ML20141H771
| ML20141H771 | |
| Person / Time | |
|---|---|
| Site: | University of Lowell |
| Issue date: | 05/16/1997 |
| From: | Bettenhausen L MASSACHUSETTS, UNIV. OF, LOWELL, MA (FORMERLY LOWELL |
| To: | Michaels T NRC (Affiliation Not Assigned) |
| References | |
| NUDOCS 9705270117 | |
| Download: ML20141H771 (29) | |
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l l UNIVERSITY OF MASSACHUSETTS LOWELL ONE UNIVERSITY AVENUE ,
L LOWELL, M A 01854-2881 i
May 16,1997 l i l Theodore S. Michaels, Senior Project Manager PDND/DRPM/NRR Mail Stop llB20 U.S. Nuclear Regulatory Commission' Washington, DC 20555-0001 Docket No. 50-223 License No. R-125 l
Dear Mr. Michaels,
l This responds to your request for information dated January 24,1997 regarding HEU to LEU conversion of the University of Massachusetts Lowell
- Research Reactor (UMLRR).
l The information requested is attached. A general description of the conversion following the format of Appendix 18.1 to NUREG 1537, Guidelines for Preparing and Reviewing Applications for the Licensing of Non-Power Reactors,is included to place the information in context, and to provide references to material previously submitted regarding the HEU to i
- LEU conversion of UMLRR.
Should you have questions regarding the details of this submittal, refer +
them to Dr. Gunter Kegel, Director of the Radiation Laboratory, at (508)934-3280 or Lee Bettenhausen, Reactor Supervisor, at (508)934-3365. .
f l $, YY be H[BeTtenhausen Reactor Supervisor
Enclosures:
As stated f{b0 l cc w/ enclosures: See next page i
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I 9705270117 970516 DR ADOCK 050002 3 ,
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U.S. Nuclear Regulatory Commission Docket No. 50-223 CC: I l
- Mayor of Lowell City Hall-Lowell, Massachusetts 08152 -
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- Office of Attorney General Environmental Protection Division :
19th Floor l One Ashburton Place :
Boston, M A 02108 :
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REACTOR SAFETY SUBCOMMITTEE MEMBERS
- University of Massachusetts Lowell 3
John White :
Warren Church l Mary Montesalvo '
George Chabot Gunter Kegel .
Lee Bettenhausen Kanti Prasad !
P David R. Medich i
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CONVERSION FROM HEU FUEL TO LEU FUEL UNIVERSITY OF M ASSACHUSETTS LOWELL RESEARCH REACTOR
- 1. GENERAL DESCRIPTION OF THE CONVERSION 1.1 Introduction The University of Massachusetts Lowell Research Reactor (UMLRR)is one of the last MTR plate-type research reactors to convert from Highly-Enriched Uranium (HEU) fuel to Low-Enriched Uranium (LEU) fuel. Thus, most of the topics suggested for the content of a conversion safety analysis report have already been addressed. See, for example, Reference 0 Major points will be restated with references to the documents which contain details. The conversion for UMLRR is an exchange of LEU fuel elements and some specific core components for the HEU fuel originally supplied in 1971 and in use since then without addition or change. The major changes for the conversion are summarized in the table which follows. A more detailed summary of reactor data can be found in Reference.1 descriotion HEU fuelled core LEU fuelled core fuel U-93% enriched U- 19.75% enriched fuel elements 26-30 20-24 fuel plates per element 18 16 U-235 per element 135 gm 200 gm central flux trap none one-graphite / water trap element location of regulating core position D-8 core position D-9 rod 1.2 Summary and Conclusions of Safety Considerations Detailed analyses and comparisons of HEU and LEU cores can be found in a prior submittall Major results are briefly included here.
O USNRC NUREG-1313. " Safety Evaluation Report Related to the Evaluation of Low-Enriched Uranium Silicide- Aluminum Dispersion Fuel for Use in Non-Power Re actor s",19 8 8.
I FSAR Supplett ent for Conversion to Low Enrichment Fuel for the University af Massachusetts Lowell (UML) Reactor, UML Staff, May 1993
CONVERSION FROM HEU FUEL TO LEU FUEL UNIVERSITY OF M ASSACHUSETTS LOWELL RESEARCH REACTOR LIMITING PO'WER FOR NATURAL CONVECTION Water Above LEU Fuel HEU Fuel Current TS Cors.
24ft 335 kw 429 kw 125 kw 2.0 ft 1.33 kw 1.25 kw FORCED FLOW -FIG 3.1 of Ref 1 (enclosed) shows the combinations of power and flow for onset of nucleate boiling (ONB).
Operation at 1600 gpm flow (1300 gpm scram setpoint) provides ample l
margin to ONB at Mw licensed thermal power.
BURNOUT RATIO- Figures 3.3 and 3.4 of Reff (also enclosed) show a minimum critical heat flux to ONB ratio of 19.5 at 1 MW operation for LEU Fuel with Hot Channel Factor. This occurs at an ONB flow rate of 343 gal / min, well below the scram setpoint of 1300 gal / min.
