ML20138K196

Provides Requested Info Re Document Detailing Membership & Background of Plant Engineering Assurance Group Members. Update of Activities Discussed in Encl

ML20138K196
Person / Time
Site:	Dresden
Issue date:	12/06/1996
From:	Jamila Perry COMMONWEALTH EDISON CO.
To:	Beach A NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
Shared Package
ML20138K202	List: ML20138K196 ML20138K208
References
CAL-RIII-96-16, JSPLTR-#96-0230, JSPLTR-#96-230, NUDOCS 9702180050
Download: ML20138K196 (7)

Text

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, Commonwraith I dison Company Dresden Generating Station Mk 6500 North Dresden Road Morris II. 60 MO  !

ret ai s-942 2920

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a December 6,1996 fbi v !M

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JSPLTR #96-0230 SGA 1 DRS Of ,

Mr. A. Bill Beach .

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. Regional Administrator NRMA I Region III i

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U. S. Nuclear Regulatory Commission RLE_

801 Warrenville Road  !

i Lisle, IL 60532-4351

Reference:

1. NRC Confirmatory Action I euer RIII-96-016, A. Bill Beach to J. S. Perry, dated November 21,1996.

2. J. S. Perry to A. Bill Beach letter, dated November 8,1996.

Dear Mr. Beach:

,m Your Confirmatory Action Letter, RIII-96-016 (Reference 1), requested a document y

detailing the membership and background of Dresden Engineering Assurance Group i (V) (EAG) members, the charter of the EAG, responsibility, and EAG implementing  ;

procedures. This letter provides the requested information along with an update of activities discussed in our November 8,1996 letter (Reference 2).

A brief biography of the members is provided in Attachment 1. Attachment 2 provides the Charter of the EAG. Attachment 3 provides the procedure (Desk Top Instruction) governing the roles and responsibilities of the Dresden Engineering Assurance Group. These are initial versions of the EAG Charter and Procedure. The Charter and Procedure may be modified as EAG activities proceed and additional experience is gained. ,

We have completed revision to the Nuclear Engineering Procedures on control of calculations to provide clearer guidance, expectations, and direction on the review, control, and reconstitution / verification of calculations for equipment or portions of systems affected by new modifications. Training on these revisions (planned to be completed by December 2,1996) has also been completed for most of the affected eagineering personnel. However, because of end-of-year vacations and schedule conflicts, some personnel have not been trained. Measures have been established to j i ensure that engineers who have been trained are the reviewers of system modifications f j until all the training is complete. All affected engineers are expected to receive this  ;

O training by January 31,1997.

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9702180050 961206 PDR ADOCK 05000010 Q PDR A tinicom Company

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USNRC Page 2 L December 6,- 1996 i

l We will continue to advise you of our efforts to improve Dresden Station, both in

response to the Confirmatory Action Letter, and to advise you of additional 4

improvements as they occur.

I j If you have any questions concerning this issue please contact Mr. Frank Spangenberg, 4

Dresden Station Regulatory Assurance Manager, at (815) 942-2920, ext. 3800.

j' Sincerely, i

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l J. Steph n Perry i Site Vice President i

Dresden Station 4

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Mr. Samuel J. Collins

? Mr. John F. Stang.

Mr. Clark L. Vanderniet U.S. NRC Document Control Desk

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i Illinois Department of Nuclear Safety 4

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ATTACHMENT 1 BIOGRAPHY OF TEAM MEMBERS R

The members of the Dresden Engineering Assurance Group Are:

Kenneth W. Frehafer Mr. Frehafer has over 16 years experience in the nuclear power industry. After graduating from the University of Wisconsin, Madison with a B.S. EE degree, he started his career with Newport News Shipbuilding as a Shift Test Engineer in both submarines and carriers. In 1990, he started work in the commercial power industry with Florida >

Power and Light, Turkey Point Station, in the Site Engineering department. As the Site Design Bases

! Engineering group lead, he developed, reviewed and approved 10 CFR 50.59 Safety F. valuations, operability assessments, design changes, and coordinated INPO and NRC correspondence.

