ML20087J556
| ML20087J556 | |
| Person / Time | |
|---|---|
| Site: | Shoreham File:Long Island Lighting Company icon.png |
| Issue date: | 03/21/1984 |
| From: | Finlayson F, George Minor, Radford E SUFFOLK COUNTY, NY |
| To: | |
| Shared Package | |
| ML20087J534 | List: |
| References | |
| OL-3, NUDOCS 8403220305 | |
| Download: ML20087J556 (33) | |
Text
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. C4 d4?ag UNITED STATES OF AMERICA l/ ., ' O .*/g NUCLEAR REGULATORY COMMISSION 'r -
Before the Atomic Safety and Licensing Board '
)
In the Matter of )
)
LONG ISLAND LIGHTING COMPANY ) Docket No. 50-322-OL-3
) (Emergency Planning)
(Shoreham Nuclear Power Station, )
Unit 1) )
)
)
TESTIMONY OF FRED C. FINLAYSON, GREGORY C. MINOR AND EDWARD P. RADFORD ON BEHALF OF SUFFOLK COUNTY REGARDING CONTENTION 61 Q. Please state your names and positions.
A. My name is Fred C. Finlayson. I am a Principal Asso-ciate of F.C. Finlayson & Associates, 12844 East Cuesta St.,
Cerritos, Claifornia.- A copy of my professional qualifications is attached to this testimony as Attachment 1.
A. My name is Gregory C. Minor. I am a founder and vice-president of MHB Technical Associates, 1723 Hamilton Ave-nue, San Jose, California. A copy of my professional qualifi-cations is attached to this testimony _as Attachment 2.
A. Jur name is Dr. Edward P. Radford,.and I am Professor of Epidemiology at University of Pittsburgh. I received my i
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l M.D. degree from the Harvard Medical School in 1946. My
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specialty is the subject of the health effects of ionizing ra-diation, which I have taught at the Harvard University School j of Public Health, the University of Cincinnati School of Medi-cine, Johns Hopkins University School of Hygiene and Public
- Health, and the University of Pittsburgh. I am presently on leave of absence from Pittsburgh in order to conduct research in Japan on new data that have been compiled ragarding the t
health effects of the atomic explosions in Japan in 1945. My professional qualifications and background are set forth in my curriculum vita which is Attachment 3 to this testimony.
O. What is the purpose of this testimony?
t A. (Finlayson, Minor, Radford) The purpose of this-tes-l timony is to address portions of Emergency Planning Contention
, 61. .
!; . O. Many subparts of Contention 61 refer to " shielding factors." What is a shielding factor?
l A. (Finlayson, Minor) A shielding factor is the ratio-of the dose a person 1would receive while in a shelter, comparad to the. dose he would receive if shelter were not taken. For example, a shielding factor of 0.2 means that a person'in a
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e shelter would receive 20% of the dose he would have received if he had not taken shelter; a shelter with a shielding factor of 0.2 results in an 80 percent dose reduction. In Table 3.6.5 of the LILCO Plan, LILCO identifies shielding factors from a cloud dose for various structures in the EPZ as follows:
Structure Shielding Factor Wood frame without basement 0.9 Wood frame with basement 0.6 Masonry house without basement 0.6 Masonry house with basement 0.4 Large office or industrial building 0.2 Vehicles 1.0 Q. Subpart G of Contention 61 states:
G. Many other homes in the EPZ, even if they provide more shielding than a wood house, will only reduce doses about 50 percent. In a severe accident, a 50-percent dose reduction will still result in health-threatening doses.
What kind of homes in the EPZ will reduce doses by about 50 percent?
A. (Finlayson, Minor) A shielding factor of approxi-mately 0.5.--
that is, a 50 percent dose reduction -- approxi-mates the average shielding available from houses that are constructed of masonry with and without basements.
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O. In a severe accident at the Shoreham plant, assuming a 50 percent dose reduction is achieved by sheltering, will health-threatening doses result to people within the EPZ?
A. (Finlayson, Minor) Yes. Assuming a 50 percent dose reduction, 8 percent of severe accidents at Shoreham involving a release of radioactive material will result in a person with-in ten miles of the plant receiving a dose exceeding 30 rems.
See Table 1 which is Attachment 4 hereto. Five percent of those accidents will result in a person within two miles of the plant receiving a dose exceeding 100 rems; one percent of those accidents will result in a person within five miles of the plant receiving a dose exceeding 100 rems.
A. (Radford) A 30 rem dose is considered the threshold of early injuries. People who receive 30 rem doses will proba-bly not experience any acute effects (i.e., deaths or injuries occurring within 60 days after exposure), but.their lifetime chances of developing cancer will increase by about 21 percent over the normal rate. Doses above 30 rem are more likely to cause early acute effects and result in even greater increases in the chances of developing cancer.
