ML20100A901
| ML20100A901 | |
| Person / Time | |
|---|---|
| Site: | Indian Point  |
| Issue date: | 11/21/1984 |
| From: | Otoole J CONSOLIDATED EDISON CO. OF NEW YORK, INC. |
| To: | Murley T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| Shared Package | |
| ML20100A903 | List: |
| References | |
| NUDOCS 8412040126 | |
| Download: ML20100A901 (38) | |
Text
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. . . - q, s; ., , 'e John D. &Toole Vice Prespdent Consolidated Edison Company of New York, Inc.
- 4 Irving Place. New York, NY 10003 Telephone (212) 460-2533 t
November.21, 1984 Dr. '1hcznas E. Nrley l Regional Administrator U.S. Nuclear Regulatory Ocmnission Region I 631 Park Avenue King of Prussia, Pa. 19406
Dear Dr. N rley:
The letter of Mr. Richard C. DeYcung dated Septerter 27, 1984 together with the Order Modifying License of the sane date has been forwarded to me for reply. We agree with your observation that, as a result of the events leading to the issuance of the Order Modifying License, there were no exposures in excess of regulatory limits. However, we do see wrtunities for further inproving the effectiveness and functioning of our radiological
! controls program.
Provided herewith as Appendices _A, B, and C are our response to items A(1), A(2),' and A(3), respectively, frcxn the Order Modifying the License.
Appendix D contains the names of the merters of the Radiation Protection oversight Ctmnittee and their qualifications. Appendix E contains the recently approved Station Administrative Order 301, " Radiation Protectim i
Plan" which outlines the plan for and elements of the upgraded Radiation Protection Program.
Should you or your staff have any questions, please contact us.
Ve truly yours,
/
t cc: Mr. Richard C. DeYoung, Director %v
- Office Of Inspection and Enforcement f.
U.S. Nuclear Regulatory Ccmnission Washington, D.C. 20555 i
Senior Besident Inspector U.S. Nuclear Regulatory Cannission P. O. Box 38 Buchanan, New York 10511 O
OShh7 pg 8412%oh26 gi tt I i k a
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,,e he APPENDIX A Page 1 of 3 RESPNSE 'IO ITEM A(1) - ACTICN PLW IcrICN ITEM DlKJumm MTTMiINE DATES
- 1. Develop Radiation A description of the program (Appendix E to October 12, 1984 Protection Plan this transmittal) outlining the policy, basis and objectives of the Padiation Protection Program shall be developed as a Station Administrative Order for the Indian Point Station. In addition to the Station radiation protection policy and cbjectives, Appendix E addresses the following:
a) Provision for positive control of Ifigh Radiation Areas. (Section E-1.c.)
b) A clear and effective Radiation Nbrk Permit (RWP) system. (Section E-1.c.)
c) A technically adequate and effective Respiratory Prei.ection Program.
(Section E-2.b.)
d) An effective Training Program for both ertployee and contractor health physics staff and radiation workers. (Section D).
e) A program which documents existing corporate philosophy to maintain radiation exposures as low as is reasonably achievable.-
(Section E-1.b.)
f) A system for auditing and evaluating program i
irtplementation by qualified asmssors at least annually. (Section I-2.d)
- 2. Develop Radiation A manual that establishes the requirements Novertber 20, 1984 Protection Manual for the Indian Point Fadiation Protection Program shall be developed using the guidance contained in NUREG 0761. 'Ihe manual shall describe the following:
o Administrative and functional responsi-bilities of the Environmental Health and Safety organization.
l o Indian Point radiation protection train-ing and qualification.
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APPDDIX A I
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. ACTICE ITDI -
DESCRIPTI M MTTRATCelE DATEE N
~ o 'Ihe dose control system 'for evaluat-l ing, .controllinQ, Innitoring and recording doses.r, o 'Ihe system for identificatim, accountability, control, movement, storage, and inventory of radioactive materials.
L o 'Ihe type and frequency of radiological surveys.
o 'Ihe types, nunbers and calibration criteria of radiation protection instruentation.
o 'Ihe types and frequencies of radiological reviews, audits and appraisals-including deficiency reporting-and corrective action mechanisms.
p l: 3. Develop Inplanent- Procedures that provide instructions and the March 8, 1985
[ j ing Procedures for steps to inplement the Radiation Ptobection -
Radiation Frei.ection Manual requirenents will be developed. A
-Manual Requirements preliminary list of prorwhwes by major topic / subject are attached (Attachment 1).-
'Ibe procedures will be subject to a-field i
validation prior to approval and inpleenta-l ticm.
- 4. Provide Training Upon cmpletion of the Radiation Fici.ection June 30, 1985 fcr on-site Manual, training objectives will be Personnel. identified, lesson plans developed and supplemental training conducted for personnel
! working at the Indian Point Station. 'Ihe l training will thereafter routinely be given to the radiation protection staff and capany and contractor radiation workers.
- 5. Program Approval Upcm cmpletion of the Radiation' Protection
+ ;Inplementation Procedures:and during the conduct of' retraining in the upgraded pro-gram requirments, an appraisal similar in 7 .. scope and methodology _to that of NUREG 0855,-
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.g APPDDIX A PAGE 3 of 3 mm m DESCRIPTIGI W N MN
" Health Physics Appraisal Program," will be conducted by individuals knowledgeable in ,
ca mercial power reactor Health Physics and independent of the station radiation protection organization. The appraisal re>_-+1x3ations will be reviewed by the facility staff, written responses pre-pared, and action itens generated.
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,jr Page 1 of 4 ATDO9ENT 1 to APPDOIX A .
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, PRELIMINARY PRO 3 DURE LIST AIARA AIARA Job Review AIARA Goals and Measurement AIARA Reviews of Design Modifications AIARA. Reviews of Wrk Promhwes AIARA History File EXPOSURE C3FfROL -
4 Administrative Exposure Control Area Definition and Posting Radiologically Controlled Area Access Controls High Radiation Area' Key and Access Control Contamination Control Radioactive Material Control.
Area and Ruipnent 1 Release Requirements Decontamination of Personnel Radiation Work Permit RADIATIN PROTECTION OPERATIWS Routine Survey Requirements Non-Routine Survey Requirements Performance of Radiation and Contamination Surveys Airborne RM4=tivity Sanpling Control, Ieak Test, and Disposal of Licensed Sources DOSIMETRY Issue and Control of TID's ,
Ekb saity and Special Monitoring 1 Monitoring for Neutron Radiation TID Mr Operation TID Reader Calibration TID Acceptance Testing .,
. Direct Reading Dosimeter Issue and Control Radiation Exposure Records and Reports.