CONSEQUENCES OF FISSION PRODUCT RELEASE The accident considered for radiological consequences is the same one analyzed in the Updated Final Safety Analysis Report 2, release of fission products from a single fuel plate after long term operation and fission !
product buildup. The differences between the analysis of Iand 2 are due I to the release t ate calculation for iodine and the use of a highly '
conservative (Pasquill Type F stability, ground level release) dispersion model to calculate doses at the site boundary,48 meters, for the HEU-to-LEU conversion safety analysis. This compares to calculation of accident doces in containment from a slower iodine release modelin Reference 2, l
Exoosure to: Duration UFS AR CH. 9 SFS AR CH. 9 (in containment) (at 48 meters) thyroid 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> 8.4 Rem 1.12 Rem infinite 751.4 Rem 52.2 Rem whole body 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> 5.33 Rem 0.61 Rem 720 hour0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> 29.4 Rem 1.67 Rem
CORE FLOW RATE VER3US POWER -
CORE FLOW RATE BELOW ONB 2700 .
7 2400- +-
-r Z 2100- ~
- ff-1800- L -r --
1500- -
J' h 3200 e
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0 1 2 3 '4 5 6 POWER (MW)
HEU with HCFs -*- LEU w/o HCFs -El- LEU with HCFs Figure 3.1 Core Flow versus Power for the HEU and LEU Cores with and without HCFs
Burnout Ratio Versus Flow Rate HEU w/o HCFs 55 ig.w.l l
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x 50 b 45 5 \l y 40 m 35 2
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Burnout Ratio Versus Flow Rate I HEU with HCFs 45 g 40 r-! l l C
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Figure 3.3 Burnout Ratio versus Core Flow for HEU Core With and Without HCFs
Burnout Ratio Versus Flow Rate t (EU w/o HCFs 45
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Total Core Flow Rate (Gal / Min) !
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4 I Burnout Ratio Versus Flow Rate LEU with HCFs 35 lo8
- I g;. 30 !
$ 25 \ g E,' 20 A-hi O '
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0 300 .
600 900 1200 1500 1800 2100 2400 2700 Total Core Flow Rate (Gal / Mini Figure 3.4 Burnout Ratio versus Core Flow for LEU Core With and Without HCFs
CONVERSION FROM HEU FUEL TO LEU FUEL -
UNIVERSITY OF MASS ACHUSETTS LOWELL RESEARCH REACTOR l.3 Summary of Reactor Facility Changes Only one physical change to the reactor facility is necessary to convert to LEU fuel. The core location of the regulating rod needs to be changed because of the smaller LEU core configuration. The regulating rod is to be moved one core position,3 inches. All other physical aspects of the core grid, core support, instrumentation, cooling system, and other physical ;
facility features will remain the same. ^
The fuel elements will, of course, be somewhat different in characteristic, but not appearance. The LEU elements will use 19.'75% ;
enriched uranium in a 16 fuel plate,2 aluminum plate fuel element which '
will contain 200 gm of U-235 as well as U-238.
Several other changes to the facility are in progress; FSAR changes will describe these (when the as built information is developed}? These changes are: nuclear instrumentation upgrades, radiation monitoring ,
system upgrades, and a replacement permanent emergency generator for the damaged permanent generator and its temporary replacement. None of these changes are related to LEU fuel conversion and none require Technical Specification change. Each is being done to maintain FSAR +
description and functions except for the manufacturor's nomonclature. ,
1.4 Summary of Operating License, Technical Specifications, and Procedural Changes The possession limits for uranium in the facility operating license will require changes. The existing limit in paragraph 2.B.(2) of 4.80 kilograms of uranium-235 needs to be increased temporarily to 10.3 kg U-235 while both LEU and HEU fuel are used and stored in the facility. This temporary limit is needed to cover the period until the irradiated HEU fuel is returned to a Department of Energy facility; the period is envisioned to be 6 to 12 months to allow for cooling of irradiated fuel and the scheduling and shipping of the cask for fuel return. Following the temporary dual fuel period, a permanent possession limit of 5.50 kg U-235 for the LEU fuel would be required.
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CONVERSION FROM HEU FUEL TO LEU FUEL UNIVERSITY OF M ASSACHUSETTS LOWELL RESEARCH REACTOR I
Technical Specification safety limit changes involve power and flow safety limits, natural convection safety limits, and corresponding limiting safety system settings. Limiting conditions for operation require some changes to reflect new core components. Of course, the design features, Section 5, requires replacement to describe the LEU fuel. The proposed Technical Specifications for operation with LEU fuel were submitted to USNRC on May 21,1993. Clarifications and revisions resulting from discussions with NRC staff were submitted on February 24,1994.
Changes to procedures will be made as procedures are reviewed'in the process of updating to incorporate LEU fuel operations. The only areas evident at this time are descriptions of new or modified core components and incorporation into procedural steps, such as verifying all grid positions are filled with appropriate components and insuring that 5 or fewer radiation baskets which do not have flow restrictors are present in the core.
1.5 Comparisons with Similar Facilities Already Converted.
The UMLRR conversion is very similar to several conversions already accomplished at, for instance, the University of Michigan, the University of Virginia, and Rhode Island Nuclear Science Center (RINSC).
Of these, RINSC is a sister facility with similar features. For example, the fuel elements at UMLRR and RINSC are the same, as is the regulating rod position and the need for an offset in the LEU core. No substantive problems were evident in the HEU-to-LEU conversion at RINSC.
o CONVERSION FROM HEU FUEL TO LEU FUEL UNIVERSITY OF MASSACHUSETTS LOWELL RESEARCH REACTOR 4
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- 12 CONDUCT OF OPERATIONS 3
- 12.1 Organization and Staff Qualifications 5
i- The University of Massachusetts Lowell Research Reactor (UMLRR) 4 operating organization is described in the Updated Final Safety Analysis 2
organization is under the direction of Dr. Guntt Tegel, Director of the
- Radiation Laboratory. The conversion activities would be overseen by the Reactor Supervisor, and the Radiation Safety Officer. Other key members
- are theProfessor of Chemical and Nuclear Engineering who is Chairman of 4
the Reactor Safety Subcommittee of the University Radiation Safety
- Committee and the Radiation Services Manager. Biographies for the j incumbents are attached to this report. The remainder of the organization j
are graduate and undergraduate student workers, including those who i have obtained Senior Reactor or Reactor Operator licenses in the course of
- studies and work assignments.
