LD-88-053, Application for Amend to License SNM-1067,clarifying Enhanced Mgt Team Via Organizational Changes.Fee Paid
| ML20151U080 | |
| Person / Time | |
|---|---|
| Site: | 07001100 |
| Issue date: | 07/13/1988 |
| From: | Scherer A ABB COMBUSTION ENGINEERING NUCLEAR FUEL (FORMERLY |
| To: | Rouse L NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| Shared Package | |
| ML20151U083 | List: |
| References | |
| 24504, LD-88-053, LD-88-53, NUDOCS 8808180394 | |
| Download: ML20151U080 (46) | |
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Docket No. 70-1100 License No. SNM-1067 Mr. L. C. Rouse, Chief kf g$)l 0 5 &.
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[_y Fuel Cycle Safety Branch
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Division of Fuel Cycle, Medical,
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Academic and Commercial Use Safety BY ~f06 *
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' Ox Attn: Document Control Desk U.S. Nuclear Regulatory Commission L
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Washington, D.C.
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Subject:
License Amendment Request
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Dear Mr. Rouse:
Combustion Engineering recently informed the Nuclear Regulatory i
Commission of changes made to our Nuclear Fuel organization to strengthen i
our management team. These organizational changes have made it necessary to revise our Windsor Nuclear Fuel Mannfacturing Facility License Number SNM-1067. This letter, therefore, requests Nuclear P.egulatory Commission approval of a clarifying amendment as provided in the Enclosure.
Consistent with the existing license, this amendment includes both names and resumes of key personnel included in our enhanced management team.
A brief summary of the changes incorporated in the amendment are as follows:
Mr. F. M. Stern has been named to the new position of Vice President, Nuclear Fuel Manufacturing.
In tids capacity, Mr. Stern is responsible for all nuclear fuei manufacturing related activities for the Windsor Fuel Manufacturing Facility. Mr. Stern reporte to Dr. P. L. McGill who has overall responsibility for all Nuclear Fuel related activities.
Mr. A. E. Scherer is the Director of Nuclear Licensing for Nuclear Power Systems.
In addition to his other responsibilities, as a member of the Nuclear Fuel management team Mr. Scherer will be responsible for the C-E/NRC interface on matters concerning the Windsor license Of*)
8eO81GO394 G80713 i \\
PDR ADOCK 07001100 C
PDC Power Systems 1000 Prospect Kn Road (203) 688 1911 Combuston Engineenng, Inc.
Post Offce Box 500 Telex: 99297 Windsor, Connectcut 06095-0500
s Mr. L. C. Rouse LD-88-053 July 13, 1988 Page 2 of 3 and shipping container Certificatea of Compliance.
In this capacity, Mr. Scherer reports to, and acts on behalf of, Dr. McGill.
Mr. C. R. Waterman has been appointed to the position of Plant Manager for the W!ndsor Nuclear Fuel Manufacturing Facility.
He is
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responsible for the proper implementation of all day-to-day i
manufacturing activities.
Mr. Waterman reports to Mr. Stern.
Mr. P. R. Rosenthal has been appointed to the new position of Manager of Radiological and Industrial Safety.
He is responsible for all radiological protection, nuclear criticality safety, and industrial I
safety related activities for the Windsor and Hematite Nuclear Fuel Manufacturing and Product Development facilities. Mr. Rosenthal reports to Mr. Stern.
Mr. L. N. Grossman has been named to the new position of Director of Manufacturing Technology.
He is primarily responsible for plant upgrades for the Windsor and Hematite Nuclear Fuel Manufacturing l
and Product Development facilities. Mr. Grossman is also available I
for expert manufacturing advice at the Windsor fecility.
Mr. Grossman reports to Mr. Stern.
Mr. G. H. Chalder has been appointed to the new position of Senior Staff Consultant.
He will be providing expert advice on fuel facility operation to the Vice President, Nuclear Fuel Manufacturing and the Windsor Plant Manager. Mr. Chalder reports to Mr. Stern.
The position of Manager, Nuclear Licensing, Safety, Accountability, and Security of the Windsor Facility has been eliminated. Mr. R. E.
Sheeran, who formerly served in this position, has been named to the l
new position of Manager, Accountability and Security.
He will be responsible for the accountability and security issues related to all the special nuclear and source materials received by the Windsor Nuclear Fuel manufacturing and Product Development facilities.
Mr.
Sheeran remains available for consultation and support as part of the enhanced Nuclear Fuel manufacturing team. M:. Sheeran reports to Mr. Waterman.
The license amendment provided in the Enclosure represents the minimum changes required to clarify the enhanced management team put in place by the organizational changes discussed above. We recognize that the overall application presentation would be much improved by more extensive updating.
It is our intent to address such an improvement as part of the ongoing license renewal process.
The application fee for this amendment request is being transmitted under separate cover.
Three (3) copies of the Enclosure are included for your use.
s Mr. L. C. Rouse LD-88-053 July 13, 1988 Page 3 of 3 If I can be of further assistance in this matter, please do not hesitate to call me or Mr. C. M. Molnar of my staff at (203) 285-5205.
Very truly yours, COMBUSTION ENGINEERING, INC.
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A. E. 6herer Director Nuclear Licensing i
AES:ss Enclosure t As Stated cc:
G. II. Bidinger (NRC)
J. Roth (NRC-Region I) 4 d
Docket No. 70-1100 License No. SNM-1067 ENCLOSURE 1 COMBUSTION ENTL;EERING, INC.
WINDSOR FUEL MANUFACTURING FACILITY REQUEST FOR LICENSE AffiENDMENT LIST OF AFFECTED PAGES JULY, 1988 A
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Docket No. 70-1100 License SNM-2067 WINOSOR FUEL MANUFACTURING FACILITY i
I REQUEST FOR LICENSE AMENDMENT i
Combustion Engineering requests that the license (SNM-1067) for its Windsor Fuel Fabrication Facility be amended to reflect changes which have been made to the Nuclear Fuel Manufacturing organization. The license pages affected by this amendment and their respective revision numbers are listed below. The proposed change pages are provided in Enclosure 2.
I hietedP_aae Added M
,P_ag,e No.
Rev.
M No.
Rev.
l 1.2-2 01 1.2-2 04 I.2-2a 00 I.2-3 05 1.2-3 06
!.2-4 05 1,2-4 06 i
1.2-5 03 1.2-5 04 I.2-6 05 1.2-6 06 I.2-7 05 1,2-7 06 f
I.2-8 05 1,2-8 06 I.2-10 04 I.2-10 05 I.2-10a 00 I.2-15 03 I,2-15 04 1.2-16 05 1.2-16 06 I.2-18 06 I.2-16 07 1.2-19 05 1.2-19 06 I.2-20 04 1.2-20 05 i
1.2-21 03 1.2-21 04 1.2-24 01 I.2-24 02 1
1.3-1 05 I,3-1 06
Docket No. 70 1100 SNM-1067 Deleted Page Added Page P32e No.
Rev.
Page No.
Rev.
I.3-2 06 I.3-2 07
!.4-2 04 1.4-2 05 II.3-3a 01 II.3-3a 02 II.3-Sa 01 II.3-Sa 02 II.3-6 03 11.3-6 04 II.3-6a 00 II.3-6b 00 II.3-6c 00 II.3-6d 00 II.3-6e 00 II.3-6f 00 II.3-7 03 II.3-7 04 11.3-8 03 II.3-8 04 II.3-9 03 11.3-9 04 II.3-9b 01 II.3-9b 02
!!.3-9c 01 II.3-9c 02 11.3-10 03 I I. 3 04 11.3-11 03 11.3-11 04
!!.3-12 03 11.3-12 04
!!.3-32 03 II.3-32 04 II.3-33 03 II.3-33 04 t
Docket No. 70-1100 SNM-1067 ENCLOSURE 2 COMBUSTION ENGINEERING, INC.
WINDOSR FUEL FABRICAT!!!i (ACILITY REQUEST FOR LICENSE AMMENDMENT PROPOSED LICENSE APPLICATION PAGES
1 The Executive Vice President, Nuclear Power Systems is responsible for all activities carried out in the Nuclear Fower Systems Division.