Dosimetry Investigation Reports BIGASSAY Conduct of the Bioassay Program Assesment of Bioassay Results Efficiency calibration of the NA 6700 Counting System - APT Phantorp NA 6700 FMt4, Background Acquisition and Quality Assurance Checks
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F Y ATI7GMENT 1 to APPENDIX A PRELIMINARY Pfu.mns LIST BIGASSAY (continued)
Whole Body Counting Using the NA 6700 System Bioassay Records and Peports RADIOIOGICAL ENGINEERING Ternporary Shielding Program High Radiation Area Enclosure Design and Acceptance l Ommitment Tracking System Station Radiological Status Reporting System Installation & Acceptance Criteria for 'Ibaporary Ventilation Systems Dose Calculation Radiological Work Practices Developnent INSTRUMENIATICE General Use and Care of Instrumentation calibration Facility Operation Calibration, Functional and Operational Checks of Radiation Protection Instrumentation Decay Corrections for Radioactive Sources Use of the Model 1000 B Ganma ralihrator Count Rocra Standard Practices Iaboratory Calibration Checks and Use of the Victoreen Condenser 'R' Meter Calibration and Use of the Eberline BC-4 Calibration and Use of the SPA-3 With tra MS-2 Calibration and Use of the PCCllT and DS-2 Calibration and Use of the Iberline SAC-4 Calibration and Use of the Baird Atcmic Poly Spec Scaler and SSC-3 Autanatic Planchet Changer Calibration and Use of the SC2B/DS-2 Calibration and Use of the Iberline SN!2/ID-22 Air Sanples Calibration and Use of the Iberline RAS-1 Portable Air Sanpler Calibration and Use of the Iharline NIS-2 Calibration and Use of the NMC AM-2A CAM Calibration and Use of the NbC N1-28 CMi Calibration and Use of the l@C 331F CM1
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A'ITACHENP 1 to APPEN)IX A PRELIMINARY PIOCEDURE LISP 1 1
' Air Sanples (continued) l 1
Calibration and use of the !@C Digital CAM I calibration and Use of the 19C Digital CAM calibration and Use of the Triton 1055B- ,
Calibration 'and Use of the Triton JLI 955B Calibration and Use of'the Triton III-calibration and Use'of the Fadeco ID-28 IcVol Calibration and Use of the GP-4 Air Monitor Calibration and Um of the Dupont 4000A Iapel Air Sanpler .
. Calibration and Use of the Victoreen Iapel Sanpler Model l
- 08-430 l ralibration of the "Siersat" Fersonnel Air Sanpler l ralibration and Use of the Sipin Iapel Sanpler Calibration and Um of the Gillian Model HFS 113 Iapel Air i Sanpler Portable Calibration and Use of the Eberline h14 Calibration and UEe of the NMC Frisker calibration and Use of the Eberline RO-1 Calibration ~ and Use of the Eberline P0-2 and ID-2A l Calibration and Use of the Eberline PO-4A l ralibration and Use of the Eberline RD-7BM .)
calibration and Use of the Eberline PIC 6A Calibration and Use of-the Eberline E140
' Calibration and Um 'of the Eberline E-510 D-N Calibration and Use of the Eberline E-520 calibration and Use cf the Eberline E530N/HP-200 Calibration and Use of.the CP-MJ High Range Underwater Meter Calibration and Use of the Iberline 'Deletector Calibration and Use of1the Victoreen 740 ETP ralibration and Um of the Digimaster, Xetex 305A and 305B Survey Meter .
Calibration and.Um of the Eberline. PAC-4S Calibration and Use of the Eberline PNR-4 Neutron REE Counter Calibration and Um of the Indlum ledel 50M calibration and Use of the P W 7 Micro R Meter Use of the QXI 715/720 calibration and Um of the Rad-Tad Calibration and Um of the Xetex Digital DosiJneters, Models 409A, 415A and 415A Modified Calibration and Use of the Indlun 43-2 Alpha Probe .j Dosimeter Charger Use Fixed Calibration and Use of the GA 2T Ganma Alarm Calibration and Use of the Radiation Monitor Model PRM llOC
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-PRELIMINARY PROCEDURE LIST Fixed (continued)
Calibraticn and Use of the Eberline BM-16/RD17A calibration and Use of the Eberline BM16/HP-200 Calibration and Use of the AM-2 Ganma Alarm calibration and Use of the Eberline PMC/PMP-4B Portal Manitor:
Calibration and Use of the Hard Hat Monitor RESPIRA'IORY PROTECTION Respiratory Protection - Operational Selection and Use of Respiratory Protection Devices Control, Issue and Storage of Respiratory Protection Devices MPC Hour Tracking and Stay Times Respiratory Protection - Facility Inspection and Inventcry of Respiratory Protection Devices Cleaning and Sanitizing of Respiratory Protection Devices Maintenance and Repair of Respiratory Protection Services Calibration and Use of the MSA Filter Ibsistance Tester calibration and Use of the Air Techniques ledel 9127 for Testing of Respirator Cartridges Respirator Seal Bench Test.ing Respiratory Protection - Fit Testing Calibration, Maintenance and Use of the Frontier Enterprise Fit Test System Calibration Maintenance and Use of the Air Technique Fit Test System i
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, u - APPDDIX B .>
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RESFWSE 'IO I'IEM A (2)' - INTERIM ACTIWS ,
Consolidation of Procedures- . .
Consolidation of Envirarsnental Health & -Safety Procedures (DI&S) , Health' 4
Physics Procedures (HPP) and Health Physics , Instructions (HPI) ~ has ~ been
.capleted. The final -index : of procedures _is attached to ' this- Appendix.
'Ihe ' procedures will be inplemented upon coupletion' of H.P. Technician 1 supplanental training.
Persmnel'~ Training
. A review of the consolidated procedures described above was conducted i during the week of October 21, 1984. 'Ihe purpom of the review was to
. determine the , supplemental training required for. health. physics technicians. . 'Ibe supplemental training will be cczopleted by Da--u+r ~7, 1984. . Additionally, the radiation safety training provided .to personnel working within radiologically controlled areas will be reviewed to '
determine 'if training modifications are necessary to enhance -personnel understanding of program requirements. Designated changes; will be
. incorporated into training lesson ' plans and presented as part of initial and annual regnalification training.
'Ihe . review and revisicn will be performed by January 7, 1985.
Enhanced High Radiation Area Control
'Ihe' following enhancements to high radiation area control have been or'will be inplemented:
o'- Instructions on inplementation of high radiation area controls, frequency of high radiation area surveillance and training of .
perscnnel responsible for inplementation were put into effect .for interim enclosures until the locked gates were installed.
I o Iocked expanded metal gates were constructed for high radiation
, areas (- > 1R/hr) within containment. 'Ihe expanded metal gates I are not seismically qualified but will- be replaced at a -later date by permanently mounted seismically . qualified structures.
Until construction of- the permanent seismically qualified barriers, the expanded metal gates will be utilized. during -
=. periods of reactor shutdowns. 1 All entries at other times shall-continue to be accuplished under the control of a qualified radiation monitor.