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i 12.2 Procedures
! Existing approved procedures cover most aspects of the HEU to LEU l conversion except for the handling and quality assurance for shipment of l irradiated HEU fuel and some specific tests or activities. A list of pertinent i
procedures is tabulated below in Section 12.6. Existing procedures will be I reviewed and revised as necessary to inspect, handle, and store LEU and i HEU fuel during the transition and the use of LEU fuelin the reactor core.
! Procedures used by other research reactors for irradiated fuel
- shipping cask receipt, handling, radiological survey, loading, shipping, and
- routing have been obtained and examined. These are suitable for i
! adaptation at UMLRR. Specific procedures will be developed based upon l I
successful ones used by similar facilities and then reviewed and approved
! for use at UMLRR.
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- 2 Updated Final Safety Analysis, University of Lowell Reactor.1985 3While this follows the format of AppendiI18.1 to NUREG 1537. sections involving l
} previously suomitted material are omitted. j i
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CONVERSION FROM HEU FUEL TO LEU FUEL UNIVERSITY OF M ASSACHUSETTS LOWELL RESEARCH REACTOR 1
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12.3 Operator Training and Requalification A ' review of the material required in a requalification program in accordance with 10CFR55.59 forms a basis for this enhanced program.
(i) Theory and principles of operation. The changes from a HEU core to a LEU core will be included in the lecture / discussion of (ii).
(ii) General and specific plant operating characteristics. A specific lecture / discussion on the differences expected in core behavior and the specific operating characteristics will be prepared and conducted.
The efficacy of the training will be validated with a quiz.
(iii) Plant instrumentation and control systeais. No changes.
(iv) Plant protection systems. No changes.
(v)' Engineered safety systems. No changes.
(vi) Normal, abnormal, and emergency operating procedures.
No substantive changes are anticipate' Minor changes will be disseminated through the present revi-C/ read / sign system used for i procedure changes. '
(vii) Radiation control and salety. No changes.
'(viii) Technical Specifications A specific lecture / discussion on TS changes will be presented and validated with a quiz. !
l The receipt of new fuel and core components, their storage, interim i storage of HEU fuel while awaiting shipment, and the core change test plan will be the subject of a specific lecture / discussion held shortly before the-reactor shutdown for conversion for all operators and involved staff. Pre-evolution briefings will be conducted prior to each major step in the i ccnversion process.
12.4 Emergency Plan No changes to the facility Emergency Plan are necessary for HEU to LEU conversion.
I CONVERSION FROM HEU FUEL TO LEU FUEL UNIVERSITY OF MASSACHUSETTS LOWELL RESEARCH REACTOR l
12.5 Physical Security Plan No changes to the existing Physical Security Plan are necessary. The period when both HEU and LEU fuel are on-site prior to the return of irradiated fuelis adequately handled in the existing Security Plan in accordance with 10CFR73.60. Return shipment of irradiated HEU fuel will i be accomplished by procedures developed to satisfy 10CFR73.67(e). l 12.6 Reactor Reload and Startup Plan The LEU Conversion Plan is outlined in Table 12.6.1. Most of the specific steps would be accomplished in accordance with existing
, operations or surveillance procedures. Table 12.6.2 provides a list of 4
these. Original startup test procedures 4 and the data obtained will be l
consulted and used with relevant information for fuel loading, control rod calibration, and other information. The test specifications for certain tests, such as core flux mapping and temperature coefficient will be adapted and used in the LEU test program so that direct comparisons of LEU and HEU cores can be made. (These are outlined in Table 12.6.3.) The test results obtained from the LEU conversion plan wculd be compared with those obtained for the HEU core and the predicted LEU values in a report of startup testing to be submitted to USNRC and DOE.
13 ACCIDENT ANALYSIS The analyses for core performance and accidents were submitted to USNRC in May,1993 (Reference 1) Accidents considered were fuel element failure during operation, a refuelling error substituting a fuel element for the central flux trap or an element dropped onto the core, a step increase of 0.5% reactivity while operating, continuous withdrawal of a control blade, and a cold water insertion into the reactor core. All of the consequences of these accidents are bounded by the analyses which set the Safety Limits i The radiological consequences of the release of all radiogases and radioiodines from a highly irradiated fuel plate were analyzed. Results of this analysis are summarized in Section 1.3 above and compared to previous dose consequences.
