vendor Manual Committee Member, Configuration Management Committee American Society of Mechanical Engineers, Member PUBLICATIONS: " Configuration Management - Design Baseline is the Key," American Nuclear Society Transactions, Winter Meeting,1989

" Materials Management and Spare Parts Issue Workshop," co-organizer, American Nuclear Society, Summer Meeting,1990 i

" License Renewal Topical," assistant technical program chamnan,

, American Nuclear Society, Summer Meeting,1991 O

d "The Next Generation of Nuclear Power Plants: A Status Report,"

chairman, Designs Sessions, American Nuclear Society, Winter Meeting, i

1991 "An Integrated Approach to License Renewal in the United States: An A/E's Perspective," PLEX 91 Con 0.:rence Proceedings, Berlin, Germany Contributing Author, " Support of Design Basis Information Needs," TG14, NIP.MA,1992 Contributing Author, " Position Paper for Implementing a Configuration Management Enhancement Program for a Nuclear Facility," NIRMA, 1992 Co-Author, "The Early Site Permit Siting Guide: Criteria and Procedures for Selecting an ALWR Site," American Nuclear Society, Summer

, Meeting,1993

" License Renewal and Its Information Management Considerations,"

NIRMA Symposium,1993 4

" License Renewal at Wisconsin Electric, a Strategic Investment," PLEX 93 Conference Proceedings, Zurich, Switzerland

" Guideline for Implementing Vendor Information Programs," TG-18, Chairman, NIRMA,1994 P

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" Issue Requiring Assessment When Extending the Gperating Life for an Existing Power Plant," Third Annual U.S/Eastem Europe /Fonner Soviet Union Electric Power Technologies Conference, Bucharest, Romania, April 1995

" Transactions 1995 Annual Meeting," Technical Program Chair, American Nuclear Society, June 25-29,1995

" Reactor Vessel Annealing Projects," GCTech Notes, August 1995

" Aging Management Guideline for Comme cial Nuclear Power Plants -

Tanks and Pools," SAND 96-0343, DOE /Sandia National Labs, February 4

1996 AWARDS: Gulf Oil Trading Company Award - Marine Power Systems ANS - Outstanding Session Organizer: Next Generation of Nuclear Power Plants l

ANS - Outstanding Session Organizer: Materials Management Workshop '

NIRMA - Cenificate of Scholarship - Significant Contributions &

I n d s hip 1

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Twenty-five years of combined professional experience in the operations, quality control / quality l

assurance, maintenance, training, management and supervision associated with commercial nuclear and  !

fossil power plants, nuclear weapons facilities, chemical processing and waste facilities and naval nuclear and fossil power plants.

EXPERIENCE: PARSONS POWER (formerly Gilbert / Commonwealth) since 1980

1996 to Present Manager, Company Quality - Responsibilities, as listed below, for the Nuclear Quality Program expanded to encompass all company quality programs.

9 1993 to Present Manager, Nuclear Quality Program - Development and implementation of the l

' Parsons Power Group Inc. Nuclear Quality Program with administrative responsibility and organizational freedom and authority for assessing and assuring ,

the program's effectiveness in nuclear safety-related activities. This includes all '

design, procurement, construction management and other related services. j

' Responsible for integrating quality into work processes, providing feedback and '

continuous improvement to production teams. Provide assistance to Government, Industrial and International Units implementing various regulated quality programs. Maintain active participation in NEl, ASME, ISO, ASQC and other industry organizations to remain current, knowledgeable and visible as a leader in our industry. Provide external consulting services in above areas.

1991-93 Manager, Nuclear Quality Assurance Engineering Support - Evaluated and 4

improved quality process activities associated with design modification efforts for various operating nuclear ststions. Responsibilities included program (n") development, process assessment, commercial grade surveys and source verifications, staffmg, and providing technical QA guidance. Interfaced with client organizations and intemal organizations to assure effective implementation of quality assurance programs.

1990-91 Quality Verification Manager - DOE-regulated Savannah River Site, Replacement Tritium Facility - Responsible for development, implementation, and management of an effective, integrated quality verification program, including surveillance and independent inspection activities for construction, tumover, preoperational testing, stanup, and operation of the Savannah River Site Replacement Tritium Facility, while meeting the requirements of NQA-1 and the Westinghouse Savannah River Company QA Manual (lQ). Additional responsibilities included evaluating the overall effectiveness of quality programs and providing mechanical / operational quality engineering guidance in technical (design, const: action and operations) and quality related activities.

1989-90 Manager, Quality Engineering Program - Responsible and accountable for overall mar ,,, ment and continued development of Quality Engineering activities.

Activities included all operational related quality services, such as performance-based audits, surveillances and commercial grade assessments, QA/QC program i

development and assessment, consulting services, site quality engineering and technical training. Managed services encompassed NRC, DOE and petroleum industry regulated environments. Responsible and accountable for development of penetration and sales action plans, strategic planning, proposals, expenditure tracking, and overall program profitability.

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m 6 i U Collateral assignments included project manager responsible for primary client I liaison for multiple projects. Experience included contract administration, costing, scheduling and coordination of all division activities associated with assigned projects. Also directed, supervised and participated in consultmg i

assignments as requested. I 1985-88 Manager, Operations Quality Services - Responsible for administration and l

technical supervision of Quality Engineering activities in the areas of Operational ,

QA/QC and Construction Quality Engineering; program development; program j planning; FSAR 17.2 development. Provided direct planning and consulting support for commissioning and operations. Collateral assignments as quality consultant.

DOE-regulated Savannah River Nuclear Plant - Assisted in development and l implementation of the site auditing program. Tasks included program development, auditor training, directing and supervising auditing personnel and quality verification / assessments.

1984-85 Manager External Audits -Implemented and coordinated vendor auditing services, organized and supervised the efforts of assigned personnel, and coordinated inter-office activities for the above program.

1982-84 Supervisor of Construction and Modification QA - Responsible for administrative l and technical supervision of site quality engineering personnel relative to design, procurement, manufacturing, construction and spare parts.

1980-82 Quality Assurance Specialist - Florida Power Corporation, Crystal River Nuclear Station, Unit 3 - Assembled concurrence work packages for systems modifications entailing compilation of design requirements, meterial specification and qualifications, line specifications, NDE and ISI requirements. Assisted in development of trend analysis and repair procedures for mechanical components.

Coordinated review of technical and quality requirements applicable to spare part procurement. Performed quality review of plant technical specification surveillance and in-service inspection procedures.

1968-80 U.S. Navy 1978-80 USS George Bancroft - Engineering Department Leading Chief Petty Officer, Engineering Watch Supervisor, Engineering Officer's Enlisted Assistant, Engineering Department Training Officer, and Technical Adviser for Steam Generator Eddy Current Inspection - Supervised nuclear propulsion plant operation, maintenance, data collection, and quality assurance. Responsible for training and qualification of engineering watch supervisors, engineering laboratory technicians, and Mechanical Division personnel. Supervised 40 to 45 men.

Received Navy Achievement Medal for personal performance, l

1976-78 USS Hunley - Radiological Controls Division Leading Chief Petty Officer, Radiological Control Shift Supervisor - Coordinator and supervisor of environmental monitoring of U.S. Naval harbors and ports. Supervised all 824612-11004 Page 2

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U radiological controls aspects of repair work on nuclear systems of tended units, including internal inspections / repairs of steam generators; accountability, processing, and shipping ofliquid and solid radioactive waste materials; and supervised and coordinated radioactive exposure control system for 200 men.

Responsible for administration of preventative maintenance program, data collection, QA, and training / qualification of radiological Controls Shift Supervisors, Monitors, and Radiation Workers. Supervised 20 to 40 men.

Received Navy Achievement Medal for personal performance.

1973-76 U.S. Naval Nuclear Power Training Unit, Ballston Spa, New York - Engineering Watch Supervisor, Leading Engineering Laboratory Technician, Senior Classroom Instructor and Section Adviser. Counselled and motivated students; established, organized, and directed class scheduling and study programs; taught reactor plant rystems, primary and secondary chemistry; and tutored academically weak students.

1970-72 USS Sea Devil - Leading Engineering Laboratory Technician, Mechanical Operator 1969 USS Edward McDonnel (DE-1043) - Mechanical Operator EDUCATION: A.S., University of the State ofNew York,1990 University of Virginia,1966-68 s St. Joseph's College,1968 Q BSI ISO 9000 Lead Assessor Training Course (RAB, UK),1994 Additional Courses:

INPO Accredited Training Project Management Course Leadership, Management Effectiveness Course Certification Program for Conducting Commercial Grade Surveys and Source Verification Steam Generator Internal Inspection / Repair Course U.S. Naval Submarine School Engineering Laboratory Technician School U.S. Naval Nuclear Power Training Unit Machinist Mate A School N.Y. Regents Nuclear Technology Degree Program CERTIFICATION: Lead Auditor Examiner per ANSI N45.2.23 RAB Certified Quality Systems Lead Auditor (Q04520)

Level III Mechanical Examiner per ANSI N45.2.6 SECURITY CLEARANCE: DOE "Q" Clearance O

Q.)

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p Lead Engineer, Mechanical Systems G'

Extensive experience in engineering, project / task management, design and operations support for nuclear and Yossil power stations including turbine cycles, pumps, heat transfer, compressed air and boiler systeins.

EXPERIENCE: PARSONS POWER (formerly Gilbert / Commonwealth since 1961 1

l 1984-Present Senior Mechanical Engineer / Project Mechanical Engineer - South Carolina '

Electric & Gas Company (SCE&G), V.C. Summer Nuclear Station -

Provided senior level technical advice to Nuclear Operations: l Independent Design Review of modifications which were being installed during 1996 outage and completed modifications for compliance with the Final Safety Analysis Report (FSAR) commitments. Prepared FSAR

revision notices for completed plant modifications.

Technical Consultant to SCE&G's response team for a Service Water Operation & Performance Inspection (SWOPI) self-assessment.

Participated in evaluation of open cycle cooling systems and prepared modification packages including installation of a closed cooling cycle and cooling tower for turbine plant cooling services.

Reviewed SCE&G's calculations for essential cooling water systems ID performance and operating parameters at uprate conditions.

O Independent review of completed modification packages to evaluate adequacy of revisions to plant documentation for configuration management. Evaluation included determining if all affected documents were revised.

Surveyed NRC SWOPI inspection reports for type of findings and violations noted, and prepared a summary report including recommendations. This report was prepared as part of the planning effort for a SWOPI self-assessment.

Prepared five detailed design basis documents for chilled water, component cooling, compressed air, containment spray and post accident sampling systems. Involved in design ofplant modifications, and participated in technical response teams supporting plant operation and maintenance.

Revised configuration control documents to reflect plant modifications.

Prepared responses to non-conformance notices and independent safety evaluation questions from client audit of safety shutdown systems.

Evaluated and revised emergency feedwater system set points resulting from revision to low steam generator pressure set point by Westinghouse.

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Directed preparation of computer model to simulate operating modes for fouled service water system.

Prepared initial feasibility review for plant rerate, review of feasibility study for rerate and prepared evaluations / cost estimates for modifications required to support rerate.

Involved in the technical and safety evaluation for on-line testing of main steam safety valves.

Prepared modification package to replace feedwater isolation valve actuators including analysis of actuator force requirements and stroke time at zero power and at power.

Prepared modification packages to drain pressurizer safety valve inlet loop seals, replace containment isolation valves on sample line from pressurizer, replace cooling water supply source for safety related pumps, install new blowdown system isolation valves and modify blowdown system to eliminate water hammer.

1990-94 Project Mechanical Engineer - Florida Power Corporation, Crystal River Station Unit 3 - Responsible for technical direction, schedule and budget control of mechanical engineering tasks to support plant operation.

L Engineering tasks include: study for decay heat modifications, hydraulic calculations to establish minimum acceptable pump performance for ASME Section XI testing, evaluation of asbestos gasket replacement materials, modification to install a chilled water system, tank volume calculations to correlate actual capacity with indication and a feasibility study for further plant uprate.

General Public Utilities, Three Mile Island - Prepared and reviewed portions ofinstrument air, extraction steam and heater drain design basis documents.

NEK, KRSKO Station - Assessed essential service water system using Generic Letter 89-13. Evaluated plant systems for power uprate at time of steam generator replacement. Prepared plant modification packages including post-accident sampling, hydrogen monitoring, installation of essential service water strainers, and charging pump suction vent isolation valves.

Wisconsin Electric Power Company, Point Beach Station - Preparation of design basis documents for condensate /feedwater system and reactor coolant system. Technical review of design basis documents for fuel handling, control building HVAC, service water and air systems.

Philadelphia Electric Company, Peach Bottom Station - Prepared high pressure service water system design basis document.

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.N l Baltimore Gas & Electric, Calvert Cliff Station - Prepared instrument air  !

DBD.

Rochester Gas & Electric, R.E. Ginna Station - Assisted in responding to j EDSFI questions and analysis ofplant capability for additional uprate if steam generators are replaced. Preparation of a new thermal insulation specification for plant.

1982-84 Senior Mechanical Engineer - Cleveland Electric Illuminating Company, Perry Nuclear Power Plant - Provided technical guidance for Design Criteria Review and System Interaction Review task forces. General Electric NSSS Design Criteria were compared with supporting balance-of-plant design l documentation for criteria review effort; second effort examined availability and interactions of support and interface systems required for safety system function.

1977-82 Manager, Instrumentation and Control Section - Responsible for management, coordination and scheduling of all engineering and design functions associated with instruments and controls of nuclear and fossil 1

power stations.

1979-80 Project Instrumentation and Control Engineer - Allis-Chalmers Corporation, KILnGAS Demonstration Plant - Provided process review and preliminary design.

1979 Project Manager - South Carolina Electric & Gas Company, A.M. Williams Station - Provided planning, scheduling coordination and review of arrangement and equipment specifications for coal conversion.

1974-77 Senior Project Manager - Rochester Gas & Electric Corporation, R.E. Ginna Nuclear Station, Unit 1 (490 MW)- Coordinated and directed activities for the Construction, Quality Assurance and Utility Divisions on projects.

Responsibilities included manpower and cost control, established priorities

and monitored progress.

f 1973-77 Supervising Engineer - Responsible for technical performance of personnel assigned to nuclear projects, review of overall designs to insure consistency, and timely completion ofprojects.

1971-73 Project Manager - A.M. Williams Station, Unit 1 (637 MW, oil-fired) -

Planned, scheduled, coordinated and monitored design and engineering activities.

Project Manager - R.E. Ginna Nuclear Station - Planned, scheduled, coordinated and monitored engineering and design activities involving modification. Performed site studies for nuclear units.

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1969-71 Project Mechanical Engineer - A.M. Williams Station, Unit 1 - Involved in design, engineering and specification.

1969 Mechanical Engineer - Worked on preliminary design and specification for liquid metal breeder (375 ME) study.

Mechanical Engineer - Baltimore Gas & Electric Company, H.A. Wagner Station, Unit 4 (415 MW, oil-fired cycling unit)- Worked on design, engineering and specification.

4

, 1968-69 Mechanical Engineer - Westinghouse Electric International Company, two 600 MW power generating facilities - Worked on preliminary design and specification.

t 1967-68 Mechanical Engineer - Florida Power Corporation, Crystal River, Unit 3 (855 MW) - Involved in design, engineering and specification.

1965-70 Project Mechanical Engineer - Rochester Gas & Electric Corporation, R.E.

GinnN Unit 1 (490 MW)- Involved in design, engineering specification and start-up assistance.

1964-65 Mechanical Engineer - Pennsylvania Electric Company's Keystone Station,

's

, (d Units 1 & 2 (900 MW each) - Provided mechanical control design, engineering and specification.

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1963-65 South Carolina Electric & Gas Company, Canadys Station, Unit 3 (200 MW) and Baltimore Gas & Electric Company, Wagner Station, Unit 3 (325 MW) - Provided mechanical control and piping design, engineering and specification.

1961-63 Terminor, S.A. (Spain), Guardo, Unit 1 (140 MW) - Provided mechanical design, engineering and specification.

1962 U.S. Army Reserve i

1956-61 Western Electric Comoany. Laureldale. Pennsylvania and Buffalo. New

.Y.91k l Various engineering assignments. l EDUCATION: B.S., Mechanical Engineer, University of Buffalo,1961 l Graduate study in Mechanical Engineering, Villanova University,1961-65 REGISTRATION: Professional Engineer - Pennsylvania (1966)

SOCIETIES: American Society of Mechanical Engineers Turbine Water Damage Prevention Committee, Member Performance Test Code Committee, PTC-12.2, Alternate 824612 11004 Page 4

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l l PUBLICATION: Co-authored, " Planning On-line Condenser Tube Inspections," h

. Encmeenne, October 1990.

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(qy Lead Engineer, Electrical - I&C Systems Extensive experience in positions of progressively increasing responsibility in engineering.

Experience includes proven and demonstrated expenise in project engineering, engineering design and applications, professional engineering and support staffmanagement, personnel hiring and training, interpersonal and communication skills.

E22ERIENCE: PARSONS POWER (formerly Gilbert / Commonwealth) since 1988 l 1993 to Present Senior Project Engineer - KRSKO Nuclear Plant and South ~ Carolina l Electric and Gas - Provide innovative solutions to plant problem via process improvements and/or modifications.

Projects included a Human Factors Evaluation of the plant and l

Man-Machine Interfaces in the main control complex which contained '

various Controls, CRTs and Dynamic Screens.

Provided a new DCS (Infi 90) design and installation for new cooling water process system. Developed the system configuration, specification, logic, procurement and installation package.

Pennsylvania Power & Light - Provide leadership for study to upgrade the l feedwater system with new digital system. Managed a team comprised of PP&L plant, operations, engineering and management to improve their ,

scoping process for input to their five year plan.

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U 1991-93 Senior Project Control System Engineer - U.S. Department of Energy (DOE) Advance Neutron Source Reactor (ANS)in suppon of a new heavy water reactor to be built in Oak Ridge, Tennessee. Located at the Reading Gilbert / Commonwealth office, this project is responsible for the total design and licensing per NRC requirements as applicable to the nuclear industry. l Duties included staffing, preparing proposals and providing technical supervision of designers and control systems engineers.

Project utilized the latest advance light water reactor (ALWR) design concepts, plant-wide integrated controls, man-machine interface, total plant configuration management system and latest control room design concepts.

Developed the plant control and data acquisition architecture and defined design requirements for total plant integration. Also, developed the project computer network.

Provided leadership in assembling a control systems team to provide a total plant-wide integrated control system and simulator for this project. Team members composed of Gilben/ Commonwealth, Westinghouse Nuclear and Advanced Technology Division, and Westinghouse Process Control Division. This team would provide a state-of-the-an integrated control system for the ANS project.

Issued plant design requirements (PDR), conceptual safety analysis report (CSAR) and conceptual design report (CDR) for this project.

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.O i Technical review of ALWR designs (GE, CE, Westinghouse) in suppon of a feasibility study to construct four new units for Tennessee Valley Authority, Hartsville, Tennessee, location. Assisted in the development of a cost estimate for each reactor type.

1988-91 Engineering Manager - Gilbert /Comm mwealth Hixson Office / Tennessee Valley Authority (TVA).  !

Sequoyah Nuclear Plant - Supervised a multi-discipline group of engineers j and designers to support TVA's post restart effort for their Sequoyah station. .

Responsible for proposal development, contract negotiations, staf.ing, j presentation to TVA and assure high quality of work.

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Major Project - Prepared design ;mckages to replace the existing Foxboro reactor protection system (RPS) urdware with a new Westinghouse Eagle 21 digital system. Also associated with this project is the performance of RPS loop accuracy calculations and the elimination of the reistance thermal l detectors (RTDs) in the reactor coolant system bypass lines.

Tennessee Valley Authority, Sequoyah Nuclear Plant, Units 1 & 2 - Overall responsibility for the implementation of the detailed control room design review for Units 1 & 2. Included the specification and implementation of a n

v new digital annunciator system.

Other projects included Technical Suppon Center Computer hardware upgrades, P250 computer changes, resolution to Conformance Adverse to Quality Repons (CAQR), Boron injection tank removal, upper head injection modification and support for other projects as requested by TVA.

Senior Project Engineer - Gilben/ Commonwealth Reading Office -

Philadelphia Electric Company, Peach Bottom Atomic Power Plant -

Supervised project control systems engineers and designers. Responsible for defining and scoping work, schedule, budget commitments and personnel training. Defined major design review objectives to assure high quality; and assure that work complied with technical and licensing -

requirements prior to issue. Responsible for instrument setpoints l compliance review against commitments, air compressor upgrade j modification, reactor coolant isolation cooling modification, nuclear i instrumentation system upgrade study, hydrogen analyzer replacement I modification, remote shutdown panel upgrade study, high range radiation l

monitor study, auxiliary boiler modification, Rosemount trip unit l replacement study, and modifications and studies of miscellaneous variables ,

for Regulatory Guide 1.97. '

General Public Utilities, TMI-1, B&W PWR - Performed design engineering, analysis and specification ofinstmment and control systems.

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b Consulting Engineer - Virginia Electric & Power Company, Regulatory l Guide 1.97 - Evaluated existing program and identified deficiencies (PWR, Westinghouse).

Florida Power Corporation, Crystal River (B&W PWR) - Supported new designs related to control systems upgrades.

Technical Consultant - Carolina Power & Light Company, S. Harris Station, 2

Engineering Group Review - Evaluated and made recommendations for the improvement of engineering design program. Audited and commented on site design project (PWR, Westinghouse).

1987-88 Steam Electric Inc.. Greenvale. New York Project Engineer / Consulting - Long Island Lighting Company, Shoreham i Nuclear Plant - Responsible for design of new instrumentation systems for a i

proposed supplemental containment system vent, and integration of new systems with existing plant computers to monitor and control auto i activation of the new containment vent. This venting system was the first planned installation in the U.S. nuclear industry.

Prepared safety evaluation for the NRC tojustify impact on the existing i design basis. Ensured that the design met technical and licensing I t

c requirements.

Designed control panels. Implemented programmable controllers, logic drawings, and computer integration with new systems. Also developed specifications for all new control systems.

1985-87 Gilbert / Commonwealth. Readinc. Pennsylvania Systems Engineer - Gilbert / Commonwealth Reading Office - Pennsylvania Power & Light Company, Susquehanna Station (BWR) - Performed design engineering, systems analysis, and specification ofinstrumentation and control systems. Evaluated balance-of-plant end NSSS systems, defined problems, recommended corrective action and issued new designs.

Prepared diagrams, designed control panels, implemented programmable controllers, and presented the design to support assigned project. Provided technical supervision of project discipline engineers. Developed schedule, budget commitments and personnel training. Projects included high pressure coolant injection control circuit design, radwaste evaporator mterlock, control evaluation and design of HVAC systems, redesign of standby gas treatment system control logic and circuits, and neutron monitoring system. Performed systems review and provided direct resolutions to technical problems. Responsible for the planmng, design and supervision of the engineering team to respond to Appendix "R" modifications, and for direct site operational support for problem systems.

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, 1984-85 General Electric Comoany - Nuclear Energy Business Ooerations. San Jose.

California System Engineer - Represented Nuclear Controls and Instrumentation in the suppon of site installation of power generation control complex equipment and NSSS systems. Solved and documented design-related problems and provided a single point C&I engineering interface at the site. Provided l technical supervision of discipline engineers, and approved systems engineers' work on plant NSSS to ensure that work met technical and licensing requirements.

Nuclear Project: Niagara Mohawk Power Corporation, Nine Mile Point, Unit 2 (1080 MW, BWR) 1982-84 Vircinia Electric and Power Comoany. Richmond. Vircinia 4

I&C Engineer - Analyzed, designed and specified instrumentation and control systems for nuclear power plants. Evaluated station problems and recommended corrective action, from designing a new system to upgrading an existing one. Also provided suppon at the site engineering office.

Prepared design change packages to include design, calculations, engineered materials, drawings, and assurances that the package complied with all applicable industry codes and standards, such as IEEE, ANSI and NEMA.

1 Also provided support for projects during construction and installation.

Project Lead Engineer - Virginia Power Company - Supervised consulting engineers who reviewed, revised and updated surveillance and maintenance program. Responsibilities included defining major objectives to assure high plant availability and retention of qualification for equipment. The program addressed NRC concerns and station commitments. All procedures were j reviewed and updated with respect to program goals and commitments.

f Also technical consultant on the installation of NUREG 0696 data system.

Nuclear projects included: Surry Power Station, Units 1 & 2 (900 MW

! each, PWR); and North Anna Power Station, Units 1 & 2 (900 MW cach, PWR). Westinghouse NSSS.

Projects included Westinghouse 7100 and 7300 series protection systems

(NSSS), control room (NUREG 0700), Appendix "R" (10CFR50), Incore i T/C, boron reduction, Regulatory Guide 1.97 (response letter to NRC, design and compliance), reactor flux monitoring system, loose pans monitoring, NUREG 0696 (design fiber optic data acquisition system),

technical support center, supervising personnel revising VEPCO's surveillance and maintenance program, and implementing 10CFR50.49. j 1979-82 General Electric Comoany. Fitchburn. Massachusetts Control Engineer - Updated instrumentation systems for Mechanical Drive o Turbine Depanment. Designed and advised on the installation of Hewlett Q

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U HP 2250 processors to a new control room to enhance product testing.

Equipment included microprocessor data systems, programmable controllers, electronic governors, and a variety oflaboratory equipment.

Provided technical consuhation for electronic test equipment and procedures for MDTD, including evaluation and specification of new equipment. Also designed instrumentation systems and supervised an electronics laboratory which conformed to NBS requirements and quality.

Supported and resolved controls and electrical problems related to MDTD manufacturing operations.

Planned, designed, budgeted and initiated new projects to enhance manufacturing capabilities such as; structureborne noise monitoring system, electrical load measuring system, performance testing facility, data acquisition systems and other facilities required to enhance product quality.

Project Engineer -Interfaced and assisted marketing with clients during product esting. Made technical presentation of product to clients and respon.ied to questions or problems. Presented test facilities and reviewed

tee data with clients. Total project responsibility frem initial design to final installation and operation.

Utility: TVA, Houston Power & Light Company, Florida Power -

Corporation, (Nuclear) Gulf State Utilities.

Industrial: Exxon, Gulf, Dupont, ICI, Mobile Government: U.S. Navy 1976-79 General Electric. Schenectadv. New York Instrumentation Engineer - Implemented seismic analysis equipment and analytical instrumentation for the power industry. Designed and installed electronic data system and controls for large steam turbines and generators (in-house and field). Provided field support for these systems. Prepared technical reports and data folders for completed projects.

Assigned to a product development and testing engineering group to support manufacturing of motors, turbines, generators and gas turbines. Develop testing requirements and upgrade plant facilities to meet new product testing requirements.

Nuclear projects: Trojan, PWR; Duane Arnold, BWR; River Bend, BWR.

J 1975-76 Mohawk Data Science. Herkimer. New York Electronic Specialist - Printed circuit board testing, design and data systems debugging. Also performed startup and test of these data systems.

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1 1972-74 Divine Brothers. Utica. New York Technician - Maintained oven controls and other instrumentation equipment related to production line for polyurethane castings.

1969-74 U.S Army Reserves. Civil Affairs Groue Evaluated resources of assigned area and documented in report format for possible use during a national emergency or local disaster.

Honorable Discharge.

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EDUCATION: B.S., Electrical Engineering, Central New England College of Technology, Worcester, Massachusetts (Cum Laude),1981 AAS, Electrical Technology, Mohawk Valley Community College, Utica, New York (Cum Laude)

Additional Courses:

Project Management, Worcester Polytech Institute,1981  ;

Effective Presentation, Worcester Polytech Institute,1981 l

Microprocessor 6502,1982 '

Hewlett Packard 1000 Computer,1983 Valaidyne HD310 System for Nuclear Power Stations,1985 TEC Products for Nuclear Power Stations,1985 Programmable Controllers:

PowellIndustries,1984 Os Baily Controls 7000 Series,1984 Allen Bradley,1985 Texas Instrument,1986  :

Control Systems:

Westinghouse 7100 & 7300 system Nuplex 80 Westinghouse Eagle 21 Westinghouse WDPFII Integrated Control System Bailey INFI 90 Foxboro A/' System i

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O Lead Engineer (V tional Analysis Eighteen years of experience in management of small and large projects, including 15 years in perfonning and managing design moc ifications of nuclear power plants. Proven ability in evaluating and establishing effective and efficient business processes. Nationally recognized authority on nuclear spent fuel management and high level waste disposal issues. Outstanding leader with proven record of accomplishments EXPERIENCE: Performance Technoloev. Inc.

1995 to Present Principal Consultant - Business process consulting to the utility, transportation, govemment, and public sector.

4 Risk Management - Led a cross-functional team in ma? ping existing ,

processes for managing elements of risk at Conrail inc..uding rail car and '

freight damage, personal injury reduction, environmenta!, and litigation.

The team developed process changes totaling $9.2 million in annual savings and introduced statistical measurements to monitor the new processes.

Facility Processing Capacity - Training and consulting services for mapping ofinterfaces between organizations and various process that exist at a major rail car classification facility. Developed changes in information technology, facility design personnel utilization, maintenance processes, and performance measurem, ents to increase traffic flow and reduce existing process bottlenecks.

3 1981-95 Gilbert / Commonwealth. Inc.. Readinc. Pennsylvania (V

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1994-95 Senior Consultant - Provided management services, and consulting in the areas of high performance business process reengineering and high level

, waste and spent fuel management.

Maintenance Work Control Process - Consulted on process design methodology, and facilitated mapping and redesign of maintenance process for IES Utilities. The Project Team identified 35% annual savings for work planning and administration.. Automated generation ofpreventative maintenance work packages will reduce O&M costs by $2.5 million/ year.

As-built Documentation Process - Consulting services to identify the way different groups were updating design documentation as a result of equipment and facilities modification at American Electric Power. Process ma ps provided a tool to communicate to management the current problems and process inefficiency in preparation for a redesign of the document control process.

Modification Process - Consulted on process design methodology, and facilitated redesign of modification process for major design changes at Pennsylvania Power & Light (PP&L). Facilitated cross functional client team, consisting of union and nonumon personnel, through mapping and analysis of existing process, benchmarking, process measurements, design of new process, development of business case and implementation plans.

The resulting process, organization, information technology and management control changes was estimated by PP&L to be worth $2.6 million/ year in savings.

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d 1993-94 Process Consultant - Assi ned to general engineering services project for Carolina Power and Li CP&L). Responsible for design and implementation of cost effective interface processes between G/C and

CP&L. Devised work task proposal process to shorten turn around time and improve communication with client on how G/C would perform work and interface with CP&L. Implemented project management controls to ensure l effective, high quality engineering services. Provided assessment and improvement recommenc ations of CP&L intemal client lower costs and become more compedtive. processes to help this 1993 Process Consultant - Assigned to continuing services project for PP&L.

i Responsible for reengineenng the project pro posal development process.

The new process reduced average tum around time from three weeks to four days, and eliminated an anticipated need to increase project support staff.

1992 Litigation Suppon: Provided consulting services to the U.S. Department of Justice on various aspects of nuclear power plant design and the nuclear utility industry in sup? ort oflitigation regarding the construction costs associated with cance led nuclear power facilities.

1991-92 Project Manger - Responsible for $6.2 million annual revenue for G/C services provided to Philadelphia Electric Company (PECo). Directed a I multi-disciplined team that performed engineenng/ design and related nuclear power plant sup? ort services for this client. Work included y modification design pac cages, engineering programs and studies (including j

GL 89-10, GL 89-13, and EQ), and development of design configuration '

basis documents Responsible for overall direction and management of the project team, and the enhancement of client interface processes.

l 1989-91 Senior Project Manager - Philadel ?hia Electric Company, corporate home office staff extension - Accountab e to the manager of p 'ects for directing a staff ofmodification team project managers in pre on for Peach Bottom, Unit 3, cycle 8 operations and refueling outage. Project Mancger <

for resolution of service water design basis system functionaltesting '

deficiency. Successfully lead a team of engineering and plant staff personnel in perfctming design basis investigation, functional testing, and  :

preparation for NRC reviews.

1988-89 Site Manager - Philadelphia Electric Company, Peach Bottom Atomic l Power Station - Supervised and managed a multi-disciplined engineering and administration group of 60 people supponing the restart of Units 2 & 3. I Responsible for cost, schedule and technical qua ity of work. Major areas of support include development and implementation of commercial grade dedication program for spare parts, engineering and design of modifications required for restart, disposition of non-conformances anc station questions, walkdowns and suppon for INPO and NRC audits and inspections.

1981-88 Project Engineer - Provided project administration and technical direction for vanous engineering projects including spent fuel stora ge expansion at O Peach Bottom and Limenck stations, advanced conceptua design of high level waste packages for a national geologic repository in basalt rock, and

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development of the nation's first license application for a new facility under 10CFR part 72 and applicable NRC regulatory guides.

1980-81 American Electric Power Service Corocration. New York. New York Nuclear Engineer - Engaged in contract negotiation and admmistration of  ;

nuclear fuel supply services. Performed fuel cycle cost analyses used in l

determining rates and operation cycle lengths. Responsible for monitoring l government programs related to nuclear spent fuel. l 1978-80 Project Engineer - D.C. Cook Nuclear Plant - Responsible for expansion of the spent fuel storage capacity including: bid specification, design review, l license analysis and installation of high-density racks. '

1974-78 Engineer and Co-op Student - Performed in-core neutronic analysis. D.C. ,

Cook, Unit 2, - Supported initial criticality and low power physics testing.  ;

EDUCATION: B.S., Engineering Physics, Cornell University, Ithaca, New York,1976 i M.S., Nuclear Engineering, Comell University, Ithaca, New York,1977 REGISTRATION: Professional Engineer - Pennsylvania (1983)

SOCIETIES: Chairman of Standards Committee ANS 57.7 " Design Criteria for an Independent Spent Fuel Storage Installation (Water Pool Type),"

American Nuclear Society y Chairman of Standards Committee ANS 57.9 " Design Criteria for an Independent Spent Fuel Storage Installation (Dry Storage Type),"

American Nuclear Society Chairman of Standards Committee ANS 57.10 " Design Criteria for Consolidation of LWR Spent Fuel, " American Nuclear Society Past member of Standards Committee ANS 57.2 " Design Requirements for LWR Spent Fuel Storage Facilities at Nuclear Power Plants" Past member of Standards Committee ANS 57.3 " Design Requirements for New Fuel Storage Facilities at LWR Plants" PUBLICATIONS: " Interim Spent Fuel Storage Using Rod Consolidation," American Nuclear Society

" Spent Fuel Storage: What's the Next Step?," Waste Management Conference "Altematives for Spent Fuel ," WATTec Annual Energy Conference "Altematives for Dry Storage," Institute of Nuclear Materials Management

" Wet Pool Independent Spent Fuel Storage Installation" American Nuclear Society

" Prospects for Spent Fuel Disposal in the U.S.A.," USA ROC Joint Economic Councils, Taipei, Taiwan "GAI-Vault, G/C Reference Design Dry Spent Fuel Storage Vault,"

American Nuclear Society Topical Meeting

" Economic and Feasibility Analysis of I8-Month Fuel Cycles," American Nuclear Society Annual Meeting O

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M 1 Lead Engineer, Licensing and Risk Assessment Twenty-three years of experience in nuclear licensing and plant operations in support of domestic

' and intemational clients. Nuclear licensing experience includes technical coordination during operating license review, regulatory conformance reviews, safety issue resolution, regulatory interface, safety analysis preparation and review, independent design verification, and safety evaluation preparation.

EXPERIENCE: PARSONS POWER (formerly Gilbert / Commonwealth ) since 1979 1985 to Present Senior Nuclear Licensing Engineer - Principal contact for Parsons Power  !

(Gilbert / Commonwealth) nuclear licensing activities. Responsible for 4

evaluating and disseminating Nuclear Regulatory Commission and industry-related licensing information to appropriate technical disciplines and all nuclear projects. Act as the company's point of contact for Nuclear Energy Institute (NEI) matters. Responsible for providing licensing input

' for all nuclear projects and programs such as license renewal, maintenance rule implementation, regulatory interpretation, responses to NRC Bulletins /Information Notices, input and review of safety evaluations and attendance at NRC t :d ACRS meetings.

Projects include:

South Carolina Electric & Gas Company, V.C. Summer Nuclear Station Nukleama Elektrama Krsko NPP, Slovenia.

National Electric Company - Bulgaria Philadelphia Electric Company, Peach Bottom Atomic Power Station and Limerick Generating Station Pennsylvania Power & Light Company, Susquehanna Steam Electric Station l Public Service Gas & Electric, Salem and Hope Creek Stations Florida Power Corporation, Crystal River, Unit 3 Tennessee Valley Authority, Sequoyah and Bellefonte Stations GPU Nuclear Corp. Saxton Experimental Nuclear Facility Senior Licensing Engineer - South Carolina Electric and Gas - V. C.

Summer Nuclear Station, FSAR Verification Program including programmatic input, safety evaluation review, and preparation of FSAR changes.

Senior Licensing Engineer- GPU Nuclear Corporation - Coordination of licensing act;vities in support of preparation and submittal of a Decommissioning Plan for the Saxton Nuclear Experimental Facility, located in Saxton, Pennsylvania, to the NRC.

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C) v Senior Licensing Engineer - Responsible for the fmal licensing review of the report on Control Room Design Review for NPP Krsko.

Task Manager - Nuklearna Elektrama Krsko, Regulatory Compliance Program review - Responsible for technical activities injoint venture with NSSS vendor for review of compliance to all NRC regulatory changes,  !

regulatory guides, generic letters, unreviewed safety questions and bulletins issued by the NRC since 1974.

1 Project Licensing Engineer - DOE /MMES, Advanced Neutron Source  !

Project (ANS) - Responsibilities included the preparation of l licensing / regulatory plan and permitting plan, coordination of preparation of A/E sections of the Conceptual Safety Analysis Repon and regulatory interpretation. '

Task Manager - NE Krsko, FSAR Upgrade Project - Responsible for the l

preparation and publication of the Updated Safety Analysis Report, including review and incorporation of plant modifications and technical ,

specifications. l Pennsylvania Power & Light Company - Technical specialist in support of ,

internal audits in the areas of plant chemistry program and medical I qualifications oflicensed operators.

Project Licensing Engineer - South Carolina Electric & Gas Company, V.C.

Summer Nuclear Station (PWR) - Coordinated licensing activities including review ofdesign change safety evaluations, and tracking design modifications for inclusion in FSAR update. Preparation of FSAR amendments required by 10CFR50.71(c). Provided input to Phase I implementation of 10CFR50.65 " maintenance rule."

1979 to 1985 Project Licensing Engineer - Cleveland Electric Illuminating Company, Perry Nuclear Power Plant, Units 1 & 2 (1200 MW each) - Responsible for technical coordination oflicensing activities during fmal safety analysis review development and operating license review stage. Met directly with NRC reviewers to resolve issues . Also provided technical assessment of U.S. Nuclear Regulatory Commission documents, preparation of technical input in support of the Safety Evaluation Report , prepared NRC presentations and coordinated G/C input for ACRS presentations and coordination of technical specification input. Panicipated on team to resolve action items from NRC Integrated Design Inspection (IDI).

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a 1973-79 Metrooolitan Edison Comoany. Readine. Pennsylvania 1978-79 Supervisor of Generation Licensing - Responsible for the licensing of the company's nuclear generating units and fossil fueled generating units including interface with the Nuclear Regulatory Commission, Environmental Protection Agency, and Department ofEnvironmental '

Resources. Served on Executive Committee of Babcock & Wilcox Owners Group. Direct supervision of 14 people.

I 1975-78 Lead Nuclear Engineer - General Public Utilities, Three Mile Island Nuclear I Station, Unit 1 - Responsible for core physics, special nuclear material j control, reactor refueling, reload licensing and physics testing.

l 1973-75 Project Engineer, Three Mile Island Nuclear Station, Unit 1 - Assisted on shift in initial stanup activities of 900 MW nuclear unit, including initial fuel receipt and fuel loading, initial startup, and power operations. Assisted in review and preparation ofplant surveillance, test, and operating procedures.

1970-73 The Pennsylvania State University. University Park. Pennsylvania Breazeale Nuclear Reactor - Assisted in daily operations of 1 MW TRIGA O research reactor facility (full-time position). Obtained Atomic Energy Commission Reactor Operator's license while continuing research in the area of thennoluminescent dosimetry. Assisted in training program for utility reactor operators.

EDUCATION: B.A., Physics, Susquehanna University, Selinsgrove, Pennsylvania,1969 M.S., Nuclear Engineering, The Pennsylvania State University, University Park, Pennsylvania,1973 Additional Courses:

Supervisory Development for Utility Managers, Rutgers University, 1978 Facilitator Certification, The Quality Advantage, ODI,1992 SOCIETIES: American Nuclear Society CERTIFICATION: Certified Lead Auditor O

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4 Lead Engineer, Project Support Over 25 years of experience managing complex, tumkey, lump sum, multi-million dollar projects. Vice President of domestic and intemational, power and industrial groups responsible l for operations and business development. Managed intemational and domestic tumkey projects.

Managed a variety ofindustrial and power projects. Direct, hands-on experience in the project business / project management, construction, engineering and purchasing areas.

EXPERIENCE: PARSONS POWER (formerly Gilbert / Commonwealth) since 1996 1996 to Present Vice President, Major Projects - Responsible for pursuit and managem.mt of large, domestic and intemational, lump-sum tumkey projects. This

' responsibility includes the management of project controls, procurement, estimating and construction.

1993-96 Raytheon Eneineers & Constructors. Philadelohia. Pennsylvania Vice President Projects / Project Director - Responsible for the execution of intemational tumkey projects. Successfully completed the Maraven IPP Project, the first independent power plant in Venezuela.

1990-93 Gibbs & Hill. Inc.. New York. New York Vice President, Power and Industrial Group - General management and ,

business development responsibilities. Duties included the management of l design, construction management, and project management professionals l for a major architect / engineer in the power and industrial market. Projects

(" included power plants and industrial facilities worldwide. Gibbs & Hill was acquired by Raytheon Engineers & Constructors in 1993. '

1986-90 General Electric Company. Schenectadv. New York Senior Project Manager / Manager, Projects - Recruited and participated in the startup of the Domestic Projects Group, which was responsible for turnkey projects including fossil, refuse, tire, and agri-waste-fired plants.

Managed a group designing and building GE's first STAG 107F prototype ,

combined cycle power plant for Virginia Power.

1983:86 fuller Company. Bethlehem. Pennsylvania 1984-86 General Manager, Project Management - Managed and directed a group performing project management, estimating, scheduling, product and construction /stanup services for turnkey projects worldwide.

1983 84 Project Manager - Managed the design, equipment procurement and manufacturing, and construction and startup for a cement plant upgrade.

Project was completed ahead of time and under budget. <

1979-83 Kuliian Comoration. Philadelohia. Pennsylvania .

Project Manager for a consulting engineer for both steam and gas turbine fossil fired power plants. Projects included:

Al Jobail Desalination / Power Plant, Saline Water Conversion Corporation, Saudi Arabia - Phase II - 1100 MW/210 MGPD - In Persons Power onme 824612 11004 Pagei

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joint venture with Catalytic Inc., managed nine turnkey contractors from concept through startup. Project completed on time, within

, budget. Project cost $2.0 billion.

" Hussein Thermal Power Station, Jordan Electricity Authority - 2x33 MW steam power plant. Project cost $70 million.  :

'. Al Qasim Military City, U.S. Army Corps of Engineers, Saudi Arabia - .

100 MW gas turbine plant. Project cost $75 million.

, 1974-79 General Electric Comoany, New York. New York Project Manager - International Projects Department - Project Manager for various tumkey, international gas turbine projects, managing multinational 1

consortium partners from design through startup. Projects included:

Mecca Power Station, Saudi Electric Company, Saudi Arabia - 150 MW gas turbine power plant. Project cost $76 million.

Haoud El Hamra-Skikda, Sonatrach, Algeria - Cmde oil pipeline.

Project cost $200 million.