He has delegated the responsibi'lity for all activities carried out under License SNM-1067 to the Vice President, Nuclear Fuel.
The Vice President, Nuclear Fuel Manufacturing is responsible through the Vice Presidant, Nuclear Fuel for all nuclear fuel manufacturing activitias.
He is assisted by a team which include the Senior Staff Consultaat, the Manager of Radiological and Industrial Safety, the Director of Manufacturing Technology, and the Windosr Plant Manager.
The Senior Staff Consultant advises 4h4 assists, as neesssary, the Vice President, Nuclear Fuel Manufacturing and the Plant Manager on matters regarding facility operation.
The Vice President, Nuclear Fuel Manufacturing has delegated programmatic responsibility for radiological, nuclear criticality, and industrial safety to the Manager of Radiological and Industrial Safety.
He is responsible for the surveillance of gli activities in which radioactivity is involved to ensure that th's health and safety standards set fu th in the license application are met.
He has the necessary authority to halt any operation which falls outside those limits, and he is responsible for indicating the necessary remedial action to bring the operation within acceptable limits.
The Vice President, Nuclear Fuel Manufacturing has delegated responsibility for plant upgrades to the Director of Manufacturing Technology.
License No. 3NM-1067, Docket 70-1100, Rev. 04 Date: 7/13/88 Page 1.2-2 1
2.2.1 Product Development The Director of Product Development is responsible tiirough the Vice President. Nuclear Fuel Manufacturing for the accountabili ty, f
i nuclear criticality safety, and radiological safety related to all
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Special Nuclear and Source Materials received and used in product l
development.
He assules.ompliance with federal and state i
regulations and the requirements and limitations set forth in the license.
In this position, the Director of Product Development assures that all operations involving nuclear materials have been analyzed to establish the required safety limits and controls.
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I License No. SNM-1067, Docket 70-1100, Rev. 0 Otte:
7/13/88 Page I. 2-2a
The basic organization structure is shown in Figure 2.2.1.
2.2.2 Nucleae Fuel Manufacturing The Plant Manager reports to the Vice President, Nuclear Fuel Manufacturing, and is responsible for the accountability, security, nuclear criticality safety and radiological safety related to all Special Nuclear and Source material received by Nuclear Fuel Manufacturing and used in any manufacturing process.
He assures compliance with federal and state regulations and the requirements and limitations set forth in the license during all phases of manufacturing.
In this position, the Plant Manager has delegated to the Production Manager and the Manufacturing Engineering Manager responsibility to assure that all operations involving nuclear materials have been analyzed to establish the required safety limits and controls.
The Manager or Radiological and Industrial Safety, or Nuclear Criticality Specialist shall assist the Manufacturing Engineering Manager and Production Manager by actually performing the analysis required and establishing the appropriate controls.
In addition, the Supervisor, Health Physics and Safety shall assure that the required safety limits and controls are being followed by the use of Litense No. SNM-1067, Docket 70-1100, Rev. 06 Date: 7/13/88 Page 1,2-3
daily internal audits.
The Health Physics and Safety Supervisor is responsible for the surveillance of all Nuclear Fuel Manufacturing activities in which radioactivity is involved to ensure that the health and safety, as well as criticality standards set forth in the license, are met.
He has the necessary authority to halt any operation which falls outside those limits, and is responsible for indicating what remedial action is necessary to bring the operation what remedial action is necessary to bring the operation within acceptable limits. However, if the operation is halted because of criticality safety considerations, the Health Physics & Safety Supervisor will contact the Manager of Radiological and Industrial Safety, the Nuclear Criticality Specialist, or the Nuclear Safety Committee whol shall determine necessary corrective actions to be taken.
The basic organizational structure for Nuclear Fuel Manufacturing is shown in igure 2.2.1.
2.2.3 Licensing Interface with the NRC The Director of Nuclear Licensing is responsible for the interface between Combustion Engineering, Inc. and the NRC as related to license SNM-1067. He also has the authority to make contiitments on behalf of Combustion Engineering, Inc. with regards to SNH-1067.
2.2.4 Independence of Safety Personnel The Director of Product Development reports tc the Vice President Nuclear Fuel. The Senior Staff Consultant, Plant Manager, the Manager of Radiological and Industrial Safety, and the Director, Manufacturing Technology all report to the Vice President, Nuclear Fuel Manufacturing.
The Manager of Accountability and Security, the Nuclear Criticality Specialist, the Engineering Manager, and the Production Maneger all report to the Plant Manager, Nuclear Fuel Manufacturing.
The Production Manager will enforce all safety related rules and procedures; he will interact as necessary to ensure uniform compliance.
License No. SNM-1067, Docket 70-1100, Rev. 06 Date:
7/13/88 Page !.2-4
Conflicts of interest are thus minimized and independence of safety personn61 is assured.
2.3 NUCLEAR SAFETY COMMITTEE A Nuclear Safety Committee comprised of engineers and scientists, representing all areas of the Nuclear Power Systems Division nuclear and scientific community, has been organized and assigned as one of its responsibilities the function of providing assurance to management that nuclear manufacturing ooerations are carried out in a safe manner.
The Committee acts in a staff capacity reporting to the Senior Vice President, Nuclear Power Systems.
The functions of the Committee are to:
Assure an independent review and approval of all Nuclear Criticality Safety aspects of process and equipment changes not covered by Tables 4.2.5 and 4.2.6 related to nuclear safety. A qualified person designated by the Chairman of the Committee performs the independent criticality safety reviews. The independent reviewer shall meet the minimum qualifications of a o
nuclear criticality sper.ialist.
Audit all manufacturing and Product Development operations o
involving SNM annually, with no more than 13 months between audits.
This audit must include as a minimum, a review of the nuclear criticality and radiological safety programs and their application and to assure that management policies are consistent with the License No. SNM-1067 Docket 70-1100, Rev. 04 Date:
7/13/88 Page 1,2-5
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objective cf maintaining occupational radiation exposures as low as i
reasonably achievable.
The Committee member who reviews the criticality safety program shall be a person other than the one who is authorized to perform the monthly criticality safety audit.
The committee member who reviews the Radiological Program shall be a person other than the one who is authorized to perform the ti.onthly l
Radiological Safety Audit.
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l The audit reports shall be sent to the Vice President, Nuclear Fuel l*
Manufacturing with copies to the Vice President, Nuclear Fuel, and the Executive Vice President Nuclear Power Systems and operational supervision.
Reviews and approves applications for SNM license renewals and i
amendments affecting nuclear criticality safety prior to submittal l
to NRC.
J 2.4 PERSONNEL SELECTION (APPROVAL AUTHORITY) FOR KEY POSITIONS
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2.4.1 product Development The Director of Product Development has approval authority for the l
following key positions: Manager-Core Material: Development and Manager-New Product Development.
l 2.4.2 Nuclear Fuel Manufacturing
.i The Plant Manager, Nuclear Fuel Manufacturing has approval authority for the following key positions:
Engineering Manager, production Manager, Production Superintendent, Manager of Accountability and Security, Nuclear Criticality Specialist, and Health Physics and Safety License No. SNM-1067, Docket 10-1100, Rev. 06 Date:
7/13/88 Page !.2 6
Supervisor.
2.4.3 Nuclear Safety Committee The Senior Vice President, Nuclear Power Systems has the approval authority for members of this committee.
2.5 EDUCATION AND EXPERIENCE REQUIREMENTS FOR ALL KEY SAFETY AND OPERATIONS PiRSONNEL 2.5.1 plant Manager Nuclear Fuel Manufacturing The qualifications for this position shall be a Bachelors Degree in one of the sciences or engineering.
In addition, at least three years supervisory experience is required as well as an understanding of nuclear criticality safety, health physics, and industrial safety aspects of fuel handling and knowledge of administrative controls imposed on nuclear fuel handling operations.
2.5.2 Manager of Accountability, and Security The minimum quslification for this position shall be a Bachelors Degree in one of the sciences or engineering or equivalent, and experience in positions which demonstrate sufficient judgement and analytical capability to establish and maintain technically sound accountability and security programs for the special and source nuclear materials delivered to the Windsor facility.