He is now working for Commonwealth Edison at Dresden Station l

as the Engineering Assurance Group lead.

l l Kirk W. Peterman

) Mr. Peterman has over 20 years experience in the nuclear i

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\, power industry. He graduated from the University of Missouri-Columbia with a B.S. degree in Physics in 1973. He j

also holds M.S. degrees in Nuclear Physics (1974) and i

Nuclear Engineering (1978). He joined Comed in 1977 after 1 i

completing a two year' tour with the United States Peace i Corps. His duties included supervising the Nuclear Fuel Services Plant Support Group, the Nuclear Station Regulatory

! Assurance Group, and Dresden Station Outage Manager. He is currently the Project Control Supervisor for the Dresden Design Engineering organization. l I

Carlos de la Hoz Mr. de la Hoz has over 13 years experience in the nuclear power industry. He received a Bachelor of Science Degree in Nuclear Engineering from Purdue University in 1983. Since I l graduating from Purdue University, he has been employed at Comed Dresden Nuclear Power Station. His duties included  ;

Lead Nuclear Engineer, which supported Operations to ensure l safe operations of the reactor core in accordance with l

, Technical Specifications, UFSAR and the applicable reload

analyses. He received his SRO License in 1993, and is now in s

s the Dresden Plant Engineering Group as the Station Reactor Engineer. In addition, Carlos is assigned to the 50.59 2

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s Expert Panel. j l

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,, Richard H. Johnson I \

(' '/ Mr. Johnson graduated from the University of Illinois, earning a B.S. degree in Engineering Physics and M.S. and Ph.D. degrees in Nuclear Engineering. He was an Assistant Professor at Purdue University from 1975 through 1981 and worked on fast breeder reactor research projects at Purdue and Argonne. In 1981, he joined the Comed Production Training Department where he helped develop reactor operator training programs for Byron, Braidwood, and LaSalle County Stations. In 1986, he transferred to Dresden Station as a fire protection System Engineer. As a Group Leader in the Technical Staff from 1987 through 1991, he implemented thermal and safety system performance monitoring and commercial grade parts dedication programs; he also had responsibility for many other programs, including in-service testing, temporary rigging, NPRDS, environmental qualification, and replacement parts classification. In 1991, he transferred to the Dresden Regulatory Assurance Department and participated in operating experience reviews and root cause investigations. Mr. Johnson has served as a Probabilistic Risk Assessment Analyst since 1993, first in the corporate engineering staff and currently in the Dresden Plant Elgineering Staff.

Hugh D. Campbell n

( ) Mr. Campbell has over twenty eight years in Nuclear Power l

\~ / and Engineering. His formal education includes B.S, M.S., I and Ph.D. in physics from the University of British l Columbia. He began his career as a faculty member of the Nuclear Engineering Sciences Department at University of Florida. He taught courses and conducted research in Thermodynamics, Reactor Analysis, Plasma Physics, and Thermonuclear Fusion. He conducted training for Shift Technical Advisor program at Crystal River Nuclear Station. .

After retiring from the university in 1982, he has worked in l Nuclear Industry in several different areas, including Plant Startup, PRA/IPE, and various mechanical and heat transfer projects for Comed. As a member of the Expert Panel, he assisted Maine Yankee during their NRC Independent Safety Assessment, and Dresden during their Independent Safety Inspection. (Mr. Campbell is currently fulfilling a previously committed offsite assignment. He will be returning to Dresden Station in early January, 1997) l

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Joseph R. Basak l Mr. Basak has over twenty-four years of power industry  ?