1972-74 General Electric Comoany. New York. New York Buyer, Purchasing Operation - Intemational Projects Department -

Responsible for negotiating the purchase ofmajor mechanical equipment for power plants being constructed overseas.

1970-72 _Il.S. Army. Coros of Encineers Lieutenant - Facilities Engineer - Combat Engineer Platoon Leader.

EDUCATION: B.S., Mechanical Engineering, Pratt Institute, Brooklyn, New York,1968 M.S., Mechanical Engineering, Polytechnic Institute of Brooklyn, New York,1971 REGISTRATION: Professional Engineer - New Jersey, Pennsylvania and New York i

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]V Consultant A successful leader of projects and organizations. Responsible for the design, licensing, construction, operation and maintenance oflarge capital projects, including power plants, research laboratories, industrial and military facilities, for domestic and international customers. Demonstrated successful, profitable leadership of diverse groups of project managers, design engineers, salespersons, technicians, designer:, construction, operations and maintenance personnel. Proven abilities to predict and adapt to the continuous changes in business conditions driven by technical, economic, political, social, competitive, or demographic forces. PC and CADD literate.

EXPERIENCE: PARSONS POWER (formerly Gilbert / Commonwealth) since 1967 1996 to Present Senior advisor and consultant. Special consulting assignments for various customers on a variety of projects.

1994 96 Vice President and Director of Projects for Parsons Power, a large engineering-construction management company in eastern Pennsylvania. Responsible for direction of 18 project managers executing energy projects in the U.S., Europe, and Asia, including work quality, scoping and scheduling, new business development, and contracts. Special assignment in 1994 to develop company strategy and plan to improve overall productivity. Led a team of project managers, engineers, designers, and automation specialists to develop a detailed plan to automate production work processes and restructure the company to achieve 30 percent productivity gain. 'ne program was successfully implemented in 1995 96.

1991-94

[]

V Vice President and Project Director - Leader of a team designing the Advanced Neutron Source, a new $2 billion neutron scattering, isotope production and research facility for the Oak Ridge National Laboratory, with a 330 MWt nuclear reactor as the source of the neutrons. Responsible for development of the design, QA, safety analysis report, construction plan, cost estimate and overall. Congress canceled the project in 1995.

1985 90 Vice President and Manager of Engineering - Responsible for management, administration and technical direction of the Engineering and Research Departments including 700 engineers and other personnel involved in the design and modification of nuclear and fossil power plants, power transmission, industrial and government facilities. Also, Vice President of corporate sales including direction of sales and proposal staff, proposal preparation and review, pricing and marketing strategy during 1986-87.

1982-85 Vice President, Project Management . Responsible for direction of project management activities including supervision of 20 project managers, establishment of management techniques, contract negotiations, periodic review of project progress and resolution of problems. Also responsible for the company's procurement, planning and scheduling, and cost engineering activities.

During this assignment, design and construction of three nuclear units and one fossil unit were completed, totaling 3,350 MW. There were also numerous modifications to existing power and industrial plants and government facilities, as well as the design and constructica of a coal gasification plant.

1977-82 Vice President and Manager of Engineering - Responsible for technical and O administrative direction of over 1,000 engineers and other design personnel

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engaged in the design and modification of power plant facilities in the U.S.,

Europe and Asia. Responsible for staffing, training, design control, budgeting, personnel recruiting and development and implementation of operating procedures and design standards. During this assignment the design and construction of two fossil units and five nuclear units were completed, totaling 5,700 MW.

1973-77 Manager of Mechanical Engineering Department and Chief Mechanical Engineer - Technical and administrative direction of 140 design engineers and technicians performing mechanical design on fossil and nuclear projects. Duties included review and approval of mechanical specifications, chairperson of the System Design Review Committee, development and implementation of standards, personnel recruiting and training, budgeting, cost control and support of marketing activities.

1967-73 Various assignments ofincreasing responsibility as design engineer, project engineer and project manager. Leadership of groups of engineering and design personnel for several domestic and international projects.

1963-67 Mississioni Power and Light Comoany. Jackson. Mississioni Station Mechanical Engineer - Responsible for design review, construction supervision, plant startup, maintenance coordination and operator training for a new 550 MW fossil plant. Plant engineer and relief shift supervisor on several other units from 33 MW to 250 MW.

1961-63 General Dynamics Corporation. San Dieco. California Site Activation Engineer - Responsible for construction, equipment installation, checkout, design modification, startup and crew training for hardened launch facilities for intercontinental ballistic missiles (Atlas "F") in Texas, Oklahoma, Kansas and New York.

1958-61 U.S. Armv. Aberdeen. Maryland: Huntsville. Alabama: White Sands.,

New Msxico: Whionany. New Jersey Platoon Leader, Missile Maintenance Unit - Project officer for weapons development agency and assistant contracting officer at Bell Telephone Labs.

Responsible for hands-on maintenance of high-tech hardware, development and test of new weapons systems and contractor coordination.

EDUCATION: B.S., Mechanical Engineering Mississippi State University,1957 Postgraduate Study, Mechanical Engineering, Rutgers University,1963 Many short courses, seminars, workshops and company-sponsored training, including Total Quality Management courses. Guest lecturer on Project Management at Pennsylvania State University and Virginia Military Institute.

REGISTRATION: Professional Engineer - Mississippi (1966), Pennsylvania (1971), Florida (1973) and Tennessee (1990)

SOCIETIES: Member, American Society of Mechanical Engineers, American Nuclear Society O EPRI Steam Generator Owner's Group, Architect Engineer Advisory Committee, 1974-78

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Edison Electric Institute (EEI) Prime Movers Architect-Engineer Advisory

Committee, 1980-87 Industry Committee - American Power Conference,1975 85 l Atomic Industrial Forum (now NEI)- Three Mile Island Lessons Learned Task Force,1979-81; Committee on Reactor Licensing and Safety,1985-88;

, Subcommittee Chairperson,1988 Director, Magnetohydrodynamics Development Corporation, Butte, Montana, 1985-91 Company Representative, Supplier Participant Advisory Committee, Institute of Nuclear Power Operations,1987-95, Chairperson, 1991-92

- Director, Caron Foundation, Wernersville, Pennsylvania, 1988-93 PUBLICATIONS: Numerous articles and presentations on engineering and management topics O

s24612 11004 Page 3

M Advisory Panel Founder ofM providing personal consulting services to the power industry.

Retired Chief Executive Officer / President ofm a consulting firm to the power industry, which he founded in 1977. Presently consults for many electric utilities and i

several power equipment manufacturers, the Electric Power Research Institute, two National l Laboratories, and the Research Division of the U.S. Nuclear Regulatory Commission. For more than 20 years, employed by the General Electric Company in various technical and managerial l

positions, including General Manager, Boiling Water Reactor Operations, responsible for all the engineering and manufacturing of General Electric nuclear power business. Member of the National Academy of Engineering, a fellow of the American Society of Mechanical Engineers I

and the American Nuclear Society. Member of several nuclear power plant safety and review committees. Serves on the Advisory Council for the Institute of Nuclear Power Operations (INPO) and was a member of the Independent Advisory Board of the B&W Owners Group Safety and Performance Improvement program. Has authored over 50 publications and given several invited lectures to national and intemational technical conferences. ,

EXPERIENCE: M. San Jose. California i

1994 to Present Consultant 1993-94 M

President of engineering / management consulting firm with 60 employees, a budget of sales of 57 million, and a net worth of 53 million. Involved in the f]

v following types of work:

Member of the Industry Advisory Board during the Three Mile Island Unit 2 accident.

Consultant to the Kemeny Commission Staff.

Consultant to Brookhaven National Laboratory and Idaho National Laboratory.

Consultant to Electric Power Research Institute.

Consultant to many U.S. utilities, including being a member of four independent safety review boards (GPU, Detroit Edison, Arizona Public Service, and Iowa Electric).

Member of Nuclear Oversight Committee for Public Service Electric and Gas and Arizona Nuclear Power Project.

Member ofIndependent Oversight Committee for Detroit Edison.

Consultant to the NRC on their Advanced Code Review Committee.

Consultant to World Bank /UNDP on nuclear safety in Korea.

Consultant to Independent Engineering Review of Hanford-2.

Member of four PRA Peer Review Boards.

Springer Professor, University of California, Berkeley.

Adjunct Professor of Engineering, University of California at Los Angeles.

Member, Independent Advisory Board, B&W Owners Group.

Director, Iowa Electric and IE Industries.

Member, Independent Transition Team to Secretary, Department of Energy.

s Peer Review of NRC Source Team Studies.

) Member of NRC Panel on Source Term Issue Resolution.

. F Member of NRC Severe Accident Scaling Methodology.

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Advisor, Board of Directors, Philadelphia Electric.  ;

Member, NRC Nuclear Safety Research Review Committee. l Member,1nmpendent Power Limits Review Committee for Savannah River.

1954-77 General Electric Comoanv. San Jose. California 1975-77 General Manager, Boiling Water Reactor Operations - Responsible for th: l engineering and manufacturing of all boiling water reactors. Approximately 5,000 employees. Resigned to form own independent consulting firm.

i 1973-75 General Manager, Boiling Water Reactor Systems Department -

Responsible for the design and development ofnuclear systems including fuel. Also responsible for the manufacturing of control and instrumentation.

Approximately 2,300 employees.

1971-73 General Manager, Nuclear Fuel Department - Responsible for the design, development, and manufacture of nuclear fuels for light water reactor systems and for reprocessing ofirradiated fuel. Approximately 1,600 employees.

1968-71 Manager, Design Engineer, Atomic Power Equipment Department -

g Responsible for design engineering of all nuclear systems being offered by the General Electric Company and for all recent and future project management functions associated with domestic nuclear systems.

630 employees.

1966-68 Manager, Systems Engineering, Atomic Power Equipment Department -

Responsible for conceiving and defining nuclear power plant systems for all requisition and proposal plants and all near-term improvements in nuclear power plant systems.150 employees.

1959-66 Manager, Heat Transfer and Reactor Projects, Atomic Power Equipment Department - Responsible for heat transfer and fluid flow development in boiling water reactors. 30 employees. Gave courses at San Jose rtate and Santa Clara University.

1956-59 Advance Nuclear Specialist, Atomic Power Equipment Department -

Worked on advanced reactor concepts such as fast oxide breeders. Gave lectures to General Electric Engineering Advance Program.

1954-56 Supervisor, Atomic Power Equipment Department - Responsible for the design, safeguard analysis, and development of small atomic power plants and test reactors. Fifteen employees.

1953-54 Knolls Atomic Power Laboratorv. Schenectadv. New York Engineer Analyst - Worked with steam boilers and superheaters.

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Pamru Po.w ome 124612 11004 Page 2

i: O 1950-53 University of Califomia. Berkelev. Califomia Research Engineer - Conducted boundary layer studies of heat transfer in high speed flight.

1950-53 University of Califomia. Berkelev. California Technical' Assistant.

EDUCATION: Ph.D., Mechanical Engineering, University of Califomia at Berkeley,1953 M.S., Mechanical Engineering, University of Califomia at Berkeley,1951 B.S., Mechanical Engineering, Caiversity of California at Berkeley,1949 1

HONORS AND Donald A. Kem Award form the AIChE (1993) i AWARDS:

Walter H. Zinn Award of the ANS Nuclear Power Division (1989) 50th Anniversary Award of the ASME Heat Transfer Division (1988)

Technical Achievement Award, ANS Thermal Hydraulic Division (1987)

Fellow, ANS (1987)

Member, National Academy of Engineering (1974)

Fellow, ASME(1974)

ASME Heat Transfer Memorial Award (1966)

ASME/AIChE Heat Transfer Conference Award (1963)

SPECIAL Vice-Chairman, Management Committee, CBI Nuclear, Memphis,

] ASSIGNMENTS: Tennessee Vice-Chairman, Japan and Italy Nuclear Fuel Manufacturing Companies Member, Editorial Board, Nuclear Engineering and Design Member, Editorial Board, Intemational Joumal of Heat and Mass Transfer, Nuclear Science and Engineering, Heat Transfer in Russia, Heat Transfer in Japan Member, AEC Task Force on Emergency Core Cooling Delegate,1964 Intemational Conference on Peaceful Uses of Atom Chairman, ASME Heat Transfer Division Chairman, National Heat Transfer Conference Committee Consultant, Associated Midwestern University l

Review Committee, Argonne National Laboratory, Reactor Safety Chairman, ANS Thermal Hydraulics Disision PUBLICATIONS: M" Heat Transfer to Constant Property Laminar Boundary-Layer Flows with Power-Function Free-Stream Velocity and Wall-Temperature Free Station Velocity and Wall-Temperature Variation," Journal of AeronauticalSciences,19, No. 5,341-348 (May 1952)

Md R. A. Seban," Skin Friction and Heat Transfer for Laminar Boundary Layer Flow with Variable Propenies and Variable Free-Stream Velocity," Journal ofApplied Mechanics, 20, No. 3, 415-421 (September 1953).

R. M. Drake, Jr., R. A. Seban, D. L. Doughty andM, " Local Heat-Transfer Coefficients on Surface of an Elliptical Cylinder, Axis C Ratio 1:3, in a High Speed Air Stream," Transactions ofthe ASME,75,

\ No. 7,1291-1302 (October 1953). l I

82461211004 Page 3

I O l R. A. Seban, R. M. Drake, Jr., D. L. Doughty, and , "The Effect of 4

Single Roughness Elements in the Heat Transfer om a 1:3 Elliptical Cyhnder," ASME Paper No. 53-A-86, ASME Annual Meeting, November 29 - December 4,1953.

S. Scesa and M " Heat Transfer to Constant-Property Laminar Boundary Layer Wedge Flows with Stepwise and Arbitrary Wall-Temperature Variation," Transactions ofthe ASME, 76, No. 2,279-286 (February 1954).

M"Effect of Large Temperature Changes (including Viscous Heating) Upon Lammar Boundary Layers with Variable Free-Stream Velocity," Journal ofthe Aeronautical Sciences, 21, No. 7, 459-474 l

' Heat Conducting Bodies in Boundary-Layer Flow," Journal of Acronautical Sciences,22, No. 6,440 (June 1955).

M " Integral Methods in Natural-Convection Flow," Journal of  ;

Applied Mechanics, 22, No. 4, 515-522 (December 1955). l M " Heat-Conduction Methods in Forced-Conversion Flow,"

Transactions ofthe ASME,78, No. 8,1672-1636 (November 1956).

R. H. Dempsey, J. J. Jacobson,M and B. Wolfe, " Core and Facilities,"  :

Nucleonics,15, No. 3,44-47 (March 1957).

M " Generalized Correlation of Boiling Heat Transfer," Journal of Heat Transfer, 81, Series C., No.1,37-42 (February 1959).

M, R. A. Fuller and R. O. Niemi, " Heat Transfer to Water in Thin O

Rectangular Channels," Journal of Heat Tranrfer, 81, Series C., No. 2, 129-143 (May 1959).

Md E. S. Beckjord, " Hydraulic Instability in a Natural Circulation Loop with Net Steam Generation at 1000 psia," GEAP-3215, July 15,1959; and ASME Paper No. 60-HT-27.

M Model

", Steam SlipofHeat

" Journal - The Theoretical Transfer, Prediction 82, Series from Momentum C, No. 2,113-124 E olomik, C. L. Swan and A. W. McKinney," Eccentric Rod Burnout at 1000 lbf/in with Net Steam Generation," International Journal of Heat Mass Transfer,5,595-614 (1962).

D. H. Imhoff and M "Importance of High Power Density Boiling Water Reactor Development to Widespread Economic Nuclear Power,"

American Power Conference (1962).

Mand A. P. Bray," Reliability of Bumout Calculations in Nuclear Reactors," Nuclear News, ANS (February 1963).

M" Thermal and Hydraulic Perfonnance of Boiling Water Reactors,"

P r No. 89,1962 Nuclear Congress, June 4-7,1962, New York.

" Prediction of Two-Phase Pressure Drop and Demity Distribution from Mixing Length Theory," Journal ofHeat Transfer, 85, Series C.,

No. 2,137-152 (May 1963).

E. Janssen, Mand J. A. Kervinen, " Investigations of Bumout in an Internally Heated Annulus Cooled by Water at 600 to 1450 psia," ASME Paper No. 63-WA-149.

M " Thermal and Hydraulic Performance of Boiling Water Reactors,"

Nuclear Engineering,60, Part XI, No. 51,110-118 (1964).

I Persons Po-w ome 824612 11004 Page 4

O E. E. Polomik,M and S. G. Sawochka, " Film Boiling of Steam-Water i

Mixtures in Annular Flow at 800,1100 and 1400 psi," Journal ofHeat Transfer, 86, Series C, No.1, 81-88 (February 1964).

, J. Batch and J. Casterline, " Critical Heat Flux Considerations in e ermal and Hydraulic Design of Water-Cooled Nucleer Reactors,"

Third International Heat Transfer Conference, Geneva, Switzerland 1964).

" Prediction of Two-Phase Critical Flow Rate," Journal ofHeat

ransfer,87, Series C, No.1,53-58 (February 1965).

M " Critical Heat Flux in Forced Convection Flow," University of CaIiTornia Lecture Series on Boiling and Two-Phase Flow, at Berkeley (April 1965).

. T. Sorlie, M M. F. Lyons and J. E. Boyden, " Experience with BWR Fuel Rods Operating Above Critical Heat Flux," Nucleonics,23, No. 4, 62-65 and 88 (April 1965).

M " Theoretical Predictions of Fully Developed Adiabatic Two-Phase i

Flow," University of Exeter, England, Symposium on Two-Phase Flow, June 1965.

M " Prediction of Two-Phase Annular Flow with Liquid Entrainment," International Journal ofHeat Mass Transfer, 9,171 -l 88 (1966).

R. L. Crowther, E. A. Evans, W and W. V. Macnabb, " Plutonium l Utilization in Boiling Water Reactor Power Plants," Commercial O Plutonium Fuels Meeting, Washington, D.C., March 1-2,1966.

L/

' M " Turbulent Flow in an Annulus,"JournalofHeat Transfer,89, Series, No.1,25-31 (February 1967).

M Plants

"," Systems Approach IAEA Symposium to Containment on the Containment andDesign Siting of in Nuclear Power Nuclear j Power Plants, SM-89/51, Vienna, Austria, April 3-7,1967.

" Forced Convection Subcooled Boiling - Prediction of Vapor i

o umetric Fraction,"InternationalJournal ofHeat Mass Transfer,10, 951-965 (1967). 1 R. B. Richards and W, " Reactor and Fuel: An Integral System," )

' Electrical World,27-28 (April 20,1970).

C. K. Beck, Paul Tomkins, David McElroy, Wayne Carbiener and M," Nuclear Safety: Responding to the Critics (Round Table Panel)," Power Engineering, Part I,26-35 (May 1970), Part II,25-49 (June 1970). i

, C.Reactors, E. Kent,@ Symposium on Environmental Aspects of Nuclea Stations, International Atomic Energy Agency, New York 4

(August 11,1970).

D. H. Imhoff, M and F. A. Schraub," Thermodynamic Developments in Boiling Water Reactors," XVI Nuclear Congress of Rome (Italy),

Developments of Thermodynamics in the Nuclear Field and Their Contribution to Other Uses, March 25-16,1971.

W A. P. Bray, J. F. Cage and J. E. Kj'emtrup, "Large Boiling Water Reactors - Operations Confirm Design, American Power Conference, Chicago, Illinois, April 21-23,1971.

O g

W "UtilityInvolvement: How Much?" Nuclear Industry, Vol.19, No. 2 (Febmary 1972).

Porscris Power Groe 824612-11004 Page$

A. B. Carson, B. F. Judsor, and J. E. Van Hoomissen, " Fuel

! Reprocessing - A General ., ectric View," 6th Annual Conference of Japan Atorme Industrial Forum, Tokyo, Japan, March 7-9,1973.

" Standardization and Safety Research and Development," AIF i.

hop on Reactor Licensing and Safety, New Orleans, Louisiana, January 25-28,1976.

"Three Mile Island: A Call for Fundamentals and Real Time i ysis," Heat Transfer Engineering, Vol.1, No. 4, April-June 1980.

and J. M. Healzer, Analysis ofAnnular Liquid-Gas Flow with

' nrrainment - Concurrent Vertical Flow in an Annulus, EPRI NP-1563 ,

(October 1980).

M T. L. Gerber, G. Roy and A. Wanner, Review ofProposed Improvements, including Filter / Vent ofBWR Pressure Suppression and PWR Ice Containment, EPRI NP-1747 (April 1981).

i J. M. Healzer and D. Abdollahian, " Prediction of Critical Heat I ux m Ve tical Pipe Flow," Nuclear Engineering and Design, V01. 65, No.1, May 1981.

J. M. Healzer, " Application of Mixing Length Theory to Wavy

' ent Liquid-Gas Interface, Journal ofHeat Transfer, Vol.103, No. 3 (August 1981).

M and D. Abdollahian," Homogeneous Non-Equilibrium Critical Flow Model," InternationalJournal ofHeat and Mass Transfer, Vol. 25, No. 6 (June 1982).

M " Lessons in Reactor Thermal Hydraulics from Operating Plant i

' Transients," Proceedings on Thermal Hydraulics of Nuclear Reactors (1983 .

! M )" Historical Perspective of Thermal Reactor Safety in Light l

Reactors," Proceedings ofIntemational Reactor Safety (1986). i M C. B. Johnson, C. R. Jones and K. Watkins, " Evaluation of Boiling Water Reactor S WR) Mark I Containment Failure Due to Contact with Molten Corittn," 6th National Congress of Heat Transfer, Bari, Italy (June 1988).

M G. Lellouche and R. May, " Elements of Uncertainty and Meaning i of 95% Probability Level for LOCA/ECCS Analysis," EPRI Workshop, i

Can0 ridge, Mass. (August 1988).

B. E. aor yack, et al., " Quantifying Reactor Safety Margins - Part 1:

An Overview o the Code Scaling Applicability, and Uncertainty

' Evaluation Methodology," Nuclear Engineering and Design 119, North Hc.lland, pp. 1-15 (1990).

G. E. Wilson, et al., " Quar.tifying Reactor Safety Margins - Part 2:

Characterizauon o important Contributors to Uncertainty," Nuclear Engineering and Design 119, North Holland, pp. 17-31 (1990).

W. Wulff, M et al., " Quantifying Reactor Safety Margins - Part 3:

Assessment and Ranging of Parameters," Nuclear Engineering and Design 119, North Holland, pp 33-65 (1990).

G. S. Lellouche, et al., " Quantifying Reactor Safety Margins -

Part 4: Unce ty Evaluation ofLBLOCA Analysis Based on TRAC-PF1/ MOD 1," Nuclear Engineering and Design 119, North Holland, pp 67-95 (1990).

o Parsore Power Grow 824612 11004 Page 6

l 1

!p l y  ;

4 N. Zuber, G. E. Wilson,g, et al., "Qauntifying Reactor Safety

Margins - Part 5

Evaluation of Scale-Up Capabilities of Best Estimate l Codes," Nuclear Engineering and Design 119, North Holland, pp 97-107 (1990).

I. Catton, R. B. Duffey, R. A. Shaw, M et al., " Quantifying Reactor Safety Margins - Part 6: Physically Based Method of Estimating PWR

, Large Break Loss of Coolant Accident PCT," Nuclear Engineering and Design 119, North Holland, pp 109-117 (1990).

M " Scaling of Entrainment Fraction During Direct Containment Heating," to be published (1990). Co-author ofAn /ntegratedStructure andScaling Methodologyfor Severe Accident TechnicalIssues Resolution - NUREG/CR-5809 (1991).

M "The Important Role of Thermal Hydraulics in 50 Years of Nuclear Power Applications," Nuclear Engineering and Design 149,1-10 (1994).

M, " Heat Transfer During Molten Corium-Concrete Interactions,"

Nuclear Engineering and Design 151,235-246 (l 994).

Contribution to Books:

Natural Convection Chapter, Liquids Metals Handbook, U.S.A.E.C. (1955).

Fluid Flow Chapter, V01. 2, The Technology ofNuclear Reactor Safety, edited by J. H. Thompson and J. C. Beckerly, MIT Press.

Report ofAdvisory Task Force on Power Reactor Emergency Cooling,

(,.,) U.S.A.E.C. (1967).

v Proceedings of the 1964 Heat Transfer and Fluid Mechanics Institute,

{' edited by Warren H. Giedt and M Star. ford Press.

4 d

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Prione Po ome 824612 11004 Page 7 J

/--

(D w) Risk Assessment Physicist and engineer with a background in research, operations support, engineering, analysis, and executive management. Ph.D. thesis on unified systems safety analysis first advocated what is now known as probabilistic risk assessment (PRA). Built the first consulting team to perform 4

the initial comprehensive and quantitative risk assessments (QRA) for the commercial nuclear power industry. Major contributor to the analytical methods and thought processes employed in PRA. Prime mover in elevating risk assessment to a science and engineering discipline that has had a major impact on management culture and the performance oflarge, complex engineered systems. Served as general chairman of several national technical society meetings and founder of the Southem Califomia Chapter of the Society for Risk Analysis. U.S. representative on several international panels and delegations offering technical advice to foreign nations including 4

Eastern Europe. Extensive experience as an expert witness in hearings related to risk and safety.

EXPERIENCE: PLG. Inc.

1975 to Present President, Chairman of the Board, and Chief Executive Officer of a consulting firm of engineers, applied scientists, and management consultants with offices in Newport Beach, California; Bethesda, Maryland; Encinitas, California; Albuquerque, New Mexico; and Tokyo, Japan.

1957-75 Holmes & Narver. Inc.

Key positions held included member of Board of Directors; President, Nuclear and Systems Sciences Group; Senior Corporate Vice President; p Vice President, Science and Technology, The Resource Sciences

} Corporation, Tulsa, Oklahoma (parent company to Holmes & Narver, Inc.).

1955-1957 Atomic Barcy Commission. Washincton DC Physicist.

1952-54 Phillins Petroleum Comnany (Atomic Energy Commission Contractor)

Physicist - National Reactor Testing Station, Idaho.

EXPERTISE: Nuclear Energy Thought leader and leading practitioner of PRAs of nuclear power plants.

Consultant in risk, reliability, engineering analysis, and management analysis of nuclear power plants. Directed more than 35 nuclear power plant large scope PRAs. Served on numerous national and international advisory groups, panels, and delegations connected with nuclear plant safety and engineering. Vice Chairman ofNational Academy of Sciences' Board on Radioactive Waste Management. Member of the Waste Isolation Pilot Plant Committee, the Committee on Separations Technology and Transmutation Systems, the Committee on Environmental Management Technologies, and the Committee to Review Risk Management in the U.S. Department of Energy's Environmental Remediation Program.

e Parsons Power Group 824612-11004 PageI

Aerospace Researched space and defense methods in safety and reliability and other assurance sciences. Served on National Research Council's Committee on Space Shuttle Criticality Review and Hazard Analysis. Risk and safety consultant to National Aeronautics and Space Administration's Associate Administrator for Safety, Reliability, Maintainability, and Quality Assurance. Course Director of the American Institute of Aeronautics and Astror.autics Annual Course on Quantitative Risk Assessment and i Management. Team leader of risk and safety analyses for military aerospace  :

systems and study director of QRAs of space shuttle subsystems. Facilitator i at the national technical society level for technology exchange in risk and l safety for the aerospace, nuclear, defense, and chemical industries. Private pilot.

4 Chemical Process I Member of technical startup and operations team for the world's first chemical reprocessing plant for highly enriched nuclear fuel. Instigator of quantitative risk assessment methods for chemical process plants.

Researched risk and safety analysis techniques for application to chemical plants. Directed numerous risk assessment efforts i alving a wide variety of chemicals, chemical processes, and refinery ope aions. Directed j independent oversight team during restart and early operation of a chemical process plant critical to the nuclear fuel cycle. Risk and safety consultant  :

and advisor to chemical plant owners and operators. Served on National Academy of Sciences' Committee on Army Chemical Stockpile Disposal Program. l Academic Adjunct Professor, University of California, Los Angeles.

Lecturer, Annual Reactor Safety Course, Massachusetts Institute of Technology.

Chairman, Associated Universities Visiting Committee for the Brookhaven National Laboratory Department of Nuclear Energy.

Chairman, Industrial Liaison Committee, Nuclear Engineering and Engineering Physics Department, University of Wisconsin.

Member, External Advisory Group, University of Wisconsin Center for Human Performance in Complex Systems.

Served on and chaired many accreditation teams evaluating engineering programs at universities throughout the U.S.

O Patens Power Greg 824612 11004 Page 2

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O i Extensive short course, seminar, workshop, and committee assignments at I universities, government agencies, corporations, and other institutions, such  !

as the U.S. Department of Energy, the North Atlantic Treaty Organization, l United Kingdon's National Center of Systems Reliability, the Electric '

Power Research insutua and the Governor of California's Emergency Task Force on Earthquake Prepednesi.

Member, National Research Council's Working Group; U.S.-Japan Joint Task Force on Engineering Education.

EDUCATION: Ph.D., Engineering and Applied Science, University of Califomia, Los Angeles,1968 M.S., Engineering, University of Califomia, Los Angeles,1962 j U.S. Atomic Energy Commission Grant-in-Aid, Oak Ridge School of

, Reactor Technology,1954-55 B.S., Physics, Brigham Young University,1952 REGISTRATION: Professional Engineer, State of Califomia HONORS AND i AWARDS: Recipient of the Society for Risk Analysis' Highest Honor, the Distinguished Achievement Award,1994 Invited by the North Atlantic Treaty Organization to collaborate with 4

Eastern, Central, and Western European scientists to develop new t disarmament technologies,1994-95 Appointed to the U.S. Nuclear Regulatory Commission's Advisory Committe: on Nuclear Waste,1994 Elected to the National Academy ofEngineering,1993

Fellow, American Nuclear Society Fellow, Society for Risk Analysis Fellow, Institute for the Advancement of Engineering Past President, Society for Risk Analysis (an intemational professional

, society),1990 Past President, Los Angeles Maintainability Association Member, Engineering Accreditation Commission, a National Commission of the Accreditation Board for Engineering and Technology Member, American Nuclear Society 14-member delegation to Czechoslovakia and Hungary on Nuclear Power Plant Safety,1991 Selected to attend the United States Atomic Energy Commission's prestigious Oak Ridge School of Reactor Technology to do graduate work in Nuclear Science and Technology,1954 PUBLICATIONS: Published more than 200 papers and reports on risk, reliability, engineering, and technology.

Author of several book chapters and editor of the text, The Analysis, Communication, andPerception ofRisk, Plenum Press,1989.

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Thirty-four years of extensive practical and theoretical knowledge of the thermal and fluid sciences. Experience in thermal power plant design, constmetion, operations and maintenance .

which including engineering project management; supervising engineering personnel for i technical, scheduling and budgetary requirements of design engineering and support ofplant 1 operations; design control procedures; quality / technical aspects of design change packages; I developing and issuing design change packages.

Also experienced in teaching BS level courses in the thermal and fluid sciences and evening review courses for the EIT and Mechanical PE examinations.

EXPERIENCE: PARSONS POWER (formerly Gilbert / Commonwealth) since 1991 1991 to Present Senior Mechanical Engineer, Mechanical Department - Various tasks .

include: j Westinghouse, Orlando - Develop preliminary thennal storage system for Greenhouse heating utilizing co-generation plant for heat source. l System includes pumps, storage tanks and heat exchanger sizing, storage tank heatup/cooldown times along with development of various modes of operation.

Westinghouse, Pittsburgh - Performed design and specification of extemal instrumentation system for In-Situ Reactor Vessel Annealing g Project.

, 'g Cleveland Electric Illuminating Company, Perry Nuclear Plant -

Performed review and verification of RELAP 5 computer modeling of 6

the RHR system for potential water hammer. Transient evaluated was initial operation in the suppression pool cooling mode, LOOP, and subsequent restart of the RHR pumps. Developed Program Plan to meet requirements of Generic Letter 89-13.

Pennsylvania Power & Light Company - Assisted with modification package to installation reactor vessel water level instmmentation line backfill system. Performed calculations, evaluated system components, assisted in PORC presentation of Safety Evaluation.

Prepared modification package to install reactorjet pump holddown beams. Reviewed condenser hotwell sampling system hydraulic problems and developed solutions.

Tennessee Valley Authority (TVA), Watts Bar Nuclear Plant -

Verification of mechanical calculations for CVCS, SIS, RHR and RCS. Verification of FMEA for CVCS, SIS, RHR, RCS and Aux Bldg HVAC. Also, verification of HVAC calculation for Aux Bldg.

South Carolina Electric & Gas Company, V.C. Summer Nuclear Station

- Function as a principal engineer. Site Lead Engineer for installation ofHVAC systems. Performed calculations at site for Unit Uprate.

Lewisburg Prison - Review chilled water system and auxiliaries for operability and design requirement fulfillment.

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Peraru Po oroe 824612.Ilm p g, 3

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GPU Nuclear Corporation, Three Mile Island, Unit 1 - Review SBO Diesel Cooling System for operational capability. Also interfaced with client on Kepner-Tregoe (K-T) decision analysis of cooling RCP seal water prior to injection. Obtained an industrial expert to evaluate refrigerant cooling systems.

TVA, Sequoyah Nuclear Plant - Performed several station modification package reviews and package scope development for charging pump suction H2 Problems, study for positive displacement charging pump replacement, blowoffpanels on MS safety valve vault, and fire rating ofmaterials.

Philadelphia Electric Company, Limerick Nuclear Plant, Generic Letter 89 Resolution of valve closure time influence on resultant surge pressure.

Nuklearna Elektrama, Krsko Nuclear Plant, Slovenia - Interface on PASS, ESW and Mid-Loop plant modification packages. Involved in on-site startup and testing of post-accident gas and liquid sampling systems. Prepared preliminary RFP specification work involving removal of the old and installation of the new Steam Generators.

Baltimore Gas & Electric, Calvert Cliffs Nuclear Plant - Project engineer on K-T decision analysis for positive displacement pump problems and potential resolution of problem.

Assist department personnel with difficult and/or intricate design y problems associated with fluid flow, heat transfer, different working t

fluids, etc.

Advisor, Specialty Groups - Activities include:

Public Service Electric & Gas, Salem, Units 1 & 2 - Interface with HVAC group on calculations. Effort includes verification and senior engineer overview.

Cleveland Electric Illuminating Company, Perry Nuclear Plant - MSIV leakage problem design change package & K-T root cause analysis review.

Florida Power Corporation, Crystal River, Unit 3 - Review and redo of calculation for qualification of 48" butterfly valve disc stop.

Industrial Group Interface Caterpillar, York Plant - Process steam line expansion joint failure.

Procter & Gamble - Heat transfer analysis of paper pellet transfer line.

Kodak Plant - Discharge stack sound emittance.

1989-91 Tennessee Valley Authority. Knoxville. Tennessee Senior Engineer Specialist - Browns Ferry Nuclear Plant, Mechanical / Nuclear Engineering Section - Section consultant on thermal / fluid systems studies and designs; mechanical / nuclear design change packages; mechanical calculations; systems design and operation; O machine design reviews; and ASME B&PV Code Section III and ANSI B31.1 Code Usage.

Parmens Pe er orme 324612 11004 Page 2

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Lead Manager - Oversaw Bechtel Project for the resolution of drawing discrepancies on flow diagrams (10-month duration). Responsible for closure of all mechanical / nuclear design documentation to support Unit 2 restart. Supervised 33 personnel to develop and issue SPAE packages to retum systems to service. Packages included:

70 packages - Mechanical responsibility 15 packages - Support of electrical discipline 2 packages - Support of civil / structural discipline Mechanical / Nuclear Interface with Audit Teams - SSFI Internal Audit on RHR System and SSQE NRC Audit on Core Spray System.

Level I Preparer and Level II Reviewer - 10CFR50.59 Safety Assessments / Evaluations.

Served as Altemate Nuclear Engineering Representative on PORC.

Functioned as the acting lead mechanical / nuclear engineer after hours / weekends on rotating basis and at times during engineer's absence from site during the normal work day.

1987-89 J ouisiana Power & Licht. New Orleans. Louisiana I Supervisor of Mechanical / Civil Design Engineering Group - Nuclear N

Operations Engineering and Construction Department, Waterford 3 Nuclear Station - Group was divided into five units: civil / structural, piping / supports, mechanical systems, building services and mechanical specialties. After taking this position in April,1987, increased personnel from 7 to 23 tecimical and 2 clerical personnel.

The group was responsible for design changes to the plant and supported daily plant operations by answering requests for engineering evaluations, disposition of nonconformances and other appropriate requests. Technically responsible for the scheduling and budgeting of three large projects. These projects included the updating of redlined drawings remaining from construction, tb development of Design Basis Document for BOP and NSSS systems, and Snubber Reduction Program for safety related systems.

Member of emergency response team. Held position as supervisor of the Operations / Engineering Support Group at EOF. Participated in three (3) practice drills and one (1) NRC drill for score.

1984-87 Gilbert /Comrnonwealth. Readine. Pennsylvania Mechanical / Nuclear Engineering Department, Consultant to Department Personnel - Sou'h Carolina Electric & Gas Company, V.C. Summer Nuclear Station, Continuing Services Project - Functioned as principal mechanical engineer. Developed BIT removal work package, feasibility study for the re-establishment of water loop seal on the pressurizer PORV's; evaluated Persons Po or orme 824612 11004 Page 3

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the reactor vessel refueling seal failure, and the consequences ofloss of refueling water on spent fuel cooling and radiation levels from fuel assembles. Responsible for the Quarterly Senior Engineer Overview of SCE&G mechanical NCN dispositions and plant modification package l original 10CFR50.59 and revisions, assuring the design basis of the plant l

was maintained. Interfaced with other disciplines and overviewed G/C work packages, assuring that the design basis of the plant was maintained.

Developed unreviewed safety question evaluations (10CFR50.59) for NCN's.

Project Task Engineer - Virginia Power, Surry Units 1 & 2, Pressurizer Safety Relief Valve Loop Seal Heating Study Project Task Engineer - Tennessee Valley Authority, Bellefonte, Units 1 l

& 2, - Identified and evaluated internally generated missiles inside and l outside containment. '

1983 84 Public Service Electric & Gas, Salem Nuclear Power Station, Quality l Assurance Engineering Group - Reviewed design change packages for '

compliance with design requirements, FSAR commitments and station procedures. Assisted QA Department with the review of engineering rewlutions to significant deficiencies.

b 1982-83 Project Mechanical Engineer - South Carolina Electric & Gas Company, V.C. Summer Nuclear Station, Continuing Services Project - Designed plant modifications, scheduled G/C work, assigned engineering / drafting i personnel to tasks, functioned as liaison with mechanical equipment I suppliers, interfaced with counterpart engineers at the site and office.

1981-82 Project Mechanical Engineer - South Carolina Electric & Gas Company, l 1

V.C. Summer Nuclear Station - Responsible for all mechanical r.nd nuclear system design, related FSAR sections, NSSS liaison, vendor liaison on Mechanical Department procured equipment, resolution of field construction problems and NRC questions. Assigned mechanical / drafting personnel tasks and scheduled / monitored tasks.

1979-81 Lead Nuclear Engineer - South Carolina Electric & Gas Company, i V.C. Summer Nuclear Station - Responsible for NSSS liaison, G/C design systems supporting NSSS operations and safe shutdown from the DBA, related FSAR sections, vendor liaison on Mechanical Department procured equipment, and resolution of field construction problems. Assumed the G/C mechanical resident engineer position at site as necessary.

l 1979 GPU Headquaners, Three Mile Island, Unit 2 - Assisted in the review of mechanical systems and equipment necessary for long term cooling.

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l 1977-79 Resident Engineer - Tabriz Thermal Power Plant Project, Tabriz, Iran -

Prepared and issued daily, weekly, and monthly progress and construction reports; maintained records for the npproval ofprogress payments to the constructor; and petty cash fund for G/C personnel. Assisted in resolution of construction and engineering design problems with the client. Conducted two survey trips of the progress to prepare and condition of the overland j

route (450 miles) for the 300 ton T/G stator.

i 1976-77 Engineering Department Staff Engineer - Developed, improved and '

maintained Design Control Procedures for the design, review, verification and recording of systems and components in nuclear and fossil power plants. The procedures for nuclear work meet the requirements of ANSI 45.2.11.

I 1975-87 Pennsylvania Power & Light, Allentown, Pennsylvania - Conducted after hours EIT review course and ME PE review course.

1975-76 South Carolina Electric & Gas Company, V.C. Summer Nuclear Station -

Responsible for G/C design systems supponing NSSS operations and safe shutdown from DBA, related FSAR sections and specified safety and non-safety related components.

I 1973-76 Conducted an EIT review course for G/C employees.

U 1973-75 Project Mechanical Engineer - Performed preliminary studies, throughout Pennsylvania, to locate suitable sites for supponing 8,000 MW to 20,000 MW combinations of nuclear and fossil generating units.

Project Mechanical Engineer - 800 MW Coal-fired Unit Emironmental Repon - Responsible for the heat dissipation systems, fuel source, flue gas cleanup and noise abatement sections.

Staff Assistant to the Chief Mechanical Engineer - Mechanical / Nuclear Department - Directed preparation of Design Guides.

1972-73 Bettis Atomic Power Laboratory. Westinchouse Electric Comoration. West Mif0in. Pennsylvania Senior Engineer - Responsible for the technical oversight of contractor preparation of necessary specifications to control modifications and maintenance tasks to remove the PWR Core II and install the LWBR Core in the Shippingpon Atomic Power Station.

1969-72 Vircinia Polytechnic Institute and State University. Blacksburc. Vircinia Instructor in Mechanical Engineering - Lectures in thennodynamics, fundamental engineering and FORTRAN IV programming while working toward a Ph D in mechanical engineering. -

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!V 1967-69 McKeescort Camous of Pennsylvania State University Evening Instructor - Taught instmmentation and the ME review for the PE exam.

1966-69 Bettis Atomic Power Laboratory. Westinchouse Electric Corooration. West Mifflin. Pennsylvania Engineer - Pressurized Water Reactor Project - Performed digital computer parametric studies of plant operational response to the effects of a steam generator tube rupture. Performed digital computer studies on how the restriction of primary flow to certain U-tubes in a steam generator would effect the plant's power production capabilities. Witnessed leak rate test and evaluated data on the Shippingport reactor plant containment vessel to qualify the plant for continued operation. Prepared numerous work packages for plant maintenance and modifications.

1964-66 Tamna Electric Company. Tamoa. Florida Engineer, Production Staff- Engineering consultant to the station superintendent and staff concerning operations, maintenance, modifications and spare parts procurement. Performed numerous design changes and maintenance packages including design, procurement, outside contractor liaison and monitored work. Prepared station monthly maintenance reports.

Q(% 1962-63 Vircinia PoNtechnic Institute. Blacksburg. Vircinia Graduate Student in mechanical engineering with the power plant engineering option. Worked 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> per week at the school's power plant. i 1962 Tamoa Electric Comnany. Tamoa. Florida Engineering Trainee - Foundation footing inspector for tower support installation on 230 kV transmission line.

EDUCATION: Ph.D., Virginia Polytechnic Institute and State University,1973 M.S., Mechanical Engineering, Virginis Polytechnic Institute,1965 '

B.S., Mechanical Engineering, Virginia Polytechnic Institute,1962 Additional Courses:

Xerox Management for Motivation, Gilbert / Commonwealth,1982 Kepner-Tregoe Problem Solving & Decision Making Course, TVA, Browns Ferry Nuclear Plant,1990 10CFR50.59 Safety Assessment / Evaluation Course, TVA, Browns Ferry Nuclear Plant,1990 Engineering training courses, Gilbert / Commonwealth,1992-93 l REGISTRATION: Professional Engineer - Virginia (1967) and Pennsylvania (1974)

SOCIETIES

American Society of Mechanical Engineers, Phi Kappa Phi s24612-11004 Page 6

1 PUBLICATIONS: "An Implicit Numerical Solution for the Laminar and Turbulent Flow of an

" Incompressible Fluid Along the Axis of a 90 - Degree Comer," Ph.D.