Lic.nse No. SNM-1067, Docket 70-1100, Rev. 06 Date:
7/13/88 page 1,2-7
2.5.3 Supervisor-Health physics and Safety The minimum qualifications for this position shall be a Bachelors Degree in one of the sciences or engineering, or sufficient experience in radiation protection positions which demonstrate good judgement and capability to establish and maintain an effective nuclear criticality and radiation safety program.
2.5.4 SECTION DELETED 2.5.5 Nuclear Criticality Specialist The minimum qualifications for this position shall be a Bachelors Degree in one of the sciences, engineering or equivalent and experience in outside-of-reactor nuclear criticality safety or nuclear fuel manufacturing facility criticality safety.
License No. SNM 1067, Docket 70-1100, Rev. 06 Date:
7/13/88 Page 1.2-8
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one of the sciences.
Committee members must not be directly 1
involved in the production or production development facilities J
utilizing the nuclear material.
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An individual must disqualify himself if there is a conflict of interest with the production or product development groups.
The Comittee member or the Consultant to the Comittee who performs the independent criticality safety review shall meet the minimum qualifications for a Nuclear Criticality Specialist and sht'l not be the person who is authorized to conduct the monthly criticality audit: and shall not be the initial I
reviewer.
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The Comittee member or the Consultant to the Comittee who f
performs the independent radiological safety review shall meet the minimum qualifications for the Manager of Radiological and
,lo Industrial Safety shall not be the person who is authorized to l
conduct the monthly radiological safety audit and shall not be i
the initial reviewer.
r 2.5.10 SECTION DELETED 2.5.11 HP Technicians
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The minimum qualifications 'or HP Technicians shall be a H.S.
Graduate (or equivalent) with a minimum of 1 y9ar experience in the
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Health Physics aspect of wcrking with Radioactive Materials, f
I 2.5.12 Manaaer of Radiolonical and Industrial Safety I
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The minimur qualification for this position shall be a Bachelors Degree in one of the sciences or engineering and experience in i
License No SNM-1067, Docket 70-1100, Rev. Da Date:
7/13/88 Page !.2-10
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I positions which demonstrace sufficient judgement and analytical capability to establish and maintain technically sourd radiation protection, safety and nuclear criticality program 3.
l 2.5.13 Director of Nuclear Licensing The minimum qualification for this position shall be a Bachelors Degree in one of the sciences or engineering and experience in l
positions which demonstrate sufficient judgement and capability to caordinate the Combustion Engineering, Inc licensing interface with the Nuclear Regulatory Commission for nuclear fuel manufacturing related activities.
2.5.14 Vice President. Nuclear Fuel Manufacturing i
l The minimum qualification for this position shall be a Bachelors t
Degree in one of the sciences or engineering and experience in positions which demonstrate sufficient judgement and capability to administer the operation of the Combustion Engineering, Inc. Nuclear i
Fuel Manufacturing and Product Development facilities.
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I License No. SNM-1067, Docket 70-1100, Rev. 0 Date:
7/13/88 Page !.2-10a
1 tv ::certain the effectiveness of the training.
2.7 OPERATING PROCEDURES 2.7.1 product Development Product Development, because of the nature of the work to be performed, does not utilize standard operating orocedures.
The use of Radiation Work Permits (RWp's) for all work with radioactive materials assures that appropriate saVety procedures are followed.
Written health and safety restrictions for all operations on radioactive materials shall be provided in the form of approved Radiation Work Permits or approved detailed procedures, and i
appropriate operational limits are posted in the vicinity of work i
I stations. The Menager of Radiological and Industrial Safety or the supervisor, Health Physics and Safety will approve RWP's based on the personnel doses which are irvolved with the work to be
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performed.
1 All RWP's shall be reviewed weekly by an individual having the minimum qualifications of the Supervisor-Health Physics and Safety.
Product Development has simple slab or mass limited areas.
The mass limited areas shall be separated by a minimum of 12 feet, making criticalit) safety an easily managed program.
Changes in criticality areas by Product Development personnel shall be formally described and submitted to the Manager of Radiological and i
Industrial Safety in writing for review and approval. He also determines whether the proposed chances in these areas can be approved j
License No. SNM-1067. Docket 70-1100. Rev. 04 Date: 7/13/88 Page !.2-15
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l internally or whether a license amendment is required. All approval documents and records of evaluations are maintained in sufficient i
detail to permit independent review of the analyses and that such records are maintained for at least six months after termination of the operation evaluated.
2.7.2 Nuclear Fuel _ Manufacturing l
It shall be the responsibility of the plant Manager (NFM) to assure f
that all operations involving radioactive materials have written procedures which include the appropriate safety requirements and are followed.
Written operating procedures are provided by the cognizant
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engineering supervisor for all operations, including equipment clean-up during enrichment changes.
These include all I
accountability, criticality and radiological safety restrictions, I
and limits, and must be approved by the Manager.of Radiological and f
Industrial Safety, the Nuclear Criticality Specialist, the Manager of Accountabilty and Security, or the Supervisor, Health Physics and Safety prior to the start of any operation. To assure all operating
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procedurss are maintained current and all superseded documents are j
removed from circulation, all procedures must be processed through the central document control system. This system also assures that I
appropriate approvals are on all procedures prior to issuance. All I
approved operating procedures shall be available in the related work
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area.
l Before the cognizant engineering supervisor may initiate I
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License No. SNM-1067 Docket 70-1100, Rev. 06 Date:
7/13/88 page !.2-16
l criticality safety which fall within the criteria of Section 4.2 l
providad that an independent review is performed by the Nuclear Safety Committee or persons designated by that Committee.
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The Manager of Radiological and Industrial Safety, the Manager of Accountability and Security, Nuclear Criticality Specialist or, the l
Supervisor Health Physics and Safety determine whether a change can be made within the framework of the license or whether an NRC amendment is equired for the proposed change.
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2.3 AUDITS I
All audits shall be performed in accordance with a written plan.
l 2.1.1 product Development Operations in Product Development will be forma 11 / audited as i
folle.s:
Once each working day by a Health Physics Technician for Health Physics Compliance and Critical,ity Compliance. He shall submit his findings in writing to the Manager of Radiological and Industrial Safety.
Operations will be audited on a monthly basis by an individual, who meets the minimum qualifications of the Manager of l
Radiological and Industrial Safety.
He will verify the l
adequacy of the Radiation Protection Program and that all l
designated limits and controls are being followed, i
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License No. SNM-1067 Docket 70-1100 Rev. 07 Date:
7/13/88 Page !.2 18
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i He will review records of radiation exposure, contamination
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1evels and airborne concentrations for trends and abnormalities.
His review will determine whether the t
appropriate corrective actions have been implemented to assure j
all exposures are maintained as low as reasonably achievable (ALARA). The findings of the monthly audits shall be documented and copies submitted to operational supervision, to the Vice President, Nuclear Fuel Manufacturing, the Vice President - Nuclear Fuel, and to the Executive Vice President -
I Nuclear Power Systems.
The reports shall include items from j
previous audits.
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Once each year by the Nuclear Safety Comittee, the committee l
will review all aspects of the criticality and Radiological i
Safety Programs and will transmit their report in writing to f
the Vice President - Nuclear Fuel with ccpies to the Vice i
President, Nuclear Fuel Manufacturing, the Executive Vice President, Nuclear Power Systems and Operational Supervision, f
e 2.8.2 Nuclear Fuel Manufacturino Coerations Operations at the Nuclear Fuel Manufacturing facility will be f
formally audited as follows:
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Once each working day by a Health Physics Technician for Health Physics compliance and criticality compliance.
He shall submit his findings in writing to the Supervisor Health Physics and Safety.
Once each month for radiological safety by an individual who meets the minimum qualifications of a Radiation i,
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License No. SNM-1047, Docket 70-1100 Rev, 06 Date:
7/13/84 Page 1.2-19 p
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r Specialist.
He shall audit for compliance with all regulations and j
operational procedures and shall assess the adequacy of the radiological safety program, His findings shall be documented and submitted to the Plant Manager - Nuclear Fuel Manufacturing.