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Page 2 of 2 APPIND1X B RESPCNSE 'IO ITEM A (2) - -INTERIM JCTICES o Health Physics personnel were assigned to perform increased surveillance of the high radiation work-area on the 95' and 68'/46' elevations of the Vapor Containment.
o Additional dose - indicating alarming dosimeters have been purchased and the instruction on their purpose and use have-been included in worker radiation safety training.
o The training lesson plans will be reviewed and modifications made to reasonably assure personnel understand the purpose-and requirements of High Radiation Area Controls. 'Ihese changes will be incorporated into training lesson plans as part of initial and annual requalification training.
'Ibe review and revision will be performed by January 7, 1985.
Increased Management Oversight A former radiation protection and radwaste manager has been assigned to the radiological assessor's position. 'Ihe radiological ~ assessor reports directly to the Vice President, Nuclear Ibwer and provides assessments of radiological work performance and canpliance.
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ATDONENT l' UD APPEtOIX B
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ItUEX OF CCESnrJr%TED PROCHX1RES '
AIARA
~HPP '1;l- ^ - Inplementation' of - AIARA policy.) t w_ HPP 1.2 Achinistrative Radiation Exposure Control. -
EMS 3.001- Radiological Protection Surveillance
-Evaluation.
NYM CONTROL
'HPP 2.1 Radiation Work Permits HFP 2.2 Radiation, contamination and airborne
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activity guides and limits.
..HPI 2.24 _ Access control to contamination areas.
HPI 2.210 . Instructions to VC Control Point personnel in the event of an evacuation.
EHS 3.101 Access control Areas EMS 3.102 controlled area entry / egress EHS 3.104 Vehicle entry / exit from controlled area staging locations.
EHS 3.105 Supplementary access control points.
EHS 3.106 Containment building entry.
EHS 3.107- Vapor containment building control point IHS 3.109 Iccked high rad area control EHS 3.350- Releam of tools / equipment to unrestricted areas EHS 3.603 Airborne contamination monitoring program guidelines EMS 3.604 Radiewtive noble gases EHS 3.620 Determination _ of maximum _ permissible concentration and MPC hours SURVEYS HPP 3.2 Ibutine and special contamination surveys-
.HPI 3.13 Beta dose rate determination .
HPI 3.21 Contamination survey techniques EMS 3.203- Radiation surveys EMS 3.204 Bequirements for hot spots
-DOSIMETRY HPP 4.1 Issuance and control of personnel dosimetry HPP 4.2 Bioassay and whole body counting HPI 4.11 Instruction for the issuance and control of dosimetry devices HPI 4.12 Film Badge Quality Control HPI 4.13 Direct-rmwiing dosimeter leak check and
<-alibration
, HPI.4.14 Direct-awling dosimeter use.
PPI 4.15 Um of. Rad Tad HPI'4.16 Calibration of Rad Tad i .HPI 4.17 Inst, <*W, off-scale dosimeter leak check and calibration
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- $N . ATDOiMENT 1 'IO APPDOIX B INDEX-CF CONSOLIDA'IED PROCEDURES HPI 4.18 Personnel contamination and/or overexposure investigation .,
HPI 4.19 Dosimetry discrepancy e. valuation a
~HPI 4.110 '_Use of' TID .Results! t.
HPI w.112. Instructions for generating ,
in-controlled = area report via the health physics coaputer.:
HIS 3.201 Radiation Exposure Limits r HIS 3.202 Personnel dosimetry assigment criteria EHS 6.401 Use of TID Ber INSTRLNENIATICE HPP 5.2 Survey.and laboratory instruments Health Physics Instructions HPI 5.21 ' Use of Eberline E-520 HPI 5.22 calihration of Eberline E-520 HPI 5.23~ Use of Eberline RO-1 HPI 5.24 calibration of Eberline RD-1 HPI 5.25 Use of Eberline RO-2 & RD-2A HPI 5.27 'Um of Eberline PIC-6A iHPI 5.28 Calibration of Eberline PIC-6A HPI 5.29 Use of Digimaster, Xetex 305P and 305B Portable Survey Meters HPI 5.210 Calibration of Digimaster, Xetex 305A and 305B Portable Survey Meters HPI 5.211- Use of Eberline Teletector HPI-5.212 Calibration of Eberline Teletector'
, HPI-5.215 Use of Victoreen 740F Cutie Pie HPI 5.216 Calibration of Victoreen 740F Cutie Pie HPI 5.217 ~ Use of Eberline PNR Portable Neutron Rem Counter HPI 5.218 - Calibration' of Eberline PNR Portable Neutron aan Counter HPI 5.219 Use of Eberline h14 HPI 5.220 Calibration.of 'Eberline h14 HPI 5.221 Um of Eberline PAC-4S HPI 5.~222 Falihration of Eberline PAC-4S
-HPI 5.227 Use of GA-2T Ganma Alarm
.HPI 5.228 ralihratim of GA-2T Ganma Alarm .
HPI 5.229 Use of Victoreen R-Meter HPI 5.230 Calibraticn of Victoreen Mockl Condenser
'R' Meter.
HPI 5.231 - Use of Eberline E-530 Porta'ne Geiger Counter HPI 5.232- Calibration of Eberline E-!,30 Portable Geiger Counter .
HPI 5.233 Use of Eberline RAS-1 Po.'.able Air Sanpler
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- Calibration of Eberl'ine RAS-1 Portable Air m -- .
-HPI -5.234?
Supler HPI . - 5.235 Use of Dosimeter Chargers ,
.HPI '5'.236
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= Use of Eberline AMS-2 CAM i HPI 5.237: , Calibration of Eberline AMS-2 CAM
'HPI 5.238 Use 'of DNC AM-2A CAM "
HPI 5.239 Calibration of DNC M 2A CAM
'HPI J5.240 Um of INC AM-2B CAM HPI-' 5.241 calihration of !@C AM-2B CAM HPI 15.242 Use of SAM-2/RD-22 HPI 5.243 Calibraticn of SAM-2/IO-22 HPI 5.244 Use of Triton -(JLI) 955B HPI 5.245 Calibration of Triton '(JLI) 55B y; HPI 5.246 Um of Triton 1055B-HPI 5.247 Calibration of Triton 1055B
.HPI 5.248 Um of BC-4 HPI 5.249 calibration of BC-41
' HPI 5.251 Calibration of SPA-3 and MS-2 HPI 5.253 Calibration of PCC-llT and DS-2
-HPI 5.254 Calibration of Standard Radiation Sources HPI 5.257 Um of DuPont 4000A lapel Air Sanpler HPI 5.259. Um of the NMC AM-331F CAM HPI '5.260 Calibration of the INC AM-33IF CAM HPIE5.263 Use of SAC-4 HPI 5.264 Calibration of SAC-4 HPI 5.265 Establishing Reference Parameters for Model 1000 Calibrator--
HPI 5.267 Um of the P&7 Micro R/Hr Meter HPI 5.268 Calibration of the PIN--7 Micro R/Hr Meter HPI 5.269 Um of Eberline Bl>4A -
- HPI 5.270 Calibration of the Eberline BD-4A-HPI .5.271 Um of Eberline 14n-16/RD-17A HPI 5.272 Calibration of Eberline RM-16/RD-17A
.HPI 5.275 Use of Eberline h16/HP-200 HPI 5.276 Calibration of Eberline M16/HP-200 HPI 5.277 Um of the AM-2 Ganna Alarm HPI 5.278 ralibration of the AM-2 Gamna Alarm HPI 5.280 calibration Victoreen Label Sanpler Model 08-430 HPI 5.281 Calibration of the "Siersat" Personal Air Sanpler HPI. 5.282 Calibration of Sipin Iabel Sanpler HPI 5.283 Use of Eberline R07-BM HPI 5.284 Calibration of Eberline R07-BM HPI 5.285 Use of the Eberline Model E-530N Portable Geiger County with HP-200 Remote Probe HPI 5.286 . Calibration of the Eberline ledel E530N Portable Geiger County with HP-200 Remote Probe HPI 5.287 Use of Radeco HD-28 Im-Vol i.