4 Startup Test Specification and Instructions. Lowell Technological Institute,22 A2278,
< Rev. O May 1974, General Electric Company, San Jose, CA
. CONVERSION FROM HEU FUEL TO LEU FUEL UNIVERSITY OF M ASSACHUSETTS LOWELL RESEARCH REACTOR
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Table 12.6.1 LEU CONVERSION PLAN PROPOSED SEQUENCE OF WORK LEU NORMAL
- 1. REGULATING BLADE FINAL CONSTRUCTION AND APPROVAL X
- 2. PLAN REVIEW AND APPROVAL X
- 3. SAFETY AND DECON EQUIPMENT X
- 4. SCHEDULE FOR FINAL REACTOR SHUTDOWN X
- 5. HEU FUEL C00LDOWN REVIEW X
- 6. HEU FUEL STORAGE SEQUENCE X
- 7. M AKE-UP DEMINERALIZER CAPACITY CHECK /
- RESIN CH ANGE X
- 8. CLEAN-UP DEMINERALIZER CAPACITY CHECK /
RESIN CHANGE X 9.- RECEIPT OF GRAPHITE REFLECTORS X
- 10. STORAGE SEQUENCE FOR GRAPHITE REFLECTORS X
- 11. RECEIPT OF LEU FUEL X i
- 12. STORAGE OF LEU FUEL X !
- 13. GRAPHITE TEST FIT X
- 14. LEU FUEL TEST FIT l
X 15 POOL GATE INSTALLATION X
- 16. POOL DRAIN X
- 17. GRID BOX RADI ATION SURVEY X
- 18. GRID BOX INSPECTION X
- 19. REGUL ATING BLADE REMOVAL AND STORAGE X
- 20. NEW REGULATING BLADE INSTALLATION X
- 21. NEW REGULATING BLADE TESTING X
- 22. GATE REMOVAL AND POOL REFILL X
- 23. GRAPHITE LOADING X l
- 24. SAFETY BLADE WITHDRAWAL CHECKS X l
- 25. RESET ALARM AND SCRAM SETPOINTS X i
- 26. LEU FUEL LOAD AND CRITICALITY DETERMINATION X
- 27. PRIM ARY SYSTEM FLOW CHECK WITH FULL CORE X
- 28. BL ADE WORTH DETERMINATIONS X
- 29. l EXCESS REACTIVITY DETERMINATION X l
- 30. NEG ATIVE TEMPERATURE COEF. DETERMINATION X
- 31. THERM AL FLUX M APPING X
- 34. HIGH POWER CALIBRATION - CALORIMETRIC X 35 RADI ATION MONITORING LEVELS CHECK X
- 36. PHYSICS BEAMPORT PARAMETERS CHECK X
- 37. XENON MEASUREMENTS X
- 38. NRC AND DOE FINAL REPORTS X
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n l- ' CONVERSION FROM HEU FUEL TO LEU FUEL
' UNIVERSITY OF M ASSACHUSETTS LOWELL RESEARCH REACTOR I
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Table 12.6.2 i
EXISTING APPROVED PROCEDURES Number Illig Revision D. gig RO-1 Critical Experiment - 1 2 /16 /8 4 l RO-1A Critical Experiment with Known I Configuration 0 5/23/94 R0-2 Reloading the Core to a Known !
l- Configuration 4 5/09/91. -
R0-8 Moving and Positioning of Core l 1 2 /16 /8 4 _ :
! RO-9 Reactor and Control System !
Checkout 10 9/21/95 R0-10 Receipt and storage of-New Fuel Elements 1 2 /16 /8 4 ,
RO-11 Handling of Irradiated Fuel 2 5/22/91 .
SP-13 Calibration of flow and dP
! Measuring Devices 5 -7/1/93 SP-15 Rod Reactivity Worth ~ Calibration 2 5/24/91 l SP-16 Rod Drop and Drive Measurements 4 7/31/87 l
SP-17 Visual Inspection of Control Blades l' and Regulating Rod 3 5 /10 / 9 4 ,
SP-26 Reactivity Evaluations 0 5/22/91 -
SP-18 Draining the Pool 2 7/31/87 j i
CONVERSION FROM HEU FUEL TO LEU FUEL 1
UNIVERSITY OF M ASSACHUSETTS LOWELL RESEARCH REACTOR I
Table 12.6.3 1 STARTUP TEST INSTRUCTIONS 4
. TO BE ADAPTED FOR LEU CORE d
1
< Test No. Iltle l
4 Temperature Coefficient of Reactivity
! 6 Core Neutron Flux Measurement l
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G.H. R. Kegel I PRESENT POSITION Professor, Department of Physics and Applied Physics, University of Lowell EDUCATION l'
1961 - Ph.D. Massachusetts Institute of Technology, Cambridge, Massachusetts FIELDS OP SPECI ALIZATION Nuclear Physics, millimicrosecond electronic techniques, nuclear instrumentation, radiation detection.
OTHER RELATED EXPERIENCE Chairman, Department of Physics and Applied Physics, University of Lowell Professor of Nuclear Engineering, Lowell Technological Institute Supervisor of Accelerator Facility, University of Lowell Nuclear Center Professor of Physics and Director of Radioactivity Laboratory Physics Institute of the Catholic Univeristy, Rio de Janeiro, Brazil Engineer at the Division of Electricity of the Instituto Nacional de Tecnologia, i Rio de Janeiro, Brazil l PUBLICATIONS (a) Book Chapters
- 1. " Naturally Occurring Radionuclides in Food and Waters from the Brazillian Areas of High Radioactivity", M. Eisenbud, H. Petrou, R.T. Drew, F.X. Roser, S.J., G.H.R. Kegel, and T.L. Cullen, S.J., in The Natural Radiation Environment, edited by John A.S. Adams and Wayne M. Lowder, University of Chicago Press, Chicago, IL (1964).
- 2. "Radiogeology of Some High-Background Areas of Brazil", F.X. Roser, S.J.,
G.H.R. Kegel, and T.L. Cullen, S.J., in The Natural Radiation Environment, edited by John A.S. Adams and Wayne M. Lower. University of Chicago Press, Chicago, IL (1964).