Once e:ch month for nuclear criticality safety by an individual who meets the minimum qualifications of the Nuclear Criticality Specialist.
The Manager of Radiological and Industrial Safety or the Nuclear Criticality Specialist shall audit for compliance with all regulations N gerating procedures, and shall assess the adequacy of th- % Solished criticality safety program.
Audit findings shall La documented and repnrted to the Plant Manager - Nuclear Fuel Manufacturina.
Once each year by the Nuclear Safety Committee.
The 'comni u?
will review all aspects of the criticality and radiologicU safety programs and will transmit their report in writing to the Vice President - Nuclear Fuel with copies to the Executive Vice President, Nuclear Power Systems, Vice President, Nuclear Fuel Manufacturing, and operat.ioaal supervision.
Follow-up actions on audits of Product Development will be the responsibility of the Director, Product Development and for audits of the manufacturing facility, it will be the responsibility of the Plant Manager, Nuclear Fuel b nufacturing, All audits shall include a section for previously identified items requiring corrective action and the action taken to correct such items.
License No. SNM-1067, Docket 70-1100, Rev, 05 Date: 7/13/88 Page 1.2-20
2.9 INVESTIGATIONS AND REPORTING 0F 0FF-NORMAL OCCURRENCES Any unusual events that could lead to radiation health and safety problems shall be reported to the Plant Manager, Fuel Fabrication, O
the Manager of Radi logical and Industrial Safety, or to the o
Director, Product Development as appropriate.
The NRC shall be notified of such occurrences including any event that would significantly decrease the effectiveness of the Radiation or Nuclear Criticality Safety Program.
It is the intent of Combustion Engineering, Inc. to be in compliance with the reporting requirements of 10 CFR Part 21 for reporting of defects and noncompliance and 10 CFR 73.71 for events that significantly threaten or lessen the effectiveness of safeguards or for events that significantly threaten or lessen the effectiveness of Nuclear Criticality or Radiological Safety.
2.10 RECORDS Records relating to health and safety shall be retained indefinitely.
Such records shall include plant alterations or additions, abnormal, and off-normal occurrences and events associated with radioactivity releases, criticality analyses, audits and inspections, instrument calibration, ALARA findings, employee training and retraining, personnel exposuras, routine radiation surveys, and environmental surveys.
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l License No. SNM-1067, Docket 70-1100, Rev. 04 Date:
7/13/88 Page I.2-21 1
NUCLEAR POWER SYSTLMS DIVISION SENIOR VICE PRESIDENT NUCLEAR SAFETY COMMITTEE NUCLEAR FUEL CHAIRPERSON VICE PRESIDENT l
QUALITY CONTROL NUCLEAR LICENSING MANAGER DIRECTOR NUCLEAR FUEL FUEL ENGINEERING PRODUCT DEVELOPMENT NUCLEAR FUEL MANUFACTURING PRODUCTS t
VICE' PRESIDENT DIRECTOR DIRECTOR DIRECTOR RADIOLOGICAL AND NUCLEAR FL..
MANUFACTURING NUCLEAR FUEL INDUSTRIAL SAFETY MANUFACIURING TECHNOLOGY MANUFACTURING MANAGER PLANT MANAGER DIRECTOR SENIOR STAFF CONSULTANT i
NUCLEAR MANUFACTURING HEALTH PHYSICS PRODUCTION ACCOUNTABILITY CRITICALITY ENGINEERING AND SAFETY AND SECURITY SPECIALIST MANAGER SUPERVISOR MANAGER MANAGER l
l License No. SNM-1067 Docket 70-1100 Rev. 2 Date 7/13/88 Page I.2-24 L
3.0 RADIATION PROTECTION 3.1 ADMINISTRATIVE REQUIREMENTS 3.1.1 Radiation Work Permit Procedures Product Develooment All work with radioactive materials in the Product Development will require a radiation work permit (RWP). The Health Physics technician shall establish radiological requirements and set individual exposure limits which shall be approved in writing by the supervisor of Health Physics and Safety or the Manager of Radiological and Industrial Safety.
Nuclear Fuel Manufacturino All non-routine maintenance or repair operations on equipment in contaminated areas must be covered by a Radiation Work Permit (RWP),
including those non-routine maintenance cperations in which the ventilated containment is compromis,ed. The RWP shall be requested by the cognizant supervisor or engineer.
The RWP will be issued by o
the Supervisor of Health Physics and Safety or the Manager of o
Radiological and Industrial Safety.
It will include all safety requirements, protective clothing and equipment, and health physics monitoring requirements necessary to assure that the proposed operation is conducted in a safe manner.
RWP's shall be reviewed 0
for their need every 30 days as a minimum. The the Supervisor of 0
Health Physics and Safety or the Manager of Radiological and o
Industrial Safety must also close out on RWP's to assure that License No. SNM-1067, Docket 70-1100, Rev. 06 Date:
7/13/88 Page I.3-1 i
4 the work was completed in a satisfactory manner prior to restart of the relate'd operation.
Written operating procedures for the Health and Safety group are provided and followed in the manufacturing facility and in Product Development.
Any changes in or new operating procedures for the 0
Health Physics and Safety group are approved by the Manager of Radiological and Industrial Safety, the Nuclear Criticality Specialist, or the Plant Manager, Fuel Fabrication in the 0
manufacturing facility, and by the Manager of Radiological and 0
Industrial Safety or the Director, Product Development for those in Product Development.
3.1.2 ALARA Commitment C-E management is committed to maintaining radiation exposures to personnel as low as reasonably achievable (ALARA).
Product Development assures that the ALARA concept is met by the following:
A Radiation Work Permit {RWP) program that controls all operations involving the handling of radioactive material is utilized with approvals required at various exposure levels to assure all exposures are kept at ALARA.
An audit of Product Development with emphasis on the ALARA goals is performed annually by the Nuclear Safety Committee as stated in Section 2.8.1.
The major emphasis of this audit will be to review all changes implemented by management to achieve ALARA and to make recommendations to assure continued adherence to the ALARA concept.
Trends in radiation exposure, contamination levels, and airborne concentrations will be reviewed and recomendations made where necessary.
License No. $;.M-1067, Docket 70-1100, Rev. 07 Date:
7/13/88 Page 1.3-2
i 4.0 NUCLEAR CRITICALITY SAFETY and restricti~ns.
The adequate performance of individuals is o
i continually ascertained by the supervisor.
1 It shall be the responsibility of the supervisor to assure that each work station is properly posted, and that operations are performed in compliance with posted limits and written instructions.
4.1.3 Request for Changes and Criticality Analysis All proposed changes in process, equipment, and/or facilities that could affect nuclear criticality, radiological or industrial safety shall be approved in accordance with the requirements set forth in Section 2.2.2 of this part.
The necessary analysis and resultant safety limits shall be established by a person having the minimum qualifications of a Nuclear Criticality Specialist, procedures have been established for requesting changes and all request forms, approval forms, and associated documentation shall be maintained under the supervision of the Supervisor, Health Physics and Safety.
4.1.4 Posting of Limits All work stations and storage areas shall be posted with a nuclear safety limit approved by the Manager of Radiological and Industrial Safety or the Nuclear Criticality Specialist.
The Supervisor, Health Physics and Safety, maintains records of the review and approval of each posted safe nuclear criticality safety limit.
4.1.5 Internal Review Requiraments All process / equipment / facility changes which affect nuclear criticality safety shall be reviewed and approved in writing by the Nuclear Criticality Specialist.