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ATTACHMENT 1 'IO APPENDIX B INDEX OF CINSnTJTATED PROCEDURES HPI 5.290 Calibration of Xetex Digital Dosimeters, bbdels 409A, 415A, and 415A Modified HPI 5.291 Use of GP-4 Air Monitor HPI 5.292 Calibration of GP-4 Air Monitor HPI 5.295 Use of Siersat, Victoreen & Sipin Personnel Air Sanplers HPI 5.296 O p ration of Gilian Model HFS113 Iapel Air Sanpler HPI 5.297 Calibration of Gilian bbdel HFS113 Iapel Air Sanpler HPI 5.2102 Use of Radiation }bnitor }bdel PI@i llOC HPI 5.2103 Use of Triton bbdel 111 HPI 5.2107 Use of the Eberline E-140 Count Fate Meter HPI 5.2108 ('alihration of the Eberline E-140 County Fate Meter HPI 5.2127 Use of the T.A. CP-NU High Range Underwater Meter HPI 5.2128 Calibration of the T.A. CP-bU High Range Underwater Meter HPI 5.2139 Use of the Indlum Model-5 Gi Meter HPI 5.2140 Calibration of the Indlum Model-5 bbter EHS 3.701 Radiation Protection Counting Bocm Standard Practices EHS 3.705 Use of PCC-llT/DS-2 Piveartional Cbunter EHS 3.706 Use of Baird AtcInic Polyspec Scaler and SSC-3 AutcInatic Planchet Changer HIS 3.707 Use of MS-2/ SPA-3 Single Channel Scintillation Counting System EHS 3.710 Use of Xetex Digital Dosimeters, Models 409A, 415A and 415A Modified EHS 3.801 Operation of the Eberline bbdel 1000 Calibrator EHS 3.806 Calibration of the Baird Atadc Polyspec Research Spectrmeter and SSC-3/SSC04 Solid Sanple Changer Radioactive Material Control HPP 6.3 Inventory and leak testing of sealed sources HPP 6.5 Use of Calibration sources HPP 6.6 Control of Radioactive material HPI 6.4.3 Contamination Injury c EHS 3.356 Personnel Decontamination Protective Equignent HPP 7.1 Protective clothing specifications, use and maintenance
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. ATDCINENT 1 'IU APPHOIX B I!OEX OF.CXNinr.Tr%TED PROCEDURES Training Radiation Fici.cction Training HPP 8.1'-
. Job Specific Procedures
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EHS 3.401 Contaminated underwater diving. operations-
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HIS 3.402 Radiological oontrols for_Radi @ @ y i
- HIS 3.403- Steam Generator G annel Head Entry
-HIS '4.700 Hi&S Support for Receipt, Solidification and shipnent of resin fran the~ spent resin storage tank :(BWST)
His 8.000 Installation of 'Denporary Shielding HIS .10.201 Receipt of New Fuel EHS 13.010 Disposal of high level waste in Unit #2' Baling Station HIS ' 13.030 Receipt of Solidification of Evaporator-Bottoms HPP 10.2 Reports to the NRC of Incidents Involving IJoensed Material HPP 10.3 Routine reports to the NRC covering personnel HPP 10.4 Reports to individuals HPI. 10.11 Scheduling of-H.P. Work Coverage HPI '10.12 Radiatim Exposure Records HPI 10.13 Instrunent calibration records HPI 10.14 Radiation, contamination'and airborne survey records HIS 1.300 Hi&S Records Administration:
DIS 2.006 Dissemination of Information Relative to Environmental Health and Safety Procedures HIS 2.0101 DI&S Procedure Preparation ~, Revisions and Controlled Distribution -
HIS 3.003 Radiation Protection Section Duties and Responsibilities Respiratory Protection Program HPP 11.1 Respiratory Frei.cction Program HPI 11.10 Bespiratory Fwi.cction Training Program HPI 11.13. Evaluation of Hazards, selection and use' of -
respiratory protection devices ..
HPI 11.14. Use of self cTitained breathing apparatus and supplied airline respiratcrs HPI 11.15 Maintenance and repair of respiratory '
protection devices HPI: 11.16 Bespiratory Protection Training Program for Air Purifying Respirators
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ATDONENT 13D APPDOIX B
- HOEK T OCNSnr.TTRTED P10CEDURES IDI 11.17 Deue1Laidnation, sanitizirg, cleaning 'and '
surveying respiratory protection devices.
-HP1 '11.23 Um'of Respiratory Fr6uicticn Devices for Ehergency Conditions ._ . .
HPI 11.24 Bespiratory Program Inspections and Quality Assurance HPI 11.25 Use 'of the 0127 DOP PersL.uia:ter' for Testing HPI 11.26 Operation and calibraticn of 3DA 50 AEROSOL Test Booth EHS 3.651 .Bespirator Seal Booth Testing 1
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' APPENDIX C RADIATION PROTECTION OVERSIGHT COMMITTEE CHARTER-1.0 PURPOSE s
To describe the Radiation Protection Oversight t
Committee, includingLthe Committee (me'bership, m authority '
and conduct of' reviews.-
2.0 SCOPE The Committee monitors and reports on the effectiveness and quality of the Indian Point Station' Radiation Protection Procram.
-3.0 AUTHORITY The Committee shall report to and-advise the Vice President, Nuclear Power. The Committee functions'will begin upon review and approval of this charter and the committee membership by the NRC Regional Administrator -
Region One.
4.0 -TERM The Committee shall function at least until the completion of the action plan, and the submittal'and acceptance by the Rogional Administrator, Region One, of a
- final report .which summarizes progrn. ;mprovements and.