Dissertation, Virginia Polytechnic Institute and State University,1972.

' " Advanced-Cycle Power Via Coal Gasification," Proceedines of the American Power Conference, Volume 36,1974.

" Design and Development of a Postaccident Sampling System,"

Proceedines of the American Power Conference, Volume 43,1981.

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p Senior Consulting Engineer Over 28 years of power engineering experience in project management, thermal hydraulic / heat transfer analysis mechanical systems evaluations; control systems analysis, testing, process control and instrumentation; nuclear safety and radiological analysis and design.

EXPERIENCE: PARSONS POWER (formerly Gilbert / Commonwealth) since 1973 1985 to Present Project Engineer - Responsible for all nuclear analytical activities involved in preparation of PSAR/FSAR and plant design in radiation protection and shielding, health physics, accident analyses, tiermal hydraulic analyses, dose assessment, equipment qualification, heat transfer, toxic chemical ,

hazards evaluations, turbine missile risk analyses, suppression pool l hydrodynamics, liquid, gaseous and solid radwaste system evaluations and mechanical systems steady state and transient hydraulic analyses for PWR and BWR nuclear power plants.

1996 Pennsylvania Power & Light Company, Susquehanna Steam Electric Station - Perform ECCS strainer debris source term and submerged drag loads for replacement ECCS strainers USNRC Bulletin 96-03.

1994 South Carolina Electric & Gas, V.C. Summer Nuclear Station - Evaluations of thermal response of equipment to postulated high temperatures following postulated steam line break using thermal analyses.

1994 Pennsylvania Power & Light, Susquehanna Steam Electric Station -

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Developed method to detennine expected hydraulic time delay in RV level vent to reference leg modification.

1994 Pennsylvania Power & Light, Susc uehanna Steam Electric Station -

Provided validation of Seismic anc. Hydrodynamic Loads DBD.

1993 South Carolina Electric & Gas, V.C. Summer Nuclear Station - Performed steam generator replacement (power uprate) accident analysis and licensing support.

1992 Tennessee Valley Authority, Watts Bar Nuclear Power Plant - Performed analyses in su port of calculation upgrade program relative to heat transfer and thermal h draulics.

1992 Philadelphia Electric Company, Limerick Generating Station - Performed 89-10 evaluation relative to MOV pressure drop including systems and dynamic time response.

1991 Tennessee Valley Authority, Sequoyah Nuclear Power Plant - Prosided direction and instrumental m coordinating the Sequoyah main steam valve vault blow-off roofmodification.

1981-85 Supervising Engineer - Thermal Fluid Analysis - Coordinated and developed areas related to thermal-hydraulics, including multi-phase flow, containment integrity, subcompartment integrity, suppression pool hydrodynamics, eclulpment qualification pressure and temperature, pipe rupture and operational transients.

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1975-81 Nuclear and Safety Analysis Engineer - South Carolina Electric & Gas Company, V.C. Summer Nuclear Station and Korea Electric Company, Ko-Ri Station, Units 1 & 2 (600 MW)- Thermal hydraulic analysis work involving containment pressure / temperature response to LOCA and main j steam line break. <

Nuclear and Safety Analysis Engineer - V.C. Summer Station and The Electric Utilities of Croatia and Slovenia, KRSKO, Unit 1 (600 MW)-

Performed thrust and jet impingement force analyses, subcompartment j pressurization analyses and equipment qualification thermal analyses. l 1973-75 Control Systems Engineer - Rochester Gas & Electric Corporation, R.E. '

Ginna Nuclear Station and Florida Power Cor wration, Crystal River, Umt 3 (R.G.1.97 neutron flux monitoring system) - 1 signed feedwater recirculation control schemes, sign of radiation monitoring system for high temperature gas cooled reactor and instrumentation and control design for HVAC system and standby auxiliary feedwater system. Work included preparation of ec uipment specifications, design specifications, request for l

proposals and bi is ofmaterial. Involved with vendor selection and contract award.

1968-72 Pratt & Whitney Aircraft. West Palm Beach. Florida Control Systems Engineer - Computer Analysis ofhydromechanical and electronic control systems for aircraft engines.

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Experimental Test Engineer - Responsible for specification for and hardware test of aircraft engine hydromechanical controls.

1964-66 Pan American World Airways. Cane Kennedy. Florida Co-op Student - Responsible for data reduction in geodetic s'avey group.

EDUCATION: B.S., Engineering Science, Florida State University,1967 M.S., Engineering Science, Florida State University,1968 M.E., Nuclear Engineering, University of Florida,1973 REGISTRATION: Professional Engineer - Pennsylvania (1976)

SOCIETIES: American Nuclear Society PUBLICATION: " Marine Environmental Interaction with an Offshore Nuclear Power Plant,"

Coauthor, American Nuclear Society,1976.

" Determination of PWR Safety Valve Discharge Piping Forces with RELAPS/ MOD 1," Coauthor, American Nuclear Society,1982.

" Analysis of BWR-RHR System Water Hammer Following Coincident LOCA and LOOP Events," American Nuclear Society Annual Meeting, 1987.

"Using Thermal Lag Analyses to Justify Existing Insulation Resistance Data," G/C Tech Notes, July 1994.

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FEB 11 '97 06:16PM PARSONS POWER NPU P.13 r

l o) t Senior Mechanical Engineer Over 38 yens of experience in mechanical, aerospace and plant engineering activities invohing design and stress analysis; management of design and analysis ofindustrial facilities, including power piping and pipe support systems; airframe design and analysis, aircran structures and systems maintenance and operation; and manufacturing engineering including metal-working, fabrication, experience, plant safety and personnel administration. Seventeen years of management including supervision of up to 100 professional and technical personnel for nuclear and fossil plant piping enginecting projects involving new plant design, continuing services, plant life extension, and military aircraft maintenance and modification.

EXPERIENCE: P ARSONS POWER (formerly Gilben/Commomvealthbince 1973 1985 to Present Piping Engineering Consultant - Senior consultant and project engineer for stress analysis and support design for power and process plant piping systems; development of analysis and design procedures; on-site investigation and resolution of piping and support problems for fossil and nuclear plants. Senior project engineer for fossil plant piping system evaluations to support plant life extension programs at Pennsylvania Electric Company, Pennsy)vania Power & Light Company, Metropolitan Edison Company, Baltimore Gas & Electric Company, New York State Electric &

Gas Company, Potomac Electric Power Company, South Carolina Electric

& Gas Company, Northeast Utilities, Arkansas Power & Light, Egyptian Electric Authority, Santee Cooper, and GE Transportation Systems (Erie).

p Forensic Engineering - Assignments included:

\'J Product liability litigation consultant on centrTugal clutch design and operation Contract litigation consultant for U.S. Navy Facilities Cormnand on buried piping installation Litigation consultant on piping systems for Bethlehem Steel Corporation.

Consultant - various nuclear plants operated by General Public Utilities Nuclear (GPUN), Cleveland Electric, Florida Power and South Carolina Electric & Gas - Helped resolve piping system operational and code reconciliation problems which involved flow transients, pump vibration, buried piping analysis, non-metallic pipe failures.

Senior Engineer - Tennessee Valley Authority, nuclear projects:

Piping Engineering Consultant - Sequoyah Nuclear Power Plant, Restart Effort - Provided technical guidance on-site (three months) to mechanical and civil engineers to resolve Unit 2 power piping operational and documentation problems; directed piping and support walkdowns and pipe stress re-analysis of Unit I main steam piping. Participated in resolution of concerns about Unit 2 alternate analysis review program.

Lead Engineer - Browns Ferry Nuclear Plant - FS AR commitment review

for seismic qualifications of mechanical and electrical systems.

Developed and revised ana'esis procedures to qualify flexible couplings

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V and buried piping for Sectici !U compliance.

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O Developed and revised analysis procedures to qualify flexible couplings and buried piping for Section III compliance. l Yellow Creek Nuclear Plant - Co-author of attemate analysis and suppon spacing criteria document (1979).

1982-85 Manager, Piping Stress Analysis - Managed piping stress analysis activities for nuclear and fossil power plants, including thermal, deadload, seismic l and other dynamic stress and load analysis ofnuclear safety class 1,2, & 3 and non safety piping. Provided piping stress analysis continuing services for nuclear, fossil and process plants. Served as consultant for life-extension of piping and pipe suppon systems for fossil plants.

1974-82 Manager, Piping Engineering (Fossil) - Supervised thermal flexibility, dynamic and deadioad analysis of power cycle piping and design of pipe supports, restraints and supplementary structures for several fossil-fueled power plants designed per ASME B31.1 and B31.3 codes. Developed special stress analysis techniques for fossil and nuclear plants, including seismic analysis of buried nuclear safety class piping in accordance with Section Ill, ASME Boiler and Pressure Vessel Code.

1973-74 Senior Piping Engineer - Designed and analyzed power piping and support p systems for fossil acd nwicar plants. Developed engineering design

( standards and provided in-house training to pipe support designers in stress analysis and strength ofmaterials.

1985-86 The Pennsylvania State University merks Camous)

Pan time Instructor - B.S. (Engineering) credit courses in engineering experimentation, graphics and computer literacy (Fall 1985, Spring 1986).

Member, Berks Campus Technical Advisory Council since 1974.

1972 to Present Brecknock Townshio. Berks County. Pennsylvania Planning Commission, chairman since 1982, secretary 1976-1982; Vacancy Board, chairman since 1980.

1969-73 Albert Seisler Machine Comoration. Mohnton. Pennsylvania Plant Engineer and Mechanical Power Transmission Consultant - Performed structural design and construction supervision of a 3000 sq. ft, steel-framed, highbay machine shop with overhead crane capacity of 20 tons. Canied out complete design and sales engineering for centrifugal clutches to 2000 hp capacity. Served as personnel and marketing manager for 24-employee machine shop with responsibility for apprenticeship program and Occupational Safety and Health Administration (OSHA) compliance.

, 1970-71 The Pennsylvania State University merks Camous)

Pan-time Instructor - Taught unit courses in design of machine elements, jigs and fixtures.

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r 1965-69 Air Force Logistics Command. Kelly Air Force Base. Texas Supervisory Aerospace Engineer - Section chief; design and modification engineering for aircraft ejection seats, escape systems, parachutes and cargo handling and tie-down equipment. Managed Texas A&M University's Graduate Engineering Extension Program at the base.

1959-65 Air Force Locistics Command. Olmr*1d AFB. Pennsylvania Aerospace Engineer - Lead engineer for airframe modification design, aircraft accident investigation and damage surveys.

1957-59 Bell Aerosystems Corooration. Niacara Falls. New York Aerospace Stmetures Engineer - Airframe and missile launch gear stress analysis.

1956-57 Lockheed Aircraft Corporation. Van Nuvs. California Associate Engineer - Missile airframe design.

EDUCATION: B.S., Mechanical Engineering, The Pennsylvania State University,1956 M.M.E., Texas A&M University,1969 Additional Courses:

Machine Design, University of Southern California,1956

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Intensive Spanish, Our Lady of the Lake College, San Antonio, Texas, 1966 Finite Element Analysis Seminar, Bucknell University,1976 AISC-Simplified Steel Design, Gilbert / Commonwealth,1976 Managing for Motivation, Gilbert / Commonwealth,1977 Assertive Management Seminar, Temple University,1984 Project Management, Gilbert / Commonwealth,1984 Proposal Writing, Gilbert / Commonwealth,1987 Total Quality Advantage, Gilbert / Commonwealth,1992 REGISTRATION: Professional Engineer, Mechanical - Pennsylvania (1965) and Maryland (1980)

National Engineering Council Certificate (1976)

SOCIETIES: National Society of Professional Engineers (President, Reading Chapter of PSPE,1982-83; director 1975-78,1993-present)

American Society of Mechanical Engineers (Member of ASME B31.1 Power Piping Code Committee; member of the Operations, Applications and Components Committee of the Pressure Vessel and Piping Division; developer and chairman of sessions at the ASME PVP Conferences in 1988,1989,1990,1992,1993, and 1994).

American Society of Civil Engineers (Member of Dynamic Analysis Committee 1979-1987, Director, Reading Subsection 1988-90)

PUBLICATIONS: The following are representative of over 30 publications:

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Co-author, " Pipe Support Problems in Fossil Power Plants - Identification and Correction," ASME PVP Vol. 53, ASME Pressure Vessels and Piping Conference, Denver, June 1981.

Co-author, " Fatigue Failures in Power Plant Headers - Two Case Histories,"

AShE PVP Vol. 62, AShE Pressure Vessels and Piping Conference, Orlando, June 1982.

Co-author, " Constant Supports - How Constant?" AShE PVP Vol. 90, ASME Pressure Vessels and Piping Conference, San Antonio, June 1984.

" Fossil Plant Pipe Hanger Surveys - Three Case Histories," AShE PVP Vol. I12, ASME Pressure Vessels and Piping Conference, Chicago, July, 1986.

"The Art of Pipe Support Adjustment," ASME Paper 87-PVP-12, Fifth National Congress on Pressure Vessels and Piping Technology, San Diego, June 29-July 2,1987.

Co-author, " Pipe Suppon Optimization in an Operating Fossil Power Plant,"

ASME PVP Vol.169, ASME/JSME Pressure Vessels and Piping Conference, Honolulu, July 23-27,1989, pp.125-135.

" Simplified Analysis of Steamhammer Pipe Support Loads," ASME PVP p Vol.169, ASME/JSME Pressure Vessels and Piping Conference, s Honolulu, July 23-27,1989.

" Pump Problems and Piping Panicipation - Real and Alleged," Current Practices and Trends in Mechanical Failure Prevention, The Vibration Institute,1990.

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" Control of Pipeline Dynamics with Disk Spring Restraints," ASMEJournal ofPressure Vessel Technology, Vol.113, May 1991.

Co-author, " Identification and Elimination of Problem Exp msion Joints in Power Plant Piping," ASME PVP Vol 218, ASME Pressure Vessels and Piping Conference, San Diego, June 23-27,1991. 1

" Restrained Underground Piping - Some Practical Aspects of Analysis and l Design," Proceedings of the Third U.S. Conference on Lifeline i

Earthquake Engineering, UCLA, August 22-23,1991, TCLEE I Monograph No. 4. '

1 Co-author, " Elbow Support Lug Attachment Weld Cracks - A Case  !

History," ASME PVP Vol. 236, ASME Pressure Vessels and Piping I Conference, New Orleans, June 21-25,1992.

"More Pipe Suppon Problems in Fossil Power Plants - Identification and 1

Correction," ASME PVP Vol. 255, ASME Pressure Vessels and Piping i Conference, Denver, Colorado, July,25-29,1993.

l "Supponing a Riser - Some Do's and Don'ts," ASME PVP Vol. 282, ASME i O Pressure Vessels and Piping Conference, Minneapolis, MN, June 19-23, 1994. j V '

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g Mechanical Engineer i

Twenty five years of project engineering / project management experience in design of fluid systems, primarily for steam electric utility facilities, covering a broad range of systems, ,

including auxiliary and main steam; condensate and feedwater; open and closed cycle coohng l water; nitrogen, instrument air and service air supply / distribution; LP gas and fuel oil storage, i

combustible gas control / hydrogen recombination; radioactive / hazardous liquid, solid and i gaseous waste treatment and disposal; and chemical addition. Specific responsibilities have included system conceptualization; cost / benefit studies; system configuration and layout; preparation of technical procurement specifications for many types ofprocess equipment (e.g.,

tanks, heat exchangers, pumps, filters, demineralizers, evaporators, instrumentation, and process  ;

controllers); manual and computerized thermal / hydraulic analyses; sizing of control valves, l pumps and heat exchangers; technical bid evaluations; preparation ofsystem descriptions and 1 operating procedures; and installation startup and testing support. Management experience hr.s ranged from serving as task manager to lead project engineer to project manager. The magnitude of projects worked on has also covered a wide range, from small retrofits to large, i multidiscipline, multi-million dollar installations requiring several thousand hours of engineering effort. ,

EXPERIENCE: PARSONS POWER since 1996 1996 to Present Consultant / Lead Mechanical Engineer - Florida Power Corporation, Crystal River Unit 3 - Perform a comprehensive single DC failure analysis during a l postulated LOOP /LOCA event. Work involved detailed study and ,

understanding of some 25 plant systems required for safe shutdown l following a LOCA event and an evaluation of the effect of a single failure b of each DC powered or controlled component in each of these systems on plant response to a LOCA.

1994-96 Self-Emnioved Residential Construction Contractor Provided full range of services from design and construction management to actual construction of custom homes and additions. Experienced in all '

phases of this type of construction, including siting, surveying, excavation, concrete and masonry, framing, electrical, heating, plumbing, and l supervision of trades.

1981-94 Gilbert / Commonwealth. Inc.. Readinc. Pennsylvania 1994 Task Manager - Cleveland Electric Illuminating Co., Peny Nuclear Power Plant - Formalization of program plan for control of Zebra mussel / Asiatic clam infestation of service water systems.

1992-94 Seconded Field Engineer - Public Service Electric & Gas, Hope Creek Nuclear Power Plant - Duties included engineering support for modification and upgrade of four liquid radioactive waste evaporators in preparation for startup after being mothballed since mid-1980's.

1991-92 System Engineer - Advanced Neutron Source (ANS) Project - Developed all aspects of conceptual system design for radioactive, hazardous, mixed, and p conventional liquid, solid and gaseous waste systems for the ANS facility to y be built at Oak Ridge National Laboratory (ORNL).

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1990-91 Task Manager - Florida Power Corporation, Crystal River, Unit 3 -

Technical lead and interdisciplinary coordinator for a project to develop computerized hydraulic models for all safety-related cooling water systems.

These models were then used to evaluate adequacy of head margin on l existing pumps to meet ASME Section XI requirements and served as the l calculation of record for all future plant modifications.

1989-90 Project Engineer - Rochester Gas & Electric, R.E. Ginna Nuclear Power l Plant - Responsible for design and management of miscellaneous plant l modifications and improvements. The most significant of these was providing safety reviews and evaluations in suppon of a complete as-built redraw ofnearly 200 system P& ids. l 1989 Task Manager - GPU, Three Mile Island, Unit 1 - Task manager responsible for design and day-to-day management of several plant modification projects, including redesign and construction of radwaste solidification facility, relocation / redesign of hot instrument repair shop and chemistry laboratory, design / construction of reactor coolant pump local / remote motor bearing lube oil fill system.

1988-89 Assistant Project Engineer - Philadelphia Electric Company, Peach Bottom Atomic Power Station - Group leader for Mechanical Engineering Department support of the restan effon after USNRC ordered shutdown due L to numerous safety violations. Responsible for design of miscellaneous plant modifications and upgrades, answering field engineering / construction questions, aad perfonning safety analysis reviews.

1987-88 Field Engineer - Seconded engineer at PECo corporate offices. Responsible for various liquid and solid radwaste system modifications and upgrades at Limerick and Peach Bottom nuclear power plants.

, 1987 Task Manager / System Engineer - GPU, Three Mile Island, Unit 1 -

Technical lead and interdisciplinary coordinator for an innovative project involving the redesign and modification of the seating surfaces of numerous containment isolation valves. An estimated savings of $1 million was achieved by modifying the existing valves in place rather than installing new valves.

1986-87 Project Engineer - Responsible for design and management of site preparations at three Commonwealth Edison power plants for temporary installation of a demonstration mobile radioactive waste incinerator built by Aerojet Nuclear under contract to U.S. Department of Energy (DOE). Work included layout / design of the equipment pads in the yard, design of suppon services (water lines, electrical supply and LP gas), procurement suppon for equipment and materials, preparation of an SAR, and resolution of NRC comments on design.

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O 1985-86 Senior Project Engineer / Project Manager - Commonwealth Edison  !

Company, Zion (PWR) Nuclear Power Plant - Responsible for design and management of an $8 million project to decontaminate and decommission an existing waste evaporator and to retrofit a new forced circulation '

crystallizer and related support services.

1983-84 Project Engineer - DOE, Waste Management Division - Responsible fer design and management of conceptual design and licensing demonstration of a waste incineration facility.

1 1981-82 Project Engineer - ORNL - Lead investigator on L project to develop a I comprehensive 10-year plan for the upgrade of ORNL's existing radioactive waste treatment facilities.

1980 Bechtel Power Corocration. Gaithersburg. Maryland Site Liaison Engineer - General Public Utilities Corporation, Three Mile Island, Unit 2 - Field assignment as group supervisor in charge of efforts to develop plans for decontamination of reactor and auxiliary buildings. Also provided liaison services between field constmetion group and home office design group for various plant modifications required during cleanup efforts following TMI accident.

O Q' 1972-79 Gilbert /Commonwealth. Reading. Pennsylvania Radioactive Waste Management Consultant - Member of Radwaste Management Group responsible for all in-house projects in areas related to radioactive waste processing, management, and disposal. Responsible for the conceptual design of a five year on-site storage facility for solid radwaste. Also, member of the AIF committee which studied alternatives for on-site storage of solid radioactive waste and the ANSI working group for standards on liquid and gaseous radioactive waste systems. Involved in a study for Ontario Hydro to evaluate various methods for treatment and solidification ofliquid wastes from heavy water reactors. Other projects included:

Florida Power Corporation, Crystal River Unit 3 - Economic / technical evaluation of various options for volume reduction, solidification and storage ofradioactive waste.

On-site waste management reviews conducted for several utility clients.

ORNL-sponsored in-depth survey ofstate-of-the-art techniques for volume reduction of radioactive waste.

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Consultant - Metropolitan Edison Company, Three Mile Island Station, Unit 2 Recovery Site Support - Responsible for design and  ;

construction of high activity waste staging facility, fabrication and i field testing of a shielded high activity waste transfer bell, and j miscellaneous waste management technical support. l System Engineer - Cleveland Electric Illuminating Company, Perry (BWR)

Power Plant - Responsible for detailed designs of numerous process piping systems, including liquid, solid, and gaseous radwaste; sampling; containment spray; containment vacuum relief; and combustible gas control.

Responsibilities included development of system diagrams and system 3

descriptions; sizing equipment; writing equipment procurement l

specifications; evaluating vendor proposals; supervision of drafting; and '

providing information for safety analysis and environmental reports.

1971-72 Sarcent and Lundy Encineers. Chicaco. Illinois Mechanical Engineer, Project Level - Nonhem Indiana Power Company, Bailly Nuclear Power Plant (BWR) - Responsible for detailed design of numerous process piping systems such as main steam, condensate, and feedwater.

/ 1967-68 h] Franklin Institute Research Laboratories. Philadelchia. Pennsylvania Co-op Student - Performed computerized stress analysis of such items as reactor vessels and heavy machine pans. Duties included the formulation of mathematical models, preparation of computer code input, and analysis of computer output.

1966-67 Ebasco Services Inc.. New York. New York Co-op Student - Pennsylvania Power & Light Company, Brunner Island Coal Fired Power Plant - Construction Engineer's Assistant. Duties included drafting, quantities computations, surveying, concrete batch plant inspection, and supervision of concrete placement.

1965 Co-op Student - Pennsylvania Department of Forests and Waters, Harrisburg, Pennsylvania - Design Engineer's Assistant. Involved in the design of dams and other flood control projects. Duties included drafting and quantities calculations.

EDUCATION: B.S., Mechanical Engineering, Drexel University,1969 M.S., Nuclear Engineering, The Pennsylvania State University,1971 Additional Courses:

Radioactive Waste Management for Nucler.r Power Reactors, Georgia j Institute of Tecimology,1974 i

!c SOCIETIES: Member, American Society of Mechanical Engineers i k.

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lnV PUBLICATIONS: "An Architect Engineer's Approach to ALAP in Operations," presented at

Annual ANS Conference, Tucson, Arizona, August 1975.

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" Overview of Liquid Radioactive Waste Management for Light Water Reactors," presented at IAEA Course in Safety Analysis Review, ANL, l October 1978.

" Volume Reduction: A Shon-Term Answer to the Mounting Radwute Problem," Power Magazine, July 1980, Vol.124, No. 7.

" Licensing Retrofit Incinerators at Commercial Nuclear Power Plants,"

? resented at ANSI Winter Meeting, San Francisco, California, November 1983.

"Backfitting an Advanced Radwaste Volume Reduction System Employing Modeling Technic ues," presented at Waste Management 1984, Tucson, Arizona, March 1984.

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Senior Mechanical Engineer V'/m) '

Thirty-three years of experience in engineering and design of nuclear and non-nuclear facilities for power generation and other purposes, covering a wide range of technologies. Twenty years of experience in supervision of up to 50 professional and technical support personnel on nine design projects and six engineering studies, with construction costs ranging from $15 million to several billion dollars.

EXPERIENCE: PARSONS POWER (formerly Gilbert / Commonwealth) since 1971 1996 to Present Lead Engineer - Advanced Circulating Pressurized Fluid Bed Combustor  !

(ACPFBC) Repowering Study, U.S. Department of Energy (DOE), Office of Fossil Energy - Responsible for engineering and design in two conceptual designs, each involving ACPFBC repowering of an existing fossil steam power plant. One design is for Carolina Power & Light Company, repowering two 100 MWe units of the L.V. Sutton Station; the second design is for Duke Power Company, repowering one unit of the Dan River Station.

1994 to Present Task Manager - Advanced Technology Repowering, Clean Coal Technology Demonstration Program, (DOE), Morgantown Energy Technology Center - Supervise analysis, design, and economic evaluation of a wide range of clean coal technology options for repowering existing fossil-fired power plants. The study includes atmospheric and pressurized A fluid bed combustors (bubbling and circulating bed types), integrated V

gasification combined cycles, and refueling with a process derived fuel.

Performed evaluations of combustion turbine integration and matching to these clean coal technology and gasifier systems.

1993-96 Task Manager - Reference Plant Design, Clean Coal Technology Demonstration Program, U.S. Department of Energy, Morgantown Energy Technology Center - Supervised design and economic evaluation for three reference clean coal power plants, including a 400 MWe pulverized coal-fired plant with flue gas desulfurization; 350 MWe pressurized fluidized bed combustor plant; a 400 MWe low sulfur process derived fuel fired plant with duct injection flue gas desulfurization. These designs, along with a previously prepared 400 MWe atmospheric fluid bed plant design, formed a reference basis for DOE and electric utility economic and technical comparisons.

1994 Mechanical Engineer - Big Rock Point Decommissioning Study, Consumers Power Company - Performed technical evaluation and prepared sections of a technical report for the dismantlement, segmentation, packaging and shipping of the Nuclear Steam Supply System for Consumer Power Company's Big Rock Point Nuclear Power Plant, Charlevoix, Michigan. The Big Rock Point plant is a 70 Mwe Boiling Water Reactor of early vintage, planned to operate until the end ofits Operating License in the year 2000. The technical report provides a detailed plan and rationale for the disposition of highly radioactive components, with consideration of economic, shipping, and ALARA issues, and is the basis for Consumer Permans Power Groe 824612-11004 PageI

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1 l0 Power Company's submittals to the NRC and Michigan state PUC for j necessary approvals to proceed.

1991-93 Senior Project Engineer - Advanced Neutron Source Project, U.S.

l Department of Energy, Oak Ridge National Laboratory - Supervised design  ;

ofmechanical systems for the ANS Facility, including cooling water, gases, 1 vacuum, wastes (conventional and radioactive), emironmental control and ,

fire protection. Design requirements include passive cooling capability for 1 safe shutdown, and compliance with NRC regulations. ANS was a $2.7 billion steady state neutron generating research facility that uses a heavy water cooled and moderated reactor.

1987-92 Engineering Manager - Bethel Valley Low-Level Waste Project, U.S.

Department of Energy, Oak Ridge National Laboratory - Super ised 25 professional and technical personnel in the design of a low level radioactive waste collection and transfer system meeting current environmental j regulations. Supervised preparation of design, installation and stmetural  !

integrity assessments for low level waste tank systems; responsible for  !

Professional Engineer certification of the assessments. Construction budget  !

was $35 million, with 24-month design and constmetion schedules.

1986-91 Senior Task Engineer - South Carolina Electric & Gas Company,

( ,) V.C. Summer Nuclear Station (900 MW PWR)- Provided senior level V technical support for ongoing plant operations including:

Plant Rerate Feasibility Study, including steam generator replacement.

Preparation of detailed Design Basis Documents for emergency feedwater, steam generator blowdown and spent fuel cooling systems; in-depth technical review of six other design bcsis documents.

Technical support to SCE&G, Independent Safety Evaluation Group (ISEG), providing in-depth technical review of as-built safety-related systems to assure proper design bases and functions.

Task manager for design, procurement and installation of a steam generator wet layup system.

1986 Project Manager - Corps of Engineers, Omaha Power District, Deep Basing Planning Studies - Supervised conceptual design and life cycle cost evaluation of diesel engine / gas turbine power plants, electric substations and power distribution systems. Power plants evaluated in study were located on the surface, and generated and distributed from 10-30 MWe to a Deep Base. Supervised 10 professional personnel in this $160,000 study.

l 1985 Project Mechanical Engineer - Westinghouse Electric Company, proposed l

power plant (1000 MWe PWR), Peoples Republic of China - Supervised engineering and design of mechanical and nuclear systems. Pre-award i

73 effort included support of accelerated design and construction schedule.

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The plant incorporated state-of-the-art design concepts for a Westinghouse PWR.

Project Manager - U.S. Department of Energy, Secure Military Power Plant - Supervised conceptual design of a 10 MWe nuclear power plant.

Scope included integrated design of complete facility in conjunction with prime contractor, GA Technologies, for Idaho National Engineering Laboratory. Supervised 10 professional and technical personnel in a i

$140,000 effort. l 1982-84 Engineering Supervisor- U.S. Air Force, Ballistic Missile Office, Power Systems Deep Basing Support Systems and Facilities Integration Program -

Directed technical evaluation and analysis of alternative power generation ,

technologies and conceptual design ofintegrated power systems. I Evaluations included reliability, availability, maintainability, life cycle costing and hardenability for closed cycle heat engine power plants (diesel,

' gas turbine) with exhaust gas recycle, closed cycle fuel cell power plants (alkaline and phosphoric acid technologies), and small nuclear power plant technologies. Power plants ranged in size from 50 kWe to 10 MWe.

Supervised a multi-discipline team of 15 professional personnel.

1981-82 Engineering Manager - Allis Chalmers Corporation, KILnGAS commercial O

1 module - Supervised engineering and design of a 600-ton-per-day coal gasification plant with a constructed cost of over $100 million. Supervised a multi-disciplined professional and design staff of up to 50 personnel.

1979-80 Project Mechanical Engineer - General Public Utility, Three Mile Island Nuclear Station, Unit 2 - Supervised mechanical engineering and design for an evaporator / crystallizer and solidification facility. Facility was designed for volume reduction and solidification ofliquid radioactive wastes generated in Unit 2 post accident cleanup; budgeted cost was $15 million.

1978-79 Project Mechanical Engineer - Electric Utilities of Croatia and Slovenia, KRSKO Nuclear Power Plant, Unit 1 (600 MW) PWR - Supervised mechanical engineering and design. Responsibilities same as for V.C.

Summer Nuclear Station assigmnent described below.

1977-78 Senior Project Engineer - Sout Carolina Electric & Gas Company, V.C.

Summer Nuclear Station, Unit 1 (900 MW, PWR)- Supervised fluid system engineering and design, and up to 40 professional and technical personnel in the following areas: mechanical, nuclear, HVAC, water treating and piping engineering.

1975-76 Project Mechanical Engineer - V.C. Summer Nuclear Station, Unit 1 (900 MW, PWR) - Supervised 20 professional and technical support personnel in the preparation of flow diagrams, system descriptions, equipment and piping specifications, FSAR input and piping design.

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l 1973-75 Project Mechanical Engineer - General Atomic high temperature gas-cooled

, reactor - Supervised mechanical engineering on balance-of-plant design of l

two reference plants: a 1180 MWe unit for U.S. siting and an 800 MWe unit for a Japanese site. Prepared flow diagrams, system descriptions and system optimization studies.

l 1971-72 Mechanical Engineer - Responsible for preparation of flow diagrams, I system descriptions, equipment specifications and optimization studies for circulating water systems involving steam condensers and cooling towers, and alternative heat sinks such as cooling ponds.

1964-71 Pratt and Whitney Aircraft. Division of United Aircraft. East Hartford.

Connecticut 1969-71 Senior Analytical Engineer, New Product Development Group - Developed analytical techniques and computer programs for analysis of propulsion systems and engines. Used thermodynamics, aerodynamics and numeri;al analysis techniques to develop gas property and combustion subroutines for use in a state-of the-art, modular computer program that became the basis for P&W's jet engine performance predictions.

1964-69 Senior Analytical Engineer, Current Engine Performance Group -

,p Responsible for performance analysis of TF30 engine, a supersonic, after-burning turbofan used for propulsion in the F-111 aircraft. Theoretical k calculations and analyses were compared to wind tunnel and flight test data to provide a basis for optimizing performance and demonstrating achievement of performance guarantees.

1963 Bureau of Plant Maintenance. Board of Education. New York. New York Junior Mechanical Engineer - Field reporting and design work on HVAC equipment to upgrade obsolete designs for school buildings in New York City.

EDUCATION: B.S., Mechanical Engineering, Polytechnic Institute of Brooklyn,1963 M.S., Mechanical Engineering, Rensselaer Polytechnic Institute, Troy, New York,1969 l Additional Courses:

l Postgraduate mathematics courses (part-time), Trinity College, Hartford, i Connecticut,1965-67 l ASME Code,Section III Nuclear Power Plant Components, ASME l Course,1976 I

ASME Radioactive Waste Management,1987 Cogeneration Systems, George Washington University,1980 The Quality Advantage, Gilbert / Commonwealth,1990

, Mastering Business Development, Sales Management Systems Inc.,

1992-93 i

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O REGISTRATION: Professional Engineer - Connecticut (1968), Pennsylvania (1972) and Tennessee (1989)

SOCIETIES: American Society of Mechanical Engineers PUBLICATIONS: " Systems Integration," APPA Engineering and Operations Workshop,1996.

Co-author, " Repowering with Clean Coal Technologies," American Power Conference,1996.

" Effects of External Boost Compression on Gas Turbine Performance in CPFBC Applications," Thirteenth AnnualInternational Pittsburgh Coal Conference,1996.

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, d, Over 28 years of experience in system engineering, machine design, life assessment / extension, predictive maintenance, manufacturing, welding and nondestructive testing. Nine years of experience in design, application, manufacture and troubleshooting of steam / gas turbines, pumps, .

! compressors, condensers, pressure vessels, heat exchangers, gears and diesel generators. I Demonstrated skills in project management, procurement, writing of equipment and installation design specifications, and PC applications including Wordperfect, Word, Designer, and Excel. l Workmg knowledge of ASME, ANSI codes and OSHA regulations. Effective communicator  !

with excellent presentation skills.

EXPERIENCE: PARSONS POWER (formerly Gilbert / Commonwealth) since 1992 1992 to Present Lead Engineer - Responsible for engineering, design and installation of l multi-discipline projects. Perform welding engineering consulting services.

Typical projects completed include:

1994 to Present Procter & Gamble Paper Products Company - Typical projects completed include:

Upgrade of bleaching operations including recycle of Post Bleach Washer filtrate, improvement to #1 Pre-Bleach Washer showers, replacement of high. shear pump and replacement of PoBW Heat Exchanger SO2 recovery system improvements including supplementary cooling for the acid plant (scrubber, absorber and pre-absorber), liquid SO 2 (n)

H addition, SO; monitor, scrubber venturi replacement, pH instrumentation and sample coolers

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HVAC systems including chilled water, DX and absorption units in the pulp mill, boiler house, water treatment and office areas

, l Fugitive dust control system for conveyors, truck dumping, radial stacker l and pneumatic transfer system Material handling system for waste fuel (bark, wood chips, wood dust and paper making waste)

Ancillary support systems (steam, high pressure showers, piping, pumps, etc.) for paper machine capacity increase.

Condensate systems to retum condensate from the pulp mill to the boiler house 1994 Occidental Chemical Company Evaluation of hot air drying system for a vinyl manufacturing plant.

1993-94 Pennsylvania Power & Light Company, Susquehanna N.S. - Typical projects completed include:

Modification of deep bed condensate demineralizer system Replacement of 1100 MW HP Turbine, First Stage Buckets ASME Safety Relief Valve setpoint changes Analysis and performance of condenser tube staking Analysis of fluid system to increase flow 10 percent Analysis, redesign and replacement of Rad Waste filter q Prepared procedure to inspect shell and tube and air cooled heat Q exchangers Pasons Po.w Gree 16 7 16210 Page1

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V 1993 Westinghouse Hanford - Complete evaluation of process and steam district heating systems and steam generation plants including erosion / corrosion l

affects and physical assessments of steam lines ranging in age from 10 to 50 years.

1993 Public Service Electric & Gas, Hope Creek N.S. - Evaluation and redesign of high temperature asphaltic solid waste disposal system including pumps, extruders, instrumentation and the extrusion process.

1992-93 Rochester Gas & Electric, Ginna N.S. - Typical projects completed include:

Analysis of fluid flow elements and associated instrument loops Redesign and repair of the high pressure turbine exhaust (steam crossunder) poing to mitigate erosion / corrosion Develop and imp ement a program for control and mitigation of biofouling in service water Mechanical performance evaluation and modification of a turbine driven auxiliary feed pump 1992 Philadelphia Electric Company, Limerick N.S. - Thermal binding evaluation of gate valves.

1992 NES/KRSKO - Preaared steam generator replacement study for this Westinghouse two-loop plant.

1992 Lonc Island Lichtine Comoany. Mellville. New York Provided engineering services for the design of gas systems, ?i pelines, meter sets and regulator stations. Prepared specifications anc construction standards for natural gas pipelines and gas distribution. Prepared program to control the procurement, storage, use and disposal of consumables.

Prepared an Asbestos Abatement Program.

1989-91 Conam Insoection Inc.. Sharon Hill. Pennsvlvania Typical projects completed include:

Philadelphia Electric Company-Peach Bottom and Limerick NS Thermal and mechanical performance evaluation of Safety Related HVAC chillers and main condensers

, Philadelphia Electric Company-Cromby and Eddystone Stations Coal-fired, boiler life assessment, replacement of HP feedwater heaters and main steam valves Consolidated Edison Company of New York, Indian Point, Unit 2 Engineering and testing for fuel rack replacement and program for the upgrading of commercial grade items.

Consolidated Edison Company of New York, Astoria Station, Units 1-5 Life assessment of main steam piping and condenser.

Episilon Chemicals, Chester, Pennsylvania (l Post accident survey / evaluation of 700 ton reactor vessel and i

3000 feet ofpiping i I/97-16210 Pase2

FEB 11 '97 0616Pf1 PARSONS POWER NPU P.24 f')

, V Star Refining, Delaware City, Delaware Oil refinery injection point survey ofcoker, FCC Unit and appurtenant systems, life assessment program for reactor vessels, associated piping and heat exchangers Gilberton Co-Gen, Frackville, Pennsylvania Life Assessment evaluation of fluidized bed boiler, shcIl and tube air preheaters and main steam piping ARCO Chemical Company, Beaver Valley, Pennsylvania Life Assessment Program of styrene plant including reactor, emuent exchangers and all critical piping Consumers Power, Palisades Nuclear Power Steam Generator Replacement engineering and logistics support including welding, NDE, and ASME Section III/XI services for main steam, primary coolant, auxiliary feedwater and service water system Alantic City Electric, Deepwater Station Erosion / Corrosion survey of boiler feedwater, condensate and two-phase flow piping systems including heater drain and steam extraction lines Prince Foods, Camden New Jersey Life assessment and erosion / corrosion survey of food manufacturing g pressure vessels, heaters, vats, storage tanks and piping.

b 1987-89 Bechtel/KWU Alliance. Gaithersburc. Maryland Typical projects completed include:

Public Service Electric & Gas Company, Salem and Hope Creek Stations Life assessment and performance evaluation of heat exchangers, condensers and interconnecting piping and components New York Power Authority, Indian Point Station Unit 3 Field Project Engineer - Steam Generator Replacement - Eddy current testing, B 31.1 and Section XI inspections and evaluations, document control, QC inspection and access control / monitoring General Public Utilities, Oyster Creek and Northeast Utilities, Millstone Unit 1 Automated UT inspection of the reactor nozzles.

Gulf States Utilities, River Bend Life Assessment of high energy piping systems.

1985-87 United StateLTenine Co . Hoboken. New Jersey Performed engineering, design and developed robotic systems to perform automated ultrasonic inspection. Performed automated UT inspection on nuclear and petrochemical reactor vessels, high energy steam piping, erosion / corrosion surveys of piping and vessels and IGSCC on BWR piping

systems. Designed and installed material handling, rolling mill equipment l and automated testing facilities for U.S. Steel-Gary, Indiana and Bethlehem l Steel-Burns Harbor, Indiana.

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1981-84 Westem Stress Inc.. Mount Forest. Ontario. Canada Performed engineering and management of onsite heat treating and welding services.

1979-81 Nuclear Power Services. Secaucus. New Jersev Engineering and design of p,iping, pipe hangers, cable trays, and structural components; seismic analysis, vibration analysis, baseplates and as-built drawmg preparation.

1976-79 Combustion Encineerinn - Lummus. Bloomfield. New Jersev Engineering, design and constmetion of petrochemical facilities, heat exchangers, fired 2 eaters, air coolers and dry cooled steam condensers.

1967-76 DeLaval Turbine Inc.. Trenton. New Jersey Designed, manufactured and performed trouble shooting of gas turbines up to 100 MW, boiler feed pumps u, to 40,000 BHP, centrifugal compressers, condensers, diesel generators anc radwaste filters. Foundry engineering and development ofinvestment cast process for austenitic steel components and heavy walled 12% chrome castings.

EDUCATION: B.S., Mechanical Engineering, New Jersey Institute of Technology,1967 Additional Courses:

Graduate Business Study, Rider College r

Instructor for the following courses:

Lecturer, Engineering Affairs, Princeton University Rotating Machinery Design Operation and Maintenance, Philadelphia Engineers' Club SOCIETIES: American Society for Quality Control American Society of Mechanical Engineering, Trenton Section, Vice Chairman LANGUAGE: Spanish PATENTS: Dry Cooled Ultimate Heat Sink for Nuclear Power Plant PUBLICATION: " Optimized Method for Steam Turbine / Dry Cooled Condensor Design,"

1979.

" Time of Flight - Automated Ultrasonics for Heavy Walled Reactor Pressure Vessels," 1986.

" Automated Ultrasonic Inspection of High Energy Steam Piping," 1987.

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6 i Mechanical Engineer l 1 Sixteen years of design, licensing and project engineering experience in the nuclear power i industry. Performed in-plant and design engineering, licensing, plant operations and supervisory i roles. Responsible for performance and oversight ofnuclear plant licensed activities performance and independent review of 10CFR50.59 safety evaluations, mechanical piping and equipment design calculations and application, project and construction management, system 1 l functional and operational evaluations, and supervision of engineers and plant operators. l l Extensive knowledge of nuclear power plant systems and equipment design, operation and

! l maintenance; industry practices, codes and regulatory standards; plant work control processes; and plant support requirements. Experience leading multidisciplinary project teams. Proficient l in the use of computer hardware and software, including general office software and several l

technical and engineering codes / programs.

EXPERIENCE: PARSONS POWER since 1997 I 1997 to Present Assigned to the nuclear group.

1990-97 ABB Combustion Encineerinc. Windsor. Connecticut Lead Design Engineer / Project Manager - Baltimore Gas & Electric (BGE),  !

Calvert Cliffs Nuclear Power Plant (CCNPP) - Engineering projects consist l of nuclear power plant design modifications and engineering calculations, design and licensing basis changes,10CFR50.59 safety evaluations, plant modification implementation /constmetion management, and independent

'p design review. Duties required application of piping and component design d code (ASME Boiler and Pressure Vessel Code, ANSI Power Piping Code, ANSI Standards) requirements, inspection and repair requirements, industry standards and regulatory requirements, and ASME/ ANSI quality standards.

Responsible for all aspects ofproject execution including initial scoping through detailed design, technical quality, cost and schedule management, l

and project implementation.