Q. Subpart H of Contention 61 states:
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i H. According to LILCO, the average shielding factor available in the EPZ is 0.7, which means that, on the average, those who follow a sheltering recommenda-tion will nonetheless receive 70 percent of the dose they would receive from the plume if they were outside the shelter.
Where does LILCO identify 0.7 as the average shielding factor available in the EPZ?
4 A. (Finlayson, Minor) LILCO states in OPIP 3.6.1 (page 36)1/ that the average shielding factor in the EPZ is 0.7.
This means that on the average, a person taking shelter in the EPZ would experience a 30 percent reduction in the dose he or she would receive if he or she did not shelter.
Q. Subpart I of Contention 61 states:
I. The cloud doses resulting from a release of radioactive fission products from the Shoreham plant could be so substantial that even taking into account the 30 percent average dose reduction pro-vided by shelter in the EPZ, persons who follow a sheltering recommendation could still receive doses that would cause ad-verse health effects.
In a severe accident at Shoreham, assuming a 30 percent dose
-1/ In Revisions 0, 1 and 2 of OPIP 3.6.1, Attachment 7 states that "[t]he average shielding factor from surveys taken in the EPZ was found to be 0.7.' This attachment was elimi-nated in Revision 3, but the 0.7 average shielding factor is still identified for use in performing the calculations described in OPIP 3.6.1.
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. o reduction ia achieved by sheltering, will persons in the EPZ who follow a sheltering recommendation receive doses that could cause adverse health effects?
A. (Finlayson, Minor) Yes. In a severe accident at Shoreham involving the release of radioactive material, and as-suming LILCO's average cloud shielding factor of 0.7 and a 0.2
< ground dose shielding factor, 12 percent of those accidents will result in persons within the 10 mile EPZ receiving a dose exceeding 30 rems. (See Table 1) Nine percent of those accidents will result in persons within two miles of the plant receiving a 100 rem dose. One percent of those accidents will result in persons within nine miles of the plant receiving a dose exceeding 100 rems. For those people in the EPZ who take shelter in wood frame houses without basements, only a 10 percent cloud dose reduction will be available. In a severe accident at Shoreham involving a release of radioactive material, and assuming a 60 percent reduction in ground dose, 15 percent of those accidents will result in a dose of 30 rems to persons in wood houses without basements located within ten miles of the plant.
Five percent will result in a 100 rem dose to persons in such houses located within two miles of the plant; one percent will result in a 100 rem dose to persons in wood houses without basements located within ten miles of the plant.
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Q. In light of the average shielding factor in the EPZ identified by LILCO, do you agree with the portion of Conten-tion 61 which alleges that assuming people were willing and able to follow a sheltering recommendation, there is no assur-ance that taking such action would provide the dose savings necessary to prevent persons from receiving health-threatening radiation doses?
A. (Finlayson, Minor, Radford). Yes. Sheltering, if implemented, does provide for a reduction in dose compared to the situation without sheltering and shielding factors are used to express this reduction.
Sheltering can, in many circumstances, reduce doses to the point where they are not im-mediately life-threatening. However, assuming the average shielding factor identified by LILCO in the Shoreham EPZ, in the event of a severe accident-there is no assurance that the dose savings from sheltering would be significant enough to re-duce doses to levels below those which are threatening to health.
(Finlayson, Minor) For example, in the area within two miles of the plant, the type of sheltering has little effect on the chances of receiving a health-threatening dose of 30 rems.
Even at a distance of ten miles from the plant, the chances of
. o receiving a dose exceeding 30 rems, assuming sheltering is implemented, range from eight to fifteen percent; with LILCO's average shielding factor sheltering results in a twelve percent chance of such a dose. In addition, there is a five to twenty percent chance of people within two miles of the plant receiving a 100 rem dose, depending on what type of shelter is available, assuming a sheltering recommendation is followed.
O. Subpart B of Contention 61 states:
Persons who are traveling in their cars or other vehicles at the time of a sheltering recommendation may not be able to reach shelter fast enough to obtain any protection from a release of radioactive fission products.
tially no protectionVehicles from radioactiveoffer essen-doses.
If persons are in vehicles at the time of a sheltering recom-mendation, and are unable to reach shelter before passage of the radioactive plume, what protection from radioactive doses will they receive?
A. (Finlayson, Minor) In Table 3.6.5 of the Plan, LILCO identifies vehicles as having a shielding factor of 1.0, which is the same as providing no effective cloud shielding. Thus, assuming a severe accident at Shoreham involving a release of radiation, people who are in cars or other vehicles within ten
7 miles of the plant for about two hours would have a 15 to 35
! Percent chance of receiving a dose in excess of 30 rems.
i Q. Does that conclude your testimony?
- A. (Finlayson, Minor, Radford) Yes.