3 "The Use of Unactivated Sodium Iodide", L.E. Beghian, and G.H.R. Kegel,in Scintillation Spectroscopy of Gamma Radiation, Chapter X, Gordon and Breach. New York (1967).
(b) Published Papers and Presentations 34 Articles in refereed journals 35 Articles in Conference Proceedings 17 Presentations at National and International Meetings
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BIOGRAPHY LEE H. BETTENHAUSEN EDUCATION Ph. D., Nuclear Engineering, University of Virginia, Aug.1974 B. S., Engineering Science, Penn State University, June 1956 EXPERIENCE University of Massachusetts Lowell. Lowell. MA.
Reactor Supervisor, 1994-present 4
Responsible for licensing, maintenance ~and operation of 1 MW research reactor. Licensed Senior Reactor Operator. Adjunct 4 Professor of Chemical and Nuclear Engineering. Member, Radiation
- Safety Committee, Research into boron neutron capture therapy for i glioblastoma and radiation service life for materials and instruments.
U. S. Nuclear Regulatorv Commission. King of Prussia. PA Branch Chief, 1985-1994 Operations Branch, 1990-93, managed 20 operations
- engineers responsible for examining and licensing nuclear power 1
plant operators and inspecting control room staffing and operations, operating procedures, fire protection, and quality assurance.
Nuclear Materials Safety Branch, 1987-90, managed 30
- health physicists and support staff responsible for licensing and inspection of 3,000 holders of materials licenses ranging from a single user of a radioisotope gauge to sophisticated research and
- patient treatment in large university hospital and federal research f acilities.
, Reactor Projects Branch, 1987-89, managed 17 resident inspectors and engineers responsible for the reactor safety inspection programs at 8 nuclear power plants on 5 sites.
Operations Branch, 1985-87, managed 20 reactor engineers responsible for inspection of preoperational and startup testing of 8 nuclear power plants and of operational programs such as training, maintenance, surveillance, and quality assurance.
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l Section Chief, 1981-1985 i Supervised 8-10 reactor inspectors responsible for l preoperational and startup testing and reactor engineering. l Inspector, 1978-1981. !
Inspected initial startup testing, testing after refueling, l training programs, and special tests at nuclear power plants. l U. S. Environmental Protection Acencv. Philadelohia. PA i Regional Health Physicist, 1974-1978 Responsible for environmental assessments of radiation producing activities in the Middle Atlantic states. These included development of emergency response plans dealing with radiation releases to the environment, coordination of state 'and federal radiation monitoring programs, review of environmental impact statements, training state- technical staff, and coordinating studies of non-ionizing radiation .in environment.
University of Virginia. Charlottesville. VA Licensed Reactor Operator, 1967-1971 Reactor Health Physicist, 1966-1967 Graduate Student, 1966-1974 Laboratory Assistant, 1970-1971 Lecturer in Nuclear Engineering, 1971-1974
- Qualified User of Radioisotopes, 1968-1974 i
Battelle Memorial Institute. Columbus. OH Research Physicist, 1959-1966 Licensed Senior Reactor Operator for Battelle Critical Assembly Laboratory (CAL). Chairman, CAL subcommittee, Radiation- !
Safety Committee. Inventor of pulsed x-ray device for radiation !
effects studies. Author of studies on radiation effects and high i voltage insulation. Researcher in nuclear reactor experiments, experiments in radiation source use, the holography for industrial and commercial uses.
U. S. Air Force Weather Officer for heavy jet bombardment wing,1956-1959
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. 3 Professional Activities Registered Professional Engineer, Ohio and Virginia Member: Institute of Electrical and Electronics Engineers, American Nuclear Society, Virginia Academy of Sciences, Delaware Valley Society for Radiation Safety, Health Physics Society l .
Licensed Senior Reactor Operator'(Battelle and University of j Massachusetts Lowell) and Reactor Operator (University of Virginia) 4 Honors: Phi Eta Sigma, Sigma Tau, Sigma XI Fellowships: University of Virginia, Atomic Energy Commission selected for regional and specialty editions for Who's Who NRC Awards:High Quality-1983 and 1987; performance-1992 i NRC "O" security clearance; AEC "O" and DoD Top Secret l Citizenship: USA 1
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1 s l WARREN W. CHURCH, CHP Certified Health Physicist HOME: 601 Main Street WORK: University of Massachusetts Lowell ,
l Dunstable, Massachusetts 01827 One University Avenue ]
(508) 649-6118 Lowell, Massachusetts 01854 )
(508) 934-3372 I (508) 459-6361 EXPERIENCE l UNIVERSITY OF MASSACHUSETTS AT LOWELL, Lowell, MA,1988-Present Radiation Safety Officer. !
- Develop, plan, and manage campus-wide radiation safety program. Major radiation sources at the university include a one-megawatt research and training ;
reactor, a 5.5-McV Van de Graaff accelerator, and a 300,000+ Curie Co-60 irradiator.
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Other sources include radioisotope laboratories and X-ray and laser facilities.
- Perform risk analyses on radiation emissions for compliance with federal and state requirements.
- Develop and regularly update safety manuals and procedures.
- Provide radiation safety training for radiation source users and university students.
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- Supervise Radiation Safety Office staff in carrying out radiation surveys, inventories, calibrations, and dosimetry services.
- Manage radioactive waste disposal program.
- Review, evaluate, and approve experiments and other activities involving radiation sources, j
- Conduct audits of radiation safety programs.
- Develop and coordinate emergency plan for Research Reactor, including provisions for outside agency responses.