Performed detailed plant power uprate feasibility study to determine the acceptability of power plant systems performance at above-design power levels. Responsible for steam and power conversion systems performance evaluation. Included development of secondary plant flow / pressure drop model and use of turbine cycle thermal performance modeling codes.

I Detcrmined altemative approaches to resolve system / component performance deficiencies and developed cost estimates for implementation of the alternatives.

1 Provide consulting support in the development and implementation of a nuclear plant license renewal project in support of a license renewal l application submittal. Responsibilities include performance of equipment i life cycle evaluations to determine the effects of corrosion, fatigue, thermal l

and radiation effects on functional capability; participation in the development ofindustry and regulatory license renewal requirements; development of site-specific process methodology and implementation p procedures; development of site programs to manage equipment aging p effects; and integration of project results into plant processes.

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1983-90 Vircinia Electric and Power Comoany. Suny Power Station. Surry. Vircinia Positions held included Senior Engineer, Shift Technical Advisor, Outage Coordinator, Startup Test Director, Radiological Engineering Supervisor, Operations Assistant Shift Supervisor (Licensed Senior Reactor Operator).

Performed functions ofincreasing responsibility that included design and project engineering (plant design modifications and calculations, equipment failure cause analysis and resolution, construction project management, preventive maintenance task development); oversight and review of nuclear operations activities and events; preparation and independent review of 10CFR50.59 safety evaluations and operating license amendments; lead for radiological engineering group (staffing, administration, supervision) to provide shielding analysis. ALARA support and radiological engineering controls; development, planning and execution of testing programs (electrical distribution verification test, engineered safety features system fur.ctional tests, routine surveillance and performance tests); and coordination of plant outage maintenance and construction activities. As Licensed Senior Reactor Operator, responsible for overall safety and operation of a nuclear generating unit including supervision and training for plant operators, performance assessment of operating and stand-by equipment, compliance with requirements of the operating license, and

, accomplishment of generation goals.

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1980-83 Newoort News Shinbuildinc and Drvdock Co.. Atomic Power Division, Newnort News. Vircinia Engineer - Duties included design, development and modification of naval 4

nuclear propulsion plant systems including systems fluid flow analyses, pipe stress analyses, component replacement qualification, initial criticality and reactor plant startup testing.

EDUCATION: B.S., Mechanical Engineering, Michigan Technological University,1980 REGISTRATION: Professional Engineer - Commonwealth of Virginia Senior Reactor Operator License - Surry Power Station (1987-90)

SOCIETIES: American Society of Mechanical Engineers American Nuclear Society American Society of Heating, Refrigerating and Air-Conditioning Engineers National Society of Professional Engineers National Association of Corrosion Engineers

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Senior Nuclear Engineer Over twengt-six years of experience in power engineering with emphasis on project and engineering .

management, problem solving, program and project assessments, consulting services and specialty i services for domestic and intemational programs.  :

i EXPERIENCE: PARSONS POWER (formerly Gilbert / Commonwealth) since 1970 l 1996 to Present Air Products and Chemicals Inc. - Project Manager for the Union Camp Corporation ASU, an 80 tpd lox facility. I 1995 Project Manager - Kozioduy Nuclear Plant Seismic analyses of Shelve Building -  !

Responsible for contract management, and sub-contractor interface.

Assistant Project Manager - Falisades Nuclear Plant Reactor Vessel Annealing -

Responsible for shielding, thermal analyses, and suppon programs and tasks.

Technical consultant to the U.S. Depanment of Energy (DOE) for the Tomsk and Krasnoyarsk plutonium production reactors power conversion program -

Responsible for the demand analyses for the reactor replacement program for PNL.

1993-95 Task Manager, Nukleama Elektrarna Krsko, Decommissioning Waste Characterization Program - Developed a computer code to calculate and evaluate the waste arising from the decommissioning of the Krsko nuclear power plant in Slovenia.

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,/ Senior Consultant, International Projects - Provided technical guidance and management assistance for all international power projects. Provided technical suppon for engineering tasks and opponunities. Provided technical assistance and development suppon to engineering personnel for work on foreign assignments.

Technical responsibility for decommissioning and decontamination, low-level and high-level waste projects International Atomic Energy Agency (IAEA) Technical Experts - Reviewed and provided guidance and direction to the Peoples Republic of Bulgaria for the Low-and Intermediate-Level waste disposal program. Reviewed program reports, regulation and studies.

Engineering Manager / Consultant for the Consumer Power Company's Big Rock Ponit Decommissioning plan and study for the removal of components during the dismanticment operations.

Gilbert / Commonwealth International. Inc.

1992-93 Regional Technical Director - Central & Eastem Europe operations - Responsible for all Business and Technical activities in Eastern & Central Europe. Project Director for BNL contract for Near-Term Risk Reduction in Soviet-Designed Reactors for Russia and Ukraine.

Manager - International Power Technology Projects - Responsible for the management of projects for Eastern and Central Europe and Korea. Responsible for client development and project planning, sales , implementation and coordination.

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I V) i Gilbert / Commonwealth 1991 92 Project Manager - Yugoslavia Projects - Responsible for the sale, management and execution of task assignments associated with the Kriko Nuclear Plant, and other power generation facilities in Yugoslavia.

l Project Mechanical Engineer - Managed and led mechanical engineering design team for the conceptual design of the A dvanced Neutron Source Reactor and experimental facility for Martin Marier i at Oak Ridge National Laboratory.

Manager (Acting), Mechanical Engineering Department - Responsible for the administration and technical direction and management of all Mechanical Engineering Department personnel.

Safety Self-Assessment program team member for the review of safety issues at the Morgantown Energy Technology Center. Led a team of engineers to review site programs and operations versus the environmental and safety requirement of the DOE Tiger Team document.

1990-91 Manager, Resource Staffing, Mechanical Engineering - Responsible for assessing assignments for department personnel and other associated Mechanical Department related administrative activities.

Consultant, Root Cause Analysis Program - Pennsylvania Power & Light O Company - Performed root cause analysis on engineering process for the h'

determination and response to engineering discrepancy issues. Participated as a team member in the development of organization and process recommendations to improve the response time and resolution of engineering issues for the engineering department.

1988-90 Manager, Nuclear Specialty Services, Nuclear Business Unit - Responsible for the identification, development, management and specialty nuclear services.

Technical Consultant, TVA Sequoyah Nuclear Plant - Responsible for the review and assessment of engineering programs for compliance to INPO evaluation programs.

Technical Consultant, LP&L Waterford - Provided technical overview and input to the Outage Optimization Program and the Nuclear Excellence Program.

1984-87 Project Manager / Assistant Program Manager - Sacramento Municipal Utility District, Rancho Seco Nuclear Plant - Team leader for six safety system inspections as part of the safety system functional inspection. Assisted program manager with remaining twenty-seven system reviews as technical consultant.

Mechanical Engineering Consultant - TVA Sequoyah Nuclear Plant, member of design review team to assess the engineering modification process at TVA and evaluate its compliance to defined procedures and processes.

Technical Specialties - Section Manager, Mechanical Department - Responsible for all radwaste, HVAC, and fire protection engineering services.

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Project Manager - Rockwell Intemational, Basalt Waste Isolation Programs - ,

Waste container designs analysis and development.

Assistant Task Engineer- South Carolina Electric & Gas Company, V.C. Summer Nuclear Power Plant - Appendix "R" analysis.

Procurement Engineer - Philadelphia Electric Company, Limerick Nuclear Station, onsite Spare Parts Program.

i 1982-84 Manager of Engineering - Wimpey-Gilbert Joint Venture, United Kingdom -

Responsible for radwaste design, research and development, and decontamination and decommissioning. Project manager for the following:

British Nuclear Fuels Medium Active Solidification Waste Encapsulation Plant Project - Solidification research and development to develop mixing system j and hardware for spent ion exchange resins and reprocessing sludge.

British Nuclear Fuels Medium Active Solidification Waste Encapsulation Plant 3

Project - Intermediate level waste storage facility design.

British Nuclear Fuels - High integdty container study.

Central Electric Generating Board - Intermediate level waste storage facility design.

l Decontamination of Radium contaminated facilities in the greater London area.

Decontamination of Ministry of Defense facilities.

l Expert witness for decommissioning of the following projects:

! Grand Gulf, Mississippi Power & Light Company - Appeared before Federal

! Energy Regulatory Commission.

1 Florida Power & Light Company, St. Lucie, Units 1 & 2 - Appeared before Florida Public Utility Commission.

Florida Power & Light Company, Turkey Point, Units 3 & 4 - Appeared before Florida Public Utility Commission.

Louisiana Power & Light Company, Waterford, Unit 3 - Appeared before Louisiana Public Utility Commission.

1980-82 Project manager for the following decommissioning projects:

I Japanese 3 loop PWR nuclear power plant, PWR owners group.

Florida Power & Light Company, Turkey Point, Units 3 & 4.

Florida Power & Light Company, St. Lucie, Units 1 & 2.

Ontario Hydro, Pickering "B."

Baltimore Gas & Electric Company, Calvert Cliffs.

Mechanical Engineering Manager - Responsible for fluid and suppon systems design for the Elmo Bumpy Torus - Proof of Principle fusion facility.

1978-80 Principal Engineer - Responsible for engineering design on the following projects:

Florida Power Corporation, Crystal River, Unit #3- Adjacent spent fuel storage facility.

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g V I Consumer Power Company, Palisades facilities - Adjacent spent fuel storage facility.

Consumer Power Company, Palisades and Bid Rock Point Units - Low level  !

waste storage facility.

Consumer Power Company, Palisades facility - ALARA review of steam generator removal study.

Oak Ridge Associated Universities - Low level waste on-site storage and spent fuel on-site storage study.

Southern Company Service, Hatch and Farley nuclear stations - Technical evaluation of decommissioning studies.

Project Engineer - Mitsubishi Heavy Industries - Responsible for BOP fluid systems design for the study and evaluation of Spherical Containment for use with the Pressurized Water Reactor Systems.

Project Engineer - Review of the Iran 1&2 nuclear reactor radwaste systems for Kraftwerk Union.

1977 Westinghouse Japan - On-Site Systems Advisory Engineer - Kansai Electric Power Company, Ohi Nuclear Power Station Units 1 & 2 (1100 MW each)-

Responsible for engineering required for startup. I 1975-77 Project Nuclear Engineer - Ohi Nuclear Power Station, Units 1 & 2 (1100 MW l each) i Project Interface Engineer - South Carolina Electric & Gas Company, V.C. Summer Nuclear Station, Unit 1 (900 MW)

Engineering Reviewer - Electric Utilities of Croatia and Slovenia, Krsko Nuclear Station, Unit 1 (600 MW) 1976 Final Safety Analyses Report Reviewer - Korea Electric Company, Ko-Ri Nuclear Power Plant, Unit 1 (PWR) - Performed technical review for safety analysis report.

Metropolitan Eoison Company, Three Mile Island, Unit 1 - On site nuclear engineer assisting Core 1, Cycle 1 refueling.

1970-75 Nuclear / Mechanical Engineer - Kansai Electric Company, Ohi Nuclear Project -

Designed systems for a four-loop, two-unit 1100 MW pressurized water reactor with ice condenser containment.

System Engineer - Rochester Gas & Electric Ginna Nuclear Plant - Site assignment to assist in outage support.

System Reviewer - Ohio Edison Company, Eric Nuclear Station, Units 1 & 2 (1280 MW PWR).

Korea Electric Company, Ko Ri, Unit 1 (600 MW, two-loop single-unit)-

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Reviewed startup and testing procedures and system and equipment design for a pressurized water reactor.

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Cleveland Electric Illuminating Company, Perry Nuclear Project (1200 MW, four-loop)- Reviewed system design and equipment specifications for the two unit boiling water reactor.

1970 4

Engineering Technician - Developed and revised computer code used in analyses

' of nuclear power plants.. Performed shielding calculations and prepared environmental surveys for safety analysis repons.

1967-70 Bendix Electronics Inc.. Mountainton. Pennsylvania Electronics Technician - Repaired, tested, and calibrated instrumentation.

i 1964-67 U.S. Navy Electronics Technician in communication, calibration, and testing.

EDUCATION: B.S., Nuclear Engineering, The Pennsylvania State University,1971 Additional Courses:

' Pipe Stress Analysis Seminar, Gilben Associates,Inc.,1971 Introduction to Environmental Protection, Gilben Associates,Inc.,1972 Nuclear Power Plant Components, ASME, November 1974-75 Basic Fossil Power Plants, Gilbert / Commonwealth,1978 Inertial Confinement Fusion, ANS,1979 Advocacy Training Workshop, Management Consulting,1982 Management Development Center, Gilbert / Commonwealth,1985 C)

V Project Management, Gilbert / Commonwealth,1986 Lotus 1-2-3, Albright College,1986 Financial Management, Gilbert / Commonwealth,1988 Liability and Contract Management, Gilben/ Commonwealth,1988 The Strategy for Winning, Gilbert / Commonwealth,1988 Professional Business Development, Gilbert / Commonwealth,1992-93 The Quality Advantage, Gilbert / Commonwealth,1993 REGISTRATION: Engineer-in-Training - Pennsylvania (1972)

SOCIETIES: Member, American Society of Mechanical Engineers Member, American Nuclear Society - Northern Section (Vice-Chairman)

Member, American Nuclear Society COMMITTEES: Member, Public Advisory Committee to the Pennsylvania Depanment of Environmental Resources for LLW Disposal in Pennsylvania (Appalachian Compact)

Former Vice-Chairman, ASME High-Level Waste Committee Former Chairman, ANSI N208," Fuel Handling Systems Design" Former Chairman, ANSI-N209, " Design ofNew Fuel Storage Facilities" Former Chairman, ANSI N210, " Design of Spent Fuel Storage Facilities" Contributor to:

ANS 57.7, " Design Criteria for an Independent Spent Fuel Storage Installation (Water Pool Type)"

ANS 57.9, " Design Criteria for Dry Spent Fuel Storage Installation" Liaison Member to ASME Advanced Technology Committee Persors Power Grow 824612 11004 Page5

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PUBLICATIONS: " Estimating Radiological Conditions for Decommissioning Studies," Egy.n Ennineerine. June,1982

" Elements of Decommissioning," Symposium, Seattle, Washington "The Options for Solidifying Low Level Waste," Nuclear Engineering International, March,1983

" Nuclear Plant - Dismantling the First Generation," Heavy Construction, June, 1983 j

" Solidifying Waste with a Mobile System," Nuclear Engineering International, i February 1984

" Closure Seal for Basalt Repository High Level Waste Containers and Closure Head," N. Jayaraman, Joint AShE/ANS Nuclear Powe-Conference, Philadelp ta, ennsy vania, July,1986 l

" Conceptual Design of Waste Packages for the Nuclear Waste Repository in Basalt Rock," Dobson, Koch, 3 Joint Nuclear Power Conference, 1

Philadelphia, Pennsylvania, July,1986

" Radioactive Waste Disposal," ASME Course on Nuclear Power, Delaware Valley Section, May,1986 l I

"High Level Waste Packages for the Nuclear Repository in Basalt Rock," ASCE Structures Congress, New Orleans, Louisiana, September,1986

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" Waste Management and The States,"IAEA Workshop on Waste Management, Palo Alto, CA, March,1994 l l

" Analysis Of The National Concept For The Siting Of The Near Surface l

Repository For Low And Intennediate Level Radioactive Waste", IAEA

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Expert Mission Report - TC BUL 9/016, Sofia, Bulgaria, July 1994  !

" Big Rock Point Decommissioning Study," GC Report-3048, August 1994 "DEWCHAP Decommissioning Waste Characterization Program," Waste Management 95, Tucson, AZ, February 1995

" Decommissioning Waste and Its Influence on the Cost of Decommissioning," M.

M U.S.-Eastern Europe-Former Soviet Union Electric Power Technologies Conference, Bucharest, Romania, April 1995

" Plant Life Extension,"M, E.A. Blocher, U.S.-Eastern Europe-Former Soviet Union Electric Power Technologies Conference, Bucharest, Romania, April 1995 Demand Analyses for " Nuclear Power Replacement Options Study for Seversk (Tomsk-7) and Zheleznogorsk (Krasnoyarsk-26)" for USDOE Decerr.ber 1995 O

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Senior HVAC Engineer Twenty-eight years of experience in engineering activities for major power generating, industrial, and high technology facilities in the United States and abroad.

EXPERIENCE: PARSONS POWER (formerly Gilbert / Commonwealth) since 1972 1978 to Present Lead Engineer - Responsible for engineering supervision and design of heating, ventilating and air-conditioning (HVAC) systems for the following projects:

1 Smith Kline Beecham Pharmaceutical - Project Manager for the air system analyses of eleven large laboratory buildings to increase and improve system's performance and upgrade the system's heat recovery feature.

Caterpillar Inc. - Plant waste heat reco;ery study to save about $1M in energy Costs.

Westinghouse Electric Corporation - Force cooling systems to dissipate the heat from existing nuclear reactor while undergoing an in-place annealing process.

Philadelphia Navy Yard - Upgrade of an existing foundry facility's general and industrial ventilation systems. Replace existing conventional chillers with the adsorption type.

Electric Utilities of Croatia & Slovenia, KRSKO Power Plant - Prepared

/~N the report that evaluated and recommended the most cost effective V option to convert the existing chillers to non-CFC refrigerant chillers and meet the EPA CFC regulations.

Tennessee Valley Authority, Watts Bar Power Plant - Upgraded HVAC calculations and documents in preparation for an external regulatory audit.

Lewisburg Fedeial Prison - 1200 ton chilled water system with 1500 ton ozone treated cooling tower,60,000 lb./hr steam heating system.

Philadelphia Electric Company, Delaware River Water Diversion Project

- Award winning 6900 ton chiller with 11,490 ton cooling tower system to cool ozinated water diverted from the Delaware River.

Pennsylvania Power & Light Company, Power Management System, Supervisory Control and Data Acquisition (SCADA) Systems -

Control room, computer room, battery and UPS room HVAC Systems.

Public Service Electric & Gas, Salem Power Plant - HVAC continuing services.

Florida Power Corporation, Crystal River Power Plant, Unit 3 (855 MW)- HVAC continuing services.

General Public Utilities Corporation, Three Mile Island Power Plant, Unit 1 (820 MW)- HVAC continuing services.

Pennsylvania Electric Company, Power Plants - HVAC continuing services.

Persons Power Groe 824612 11004 Page1

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V,T Department of the Navy, Aircraft Systems Integration Lab - HVAC system for a flight simulation facility used to train fighter pilots.

Baltimore Gas & Electric, Brandon Woods Energy Park Heat Recovery Study - Conversion ofplant waste heat for use by a nearby industrial

. Park.

Korea Electric Company, Ko-Ri Unit 2 Power Plant (600 MW)- HVAC systems for the entire plant.

Electric Utilities of Croatia & Slovenia, KRSKO Power Plant (600 MW)

- HVAC systems for the entire plant.

Delmarva Power & Light, Indian River Unit 4 Fossil Power Plant (400 MW) HVAC systems for the entire plant.

Corning Glass Works - Plant general ventilation systems and glassware forced convection cooling systems.

Responsibilities include technical and administrative supervision; preparation of flow and control diagrams; writing system descriptions, control sequence ofoperation, technical specifications and safety analysis repoits; equipment selection; bid evaluations; computer modeling to determine heating and cooling loads, energy consumption and pipe and ductwork pressure losses; and life cycle costing to determine the most c economical and energy efficient system. Charcoal and HEPA filters are

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extensively used in the majority of the above projects.

HVAC Continuing Service - Responsibilities include preparation of modification packages to upgrade HVAC systems; develop HVAC design basis documents (DBD); resolve licensing issues; analysis of HVAC systems to determine normal and accident (loss of HVAC) environmental conditions; perform third party review on HVAC systems; and participation in audits and reviews.

1973-78 Engineer - Cleveland Electric Illuminating Company, Perry Nuclear Power Plant, Units 1 & 2 (1200 MW each) - Designed HVAC systems, prepared flow diagrams, wrote system design descriptions, calculated heatmg and cooling loads and selected , appropriate equipment. Design included two separate chilled water coohng systems - the reactor building system included three 500 ton centrifugal chillers and the turbine building included three 800 ton centrifugal chillers.

1972-73 Senior Draftsman - Checked HVAC and plumbing drawings for domestic and foreign projects.

1970-71 Comorehensive Desieners Inc.. Philadelphia. Pennsylvania Designer - Designed frames, fittings and release mechanisms for the Fairchild Industries ATS communication satellite.

1967-70 Boeine Comoany. Commercial Airolane Division. Seattle. Washincton (v Associate Engineer - Designed airframe structures and assembly tools for commercial airplanes.

ParaansPoweron e s24612 11004 Page 2

O COMPUTER Includes FORTRAN IV and BASIC computer programming, macros j EXPERIENCE: and templates for Microsoft comraercial software. Hands-on '

experience with Windows 95, Microsoft Office Professional, Lotus 1-2-3, Wordperfect, TK Solver, EUREKA, MathCad, and Carrier E20-II HVAC Programs.

EDUCATION: B.S., Mechanical Engineer, University of Santo Tomas (Philippines),1966 M.S., Engineering Science, The Pennsylvania State University,1977 Additional Courses:

Computer Applications to Engineering Problems, University of 3 Washington,1968-69 Stmetural Analysis and Materials, University of Washington,1970 Nuclear Power Engineering Seminar, Engineer's Club of Philadelphia, 1974 Foundations of Management, Gilbert / Commonwealth,1978 Basic Fossil Power Plant, Gilbert / Commonwealth,1978 HVAC Computer Software (E20-II) User Training, Carrier Corporation, 1985 AEE Waste Heat Recovery Seminar, The Association of Energy Engineer,1985 Clean Room Design, Engineer's Club of Philadelphia,1985 High Technology Clean Room Design and Construction, ASHRAE, 1989 O.

' Total Quality Advantage Seminar, Gilbert / Commonwealth,1991 Fundamentals of Supervision, Gilbert / Commonwealth,1993 l

Piping Codes and Materials, Gilbert / Commonwealth,1994 REGISTRATION: Professional Engineer - Pennsylvania (1978)

SOCIETIES: American Society of Heating, Refrigerating and Air-Conditioning Engineers, Member The American Society of Mechanical Engineers - Code of Nucicar Air and Gas Treatment Committee, Member PUBLICATIONS: "A Numerical Procedure for Determining Thermodynamic Properties of Air," M.S.E.S. Thesis, Penn State Library

" Technical Training- HVAC Systems," Gilbert / Commonwealth Library l "PC Computer Program B002 Duct Pressure Loss Documentation and User's Manual," Gilbert / Commonwealth Library Design Guide-DG1," Duct Pressure Loss Calculation Spreadsheet,"

Gilbert / Commonwealth Library Design Guide-DG2, "ASME Method-P and Tank Heat Load Calculation Spreadsheet," Gilbert / Commonweal Library

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824612-11004 Page 3  !

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i Senior Structural Engineer Extensive experience in structural design and management ofdesign activities for power plants  !

and commercial / industrial structures on site and in the office. I EXPERIENCE: PARSONS POWER since 1995 1995 to Present Perform various structural engineering activities required at TMI site, which include pipe support design to turbine deck stiffening. Perform design review functions for plant crane upgrades of Oyster Creek site. Major involvement in B&W Owners Group effort on plant life extension.

1983-95 Gilbert / Commonwealth. Inc.. Reading. Pennsylvania j

Project Structural Engineer - General Public Utilities Three Mile Island, '

Umt 1 (855 MW) anc Oyster Creek (650 MW); and Cleveland Electric Illuminating Company, Peny Power Plant, Units 1 & 2 (1200 MW) -

Coordinated the total effort of stmetural discipline continuing services.

Coordinated the seismic portion of equipment qualification at the site.

Acted as consultant for design work on stmetures and piping systems subjected to dynamic loads. Major participant in SQUG walkdowns, and modifications at TMI and Oyster Creek.

1982-83 Project Manager - Florida Power Corporation, Crystal River, Unit 3 -

Managed continuing services effort for Gilbert / Commonwealth.

g 1981 Site Group Manager - South Carolina Electric & Gas Company, -

e V.C. Summer Station - Managed task force of 35 Gilbert / Commonwealth l

} designers and drafters on the site.

l 1977-81 Structural Project Engineer - Korea Electric Company, Ko-Ri Plant, Unit 2 l (600 MW) - Responsible for total effort of the structural discipline.

1975-77 Assis*. ant to Project Engineer - Electric Utilities of Croatia and Slovenia, KRSKO Nuclear Power Plant, Unit 1 - Involved in the seismic design of structures and major nuclear steam supply system equipment supports.

1973-75 Consultant at Commonwealth Associates - Ohio Edison Company, Erie Plant, Units 1 & 2 (1200 MW each) - Provided consultation in structural disci ? line and project management. Extensively involved in the deve opment of the project management manual, the integrated design / construction schedule, the design control and project procedures, and coordination with the corporate and client quality assurance organizations. l 1971-73 Coordinating Engineer - Ko-Ri Plant, Unit 1 - Responsible for the technical supervision, scheduling, and plannmg of the structural effort on the design of the containment building. Functioned as a structural project engineer at the end of assignment.

1969-71 Junior Engineer - Performed miscellaneous design in concrete and steel for domestic and foreign power plants and commercial / industrial buildings.

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V 1971-73 The Pennsylvania State University. Readina. Pennsylvania Instnietor - Taught various courses in statics, strength of materials, and steel and reinforced concrete design.

1967-69 Louis C. Kinescott & Associates Inc.. Kalamazoo. Michigan

Structural Engineer - Designed school buildings in concrete and steel.

1958-61 U.S. Marine Coros EDUCATION

B.S., Civil Engineering, University of Maryland,1965 4

M.S., Structural Materials, University of Maryland,1967 1 Additional Courses:

4 IPEEE, SQUG, and LRFD training 1

REGISTRATION: Professional Engineer - Pennsylvania (1973), Ohio (1973), and Michigan (1974)

LANGUAGE: Lithuanien (fluent) i O

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V Senior Structural Engineer i

1 Experienced in civil / structural / piping engineering and project management involving domestic and international major power generating plants, industrial plants, govemment facilities, commercial buildings, and bridges. Supervised a staff of over 40 engineers and senior designers.

Experienced as a project engineer on various power plant projects. Expert in the areas ofr. ismic engineering, vibrating equipment foundations, finite element design, and stress analysis with  !

emphasis on problem solving. Extensive experience in applications ofmany different finite element programs including: IMAGES-3D, STARDYNE, STAADIII, BASEPLATE II, SAP, GTSTRUDL, ADINA, ANSYS, TPIPE, CAEPIPE, FLUSH and SASSI on supercomputers, mainframes and PC systems.

EXPERIENCE: PARSONS POWER (formerly Gilbert / Commonwealth) since 1989 1995 to Present Supervising Engineer - Supervise two structural and piping engineering groups with over 40 engineers and senior designers. Duties include coordinating project assignments and levelizing manpower requirements, coordinating and overseeing performance appraisal process, representing the groups in proposal, project kick-off and project review meetings, and I handling day-to-day technical and administrative problems. l 1995 to Present Project Manager - Kozloduy Power Plant, Bulgaria - Direct and manage I services performed by Parsons Power on the Soviet-designed six-unit plant.

Control and manage project scope, schedule and cost. Interface with client c regarding project status, direction and altematives. General responsibility

( includes client satisfaction, assisting client in defining work scope and business development. Work force includes eight local engineers in addition to the Parsons Power team. Supervise and manage subcontracted efforts.

1996 Engineering Manager - Ponderosa Recycled Fibres Plant - Scope included perfonning piping analysis, design of about 1,700 pipe supports and assisting the contractor to procure, assemble and erect supports.

Responsible for planning and scheduling, preparation of design documents (specifications, drawings, bills of materials) and monitoring progress.

Task Manager - Pennsylvania Power & Light, Susquehanna Steam Electric Station - Assembled, directed and supervised a multi-discipline team in design of a 6,200-foot river water make-up pipeline. Provided pipe routing surveys, permits for highway and railroad crossings, pump evaluation, pump controls, valve design, pipe sizing, design pressure determination, flow capacity, drawings, and procurement, installation and testing specifications.

Consultant - Pennsylvania Power & Light, Susquehanna Steam Electric Station - Provided consultations and analyses for resolution of a number of technical issues relative to design of a new spent-fuel facility and heavy-load drop of spent-fuel transfer cask.

Permans po w orme 824612 11004 PageI

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1995 Task Manager - Manin Marietta Energ/ Systems Inc., DOE Paducah Gaseous Diffusion Station - Performed natural phenomena hazard linear and s

nonlinear analyses for two buildings. Designed structural upgrades.

1994-95 Task Manager - Pennsylvania Power & Light, Susquehanna Steam Electric Station - Assembled, directed and supervised a team of 15 multi-discipline i engineers in an 8,000-manhour task. Inspected and performed structural I evaluations of turbine building, main turbine condenser, and numerous block walls for increased design loads. Inspected and performed piping l

analyses for numerous piping systems in turbine building. The evaluations were based on innovative procedures that resulted in a 75% reduction in modification cost (a saving of more than $1 million).

1991 to Present Seismic Engineering Consultant - Clients consist of more than 30 electric utilities, industrial companies, equipment suppliers and government agencies including Tennessee Valley Authority, Pennsylvania Power &

Light, Florida Power Corporation, Carolina Power & Light, General Electric, Westinghouse, Air Products, Procter & Gamble, and U.S.

Department of Energy. Developed seismic design criteria, performed seismic design, evaluated seismic design adequacy, developed innovative cost-effective proce designed earthquake,dures for seismic monitoring instrumentation evaluation, networks, designed authored post- seism earthquake response procedures, investigated recorded real earthquake motions, and evaluated earthquakes that exceeded seismic design basis.

Scope included buildings in nuclear and fossil power generating plants, government and industrial facilities, hi-rise buildings, bridges, storage

tanks, spent fuel facilities, piping systems, electrical and mechanical equipment, chimneys, and cooling towers.

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1991 to Present Machine Foundation Consultant - Provided consultations and analyses for resolution of numerous technical issues relative to design of foundations for vibrating machinery for General Electric, Westinghouse, Air Products, Procter & Gamble, Tennessee Valley Authority, New York State Electric &

Gas, Florida Power Corporation, and Panther Creek Energy Facility.

Designed foundations for steam turbine-generators, gas turbine-generators, pumps, fans and compressors.

1992-95 Program Manager - Managed Gilbert / Commonwealth's efforts in the applications of the SQUG and IPEEE programs at several nuclear power plants. Performed seismic verification walkdowns, generated new seismic input and evaluated outliers. Developed a computer software for evaluation oflarge vertical bottom-supponed tanks. Authored department procedures on seismic qualification by experience.

1991-95 Project Structural Engineer - Florida Power Corporation, Crystal River, n Unit 3, and Baltimore Gas & Electric, Calvert Cliffs Nuclear Power Plant U,

Persons Power Group 824612 11004 Page 2

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Units I and 2 - Responsible for technical, budgetary and scheduling issues for all civil / structural work.

1993-94 Task Engineer - Pennsylvania Power & Light, Susquehanna Steam Electric l

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' Station - Supervised a team of seven engineers. Performed advanced l nonlinear finite element assessment of two hyperboloidal reinforced concrete cooling towers to determine ultimate failure load, mode of failure and zone ofinfluence.

Egyptian Electricity Authority, Cairo South Combined Cycle Plant -

Provided consulting services relative to design of concrete pile foundations

in light of after-design recorded high-magnitude earthquakes.

4 Consultant - Pennsylvania Power & Light, Susquehanna Steam Electric Station - Made two presentadons to :nore than 60 site engineers on i earthquake awareness and prepmidness. Provided consultations on the utilization of the SQUG's GIP methodology for qualification of non-safety piping systems and made a presentation to the Nuclear Regulatory Commission on this subject.

1991-93 Pennsylvania Electric Company, Seward Station - Responsible for design of a steel sheet pile retaming wall system to protect plant from flooding and A) prevent recirculation from discharge ofone unit to intake of another unit.

Lead Engineer - Florida Power Corporation, Crystal River Unit 3 - i Assembled, directed and supervised a team of 10 engineers. Responsible

' for evaluation of more than 750 pipe supports to detennine factor of safety i against pullout of preloaded anchors and UNISTRUT concrete inserts 3

including prying effects.

l Cleveland Electric Illuminating Company, Perry Nuclear Power Plant -

Evaluated local stresses in the containment dome by using WERCO computer program and detailed finite element analyses.

Task Engineer - Martin Marietta Energy Systems Inc., Advanced Neutron Source - Developed a finite element model of the reactor building including the shield stmeture, containment vessel and interior concrete structure.

Performed several studies to investigate the effects of seismic loads on the conceptual design of this new Department of Energy Research Facility.

Litwin Engineers and Constructors Inc. - Performed a blast resistant design for the control building of a Hess petrochemical facility.

South Carolina Electric & Gas Company, V.C. Summer Nuclear Station -

Provided consultation and analyses for the evaluation of the refueling water storage tank, condensate storage tank and reactor water make-up tank due to g a design deficiency in their anchorage systems.

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1989-91 Martin Marietta Energy Systems Inc., Oak Ridge National Laboratory -

Conducted a retrofit feasibility study to investigate high-hazard buildings for natural phenomena structural upgrading due to effects of postulated earthquakes and tornado-level winds. Designed structural upgrades.

Task Manager - Krsko Nuclear Power Plant (Slovenia) - Interfaced with client's representatives and provided input to proposals, budgets and schedules. Participated in performing seismic hazard analyses using EPRI and LLNL methodologies. Conducted seismic analyses and investigated soil / structure interaction effects by using state-of-the-art methodologies and computer software. This plant has experienced over 200 regional earthquakes since 1980. Suvice revenues were about one million dollars.

Provided locations and trigger and set points for new earthquake monitoring equipment. Developed computer software to determine OBE exceedance according to EPRI publications and draft regulations.

Associated Universities Inc., Brookhaven National Laboratory - Prepared cost estimate, evaluated cost-benefit ratio and designed foundation isolator (open tren A) to isolate sensitive X-Ray facility and to attenuate unacceptable compressor induced vibration levels.

Consultant - Performed dynamic equipment qualification, and provided consultations and analyses for resolution of numerous technical issues relative to dynamic equipment qualification programs at Susquehanna ,

Krsko, Salem, Nine Mile Point, Perry, V.C. Summer, FitzPatrick, Crystal River 3, Kozloduy and Sequoyah nuclear power plants.

Tennessee Valley Authority, Sequoyah and Watts Bar Nuclear Power Plants, Units 1 & 2 - Performed seismic response spectrum analyses of ,

electrical systems to validate use of generic design standards. Parametric I studies were also performed to evaluate mass ratio effects, to develop a rigorous method to account for missing mass and to evaluate methods u.;ed for combining high frequency modes.

General Public Utilities, Three Mile Island Nuclear Station, Unit 1 -

Performed a seismic analysis of the primary coolant system for qualification of the pressurizer surge line.

Procter & Gamble, Mehoopany Plant - Responsible for design of a structural steel structure with removable parts supporting paper rolling equipment.

Tennessee Valley Authority, Sequoyah Nuclear Power Plant, Units 1 & 2 -

Performed investigative studies of the dynamic response of steel containment structure to various LOCA induced transient pressure loads.

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V The studies involved time history analysis and fourier decomposition analysis of displacements and acceleration.

South Carolina Electric & Gas Company, V.C. Summer Nuclear Station, Unit 1 - Performed thermal analysis for the reinforced concrete containment structure. Developed a finite element model for the steam generator replacement and generated N-411 damped seismic spectrum curves.

i Cleveland Electric Illuminating Company, Peny Nuclear Power Plant, Unit 1 - Evaluated the response of the bioshield stmeture to dead, rupture, thermal, seismic, and jet loads. Performed a finite-element analysis to determine the ultimate failure load of the personnel access airlocks in response to an Nuclear Regulatory Commission request to examine the plant for severe accident vulnerabilities.

i 1995 to Present Pennsylvania State Universitv. Readine. Pennsylvania Adjunct Professor in Engineering Department - Teaching undergraduate T

courses and professional engineer exam review course in civil engineering.

1990 to 96 Temole University. Philadelphia. Pennsylvania Adjunct Professor in Department of Civil Engineering - Taught three graduate courses and acted as thesis advisor for master students.

O V 1985-89 Vireinia Tech. Blacksburn. Virginia 1986-89 Research Assistant - Served in many projects funded by the U.S. Air Force and National Science Foundation. Worked on nonlinear dynamics of l foundations and superstructures.

1985-86 Teaching Assistant - Teaching load included statics, dynamics, deformable I

bodies, mechanics of composite materials, incompressible fluids.

1983-85 Gamma Ennineerinn. Jordan

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Site Engineer - Responsible for many aspects of a 5800,000 construction project including design, supervising foremen, and directing contractors.

Developed cost estimates and submitted progress updates.

J 1984-85 Design Engineer - Worked on design of a five-story structural steel building, an elevated water tank, a folded-plate long-span hall, and a multi-span arch bridge. These projects included design of different types of

foundations.

1983-84 GND College. Jordan Lecturer - Admmistrated teaching load for three engineering instructors and taught five undergraduate courses.

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TEACHING: University Courses Taucht-Earthquake Engineering Structural Dynamics Engineering Mechanics i Structural Analysis Construe. Materials Concrete Structures Design Surveying Specifications Finite Element Analysis Statics Dynamics Composite Materials i Graphics AutoCAD Professional Engr. Review Applied Fluid Mechanics Traininc Courses Taucht:

Turbine-Generator and Boiler Feedwater Pump Foundations, KOPEC,1996

. Design of Machine Foundations, Samsung,1995 Seismic Engineering, Krsko Nuclear Power Plant,1995 4 Current Seismic Design Criteria in the U.S.A., Gilbert / Commonwealth, 1995

Design of Machine Foundations, Gilbert / Commonwealth,1995 Earthquake Awareness and Preparedness, Pennsylvania Power & Light,

+

1994 l

Structural Fragilities, Baltimore Gas & Electric,1994 Soil / Structure Interaction Effects, Rochester Gas and Electric,1993 Lessons Leamed: 1992 High Magnitude Califomia Earthquakes, Gilbert / Commonwealth,1992

,, Structural Dynamics, Gilbert / Commonwealth,1992 (j

t Seismic Qualification by Experience, Public Service Electric & Gas,1992 Random Vibrations, Virginia Tech,1989 EDUCATIOE: Ph.D., Engineering Mechanics, Virginia Tech,1989. Research sponsored by U.S. Air Force.

M.S., Civil Engineering, Yarmouk University and Virginia Tech,1986 l

(Graduated with distinction). "Research sponsored by National Science i Foundation and U.S. Navy.

B.S., Civil Engineering, Yarmouk University,1983 (Graduated with High Honors)

Additional Courses include:

Load & Resistance Factor Design (LRFD) Workshop, AISC,1991 Add-on Seismic Individual Plant Examination Training Course, EFRI, Dallas, Texas,1992

, Walkdown Screening and Seismic Evaluation Training Course, SQUG, Dallas, Texas,1992 Structural Collapse and Advanced Shoring, U.S. Army Corps of Engineers, San Luis Obispo, California,1993 The Quality Advantage, Gilbert / Commonwealth,1993 Fundamentals of Supervision, Manufacturers Association of Berks County,1993 Urban Search & Rescue, Federal Emergency Management Agency,1994 Leadership Development, Gilbert / Commonwealth,1994

/~T C) REGISTRATION: Professional Engineer - Pennsylvania (1994)

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SOCIETIES: American Society of Civil Engineers Member, Committee on Dynamic / Seismic Effects (1994-97) 1 Member, Committee on Soil Dynamics (1994-97) .

Member, District 4 Council (5000 members; 1994-96)

, Director, Philadelphia Section Board (1600 members; 1994-96)

President, Reading Branch (210 members; 1994-96)

Vice President, Reading Branch (1993-94)

Secretary, Reading Branch (1992-93)

Federal Emergency Management Agency, Urban Search and Rescue Team for Pennsylvania, Structures Specialist (1993-present)

TECHNICAL J. Geotechnical Engineering, ASCE Nonlinear Dynamics REVIEWER: J. Stnictural Engineering, ASCE J. Vibration and Control

Int. J. Nonlinear Mechanics Pressure Vessels & Piping J. Vibration and Acoustics, ASME HONORS

Parsons Power's National Engineers Week Honoree Cenificate,1996 Strathmore's "Who's Who" in Business,1995 Gilbert / Commonwealth's Cultural Award in Pride,1994 Gilbert / Commonwealth's Cultural Award in Commitment,1994

% Gale's "Who's Who" in Technology,1993 Florida Power Corporation, Teaming for Success Award,1994 Honor Society of Phi Kappa Phi,1988 t

PUBLICATIONS: The following are representative of 37 technical papers published in conferences and refereedjournals:

With Nayfeh, A., " Vertical Vibration of Machine Foundations," J.

Geotechnical Engineering Division ASCE, Vol. I15,56-74,1989. '

With Chen, C., " Experience Data and Analysis Results of High Frequency Earthquakes," Founh Symposium on Current Issues Related to Nuclear Power Plant Structures, Equipment, and Piping, Orlando, Florida,1992.

" Response Analyses of Recorded Earthquake Motions," 3rd Intemational Conference on Case Histories in Geotechnical Engineering, St. Louis, Missouri,1993.

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" Dynamic Behavior and Identification of Failure Modes of Cooling Towers," 56th American Power Conference; Chicago, Illinois,1994.

" Current Seismic Design Criteria in The U.S.A.," 57th American Power Conference, Chicago, Illinois,1995.

" Machine Foundation Design," 57th American Power Conference, Chicago, Illinois,1995.

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" Seismic Performance of a Power Plant with Foundation Interaction,"

Journal of Geotechnical Engineering Division, ASCE Peer-Reviewed Special Publication on Deep Foundations,1995.

" Retrofit of Existing Buildings," 58th American Power Conference, Chicago, Illinois,1996.

" Natural Phenomenon Hazard Evaluation of an Aged DOE Plant," 58th American Power Conference, Chicago, Illinois,1996.

LANGUAGES: Arabic (speak, read, write fluently) l l

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i o MSemor Civil Engmeer D;

Twenty-seven years engineering and management experience in commercial nuclear power facilities and the U.S. Department of Energy (DOE) Research Reactor and Defense Program (DP) facilities. Experience includes probabilistic risk assessment (PRA); design adequacy review and inspection, project and wrsonnel management; earthquake engineering; innovative solutions to complex problems; tec mical consultations; and technical presentations to regulatory agencies.

WORK HISTORY: Senior Consultant,1995 to Present Assistant Chief Engineer,1991-95 Department Manager,1982-91 l Section Manager,1979-82 Supervisor,1974-79 Senior Engineer,1972-74 Engineer,1969-72 1

EXPERIENCE: Design Adequacy Review and Inspection Consulting service to Lockheed Marietta Energy Systems, Inc. - As a peer i

reviewer, performed the independent assessment of the integrated safety q analysis and probabilistic risk assessment of the Paducah Gaseous Diffusion b t Plant with emphasis on the compliance of existing fadlities with current Codes and Standards.

4 Tennessee Valley Authority, Watts Bar Nuclear Power Plant - As a member of the tiger team, performed the independent assessment of Watts Bar Power Plant readiness for fuelload bcense application. Assessment scope included reviewing design, calculations and drawmgs; comparison ofdesign drawings / specifications with as built conditions; examining ahgnment and interface among engineering, modification / construction, and operations / maintenance groups.

Tennessee Valley Authority, Browns Ferry Nuclear Power Plant -

Performed an independent peer review and comparison with industry practice of TVA design standard and computer program (CONAN) for concrete anchorage capacity evaluation.

Tennessee Valley Authority, Bellefonte Nuclear Power Plant -Independent performance of assessment of the Stone and Webster engineering approach to mitigate cost impact and to reduce licensing risk due to floor flexibility induces seismic response.

Tennessee Valley Authority, Sequoyah, Browns Ferry and Watts Bar Nuclear Power Plants - Provided consulting services for the restart effort in .

reviewing seismic designs performed by TVA and other contractors; and in

' answering NRC questions during Design Calculation Reviews.