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-APPENDIX C
? RADIATION' PROTECTION OVERSIGHT-COMMITTEE CHARTEh
. details' plans;to maintain thh effectiveness of the program,J at :which : time the l Committee' may :be dis: ndn6 :. , ,
the direction;of'theLVice-President,; Nuclear ~ Power. ,
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The Committee shall be composed of at11 east three (3) but not more than-five (5) individuals, each of whom are qualified in examining various aspects of;a Commercial Power Reactor Radiation Protection Program.-
All members of the Committee shall_be independent of the station Environmental Health & Safety Organization. The-Vice President,' Nuclear Power will select the chairman who will appoint a secretary for the Committee. 'The-Vice President, Nuclear Power shall appoint all Committee members, alternate members and-replacement >
members should a vacancy exist,-and_shall-provide the-identity and' qualifications of each Committee member to the NRC Regional Administrator,? Region One.
6.0 MEETINGS Meetings-will be held monthly with a quorum consisting of at'least1three- (3) committee members.
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-RADIATION PROTECTION OVERSIGHT I COMMITTEE CHARTER?
7.0' CONDUCT OF REVIEWS ,
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The. Committee shall review-the conduct o'flthe radiation-
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protectionEprogramtinclu' ding;the; plans, schedules and jprocedures ,for: upgra' ding the program; The Committee"
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shall~ assign an indi.vidual-independent of;the radiation 4 -
,- protectioriz organization and the Committeei o -perform- t surveillance of the'. day-to-day, radiation protection:
activities,lev'aluata'thefeffectiveness of the radiation protection and contractor staff, -sample worker
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compliance'with. radiation protection rules and
. practices, andiadvise the Vice President,.. Nuclear Power regarding-the conduct of the radiation-protection
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> 8.0 ' REPORTS' _
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7.1 A monthly report shall be prepared by the Committee.
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i and submitt,ed'to-the Vice President,- Nuclear
~
Power, wi.th' a copyi otthe USNRC' Regional
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- s- Administrator,. Region One. .The monthly report..
q shall documeiit the Committee's. findings concerning-
[. ,the effectiveness of the radiation protection-F program. Copies of-the monthly report shall also be
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o Committee Members
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.Pago 4.of 4 APPENDIX C RADIATION PROTECTION OVERSIGHT COMMITTEE CHARTER Executive Vice' President, Central Operations Chairman, Nuclear Facilities Safety Committee General Managers ; Nuclear, Power 4
J
5.
APPENDIX D
- . RADIATION PIUfECTION CVERSIGfr CDNI'ITEE MDEERS AND QUALIFICATIONS a
MEMBERS: Charles Boyd Meinhold
'Ihcrnas A. Peterson Joyce P. Davis ALTERNATES: William E. Graber Desnond W. Chan QUALIFICATICNS: See attached resumes.
(
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- J.
GENERAL PHYSICS CORPORATION RESUME JOYCE P. DRVIS Education Massachusetts Institute of Technology S.B. (Physics)
University of Rochester, Dept. of Radiation M.S. (Radiation Biology, Medical School -
Biology)-
New York University, Institute of Environ-mental Medicine; and Graduate School of Engineering, Nuclear Engineering Dept.
-(Doctoral Program) 33 credits Fordham University, School of Law J.D. (Law)
New York University, School of Law, Graduate Division 2 courses Johns Hopkins University, Masters Program in Administration enrolled 9/84 Special Courses U.C.L.A. Special Course in Risk Assessnent for Energy Systems M.I.T. Summer Session Course of Decision Making Under Uncertainty M.I.T. Summer Session Courses on Nuclear Reactor Safety and Fast Reactor Safety ALI-ABA Courses on Nuclear and Environmental Law (Annual)
PLI Courses on Federal Water Pollution Control Act, Nuclear Litigation, Toxic, etc.
Short Courses to maintain H.P. Certification Academic Honors Fordham Law School; Dean's List, Am. Jur. Award in Environmental Law National Science Foundation Award AEC Radiological Physics Fellowship M.I.T., Dean's list and Scholarships Certifications and Honors
- Member of New York Bar, Admitted February 1972 l
Member of Maryland Bar, Admitted May 1982 Professional Engineer, Registered in New York State (since 1964) ,
Registered in Maryland (since 1981)
Certified Health Physicist, American Board of Health Physics (since 1966) l
, Experience l 1981 - Present General Physics Corperation Chief Licensing Engineer Ms. Davis is a health physicist, attorney and engineer who serves as Chief Licensing Engineer in the Engineering and Analysis Division. Ms. Davis provides consulting, super-vision and technical direction for company activities in
! the nuclear licensing, radiological health, environmental, I, and legal policy areas. Since November 1981 she has served as project manager for a series of policy related studies
lc
.s s
relating to the concept of "De.Minimis" dose carried out for the Edison Electric Institute (EEI) . She has advised the EEI on strategy for fostering the promulgation of regulatory policies by government agencies, and now serves-as a consultant - to EEI in furtherance of this work. . In 1984, she testified on this issue before NRC's Advisory Committee on Reactor Safeguards. This program involved consideration legal, policy, and technical aspects and their integration.
Starting in February 1983, Ms. Davis has also been involved in policy research and consulting for EEI on the isode of compensation for disease caused by exposure to radiation.
Ms. Davis also participated in other consulting projects for EEI relating to emergency planning, the license amendment process, and reform of the licensing process.
Ms. Davis serves as Project Manager for the Atomic Industrial Forum (AIF) study project to investigate the potential for exemption of specific streams of very low level ("de minimis") radioactive waste from NRC regulatory requirements. She is also a consultant to National Nuclear Corporation on work being carried our for the Electric Power Research Institute relating to segregation of very low level trash at the TVA's Sequoyah plant.
Ms. Davis is project manager for the NRC health physics inspector training project. She is involved in preparing and presenting instructional materials for re-training of NRC regional Health Physics inspectors.
Y Ms. Davis developed and serves as principal instructor for the General Physics courses on Nuclear Licensing. These courses provide a background, for licensing engineers and .
other interested personnel, in the Atomic Energy Act and other statutes, the NRC's regulatory program, and current and likely future regulatory developments. She has been an 7
instructor in licensing courses presented at General Physics Headquarters and at the facilities of several utilities. For Gulf States Utilities, she is developing a courst in licensing and law for health physics personnel, and for Sacramento Municipal Utility District, she participated in development of instructional materials for traing on- and off-site review Committee members.
As a lecturer in General Physics' Course in probabilistic risk assessment (PRA), Ms. Davis prepared and presented course material on the applicability of PRA techniques to l regulatory practices. She also lectures on legal and policy issues in GP courses on emergency planning.
She has prepared and submitted comments on proposed regula-
' tions, such as NRC's proposed safety goal policy, the proposed revisions to the 10CFR Part 20 regulations on
'~
.h radiation exposure control, EPA's proposed rehulations on radionuclide emissions under the Clean Air Act, and EPA's low level radioactive waste criteria development program.