- Oversee development of procedures and identification and acquisition of appropriate equipment to support Radiation Safety Program.
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HEALTH PHYSICS CONSULTANT,1988-Present Provide health physics services on an as needed basis to a variety of public and private clients, including CIS, Inc., M/A-COM, Inc., Perkin Elmer Corp., Raytheon Company, Varian Corporation, and the Massachusetts Nuclear Incident Advisory Team (NIAT).
- Developed extensive decommissioning plans to enable industrial clients to close ,
facilities where radiation sources were processed and stored, including '
performing health physics, training employees, and developing surveillance and remediation procedures that complied with U.S. Nuclear Regulatory Commission ;
requirements. --
- Provided advice and assistance to decommissioning managers during l decommissioning processes, including developing specifications to be followed by ]
decommissioning contractors, auditing all decommissioning activities, i performing risk analyses, and preparing decommissioning reports for submission to the U.S. Nuclear Regulatory Commission.
- Developed and conducted radiation safety courses for radiation workers.
- Developed and performed radiation safety surveys.
U.S. FOOD AND DRUG ADMINISTRATION, REGION I, Boston, MA 1980-1988 f Regional Radiological Health Representative and FDA Region I Radiation Safety Officer.
Regional Radiological Health Representative
- Implemented FDA Radiation protection programs in conjunction with radiation control programs of six New England states (e.g., developed and implemented Regional Mammography X-ray Survey Program). '
- Project Manager for FDA/ State contracts involving field testing of medical X-ray units.
- Primary advisor to FDA Regional Director and Program Managers in matters involving radiation protection.
- Member of FEMA Region I Radiation Advisory Committee-reviewed and evaluated Nuclear Power Plant emergency plans.
- Health Physics Consultant to federal agencies in New England regarding the safe use of X-ray equipment and radioisotopes.
- FDA Region I Radiation Safety Officer.
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WINCHESTER ENGINEERING AND ANALYTICAL CENTER, Winchester, MA, 1974-1980 Supervisory Engineer
- Independent responsibility for ensuring safe, efficient, and effective operations within the electronic product testing group, consisting of five professionals and five technicians.
- Supervised analysis of complex electronic products to ensure that radiation emissions complied with designated performance standards.
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- Performed final science reviews for sample analyses.
- Supervised and provided guidance to employees engaged in research in equipment and methods development.
MASSACHUSETFS GENERAL HOSPITAL, Boston, MA,1971-1974 Research Fellow in Physics.
U.S. PUBLIC HEALTH SERVICE, Various Locations,1962-1971 Health Physics Instructor,1966-1971.
Radiological Health Engineer,1962-1965.
CERTIFICATION
- Certified Health Physicist (CHP), American Board of Health Physics,1974.
Recertified through 1996.
PROFESSIONAL MEMBERSHIPS AND POSITIONS
- National Health Physics Society Member,1964-Present Placent Committee 1994-present, Chairman 1996
- Health Physics Society, New England Chapter Member,1966-Present Chairman, Training and Education Committee, 1972-1973 l President-Elect and Program chairman, 1973-1974 '
President, 1974-1975
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CIVIC MEMBERSHIPS AND POSITIONS l 4
- Massachusetts Low Level Radioactive Waste Management Board Member,1994-Present I l
- Town of Dunstable (Massachusetts) Board of Health Member,1989-Present Chairman, 1991-1993, 1995 4
- Town of North Reading (Massachusetts) Community Planning Commission Member, 1976-1983 Chairman, 1979-1980 HONORS
- Boston Federal Executive Board, Professional of the Year Award,1986
- U.S. Public Health Service Commendation Medal,1980
- Research Fellowship in Physics, Massachusetts General Hospital,1971-1974
- Sigma Chi and Phi Kappa Phi Honorary Societies,1966 EDUCATION Washington State University, Seattle, WA
- M.S., Sanitary Engineering, Specialty in Radiological Health,1966 University of Connecticut, Storrs, CT B.S., Civil Engineering,1962 4
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Dr. John R. White Chemical and Nuclear Engineering Dept.
University of Massachusetts at Lowell Lowell, Massachusetts 01854 !
SUMMARY
QUALIFICATIONS:
Dr. White has over 17 years experience in the development, application, and teaching of a variety of reactor physics methods, with nearly six years at the Oak Ridge National Laboratory (1977-1982) and twelve years in the Chemical and Nuclear Engineering Department at UMass-Lowell (1982-present). His research and teaching have involved him in all aspects of computational reactor physics, including transport and diffusion theory codes and methods for core design and shielding applications, cross section processing codes, perturbation theory methods, Monte Carlo criticality analysis, and fuel management design and optimization. His current teaching assignments include undergraduate courses in Computer Applications (numerical methods) and Reactor Physics and graduate courses in Dynamic Systems, Math Methods for Engineers, Space Power Systems, and Special Topics in Reactor Physics (transport theory, Monte Carlo methods, etc.).
EDUCATION:
PhD in Nuclear Engineering, University of Tennessee, Knoxville, TN. (1987).
MS in Nuclear Engineering, University of Tennessee, Knoxville, TN. (1980).
BS in Nuclear Engineering and in Electrical Engineering, University of Lowell, Lowell, MA (1977).
PROFESSIONAL EXPERIENCE:
Research Contracts Principal Investigator, " Physics Analysis of the Modular High Temperature Gas-Cooled Reactor (MHTGR)," Martin Marietta Energy Systems, Inc., Oak Ridge, TN, Jan.1991 - Dec.1991.