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Probabilistic Risk Assessment (PRA) or Probabilistic Safety Assessment (PSA)

Brookhaven National Laboratory (BNL) - Consultant to Dr. Joe Hendrie, the former NRC Chairman and the current Chairman of BNL's Reactor Safety Committee, to perfonn technical review of BNL's Probabilistic Risk Assessment (PSA) of the High Flux Beam Reactor (HFBR) for intemal events and seismic event, and to make recommendations for corrective actions based on PRA insight.

Risk Based Regulation (RBR) program using Probabilistic Risk Assessment (PRA) method - Compared vanous quantification methods including fault tree linking, event tree with boundary conditions, and comprehensive support state matrix. Melded the strength of PRA was defense in depth concept. Investi gated its application to technical specification enhancement, se. ection of Maintenance Rule systems and components,

, prioritizing motor operated valve testing of NRC Generic Letter 89-10, etc.

2 Individual Plant Examination (IPE)- Provided critique to Dr. Mike Bohn of Sandia National Laboratories on NUREG/CR-4550, Vol. 4, Rev. I, Part 3 J

" Analysis of Core Damage Frequency: Peach Bottom, Unit 2, Extemal Events."

Technical Presentations to Regulatory Agencies Nukleama Elektrama Krsko Nuclear Power Plant, Slovenia - Technical

! discussion with the Director of Slovenia Administration for Nuclear Safety on Krsko Nuclear Power Plant seismic issues.

Perry Nuclear Power Plant - Working in concert with attomeys from Shaw, Pittman, Potts, & Towbridge of Was ington, D.C., made technical 4

presentation at public hearings of the Nuclear Regulatory Commission

• (NRC) and before Advisory Committee on Reactor Safeguards (ACRS) for the purpose of obtaining fuel load license.

, Consulting Services to Domestic and International Commercial Nuclear Power Plants Nukleama Elektrama Krsko Nuclear Power Plant, Slovenia - Invited by the plant management to meet with the International Commission for Independent Safety Analysis (ICISA) which was organized by the Austrian Green Party. Defended and explained the plant design basis before the ICISA members and their consultants.

Nukleama Elektrama Krsko Nuclear Power Plant, Slovenia - Managed and

' provided consulting services on Probabilistic Seismic Hazard Analysis (PSHA) using EPRI and LLNL methodologies. Sponsored a workshop on PSHA for geologists, seismologists, and geo-physicists from Slovenia, Croatia, and Macedonia at Krsko site.

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Served as a member of Nuclear Utility Management and Resources Council (NUMARC) Ad Hoc Advisory Group NRC in the rewriting of Appendix "A,,to provide unified industry in

new section in 10CFR50.xx for seismic design.

Tennessee Valley Authority, Advanced Light Water Reactor (ALWR) Site Selection Project - Performed and managed the evaluation of constmetion

' access, site preparation, foundation design, optimal site layout for the ultimate heat smks (circulating water system and service water system),

turbine missiles, and cost estimates of Hartsville, MurphyHill, and Saltillo

' sites to select an optimal site for either a four unit evolutionary light water reactor system or an eight-unit passive light water reactor system.

Quangdong Electric Power Bureau of Peoples Republic of China and China Light & Power Company of Hong Kong, Daya Bay Nuclear Power Plant -

Invited by the plant to monitor the technical discussion and to resolve i

difference value for the safe shutdown earthquake among French engineers from Electricite de France and Chines engineers. Made recommendations which were all engineers in the meeting.

1 Kraftwerk Union IKWU), Germany - Performed and managed design I review of 1,300 MW Bushehr Nuclear Power Plant constructed in Iran, ,

4 compared German and U.S. design criteria, and defended the plant design l g basis before personnel of Atomic Energy Organization ofIran. Also y provided technical support to KWU engineering department.

' Brown Boveri Reaktor (BBR), Germany - Performed and supervised aircraft impact resistant design using soft shell concepts. Provided technical consultations and managed Babcock & Wilcox (B&W) primary coolant loop pipe rupture restraint design of Mulheim - Caerlich Nuclear Power

i. Plant.

Florida Power Corporation, Crystal River-3 Nuclear Power Plant -

Investigated causes of delamination of prestressed concrete dome considering effects of prestress loading, shrinkage and creep of concrete, i

arresting effect of coarse aggregates on the crack propagation in concrete structure, behavior of concrete structure under multiaxial stresses.

General Engineering and Construction Provided technical supervision of up to 320 structural en engineers, geotechnical engineers, hydraulics engineers, gineers, civil architects, hydrologists, geologists, seismologists, CAD oprators, designers and drafters in the performance of engineering, eva untion, assessment, design and drafting of steel, prestressed concrete, and reinforced concrete facilities in the commercial nuclear supervised scope of work m, power plants and govemment facilities.

eluded providing input to integrated scheduling Othe and capital and life cycle cost estimate, prepanny specifications and drawings for procurement and construction biddmg documents, performing conformance review of vendor's submittal, carrying out on-site construction 824612 11004 Page 3

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support and inspection. Facilities involved consisted of both new construction renovation of existing facilities.

PC SKILLS: Communications: Proficient in internet applications including e-mail, ftp, 4

telnet, gopher, http

' Presentations: Proficient in Freelance and PowerPoint Repon Writing: Proficient in MSWord and Wordperfect Engineering: Proficient in MathCad, Lotust-2-3, and Excel EDUCATION: Ph.D., Engineering Mechanics, The Pennsylvania State University M.S., Civil Engineering, Duke University

, B.S., Civil Engineering, Cheng Kung Umversity, Taiwan i

REGISTRATION: Registered Professional Engineer since 1973 SOCIETIES: Panicipated in committee work for tlie development ofindustrial standards

, with:

)

American Society of Civil Engineers (ASCE)

American Society of Mechanical Engineers (ASME)

Institute of Electrical and Electronics Engineers (IEEE) 4 Received a Certificate of Appreciation from the Board of Governors of the ASME for valued services provided to the ASME code committee.

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Walkdown Lead, Mechamcal Systems w

Thirty-one years of experience in design and supervision ofnuclear and fossil-fueled power plant piping systems, foreign and domestic.

EXPERIENCE: PARSONS POWER (formerly Gilbert / Commonwealth) since 1965 1996 to Present Kodak BLR #15 - Micro mill addition - Design coal / gas piping, overfire air and transport.  :

Grays Ferry - Designed steam turbine room, heat recovery steam generator, combustion turbine and yard area pipmg.

1995 L.S. Power - Whitewater and Cottage Grove cogeneration units - Designed yard piping for processing.

1993 TVA Johnsonville Power Plant - Desig /,.d e.nd supervised, systems for cogeneration plant supplying steam to Dupont for processmg.

1992 KRSKO, Yugoslavia - Designed post accident sampling system and hydrogen purge systems, on site to retrieve field information.

1991 Santee Cooper, Cross Station, Unit 1 (500 MW)- Designed and supervised mechanical systems for the new fossil fuel plant.

1988-90 Designed and supervised various mechanical systems for:

D b\ V.C. Summer Nuclear Plant Conemaugh Fossil Plant Homer City Fossil Plant l Keystone Fossil Plant Shawville Fossil Plant Crystal River Nuclear Plant G.E. Locomotive Power Plant 1985-87 South Carolina Electric & Gas Company, V.C. Summer Nuclear Power Plant - Involved in classification of equipment and system piping modifications.

1985 Mechanical Design Section Manager - Supervised 48 people on various nuclear, fossil and industrial projects.

1980 85 Drafting Project Supervisor - Supervised and performed field walkdown of building services, piping, and instrumentation and control systems in mechanical drafting for the following projects:

Potomac Electric Power Company, Chalk Point Station, Balanced Draft Conversion.

South Carolina Electric & Gas Company, V. C. Summer Nuclear Station, Unit 1 (900 MW).

Virginia Electric & Power Com any, Mt. Storm Station, Induced Draft Fan Addition, and Chesterfi d Station, Balanced Draft Conversion.

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1981-82 Brown Boveri, West Germany - Leamed codes, regulations and requirements for a nuclear power plant. Supervised conceptual piping design for Neupotz Nuclear Power Plant.

1979 General Public Utilities Corporation, Three Mile Island, Unit 1 - Designed piping spools suspected of having intergranular stress corrosion crackmg.

1977 4 0 Drafting Project Supervisor (Squad Leader), Mechanical Drafting - South Carolina Electric & Gas Company, V.C. Summer Nuclear Station, Unit 1 (900 MW) - Supervised up to 24 peo?le in the design and development of all the piping, drams, ventilation, and instrument systems.

1970-72 Responsible for the field design walkdown of systems and supervising the following fuel oil conversion projects: >

Buzzard Point, Potomac Electric Power Company, Norwalk Station Nonheast Utilities, Devon Station Northeast Utilities, Westport Station Baltimore Gas & Electric Company, Rivenide Statiou Baltimore Gas & Electric Company, Gould Street Station Baltimore Gas & Electric Company, C.P. Crane Station Baltimore Gas & Electric Company, Eyler Station >

Metropolitan Edison Company Kansai Electric Power Company, Takahama Nuclear Station, Unit 1 (826 MW)- Checked piping systems.

1969-70 Piping designer and checker - Baltimore Gas & Electric Company, Perryman, Westport, and Riverside Gas Turbine Peaking Units.

1967-69 Piping designer and checker - Bethlehem Steel Company, Burns Harbor Project - Units consisted of boiler houses, turbo-blowers, and turbine generators.

1966-67 Designer / Drafter - Civitavecchi Power Plant, Italy, (fossil-fueled). Also designed the boiler room and circulating water pump house for U. S. Steel Company,Irwin Works Plant.

1965-66 Drafter - Rochester Gas & Electric Company, R.E. Ginna Nuclear Station, Unit 1 (490 MW)- Responsible for the flow diagrams and isometric systems.

Pennsylvania Electric Company, Keystone Station, Units 1 & 2 (900 MW each) - Responsible for flow diagrams and systems.

1960-65 Orr & Sembower. Readine. Pennsylvania Drafter / Designer - Powermaster packaged boilers.

,- 1959-60 Aetna Steel Comoany. Pottsville. Pennsylvania Drafter and Frame Designer I.

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1955-59 U. S. Air Ferce EDUCATION: Tool and Dye, Mechanical Drafting, and Mathematics, Chicago Technical College 1959-60 i

Mechanical Design, U. S. Air Force,1957 j Foundations of Management, Gilbert / Commonwealth,1978 i

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Senior Electrical Engineer Over twenty-four years of experience in electrical engineering, engineering management and project management of original design and continuing service projects for nuclear and fossil-fueled generating stations.

EXPERIENCE: PARSONS POWER (formerly Gilbert / Commonwealth) since 1972 1996 to Present Task Manager, Florida Power Corporation, Crystal River Unit 3 -

Responsible for the Class IE DC Distribution System Failure Modes and Effects Analysis (FMEA).

1995-96 Project Manager for development of a PC version of the CKS mainframe computer program for cable routing.

1994-96 Project Manager - System analysis and design modifications for two GPUN and five Entergy units for compliance with Nuclear Regulatory Commission requirements in 10CFR73 for Protecti m Against Malevolent Use of Vehicles at Nuclear Power Plants.

1988-96 Project Manager, General Public Utilities Nuclear (GPUN), Continuing Services - Responsible for all aspects of Gilbert / Commonwealth's semees rendered to GPUN's corporate office and Oyster Creek and Three Mile Island nuclear generating stations, including:

Plant-wide installation of maintenance platforms.

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Outage support.

Computer system upgrades. ,

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Heat sink protection system upgrades.

Design basis documents for electrical and mechanical systems.

NI source range upgrades.

Digital control system / digital turbine control system support.

SQUG engineenng support.

TMI-2 post defueling monitored storage modifications. '

Station blackout rule diesel generator modifications.

Cask drop analysis.

Instrument shop relocation and control tower renovation.

Instrument air upgrade air compressor addition.

Regulatory Guic:e 1.97, instrument relocation and upgrade.

1995 Performed system reviews for the Temelin Nuclear Plant for Westinghouse International.

1982-88 Project Engineering Manager - General Public Utilities Nuclear, Three Mile Island, Unit 1, Continuing Services - Responsible for engineering management of continuing service design and consulting tasks. Assisted project manager in admimstrative requirements such as engineering liaison, project procedures, task scope / schedule control and design control. Major tasks included 10CFR50 Appendix "R" plant evaluation studies and modifications, remote shutdown system, emergency feedwater control system safety grade cabling and raceway; Powdex waste reserve processing system, chlorine detection system, emergency feedwater component (Q J upgrades, safety parameter display system and on-site technical support facility.

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l O 1979-82 Electrical Project Engineer - General Public Utilities Nuclear, Three Mile l Island, Unit 1, Restart modifications - Tasks included NUREG 578 i requirements, restart report commitments and 10CFR50 Appendix "A" Fire I Protection Modifications. Completed the following major electrical design and wiring tasks: emergency feedwater system additions of autostart, flow indication and control valve manual loaders, ESAS reset from control room, partial containment isolation on-line break, containment isolation on RB pressure, reactor anticipatory trip on turbine trip hydrogen recombiners, IE power supply to pressurizer heater, remote shutdown mstrumentation and isolation, contamment hydrogen monitors, incore thermocouples, decay heat i system vibration monitors, fire detection and protection systems, reactor l building sump level indication, reactor coolant system high point vents, electrical penetration assembly EQ terminations,ICS altemate power supply and addition of new industrial coolers.  ;

1976-79 Project Electrical Engineer - Pennsylvania Power & Light Company, Martins Creek; Bmnner Island; and Montour Station, Continuing Services -

Major tasks included a large auxiliary boiler addition, stack opacity monitor, Amertap system modifications and boiler feedwater valve control system additions.

Project Electrical Engineer - Metropolitan Edison Company, Three Mile Island, Unit 2, Recovery - HPD evaporator crystallizer facility design and fuel handling crane modifications.

O V Electrical Engineer - Metropolitan Edison Company, Titus Station -

Modifications for a forced draft cooling tower backfit including medium voltage switchgear, MCCs, cabling and control components.

Electrical Engineer - Gilbert / Commonwealth, Reference Fossil Power Plant - Responsible for electrical auxiliary system design.

Electrical Engineer - Metropolitan Edison Company, Three Mile Island, Unit 1 - Design of an industrial waste filter system and security system.

Electrical Engineer - Elmo Bumpy Torus Fusion Proof of Principle Demonstration Reactor, - Responsible for low voltage distribution and high frequency grounding system.

1975-76 Chief Resident Engineer and Site Electric Liaison Engineer -

Commonwealth Associates, CAPCO, Bruce Mansfield Units 1,2, & 3 (coal-fired, 900 MW each with wet scrubber SO; removal systems) - Tasks included late construction start-up and commissioning of Unit 1, late constmetion of Unit 2 and early construction of Unit 3.

1972-75 Electrical Engineer - Pennsylvania Power & Light Company, Martins Creek, Units 3 & 4 - Responsible for specification, venc or selection and installation design for major equipment including auxiliary transformers, generator bus duct, medium voltage and low voltage switchgear, emergency q

g diesel engine-generators, main turbine generator auxiliary, protective systems and motors.

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Baltimore Gas & Electric, Brandon Shores, Units 1 & 2 - Electrical auxiliary system design. l EDUCATION: B.S., Electrical Engineering, Lowell Technological Institute (U Mass, 1 Lowell),1972 Additional Courses:

) Power System Relaying, Institute of Electrical and Electronics Engineers Principles of Law for the Engineer, Gilbert / Commonwealth Management 18, B.K. Scanlan Foundations of Management, Gilbert / Commonwealth Gilbert / Commonwealth Project QualificationManagement of Safety Related and Supervisory Equipment, Gil Training,bert/ Commonweal Effective Reading, Xerox Financial Management, Gilbert / Commonwealth Liability and Contract Management, Gilbert / Commonwealth Total Quality Advantage Training, Gilbert / Commonwealth

, Mastering Business Development, Sales Management Systems, Inc.

Teamwork and Leadership, GPU Nuclear Corporation Safety Process Review, GPU Nuclear Cor wration TQA Facilitator Training, Organizational Jynamics, Inc.

4 Optimization of Service Organizations, Dr. W. Edwards Deming

_ REGISTRATIONS: Engineer-in-Training - Massachusetts (1972)

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V Professional Engineer - Pennsylvania (1978)

SOCIETIES:: Institute of Electrical and Electronics Engineers Member,1978 Senior Member,1988 l l

Vice Chairman, Lehigh Valley Section,1983 Chairman, Lehigh Valley Section,1984 PUBLICATIONS: Co-authored, " Design Features for Reference Coal Fueled Generating Station Auxiliary Electric Power Systems," Presented at IEEE PES i

Winter Meeting,1978.

Co-authored, " Nuclear Power plant Digital Instrumentation and Control

, Modifications," Presented at the IEEE 1992 Nuclear Science Symposium.

Co-authored, " Protection of Nuclear Plants Against Vehicular Bombs,"

Presented at the American Power Conference,1995.

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v; Electrical Engineer Eleven years of experience in electrical engineering and project management for generating station, substation, and industrial projects.

EXPERIENCE: PARSONS POWER (formerly Gilbert / Commonwealth) since 1989 1989 to Present Tennessee Valley Authority - Project Electrical Engineer - Responsible for tasks being performed for fossil and hydro generating units throughout the TVA system. Projects include Low NOx retrofits, control system upgrades, continuous emissions monitoring, lighting, and hydro generator upgrades which include static exciter replacements, relay upgrades, generator cable replacements and step-up transformer replacement.

City of Lakeland, Florida, McIntosh Unit 2 - Perfonned an electrical system reliability study consisting of equipment aging assessments and calculations of power flow / voltage drop, short circuit, surge protection, coordination and de system equipment sizing.

City of Oak Ridge, Tennessee - Addition of a fourth,10 MVA transfonner bay to the 69 kV - 13.8 kV Substation 300. Design of a new 161 kV - 69 kV substation to provide a second TVA power delivery point for the city.

ESI Energy - Due diligence review for two 35 MVA pulverized coal e

t generating units located in Trona, California.

i Martin Marietta Energy Systems, Oak Ridge Y-12 Plant - Performed review ofover one hundred 480 V unit substations containing 800+ circuit breakers to evaluate the adequacy of circuit breaker selection and application. Study involved calculation of fault cunents to check for proper interrupting duty, evaluation if circuit breaker settings adequately protected the connected '

cable, and an evaluation if coordination with the main unit substation 4 breaker was adequate. Review was accomplished utilizing databases and elec.ronic report generation to provide a uniform evaluation method and increase efficiency. Pcrformed insulation coordination study of the 161 kV system.

1 South Carolina Electric & Gas Company, V.C. Summer Nuclear Station -

Performed studies and calculations on the following topics: Class 1E ac and de voltage drop and short circuit, degraded voltage relay setpoint, low 4

voltage breaker coordination and MOV thrust margins. Created installation packages for the replacement of Class 1E batteries and for modifications to

the condensate system. Performed analysis for Station Blackout and Appendix R issues. Revised electrical calculations and procedures to minimize the effon rec %d for tracking cumulative effects. Interfaced with NRC personnel during Electrical Distribution System Functional Inspection audit.

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s Potomac Electric Power Company - Creation of an electrical model and a  ;

base set of calculations for the Morgantown Generating Station to suppon Clean Air Act modifications. Reviewed the Potomac River Generating Station electrical station service system as a possible contributing factor to a transmission system blackout event. This included performing an  !

cquipment aging evaluation for all of the major items of equipment in the l electrical auxiliary system. l l

Pennsylvania Electric Company, Shawville Generating Station - Performed I de system analysis for the addition of UPS systems for Units 1,2,3 and 4.  !

Created specifications and procurement documents for batteries and battery chargers.

Thermatrix, Inc., Tennessee - Conceptual design and cost estimates for i mobile electrical equipment to suppon an environmental remediation i project.

Nonh American Rayon, Tennessee - Powerhouse assessment for i replacement of six existing generating units with combustion turbines and i heat recovery steam generators.

O Tenn Luttrell, Tennessee - Electrical power system design for the addition

( of a Cimprogetti coal-fired vertical lime kiln. Prepared equipment

( specifications and performed bid evaluations.

Hoffman La-Roche Vitamins and Chemicals, New Jersey - Conceptual design for the electrical upgrades required at the three on-site substations for facility expansion and increased cogeneration.

ALCOA Terunssee Operations - Demand, power flow, voltage drop and shon circuit studies for the South Plant electrical system.

Tennessee Valley Authority, Bellefonte Nuclear Plant - Performed 125 Vdc equipment adequacy evaluations by performing detailed calculations of the Class IE de system.

Pennsylvania Power & Light Company, Susquehanna Steam Electric Station - Responsible for investigation of high voltage transient within diesel generator exciter circuit.

Florida Power Corporation, Crystal River Unit 3 - Performed revalidation of station ground grid and development of grounding design criteria.

U.S. Depanment of Energy, Advanced Neutron Source Project - Perfonned conceptual design of grounding and lightning protection systems for the facility and associated substations.

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Wisconsin Electric Power Company, Point Beach Nuclear Plant - Co-author of the 480 V system design basis document and reviewer for the 345 kV System design basis document.

4 American Electric Power, D. C. Cook Nuclear Station - Independent validation of the DAPPER and A_ FAULT ac analysis programs.

Nuklearna Elektrarna KRSKO, KRSKO Nuclear Power Plant - Conceptual design and equipment specification for the replacement of Class IE inverters. Worked with a Slovenian design firm (IBE) as partners in developing modifications to the essential service water system. Created a computerized Station Blackout coping calculation for the Class IE batteries which enabled the client to defer replacement of the existing batteries.

National Spokesman for the Electrical Energy Industry (US Council for l Energy Awareness / Nuclear Energy Institute) - Made numerous appearances on radio and television stations throughout the United States.

1985-89 Potomac Electric Power Company. Washincton. D.C.

Substation Engineer, Lead Engineer / Project Manager - Duties included electrical design, equipment specifications, bid evaluations, project

/7 budgeting, technical procedures and coordination ofinternal design groups, d construction personnel and outside A/E firms.

, Projects included: 230 kV and 69 kV switchyard design for a gasification combined cycle generating station, the upgrade of a coal yard substation  !

without effecting coal handling operations, plant life extension projects for two fossil generating stations including the upgrade of vital ac systems and vacuum conversion of air magnetic circuit breakers, substation ground grid design, ground grid integrity testing, stray voltage investigations, interfacing of SCADA equipment and the development of a yearly system plan for the 69 kV transmission system.

1984-85 Rural Electrification Administration. Washincton. D.C.

2 Responsible for all T&D engineering and loan applicstion review for the ntral electric cooperatives in the states of Kansas, Nevada and Oregon, with primary emphasis on substation design review. Developed spreadsheet progran for determming insulator swing angles.

EDUCATION: M.S., Engineering Management, Catholic University of America, Washington, D.C.,1988 B.S., Electrical Engineering, University of Cincinnati, Cincinnati, Ohio, 1984 Additional Courses:

Grounding and Shielding Electronic Instrumentation, University of

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Missouri, Silver Spring, Maryland,1985 Persons Power Groe I24612-11004 Page 3

O Substation Grounding Practice and Analysis, Georgia Tech, Atlanta, Georgia,1986 Practical Application ofIEEE Standard 80,IEEE Winter Power Meeting, New York, New York,1987 Power Transformers, Marquette University, Milwaukee, Wisconsin, 1987 Modem Power Systems Analysis, Auburn University, Auburn, Alabama, 1987 Cable Condition Monitoring Workshop, EPRI, San Francisco,

Califomia,1988 )

j Electrical Power System Transients and Protection, Georgia Tech, l Atlanta, Georgia,1988 4

System Restoration, Potomac Electric Power Co., Washington, D.C.,

1988 Stationary Batteries, Impell Corporation, Washington, D.C.,1989 Power System Design and Analysis,IEEE Lehigh Valley Section,1991 Fundamentals of Lighting, Illuminating Engineering Society, Lehigh University,1992 Large AC Machines,IEEE Lehigh Valley Chapter,1992 News Media Communication, U.S. Council for Energy Awareness, Washington, D.C.,1993 Medium Voltage Adjustable Frequency Drive Systems,IEEE Lehigh (r

Valley Chapter,1993 Courses Taught:

Historical Development of Metalclad Switchgear, Gilbert / Commonwealth,1989 Metering, Gilbert / Commonwealth,1990 i

Design of Generating Station Electric Power Service Systems,  !

Gilbert / Commonwealth,1992 Basics of Specifying Electrical Power Equipment, IEEE Lehigh Valley Section,1992. Developer of the course and instructor for the sessions on transformers, batteries and unintemiptible power supply systems. l Short Course on the Use of the DAPPER AC Analysis Software, Co-4 Instructor, American Electric Power, Columbus, OH,1992 De Systems Analysis, Gilbert / Commonwealth,1993 Uninterruptible Power Supply Systems and Battery Chargers,

~ Gilbert / Commonwealth,1993 Use of the DAPPER AC Analysis Software, Gilbert / Commonwealth, l 1993,1995 Fundamentals of Grounding, Gilbert / Commonwealth,1994,1995 l Cable Aging Management, Korea Power Engineering Company, Reading, PA,1994 De Systems Analysis, Nukleama Elektrarna KRSKO, KRSKO, Slovenia, 1

1994 i

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i REGISTRATION: Professional Engineer - Maryland (1989), Pennsylvania (1989), Tennessee (1994), NCEES Record Established (1995) l SOCIETIES: Senior Member,IEEE '

Member, IEEE Power Engineerir.g Society Member,IEEE Electromagnetic Compatibility Society <

Chairman, task force for IEEE Standard 1050, " Guide for Instrumentation l and Control Equipment Grounding in Generating Stations" Member, task force for IEEE Standard 665, " Guide for Generating Station Grounding" Member, task force for IEEE Standard 741, " Standard Criteria for the i Protection cf Class IE Power Systems and Equipment in Nuclear Power Generating Stations" Member,IEEE PES Station Design Subcommittee Member, American Nuclear Society 4

PUBLICATIONS: "Can Anyone Determine Remaining Life in Power Plant Cable?", Electrical World, August 1988.

Co-author, "Use of Single-Point Grounding for Instrumentation and Control Systems Installed in Existing Generating Stations", IEEE/ PES 1989 Winter Power Meeting, February 1989.

O "Short-Circuit Force Calculations in Rigid Bus Design", Pennsylvania V Electric Association Electrical Equipment Committee Winter Meeting, February 1989.

Co-author, " Vacuum Retrofit of Air-Magnetic Circuit Breakers at the Potomac Electric Power Company", Pennsylvania Electric Association Electrical Equipment Committee Winter Meeting, Febmary 1989.

" Calculations for Degraded Voltage Relays at Nuclear Power Generating Stations", Pennsylvania Electric Association, September 1991.

" Analyzing Auxiliary Systems in Nuclear Generating Stations",IEEE Computer Applications in Power, July 1992.

"A Review of Manufacturer's Recommendations for the Grounding of Distributed Control Systems in Generating Stations", IEEE/ PES 1992 Winter Power Meeting, January 1992.

"A Recommended Approach for Calculating Degraded Voltage Relay Setpoints for Nuclear Generating Stations", IEEE/ PES 1993 Winter Power Meeting, February 1993.

" Configuration Management of Electrical Engineering Data", Nuclear Plant Journal, March / April,1993.

Co-author, "CAA (Clean Air Act) Forces Utilities to Re-evaluate Station Service", Power, August 1993.

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I "CM (Configuration Management) - Make This Nuclear Mystery a Valuable Help to Your Plant", Power, September 1993.

Persons Power Grog 824612-11004 Page5

Co-author, " Optimization of Station Battery Replacement", IEEE Nuclear Science Symposium and Medical Imaging Conference, November 1993.

Co-author, " Elimination of Direct Current Distribution Systems in New Generating Stations", IEEE Nuclear Science Symposium and Medical

, Imaging Conference, November 1994.

Co-author, " Revision ofIEEE Standard 741 to Provide Needed Guidance in Setting Degraded and Loss of Voltage Relays and Their Associated Time Delays", IEEE Nuclear Science Symposium and Medical Imaging Conference, November 1994.

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• (v) Senior Electrical Engineer Thirty years of extensive experience in all aspects ofelectrical engineering design and project management for electrical power generating stations.

EXPERIENCE: PARSONS POWER (formerly Gilbert / Commonwealth) since 1966 l 1995 to Present Project Electrical Engineer - Vortec Corporation - Provide electrical engineering for a glass vitrification plant at the Paducah Gaseous Diffusion works, a Department of Energy site. The plant processes contaminated soil through a vitrification process. Design is unique in that the entire plant is l capable of being relocated to another site with minimal expense. Duties include system power studies, physical design of the electrical distribution system and routing of all power, control, and instrumentation circuits.

1996 Project Manager / Construction Manager / Electrical Engineer - IBM, Poughkeepsie, New York, Building 1 Vacate Program - Provided job functions for facility modification, coordinated all disciplines within engineering organization. Managed construction trades and provided electrical engineering consultation.

1994 -95 Project Electrical Engineer - Performed various responsibilities in the electrical engineering area, including a con:eptual design of a 40 MW 2

Wood Chip Bumer for an Independent Power Producer (IPP), design reviews for electrical engineering calculations and modifications, and l (OI) origination of calculations in support of design modifications. Performed electrical engineering responsibilities for the Chef Francisco project, which involved relocating a soup manufacturing facility from Eugene, Oregon to King of Prussia, Pennsylvania. Duties included circuit design for process facilities as well as general electric distribution. Assisted in the prepamtion of design modification for Procter and Gamble paper processing plant.

1993-94 Project Electrical Engineer - Performed several responsibilities in the electrical engineering area including design verification of the V.C. Summer relay coordinations study. Pennsylvania Power & Light, Susquehanna Units 1 & 2 plant electrical system modification preparation and verification; origination and verification of DC circuit and AC calculations.

1991-93 Project Electrical Engineer - Advanced Neutron Source - Conceptual design of the plant electrical system for a new research reactor facility to be located at the Oak Ridge National Laboratory, Oak Ridge, Tennessee. The design involved the arrangement of the one line diagram, short circuit studies, motor starting study, equipment sizing and all other necessary functions to prove project feasibility and provide a cost estimate suitable for Congressional funding.

1990-91 Tennessee Valley Authority, Bellefonte Nuclear Plant - Assisted in the calculation assessment program and report preparation as part of a study conducted by MPR Associates to determine the cost required to complete

( the construction and license the plant.

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Project Electrical Engineer - Public Service Electric & Gas, Salem and Hope Creek Stations, General Senices Agreement Contract (GSA) - l Responsible for the electrical engineering discipline for plant modification i tasks for Salem, Units 1 & 2 and Hope Creek.

1983-90 Project Engineering Manager - Florida Power Corporation, Crystal River,  ;

Unit 3, Continuing Services Project - Managed engineering efforts for all disciplines for tasks such as equipment qualification, Appendix "R," station blackout, feedwater upgrade and general modification work. Duties ,

included scoping engineering tasks, technical control and content of tasks,  !

man-hour and cost estimating, scheduling and budget control, client l interface and procedure / program interpretation. Coordination of the Design Disciplines in performance ofinternal G/C and client Quality As.arance Audits, including resolution of audit concems and findings at the conclusion of the audits. Assumed Project Manager function when Project Manager was unavailable. Also included Site Liaison / Manager duties during l Refuel V and VI.

, Lead G/C Electrical Engineer - Tenera, Comanche Peak Nuclear Power Plant - Ten-month assignment as part of the Tenera Design Adequacy Program review. Supervised six electrical engineers in performing Quality p Design Reviews. The Design Adequacy Review used the " vertical slice"

( audit approach method using the Emergency Feedwater System t.s the plant system to receive the detailed review.

1982-83 Supervising Electrical Engineer - General Public Utilities, Three Mile Island Nuclear Station, Unit 1; Florida Power Corporation, Crystal River Nuclear Station, Unit 3; and Virginia Electric Power Company, North Anna and Surry Stations - Surrvised continuing services electrical engineering efforts. Also overall task management responsibilities for certain Crystal River Unit 3 backfits inc;udin;; -energency feedwater and remote shutdown.

1982 Audit Team Member - Public Service ofIndiana, Marble Hill Plant - Served as audit team member in assessing the Commonwealth / Lord Joint Venture's compliance with quality requirements. (Commonwealth / Lord Joint Venture was the electrical contractor for Marble Hill Plant.) Audit included personnel interviews, procedure reviews, installation inspections, records retention check, training assessment, etc.

Pennsylvania Power & Light - Three-month assignment in the Quality Assurance Department to organize and assist in performance of an audit to assess the Susquehanna Steam Electric Station "As Built" Program. Audit was completed in six weeks and determined that the program was not completely in compliance. The remainder of the three-month period was spent assessing the SSES compliance with NUREG 737. This assessment p was positive in showing that modifications were in process to address the v concerns.

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l ivn 1980-82 Project Engineering Manager - General Public Utilities, Three Mile Island Nuclear Station, Unit 1 - Managed engineering disciplines of electrical,

! mechanical, and instrumentation and control for restart. Duties included l scoping engineering tasks, man-hour and cost estimating, scheduling, and  !

l budget control. Also coordinated the Design Disciplines in the performance l ofinternal G/C and external (both client and NRC) Quality Assurance audits.

1979-80 Project Electrical Engineer - General Public Utilities, Three Mile Island Nuclear Station, Units 1 & 2 - Assisted Plant Engineering Staff during .

nuclear accident and recovery. Prepared engineering modifications to l

restart Unit 1. Provided testimony in front of Atomic Safety and Licensing  ;

Board pertaining to restan Unit 1.

1974-79 Project Electrical Engineer - General Public Utilities, Three Mile Island Nuclear Station, Units 1 (871 MW) & 2 - Responsible for continuing engineering services. Also, coordinated Unit 2 cable routing data processing program Rochester Gas & Electric Corporation, R.E. Ginna Nuclear Power Plant,  ;

Unit 1 (490 MW) - Coordinated electrical design for all volatile treatment I condensate demineralizer installations.

1971-74 I oject Electrical Engineer - General Public Utilities, Three Mile Island '

Nuclear Station, Units 1 (871 MW) & 2 - Responsible for completion of engineering design and licensing of Unit 1, and provided coordination for Unit I with Unit 2 design interface problems.

Gulf General Atomic, HTGR Nuclear Generating Station (1140 MW)-

Assisted in balance of plant studies.

1969-71 Project Electrical Engineer - Designed gas turbine generating stations, including short circuit studies, plant layout, physical electrical distribution, application of equipment, electrical construction specification, underground ducts, review of purchased turbine package, and substation work on the following plants:

Baltimore Gas & Electric Company, Riverside, Unit 6 (125 MW),7 & 8 (40 MW total)

Baltimore Gas & Electric Company, Perryman, Units 1,2,3 & 4 (200 MW total)

Metropolitan Edison Company, Titus Station, Unit 5 (20 MW)

Metropolitan Edison Company, Ponland Station, Unit 4 (20 MW).

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U 1966-69 Junior Electrical Engineer - Pennsylvania Electric Company, Homer City Generating Station (660 MW each)- Involved in design of control systems, cabling and physical wire checking; application, evaluation and purchase of equipment; and startup of two mine-mouth coal-fired units.

EDUCATION: B.S., Electrical Engineering, The Pennsylvania State University,1966 I

REGISTRATION: Professional Engineer - Pennsylvania (1970), Florida (1990) and New Jersey (1991).

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Electrical Engineer Electrical engineering experience as related to nuclear power generation projects.

EXPERIENCE: PARSONS POWER (formerly (Gilbert / Commonwealth) since 1972 1994 to Present Pennsylvania Power & Light Company (PP&L) - Support site engineering in performance of an emergency modification involving Susquehanna Steam Electric Station's (SSES) perimeter security system, and also perform i,ite engineering staff duties. Provide onsite direction for modification installation during current outage.

Pennsylvania Power & Light Company, Allentown - Finalized and issued 230 kV packages required for Unit 1 outage at SSES. Replaced PP&L task engineer (6 month training assignment), coordinated packages with field installation engineers, performed presentation of packages at both SSES and Allentown for review / comment phase, and obtained final signatures in order to issue packages. Supported packages with Electrical Calculations and Analysis (Voltage drop, Current Fault Analysis for new CT Burdens, Equipment Rating Capabilities, Emironmental and Seismic Impact

' Analysis). During SSES Unit 1 outage (April 1995), was res onsible for one of three electrical installation teams in sup > ort of 230 k modification installation. Directed team in wiring of contro: cabinet in switchgear room.

Supported modification package to replace electro-mechanical 230 kV line momtoring e,quipment with new solid state equipment and fiber optic communication cable. Responsible for design mput, electrical calculations

(" and analysis (voltage drop, equipment rating capabilities, em'ironmental and l

seismic), Bill of Material, DCP Backup Package, support design /

l engineering interface, ALARA, Appendix R, FSAR change, Specification '

Change Notice, design description, and overall modification analysis (SEA).

Pennsylvania Power & Light Company - Performed ampacity and voltage drop calculations for various tasks including those associated with Generic Letter 89-10.

Task Engineer - SSES - Produced MSR and DCP package to provide permanent docking station for vendor demineralizer trucks, associated piping, power instrumentation, interfaces and alarms necessary to utilize vendor trucks in lieu of existing demineralizer system.

1992-93 Project Electrical Engineer - Public Service Electric & Gas Company, Salem Generating Station, Units 1 & 2, and Hope Creek Generating Station - Responsible for overall electrical admmistration.

Invormd in security upgrades at both Salem and Hope Creek Generating Strions for penmeter intrusion involving infrared and fiber optic equipment.

Also, led task to upgrade Salem communications system from a "one-channel party system" to a "five-channel party system" without 1 changing the two-conductor connecting cable.

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(v 1991-92 Task Engineer - Tennessee Valley Authority, Bellefonte Nuclear Power Plant - Responsible for developing position papers that document the Bellefonte technical positions and principal methods and criteria for use in resolving cable concerns with the NRC.

1989-90 Project Electrical Engineer - Florida Power Corporation, Crystal River Nuclear Power Plant, Unit 3 - Responsible for overall electncal administration.

1988 Project Electrical Engineer - Philadelphia Electric Company, Peach Bottom Atomic Power Station - Established an electrical site team acting as an extension of Philadelphia Electric Company's Nuclear Engineenng

, Department to deal with Units 2 & 3 electncal restart issues.

Involved in the development of a spare parts program and headed an electrical team to resolve concerns resulting from NRC shutdown order.

1986 Project Electrical Engineer - Tennessee Valley Authority, Watts Bar Nuclear Power Plant, two voltage drop analysis efforts - Responsibilities '

included coordination of data gathering, circuit analysis and generation of computer program to perform calculations.

1985 Project Electrical Engineer - Cleveland Electric Illuminating Company,

-m Perry Nuclear Power Plant - Responsible for overall electrical Q administration.

Also involved in responding to NRC " Integrated Design Inspection" (IDI) and Appendix "R" audits. Supported control room human factors effort.

1983-84 Assistant Electrical Project Engineer - Cleveland Electric Illuminating Company, Perry Nuclear Power Plant - Responsible for monthly and quarterly reports, schedules and budgets, wiring and systems administration and coordination, and field interface. Acted as project engineer in the absence of the project engineer.

1981-82 Lead Wiring Engineer - Cleveland Electric Illuminating Company, Perry Nuclear Power Plant - Responsible for the technical administration and schedule coordination of all wiring-related activities. Activities included elementary design, field and home office ECNs, interconnection wiring diagrams and General Electric Company Nuclear Steam Supply Systems coordination.

Perry Licensing Coordinator, Electrical Department - Responsible for all licensing-related activities other than those for equipment qualification.

1974-81 Electrical Engineer - Cleveland Electric Illuminating Company, Perry Nuclear Power Plant -In charge of the nuclear steam supp: y systems.

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O General Electric Company, Power Generation Control Complex (Control ,

Room) - Handled plant communications including telephone and offsite '

cable acquisition and qualification,125 Vdc distribution system including inverters, batteries and battery chargers, and installation specification. I 1973-74 Lead Engineer - Pennsylvania Electric Company, Continuing Service Projects on Fossil Fueled Plants - Work involved precipitator additions, review and design of a double-ended unit substation, ash handling and equipment shop addition.

'. 1972-73 Co-op Student - Florida Power Corporation, Crystal River Nuclear Power Plant - Participated in the review of vendor drawings for power generation systems. Developed calculations for cable pulling tensions involving varied conductor sizes in one conduit. l 1969-71 City of Readine. Pennsylvania l Drafter - Redevelopment Authority - Developed acquisition, condemnation l and plot plan drawmgs.

EDUCATION: B.S., Physics, Albright College,1976 l Electrical Engineerin Additional Courses: g Cooperative Program, Drexel University,1970-73 Seminar on Nuclear and Fossil Plant Equipment, General Electric,1974 Q Practical Symmetrical Components, IEEE,1978 Q Seminar on Boiling Water Reactor Technology, General Physics Corporation,1980 ,

REGISTRATION: Engineer-in-Training - Pennsylvania (1978) i i

i O l Parsons Power Onze I/97 17527 Page 3

m. Senior Control Systems Engineer b

Thirty-four years of experience in the design of nuclear and safety instrumentation for nuclear '

power generating plants and in R&D ofnucleonic instrumentation for PUREX nuclear fuel reprocessing plants. Primary areas of expertise include consulting and task management in the following areas: Radiation monitoring systems design, procurement, assessment, improvement, I replacement studies, design basis document and calibration for Nuclear Power Plants and '

Nuclear Fuel Reprocessing Plant including High Level Waste. Experienced in reactor protection and engineered safety system design, procurement, replacement studies, design basis document, setpoint calculations and methodologies, RFI/EMI and V&V. Also, experienced in controls and instrumentation systems including post accident monitoring, seismic instrumentation, in-core and  ;

out of core instrumentation, control rod control for Nuclear Power Plants and process l instrumentation for Fuel Reprocessing Plants including High Level Waste systems.

EXPERIENCE: PARSONS POWER (formerly Gilbert / Commonwealth) since 1967 1985 to Present Senior Nuclear Control Systems Consultant - Responsible for technical j consultations and design reviews of nuclear instmmentation and control l

designs relating to reactor trip systems, safety features actuation systems, seismic and environmental equipment qualification, electrical separation, radiation monitoring, and human factor engineering. Develop methodologies for and review calculations ofsafety-related set points, including effects ofinsulation resistance for PWR and BWR plants.

Task manager and principal investigator for the following:

O Department of Energy - Soviet-Designed Reactor Safety Program -

Q Preparation of the technical requirements for Safety Parameter Display System (SPDS) to be implemented at all Soviet Designed RBMK type Reactors. Selection and contract supervision of t ae SPDS vendor.

4 Florida Power Corporation, Crystal River, Unit 3 - Prepare a Technical Guideline document defining the requirements for implementing safety related analog to digital system replacements.

Carolina Power & Light Brunswick Unit 1&2 - Refurbishing of the station battery ground detector.

Florida Power Corporation, Crystal River, Unit 3 - Review and assessment of Merlin Gerin In-duct stack radiation monitor Pennsylvania Power & Light, Susquehanna, Unit 1&2 - Reviewer of setpoint calculations for Florida Power Corporation, power uprate. Crystal River, Unit 3 - Rev standard Technical Specification for Engineered Safeguard Actuation System, Leakage Monitoring, etc..

GPUN/ Jersey Central, Oyster Creek Nuclear Plant - Review of selected

safety related setpoints and methodology against ISA - 67.04 standard.

Oak Ridge National Laboratory (ORNL), Advanced Neutron Source -

Review of the technical requirements for the Neutron Source Instrumentation and Control Computer Systems incorporating reactor protection, Class IE Plant Control and Data Acquisition functions.

GPU/ Jersey Central, Oyster Creek Nuclear Plant - Preparation of design basis document for the radiation monitoring system.

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/N U l l GPUN, Three Mile Island, Unit 1 - Development of a Verification and Validation (V&V) Program for the implementation of the DCS project.