Ms. Davis serves on a Task Group of the NCRP which is developing guidance on the maintenance of radiation records.
1972 - 1981 Consolidated Edison Company Senior Attorney, Environmental and Nuclear Regulatory Law Ms. Davis was responsible for the preparation and review of documents filed in regulatory proceedings, contracts, including' plant and fuel supply agreements; comments on legislative bills and proposed regulations; briefs; other legal filings; and legal research memoranda. She researched and wrote law review articles relating to nuclear regulatory and environmental law. She gained experience in NRC licensing, show-cause, enforcement and rulemaking proceedings, and proceedings before other federal and state agencies, and in the federal and State courts. Ms. Davis was secretary of the company Nuclear Facilities Safety Committee and chairman of its Radiation Safety Subcommittee. Ms. Davis was also company representative to the Nuclear Transportation Group, Utilities Nuclear Waste Management Group, and Nuclear Utilities Group on Enforcement.
1969 - 1971 S. M. Stoller Corporation
, Nuclear Fuel Analyst Ms. Davis participated in various projects including nuclear fuel cycle economics studies, evaluation of bids for fuel cycle services, studies related to nuclear licensing and regulatory developments, preparation of environmental impact reports, design of environmental monitoring programs, and evaluation of field data.
1957 - 1969 Burns and Roe, Inc.
Senior Engineer Ms. Davis' duties included studies or future energy resources and energy conversion methods, studies in nuclear, chemical and environmental safety, site selection studies for chemical and nuclear plarts, preparation of safety analysis reports for nuclear power plant licensing, radiation shielding design, health p'aysics, radwaste system engineering, evaluation of nuclear and fossil fuel costs, preparation of bid specifications and evaluations of bids for materials and services, design of laboratories and test facilitie", and systems analyses.
et'
?, #
r Etiucational Employment and Other Educational Activities:
Adiunct Associate Professor Manhattan College, Department of Radiological and Health Sciences (1976 -
1981)
Courses: Nuclear Reactor Science Environmental Radiation City College School of Engineering, CUNY, Civil Engineering Department (1974 - 1976)
- Courses: Radiological Health Engineering ,
Contracts and Specifications - Law for Engineers Er. '*.ron aental Law Lecturer - Health Physics Certification Courses - Columbia University (1972);
N.Y.C. Office of Radiation Control (1974) .
Course in Large Scale Power Generation, Columbia University, Graduate Engineering School (1977)
Environmental Law Course, Fordham Law School (1972 - 1976)
Nuclear Regulatory Policy - Towson State University, I)dustry Luncheon Program (1982)
Course on Liability and Risk in the Nuclear Industry - Sponsored by TMS (1984) 4 Leader of Seminar on Nuclear Licensing - Company Orientation Course (1977 .179)
PROFESSIONAL SOCIETIES American Bar Association Science and Technology Section Tort and Insurance Practice Section Energy Committee, Vice Chairman (1984 - )
American Nuclear Society - New York Section, Officer (1962 - 1970);
Shielding Division, Executive Comm. (1978 - 1982);
National Membership Committee (1964 - 1970); Ad Hoc Radiation Records Committee (1967);' Standards Subcommittee, ANS 6.7 - Standards for Radiation Zoning for Design of Nuclear Power Plants (1974 - 1977),
Representative to ANSI Committee on Radiation Standards (1982 - date);
Nuclear News Editorial Advisory Board (1976 - date)
F Health Physics Society State and Federal Legislation Committee (1984 - date) j -Subcommittee on 10CFR20 (1984 - )
Society-for Risk Analysis e
Association of The Bar of The City of New York,
[ Committee on Atomic Energy, Member (1975 - 1978)
! Environmental Law Committee, Member (1979 - 1981)
! New York State Bar Association, l
Special Committee on Environmental Law, Member (1975 - 1977)
Maryland State Bar Association Atomic Industrial Forum; Member, Environmental Steering Committee (1971 --
l-1981); Member, Subcommittee on Clean Air Act Amendments (1977 - 1981) l 4
. r*
s CONSULTANCIES U. S. Environmental Protection Agency - Science Advisory Board
- Ad Hoc Committee on Environmental Monitoring (1974)
- Environmental Radiation Exposure Advisory Committee (1973 - 1978)
Sub-Seabed Disposal Program - Sandia Laboratories
- Panel to Review Project Status Report (1983)
National Council on Radiation Protection and Measurements (NCRP) - Task Group on Maintenance of Radiation Records :
(1984 - )
PUBLICATIONS The "De Minimis" Concept: Where We Are Today, presented at joint ANS-HPS meeting session, New Orleans, Louisiana, June 1984.
"De Minimis": An Industry View, presented at the meeting of the Council of Radiation Control Program Directors, Des Moines, Iowa, May," 1984.
Paper on "De Minimis" Policy Issues, presented at Lloyds of London Press Symposium on Radiation and Energy, December 1983.
Orphan Waste: Will It Find a Home?, ANS Winter Meeting, October,1983 (Co-author with J. T. Montgomery) .
"De Minimis" Aspects of Reentry and Recovery, HPS Annual Meeting, June 1983 (Co-author with S. J. Harris and William C. Rhodes) . -
Potential Beneficial Impacts on Nuclear Reactor Licensees of a Regulatory Cut-Off Policy Based on I3t Minimis Radiation Dose Criteria, ANS Winter Meeting, November 1982 (co-author with K. Rebeck, K. Travis) .
Licensing, Regulation and Commitments; Identification for Change, NRMA Conference, September 1982.
The Concept of "De Minimis" Dose and its Applicability to a Regulatory Cut-Of f Policy, HPS Annual Meeting, June 1982 (co-author with S. J. Harris).
The Feasibility of a Regulatory Cut-Off Policy, AIF Environment Conference, October 1982.
Social Aspects of Regulating Waste Heat, Waste Heat Management Conference, May 1977 (Co-Author with V. dePass and C. L. Newman) .
The Permit Program of the Federal Water Pollution Control Act of 1971,
' Fordham Urban Law Journal, Vol. II, No. 2, Winter 1973-74 (Co-Author with Robert J. Glasser) . Reprinted in 6 Envir. L. Rev. - 1975, Sherrod, Ed.
The New Federal Water Pollution Control Act and Its Impact on Nuclear Power Plants, Nuclear Safety: Part I (May - June 1974), Part 2 (July -
August 1975) .
.h>
Environmental Factors in the Lirnsing of Nuclear Power Plants, Nuclear Safety, January 1973 and May 1973..
Taming the Technological Tyger - Licensing Nuclear Power Plants, Fordtym Urban Law Journal, Summer 1972 and Fall 1972 (Vol.1, Nos.1 & 2).