Principal Investigator, "Sencitivity and Uncertainty Analysis of the High Converter Reactor (HCR)," Siemens AG, KWU, Federal Republic of Germany, Sept.1988 - Sept.1989.
Co-principal Investigator, " Low Enriched Fuel Conversion for Research Reactors," Department of Energy, Washington D.C., Sept.1986 - Sept.1988.
Principal Investigator, " Demonstration of Generalized Perturbation Methods for LWR Applications," Westinghouse Electric Corporation, Pittsburgh, PA., Jan.
1984 - Jan.1987.
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. JOHN R. WHITE 3 4
Principal Investigator, " Physics Analyses of the Hiob ~ emperahre Gas-Cooled Reactor (HTGR)," Martin Marietta Energy Systems, Inc., Oak Ridge, TN, Oct.
1983 - June 1985.
Principal Investigator, "Large Core Design Methods and Applications," Union Carbide Corporation, Oak Ridge, TN., Sept.1982 - March 1984.
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Consulting / Prior Work Experience June 1991 to December 1993 - Consultant to Reactor Physics Group at Yankee Atomic Electric Co., Bolton, MA. Implementation of transport theory codes (DORT and ANISN) on HP workstations. Develop detailed plant-specific shielding models and perform appropriate fluence and dosimetry analyses. )
Fall 1990 - Consultant to Reactor Physics Group at Yankee Atomic Electric Co.,
Bolton, MA. Performed preliminary modeling and analysis to quantify the fast ,
fluence at the inner surface of the pressure vessel at Yankee Rowe. ;
Summer of 1990 - Consultant to Engineering Physics and Mathematics Division at the Oak Ridge National Laboratory. Performed conversion, upgrade, and benchmarking of complete VENTURE / DEPTH-CHARGE system from IBM mainframe to VAX mainframe. Also provided support for VENTURE applications at ORNL.
Summerof 1988 - Consultant to the Nuclear Engineering Section of the Computer Science Division at the Oak Ridge National Laboratory, Oak Ridge, Tennessee. Performed analyses with the SCALE system in support of ORNL's effort to develop and benchmark tools for shipping cask design and analysis.
Jan.1977 to Sept.1982 - Research staff member in the Nuclear Engineering Section of the Computer Science Division at the Oak Ridge National Laboratory, Oak Ridge, Tennessee. Responsible for the development and application of large-scale state-of-the-art computer code systems for the solution of a variety of neutronic analysis problems. Specific research areas included fuel-cycle depletion analysis, the development and application of time-dependent perturbation theory, and the application of adjoint sensitivity theory and uncertainty analysis methods to the study of design sensitivities and uncertainties in large fast reactor systems. Familiar with several large code systems such as VENTURE / DEPTH-CHARGE, CITATION, FORSS, AMPX, DOT, ANISN, KENO, etc..
Summer of 1976 - Assistant to the Reactor Engineering Supervisor at Maine Yankee Atomic Power Plant in Wiscasset, Maine. Major involvement was in a project to predict transient axial power distributions in large PWRs.
May 1971 to May 1974 - Served in the United States Air Force as an electronics technician specializing in the maintenance of ground to air communication systems.
JOHN R. WHITE 3 Professional Memberships American Nuclear Society (ANS), National Member,1977 to present.
National ANS, Reactor Physics Division, Program Committee,1993 to present.
National ANS, Mathematics and Computation Division, Program Committee, 1983 to present.
National ANS, Mathematics and Computation Division, Benchmark Committee, 1984 to present.
National ANS, Mathematics and Computation Division, Treasurer, elected term 1986-87.
RECENT PUBLICATIONS (last 5 years)
K. B. Spinney, J. R. White, and R. C. Paulson, " Determination of Neutron and Gamma Radiation Fields in a Mark l BWR Drywell via Calculation and Measurement," 8th International Conference on Radiation Shielding, Arlington, Texas (April 1994).
J. R. White, et al., " Comparison of the BUGLE-80 and SAILOR Libraries for Coupled Neutron-Gamma Transport Applications," Eighth ASTM-EURATOM Symposium on Reactor Dosimetry, Vail, Colorado (Aug.1993).
J. R. White, et al., " Maine Yankee Dosimetry Capsule and Pressure Vessel Neutron Fluence Calculations," Eighth ASTM-EURATOM Symposium on Reactor Dosimetry, Vail, Colorado (Aug.1993).
K. B. Spinney, K. J. Morrissey, and J. R. White, " Equilibrium Cycle Excore i Neutron and Gamma Fluxes for the GE Simplified Boiling Water Reactor," I YAEC-1858, Yankee Atomic Electric Company (May 1993)
J. R. White and P. M. Detmolino," Simple Heuristics: A Bridge Between Manual i Core Design and Automated Optimization Methods," International Conference on Mathematical Methods and Super Computing in Nuclear Applications, i Karlsruhe, Germany (April 1993)
J. R. White and F . M. Delmolino, " LWR Core Design and Analysis Using the RESCUE Interactive Reload Design Tool," Al 91: Frontiers in innovative Computing for the Nuclear Industry, Jackson, Wyoming (Sept.1991).
J. R. White and T. F. DeLorey, " Sensitivity and Uncertainty Analysis of Integral Physics Parameters in High Conversion Reactors." Nuclear Technology 95, 129 (Aug.1991).