Tennessee Valley Authority, Bellefonte Unit 1&2 - Review of the solid state control system for adequacy to safety criteria applicable to safety related control systems.

Nukleama Elektrama, Krsko Unit 1 - Design of sampling lines for plant  !

) vent header monitoring system and secondary side condenser air '

ejector monitoring system. Determination of sampling losses for radioactive iodine and particulate.

General Public Utility Nuclear, Three Mile Island Unit 1 - Preparation of Design Basis Documents for the Engineered Safeguards Actuation System (ESAS) and Radiation Momtoring System (RMS).

Public Service Electric & Gas, Salem Units 1 & 2 - Technical supervision of the replacement of 15 radiation monitoring channels with microprocessor based equipment.

Philadelphia Electric Company, Peach Bottom Units 2 & 3 - Establish technical requirements for Torus vent radiation monitors. Establish equipment specification requirements.

Florida Power Corporation, Crystal River, Unit 3 - Review reliability and  ;

maintenance of the radiation monitoring system, and formulate attematives and suppon cost estimates for refurbishing or replacement of the system.

( Florida Power Corporation, Crystal River, Unit 3 - Prepare a f-methodology document for the calculation of safety-related mstrument setpomts.

Pennsylvania Power & Light, Susquehanna, Unit 2 - Review adequacy of the ARM's response to a spent fuel pool resin discharge, and formulate improvements in location of sensors and recording features.

GPU/ Jersey Central, Oyster Creek Nuclear Plant - Review the design, application, calibration and maintenance of radiation monitors to determine performance.

Florida Power Corporation, Crystal River, Unit 3 - Prepare the specification and coordinate the calibration of the lugh range stack and steam line noble gases radiation monitors.

GPUN, Three Mile Island, Unit 1 - Design review of heat sink protection system for compliance with safety and reliability criteria.

Florida Power Corporation, Crystal River, Unit 3 - Provide an R.F.1/E.M.I. susceptibility study and in-plant testing for E.F.I.C.

control system.

Consumers Power Company - Expen witness in support of consumers' litigation with the radiation monitoring vendor for Midland.

Prepared a 40-hour training course on nuclear instrumentation, including written material, and presented the course to Chioda Chemical Engineering and Construction Co. Ltd in Tokyo, Japan, cs part of a aroject of transfer of technology.

Oak Ridge National Laboratory - Principal Investigator in the Design review of the radiation monitoring system in the Waste Management System.

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1982-84 Interim Control Systems Department Manager - Technical and administrative responsibilities for fossil and nuclear power plant control  ;

systems designs. Maintained technical expertise in specialty areas, l including equipment qualification, nuclear instrumentation and safety i j features actuation systems.

1980-82 Nuclear Control Systems Consultant - Responsibilities included technical supervision, consultations and design reviews of nuclear instrumentation and control designs for reactor trip systems, safety features actuation systems, equipment qualification, electrical separation, radiation monitoring I and solid state controls for all nuclear projects including:

South Carolina Electric & Gas Company, V.C. Summer, Unit 1 (900 MW PWR)

Cleveland Electric Illuminating Company, Perry, Units 1 & 2 (1200 MW BWR).

Provided technical supervision to address equipment qualification as per NUREG 0588 for Virginia Electric & Power Company, North Anna Station, Units 1 & 2 and South Carolina Electric and Gas Company, V.C. Summer Nuclear Station, Unit 1 l 1979-80 Project Instrumentation and Control Engineer - Metropolitan Edison pl Company, Three Mile Island Nuclear Station, Unit 1 (871 MW) -

(d Supervised the instrumentation and control design for required restart modifications.

Developed an IAEA eight hour training course on construction and operations of nuclear power plants, including written material, and presented the course in French at the Institute National des Sciences et Techniques Nucleaires - Paris, France.

1975-79 Project Instrumentation and Control Engineer - Supervised the development of the instrumentation and control design for Gilbert / Commonwealth's Reference Nuclear Plant, including part of the Standard Safety Analysis Report (GAISSAR). Task force leader for the preparation and submittal of the fire hazard analysis repon supporting GAISSAR docket.

Metropolitan Edison Company, Three Mile Island Nuclear Plant, Unit 1, 871 MW - Participated in the preparation of the fire analysis report required by the NRC.

South Carolina Electric & Gas Company, V.C. Summer Nuclear Station, Unit 1 (900 MW) - Designed the ESF loading sequencer and radiation monitoring system.

Cleveland Electric Illuminating Company, Perry Nuclear Power Plant, Units 1 & 2 (1200MW)- Verified safety-related designs.

x 1972-75 Project Instrumentation and Control Engineer - Metropolitan Edison d Company, Three Mile Island Nuclear Plant, Unit 1 - Supervised the design Pareans Power orme 824612-11004 Page 3

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ofinstrumentation and controls, including control room boards design, computer applications, safety feature actuation system, radiation monitoring system, secondary plant instrumentation control system, and licensing.

Developed the design criteria, logics diagrams, elementary wiring diagrams, specification and vendor interface for the reactor coolant pumps power momtors.

1967-72 Instrument and Control Engineer - Metropolitan Edison Company, Three Mile Island, Unit 1 (871 MW) - Developed most of the logie diagrams for the NSSS and balance of plant auxiliaries, and developed the plant safety criteria, e diagrams,quipment specification anddesign requirements, relay panels logic diagrams, and vendor interfaces for the elementary w i

ESAS. This design was also used for Florida Power Corporation, Crystal River, Unit 3. Also prepared the design criteria, specification and vendor interface for the radiation monitoring system for TMI-l and CR3 plants.

Involved in the preparation and review of PSAR FSAR, and participation in licensing for Three Mile Island.

Korea Electric Company, Ko-Ri, Unit 1 (600 MW) - Established design criteria for the radiation monitoring system.

Invented a detection principle for battery ground detectors and designed a solid state battery ground detector based on this principle.

O

si) r 1965-67 Research and Development Engineer -Involved in the development of in-line plutonium and uranium analyzers for PUREX fuel reprocessing arocesses. Researched and developed nuclear sensors compatible with the highly corrosive and radioactive process and High Level Waste fluids including alpha radiation measurement in acid solution, beta radiation measurement in liquid effluents and measurement of Plutonium in air.

Responsible for design and construction of a small process computer for the determining uranium nitrate concentration in industrial sized pulsating exchange column. Determined the capability and sensitivity of x-ray fluorescence techniques as applied to non-intrusive on-line measurement of low-level of uranium and plutonium in the bottom feed of a pulsating exchange column.

Invented a noiseless continuous air sampler for radiation monitoring application, and selected a manufacturer and coordinated the construction of 60 samplers.

1962-65 Eurochemic. Mol. Belcium Reprocessing plant for irradiated nuclear fuel.

1962-65 Nuclear Instrumentation Design Engineer - Responsible for the development of design criteria, equipment specifications, vendors interfaces technical acceptance tests and supervision ofin-plant installation of: area gamma monitoring system, airborne dust radioactivity monitoring systems, radioactive releases monitoring systems, and, nuclear criticality detection systems for process and personnel protection.

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These systems measured, recorded, and alarmed unsafe nuclear radiation j

conditions, provided pennissive or corrective interlocks, and initiated the  ;

alant personnel evacuation system. Also helpe,d prepare the Facility Safety l 3 valuation Report required to obtain an operatmg heense.

l 1961-62 Belclan Army. Koln. Germany 1960-61 Research Center for Natural Substance. Belcium Superior Technician - Responsible for development and maintenance of electronic instruments.

EDUCATION: A2 Electrical Engineer, Ecole Technique Saint George, Brussels, Belgium, 1957 A1 Electronic, InRaci, Bmssels, Belgium,1960 Additional Courses:

Management Discussion Skills, Gilbert / Commonwealth,1976 Managing for Motivation, Gilbert / Commonwealth,1976 Speakeasy, Gilbert / Commonwealth,1977 Time Management, Gilbert / Commonwealth,1977 Seismic Qualification Seminar and Demonstration, Wyle Laboratory, 1977 Microcomputers in Control Systems, The George Washington University,1979 O Human Factors Engineering in Power Plant Design, Operation and V Maintenance, EPRI Seminar,1980 Wordperfect /DrawPerfect, Gilbert / Commonwealth PC Overview, Gilbert / Commonwealth Microsoft Word, Gilbert / Commonwealth dBase III, Gilbert / Commonwealth Lotus 1-2-3, Gilbert / Commonwealth Mathcad, Gilbert / Commonwealth REGISTRATION: Professional Engineer - Pennsylvania (1974)

SOCIETIES: Member, Institute of Electrical and Electronic Engineers, Working Group, Standard 381 - Type Test of Modules and Nuclear Power Station Protection Systems Member, Institute of Electrical and Electronics Engineers, Working Group 2.12 Radiation Qualification of Class 1E Equipment Intemational Electrotechnical Commission, Technical Committee No. 45:

Nuclear Instrumentation - W.G. 4A Radiation Monitoring (Chairman)

U.S. Reviewer ofIAEA Standards in Category D.9 Radiation Protection Instrument Society of America, ISA-SP67 Methodologies for the Determination of Set Points for Nuclear Safety-Related Instrumentation Member of the American Nuclear Society and International Electrotechnical Commission (IEC) TC45 " Nuclear Instrumentation" Chairman of IEC SC45A WGA4 " Radiation Monitoring" Member of IEC SC45A WGA5 " Core Cooling Supervision and Containing Monitoring" Active member ofISA 67-04 r[O Persons Po.or one 824612 11004 Past 5

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PUBLICATIONS: " Design Features of a PWR Engineered Safeguards Actuation System,"

l Instrument Society of America,1970. 4

" Radiation Monitoring Requirements for 871 MW Nuclear Plants," Edison Electric Institute,1972.

l

" Radiation Monitoring ofEffluent Paths," American Nuclear Society Winter Symposium,1974.

" Nuclear Plant Protection Systems - Philosophy, Radiation Monitoring Systems," Onstructor), Instrument Society of America's Advanced Power

Instrumentation Course,1975.

" Electric Power Systems Instrumentation," (Instructor), Center for

, Professional Advancement Course,1976.

" Equipment Consideration," Onstructor), Instrument Society of America's Plant Protection Systems and Radiation Monitoring Systems Course, 1977.

" Operating Experience - The Designer Point of View" International Atomic Energy Agency - International Symposium on Nuclear Power Plant Control and Instrumentation, Cannes, France,1978. J

" Modern Nuclear Generating Plant Controls - An Integrated Ap proach," l Institute of Electrical and Electronics Engineer Symposium, New York, p 1980.

lV " Advanced Control Technologies in Operating Nuclear Power Plants," l American Power Conference, Chicago,1981.  !

"R.F.I. Considerations in Introducing New Control Technologies in Operating Plants," Wattec Conference, Knoxville, Tennessee,1986.

"RFI/EMI and Its Environment in Operating Plants and Its Impact on New Control Technology," IEEE Symposium on Nuclear Power Systems, San Francisco, California,1987. i "RMS Reliability Review," S. E. - Radiation Monitoring Owners Group, Charlotte, North Carolina,1991.

" Containment Radiation Monitor - Measurement Uncertainties," S.E. -

Radiation Monitoring Owners Group, San Diege, California,1992.

" Confirming EMC - A Program," EPRI Conference - EMI and RFI Control for Nuclear Power Plant, Baltimore,1992.  !

1

" Sampling Particles in Still Air" S. E. - Radiation Monitoring Owners Group, Pittsburgh,1993.

" Steam Generator Tube Leakage Detection - Assessing Monitoring Performance," S.E. - Radiation Monitoring Owners Group, Toronto, 1994 "Assessessing the Adequacy of Radiation Monitors in Steam Generators Tube leakage Detection Systems"-ISA San Diego,1995 Paraore Powse Cme 824612 11004 Page 6

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O REPORTS / Russian RDMK Reactors, Safety Parameters Display System, Design Basis l STUDIES: Document for KURSK Unit 2,1995 l Guideline Document, " Digital Upgrades Design," prepared for Florida Power Corporation CR3, Unit 3,1994

" Evaluation of Merlin Gerin In Duct Radiation Monitor," prepared for Florida Power Corporation CR3, Unit 3,1994.

" Design Basis Document - Oyster Creek - Radiation Monitoring System,"

performed for General Public Utility Nuclear, TMI-1,1993.

" Conceptual Design Report - Sampling Lines for Plant Vent Header Monitoring System and Secondary Side Condenser Air Ejector Monitoring System," performed for Nuklearna Elektrarna, Krsko Unit 1,1992.

" Review Report - Bellefonte Units 1 & 2 - Adequacy of the Solid State Control System to Applicable Safety Criteria," prepared for TVA, Bellefonte Unit 1 & 2,1991.

" Design Basis Document - TMI-l Radiation Monitoring System,"

performed for General Public Utility Nuclear, TMI-1,1991

" Design Basis Document - TMI-l Engineered Safeguards Actuation .

System," performed for General Public Utility Nuclear, TMI-1,1990. )

" Safety-Related Instrument Setpoints - Methodology," performed for l Florida Power Corporation CR3,1990.

" Oyster Creek Process Radiation Monitoring System Review," review performed for General Public Utility Nuclear (GPUN),1989.

" Radiation Monitoring System Improvement Study," study performed for  !

Florida Power Corporation CR3, Unit 3,1989.

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" Performance of Reactor Building Area Radiation Monitors to the Fuel Pool l Cooling Resin Discharge Event - Evaluation Report," evaluation

?erformed for Pennsylvania Power & Light Company, SSES,

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l Jnit 2,1989.

O Persons Power Gro@

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Senior Control Systems Engineer O)

Over twenty-six years of experience in the design, testing, and integration ofinstrumentation and ,

control systems for fossil / cogeneration plants, coal gasification processes, nuclear generating  !

stations, and aerospace power systems. Seventeen years of supervisory experience of up to

, 165 professional and technical personnel. l EXPERIENCE: PARSONS POWER (formerly Gilbert / Commonwealth) since 1974 1994 to Present Control Systems Project Engineer / Engineering Manager - Provide technical design, supervision, and administrative services for five professional personnel on the following projects:

Tambak Lorok Block II - Jakarta, Indonesia (505MW Stag 3 109E GE GT with 150 MW GE ST Combined Cycle) - General Electric Company -

Supported GE intemal I&C group in developing and preparing associated GE design documents required to suppon the project AE (Black & Veatch, Intemational) and customer with the configuration and  !

installation of a 5,300 point Bailey Infi-90 Distributed Control System (DCS). This effon included control room layout, development of MMI associated with graphics design, annunciation repons, and historical data, j (I/O) and datalink (GT and ST) preparation, developing required control macros / logics / loops and implementation of the GT/ST/HRSG auto-sequencing logic. The task included close coordination with Bailey and

/ BNI in developing an integrated approach to the DCS implementation as V} well as interface with the customer in the resolution of comments.

PANDA Kathleen L.P. - Lake *and, FL (105MW ABB GT/HRSG Combined Cycle) - Developed geographic DCS architecture, preliminary inpm/ output /, and functional requirements document to suppon early design activities.

Depanment Automation Workir.g Group Chairman - Chaired an in-house department group whose chaner was to streamline and automate appropriate i

processes. Developed overall department design process.

1991-94 Chief Engineer Electrical / Control System: (Nuclear) - Responsible for the technical quality leadership and direction of 165 professional and technical department personnel, improvement to the design process, emerging industry technologies, input and review of detailed project designs, and support of marketing and proposal development. Administrative functions include employee development, training, personnel performance, and salary action plans. Participated in the development of an in house technical training plan. Developed and presented a course on Process Control.

1988-91 Control Systems Project Engineer / Engineering Manager - Ohio Edison Company - Provide technical design, supervision, and administrative services for 10 professional and technical personnel on the following projects:

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p Burger Station, Units 1 Provided detailed engineering design for the installation of 3 new 1,300 points I/O Bailey Net 90 DCS distributed control systems including total CRT control of motors. Work included development of project criteria, detailed design, procurement of new field instrumentation, development of digital logic, database configuration, control graphics, and all associated interface between Ohio Edison and Bailey.

Burger Station, Units 1 Prepared detailed engineering study and cost estimates for the design of an integrated control room and control system replacement for boiler, turbine, and generator monitoring and controls.

The study included system sizing, conceptual engineering design and development ofI/O, instmment, and routing lists for options ranging from 550 to 1,200 I/O.

Sammis Station, Unit 7 - Provided detailed electrical and mechanical design packages, including maintenance loop diagrams for the installation of a Foxboro distributed control system. Detailed work included instrument and wiring installation design for approximately 300 I/O, and modification of the main control board, annunciator, and electronic room.

i Sammis Station, Unit 1 - Reviewed operational problems associated with O[ the air distribution and control system for redundant variable load control room chillers.

Control Systems Fossil and Industrial Section Manager - Sen'ed as liaison between the business unit directors, resource planning and staffing, marketing and proposal development; provided technical supervision of 45 professional and technical personnel; and developed improved methodologies and design deliverables. Administrative functions include personnel performance, salary actions, and general support of the department manager.

Control Systems Project Engineer - EPRI, Control and Safety System Development Project RP1403-26. - Prepared advanced control system functional requirements and report to optimize plant operation and response using variable rate control, and self tuning and automated plant auxiliary control. Co-authored and presented f.everal papers.

Control Systems Project Engineer - B! cunt Constructors, Sunnyside Cogeneration Project, Utah - Responsible for the preliminary control system design and configuration for a total soft start distributed data acquisition and control system for a fluidized bed boiler. The design incorporated remote I data communication links to allow the DCS to access remote located I programmable controllers. Other responsibilities included the development p of a project I/O database, P&ID's, logic and loop drawings, and the control system criteria. Project included the supervision of four professional and i technical personnel. '

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Control Systems Project Engineer - Blount Constructors, Scrubgrass l Cogeneration (BOMW) Project, Pennsylvania - Responsible for the i conceptual DCS system architectural design and for establishing project I/O.

Control System Project Engineer, Keystone Shipping, Cogeneration Project

- Responsibilities were similar to the Sunnyside project, except that preliminary design information was used to prepare inputs for final report, costing, and a total project bid specification.

Proposal Manager - Worked on numerous control system upgrada projects.

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1986-88 Control Systems Project Engineer - New York Power Authority, 1 J.A. FitzPatrick Nuclear Power Plant (BWR) - Responsible for control system design and modifications to add an altemate rod insertion system (ARI) and upgrade the standby liquid control system (SLCS). Also designed control panels, logic, wiring, installation procedures, and 10 CFR 50.59 safety evaluations. Supervised five professional and technical personnel. ,

Control Systems Engineer - Florida Power Corporation, Crystal River Nuclear Power Plant, Unit 3 (PWR)- Developed Regulatory Guide 1.97

'm) Instrument and String Loop Drawings, including review of as-built and modification packages to develop the R.G.1.97 Instrument and String Loop Drawings.

Task Engineer - Intergraph Corporation, Plant Design Software (PDS) -

Responsible for the in-house evaluation for both schematic / data base applications and 3-D modeling and piping, including product training, evaluation, and recommendation report. Also supervised seven professional and technical personnel.

1984-86 Consulting Engineer - Westinghouse (2LT) - Control systems consultant to develop architect engineering requirements and interfaces for advanced control systems for nuclear power plants, including field optimization of cabling and terminations, and integrated control room design.

Lead Engineer - South Carolina Electric & Gas Company, V.C. Summer Nuclear Power Plant (Westinghouse PWR) - Performed extensive chiller control evaluation studies on the HVAC control room chillers, including detailed time line studies of all chiller package timers and extemal interfaces.

Control Systems Project Engineer - Westinghouse Reference 1,000 MW Nuclear Power Plant - Responsible for the preliminary control systems design which was proposed to the People's Republic of China. Developed a lp V

loop / logic diagram format applicable for digital systems; developed a control systems / electrical engineering design data base; determined the quantity of remote input / output logic cabinets for the advance control i

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t) system; and directed control complex layout design to satisfy Regulatory ,

Guide 1.75/1.120 and IEEE 384. Developed project schedule, maintained I

. records, and supervised four professional and technical personnel.

Lead Engineer - South Carolina Electric & Gas Company, V.C. Summer Nuclear Power Plant (Westinghouse PWR) - Developed an overall control scheme to interface with shutdown motor central centers and switchgear, providing shutdown capability that satisfied Appendix "R" requirements.

Control Systems Project Engineer - Chiyoda - Responsible for control systems input in the preparation and development of a Nuclear HVAC Criteria document for Chiyoda. All associated nuclear control and ventilating systems were included.

1983-84 Control Systems Project Engineer - New York Power Authority, J.A. FitzPatrick Nuclear Power Plant - Responsible for control system design of a boiling water reactor (BWR) analog transmitter trip system.

Modification included replacement of digital reactor protection instruments and instmment racks, and integration of the design. Also developed schedules to support the installation outage and provided information for licensing documentation. Prepared safety evaluation and installation instructions.

Control Systems Project Engineer - Electrical Utilities of Croatia and Slovenia, KRSKO Nuclear Power Plant (600 MW Westinghouse PWR) and Korea Electric Company, Ko-Ri Nuclear Power Plant, Unit 2 (600 MW Westinghouse PWR) - Department technical consultant during start-up and operational phases. Reviewed operational problems, and recommended corrective actions.

Department technical committee member - Cleveland Electric Illuminating Company, Perry Nuclear Power Plant, Units 1 & 2 - Reviewed system operation / interaction for safety-related BWR nuclear and the balance of plant systems, including mechanical, control, and electrical functions.

Proposal Manager - Involved in the marketing efforts related to BWR applications of Regulatory Guide 1.97, remote shutdown facilities, and analog transmitter trip system.

Energoinvest (design engineering company), Yugoslavia - Participated in the development and presentation of" Instrumentation and Control Integration" course for engineers.

1981-83 Project Engineer - Allis-Chalmers Coal Gasification Demonstrator Project -

Responsible for all related instrumentation and control supervisory design and administrative functions, including design and procurement of the plant computer, distributed process control, and programmable controller p) g p

systems. Also responsible for instrument installation, specification and procurement ofinstmments and control valves, and design of support

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systems. Developed and supported project schedules maintained project records, and supervised six professional and technical personr,el.

1977-81 Project Engineer - Ko-Ri Nuclear Station, Unit 2 (600 MW Westinghouse PWR) and KRSKO Nuclear Station, Unit 1 (600 MW Westinghouse PWR) - Responsible for related instrumentation and control supervisory design and administrative functions; and coordinated and designed the balance of plant and nuclear steam supply systems, control boards and panels, instruments, control valves, instrument installations, specifications, i and all associated drawings. Developed and supported schedules to integrate instrumentation and control activities, maintained records, coordinated with the site, client, and vendors, and supervised twelve professional technical personnel.

1974-77 Instrument Engineer - KRSKO Nuclear Station, Unit 1 (Westinghouse PWR) - Prepared functional and loop diagrams, specifications, valve sizing, and system integration, including the nuclear balance ofplant systems, integration of nuclear steam supply system, applied systems and equipment, and installation, specification, and classification ofinstrumentation.

1970-74 Pratt and Whitney Aircraft - Florida Research and Develonment Center.

West Palm Beach. Florida

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s Senior Test Engineer - Responsible for research, development, and testing of hydromechanical control systems for militaryjet engines, including field trouble-shooting and system integration.

1969-70 Pratt and Whitnev Aircraft - East Hartford. Connecticut Test Engineer - Testing and evaluated hydraulic hardware forjet engines.

EDUCATION: B.S., Aerospace Engineering, The Penrcylvania State University,1969 Postgraduate study in Mechanical Engineering, University of Florida (West Palm Beach Campus),1970-71 Additional Courses:

Introduction to Emironmental Protection, Gilbert / Commonwealth,1974 Nuclear Power Plant Design, Gilbert / Commonwealth,1975 Foundations of Management, Gilbert / Commonwealth,1978 Project Management and Supervisory Training, Gilbert / Commonwealth, 1984 Lotus 1-2-3, Gilbert / Commonwealth,1985 Plant Design Software (PDS), Intergraph, Huntsville, Alabama (1987)

Instrument / Instrument Loop Drawing, Schematic Reference Data Base, Piping Reference Data Base, Intergraph, Huntsville, Alabama (1987)

The Wining Proposal Seminar, Gilben/ Commonwealth,1987 Project Engineers Workshop, Gilbert / Commonwealth,1988 dBASE III, Gilben/ Commonwealth,1988 DOS and Networking Fundamentals, Gilbert / Commonwealth,1989 R&R Repon Writer, Gilbert / Commonwealth,1989 Parsons Power Groe s24612 11004 Page5

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Special Network 90 Management Command System Engineer Course, Bailey Controls,1990 The Strategy for Winning, Gilbert / Commonwealth,1990 Topside, Gilbert / Commonwealth,1991 The Quality Advantage, Gilbert / Commonwealth,1991 Seven Habits of Highly Effective People Workshop, Covey Leadership Center,1994 Programmable Logic Controllers, Gilbert / Commonwealth,1994 REGISTRATION: Professional Engineer - Pennsylvania (1976)

PUBLICATIONS: " Control for the Future - A Development Program," co-author, EPRI Second International Conference on Improved Coal-Fired Plants,1988 i

" Functional Requirements and Design Specifications for the Improved

' Coal-Fired Power Plant (ICPP) Control System," Co-author, EPRI Conference on Power Plant Control and Automation,1989

)

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Permans Po w Game 824612-11 W Pige 6

1

( Control Systems Engineer i

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Experience includes lead systems engineer for nuclear plant design, instrumentation and control engineering, nuclear plant fire protection evaluation, field systems and piping engineering, and 4 project engineering for nuclear plant backfit services. Extensive systems design experience with nuclear steam supply system vendor, i

EXPERIENCE: PARSONS POWER (formerly Gilbert / Commonwealth) since 1972 <

1995 to Present Consultant - Pennsylvania Power & Light Company (PP&L), Susquehanna Station, Units 1 & 2 (1150 MW each - uprated) - Work directly with PP&L personnel to provide justification to extend instrument calibration intervals to 24 months to support 24-month fuel cycle and on plant modifications to add hydrogen injection system to improve rector water chemistry control.

1995 Control Systems Project Engineer- Westinghouse Barge Mounted Gas Turbine Plants - Provided technical engineering and direction to suppon barge mounted gas turbine balance of plant design. Responsibilities included instrument selection, installation and interfacing with Westinghouse digital control system.

1993-95 Project Engineer - Pennsylvania Power & Light Company, Susquehanna Station, Units 1 & 2 (1150 MW each uprated)- Provide technical and procedural direction to engineers and designers performing plant modification tasks. Assured adherence to Susquehanna Station design basis and compliance with regulatory commitments. Prepared task cost estimates (3

y.) and schedule, monitor / control performance to same. Tasks performed 3 include Station Power Uprate modifications, Setpoint Change Packages including calculations, Instrument Loop IR studies, Residual Heat Removal  ;

and HPCI control system modifications.

i 1990-93 I Task Supervisor - Pennsylvania Power & Light Company, Susquehanna l Station, Units 1 & 2 (1050 MW each) - Provided overall technical direction  :

for a schedule intensive project that replaces all reactor and secondary l system process sampling equipment; starting with new tubing through new state-of-the art on-lme monitoring equipment, and out to a new digital data acquisition system. Determined staffing requirements and organization, assured preparation of and adherence to schedules to meet client needs, .

assured cross discipline technical continuity and problem resolution, i responsible for adherence to client procedures and practice,s and for overall technical quality of work packages.

1989-90 Control Systems Project Engineer - General Public Utilities Nuclear Corporation, Three Mile Island Nuclear Station, Unit 1 (870 MW)-

Estimated and scheduled required efforts; coordinated, assisted, and directed task engineers and technicians to assure satisfactory completion of des procurement, and documentation for assigned modifications, ng engmeen studies, or other requested client support on continuing services project. In addition, provided direct onsite engmeering support during 1990 refueling outage for construction problem resolution.

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1988 Restart Suppon Project Engineer (onsite) - Philadelphia Electric Company, Peach Bottom Atomic Power Station, Units 2 & 3 (1050 MW each)- Member of onsite task force assembled to address material quality concems and provide restan assistance. Determined staffing requirements and scheduled effons.

Tracked and reponed progress via formal scheduling system. Provided technical direction and assistance to assigned engineers and technicians (both onsite and in home office) to assure consistent complete evaluation of spare pan quality concems, technical and administrative adequacy of commercial grade dedication documentation and restart modification packages.

1986-87 Control Systems Department Consultant - Performed a variety ofindependent tasks to support ongoing projects including:

Technical Auditor for seismic qualification audit of NSSS vendor.

, Pennsylvania Power & Light Company, Susquehanna Steam Electric Station - Pressure Switch Environmental Qualification package.

GPU, Three Mile Island, Unit 1 - Appendix "R" study of automatic emergency feedwater control system.

GPU, Three Mile Island, Unit I and Oyster Creek - Instrument loop accuracy calculations.

Cleveland Electric Illuminating Company's (CEI) Perry Nuclear Power Plant, Unit 1 (1265 MW)- Study and recommend solutions to recirculation valve problems.

1986 Design Adequacy Program, Third Pany Independent Reviewer - Texas t

Utilities, Comanche Peak Steam Electric Station Design Adequacy Program -

Reviewed licensing commitments to determine impact on system design requirements. Reviewed system documentation to determine status of compliance with commitments. Documented work via criteria lists and review checklists in accordance with project procedures.

1984-85 Control Systems Project Engineer - GPU, Three Mile Island, Unit 1 -

Estimated and scheduled required efforts; coordinated, assisted, and directed task engineers and technicians to assure satisfactory completion of design, procurement, and documentation for assigned modifications, engineering studies, or other requested client support on continuing services project.

1979-84 Lead Control Systems Engineer - CEI, Perry Nuclear Power Plant, Units 1 &

2 - Coordinated and assisted in the specification and evaluation of equipment.

Also involved in the resolution of vendor problems to ensure adherence to project policies and consistency of approach, with special emphasis on evaluating class IE equipment qualification programs 1977-79 Lead Nuclear Systems Design Engineer - Electric Utilities of Croatia and Slovenia, KRSKO Nuclear Power Plant, Unit 1 (600 MW) - Scheduled, coordinated, directed, and assisted nuclear island system design engineers and 4

technicians to ensure completion of design effort consistent with quality and schedule requirements, plus individual system design work. . Design work included conceptual and detailed design implemental of altemate rod insertion system added late in the derign cycle.

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1976-77 Mechanical Representative, Fire Protection Evaluation Team - Established l

general approach and detailed plan for systematic evaluation ofnuclear plant l exposure to fire hazards in accordance with U.S. Nuclear Regulatory

. i Commission requirements. Participated as equipment and general operations representative on a multiple discipline team, performing fire protection

evaluation and report preparation for

j Rochester Gas & Electric Corporation, R.E. Ginna Nuclear Station, Unit 1 l

(490 MW).  !

South Carolina Electric & Gas Company, V.C. Summer Nuclear. Station, l Unit 1 (900 MW).

Detroit Edison Company, Enrico Fermi Nuclear Power Plant, Unit 2 (1200 MW).

l 1976 Field Mechanical Engineer - Korea Electric Company, Ko-Ri Nuclear Power l Plant, Unit 1 (600 MW)- Performed onsite engineering for resolution ofpiping and support interference, reduction of piping vibration, and system-related problems.

1973-76 Project Engineer - R.E. Ginna Nuclear Station, Unit 1, Continuing Services -

Involved in the system engineering, scheduling. Also coordinated work with other engineering disciplines, prepared procurement and technical documents, and directed participation in construction problem resolution.

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1972-73 Nuclear Engineer - General Public Utilities Corporation - Responsible for evaluation ofproposed nuclear station (1100 MW). Also responsible for general assignments for various other nuclear power plants including '

' preparation of standard nuclear systems design guides for nuclear closed cooling water and nuclear sampling systems, assistance on nuclear steam supply system evaluation, and reactor containment and nuclear fuel handling study.

1967-72 Combustien Encineerine Inc.. Windsor. Connecticut 1971-72 Lead Engineer - Assigned, reviewed, and approved work of four system design engineers working on nuclear steam supply systems for nuclear power plants to insure that work met technical and licensing requirements. Conducted 4

independent investigations into general system problem areas and recommended and implemented solutions.

1967-71 System Design Engineer - Performed design engineering of reactor coolant, engineered safeguards, and auxiliary cooling systems for nuclear power plants.

Also performed engineering calculations; prepared system diagrams; insured that licensing requirements were achieved; identified and resolved interface i

incompatibilities; wrote system descriptions, test procedures, and operating

! procedures; and approved final system performance parameters.

2 EDUCATION. B.S., Mechanical Engineering, University of Vermont,1965 M.B.A., University of Connecticut,1974 h

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REGISTRATION: Professional Engineer - Pennsylvania (1975)

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Equipment Qualification Sixteen years of experience in Equipment Qualification work and task management in the U.S.

nuclear mdustry.

EXPERIENCE: PARSONS POWER (formerly Gilbert / Commonwealth) since 1985 1990 to Present EQ Program Coordinator - Pennsylvania Power & Light, Susquehanna Steam Electric Station - Task Manager for the followmg projects:

EQ Program Upgrade Project - Responsible for modification and upgrading of EQ documentation (EQARS). Management of the project included estimating, scoping and successful procurement of the work. Responsible for management of cost, schedule and quality of work. Task was completed under budget and on schedule ($1.5 million).

Equipment Requalification Task - Analysis and Requalification of equipment affected by Power Uprate accident environment ($0.5 million).

EQ Binder Assessment Task - Reviewed the EQ binders to determine technical adequacy and regulatory compliance. Responsible for estimating, bidding and successful procurement of the work. Task was successfully completed under budget and to the satisfaction of the client.

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1988-89 EQ Program Coordinator - Philadelphia Electric Company (PECo), Peach 4

Bottom Atomic Power Station - Provided complete EQ consultation for

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V NRC licensing of the plant restart which included implementation of

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Regulatory Guide 1.97 commitments. Provided technical and regulatory guidance for requalification of commercial grade equipment ($1.2 million).

1985-87 EQ Task Manager - South Carolina Electric & Gas, V.C. Summer Nuclear Station - Developed EQ packages for 1E equipment and completed EQ

central file for harsh environment. Used location specific environment and aging data to extend qualified life of 30 equipment groups including NSSS 1

' equipment supplied by Westinghouse. Analyzed and modified vendor

1. replacement and maintenance recommendations to suit plant application.

Established necessary EQ maintenance and surveillance requirements for continued qualification.

1978-85 Bechtel Power Corocration. Ann Arbor. Michigan Senior EQ Engineer - Detroit Edison Company - Developed NRC submittal for environmental qualification ofIE ec uipment in harsh em ironment.

Prepared test / analysis evaluation check'ist for EQ review consistent with NUREG 0588 and DOR guidelines requirements. Used test data, supplementar qualification.y analysis Worked andspare as the lead material search toengineer parts qualification establish to component resolve NRC concerns about commercial grade items used in Fenni II.

Contract Engineer - Consumers Power Company, Palisades and Midland Plants - Managed and administered subcontracts for Nuclear Steam Supply and Balance of Plant equipment. Developed subcontract packages and prepared amendments. Closed out contracts subsequent to satisfactory completion of work ($18 million).

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O 1976-78 County of Henrico. Richmond. Virginia Pro ect Engineer - Design, planning, and project management of public bui dings and hospitals. j 1970-75 Swadeshi Polytex Ltd.. Delhi. India Zimmer A.G., Frankfurt, West Gennany - Project design and construction ,

coordination of continuous process polyester fiber plant. I EDUCATION: B.S., Civil Engineering, Birla Institute of Technology, Ranchi, India,1969 O

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( Walkdown Lead, Electrical-I&C l i Twenty-three years of experience in electrical, control systems physical and wiring design for nuclear and fossil fueled power generating stations. Physical design background includes cable ,

tray, conduit, bus duct, cable duct, underground duct bank, cable tray and conduit supports,  !

control boards, relay racks, MCC, switchgear and load center layout, equipment mounting, fire barriers, lighting and grounding. Wiring design background includes one line, three line, elementary, instrument loop and maintenance diagrams, wiring diagrams for control boards, relay racks, MCC, switchgear, transformers and load centers, control stations, electrical grounding, computer equipment and instrumentation.

EXPERIENCE: PARSONS POWER (former1v Gilbert / Commonwealth) since 1973 1995 to Present Lead Designer (Design Technician II) - Florida Power Corporation - Crystal River Unit 3 - Responsible for design review for Appendix R revalidation and any modifications resulting from those findings. Responsible for l supervising all design tasks, developing manhour and cost estimates, scheduling of manpower, and assignment of tasks. Also, functioned as work authorization manager for select tasks. Responsible for all disciplines schedules and budgets. Frequent communication with clients and construction personnel. Maintain FPCs CKS Cable Routing Files, FPCs Controlled Library and Aperture Card System. Evaluate remote shutdown panels and emergency feedwater initiation and control system for separation

f. compliance. Provide input to calculations for separation exceptions for the remote shutdown panelt, the emergency feedwater initiation and control

. system and the safety related relay racks.

t Designer - Westinghouse Electric Corporation, Greys Ferry Cogeneration Project - Responsible for design of underground duct banks, embedded conduits, equipment grounding, lighting, and PC-CKS cable routing.

1994 to Present Nuclear Production Unit Security Monitor - Responsible for ensuring Safeguards Information is handled, documented, stored and transmitted per Gilbert / Commonwealth PPM Procedure 8N.

1990 to Present Project CAD Coordinator - Florida Power Corporation - Crystal River Unit 3 - Responsible for scheduling CAD work on the project, ensuring Quality and that the CA9 deliverables met the clients and Gilbert / Commonwealth's CAD specifications.

1993-95 Project Design Supervisor (Design Technician III) - Florida Power Corporation - Crystal River Unit 3, New York Power Authority - James FitzPatrick Station, General Public Utilities - Three Mile Island Unit 1, Baltimore Gas and Dectric - Calvert Cliffs Station, Rochester Gas and Electric - Ginna Station Responsible for supervising all design tasks, developing manhour and cost estimates, scheduling manpower, and assigning tasks to design personnel. Normally served as the primary checker / verifier for all power, control and instrumentation construction

[ work packages. Significant tasks include radiation monitors upgrade and replacement, HPI flow indication upgrade, added new source of off-site

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Persers Power Crme 824612-llW P.ge I

Cr l power, deluge system for off-site power transformer, condenser retubing, SW isolation to RC pumps, addition of a backt.p engineered safeguard I transformer, additional emergency feedwater pump, input to a revised Separation Criteria Document, evaluation of control boards and relay cabinets layout and wiring to assure compliance with the revised criteria,

' modifications to cabinets to meet the revised criteria. Added a 200 ton chiller to the RB HVAC system, installed a new plant integrated computer system, and added a new Inverter. Developed module for separation barrier testing, leak rate test instrumentation upgrade, L&N Transmitter Replacement. Also, added a 4KV Switchgear, bus duct and cable tray 4 additions. Replaced an electrical equipment due to degraded voltage.

Inputted Electrical Separation Exceptions. Supported FPC's EDSFI Evaluation and inputted the development and debugging of Gilbert / Commonwealth's CKS Cable Routing Program, and maintained FPC's Cable Routing Program files.

1994 Nuclear Production Unit Move Coordinator - Responsible to coordinate the move of the Nuclear Production Unit.

1990-93 Project Electrical Design Supervisor - Florida Power Corporation, Crystal River, Unit 3, Continuing Services Program - Responsible for supervision c of Electrical & Control Systems design tasks, scheduling of manpower and i assignment of tasks. Responsible for developing manhour and cost estimates. Also, functioned as task lead engineer for selected tasks.

Reported to project manager and Project Electrical Engineer.

Lead designer or checker / verifier on electrical, controls and instrumentation construction work packages. Significant tasks: human engineering factors (major modifications to the main control board), emironmental qualification (instrument, limit switch, wiring and terminal block replacement), control room habitability modifications, addition of a third letdown cooler (motor operated valve and instmment additions), installation of new security computer system, access control system, and perimeter intrusion detection system, diesel load shed modification (design a relay system to automatically shed non-priority loads until the diesels are up to speed and voltage), design new kitchen in the control room, pressurizer heater status indication, modifications for high energy line break protection, and also maintained FPC's cable routing program files.

1990 Developed and instructed an electrical design course for security, communications, and fire protection systems. Also developed and instructed an electrical design course for Remote Shutdown, Appendix "R" and field walkdowns.

1983-90 Lead Designer - Florida Power Corporation, Crystal River, Unit 3, p Continuing Services Program - Responsible for design and supervision.

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V grounding, block diagrams, circuit schedules, pull slips and interconnection diagrams for power control and instrumentation. Responsible for field design of new cable tray system for remote shutdown system and Appendix "R" cables, numerous field walkdowns for various tasks, design of the dedicated emergency feedwater facility, checking of perimeter security system upgrade, plant access control system upgrades, R.G.1.97 upgrades, off-site power supply and engineering instructions for the installation and purchase ofmaterials.

1983 Lead Designer / Drafter - GPU Nuclear, Three Mile Island and Oyster Creek Nuclear Stations and Gilbert / Commonwealth Generic Low-Level Radwaste Storage Facility - Responsible for design and supervision. Designed construction ' drawings for installation of cable tray, conduit, conduit supports, cable tray supports, grounding and control wiring diagrams for low-level radwaste storage facilities.

1980-83 Lead Designer / Drafter - Responsible for design and supervision. Designed construction drawings for cable tray, conduit and tray supports, underground duct banks, circuit writing (block diagrams), interconnection '

wiring diagrams, panel design and wiring, termination work sheets and bill of material for purchase of equipment.

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Virginia Electric & Power Company, Chesterfield, Units 5 & 6 Balanced

( Draft Conversions and Chesterfield, Unit 6 Precipitator Upgrade - Assisted project supervisor in scheduling and supervision. Also mentored less experienced drafters.

1978-80 Drafter - Cleveland Electric Illuminating Company, Perry Nuclear Station, Unit 1 - Responsible for conduit, tray and seismic support design of:

Intermediate Building, Penetration Access Area and Reactor Under Vessel Conduit.

1975-78 Drafter - South Carolina Electric and Gas Company, V.C. Summer Nuclear Station - Responsible for the design of conduit, cable tray, seismic supports, and grounding, and computer inputs for a computer cable routing program.

1973-75 Drafter - Kansai Electric Company, Ohi Nuclear Power Station, Osaka City, Japan - Responsible for the design of conduit in the control building.

EDUCATION: Reading Muhlenberg Vocational Technician School, Architectural Drafting, 1970-1973 Reading High School,1973 Additional Courses:

Fundamentals of Wiring and Block Diagram Preparation, Gilbert / Commonwealth,1980 Basic Fossil Power Plant Training Program, Gilbert / Commonwealth, 1982 a

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CADD Awareness Training, Gilbert / Commonwealth,1984 3 CADD Training, Gilbert / Commonwealth,1988 l

Auto CADD Training, East Vocational Technical School,1988  !

Human Factors Design Conventions Document Seminar,  !

1 Gilbert / Commonwealth & Essey Cogoration,1988 Continued Observation Seminar, Gilbert / Commonwealth,1991 The Quality Advantage, Gilbert / Commonwealth,1991 Design of Generating Station Electrical Power Service Systems, Gilbert / Commonwealth,1993

Engineering Work Control Process, Gilbert / Commonwealth,1994 Fundamentals of Management and Supervision, Manufactures '

Association of Berks County and Gilbert / Commonwealth,1993 Wordperfect, Access, Excel, M.S. Word, Auto Cad, P.C. CKS, Micrographics Designer ,

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( Operations Experienced general manager and corporate officer. Led the cultural change and performance improvement at Diablo Canyon Power Plant from 1988 to 1995. During this period, cycle capacity factors increased from 65% to more than 85% on both units. Diablo Canyon was rated as an INPO Number One performer and was placed on the NRC Best Plants list three years in a row. Created the Plant Information Management System (PIMS) concept, a computerized database and work control program that has been credited as one of the major factors in the success of Diablo Canyon. Improved self-assessment programs, developed meaningful performance indicators, and initiated programs that resulted in increasing levels of safety.