Nuclear Fuel Cost Calculations, (Co-Author with M. Zizza) IAEA MeetJ ne, on Nuclear Power Costs, London, October-1967.
The Future of Energy Conversion, (Co-Author with S. Baron) Consulting Engineer, June 1963.
\
, i-CENZRAL. DYNAMices l Sectric Best Division '
l arAcronNAtirSERWCES RESUME l
NAME DF_CAND_IDATE: Thomas A. Peterson l
EXPERIENCE:
Mr. Peterson has been employed at General Dynamics / Electric Boat Division for over 17 years. During this period, he has served in various engineering and management positions, as well as provided consultation to nuclear utilities in the areas of radiation protection, planning, maintenance, and operation.
As the Manager of Reactor Plant Services, Mr. Peterson's responsibilities 1
have ranged from overall business development and management of the l organization, through assignment as the acting Radiation Protection i
Manager at a large nuclear power station (0yster Creek - periodically during 1980-1981). He was selected as a representative on the Department of Energy funded Three Mlle Island Technical Assistance and Advisory Group (TAAG) for overall review of decontamination and defueling plans.
! Specific tasks accomplished by or under his direction while heading the i
Reactor Plant Services organization include: Assessment of several i
corporate and station radiation protection programs with associated recommandations and implementation of revised standards, development of equipment (e.g., zero discharge decontamination systems, specialized ventilation equipment, Post Accident Sampling Systems (P.A.S.S.),
contamination control products, and various training programs for i
utilities) to support the nuclear industry, audits of utility performance l
in areas of radiation protection, and outage management and planning.
Marketing and technical discussions have taken Mr. Peterson to France,
! Yugoslavia, Spain England South Africa and Korea as well as throughout the United States. He was asked in France to make an impromptu presentation in front of an international Radiation Protection conference on Three Mile Island. In addition, Mr. Peterson was requested in mid 1984 to act as interim General Manager of Environmental, Health and Safety at Con Ed's Indian Point II Nuclear Station until the permanent General Manager could be hired and brought on site.
As Chief and subsequently Manager of Radiological Engineering.
Mr. Peterson had overall responsibility for the technical aspects of the l
Division's Radiological Control program which serviced up to seven reactors per year, as well as responsibility for the Industrial RadiograpV Audit Group which assured HRC license compliance. Under his i
direction were over sixty engineers and technicians involved in developing j radiological controls and engineering techni contamination spread and radiation exposure, ques to the to monitor control / reduce environment, i
- Continued -
A L A RA .. . unu.,,e -a.w.a... .,,n.u. . m
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GD EB RUCTOR PLfY4T SERVICES 05 P.03 i BENERAL DYNAMICS :
Electdc Bent mdnion nuacrunanrsimstes i
{ THOMAS A. ptTERSON PAGE Z to provide dosimetry and radiation health services, to operate a radiation analysis laboratory facility, to oversee radiological aspects of waste
- handling, processing and ship-out, and to develop all operating procedures for the Radiological Controls department. Additionally, a program was training, and qualification of engineering personnel to beestab technical / management radiological events. representatives on-shift to assess and handle unusual 4
Throughout this period, Mr. peterson has also served as one (of two) primary individuals to assess and advise shipyard and Navy I management radiological amargencies, at the Emergency Coordination Centee in the handling of During General Dynamics / Electric Boat Division's work on the Shippinort LW8R Project, Mr. Peterson took a leadership role in developing tie '
- Radiological Controls Manual for Shippingport as well as in developi implementing rocedures for use on site. Threeghout the Shipping project, Mr. eterson provided technical support and periodic on por site l radiological assessment to assure compliance with regulatory requirements.
) EDUCATION:
BS in Nuclear Engineering from North Carolina State University (1967) 1 1
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.g Boston, Massachusetts - November 1,1934 f . Fisdir: Wife and five children
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' ,t/ n- , s 7., , 1972 prweent Brookhaven Nstional Laboratory y.. M( 2 r. Division Read EccD ' - Safety and Environmental Protection Division f,3ib,'*.v .
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i.f.[ t ., l 1957 - 1962 Operational Restth Physica for Biology .
N'y R and Medical Departments and
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present Tenured Sanior Health Physicist
. . . d ' .f.' 1974 - 1982 Senior Health Physicist p 'l'?.:
1970 Health Physicist rL *fg. ,1962 Associate Health Physicist
- f. ), -t iL958 Assistant Health Physicist tg ,. , 1957 Junior Health Physicist b
June 1957 Cuest Fellow
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$*' .' :. Dose Reassessesets in the Marshall Islands
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- ENL Lecturer - April 18, 1973 on " Development of Radiation Protection Q E .l. . ^ , ~ Standards, The More Things Change, The More They Stay w,o the Same'
- f81(and ERDA Special Assignments. 1980 - 1981
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t'.Npd advisory Fawl on Accelerator Radiation Safety for the National
.b,f Accelerator Latviratory and the Stanford Linear Accelerator 9Ar{t-l L '-
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Member, Task Group on Space and High-Energy Dosimetry 3Q{p.[+.,
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' fay.h;f member,1985 Program Committee j .-Q $ -
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Levels Task Force to Review NRC Recommendation on Occupational Exposure
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.dn.d.,d' Member, Esecutive Committee 1975-1978; 1980-1983
', pit ** l. Delegate to the Third, Fourth, Pif th and Sixth International Radiation
,g l *,9'#.P Protectice Association (IRPA) Congress Amamal Meeting Place Committee Q/4 ,g#'i. !E, V h r. Awards Committse jh;pp'$ l.Q..
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l ,;. CERNERAL, DYNAMIC]
Electric Bent DMsion atAcronnu.rsenwens RESUME NAME OF CANDIDATE: William E. Graber EXPERIENCE:
Mr. Graber has been employed at General Dynamics / Electric Boat Division for 19 years and has been associated with Radfological Control Operations for 17 of those years. Throughout his career, he has served in various radfological engineering and management positions and is currently Manager of the Radiological Control Department at Electric Boat Division.
In his current position, he is responsible for the Division's Radio-logical Control Program comprising engineering, training, operations, emergency planning and administrative personnel. This organization currently contains eighty-five professional and technical personnel.
Also, he has assisted Reactor Plant Services (RPS) in the development and presentation of the ALARA training program. He works with state and
- nuclear power plant representativer. in the coordination of radiation protection and evaluation technicus during radiological emergencies and is currently a member of the Gove.=nor of Connecticut's Independent Risk Assessment Team.
Mr. Graber's experience and expertise are recognized throughout the industry. He was assigned as senior site representative from Electric Boat Division at TMI for approximately 6 months commencing March 31,1979 and was responsible for providing rattological assistance during the emergency and early recovery phases. He served as a member of the GPU Corporate Generation Review Comittee TMI-2 and assisted in estab1GiTng The HeaDh Physics Technician Training program at TNI-2 He served as Manager of Radiological Engineering during an extended outage at Oyster Creek Huclear Generating Station for 6 months in 1981. In 1982, he provided management consultant services for 3 months at India _n _ Point Station, Unit 2 for Consolidated Edison. For 1 month during this period, he assumed the position of interim General Manager. Environmental Health and Safety and during 1984, served as the RPM for nearly 3 manths. Mr.