An indepe,1 dent review shall be performed by an individual designated by the Nuclear Safety License No. SNM-1067, Docket 70-1100, Rev. 05 Date:
7/13/88 Page I.4-2
~lRUCLEAR POWER SYSTEMS DIVISION S.T. BREWER SENIOR VICE PRESIDENT NUCLEAR SAFETY COMMITTEE W.D. MAWHINNEY NUCLEAR FUEL CHAIRPERSON P.L. McGILL VICE PRESIDENT QUALITY CONTROL NUCLEAR LICENSING M. GLOTZER A.E. SCHERER MANAGER DIRECTOR NUCLEAR FUEL FUEL ENGINEERING PRODUCI DEVELOPMENT NUCLEAR FUEL MANUFACTURING J. PARRETTE R. DUNCAN PRODUCTS F.M. STERN W.C. COPPERSMITH VICE PRESIDENT DIRECTOR DIRECTOR DIRECTOR RADIOLOGICAL AND NUCLEAR FUEL MANUFACTURING NUCLEAR FUEL INDUSTRIAL SAFETY MANUFACTURING TECHNOLOGY MANUFACTURING P.R. ROSENTHAL C.R. WATERMAN L.N. GROSSMAN G.H. CHALDER MANAGER PLANT MANAGER DIRECTOR SENIOR STAFF CONSULTANT l
NUCLEAR MANUFACTURING HEALTH PHYSICS PRODUCTION ACCOUNTABILITY CRITICALITY ENGINEERING AND SAFETY G. KERSTEEN AND SECURITY M. ELMAGHRABI P. HUBERT J. VOLLARO R.E. SHEERAN SPECIALIST MANAGER SUPERVISOR MANAGER MANAGER License No. SNM-1067 Docket 70-1100 Rev. 2 Date 7/13/88 Page II.3-3a
RESUME WALTER D. MAWHINNIN Education:
Bachelor of Science in Mechanical Engineering, Tufts University,1956.
Master of Science in Mechanical Engineering, University of Connecticut,1964.
Master of Science, Executive Management Program, The Hartford Graduate Center,1981.
Summary:
Thirty years experience in nuclear power.
Duties have included engineering, quality, radiological controls, operations and project management.
Experience in the design and operations management of a Navy nuclear prototype reactor.
Chairman of the 1976 Nuclear Powers Systems task force to develop the Quality Assurance of Design Manual.
Currmt chairman of the Nuclear Safety Committee.
COMBUSTION ENGINEERING, INC.
1958 to Present Vice President, Nuclear Quality Systems 1988 to Present Responsibility to develop and implement the Nuclear Power Systems Quality Assurance Program to ensure that all products and services meet C-E, Regulatory and Customer requirements.
Director, Customer Services Department 1986 to 1988 1
Responsible for Customer Services management efforts associated i
with the sale of products and services for operating nuclear power l
plants, both of C-E and non-C-E manufacture and the followup necessary to ensure client satisfaction with those products and services.
Director, System 80 Projects 1979 to 1986 Responsible for directing all System 80 NSSS projects and l
representing C-E in client matters related to the contract, licensing, schedules, manufacturing and administrative support for project activities.
l I
i License No. SNM-1067 Docket 70-1100 Rev. 02 Date 7/13/88 Page II.3-Sa
W. D. MAWHINNEY RESUME Page
- Project Manager 1974 to 1979 Project Manager for C-E's contract with Louisiana Power & Light for the Waterford-3 unit.
Prior to that assignment he was Project Manager for the Gulf States Nuclear Project.
Assistant Project Manager 1970 to 1974 Assistant Project Manager for the C-E contract to Arkansas Power &
Light for the Arkansas Nuclear One Unit 2 project.
General Manager, Naval Reactors Division 1970 to 1971 General Manager for the S1C Naval Prototype located in Windsor, CT.
Was responsible for all aspects of site operation.
Operations Manager 1968 to 1970 Was responsible for the safe, overall operation of the reactor plant at S1C.
Training Manager 1967 to 1968 Responsible for all training programs associated with the operation of the Naval nuclear reactor.
Radiological Controls & Chemistry Manager 1966 to 1967 Responsible for radiological controls and reactor plant chemistry and for the training of civilian and Navy personnel in these subjects.
Assistant Operation Manager 1965 to 1966 Fluid-Mechanical Systems Engineering 1961 to 1965 Responsible for testing and developed the design changes for the improvement of the secondary systems.
Shift Supervisor 1960 to 1961 First as assistant and then shift supervisor, responsible as a qualified chief reactor operator for reactor operations and training naval personnel at the SIC prototype.
Engineer 1958 to 1960 Monitored the design, construction, and testing of radioactive waste disposal systems.
U. S. NAVY 1956 to 1958 Served as U.S. Navy Intelligence Watch Officer, '.ssigned to the National Security Agency.
License No. SNM-1067 Docket 70-1100 Rev 4 Date 7/13/88 Page 11.3-6
t July 1988 Fred M. Stern PROFESSIONAL EXPERIENCE:
COMBUSTION ENGINEERING, INC.,1956 TO PRESENT VICE PRESIDENT NUCLEAR FUEL MANUFACTURING,1988-PRESENT In this capacity, Mr. Stern is responsible for all nuclear fuel manufacturing related activities for the Windsor and Hematite fuel manufacturing facilities.
From 1987 to 1988 Mr. Stern was Vice President of Nuclear Quality Services.
In this position, Mr. Stern was responsible for developing and implement the Nuclear Power Systems Quality Assurance Program to ensure that all products and services meet C-E, Regulatory and Customer requirements.
From 1986 to 1987 Mr. Stern was Vice President of NSSS Projects. In this position, Le was responsible for project management and sale of Nuclear Steam Supply Systems for C-E.
From 1979 to 1986 Mr. Stern was Vice President of Nuclear Services.
In this position, Mr. Stern is responsible for the organization, planning and execution of C-E's domestic and international nuclear projects.
From 1975 to 1979 Mr. Stern was Vice Pcesident of Engineering and Development.
In this capacity Mr. Stern was responsible for C-E's nuclear nuclear steam supply systems and nuclear fuel.
From 1973 to 1975 Mr. Stern was first Director of Projects, then Vice President of Projects.
In these capacities he was responsible for C-E's nuclear stesm supply system projects including responsibility for licensing, 9tartup activities; nuclear training and nuclear drafting.
From 1967 to 1973 Mr. Stern was Manager of the Baltimore Project.
In this capacity he was responsible for the technical direction of the design, specification, and procurement of the nuclear steam supply system and reactor procurement of the nuclear steam system and reactor fuel for the Calvert Cliffs Plant being constructed in Baltimore.
He was responsible for all phases of design, construction, installation and operation with specific responsibility for seeing that time schedules and cost estimates were met.
From 1965 to 1967 Mr. Stern held several positions in the Heavy Water Organic Cooled Reactor Program - a joint effort undertaken by C-E atomic International on behalf of the E.S. Atomic Energy Commission.
License No. SNM-1067 Docket 70-1100 Rev. 00 Date 7/13/88 Page II.3-6a
From 1964 to 1965 Mr. Stern was Assistant to the Division Director of the Nuclear Division.
He assisted the Division Director in technical matters with particular emphasis on core design and evaluation problems.
From 1961 to 1964 Mr. Stern was Assistant Manager of the Utility Power Reactor Project where he participated in the design of large water cocied power reactor cores.
From 1959 to 1961 Mr. Stern was Group Supervisor of the Thermal Design Group.
From 1956 to 1959 Mr. Stern was Staff Engineer in the Navel Reactor Division where he contributed to the design and development of the SIC submarine prototype.
Education:
BSME, City College of New York,1956 g
MSME, Rensselaer Polytechnic Institute,1960 License No. SNM-1067 Docket 70-1100 Rev. 00 Date 7/13/88 Page II.3-6b i
l 1
PHILIP R. ROSENTHAL Manager Radiological and Industrial Safety
SUMMARY
OF QUALIFICATIONS Broad range of safety, licensing, and management experience.
o Experienced in occupational and environmental health physics e
programs for byproduct, source, and special nuclear materials.
Management experience in research and development programs o
involving radioactive materials.
Experienced in haalth & safety design and fabrication requirements o
for radioactive material and radiochemistry facilities.
Twenty-five years experience in the transportation of radioactive o
materials including spent fuel and highway route control quantities.
Experienced program manager for decontamination, decommissioning, o
and radioactive waste management programs.