Served on the INPO Board of Directors, resulting in contributions to the improvement of the entire Nuclear Industry while gaining valuable perspectives on a wide range of operating plant and industry issues.

EXPERIENCE: GPU Nuclear Corooration 1995 to Present Board of Directors 1990-95 Institute of Nuclear Power Ooerations (INPO)

Board of Directors - Gained valuable perspective on a wide range of operating plant and industry issues during a period of unparalleled improvement in the nuclear industry.

1968-95 Pacific Gas and Electric Comoanv. Avila Beach. California 1988-95 Vice President, Diablo Canyon Operations - Developed a leadership team that implemented a cultural change to a teamwork environment, which led to significant performance improvement. During this period, cycle capacity factors increased from 65% to more than 85% on both units.

Diablo Canyon was rated as an INPO Number One performer and was placed on the NRC Best Plants list three years running. Initiated programs resulting in increasing levels of safety. Improved self-assessment programs, including development of meaningful performance indicators.

Developed effective work control and outage management programs.

Achieved O&M cost reductions of 10% in a single year, while improving performance in every area for safety and production.

1984 88 Assistant Plant Superintendent, Diablo Canyon.

1980-84 Supervising Nuclear Generation Engineer (San Francisco office).

1978-80 Resident Engineer, Diablo Canyon.

1975-78 Lead Startup Engineer, Diablo Canyon.

1968-75 Engineer / Senior Engineer (San Francisco office).

EDUCATION: B.S., Electronics Engineering, California State Polytechnic University, 1968 3 Executive Program, Stanford University, Summer f994

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.' N REGISTRATION: Professional Engineer, Nuclear Senior Reactor Operator, Diablo Canyon Units 1 and 2 l SOCIETIES: American Nuclear Society Professional Reactor Operators Society l Institute of Electrical and Electronics Engineers i

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Operations Thirty years of experience in the mana professional personnel and programs. gement and administration of technical, engineering Experienced in management and operational assessments, l

" project startup, project management, utility management and nuclear support services and consulting. l l

WORK HISTORY: Deist Associates. Inc.

1988 to Present General and project management, management and organizational l assessment, busmess development, regulatory support services 1982-88 NUS Coroonlign General and project management, management and organizational assessment, busmess development 1976-82 New York State Power Authority Manager, Nuclear Operations 1970-76 general Electric Comoany Nuclear plant startup and test; Manager, BWR Training Center 1968-70 Pennsylvania Electric Comeany Plant operations and training 1957-68 U.S. Navv q(/ Plant operations and training '

i EXPERIENCE: Organizational and Management Consulting Currently managing an executive consulting group providing operational support to the GPU Nuclear Board of Directors Nuclear Safety and ,

Compliance Committee. Under this contract, Deist Associates provides on- '

site representation at the Three Mile Island and Oyster Creek nuclear stations for the Board of Directors Committee charges with monitoring nuclear safety and regulatory compliance.

As team leader, developed and managed a special study, "The Conduct of an Analysis and Evaluation of the Management of Nuclear Related Activities of the Public Service Company of Colorado," conducted for the utility at the request of the NRC.

As team leader, managed (under contract to the Taiwan Atomic Energy Commission) a nuclear operations on-site audit of the first on-line BWR-6, Kuosheng Unit 1 (Taipower Company). Also developed and managed an intemational study of reactor operator training for Shikoku Electric Company ofJapan.

Provided management and operations consulting services to the NRC for a special management diagnostic inspection of the Calvert Cliffs Nuclear O Station. In addition, supported the NRC as a management and operations p

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_ specialist for an operational readiness inspection of the Comanche Peak Nuclear Station.

Provided management and operations, training, and management consulting services to the Niagara Mohawk Power Corporation in support of prudency i

hearing preparation; and to the Detroit Edison Company (Fermi 2) for an audit of outage preparations for the station's first reactor refueling.

Served as nuclear operations consultant to the New York Power Pool Independent Review Panel on Nuclear Plant Safety that was formed after 4

the Three Mile Island accident and as nuclear operations and training l

consultant to the NRC Peer Panel on Reactor Qualifications.

General Management As Assistant Manager, and later as Manager, Nuclear Operations, had corporate management responsibility for the operational supprt for two nuclear power generating plants. Areas of responsibility ine'.uded operations, maintenance, health physics, radiological controls, inservice inspection, traming, emergency preparedness, and on-site operational review.

, ,) While Senior Executive Consultant working under long-term contract with W AECL Technologies, Inc. (AECLT), the U.S. subsidiary of Atomic Energy of Canada, Limited (AECL), provided day-to-day management as Manager / Director, Operations. Had responsibility for all business aspects of a technical services company, includmg business development, marketing, sales, project management, and contract administration for all products and services.

i As Manager, Consulting Services, established regional business center on Long Island, New York for a major engineering consulting firm. Office was established as profitable from imtiation. As General Manager, Operations Management Services Division, expanded regional office to international business operation. Had management and profit and loss responsibility for all consultmg and training services in management support, utility operations, maintenance, radiation, protection, chemistry, health physics, emergency planning and organizational assessments.

Project Management Proposal Manager and Project Manager for the NRC Design Engineering Inspection Services project. Under this three year contract, provided engmeering and inspection personnel support to the NRC for utility inspections.

Project Director for the U.S. Department of Energy's Advanced Neutron Source Conceptual Design project. Subcontractor to Gilbert / Commonwealth, providing reactor design and reactor auxiliary system design services.

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pd As Director, Above Ground Spent Fuel Storagc Services and as Director, Decontamination and Decommissioning Semees, acted as primary management interface between AECL, AECLT, DOE, and the DOE Contractors at Hanford, Savannah River, and Oak Ridge Negotiated the teaming arrangements for multi-company teams to bid and compete on DOE proposals for Above Ground Spent Nuclear Fuel Storage and Decontamination and Decommissioning semees.

i Managed AECLT DOE proposal efforts for the storage ofN-Reactor Fuel the storage of HFIR (Hanford),

fuel (Oak Ridge),the and storage of 232-F TMI-2 fuel debris (Idaho)ty at the S

, 1 the D&D of the Facih Site.

EDUCATION: Pennsylvania State University New York Institute of Technology General Electric Company Boiling Water Reactor Technology Westinghouse Pressurized Water Reactor Technology Nuclear Reactor Operations, Saxton Nuclear Experimental Corp.

U.S. Naval Nuclear Power Training REGISTRATION: Senior Nuclear Reactor Operator, Dresden Nuclear Station Nuclear Reactor Operator, Saxton Nuclear Experimental Corp.

pJ SOCIETTES: Member, American Nuclear Society l

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E Configuration Management Consu tant More than 23 years of nuclear industry and government experience in the areas of startup, operation, technical support, design engineering, configuration management, special assessments, training, and project management. Fourteen years with a utility, equally divided  ;

between corporate and plant assignments that included Senior Reactor Operator (SRO) training I and the management of various multi-functional technical groups. More than six years with the  !

Institute of Nuclear Power Operations (INPO) as a lead design engineering and technical support i evaluator. Also responsible for initially developing INPO's position on configuration

, j management and authored INPO 87-006, a special report on the subject. Coordinated several workshop topics and presented numerous papers on configuration management.

1 i Led or participated in over 50 management and technical assessments. Assisted numerous  !

i commercial nuclear utilities and DOE facilities in the upgrade of their configuration management, design engineering, modification control, and design basis document programs.

Member of the DOE Washington team that developed the draft Nuclear Energy Order 5480.CM and associated guidance; the scope of this order includes configuration management, design basis reconstitution, and material condition and aging. Primary author for the section on configuration management.

Has guest lectured and taught courses for various colleges, universities, and other educational 4

institutions such as the American Management Association; currently a Full (adjunct) Professor 1 in Management. Active Department of Energy "Q" clearance.

EXPERIENCE: United Enercy Services Corooration since 1988 1988 to Present Section Manager - Configuration Management i Senior Consultant - Design and Configuration Management l Extensive experience in the supervision of multi-disciplined technical staffs supporting plant efforts to develop, implement, assess, or upgrade programs related to configuration management and design engineering. Included in these configuration management efforts are programmatic assessments and enhancement of areas such as program management, design control, change control, design requirement and bases recovery / reconstitution, document control, and information management.

Recent assignments include participation on the team that perfonned a reactor operation feasibility study at the Kozloduy Nuclear Power Plant in Bulgaria. Also, participated on the team that developed DOE Order 5480.CM as the primary author for the section on configuration management; developed a " Conduct of Configuration Management" guideline and action plan for the Oak Ridge National Laboratory in preparation for a DOE Tiger Team evaluation; performed independent technical reviews of the design basis documents developed to date for Southem California Edison; conducted technical reviews of the Engineering Specification, Design Change Process, Safety Evaluation, and Security programs for Wisconsin Public Service Corporation; was the Team Manager for two large team, INPO style assessments at Savannah River in the areas of operations and maintenance; participated as a full member in the Kewaunee Nuclear Plant Configuration Management Task Force; q provided consulting services to Virginia Power in the areas of configuration i j management and design engineering (which included a detailed review of Perses Power Gro@

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I 8 system and topical design basis documents as they were developed); 1 assisted in the imtial development of a system-wide configuration management program for Commonwealth Edison Company and developed configuration management criteria for assessing the development of the

, change control process and design basis documents; evaluated the areas of management, design, technical support, configuration management, operations, and mamtenance for pre-NRC and INPO assessments conducted at numerous nuclear power plants; conducted design process and design basis training for utihty and DOE personnel as part of the Safety System i Functional Inspection (SSFI) courses offered by UESC; and served as the configuration management Team Leader for the DOE (Washington, DP)

Standards Project in response to DNFSB Recommendation 90-2.

Spent eight months with another technical services organization establishing a southeast engineering office in Atlanta to support a major planned project.

1982-88 Institute of Nuclear Power Ooerations 1984-88 Section Head - Technical Support Department Program Manager and Lead Evaluator - Design Engineering Department Participated in 27 domestic and international evaluation and assistance visits as a qualified INPO plant and corporate Technical Support and Design Engineering lead evaluator.

O d As a Section Head in the Technical Support Department, responsible for reviewi:.g the technical support evaluation findmgs and upgrading the performance objectives and criteria, as required.

While in the Design Engineering Department, Program Manager responsible for developmg the INPO corporate design engineering performance objectives and criteria currently used during the corporate evaluations. In this capacity, interfaced with most of the design organizations in the nuclear industry.

Also responsible for developing INPO's position on configuration management and authored the INPO special report (INPO 87-006) on this subject. In this capacity, coordinated several workshop topics and presented numerous papers on the subject.

Interfaced with various domestic and international utilities, NSSS suppliers, and A/E's currently involved in configuration management and design basis reconstruction.

1982-84 Staff Assistant to the Vice President of the Analysis and Engineering Division - Provided internal support on matters pertaining to nuclear power plant design and operation, adnunistrative affairs, and management practices. Also responsible for developing and monitoring the division's goals, objectives, and annual budgets.

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O- i 1968-82 Florida Power & Licht Comoany l 1975-82 Group Supervisor, Supervising Engineer, and Senior Engineer in the Power i Plant Engmeering Division - Corporate Offices - Managed the Mechanical / Nuclear Specialist Group, which provided engineering support in the areas ofmetallurgy, pipe stress, heat transfer, fluid flow, seismic analyses, etc., for all fossil and nuclear plants within the Florida Power &

Light (FP&L) system. This group performed root-cause analyses and safety evaluations pr 10CFR50.59), developed and reviewed design change packages an(o plant modifications, and interfaced with Bechtel, Eb other A/Es on special technical issues related to the Turkey Point and Saint '

Lucie Nuclear Power Plants. Budgeted, scheduled, and controlled t

numerous special projects assigned to this group, e.g., development of an Engineering Management Information System (EPPMIS), response to NRC Bulletin 79-14 regarding pipe hangers and supports, et al.; EPPMIS ultimately received an INPO corporate evaluation good practice. This group also developed the specification for the steam generator replacements at Turkey Point and provided procurement, constniction, and startup support i for these replacements.

I EDUCATION: Ph.D., Business Administration, Nova University, Ft. Lauderdale, Florida (SACS Accredited),1981  :

M.B.A., University of Miami, Coral Gables, Florida (SACS Accredited),

4 1975 B.S., Depanment of Nuclear Engineering, Mississippi State University, I

) (V3 j

State College, Mississippi,1968

' Additional Courses:

' Turkey Point Nuclear Plant Operator Licensing Program,1971 Florida Power & Light Company Management Development Program (SAI, KT, Managerial Gnd, MBO, Time Management, etc.), 1972-82 Advanced Reactor Technology and Simulator Course,1987 CERTIFICATION:

Senior Reactor Operator (SRO) and Reactor Operator (RO)

Certified Level III (highest) in Nondestructive Leak-Rate Testing (per SNT-TC-1 A)

Certified Level II QC Mechanical Inspector in 1974 Certified Kepner Tregoe course leader in Analytical Trouble Shooting (ATS) and Weighted Decision Analysis (DA)

CLEARANCE: Active Depanment of Energy "Q" Clearance Per,ano Power Group 824612 11004 Page 3

-(~' M Procurement Nineteen years of experience in technical personnel management and supervision. Twelve years of experience in mechanical engineering and project management for power generating facilities, including extensive experience in recent years m developing programs for the procurement and qualification of replacement items for nuclear power plant operations.

EXPERIENCE: Seauoia Consultine Grouo. Inc. -

1996 to Present Senior Project Manager / Consultant - Provided various consulting sersices including project management, program / procedure development, technical training, process benchmarking /re-engmeering, and procurement engineering. Customers include South Carolina Electric & Gas, Tennessee Valley Authority, EPRI, Nukleama Electrama Krsko, and the JA Jones Company (operators of the EPRI Nondestructive Examination Center).

1981-96

, Parsons Power Groun Inc. (formerly Gilbert / Commonwealth) '

1991-96 Project Manager / Consultant - Responsible for the overall project management of numerous nuclear and U.S. Department of Energy (DOE) assignments.

Nuclear assignments included additional guideline development and industry-wide training for EPRI, for the following issues:

EPRI Report NP-7218, " Sampling Plans for Commercial Grade Item s Acceptance," 1991.

' . EPRI Report TR-102260," Supplemental Guidance for the Application

of EPRI Report NP-5652," 1994.

EPRI Report TR-106160, " Coatings Handbook for Nuclear Power Plants," 1996.

EPRI Report " Packaging, Shipping, Storage, and Handling Guidelines for Nuclear Power Plants,' m-progress.

Nuclear consulting assignment highlights included resolving material issues through extensive coordination with the USNRC at the TVA Watts Bar Unit 1, that ultimately led to plant licensure. A similar project was successfully implemented at TVA Browns Ferry, which enabled the restart of Unit 3.

DOE assignments included preparation of numerous project engineering documents for Martin Marietta Energy Systems, such as Functional Requirements Document (FRD), Preliminary Proposals, Risk Assessmmts, Project Waste Management Plans (PWMP), Design Criteria Documents, Safety Analyses, Quality Assurance Evaluation and Project Management Plans. Projects included environmental remediation of Oak Ridge National Laboratory's (ORNL) Waste Area Group (WAG) 6, design of a liquid low-level waste containment and transport systems, and the design of a low-level waste ion-exchange treatment facility.

1992-96 Manager of Engineering and Administration - Responsible for the technical adequacy of project deliverables and engineering functions at

/~N Gilbert / Commonwealth's (G/C) Southeast Regional Headquarters, with U

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more than 200 personnel. Directed human resource, information technology, traming, and administrative functions.

1989-91 Manager of Quality Management - Responsible for the activities of the Proposal Development, Design Control, Licensing and Technical Writing groups. Ensured that Design Control Procedures and Engineering l Operations Manuals (DCP/EOM) were properly maintained, controlled and revised to reflect the current engineering design process of work within the company.

1987-89 Project Manager - Managed and developed industry standard NP-5652 l

" Guideline for the Utilization of Commercial Grade Items in Nuclear Safety i 4

Related Applications." Coordinated input from the utility members of the l Nuclear Construction Issues Group, and provided direction for the EPRI l

task group members. Activities included conducting program assessments, '

the development of generic process and standard and the coordination ofits l approval with the Nuclear Regulatory Commission and the Nuclear Utility i Management Resource Council (NUMARC).

Developed and managed replacement item qualification and procurement programs at over 15 U.S. and international nuclear utilities. Managed the development ofinspection and survey criteria to determine the programmatic utility controls being exercised to establish procurement technical, quality and dedication requirements for replacement items.

Developed and instmeted extensive, comprehensive training courses in materials management and procurement engineering for nuclear utilities.

1986-89 Program Manager - Responsible for the marketing, development and management of materials management programs which included developing guidelines for the classification, procurement and qualification of replacement items proposed for use in safety-related applications. Program activities included assessment of commercial grade parts c ualification capabilities of numerous nuclear suppliers, performmg fai. ure modes and effects analyses and risk analyses, c evelop optimum dedication methods and gdevelopm,ing dedication design verified procurement criteriz., se documents for spare parts. Also participated in independent assessments of existing utility commercial grade item procurement and qualification programs, as well as programs at numerous nuclear / commercial equipment manufacturers.

1985-86 Mechanical Project Engineer - South Carolina Electric and Gas Company, V.C. Summer Nuclear Station, Continuing Services Project - Coordinated completion of numerous system design modifications. Assignment included technical experience with PWR main steam, main and auxiliary feedwater, post-accident sampling, service water, extraction steam, circulating water and component cooling water systems. Developed and managed the Spare Parts Qualification Program, including conducting r failure mode and effects analyses, risk analyses and developing piece-part

! dedication criteria.

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O 1985-86 Lead Mechanical Engineer - Metropolitan Edison Company, Tints Generating Station - Performed mechanical design functions for the replacement of soot blowing and control air compressors.

1984-85 Contracts Administrator, G/C Power Equipment Program - Expanded the number of surplus inventories, developed a marketing plan, established selling procedures, and developed operating procedures to negotiate the transfer of s us nuclear components and spare parts to engmeered safety-related applic tions.

1981-85 Lead Mechanical Engineer - Pennsylvania Electric Company, Continuing Services Project - Coordinated interdisciplinary efforts to successfully complete the detailed design of the following plant modifications:

Coal Pulverizer Replacement

• Fire Service System Improvement Addition ofFourth Dewatering Bin Turbine Water Induction Protection Bottom Ash Hopper Replacement Reconstruction of Existing Dewatering Bins Boiler Air Blow Design Bottom Ash Handling System.

O Also responsible for the preliminary design and timely issue of numerous

() engineering studies.

1979-81 Drexel University. Philadelphia. Pennsv1vania Teaching Assistant - Responsible for undergraduate instruction in several mechanical engineering courses while completing requirements for master's degree.

1974-79 Military Service 1978-79 Captain, U.S. Army - Supervised the design, installation, operation and ,

maintenance of commumcations systems, meluding the rapid deployment of I FM radio, radio-teletype and AM voice systems. Managed on-base telephone system and early warning communications center.

1974-78 Lieutenant, U.S. Army - Commanded a 110-person tactical communications company responsible for supporting divisional VHF multichannel, FM voice and digital, and AM single-sideband systems.

EDUCATION: B.S., Mechanical Engineering, U.S. Military Academy at West Point,1974 M.S., Mechanical Engineering, Drexel University,1981 M.B.A., Corporate and Financial Management, St. Joseph's University, 1984 Proficient in the use of most word processing, spread-sheet, database, i

presentation, projec,t planning / scheduling, time management, data j acquis.it ion, digital unaging, and communications computer software A programs.

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, 0 REGISTRATION: Professional Engineer, Mechanical - Pennsylvania (1985),

Tennessee (1992), Alabama (1993)

SDCIETIES: American Society of Mechanical Engineers (ASME)

American Nuclear Society (ANS)

National Society of Professional Engineers (NSPE)

U. S. Council for Energy Awareness, Public Speaker PUBLICATIONS: " Computerized Engineering Logic for Procurement and Dedication Processes," 1996 Annual Meeting, American Nuclear Society, Reno, Nevada, June 1996.

" Bench marking Certified NDE Personnel Needs in the US Nuclear Power Industry," 1995 Annual Meeting, American Nuclear Society, Philadelphia, Pennsylvania, June 1995.

" Process Re engineering Technology for Nuclear Power Generators,"

WATTEC '95, Knoxville, Tennessee, February 1995.

".Reengineering For Improving Nuclear Materials Control at the Oak Ridge High Flux Isotope Reactor," 35th Annual Meeting, Institute of Nuclear

, Materials Management, Naples, Florida, July 1994.

"How EPRI Guidance Can Strategically Improve Competitiveness by Optimizing the Procurement Process," 1994 Annual Meeting, American (3 Nuclear Society, New Orleans, Louisiana, June 1994.

U " ENCOMPASS - Technology Transfer of Design Engineering Processes,"

WATTEC '94, Knoxville, Tennessee, February 1994.

" Enhanced Design and Specification Methods for Next-Generation Nuclear

! Power Plant Equipment," 9th Intemational Conference on Engineering Design, the Hague, Netherlands, August 1993.

"An Acceptable Supplier / Item Performance Record Is A Viable Acceptance Method," 1993 Annual Meeting, American Nuclear Society, San Diego, Califomia, June 1993.

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" Sampling Plans for Commercial Product Testing and Verification

' Activities," ASTM Symposium on Quality and Statistics: Total Quality Management, Atlanta, Georgia, May 1993.

"How the 1980s Nuclear Procurement Initiatives Will Impact Next Generation Plant Equipment," ANS/ASME Nuclear Enery Conference, San Diego, Califomia, August 1992.

"The Future of Nuclear Materials Management: Lessons Leamed and Preparation for the Next Generation of Plants," 33rd Annual Meeting, Institute of Nuclear Materials Management, Orlando, Florida, July 1992.

" Total Quality Startup in an A/E's Regional Office," 46th Annual Quality Congress, American Society of Quality Control, Nashville, Tennessee, May 1992.

" Main Reactor Coolant Pump: Replacement Items, CGI Dedication and Nondestructive Examination," Fifth Intemational Workshop on Main m/ Coolant Pumps, Orlando, Florida, April 1992.

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c M l "Next Generation Nuclear Equipment: Lessons Leamed from the l Procurement Initiatives of the 1980s," WATTEC '92, Knoxville, j Tennessee, February 1992.

i "The Quality Management Function in an Engineering / Consulting Company," 7th Annual Fall Forum, Association for Quality and Participation, Denver, Colorado, October 1990.

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" Nuclear Materials Management in the b 90s - Computer Automated Procurement," 1990 Annual Meeting, American Nuclear Society, Nashville, Tennessee, June 1990; and ENC'90, European Nuclear Society, Lyon, France, September,1990.

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" Cost Benefits of an Effective Nuclear Procurement Program," 17th Annual l Energy Division Conference, American Society of Quality Control, i Atlantic City, New Jersey, March,1989; and 1989 Annual Meeting, American Nuclear Society, Atlanta, Georgia, June 1989.

" Nuclear Materials Management in the 1990s - Automated Procurement and  !

Barcoding," 30th Annual Meeting, Institute of Nuclear Materials I Management, Orlando, Florida, July 1989.

" Application of Acceptance Methods for Commercial Grade Items," 16th l Annual Energy Division Conference, American Soci^ty of Quality Control, Atlantic City, New Jersey, March 1988.

O p "The Utilization of Commercial Grade Items in Safety Applications," 14th Annual Energy Division Conference, American Society of Quality i

Control, Las Vegas, Nevada, September 1987.

"The Procurement and Use of Commercial Grade Items in Safety Related Applications," 1987 Winter Meeting, American Nuclear Society, Los Angeles, Califomia, November 1987.

AWARDS: American Nuclear Society, " Outstanding Session Organizer Award," 1991 '

and 1993 AnnualMeetings American Nuclear Society, "Be::t Payr Award," 1990 Annual Meeting Pennsylvania Society of Professiona: Engineer "1988 Young Engineer of the Year," Reading Chapter Recipient of Drexel University Graduate Fellowship,1979 U.S. Army Meritorious Service Medal,1978 U.S. Army Commendation Medal,1977 D

Persons Poner Grae 824612 11004 Page 5

,(qy M Lead Engineer, Process Models and Operational Analysis 1

Eighteen years of experience in management of small and large projects, including 15 years in performing and managing design modifications ofnuclear power plants. Proven ability in evaluating and establishing effective and efficient business processes. Nationally recognized authority on nuclear spent fuel management and high level waste disposal issues. Outstanding leader with proven record of accomplishments EXPERIENCE: Performance Technoloev. Inc.

1995 to Present Principal Consultant - Business process consulting to the utility, transportation, govemment, and public sector.

Risk Management - Led a cross-functional team in ma? ping existing processes for managing elements of risk at Conrail ine udmg rail car and freight damage, personal injury reduction, environmental, and litigation.

The team developed process changes totaling $9.2 million in annual savings and introduced statistical measurements to monitor the new processes.

Facility Processing Capacity - Training and consultini; services for mapping ofinterfaces between organizations and various process that exist at a major rail car classification facility. Developed changes in information technology, facility design, personnel utilization, maintenance processes, and performance measurements to increase traffic flow and reduce existing process bottlenecks.

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V 1981-95 1994-95 Gilbert / Commonwealth. Inc.. Readine. Pennsylvania Senior Consultant - Provided management services, and consulting in the areas of high performance business process reengineering and high level waste and spent fuel management.

' Maintenance Work Control Process - Consulted on process design methodology, and facilitated mapping and redesign of maintenance process for IES Utilities. The Project Team identified 35% annual savings for work planning and administration.. Automated generation ofpreventative maintenance work packages will reduce O&M costs by $2.5 million/ year.

I As-built Documentation Process - Consulting services to identify the way different groups were updating design documentation as a result of equipment and facilities modification at American Electric Power. Process ma?s provided a tool to communicate to management the current problems anc process inefficiency in preparation for a redesign of the document control process.

Modification Process - Consulted on process design methodology, and facilitated redesign of modification process for major design changes at Pennsylvania Power & Light (PP&L). Facilitated cross functional client team, consisting of union and nonunion personnel, through mapping and analysis of existing process, benchmarking, process measurements, design of new process, development of business case and implementation plans.

The resulting process, organization, information technology and 3 management control changes was estimated oy PP&L to be worth $2.6 million/yearin savings.

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1993-94 Process Consultant - Assigned to general engineering services project for Carolina Power and Light (CP&L). Responsible for design and implementation of cost effective interface processes between G/C and CP&L. Devised work task proposal process to shorten turn around time and i

improve communication with client on how G/C would perfoms work and

- interface with CP&L. Implemented project management controls to ensure effective, high quality engineering services. Provided assessment and improvement recommendations of CP&L internal processes to help this client lower costs and become more competitive.

i 1993 Process Consultant - Assigned to continuing services project for PP&L.

Responsible for reengineering the project pro;msal development process.

The new process reduced average tum around time from three weeks to four j days, and eliminated an anticipated need to increase project support staff.

1992 Litigation Support: Provided consulting services to the U.S. Department of Justice on vanous aspects of nuclear power plant design and the nuclear utility industry in support oflitigation regarding the construction costs associated with canceled nuclear power facilities.

1991-92 Project Manger - Responsible for 56.2 million annual revenue for G/C services provided to Philadelphia Electric Company (PEco). Directed a s multi-disciplined team that performed engineenng/ design and related nuclear power plant sup;mrt services for this client. Work included modification design paciages, engineering programs and studies (including

( GL 89-10, GL 89-13, and EQ), and development of design configuration basis documents Responsible for overall direction and management of the project team, and the enhancement of client interface processes.

1989-91 Senior Project Manager - Philadelphia Electric Company, corporate home office staff extension - Accountab e to the manager of projects for directing a staff of modification team project managers in preparation for Peach Bottom, Unit 3, cycle 8 operations and refueling outage. Project Manager for resolution ofservice water design basis system functional testing deficiency. Successfully lead a team of engineering and plant staff personnel in performing design basis investigation, functional testing, and preparation for NRC reviews.

1988-89 Site Manager - Philadelphia Electric Company, Peach Bottom Atomic Power Station - Supervised and managed a multi-disciplined engineering and administration group of 60 people supporting the restart of Units 2 & 3.

Responsible for cost, schedule and technical quality of work. Major areas of support include development and implementation ofcommercial grade dedication program for spare parts, engineering and design of modifications required for restart, disposition of non-conformances and station questions, walkdowns and support for INPO and NRC audits and inspections.

1981-88 Project Engineer - Provided project administration and technical direction o for various engineering projects including spent fuel storage expansion at

() Peach Bottom and Limenck stations, advanced conceptual design of high

, level waste packages for a national geologic repository in basalt rock, and Persons Power Goup 824612 11004 Page 2

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[ development of the nation's first license application for a new facility under 10CFR part 72 and applicable NRC regulatory guides.

1980-81 American Electric Power Service Comoration. New York. New York Nuclear Engineer - Engaged in contract negotiation and administration of nuclear fuel supply services. Performed fuel cycle cost analyses used in 4

determining rates and operation cycle lengths. Responsible for monitoring government programs related to nuclear spent fuel.

, 1978 80 Project Engineer - D.C. Cook Nuclear Plant - Responsible for expansion of the spent fuel storage capacity including: bid specification, design review,

license analysis and mstallation of high-density racks.

1974-78 Engineer and Co-op Student - Performed in-core neutronic analysis. D.C.

Cook, Unit 2, - Supported initial criticality and low power physics testing.

EDUCATION: B.'s., Engineering Physics, Cornell University, Ithaca, New York,1976 M.S., Nuclear Engineering, Cornell University, Ithaca, New York,1977 REGISTRATION: Professional Engineer - Pennsylvania (1983)

SOCIETIES: Chairman of Standards Committee ANS 57.7 " Design Criteria for an e Independent Spent Fuel Storage Installation (Water Pool Type),"

( American Nuclear Society Chairman of Standards Committee ANS 57.9 " Design Criteria for an

( Independent Spent Fuel Storage Installation (Dry Storage Type),"

American Nuclear Society Chairman of Standards Committee ANS 57.10 " Design Criteria for Consolidation of LWR Spent Fuel, " American Nuclear Society Past member of Standards Committee ANS 57.2 " Design Requirements for LWR Spent Fuel Storage Facilities at Nuclear Power Plants" Past member of Standards Committee ANS 57.3 " Design Requirements for New Fuel Storage Facilities at LWR Plants" PUBLICATIONS: " Interim Spent Fuel Storage Using Rod Consolidation," American Nuclear Society

" Spent Fuel Storage: What's the Next Step?," Waste Management Conference "Altematives for Spent Fuel ," WATfee Annual Energy Conference

" Alternatives for Dry Storage," Institute of Nuclear Materials Management

" Wet Pool Independent Spent Fuel Storage Installation" American Nuclear Society

" Prospects for Spent Fuel Disposal in the U.S.A.," USA-ROC Joint Economic Councils, Taipei, Taiwan "GAI-Vault, G/C Reference Design Dry Spent Fuel Storage Vault,"

American Nuclear Society Topical Meeting

" Economic and Feasibility Analysis of I8-Month Fuel Cycles," American Nuclear Society Annual Meeting Cs C

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I Licensing and Risk Assessment

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'\ M (Q Lead Engineer, Licensing and Risk Assessment Twenty-three years of experience in nuclear licensing and plant operations in support of domestic and international clients. Nuclear licensing experience includes technical coordination during operating license review, regulatory conformance reviews, safety issue resolution, regulatory  ;

interface, safety analysis preparation and review, independent design verification, and safety evaluation preparation.

EXPERIENCE: PARSONS POWER (formerly Gilbert / Commonwealth ) since 1979 1985 to Present Senior Nuclear Licensing Engineer - Pdncipal contact for Parsons Power (Gilbert / Commonwealth) nuclear licensing activities. Responsible for evaluating and disseminating Nuclear Regulatory Commission and industry-related licensing information to appropriate technical disciplines and all nuclear projects. Act as the company's point ofcontact for Nuclear Energy Institute (NEI) matters. Responsible for providing licensing input for all nuclear projects and programs such as license renewal, maintenance rule implementation, regulatory interpretation, responses to NRC Bulletins /Infonnation Notices, input and review of safety evaluations and attendance at NRC and ACRS meetings.

Projects include:

South Carolina Electric & Gas Company, V.C. Summer Nuclear Station Nukleama Elektrarna Krsko NPP, Slovenia.

. National Electric Company - Bulgaria Philadelphia Electric Company, Peach Bottom Atomic Power Station and Limerick Generating Station Pennsylvania Power & Light Company, Susquehanna Steam Electric Station Public Service Gas & Electric, Salem and Hope Creek Stations Florida Power Corporation, Crystal River, Unit 3 Tennessee Valley Authority, Sequoyah and Bellefonte Stations l GPU Nuclear Corp. Saxton Experimental Nuclear Facility Senior Licensing Engineer - South Carolina Electric and Gas - V. C.

Summer Nuclear Station, FSAR Verification Program including programmatic input, safety evaluation review, and preparation of FSAR changes.

Senior Licensing Engineer- GPU Nuclear Corporation - Coordination of licensing activities in support of preparation and submittal of a Decommissioning Plan for the Saxton Nuclear Experimental Facility,

'q located in Saxton, Pennsylvania, to the NRC.

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'V Senior Licensing Engineer - Responsible for the final licensing review of the report on Control Room Design Review for NPP Krsko.

l Task Manager - Nukleama Elektrama Krsko, Regulatory Compliance Program review - Responsible for technical activities in joint venture with NSSS vendor for review of compliance to all NRC regulatory changes, regulatory guides, generic letters, unreviewed safety questions and bulletins issued by the NRC since 1974.

Project Licensing Engineer - DOE /MMES, Advanced Neutron Source Project (ANS) - Responsibilities included the preparation of licensing / regulatory plan and permitting plan, coordination of preparation of A/E sections of the Conceptual Safety Analysis Report and regulatory interpretation.

Task Manager - NE Krsko, FSAR Upgrade Project - Responsible for the preparation and publication of the Updated Safety Analysis Report, including review and incorporation of plant modifications and technical specifications.

O O Pennsylvania Power & Light Company - Technical specialist in support of intemal audits in the areas ofplant chemistry program and medical qualifications oflicensed operators.

Project Licensing Engineer - South Carolina Electric & Gas Company, V.C.

Summer Nuclear Station (PWR) - Coordinated licensing activities including review of design change safety evaluations, and tracking design modifications for inclusion in FSAR update. Preparation of FSAR amendments required by 10CFR50.71(c). Provided input to Phase I

implementation of 10CFR50.65 " maintenance rule."

L 1979 to 1985 Project Licensing Engineer - Cleveland Elecuic liluminating Company, Perry Nuclear Power Plant, Units 1 & 2 (1200 MW each)- Responsible for technical coordination oflicensing activities during final safety analysis review development and operating license review stage. Met directly with NRC reviewers to resolve issues . Also provided technical assessment of U.S. Nuclear Regulatory Commission documents, preparation of technical input in support of the Safety Evaluation Report , prepared NRC presentations and coordinated G/C input for ACRS presentations and coordination of technical specification input. Participated on team to resolve action items from NRC Integrated Design Inspection (IDI).

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1973-79 Metropolitan Edison Comoany. Readinn. Pennsylvania 1978-79 Supervisor of Generation Licensing - Responsible for the licensing of the company's nuclear generating units and fossil-fueled generating units including interface with the Nuclear Regulatory Commission, Environmental Protection Agency, and Department of Environmental Resources. Served on Executive Committee of Babcock & Wilcox Owners Group. Direct supervision of 14 people.

1975-78 Lead Nuclear Engineer - General Public Utilities, Three Mile Island Nuclear Station, Unit 1 - Responsible for core physics, special nuclear material control, reactor refueling, reload licensing and physics testing.

1973-75 Project Engineer, Three Mile Island Nuclear Station, Unit 1 - Assisted on shift in initial startup activities of 900 MW nuclear unit, including initial 4

fuel receipt and fuel loading, initial startup, and power operations. Assisted in review and preparation ofplant surveillance, test, and operating procedures.

1970-73 The Pennsylvania State University. University Park. Pennsylvania Breazeale Nuclear Reactor - Assisted in daily operations of 1 MW TRIGA i

research reactor facility (full-time position). Obtained Atomic Energy 1

Commission Reactor Operator's license while continuing research in the area of thermoluminescent dosimetry. Assisted in training program for utility reactor operators.

EDUCATION: B.A., Physics, Susquehanna University, Selinsgrove, Pennsylvania,1969 M.S., Nuclear Engineering, The Pennsylvania State University, University Park, Pennsylvania,1973 Additional Courses:

Supervisory Development for Utility Managers, Rutgers University, 1978 Facilitator Certification, The Quality Advantage, ODI,1992 SOCIETIES: American Nuclear Society CERTIFICATION: Certified Lead Auditor I

Persons Power orme 824612 11004 Page 3

'D Risk Assessment Physicist and engineer with a background in research, operations support, engineering, analysis, and executive management. Ph.D. thesis on unified systems safety analysis first advocated what is now known as probabilistic risk assessment (PRA). Built the first consulting team to perform the initial comprehensive and quantitative risk assessments (QRA) for the commercial nuclear power industry. Major contributor to the analytical methods and thought processes employed in PRA. Prime mover in elevating risk assessment to a science and engineering discipline that has had a major impact on management culture and the performance oflarge, complex engineered systems. Served as general chairman of several national technical society meetings and founder of the Southem Califomia Chapter of the Socicty for Risk Analysis. U.S. representative on several international panels and delegations offering technical advice to foreign nations including Eastern Europe. Extensive experience as an expert witness in hearings related to risk and safety.

EXPERIENCE: PLG. Inc.

1975 to Present President, Chairman of the Board, and ChiefExecutive Oflicer of a consulting firm of engineers, applied scientists, and management consultants with offices in Newport Beach, Califomia; Bethesda, Maryland; Encinitas, Califomia; Albuquerque, New Mexico; and Tokyo, Japan.

1957-75 Holmes & Narver. Inc.

Key positions held included member of Board of Directors; President, g Nuclear and Systems Sciences Group; Senior Corporate Vice President;

( g Vice President, Science and Technology, The Resource Sciences v

Corporation, Tulsa, Oklahoma (parent company to Holmes & Narver, Inc.).

1955-1957 Atomic Enerev Commission. Washincton DC Physicist.

i 1952-54 Phillins Petroleum Comoany (Atomic Energy Commission Contractor)

Physicist - National Reactor Testing Station, Idaho, i

EXPERTISE: Nuclear Energy l 1

Thought leader and leading practitioner of PRAs of nuclear power plants.

Consultant in risk, reliability, engineering analysis, and management analysis of nuclear power plants. Directed more than 35 nuclear power plant large scope PRAs. Served on numerous national and intemational advisory groups, panels, and delegations connected with nucler nlant safety and i engineering. Vice Chair.aan ofNational Academy of 5 iences' Board on Radioactive Waste Management. Member of the Waste Isolation Pilot Plant Committee, the Committee on Separations Technology and Transmutation Systems, the Committee on Environmental Management Technologies, and the Committee to Review Risk Management in the U.S. Department of Energy's Emironmental Remediation Program.

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Aerospace Researched space and defense methods in safety and reliability and other assurance sciences. Served on National Research Council's Committee on Space Shuttle Criticality Review and Hazard Analysis. Risk and safety consultant to National Aeronautics and Space Administration's Associate Administrator for Safety, Reliability, Maintainability, and Quality Assurance. Course Director of the American Institute of Aeronautics and Astronautics Annual Course on Quantitative Risk Astessment and Management. Team leader ofrisk and safety analyses for military aerospace systems and study director of QRAs of space shuttle subsystems. Facilitator

, at the national technical society level for technology exchange in risk and safety for the aerospace, nuclear, defense, and chemical industries. Private

, pilot.

Chemical Process Member of technical startup and operations team for the world's first chemical reprocessing plant for highly enriched nuclear fuel. Instigator of quantitative risk assessment methods for chemical process plants.

Researched risk and safety analysis techniques for application to chemical J p) q' plants. Directed numerous risk assessment efforts involving a wide variety of chemicals, chemical processes, and refinery operations. Directed 4

' independent oversight team during restart and early operation of a chemical process plant critical to the nuclear fuel cycle. Risk and safety consultant and advisor to chemical plant owners and operators. Served on National Academy of Sciences' Committee on Army Chemical Stockpile Disposal Program.

Academic Adjunct Professor, University of Califomia, Los Angeles.

Lecturcr, Annual Reactor Safety Course, Massachusetts Institute of Technology.

Chairman, Associated Universities Visiting Committee for the Brookhaven National Laboratory Department of Nuclear Energy.

Chairman, Industrial Liaison Committee, Nuclear Engineering and Engineering Physics Department, University of Wisconsin.

Member, External Advisory Group, University of Wisconsin Center for Human Performance in Complex Systems.

Served on and chaired many accreditation teams evaluating engineering G programs at universities throughout the U.S.

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V Extensive short course, seminar, workshop, and committee assignments at universities, government agencies, corporations, and other institutions, such as the U.S. Department ofEnergy, the North Atlantic Treaty Organization, United Kingdom's National Center of Systems Reliability, the Electric Power Research Institute, and the Govemor of California's Emergency Task Force on Earthquake Preparedness.

Member, National Research Council's Working Group; U.S.-Japan Joint Task Force on Engineering Education.

i

,' '1 CATION: Ph.D., Engineering and Applied Science, University of Califomia, Los

Angeles,1968 M.S., Engineering, University of California, Los Angeles,1962 U.S. Atomic Energy Commission Grant-in-Aid, Oak Ridge School of Reactor Technology,1954-55

B.S., Physics, Biigham Young University,1952 REGISTRATION: Professional Engineer, State of Califomia liONORS AND AWARDS: Recipient of the Society for Risk Analysis' Highest Honor, the s Distinguished Achievement Award,1994 Invited by the North Atlantic Treaty Organization to cohaborate with

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Eastem, Central, and Western European scientists to develop new disarmament technologies,1994-95 Appointed to the U.S. Nuclear Regulatory Commission's Advisory

Committee on Nuclear Waste,1994 Elected to the National Academy of Engineering,1993 Fellow, American Nuclear Society Fellow, Society for Risk Analysis Fellow, Institute for the Advancement of Engineering Past President, Society for Risk Analysis (an intemational professional society),1990 Past President, Los Angeles Maintainability Association Member, Engineering Accreditation Commission, a National Commission 2

' of the Accreditation Board for Engineering and Technology Member, American Nuclear Society 14-member delegation to Czechoslovakia and Hungary on Nuclear Power Plant Safety,1991 Selected to attend the United States Atomic Energy Commission's prestigious Oak Ridge School of Reactor Technology to do graduate

, work in Nuclear Science and Technology,1954 PUBLICATIONS: Published more than 200 papers and reports on risk, c-liability, engineering, and technology.

Author of several book chapters and editor of the text, ne Analysis, Communication, andPerception ofRisk, Plenum Press,1989.

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()C Risk Assessment l

Over 24 years of experience in the nuclear industry Performed and reviewed Individual Plant Examination for Extemal Events (IPEEE) and fire risk quantification at numerous domestic and intemational nuclear facilities. Author / contributing author ofmore than 14 NUREG publications associated with IPEEE and risk assessments.

EXPERIENCE: Lambricht Technical Associates. Albuoueraue.NewMexico 1996 to Present President - Project responsibilities include:

Performing accident risk assessment for the Los Alamos Site-Wide Environmental Impact Statement (SWEIS).

Reviewing external event hazard submittals from nuclear power plant licensees for Energy Research,Inc.

Performed IPEEE fire risk assessment for the Slovenian Krsko nuclear power plant.

1995-96 Beta Comoration. Albuoueraue. New Mexico Vice President of Environmental Health and Safety Programs - Project responsibilities include:

(y Served as manager ofimpact assessment group for the Los Alamos SWEIS.

Developed impact and risk assessment methodological approach.

1 s Developed a strategy, based upon cost benefit assessment, to upgrade the Slovenian Krsko nuclear power plant to Westem safety standards. This work was performed for the Slovenian Government.

Performed the accident risk assessment for the Rocky Flats SWEIS.