J. R. White, " Integrating Computer Literacy into the Nuclear Engineering Curriculum," ASEE Annual Conference, New Orleans, Louisiana (June 1991)
J. R. White, K R. Robinson, and P. M. Delmolino, " Implicit Versus Explicit Perturbation Methods for the Efficient Evaluation of Alternative Core Designs,"
International Topical Meeting on Advances in Mathematics, Computations, and Reactor Physics, Pittsburgh, Pennsylvania (April 1991).
J. R. White and P. M. Delmolino, " RESCUE _ A PC-Based Interactive Reload Design Tool," Trans. Am. Nuc. Soc., 62, 551 (Nov.1990).
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Y JOHN R. WHITE 4 J. R. White and P. M. Delmolino, "An Implicit High-Order GPT Method for LWR 4
Reload Design Applications," Trans. Am. Nucl. Soc.,61,159 (June 1990).
T. F. DeLorey and J. R. White, " Quantifying the Void Coefficient Uncertainty in High Conversion Reactor Systems," Trans. Am. Nucl. Soc.,61,336 (June
- 1990).
3 J. R. White and G. A. Swanbon, " Development of a Technique for the Practical ,
implementation of Higher-Order Perturbation Methods," Nuc. Sci. Eng.,105, j 160 (June 1990). . I J. R. White and T. F. DeLorey, " Data Uncertainty Reduction in High Converter
, Reactor Designs Using PROTEUS Phase ll Integral Experiments," International Conference on the Physics of Reactors: Operation, Design and Computation, 4
Marseille, France (April 1990).
J. R. White and P. M. Delmolino, " Accurate LWR Assembly Power Distributions Based on Generalized Perturbation Theory," International Conference on the Physics of Reactors: Operation, Design and Computation, Marseille, France (April 1990).
J. R. White and K M. Avila, " Developing Feasible Loading Patterns Using Perturbation Theory Methods," International Conference on the Physics of 4
Reactors: Operation, Design and Computation, Marseille, France (April 1990).
D. Biswas, W. P. Kovacik, and J. R. White," Evaluation of the Delayed Neutron importance Factor with ENDF/B-V Data," Trans. Am. Nucl. Soc., 59, 318 (June 1989).
J. R. White and G. A. Swanbon, "A Practical Approach to Higher Order Generalized Perturbation Theory," ANS Topical Meeting on Advances in Nuclear Engineering Computation and Radiation Shielding, Santa Fe, New Mexico (April 1989).
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& l 7 Patch Road l Hollis, NH 03049 j l
home (603) 465-3687 )
work (508) 934-3375
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EDUCAT10N: Unhesity of Massachusetts at towc5 lowell, MA Master of Business Administration December,1991 University of towet Irwell, MA Master of Science, Radiological Science and Protection - May,1985 l Bachelor of Science, Health Services Administration - May,1982 )
PROFESSIONAL Unhasty of "-"+ at towd E=rhHan I . lower MA 1 EXPERIENCE: Radiation Services Mananer 1986-present Responsible for all phases of facility utilization pertaining to radiation services l Duties include:
- Scheduling and coordination of facility use by students, faculty, and industrial users. !
- Evaluation and design of sample irradiation protocols. !
- Supervision of experimental set up by operational staff to conform to experimenters' needs, reactor procedures and NRC regulations.
- Evaluation of dosimetric results and preparation of reports to facility users.
- Directing and evaluating research pertaining to dosimetry.
- Management and budgeting of negotiated contracts.
- Preparation of annual utilization and financial reports.
- Emergency team member,
- Reactor Safety Sub-Committee member Senor Reactor Oncrator 1 USNRC license number SOP 70045, Docket Number 55-60851 (Issued 5/21/92)
Reactor Oncrator USNRC license number OP-10496, Docket Number 55-6085 (Issued 2/18/87)
Responsible for the operation and maintenance of 1 MW research reactor General dutics include-
- Daily procedural and operational checkouts.
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Surveillance requirements and routine systems maintenance.
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Health Physic support - contamination surveys and radiation monitoring.
Research Assistant. 1984 1985 PERSONAL: Date of Birth- May 17,1959 Marital Status- Married Health: Excellent
REFERENCES:
Furnished upon request
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- PUBLICATIONS /' W.Tomford, H. Hung M. Montesalvo, L Beghlan,"The Effect of Radiation on Articular PAPERS: Cartilage", to be published in Vol I transactions of Orthopaedic Society, February,1992 T. Conway, J. Strick. L Beghlan, M. Montesalvo, E. Jahngen, F. Schooley, W. Tomford,
, "RadiosensitMty of HIV1", presented at the annual meeting of the American Association of Tissue Banks, Denver, Colorado, September,1990 a
F. Chen, C French, T. Wallace, M. Montesalvo, G Chabc'., "The evaluation of PMOS-FET Devices as Passive and Active High Range Dosimeters", presented at the Health Physics Society annual meeting , Boston, M A, July,1988 D. Schiff, J. Bruun, M. Montesalvo, C Wong "A Comparison of Conventional Dose Rate and low Dose Rate Co60 Testing of IDT Static Rams and FSV Multiplexers", presented at the Annual Conference on Nuclear and Space Radiation Effects, Montemy, CA, July,1985 G. Chabot, F. McWilliams, M. Montesalvo, K. Skrable, "Research Development and Application in Radiation Dosimetry at the University of 15we11", presented at the Health Physics Society annual meeting, Chicago,11, May,1985 M. Montesalvo," Evaluation of an Automated Dosimetry System", presented at the New England Chapter of Health Physics Society, Wakefield, MA, April,1985 1
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