EDUCATION BACHELOR OF SCIENCE, MECHANICAL ENGINEERING, 1959 UNIVERSITY OF MARYLAND, College Park, Ma'ryland ASSOCIATE OF SCIENCE, MATHEMATICS, 1956 BALTIMORE JUNIOR COLLEGE, Baltimore, Maryland GRADUATE STUDIES Drexel Institute of Technology, Nuclear Engineering, 1962-63 Philadelphia, Pennsylvania
'o EXPERIENCE i
COMBUSTION ENGINEERING, INC. - 1970 to Present Manager, RadioloRical and Industrial Safety - June 1988 to Present-l **
Responsible for the radiological protection, health physics, and industrial safety programs at Combustion Engineering's Windsor and Hematite Nuclear Fuel Manufacturing plants.
Ensuces that the necessary engineering and administrative controls are in place for radiological l **
protection, criticality safety, and industrial safety. Reviews and approves all proposed alterations, modifications, and additions to i.
facilities where the use of radioactive materials in involved.
i License No. SNM-1067 Dockei; 70-1100, Rev. 00 Date: 7/13/88 Page II.3-6c l
4 PHILIP R. ROSENTHAL Page 2 Manager, Radiological Protection Services - 1974 to June 1988 Respansible for all radiological protection and health physics activitie'.
for Combustion Engineer, Inc. Administers NRC licenses for byproduct, source, and special nuclear materials. Reviews and approves all proposed alterations, modifications, and additions tr. facilities where the use of radioactive material is involved.
Responsible for all C-E operations involving radioactive waste disposal, decommissioning, environmental control and the transportation of radioactive materials.
Responsible for providing health physics and radioactive material control services for all C-E field service activities.
Provides consultation services to utilities in-the area of radiological protection, waste disposal, and radioactive materials transportation.
Program manager for doce reduction development program.
Responsible for the financial control and technical direction of the program. This effort involved the development of a computerized dose tracking and evaluation system for power plant maintenance activities.
Coordinated the demonstration of the program during a refueling and maintenance oute,ge of a boiling water reactor plant.
Responsible for the design, construction, and licensing of a service center facility for contaminated and irradiated reactor tools, equipment and components.
Program manager for three decommissioning projects.
Responsible for the financial control and technical direction of each project.
The most recent project involved the decontamination and decommissioning of a uranium fuel fabrication facility to unco'nditional release criteria.
Supervisor of Mechanical Development - 1970 to 1974 Responsible for all activities relating to the mechanical development of pressurized water reactcr systems and. components. Supervised and directed the efforts of engineers and technicians in planning, execution, and evaluation programs for the development of reactor components such as fuel assemblies, Control Element Assemblies, Control Element Drive Mechanisms.
valves and seals. Responsible for the design, construction, and operation of test facilities used during the evaluation and development programs.
Provided test results, consultation and recommendatior. services to project organizations.
GENERAL DYNAMICS CORPORATION ELECTRIC BOAT DIVISION - 1964 to 1970 Senior Project Engineer Responsible for the desi p, procurement, test and evaluation of submersible sea water ]m p motor.
Also responsible for the usembly of a prototype submarine reeetor plant.
Prepared the installation procedures for the major reactor plant components and was responsible for the design of special handling equipment.
License No. SNM-1067, Docket 70-1100, Rev. 00 Date:
7/13/88 Page II.3-6d
s PHILIP R. ROSENTHAL Page 3 8
Refueling Diretor Responsible for the development of refueling procedures, tools and equipment to be used during the refueling of submarine reactors.
Supervised the refueling of six naval reactor plants.
UNITED STATES NAVY (Civilian Employee)
Mechanical Engineer - 1962 to 1964 Responsible for technical control and executive of the department's nuclear engineering research and development program.
Investigated reactor designs, fuel fabrication methods, reactor control schemes, radioactive waste systems, thermionic and thermoelectric concepts for application to existing requirements. Perforn,ed economic studies of steam and electric utility systems used by the Navy.
MARTIN-MARIETTA CORPORATION Reactor Systems Engineer - 1958 to 1962 Responsible for the design and fabrication of a radioactive waste disposal system for the processing of liquid radioactive waste.
Performed analysjs, procured components and prepared fabrication instructions for reactor components.
Provided engineering liaison with the manufacturing organization during the construction of portable nuclear power plants.
Responsible for evaluating changes inde to primary and secondary reactor systems in order to resolve fabrication and installation problems.
AFFILIATIONS o
American Nuclear Society Health Physics Society o
American Society for Testing and Materials o
- PATENTS, "Storage of Nuclear Incore Instrumentation" (Patent granted)
"Photographer's Diffuser Light" (Patent number 4,504,888)
"Disposal of Incore Instrument Detectors" (Patent pending)
License No. SNM-1067, Docket No. 70-1100, Rev. 00 Date:
7/13/88 Page II.3-6e
O L. N. Grossman M. S. Ceramic Engineering, University of California at Berkley (1960)
- 8. S. Physics, University of California at Berkley (1959)
PROFESSIONAL EXPERIENCE Combustion Enaineerina. Inc. Windsor. Connecticut. 1988 to the Present o
Dircector of Manufacturina Technoloav o
Responsible to the Vice President, Nuclear Fuel Manufacturing for o
overseeing all plant upgrades for the Nuclear Fuel Fuel Manufacturing and o
Product Developement facilities.
o General Electric Comoany. G-E Liahtina. Cleveland. Ohio. 1982 to 1988 0
Manaaer. Advanced Product Develooment.
o Responsible for management of a development center engaged in new product o
and automated process developement.
General Electric Comoany. G-E Nuclear Fuels Manufacturina. Wilminaton.
o North Carolinia. 1981 to 1982 Manaaer. Advanced Product Develooment.
Responsible for management of the automation of the manufacturing and o
quality assurance processes for nuclear fuel manufacturing.
o General Electric Company. G-E Nuclear Fuels Manufacturina. Wilminaton.
North Carolinia. 1981 to 19RZ_danaaer. Advanced Product Development.
o Responsible for management of the sixteen engineers and scientist 0
involved in the automation of the manufacturing and quality processes for o
nuclear fuel manufacturing.
O General Electric Comoans. G-E Nuclear Fuels Manufacturina. Vallecitos o
Nuclear Center. Pleasanton. California.1974 to 1981. Manager. Ceramic o
Develocment and Getter Manufacturina.
o Responsible for development of engineering ceramic materials for o
commercial and space-based nuclear reactors.
O Prior Positions: (General Electric, Pleasanton, California) o Technical Leader 1969 to 1970 0
Senior Research Ceramist 1965 to 1969 o
Metallurgist / Ceramist 1960 to 1965 l
l License No. SNM 1067 Docket 70-1100 Rev. 02 Date 7/13/88 Page II.3-6f
RESUME OP:
A. EDWARD SCHERER 11 Woodduck Farms Road Windsor, Connecticut 06095 EDUCATION:
MBA, Management, Hartford Graduate Center (Rensselaer Polytechnic Institute),1978 MS, Nuclear Engineering, Pennsylvania State University,1965 BS, Mechanical Engineering, Worcester Polytechnic Institute, 1963 EXPERIENCE:
1968 to COMBUSTION ENGINEERING, INC., NUCLEAR POWER SYSTEMS, Present WINDSOR, CONNECTICUT 1975 to Director, Nuclear Licensing - Has made Combustion Present Engineering the only vendor that has always received licenses on-time and never had one of its client's plants shut-down or de-rated by the United States Nuclear Regulatory Commission for any issue within its scope.
Responsibilities include directing all of the efforts required to obtain government regulatory permits, licenses and authorizations for nuclear products and services supplied by Combustion Engineering.
This includes responsibility for directing the preparation, approving the content, and coordinating the presentation of all licensing materials.
It includes representing Combustion Engineering before the Executive Branch, the United States Congress and membership on several senior industry Committees.
It also involves chairing the Combustion Engineering Regulatory Reform Task Force and co-chairing the Combustion Engineering /KWU Safety and Licensing Steering Committee.
From March of 1985 to September 1987, Engineering Quality Assurance was added to the above responsibilities.
In October 1987, nuclear fuel licensing for facilities in Windsor, Connecticut and Hematite, Missouri were added to the above responsibilities.
Served as Licensing Standards Supervisor from January to September 1975, and as Licensing Manager from September 1975 to February 1980.