Performed the external events hazard assessment for the Mochovce nuclear power plant in Slovakia. This work was performed for the Austrian Government.

1985-95 Sandia National Laboratories. Albuaueraue. New Mexica Senior Member of the Technical Staff- Project responsibilities include:

Project Manager for the resolution of Generic Issue 57, which addressed the adverse impact of fire protection system actuations on safety-related equipment at commercial United States nuclear power plants. This

$1.4 million, three-year project was completed in August 1993.

Member of the Intemational Commission for Independent Analysis of the Safety of the Slovenian Nuclear Power Plant. Technical responsibilities as representative for the Austrian government included performance of an O

(O extemal risk evaluation for the Krsko nuclear power plant and recommendations for plant safety upgrades.

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Project Manager for other analytical safety assessments of commercial reactor plants including Surry, Peach Bottom, LaSalle, and Grand Gulf, as

, well as Department of Energy facilities such as N-Reactor and K-Reactor at Savannah River. i Project Manager for the Fire Risk Scoping Study, which assessed the risk impact of previously unaddressed fire issues at commercial United States nuclear power plants.

Performed the seismic risk assessment for the ANO-1 Nuclear Power Plant.

Performed an internal events risk assessment for the Peach Bottom Atomic Power Station.

Developed the methodology for the resolution of Fire Risk Scoping Study issues, the assessment of Generic Issue 57, and the fire risk assessment techniques used for NUREG-1150. Reviewed other extemal event risk assessments for both commercial nuclear power plants and DOE reactor facilities. Performed a review of an application of the FIVE (fire risk) methodology documented in the Nuclear Safety Analysis Center Fire Risk Evaluation Report (NSAC/l81).

- Maintained close interaction with the Offices of Research and Regulation of

( the United States Nuclear Regulatory Commission. Many presentations t were made to the Advisory Committee on Reactor Safeguards, Congressional Subcommittee as well as a wide variety ofpresenutions to the USNRC and the nuclear community.

In February of 1990, received an award for excellence recognizing contributions to state-of-the-art fire probabilistic risk assessment methods and the insights to NUREG-1150 that resulted from their application.

Nominated for an award as Project Manager of Generic Issue 57.

1981-85 University ofIllinois TRIGA Facility Licensed Reactor Operator at the university's research reactor facility.

1972-82 United States Navy. Idaho Falls. Idaho '

Served as an Engineering Watch Supervisor and Instructor at the USN reactor training facility in Idaho Falls, Idaho. Served as a Rector Technician and Plant Supervisor aboard the USS South Carolina. Graduated in the top two percent of the class from a two-year program at the Nuclear Power School and Electronics Technical School.

EDUCATION: Pn.D., Nuclear Engineering, University of New Mexico,1994 M.S., Nuclear Engineering (with Honors), University ofIllinois,1985 B.S., Nuclear Engineering (with Honors), University of(llinois,1985

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'C t CLEARANCES: Active Department of Energy "Q" Clearance Inactive Department ofDefense Secret Clearance PUBLICATIONS: " Review of the Pilgrim Nuclear Station Individual Plant Examination for Extemal Events," prepared for Energy Research, Inc., Febmary 1996.

"Los Alamos Site Wide Em'ironmental Impact Statement Impacts and Risk i

Methodology Report," prepared for GRAM, Inc., December 1995.

" Rocky Flats Site Wide Environmental Impact Statement Accidents Analysis," prepared for Parsons Brinkerhoff, Inc., September 1995.

" Review of the Limerick Generating Station, Units 1 and 2 Individual Plant Examination of Extemal Events," prepared for Energy Research, Inc.,

September 1995.

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" Review of the Susquehanna Steam Electric Station Individual Plant Examination of External Events," prepared for Energy Research, Inc.,

September 1995.

" Review of the Nine Mile Point Unit 2 Nuclear Station Individual Plant Examination of External Events," prepared for Energy Research, Inc.,

September 1995.

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" Review of the Haddam Neck Plant Individual Plant Examination of v External Events," prepared for Energy Research, Inc., July 1995.

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" Rocky Flats Site Wide EnvironmentalImpact Statement Accident Screening Analysis," prepared for Parsons Brinkerhoff, Inc., July 1995.

" Review of the Diablo Canyon Power Plant Individual Plant Examinations for Extemal Events," prepared for Energy Research, Inc., July 1995.

" Risk / Impact Integration Approach and Inclusion of Stakeholder Preferences for DOE Decision Making Under NEPA Environmental i

Impact Statements," prepared for GRAM, Inc., Mey 1995.

"Mochovce Nuclear Power Plant Extemal Event Bounding Risk Analysis,"

i prepared for the University of Vienna, April 1995.

"Extemal Events Hazards Assessment for the Slovakian Mochovce Nuclear Power Plant," prepared for the University of Vienna, February 1995.

" Impact of Nuclear Rocket Engine Design on Control Strategies," Ph.D.

Thesis, November 1994.

" Individual Plant Examination for Extemal Events (IPEEE) Review Guidance Document," prepared for the United States Nuclear Regulatory Commission, November 1994.

"A Review of Fire PRA Requantification Studies Reported in NSAC/181,"

prepared for the United States Nuclear Regulatory Commission, A April 1994.

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" Analysis of Core Damage Frequency Due to Fire During Shutdown Plant Operational State 5, Grand Gulf Nuclear Power Plant,"

NUREG/CR-6175, March 1994.

" User's Guide for a Personal Computer Based Nuclear Power Plant Fire Data Base," NUREG/CR-4586, March 1994.

" Core Damage Frequency Analysis of External Events at the Krsko Nuclear Power Plant," prepared for the University of Vienna, October 1993.

" Analysis of Extemal Events at the Krsko Nuclear Power Plant," prepared for the University of Vienna, September 1993.

" Analysis of the LaSalle Unit 2, Internal Fire Analysis," NUREG/CR-4832, March 1993.

" Analysis of the LaSalle Unit 2, Nuclear Power Plant: Risk Methods and Evaluation Program," Volume 5, Parameter Estimation Analysis and Screening Human Reliability Analysis, NUREG/CR-4832, March 1993.

" Evaluation of Generic Issue 57: Effects of Protection System Actuations on Safety-Related Equipment: Root Cause Development and Summary Report," NUREG/CR-5580, December 1992.

g " Risk Evaluation for a Westinghouse Pressurized Water Reactor, Effects of Q Fire Protection System Actuation on Safety-Related Equipment (Evaluation of Generic Issue 57)," NUREG/CR-5789, December 1992.

" Risk Evaluation for a General Electric Boiling Water Reactor, Effects of Fire Protection System Actuation on Safety-Related Equipment (Evaluation of Generic Issue 57)," NUREG/CR-5791, December 1992.

" Analysis of Core Damage Frequency Due to Fire at the Krsko Nuclear Power Plant," prepared for the University of Vienna, December 1992.

" Risk Evaluation for a Babcock & Wilcox Pressurized Water Reactor, Effects of Fire Protection System Actuation on Safety-Related Equipment (Evaluation of Generic Issue 57)," NUREG/CR-5790, September 1992.

" Review ofIndian Point Unit 2 Risk Analysis (Including Reevaluation of Seismic Scenarios)," prepared for the United States Nuclear Regulatory Commission, June 1992.

"A Review of the South Texas Project Probabilistic Safety Analysis for Accident Frequency Estimates and Containment Binning,"

NUREG/CR-5606, August 1991.

" Analysis of Core Damage Frequency Due to Fire at the Savannah River K-Reactor," SAND 89-1786, January 1991.

" Analysis of Core Damage Frequency: Peach Bottom Unit 2 Extemal Events," NUREG/CR-4550, Volume 3, December 1990.

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" Analysis of Core Damage Frequency: Surry Power Station External Events," NUREG/CR-4550, Volume 3, December 1990.

" Analysis of Core Damage Frequency Due to External Events at the DOE N-Reactor," SAND 89-1147, November 1990.

" Recommended Procedures for Simplified External Event Risk Analysis,"

NUREG/CR-4840, November 1990.

" Review of the Oak Ridge National Laboratories HIFR Reactor Facility Risk Assessment," March 1990.

" Impact of Updated Information and Modeling Techniques on Four Previously Completed Commercial Nuclear Power Plant Fire PRAs,"

published in PSA Conference Proceedings, April 1989.

"An Overview of the Fire Risk Scoping Study: Objectives, Approach, Findings, and Follow-On Efforts," published in PSA Conference Proceedings, April 1989.

" Unaddressed Issues in File Modeling and Risk Assessment,"in Proceedings ofIAEA Symposium on Fire Protection and Fire Fighting in NuclearInstallations, March 1989.

m "An Overview of the Fire Risk Scoping Study at the EPRI Workshop on Q Nuclear Power Plant Fire Safety," published in Conference Proceedings, February 1989.

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" Fire Risk Scoping Study: Investigation of Nuclear Power Plant Fire Risk, Including Previously Unaddressed Issues," NUREG/CR-5508, January 1989.

" Seismic Risk Assessment for the ANO-1 Power Plant,"NUREG/CR-4713, March 1987.

" Analysis of Core Damage Frequency from Internal Events: Peach Bottom Unit 2," NUREG/CR-4550, October 1986.

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Over twenty years of experience in the design, operation, testing and maintenance of nuclear and '

fossil power generating plants. As Manager, Life Cycle Services, responsible for analysis, development and performance of Parsons Power's License Renewal, Aging / Lifetime Management, Plant Improvement and Decommissioning programs. Previous positions included design basis engineer, configuration management, modification engineer, pre-operational test director, shift supervisor, operations engineer, maintenance engineer and training engineer.

EXPERIENCE: PARSONS POWER (formerly Gilbert / Commonwealth) since 1988 1991 to Present Manager, Life Cycle Services - Responsible for the analysis, development and performance of Parsons Power's License Renewal, Aging / Lifetime

' Management, Plant Improvement, and Decommissioning programs.

Responsibilities include strategic planning, detailed technical approach development, resource / capability development and task management.

Task Manager - Westinghouse, Westinghouse Owner's Group (WOG), Life Cycle Management / License Renewal Program - Responsible for technical direction of Gilbert / Commonwealth activities associated with development of task scope descriptions for the program plan, consultation on Integrated Plant Assessment (IPA), analysis of Life Cycle Management / License Renewal (LCM /LR) information management requirements, and preparation of system and commodity technical report guidelines. Provided e

operations and maintenance practices evaluations, Time Limited Aging

' Analysis, and aging analysis / management reviews for WOG-EPRI Generic Technical Reports for RHR system, motor operated valves, check valves, heat exchangers, reactor vessel /RCS supports, containment, reactor vessel, class I piping, and pressurizers.

Task Manager - Sandia National Labs - Responsible for the development of an industry Aging Management Guideline (AMG) for tanks and pools.

i AMG identified design information, analyzed aging degradation, and evaluated industry aging management / maintenance practices for tanks and spent fuel storage pools. AMGs are part of U.S. Department of Energy (DOE) Plant Lifetime Improvement Program (PLIM).

Task Manager - Korea Power Engineering Company - Plant Lifetime Management (PLIM) study - Three-year economic and technical feasibility study for extended operations of the KORI-l nuclear plant in Korea.

Responsible for Phase II planning, economic evaluation, technology assessment, and establishing the scope (screening) of KORI-l systems, structures, and components. PLIM technical reports developed for reactor vessel, reactor intemals, reactor coolant pump, RCS nozzles, Pressurizer, Control Rod Drive Mechanisms, Containment I&C Cables, RCS piping, Containment, and Turbine Generator.

Task Manager - Westinghouse - Palisades Reactor Vessel Annealing, fl Responsible for the technical direction of Parsons Power activities

%) associated with NRC Thermal Annealing Request (TAR), thermal

( characterization of reactor vessel insulation, biological shield wall concrete

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analysis, ex-vessel instrumentation system, intemals characterization and shielding design, temporary reactor cavity HVAC design, and selected construction activities.

Task Manager - Westinghouse - Annealing Demonstration Project.  ;

Responsible for design, installation, and operation of ex-vessel l instrumentation system and associated data reduction. Also responsible for construction activities to prepare site and containment building for annealing operations.

Task Manager - Consumers Power - Big Rock Point Nuclear Plant -

Supported development of Big Rock Decommissioning Plan, options study, and cost estimate for NRC submission. Prepared decommissioning plan sections and supporting evaluations for reactor vessel, reactor vessel internals, steam drum, primary coolant system, control rod drive system, and reactor cleanup system. Options studies included packing / cutting details, resource requirements, and integrated scheduling.

Task Manager - Wisconsin Electric Power Company, Point Beach Nuclear Station - Responsible for the development of the License Renewal Project Management Plan. Project also included organizational readiness reviews and material assessments for major components and systems.

i^ Task Manager - South Carolina Electric & Gas Company, V.C. Summer Nuclear Station - Responsible for program planning and development of the maintenance rule program. Performed plant system screening, participated as member of expert panel, developed plant / system performance criteria, integrated maintenance rule program to Reliability Centered Maintenance program, and developed integrated information system.

Task Manager - Electric Power Research Institute - Responsible for engineering and cost data portion of the Gilbert / Commonwealth portion of the ALWR site selection and environmental criteria project. Sened as design consultant for Tennessee Valley Authority (TVA), ALWR site selection and environmental study.

1 Consultant - Prepared and conducted the following workshops:

Ontario Hydro - Life Cycle Management Strategies Korea Power Engineering Company - Life Cycle Management Florida Power Corporation - License Renewal South Carolina Electric & Gas Company - Maintenance Rule l

Implementation U.S. Department of Energy - Decommissioning and Deactivation Strategies D. Consumers Power Company - Big Rock Decommissioning Planning.

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'V Consultant - General Electric Nuclear Energy - Provided life cycle ,

component considerations and maintenance rule implementation i perspectives to support the General Electric (GE) Life Cycle Study for Chubu Electric.

Task Manager - Pennsylvania Power & Light Company, Susquehanna Station - Technical review and detailed enhancement recommendations of design standard GDS-10 " Life Assessment of SPLEX Components." 1 Consultant, Industry Initiatives / Assistant Technical Program Chairman -

ANS License Renewal Topical Meeting, Participant in IAEA pilot studies on aging management, Participant NUMARC AHAC on Maintenance Rule and License RenewalIntegration 1988-91 Program Manager - Gilben/ Commonwealth Design Basis Program -

Program manager for all Gilbert / Commonwealth design basis projects.

Prepared the Gilbert / Commonwealth corporate design guide for Design Basis Documents and provided Gilbert / Commonwealth's input to design basis committees / activities at ANS, NUMARC and NIRMA. Member of senior consultant team for TVA, Watts Bar Start-up Design Basis Strategy.

Developed General Public Utilities, Three Mile Island Design Baseline Pilot and program procedures for Baltimore Gas & Electric-Calvert Cliffs G i Nuclear Power Plant Design Basis Consolidation Program. Performed design basis verification of Davis-Besse feed and bleed system upgrades.

Assigned as senior consultant and reviewer for the following DBD projects:

Tennessee Valley Authority, Watts Dar Florida Power Corporation, Crystal River, Unit 3 General Public Utilities, Three Mile Island, Unit 1 Baltimore Gas & Electric Company, Calvert Cliffs Nuclear Power Plant South Carolina Electric & Gas Company, V.C. Summer Nuclear Station Philadelphia Electric Company, on Peach Bottom Atomic Power Station and Limerick Generating Station.

Program Manager - Gilben/ Commonwealth Configuration Management -

Lead engineer for Philadelphia Electric Company (PECo) Configuration Management Issues Review Team responsible for drawing change review, modification evaluation, maintenance of design bases, design interface reviews, modification acceptance testing and as-built programs. Provided resolution of PECo restart design issues. Also performed Waterford 3 NUCLEX assessment for design base documents,50.59 review and related configuration management issues. Configuration management audit / assessment lead at Cleveland Electric Illuminating Company, Perry Plant and Baltimore Gas & Electric Company, Calvert Cliffs Nuclear Plant.

Developed Rochester Gas & Electric Vendor Manual Upgrade Program and a

i lead assessment team. Served as senior consultant for Public Service Electric & Gas I&C Vendor Documentation Upgrade Projects.

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1982-88 Imoell Corooration. Fort Worth. Texas Group Lead Engineer - Hot Functional Test Sequence Coordinator -

Responsible for procedure development, design interface reviews, sequence preparations and operations compatibility review. Also responsible for the following technical specification surveillance test procedures: 18-Month

' Diesel Testing (Loss of Offsite Power, Safety Injection, Time Response, l od Run); Rx Trip and Safety Injection TADOTs; Containment Isolation; Containment Spray Actuation; 6.9 kV Power Supply Testing; Time i

' Response Testing; and Control Room HVAC. System engineer for switchyard and seismic monitoring.

Modification and Performance Engineer - Group leader responsible for development, preparation, review and conduct of electrical and I&C surveillance and design modification testing at 1150MW Westinghouse

PWR. Surveillance procedures included, but were not limited to, Diesel &

Blackout Sequence, Rx Trip /ESFAS Time Response, Integrated Safety Injection and Control Room HVAC. Special engineering assignments included containment leakage test director and program coordination, modification review and closcout SAR/SER Compliance Review, IE Bulletin 85-03 (Motor Operated Valves) response, technical specification ESFAS and Appendix "J" enhancements, station operating / administrative procedure review and preparation, security testing, system analysis and configuration / design basis follow for NSSS and balance of plant systems.

Section XI responsibilities for containment isolation valves, special pump performance tests (spray, RHR, service water), pressure testing and procurement document review.

Senior System Test Engineer - Responsible for start-up testing on NSSS and balance of plant systems at 1150 MW Westinghouse PWR. Test director for Integrated Leak Rate Test ILRT), Local Leak Rate Testing LLRT), Hot Functional Testing (HFT), Solid State Protection System Test and 1 E Bus Diesel Load Group Assignment (including ESF response timing). Prepared, conducted and reviewed preoperational tests, including ILRT, LLRT and IE Bus Diesel Load Group Assignment. NSSS-auxiliary sub-group leader for the following systems: spent fuel pool cooling / cleanup, service water, component cooling water, containment spray, safety cranes, leak rate testing, containment, fuel handling and vessel servicing equipment.

1977-82 General Electric / Knolls Atomic Power Labs. Schenectadv. New York Shift Supervisor - Senior supervisor in prototype plant responsible for conducting and supervising power plant operations and evaluations, including training and drills, testing, maintenance, repairs, outages and emergencies. Interfaced with engineering and craft support groups.

Reponed to the plant manager and supervised approximately 100 operators,

- engineers and trainees. Supervised major plant operations, including cold start-up, integrated plant hydrostatic r ad leak rate testing, nuclear

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instrument alignments / calibration, breaker-valve response timing, engineering safeguards testing and physics-thermal hydraulic testing.

4 Operations Engineer - Shift supervisor engineer responsible for assisting the shifi supervisor (duties described above) and acted as relief during his absence. Responsible for in-service inspections and audits, plant and station support systems, maintenance and outage coordination / follow-up, plant start-up testing and system design evaluation.

i Maintenance Engineer - Project engineer responsible for plant operation problems relating to maintenance and repair, outages, plant modifications, i

system design evaluation and scheduling. As materials engineer prepared and reviewed repair procedures, subcontracts, design evaluations and

! changes. Major design projects included, but were not limited to, site service water upgrade, radwaste management for zero discharge, work administration and reporting system, acid addition system restoration, engineering safeguards system evaluation, energy conservation modifications and steam dump restart. Prepared plant conditions aM test documents for plant outages and assisted with critical path analysis and planning.

Training / Operations Engineer - Qualified nuclear operations watch engineer O) with responsibilities for plant operations and training. Prepared and

({ conducted training sessions, hands-on training and seminars on mechanical, electrical, instrumentation and integrated plant operations / design. Assisted shift supervisor during plant start-ups, testing, outages and special training evolutions. Completed extensive theory and operations qualification program at top of class.

1973-77 United States Merchant Marine Academy Marine Officer - Engineering, maintenance and operations experience on oil-fired boiler and diesel power propulsion systems on merchant vessels.

EDUCATION: B.S., Marine Engineering / Minor Physics, United States Merchant Marine Academy,1977 KAPL Reactor Engineering School, General Electric,1977 Additional Courses:

Project Engineer Workshop, Gilbert / Commonwealth Development Center, Gilbert / Commonwealth Mastering Business Development, Gilbert / Commonwealth Microsoft Word, Gilbert / Commonwealth dBase III, Gilbert / Commonwealth Word Perfect, Gilbert / Commonwealth Excel, Gilbert / Commonwealth Lotus 1-2-3, Gilbert / Commonwealth DOS, Gilbert / Commonwealth

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V REGISTRATION: Professional Engineer - Texas (1986), Pennsylvania (1988)

Third Assistant Engineering License Steam and Diesel Vessels - USCG SOCIETIES: American Nuclear Society:

Technical Program Chair- Annual ANS Meeting,1995 Chairman - National Program Committee Vice Chairman - Committee for New Construction Vice Chairman - Power Division Executive Committee Member, Professional Engineering Exam Committee i Nuclear Information and Records Management Association Chairman, Vendor Manual Committee Member, Configuration Management Committee American Society of Mechanical Engineers, Member PUBLICATIONS: " Configuration Management - Design Baseline is the Key," American Nuclear Society Transactions, Winter Meeting,1989

" Materials Management and Spare Parts Issue Workshop," co-organizer, American Nuclear Society, Summer Meeting,1990

" License Renewal Topical," assistant technical program chairman, American Nuclear Society, Summer Meeting,1991

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"The Next Generation of Nuclear Power Plants: A Status Report,"

chairman, Designs Sessions, American Nuclear Society, Winter Meeting, 1991 "An Integrated Approach to License Renewal in the United States: An A/E's Perspective," PLEX 91 Conference Proceedings, Berlin, Germany Contributing Author, " Support of Design Basis Information Needs," TG14, NIRMA,1992 Contributing Author, " Position Paper for Implementing a Configuration Management Enhancement Program for a Nuclear Facility," NIRMA, j 1992 4

Co-Author, "The Early Site Permit Siting Guide: Criteria and Procedures for Selecting an ALWR Site," American Nuclear Society, Summer Meeting,1993

" License Renewal and Its Information Management Considerations,"

NiRMA Symposium,1993

" License Renewal at Wisconsin Electric, a Strategic Investment," PLEX 93 Conference Proceedings, Zurich, Switzerland

" Guideline for Implementing Vendor Information Programs," TG-18, Chairman, NIRMA,1994 I

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" Issue Requiring Assessment When Extending the Operating Life for an Existing Power Plant," Third Annual U.S/Eastem Europe /Former Soviet Union Electric Power Technologies Conference, Bucharest, Romania, April 1995

" Transactions 1995 Annual Meeting," Technical Program Chair, American

! Nuclear Society, June 25-29,1995 l

" Reactor Vessel Annealing Projects," GCTech Notes, August 1995

" Aging Management Guideline for Commercial Nuclear Power Plants -

' Tanks and Pools," SAND 96-0343, DOE /Sandia National Labs, February 1996 i

i AWARDS: Gulf Oil Trading Company Award - Marine Power Systems ANS - Outstanding Session Organizer: Next Generation ofNuclear Power i Plants ANS - Outstanding Session Organizer: Materials Management Workshop NIRMA - Cenificate of Scholarship - Significant Contributions &

4 Leadership O

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Project Support I

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Planner / Scheduler Over twenty-two years of diversified experience in planning and scheduling, structural, civil, and environmental disciplines involving computerized integrated schedules for nuclear power plants, industrial projects, pumping stati Proficient in the utilization of Pn,ons, treatment plants, and sewer and water distribution systems.

mavera, CUE, PREMIS and P-2 interactive project control software systems.

EXPERIENCE: PARSONS POWER (formerly Gilbert / Commonwealth) since 1973 1992 to Present South Carolina Electric & Gas Com

' Continuing Services Engineering Pnme pany, V.isC.

objective Summer controlling the Nuclear Station, budgeted hours and dollars associated with each authorized task and to ensure it is completed on or before schedule. Also, drafted the "All Inclusive Fixed Hourly Rate" pricing portion of the new Continuing Service Contract which became effective October 29,1993.

1992 to Present Project Control Manager - Nukleama Elektrarana KRSKO (NEK), Republic of Slovenia, KRSKO Nuclear Power Plant, Continuing Services 1 Engineering - Control budgeted hours, dollars and schedule within the

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terms and conditions set forth in the signed purchase orders and letters of  ;

intent.  !

l 1992 - 93 Project Control Manager - Portland General Electric Company, Trojan Nuclear Plant, Rainier, Oregon, Continuing Services Engineenng - Plant

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s closed in January 1993; four years premature, due to local citizens and environmentalist. However, a new security fence modification with lights l

and cameras was designed and installed under budget and ahead of schedule, along with other minor modifications.

1990 - 91 Project Control Manager - Pennsylvania Power & Light Company, Susquehanna Steam Electric Station (SSES), Units 1 & 2, In Lme Process Instrumentation Upgrade Project - Controlling the budgeted hours and dollars within schedule was accomplished by building a detailed, resource loaded, multi-disciplined and fully integrated CPM Schedule for 32 base scope work orders. Updated schedule weekly and produced detailed and I

summary level bar charts, schedule reports, histograms (man-hours, equivalent manpower, and cash flow), and deliverable curves. Responsible for performance measurement on a weekly basis which along with all the schedule data is utilized to define trends. Results published in biweekly reports.

1988-90 Project Control Manager, Eastman Kodak Company, Refrigeration Projects for Building 1 & 87, Brine Balance Tank Project, High Purity Water Facility (Building 61) Project, and the Dispersion Chimney Project -

Responsible for scoping the projects and generating two independent multi-disciplined critical path method (CPM) schedules. The sched ules were resource loaded anc! progress gathered weekly with performance measurement performed on a monthly basis. Results were published in monthly reports utilizing graphic charts and printouts, with a project p analysis.

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1984-88 Project Planner / Scheduler, Florida Power Corporation, Crystal River Nuclear Power Plant, Unit 3 - Responsible for generating mtegrated multi-disciplined critical path method (CPM) logic's, resource loading, gathering 3rogress, performance measurement, producing computerized graphics, data 3ase apphcations, and issuing monthly reports.

1982-83 Senior Planning and Scheduling Technician, Cleveland Electric 1

• Illuminating Company, Perry Nuclear Power Plant, Units 1 & 2 - Organized  ;

and controlled the piping engincedng schedule and the pipe s,upport data l base. Also responsible for training other technicians and engmeers in basic computerized data base applications.

1981-82 Senior Planning and Scheduling Technician - Korea Electric Company, Ko-Ri Nuclear Power Plant, Unit 2, Project Engineering Schedule - Functioned as the Acting Project Planning and Scheduling Engineer. Updated the schedule and generated reports.

1980-81 Lead Plannmg and Scheduling Technician - Metropolitan Edison Company, Three Mile Island Unit 2 - Worked on the initial entry schedule and prepared engineering and construction schedules for the evaporator / crystallizer facility. Also prepared the restart modification schedule for Unit 1.

l 1978-80 Planning and Scheduling Technician - Westinghouse Nuclear Projects:

5 Angra, KRSKO, and Ko-Ri 2 - In charge of engineerin technical assistance. Work involved updating ? regress, generati g CPM logic and integrated project schedule reports, p us supervision of other technicians.

1976-78 Structural Design Draftsman - Cleveland Electric Illuminating Compary, i

Perry Nuclear Power Plant, Units 1 & 2 - Prepared structural and detailed concrete l

design drawings. Other work included:

l Florida Power Corporation, Crystal River Nuclear Station, Unit 3 reactor dome South Carolina Electric & Gas Company, V.C. Summer Nuclear Power Plant final safety analysis report 1973-75 Environmental Draftsman - Worked on the Bushkill Lower Lehigh Sewer Projec,t preparing plans, profiles, and right-of-ways. Involved in layout and re-design of Three Mile Island Nuclear Power Plant Sewage Treatment Pint piping and the ? ping i and structural design drawings for equipment building at Three Mi e Island.

1971-73 Bureau of Water. City of Readine. Pennsylvania Engineering Aide - Lake Ontelaunee - Worked on the atlas distribution update, designed new water lines, interpolated field notes, and surveyed the watershed.

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<dr 1969-70 Wells Farno. Readine. Pennsylvania -

Installer - Installed burglar and fire detection equipment and alarms.

1967-69 U.S. Army Buck Sergeant - Attended teletype repair school. Served two years in Vietnam.

I EDUCA'110N: Business Administration Courses, Albright College,1982 and 1983 Additional Courses:

Water Treatment, Clemson University,1972 Reinforced Concrete Design, Gilbert / Commonwealth,1975 Structutal Steel Design, Gilbert / Commonwealth,1976 Basic Power Plant Systems, Gilbert / Commonwealth,1977 Business Writing Review, Gilbert / Commonwealth,1980 Principles ofMarketing, Reading Area Community College,1981 G/C CUE Training, Gilbert / Commonwealth,1982 Fundamentals of Planning and Scheduling, Gilbert / Commonwealth, 1983 Effective Listening, Gilbert / Commonwealth,1984 Time Management, Gilbert / Commonwealth,1984 STAR Training, Gilbert / Commonwealth,1985 Lotus 1-2-3, Gilbert / Commonwealth,1988 dBASE III, Gilbert / Commonwealth,1988 EXCEL, Gilbert / Commonwealth,1990 O[

Windows, Gilbert / Commonwealth,1992 SQL Server, Gilbert /Cormonwealth,1993 Intermediate SQL Server, Gilbert / Commonwealth,1993 ENCOMPASS, Gilbert / Commonwealth,1993 The Quality Advantage, Gilbert / Commonwealth,1993 GEN The Engineering Work Control Process,.

Gilbert / Commonwealth,1994 p

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m Supervisor- Library Services Twenty-three years experience in all phases of technical information center / library supervision and operations for consulting architect / engineering firm, electric utilities, and fossil and nuclear

generating facilities. Serves as liaison to public libraries and public information centers.

l l EXPERIENCE: PARSONS POWER (formerly Gilbert / Commonwealth) since 1980 l 1980 to Present Supervisor / Library Services - Responsible for business information 4

services / technical library including the organization and retrieval of more than 106,000 volumes of technical publications in the headquarters and satellite collections required to support the domestic and intemational power and industrial engineering business. The scope encompasses management, i business development, power plant design engineering for nuclear and fossil '

fuels, advanced technologies and construction management. Supervises staff to support the maintenance, ordering and document delivery services. l Managed maximum staff of ten, with budget accountability and space l allocation of 3,622 square feet. l The Library maintains full-text, directory and bibliographic access to perform literature / document searches from hundreds of online databases including U.S. Department of Defense DROLS, U.S. Department of Energy OSTI, Knight-Ridder DIALOG, EPRINET, DATATIMES, Dun &

Bradstreet's Dunsprint, STAT-USA, World News Connection , the U.S.

O NRC BRS system to access the NRC Public Document Room as well as INTERNET flat fee and CompuServe connections.

Other related capabilities include the classification and cataloging of publications, updating and maintenance of online network catalog, coordination ofindex CDROM disks for network installation and filing at new CDROM vendor and standards disks, publication routing and alerts, selection and order / expediting of documents, interlibrary loans, and photocopy requests. Performs client and employee orientation to business information sources and new technologies such as CDROM and INTERNET. Also, rnaintains direction of the preparation of training templates and services documentation.

Planned and designed floor plan for libraries with architect, supervised merger of e library collections, and coordinated library moves. Advises departments in review of retention or destruction of business documents.

Participant on Quality Action Team for satellite library for Oak Ridge, Tennessee office.

Supports management team with information support for proposal efforts to win contracts for consulting A/E firm. Served as Network Coordinator for Gilbert / Commonwealth (G/C) to access INPO's Nuclear Network.

f's d Mahtains status as U.S. DOE Contractor contact, for Library and Information Services as listed in the U.S. DOE Resource Directory of DOE l

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Information Organizations, from the Office of Scientific and Technical Information, U.S. DOE.

For U.S. DOD project, developed procedures for special library collection,

and supervised staff assigned to maintain Deep Base (MX Missile) project library. Met with U.S. Air Force, Army, and DARPA information officers to coordinate Company application for access to Defense Technical Information Services (DTIC) for technical document and status in the

Potential Contractor Program.

Co-authored script with producer and acted in production for client deliverable videotape on Library Services.

1973i0 Metronolitan Edison Comoany. Reading. Pennsvivania System Librarian - Established and maintained the System Library. Also trained and supervised library assistants; installed systems for control of library materials; organized centralized publications purchasing for the company; created and implemented library policy and procedures.

Responsible for reference, periodicals, interlibrary loan, cataloging, audio-visual, hard copy and microfilm materials, circulation, and collection development. Collaborated with libraries within the GPU System, j N including Pennsylvania Electric Company, Jersey Central Power & Light (V(

4 Company, GPU Service Corporation and GPU Nuclear. Planned layout and specified equipment for remodeled library facilities of 1,600 square feet.

Planned and administered library relocation. Performed DIALOG computer database literature searching, document retrieval and delivery.

Special Projects:

Interfaced with U.S. NRC Public Document Room superviser to audit the Three Mile Island NRC Public Document Room, Pennsylvania State Library, Harrisburg, Pennsylvania public documents sent by NRC to i TMIPDR.

Three Mile Island Nuclear Station - Established the Discovery Room in response to providing documents during the various investigations into

' cause of the TMI Accident, including design of space, preparation of operating procedures, and consultant to operation.

Established a reference collection for the TMI Observation Center.

Responded to requests from public libraries in Metropolitan Edism service territory to provide pro-nuclear hand-out literature for patrons.

Liaison to Reading Public Library for Edison Electric Institute (EEI)

Library Grant Program.

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J Managed McGraw-Hill half-pay and full-pay program, offering ter 'mical joumals at reduced rates to exempt employees. Coordinated insta .ation of custom executive central file system designed by management consultarits. Developed and maintained index system for Company Policy and Procedures Manual.

EDUCATION: B.S., Education / Minor Library Science, Millersville State College,1971 M.S., Science, Drexel University,1979 Additional Courses:

Library Science Graduate Study, Kutztown State College,1973-1974 Records Management, Villanova University,1984 Seminar: Library Interior Space Planning and Design,1985 Institute on Management of Libraries and Information Centers, ASIS &

, SLA Quality Advantage Training, Gilbert / Commonwealth Finance, Business & Statistics, SLA NASA / RECON Database Training, FEDWORLD Conference EPRINET Training, Me:ropolitan Edison Company Microsoft Word / Gilbert / Commonwealth Microsoft Access / Gilbert / Commonwealth INTERNET Satellite Workshops, State Library, Harrisburg,

/ Pennsylvania

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DIALOG Update, Knight Ridder IOLS'96 SOCIETIES: Special Libraries Association Philadelphia Chapter, Meeting Planning Committee Public Utilities Division, Membership Chairman With Winifred Sayers, GPU Service Corporation, SLA Annual Conference,

" Book Catalog for a Small Electric Utility Library" Edison Electric Institute, Library Task Force Berks County Library Association Library Automation Panel Disaster Recovery Committee U.S. DOE TIC Users Group AWARDS: G/C Cultural Values Award - Commitment, June 1995 O \

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Technical Editor

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i Over 24 years of experience in licensing and coordinating environmental permit acquisition j activities for nuclear and fossil-fueled power plant projects.

EXPERIENCE: PARSONS POWER (formerly Gilbert / Commonwealth) since 1977 1995 to Present Baltimore Gas & Electric, Calvert Cliffs Nuclear Power Plant - Provided environmental input to a Cooling Tower Study Update. The review j

included changes in the environmental requirements associated with the installation of cooling towers as a replacement to a once-through cooling water system.

Responsible for the review and identification of environmental, safety and health regulatory requirements applicable to the DOE /METC Facility.

These regulatory requirements will be used as the basis for a regulatory compliance and activities tracking database to be developed for the facility.

Department of the Navy, Philadelphia Naval Shipyard - Performed licensing tasks for the consolidation of operations at the shipyard. The following facilities being relocated and consolidated include: Asbestos Handling Facility, Hazardous Waste Handling Facility, the Carderock Test Facility Relocation, and Foundry renovations. The activity also includes the identification of environmental approvals and preparation of necessary permit applications.

Responsible for the preparations of construction permits for the Dartmouth College plant improvements projects, including the addition of a i

replacement boiler and a new emergency diesel generator.

! Provided input into the project permit schedule and identified permits,

' licenses and approvals that were required for the construction and operation of the York Cogeneration Project for Air Products and Chemicals, Inc.

Assisted in developing project permit and project construction interface logic diagrams.

t Responsible for the preparation of several RACT submittals for various utility and industrial clients, including Pennsylvania Electric Company, Metropolitan Edison Company, Pennsylvania Power Company, Gilberton Power Company, Solar Turbines Inc., and American Home Foods, Inc.

Submittals included technology feasibility and economic evaluation.

Department of Energy, Morgantown Energy Center - Provided the environmental design requirements for a Boiler Upgrade Conceptual Design Report; prepared an environmental parameters and regulatory issues sections for the Feasibility Study of Co-Firing Coal and Refuse Derived Fuel in a PFBC. Reviewed and identified regulatory requirements of possible future environmental requirements that may result from the Clean (d-) Air Act Amendments of 1990 that could affect a utility's decision on replacing, repowering, or retiring an existing plant. The study pertained to

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k the use of Clean Coal Technologies as the method of controlling or repowering the existing unit.

Panda-Brandywine - Reviewed and commented on the specification for a

continuous emission monitoring system serving a two combustion turbine, one steam turbine, combined cycle cogeneration facility for compliance with applicable federal and state monitoring requirements.

Provided completeness review for compliance with preparation of Title V Federal operating permit for a new refuse coal fired circulating fluidized bed combustor (Inter-Power of Pennsylvania, Colver Plant), an existing foundry (Lancaster Malleable Casting Company), and a food processor i

(American Home Foods).

Prepared an explanation of the air permit requirements and the information that would be needed to prepare the air permit application for a new/ replacement boiler at the University of Delaware.

1988 to 1995 Oak Ridge National Laboratory, Advanced Neutron Source (ANS)- ANS is

a state-of-the-art 300 MW research facility to be used to conduct research on neutron behavior, materials research, production of medical and

.O industrial isotopes and other projects. Prepared a Licensing and Permitting

',%) Plan, Permit List, Permit Schedule, man-hour projections for preparing

, ( permits and Permit Logic Diagrams for the permits identified.

j Responsible for the evaluation of regulatory applicability to a variety of utility, industrial and govemmental clients. Activities include investigating the regulations, summarizing the applicable requirements as they pertain to

the project, and identifying any fatal flaws in the activities. The summary usually includes information on the agency, the applicable regulations, the project activities affected by the regulation and the typical agency review time of a completed application.

Coordinated the preparation of federal and state permit applications for industrial and utility clients. Activities include cogeneration, industrial plant expansion studies, and permitting of add-on and compliance facilities.

Provided interface between design engineers, client and regulatory authorities. Duties included revision of design inputs and criteria documents for assuring proper application of Federal and State regulatory requirements; interpretation of regulations, state / national building codes, and consensus codes and standards.

Provided assistance to a variety of programs involved with marketing capabilities pertaming to compliance with the Clean Air Act Amendments of 1990. Also assisted in the preparation of engineering procedures used by the company.

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Martin Marietta, Oak Ridge National Laboratory - Reviewed and identified regulatory requirements and infermation needed to prepare air permit applications for the addition of a gas turbine and waste heat boiler (fired) as pan of a steam plant evaluation.

DOE, Lawrence Livermore National Laboratory - Reviewed project schedule for duration of Environmental Impact Statement issuance for Special Isotope Separation Project, including review of Federal Register for duration of similar projects.

1977 to 1988 Responsible for coordinating the preparation of federal and state permit applications for a variety of utility, industrial and governmental clients. The activities involved identifying, scheduling, coordinating and preparing all required permits and reports for plant construction and operation. Also, provided interface between design engineers, client and regulatory authorities.

In the area of nuclear licensing, responsible for overall coordination and preparation of federal and state permit applications, environmental report, assisted in the preparation of a Final Safety Analysis Report Update, coordinated the preparation of a report on emergency response facilities, C^ and reviewed Final Safety Analysis Report for commitments made by the utility. Details are as follows:

DOE, Hanford - Identified approvals needed for the High Level Radioactive Waste Vitrification Project.

Philadelphia Electric Company, Peach Bottom Atomic Power Station -

Coordinated the review of design and vendor drawings for discrepancies with computer listings in the nuclear records management system. Assisted as necessary to resolve the discrepancies.

Michigan Energy Resource Research Association - Assisted in the preparation of the proposals to DOE for two sites for the Superconducting Super Collider in Michigan, including environmental background information and regulatory requirements.

Toledo Edison Company, Davis Besse Nuclear Power Station - Coordinated the preparation of building permit and plumbing plan approval for the Low Level Radioactive Waste Storage Facility. Also coordinated the preparation of the building permit for the Training Simulator Facility.

Consumers Power Company, Big Rock Point Nuclear Plant - Reviewed design input for Post-Accident Monitoring Project.

i, Consumers Power Company, Midland Nuclear Plant - Responsible for h, identification, preparation, traceability, accuracy and retrievability of all t

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documents necessary to support a complete revision to Consumers Power Midland Nuclear Plant FSAR. Duties included review of utility commitments to NRC; development of a tracking procedure to ensure compliance; incorporation of commitment resolutions in FSAR; documentation of NRC questions and incorporation of responses; coordination and documentation of technical review comments by engineering disciplines and coordination between utility and construction for FSAR revisions. Reviewed overall document for compliance with Regulatory Guide 1.70. Reviewed the Design Input Manual for the Training Center and the Technical Support Center. Coordinated the preparation of the report on the Evaluation of Emergency Response Facilities.

Consumers Power, Palisades Nuclear Plant Documentation Conversion Project from FSAR to USAR Format - Duties included retrieval of historical documentation for a pre-1970 plant; traceability of documentation supporting significant design changes; reformatting drawings, diagrams, text and general contents; and developing a document traceability and retrieval system for tracking compliance commitments. Reviewed design input manual for TMI Shielding and Post-Accident Monitoring.

m Ohio Edison Company (1280 MW) Eric Nuclear Plants, Units 1 & 2 -

s Coordinated and prepared the Environmental Report, including responding

( to NRC comments on the ER and to requests for information regarding site selection.

Other responsibilities included managing the Licensing Information Center, the Company's source for up-to-date regulations, and design codes and standards; review and awareness oflegal, regulatory, and other engineering requirements necessary to obtain regulatory approvals, licenses or permits; and implement regulatory requirements and commitments made into operational terms in the facility design, construction and operation.

1972-77 Ohio Environmental Protection Anency. Bowline Green. Ohio Environmental Engineer - Responsible for coordinating air permit programs and supervising emission inventory system of the Northwest District Office.

Responsible for performing environmental inspections / audits for various industrial facilities located threughout Northwestem Ohio, including air, wastewater, and solid waste. Also responsible for review of air pollution, water pollution and solid waste disposal from industrial facilities.

Coordinated the preparation of state permit applications for Northem States Power Company's Tyrone Energy Park.

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EDUCATION: B.S., Mechanical Engineering, University of Toledo,1972 Additional Courses:

Air Pollution Control Technology, Control of Gaseous Emissions and Control of Particulate Emissions, Environmental Protection Agency, 1972-77 Supervisory Relationships, Contemporary Marketing, and Business Management, Jackson Community College,1979 Fundamentals of Dispersion Modeling and Computer Modeling Laboratory, Trinity Consultants Inc.,1990 Windows, Gilbert / Commonwealth computer training course,1994 Excel, Gilbert / Commonwealth computer training course,1994 REGISTRATION: Professional Engineer- Ohio (1976)

SOCIETIES: Air and Waste Management Association PUBLICATIONS: Co-author with T.L. Buchanan, N.J. Kuehn, O.S. Price, L.N. Rubow,

" Practical Approaches to NOx Control from Study Through Acceptance Testing and Operation," 1994 Co-author with R.E. Weinstein, " Fuel Cell Environmental Information: Fuel Cell Externality Considerations (Draft)," 1994 I

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