Graber prov,ided off-stte radiological control suaport for Electric Boat Division's previous contract at shippingport in i976 and performed audits, start-up assistance and training ass'istance for t1e Radfological control orgentration on-site.
He also directed a Radiological Control Retraining Team for six weeks in 1977 which provided a radiological control refresher course to Duquesne 1.ight Compenf Radiological Control Technicians.
- Continued -
ALARA . .a.nc.ou w.ea.m a. . awn.in
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,bu t.u Mr.H,,4LN PLHil biMV1Lt.b Us P,ul GENERAL DYNAMICS Bectric Root DMelon neacronnaursenwces WILLIAM E_. GR_AB_E_R_
Experience prior to being employed by Electric Boat includes three years at Shippingport Ato:alc Power Station from 1960 to 1963 working as a test engineer for Duquesne Light Compary. Mr. Graber's during that period involved procedure preparation, primary testing and assignments nutage support with concentration on radiological control projects.
Mr. Graber is thoroughly familiar with development and implementation of radiation protection and ALARA techniques. As Manager of Radiological Control Planning and Training he was responsible for radfological control training of all Division personnel, emergency planning and radiological control services for Division personnel at an off-site facility.
ACCHE01T_A_T_ ION _S_:
Professional Engineer - Ohio (currently licensed)
Pennsylvania (previously licensed)
Connecticut (previously licensed)
EDUCATI,0N:
BSCE - Virginia Military Institute M3A - University of New Haven Short Courses:
- U.S. Public Health Service ,
Radiological Health !
- Harvard School of Public Health l Radiological Emergencies
- FEMA-NRC Emergoney Planning
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GENERAL PHYSICS CORPORATION DESIDED W. CHAN n
Gy Manager, Health Physics Services EDUCATION Ph.D., Computational and Nuclear Physics, University of Lowell M.S., Nuclear Physics, University of Lowell B.S., Nuclear Physics University of Lowell 1983 Health Physics Society Summer School on Internal Radiation Dosimetry EXPERIENG General Physics Corporation 1982 - Present Dr. Chan is responsible for the administration and development of health physics and advanced health physics and advanced nuclear physics programs and other health physics support activities. Dr. Chan also serves as a technical consultant in emergency preparedness, internal dosimetry, environmental monitoring, dosimetry tracking, radwaste management, countroom instrumentation, ALARA engineering, computer sof tware support, mathematical modeling, nuclear data analysis, training program development, and health physics technician support services.
Dr. Chan also acted as Project Manager for advanced instruction and training material development in health physics for radiation protection and chemistry
, technicians for Iowa Electric Light and Power Company,
! Niagara Mohawk Power Corporation, Georgia Power Company, Gulf State Utilities, Southern California Edison Company, Public Services Company of Colorado, Texas Utilities Generating Company, and Toledo Edison
! Company. Representative projects include l e Program Develognent As Project Supervisor, Dr. Chan is coordinating and developing an Advanced Health Physics Training Program for NRC regional health physics inspectors.
e Environmental Study Project Dr. Chan is one of the principal investigators in evaluating the benefits, risks, and costs of establishing regulatory cutoff (De Minimis) levels for radioactive waste streams for nuclear power plants for Atomic Industrial Forum, Inc.
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GENERAL PHYSICS CORPORATION e On-site Instruction Conducted classes in health physics and radiation protection for Philadelphia Electric Company, Niagara Mohawk Power Corporation, Iowa Electric
[ Light and Power Company, and Georgia Power Company.
f e Project Coordination Acted as Project Manager for instruction and
- development of advanced training materials in 1 health physics for radiation protection and t
chemistry technicians for Iowa Electric Light and Power Company, Niagara Mohawk Power Corporation, ;
Georgia Power Company, Gulf State Utilities, Southern California Edison Company, Public Services Company of Colorado, and Texas Utilities Generating Company.
i l e Materials Development Developed training materials for a computer-based l instructional system in nuclear physics, health !
physics, and emergency planning for Toledo Edison l Company. Developed eight advanced health physics training courses for Southern California Edison and l
I Nebraska Public Power District.
e Program Development Developing training step program (with job / task l
analysis), qualification program, training implementation document, and on-the-job training pecgrams for Niagara Mohawk Power Corporation.
l 1976 - 1981 University of Lowell Dr. Chan oonducted a variety of research projects in nuclear physics * " ** "
f3 Th and scattering for $3b**intheframeworkof U
coupled channel collective model calculations and unified nuclear reaction mechanisms. This involved the developnent of computational methods, mathematical modeling, and numerical analysis. Dr. Chan was responsible for developing large scale computer codes for nuclear scattering data acquisition. Prior to this, Dr. Chan conducted research on the application of group theory to nuclear structure study, specialized in unitary group, special unitary group l and sympletic group, and their applications to nuclear i
shell model calculations. Dr. Chan was also respon-i sible for physics laboratory instructions, lecturing in freshman and sophomore physics, instrumentation l
design, and experimental testing.
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O GENERAL PHYSICS CORPORATION PIDF1tSSIONAL Member, American Physical Society AFFILIATIONS Member, National Honor Physics Society (Sigma Pi Sigma)
Member, Health Physics Society PUBLICATIONS " Classification of Nuclear Energy Levels for A=13-8 Odd-Mass and Even-Mass Nuclei in the SU(3) Group Scheme, and Extension to Symplectic-Group Theory,"
Bulletin of the American Physical Society, 24(5), 760, Paper G4,1979, Coauthor with E. Sheldon.
" Fast Neutron Inelastic Scattering on Th and 38 U,"
XIII Polish Summer School in Nuclear Physics, Mikolajki, Poland,1980, Coauthor with L. E. Beghian, E. Sheldon, et al.
" Evaluation of (n,n') Scattering Cross Sectiong3grom 0.8b38 U in 'e Standard' and er Higher Collective Bands of Th Formalism," Proceedings of a Specialists' Meeting on Fast Neutron Scattering on Actinide Nuclei, OECD/OCDE, Paris, November 1981, pp.
174-196, Coauthor with E. Sheldon.
" Analyses of Fast Neutron Inelaggjc Scattgggng to Higher (Vibrational) Levels of Th and U*I.
Standard Formalism," Physical Review, C26, 93, September 1982, Coauthor with J. J. Egan, et al.
" Analyses of Fast Neutron Inelaggjc Scattf54"9 '"
Higher (Vibrational) Levels of Th and U:II.
Intrinsic Unified Formalism," Physical Review, C26, 43, September 1982, Coauthor with E. Sheldon.
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