1973 to 1975 Assistant Project Manager - Boston Edison Project - a 3473 MWt nucleac steam supply system (and fuel) being built for the Boston Edison Company.
Shared in the responsibility for managing the design, procurement and licensing of a i
unique system valued in excess of $50,000,000 to Combustion Engineering.
License No. SNM-1067 Docket 70-1100 Rev. 4 Date 7/13/88 Page II.3-7 l
i RESUME OF:
A. EDWARD SCHERER 1970 to 1973 Reactor Project Engineer (and Test Evaluction Engineer) -
had direct responsibility for coordinating the Mechanical / Thermal-Hydraulic / Nuclear design for the Fort Calhoun Nuclear Steam Supply System and fuel (1500 MWt).
In November 1972, relocated to the plant site to directly assist in final plant assembly and start-up.
At that time, assumed the site responsibility of Test Evaluation Engineer in addition to most previous duties.
While on site, also assumed Combustion Engineering shift coverage and "hands-on" responsibility during the plant functional testing, fuel loading, initial criticality, low power physics testing and power escalation.
1968 to 1970 Assistant to the Project Manager - Omaha Project - a 1500 MWt nuclear steam supply system, turbine generator and fuel being built for the Ouaha Public Power District.
Was one of three lead engineers guiding the design, procurement and licensing of a system valued in excess of
$30,000,000 to Combustion Engineering.
1965 to 1967 U. S. ARMY 1965 to 1967 Officer, Corps of Engineers - Completed training and was qualified by USAERC as a Nuclear Plant Engineer.
In addition, completed the Engineer Officer Basic Course and served as a Nuclear Plant Engineer, Combat Unit Commander, Communications Officer and 6-4 (Supply and Logistics)
Officer in control of an $8,000,000 construction facility.
Separated as a Captain.
TRAINING: Working Capital Management Program,1986 Combt stion Engineering Finance and Accounting Program,1986 Fitness For Duty Training Program, 1985 (1987)
Introduction to the IBM Personal Computer,1985 EAP Management Training Program,1984 Power Systems Group Leadership Seminar,1984 EEOC Training Program,1979 Management Development Program, Combustion Engineering -
Hartford Graduate Center,1978 Combustion Engineering NSSS Simulator Training Program,1976 Combustion Engineering Middle Management Training Program,1975 Reactor Safety Course, Massachusetts Institute of Technology, 1975 Seminar on Project Management, University of Massachusetts, 1974 NSSS Design Lecture Series (Instrumentation and Control),
Combustion Engineering,1970 Nuclear Plant Engineer Training Program and EBOC, U.S. Army, 1965-1966 ANL-AMU.Mvanced Reactor Lab Course,1964 AEC Reactor Operator's License Course, PSU Nuclear Reactor Facility, 1963-1964 License No. SNM-1067 Docket 70-1100 Rev. 4 Date 7/13/88 Page II.3-8
RESUME OF:
A. EDWARD SCHERER REGISTERED PROFESSIONAL ENGINEER:
Commonwealth of Massachusetts, Certificate #23566 PROFESSIONAL MEMBERSHIPS:
Atomic Industrial Forum American Nuclear Society American Society of Mechanical Engineers The Society of the Sigma Xi SAMPLE PUBLICATIONS:
A. E. Scherer/W. J. Lippold, "Nuclear Plant Life / License Extension:
Putting it all Together... Successfully", Atomic Industrial Forum's Reducing the Cost of Nuclear Power Conference (J996)
F. M. Stern /A. E. Scherer/J. B. Kingseed, "Backfit Implementation: The Five Year Schedule", International ANS/ ENS Topical Meeting on Thermal Reactor Safety (1986) and the 13th Inter-Ram Conference for the Electric Power Industry (1986)
A. E. Scherer/E, H. Kennedy, "Licensing and Regulations Procedures", Handbook of Energy Systems Engineering, John Wiley & Sons, Inc. (1985)
A. E. Scherer/J. M. Westhoven, "Licensing Strategies for the 1990's: Reducing Uncertainties", American Nuclear Society Annual Conference (1985)
A. E. Scherer/J. B. Kingseed, "Backfitting Implications of the Standard Review Plan", Atomic Industrial Forum Licensing Conference:
A New Look at Regulation - Getting the Process Under Control (1982)
A. E. Scherer, "Design and Licensing Standardization", Atomic Industrial Forum Workshop on Reactor Construction and Operation - Revitalizing the Industry (1981)
A. E. Scherer/J. Goldberg, "Reference Plant Licensing Experience", Proceedings of the American Power Conference.
Volume 40 (1978)
A. E. Scherer/D. E. Kilne, "Density - Dose Behavior of Irradiated Polytetrafluoroethylene ", Journal of Applied.
Polymer Science Volume 11, PP 341-355 (1967)
A. E. Scherer, "Thrust Washer and Wear Phte Inspection Device", Student Paper Winner, ASME Regichal Student Design Contest (1963)
License No. SNM-1067 Docket 70-1100 Rev 4 Date 7/13/88 Page II.3-9 1
4 G. H. Chalder B. S. Metallurgy, University of Durham, England (1951).
PROFESSIONAL EXPERIENCE U
Combustion Engineering, Inc. Windsor, Connecticut June,1988 to the Present O
Senior Staff Consultant Responsible to the Vice President, Nuclear Fuel Manufacturing for providing expert technical advise to the Vice President of Nuclear Fuel Manufacturing anri the Plant Manager.
Combustion Engineering. Inc., Windsor, Connecticut April 1986 to June 1983 Plant Manager, Windsor, Nuclear Fuel Manufacturing.
Responsible to the Vice-President, Nuclear Fuel for the operation on a plant producing nuclear fuel and control assemblies for use in commercial PWRs, including the functions of process engineering and development, production control, manufacturing, licensing, nuclear material accountability and security.
Combustion Engineering Canada, Moncton, N.B., Canada March 1984 to Marcti 1986 Manager, Nuclear Fuel On assignment to CE Canada Mr. Chalder was responsible to the Vice-President, Operations of CE Canada for all operations at the Moncton Nuclear Fuel Plant.
The plant is a self-contained facility dedicated to the manufacture and sale of fuel assemblies for use in CANDU nuclear power reactors and includes the design and process engineering, manufacturing, R & D and Quality Assurance functions associated with the product.
Combustion Engineering, Inc., Erlangen, West Germany 1982 to 1984 Manager CE/KWU Coordination As C-E's resident representative a Kraftwerk Union, Mr. Chalder was responsible for expediting the transfer of nuclear technology between the companies under the CE/KWu Technical Exchange Agreement.
Combustion Engineering, Inc., Windsor, Connecticut 1976 to 1982 PED Task Area IAanager, Materials and ServMes In this position Mr. Chalder had technical and budgetary responsibility for internally-funded R & D programs in the areas of nuclear materials and services including irradiation testing and inspection for the coordination of this work with corresponding programs at KWU under the joint CE/KWU Technical Agreement, l.icense No. SNM-1067 Docket 70-1100 Rev. 02 Date 7/13/d8 Page II.2-9b
During this period Mr. Chalder also acted as coordinator of outside-funded development, negotiations with customers, monitoring of technical progress and budgetary control.
Halden Reactor Pro!ect, Norway 1973 to 1976 Senior Scientific Advisor While attached by CE to the Halden Project during this period, Mr. Chalder provided technical consultation to the internationally-supported Halden Base Program o1 irradiation testing and performance analysis of water reactor fuels, besides supervising the proprietary fuel test program conducted by CE and Kraftwerk Union (KWU) of Germany at Halden as part of their joint technical agreement.
Combustion Engineering, Inc., Windsor, Connecticut 1970 to 1973 Section Manager, Fuels and Control Materials During this period, Mr. Chalder managed a group responsible for all phases of work in the Nuclear Laboratories on fuel and control materials for the CE PWR and LMFBR programs, including preparation of specifications, fabrication developr6ent of a variety of fuel materials and in-and out-reactor testing and evaluation of a range of fuel assembly designs.