, experience, specializing in Instrumentation and Process  ;

4 Control'with a strong mechanical process background. His I experience includes preoperational and startup testing of .

1 Reactor Protection and Engineered Safety Features at Duane  !

2 Arnold, WNP-2, Palo Verde, and Braidwood. He has been i actively involved in instrumentation setpoint/ error analysis  !

program development and implementation, instrument j performance trending, control system upgrades, and station  :

j engineering / maintenance support. In 1994, he participated l

, in the Perry SBICI Self-Assessment as a technical  ;

consultant. He has been project manager / engineer on various )

! plant design changes in support of Comed, WEPCo, CEI, NPPD, j i CPCo, PSE&G, and Entergy. He began his career with General j i Electric.  ;

I l Charles E. Beck, P.E.

l Mr. Beck has over twenty one years of experience in nuclear plant design, maintenance, operation, and systems

) engineering. His formal education includes a B.S. EE degree from the University of Notre Dame in 1975 and a M.S. EE from 1 the Illinois Institute of Technology (IIT) in 1989, and he is currently a Ph.D. candidate at IIT. He has worked with j- Comed's Dresden Station for most of the past twelve years, O5 both as a Comed Design Engineer and in a consulting role.

His projects have included plant modifications, design calculations, system reviews, detailed circuit reviews, root cause investigations, Licensee Event Reports, operability assessments, and 10CFR50.59 Safety Evaluations He has written test plans, conducted laboratory tests, and written test reports on safety-related components, and has written  !

complete training programs. He is a Licensed Professional  !

Engineer in IL, MA, MI, MN, and WI, a Senior Member of the l IEEE, and a Member of the ANS. He has published over twenty l technical papers in IEEE Transactions and various conference ,

proceedings. He is a nine year veteran of the US Navy i Nuclear Power Program, supervising up to 130 operators and i technicians in the Electrical and Reactor Control i Departments. Currently, he is the Director of Nuclear l Operations for Kiran Consultants, Incorporated, a small, l minority-owned consulting firm.

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i ATTACHMENT 2 N- Y Dresden Engineering Assurance Group Charter .

November 18, 1996

Purpose:

The Dresden Engineering Assurance Group (DEAG) was formed as a result of commitments made to the NRC during the NRC ISI inspection (reference 1). The purpose of the DEAG is to ensure that engineering activities validate, maintain, and if necessary, reconstitute the Station's design bases.

Scope:

The DEAG will provide oversight of the following key engineering activities for Units 2 and 3:

1. Design change activities (DCPs, ECNs, Exempt Changes, Temp Alts, Setpoint Changes, DCRs).

l 2. Operability evaluations.

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( ) 3. 10 CFR 50.59 Safety Evaluations.

4. Engineering evaluations performed at the request of the Station (Doc ids).

l 5. Calculations.

6. vIrveillance trending to identify potentially degraded equipment.

7 Special Test Procedures.

8. Performance Improvement Report (PIR) process as it relates to the identification of potential operability issues.

9. Licensee Event Reports (LER's).

l 10. Other activities as requested by the Site Engineering Manager.

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~ Policy:

(~~) 1. The DEAa shall provide oversight of the engineering activities outlined above by performing select real time design basis reviews. Review activities will be weighted toward issues relating to the most risk significant systems. Oversight activities performed shall:

a. Verify that design inputs and assumptions are validated, or if necessary, verify that the design basis is reconstituted. The use of historical design inputs and analyses shall be verified to be l validated or reconstituted. l 1

b. Verify that the activity is envelop 3d by the l Station's licensing and design bases (such as the ,

UFSAR, SERs, and DBDs). {

c. Activities will be reviewed for potential l operability questions. Any potential operability j concerns will be resolved in accordance with Station procsdures. l

2. The DEAG will initially perform review / oversight activities in conjunction with existing engineering procedures. Station procedures will be revised to

/~'s formally incorporate DEAG involvement within ;he scope of

( ) pertinent engineering activities.

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3. A desktop procedure will be developed to assist oversight j activities. Periodic reports of DEAG effectiveness will l be transmitted to the Site Engineering Manager and his l direct reports. 1

4. The DEAG is an engineering resource that should be used during a31 phases of preparation and review of I engineering products.

5. The DEAG will continue performing these functions until normal engineering activities have improved to the point where these reviews are no longer necessary.

References:

1. Comed letter from J. Stephen Perry to A. Bill Beach dated November 8, 1996.

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