U.K. Atomic Energy Authority Culcheth, England 1951 to 1955 Scientific Officer Mr. Chalder was involved in process metallurgy development of uranium and refractory metals for a variety of nuclear applications.
License No. SNM-1067 Docket 70-1100 Rev. 02 Date 7/13/88 Page II.3-9c
CHARLES R. WATERMAN B.S., Electrical Engineering, Tri-State College, 1957 Professional Experience:
Combustion Engineering, Inc., 1986 to Present Plant Manager. Nuclear Fuel Manufacturing Windsor 1988 to Present Responsible for day to day manufacturing operations, accountability.
security, nuclear criticality safety and radiological safety related to all special nuclear and source material received by Nuclear Fuel Manufacturing and used in any manufacturing process. Assures compliance with Federal and State regulations and the requirements and limitations set forth in facility license SNM-1067.
Director, Outage Services 1986-1988 Responsible for development test and application of maintenance and inspection services provided to nuclear utilities. These services included integrated refueling and maintenance outages, fuel services.
major plant retrofits, full steam generator services using advanced remote controlled devices designed and built by outage services.
Responsible for all aspects of compliance with facility by-products license with the NRC.
Responsible for the operation of Amdata, Inc., a wholly owned sub-sidiary of CE.
Amdata designs and manufactures advanced ultrasonic imaging equipment and inspection services for the Nuclear, Oil and Gas and Aerospace industries.
CE/Delas Weir, Inc. 1985 to 1986 President / General Manager As President / General Manager.'/Delas Weir, Inc., was responsible for the strategic direction of this joint venture company as well 7
as day to day operations. CE/Delas Weir provided new and replace-ment heat exchanger equipment to Electric Utilities.
Engineering Planning and Management Co. (EPM) 1984 to 1985 o
President and CEO As President and CEO of EPM was responsible for strategic direction and day to day operations.
EPM supplied engineering services to the Nuclear Utility Industry and Maintenance Management Software Programs to the Food and Pharmaceutical Industries.
License No. SNM-1067. Docket 70-1100 Rev. 4 Date 7/13/88 Page 11.3-10
Charles R. Watercan Psgs 2 Sensor Engineering Company 1981 to 1984
'cresident As President Sensor Engineering Company Division of Echlin Inc.,
was responsible for strategic direction and day to day operations.
Sensor Engineering is a high-tech manufacturing company of magnetic devices for use in security, automotive and industrial control systems.
Electro-Mechanics Inc.. 1977 to 1981
. President and Chairman of the Board l
As President and Chairman of the Board Electro-Mechanics was respon-sible for strategic direction and day to day operations. Electro-l Mechanics is a manufacturer of custom electronic control systems for the Electric Utility and Commercial Industries.
Combustion Engi eering. Inc., 1965 to 1977 3
a Director Plant Apparatus 1975 to 1977 As Director Plant Apparatus was responsible for an Engineering organization charged with technical specification and procurement of all NSSS mechanical hardware also established the organization and QA Manual for CE's Engineering "N" stamp.
Project Manager. Boston Edison Project. Nuclear Power Department 1972 to 1975 As Project Manager of the Boston Edison Project, principal duties were to represent Combustion Engineering with Boston Edison and all governmental agencies in matters relating to contracts, licensing.
design, fabrication schedules, erection, startup and acceptance of the nuclear steam supply system and associated fuel. Authorized all work to be done on the project. Reviewed, evaluated, and approved all technical work on the project, including purchase orders, purchase order supplements, drawings, and specifications.
Assistant Protect Manamer. Maine Yankee Proiect. Nuclear Power Department 1970 to 1972 As Assistant Project Manager for the Maine Yankee Project Mr.
Waterman assisted the Project Manager in the direction of the tech-nical and administrative activities involved in providing the nuclear steam supply system for the reactor plant being erected for the Maine Yankee Atomic Power Company in Wiscasset. Maine. His respon-sibilities included coordinating the efforts of the NPD and other CE departments involved in this project with the customer and the architect-engineer.
License No. SNM-1067. Docket 70-1100 Rev. 4 Date 7/13/88 Page II.3-11
Charles R. Waterman Page 3 Naval Reactors Divisiori. 1965 to 1970 From 1968 to 1970, Mr. Waterman was General Manager of the Naval Reactors Division and had overall responsibility for the operation of the SIC land-based submarine prototype facility under contract between CE and the U.S. Atomic Energy Commission.
From 1967 to 1968. Mr. Waterman was Operations Manager with respon-sibility for the safe, efficient operation and maintenance of the SIC prototype and support facilities.
He was responsible for the approval and implementation of schedules of operation for testing.
training, maintenance, and plant modifications. He also was respon-sible for the control and forecast of department budgets.
From 1965 to 1967. Mr. Waterman held the positions of Assistant Operations Manager and, subsequently, Training Manager with respon-sibility for the training of SIC prototype operating personnel in all phases of prototype operation which required the coordination and direction of both Naval and Division personnel.
Connecticut Yankee Atomic Power Company. 1964 to 1965 Nuclear Engineer Mr. Waterman was in training as Assistant Plant Superintendent for the Connecticut Yankee Atomic Power Plant at Haddam Neck.
i Combustion Engineering. Inc.
1959 to 1964 Senior Shift Supervisor Naval Reactors Division As Senior Shift Supervisor, Mr. Waterman.was responsible for the safe and efficient operation of the SIC prototype.
Prior to this, he served as electrical design engineer and was responsible for the evaluation of electrical and electronic systems and equipment l
associated with the operation and control of the SIC reactor plant.
Electric Boat Division. General Dynamics Corporation. 1959 Test Director Mr. Waterman was Test Director on the Nuclear Submarine USS (BN)
George Washington and was concerned with the direction and coordin-ation of preoperational and operational tests.
Cg ustion Engineering, Inc.
1957 to 1959 Electrical Control Engineer. Reactor DeveloDeent Division Mr. Waterman participated in the preparation of reactor power and temperature analysis and reactor protection analysis for the SIC /S2C reactor plants.
License tio. Sfd-1067, Docket 70-1100 Rev. 4 Date 7/13/88 Page II.3-12 I
~
e Robert E.
Sheeran Education:
B.S. Engineering - New York University t
M.S. Engineering - New York University Professional Experience:
19 88 - Present:
Manaaer - Accountability and Security Responsible for establishing and maintaining a security program to comply with NRC regulations.
maintaining an Accountability program to comply with NRCResponsible for estab regulations.
Supervise and direct Security and Accountability personnel in support of the Manufacturing operation.
Responsible for the preparation / implementation / maintenance of Security and Accountability manuals that define the manner in which the Security / Accountability programs are carried out.
19 83 - 1988:
Manacer - Nuclear Licensino. Safety, Accountability and Security Responsible for compliance with DOT, NRC, and OSHA regulations.
Responsible for all licensing submittals and management of the following programs:
Nuclear Criticality Compliance Health Physics Industrial Safety Accountability of SNM Security of SNM 19 g i -
19 83:
Suoervisor Health Physics, Accountability and Security Responsible for compliance with DOT, NRC, and OSRA regulations.
Responsible for all license submittals and the management of the following programs:
Health Physics Industrial Safety Security of SNM License No. SNM-1067. Docket 70-1100 Rev. 4 Date 7/13/88 Page II.3-3E
1979
,1981:
Special Proiects Supervisor; Supervisor Security Special projects supervisor:
Long range planning for equipment i
and facilities; proposal development for upgrading of existing facilities, building new facilities; preparation of capital appropriation requests for new equipment / facilities to meet projected production requirements.
Maintaining up to date awareness of federal / state / local requirements with regard te environmental impact of new equipment / facilities on Windsor /
Hematite sites.
Supervisor Security:
f: cree, prepare licensing submittals for NRC approvalssupervise facility security maintain procedure manuals.
prepare and Professional Affiliations Member of the Institute of Nuclear Materials Management (INMM)
License No. SNM-1067, Docket 70-1100 Rev. 04 Date 7/13/88 Page II.3-33
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7O'//OO C0flTROL fl0.
DATE OF 000.
DATE RCVD. 7 FCUF-POR FCAF LPDR la E REF.
suEcuARDS FCTC OTHER _
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