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ATTACHMENT 1 i
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I FRED C. FINLAYSON REACTOR SAFETY ASSESSMENT
, , PRINCIPAL ASSOCIATE NUCLEAR POWER PLANT F.C. FINLAYSON & ASSOCIATES PROBABILISTIC RISK 12844 E. CUESTA STREET ASSESSMENT CERRITOS, CALIFORNIA 90701 REACTOR ACCIDENT CONSEQUENCE ASSESSMENT ENERGY SYSTEMS DESIGN AND ANALYSIS EACKGROUND
SUMMARY
Dr. Finlayson has extensive experience in the field of assessment of the safety, reliability and risks of nuclear power reactors. He has recently conducted an evaluation of potential risks and consequences of severe reactor accidents in the Shoreham Nuclear Power Plant. He supported an avaluar. ion of the impact and application of BWR suppres-sion pool scrubbing capabilities on emergency planning as part of an evaluation of a probabilistic risk assessment of General Electric's DNR-6, standardized nuclear power plant design. He also provided technical direction of the probabilistic risk analyses conducted for the State of California's evaluation of Emergency Planning Zone requirements. He was the principal investigator and program manager of the NRC's first investigation of the adequacy of human engineering in' nuclear power plant control rooms under severe accident conditions.
He is currently conducting an investigation for the NRC of the feasi-bility of instituting a voluntary non-punitive reporting system for human errors in nuclear power plants. Dr. Finlayson was also the manager of The Aerospace Corporation program that provided systems integration and technical direction of the California Energy Commis-
. sion's study of underground nuclear power plant designs, costs, and their relative effectiveness in reducing the consequences of extremely severe accidents. -
Dr. Finlayson has been a consultant to the NRC, U.S. General Acc~ount-ing Office, and other federal and state governmental agencies on nuclear safety related issues such as site-specific risk analyses, human engineering, large-scale reactor ~ test program design and effec-tiveness,-sabotage, waste transport hazards, and a wide variety of other related topics. He is currently a member of the Amerie n Physical Society's Review Committee for evaluation of the status and adequacy of sourcs terms for product releases from severe nuclear power plant, accidents. He served on several review committees for the "PRA Procedures'Gaide" (NUREG/CR-2300) for probabilistic risk assessments for-nuclear power plants. He was a member of the NRC's 1980/1981 LOFT Special Review Group and was consultant to the NRC's Rogovin Special Inquiry Group in their investigation of human engi-neering factors associated with the Three Mile Island incident. He has performed several assessments of the design and effectiveness of ECCS for LWRs, including the analysis which he prepared as a member of the American Physica~l Society's Review Committee (1975) on Light Water Reactor Safety. 1 l
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EDUCATION BS Mechanical Engineering, Brigham Young University, 1958 PhD Mechanical Engineering, Northwestern University, 1964 EXPERIENCE The Aerospace Corporation, Los Angeles, CA (1972-Present). Dr.
Finlayson is currently Manager, Nuclear Systems and Safety, Energy and l'sscurces Division. In this capacity, he is responsible for programs dealing with nuclear power plant safety, reliability and risk assessment. He directed the systems engineering and technical management efforts for the recent California study of statewide nuclear power plant risks and associated emergency planning zone requirements; and directed a similar program for a major study of underground nuclear power plant siting. He was also the program manager for an assessment of the impact of plutonium fuel cycle safeguards, and an evaluation of nuclear control room human engi-neering. He has also managed and performed systems analyses of industrial process heat applications of geothermal power as well as conceptual design and evaluation studies of hybrid solar / geothermal power systems. Studies.of local and national energy consumption patterns and the effectiveness of selected conservation measures
~~
have also been performed under his direction.
Physics International Company, San Leandro, CA (1968-1972). Dr.
Finlayson directed and conducted research in strategic and tactical.
weapon systems survivability / vulnerability, numerical analyses of the propagation of strong shocks in geologic media and structural materials, and structure-medium interactions.
The Aerospace Corporation, Los Angeles, CA (1964-1568). Dr. Finlayson conducted investigations of ground based system survivability to all relevant effects of nuclear weapons.
The General American Transportation Corporation, Chicago, IL (1960-1964).
Dr. Finlayson conducted research on the interactions of strong shocks in air and earth materials with above-ground and buried structures.
PROFESSIONAL ACTIVITIES Dr. Finlayson is a registered Professional Nuclear Engines.- in the State of California. He is a member of the American Nuclear. Society-and the Institute of Electrical and Electronics Engineers (Reliability Scciety).
PUBLICATIONS
" Closures for Hardened Protective Hangers", AFSWC-TDR-62-77, MRD Division of General American Transport Corporation, Niles,. Illinois, August 1962.
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" Air Blast Load Reduction on Above Ground Structures", Proceedings of the 32nd Symposium on Shock, vibration, and Associated Environments, Part'II, Bulletin.No. 32, Office of the Director of Defense Research and Engineering, November 1963.
" Design Procedures for Shock Isolation Systems of Underground Protective Structures, Volume II,1 Structure Interior Motions Due to Directly Transmitted Ground Shock", AFWL RTD-TRD-63-3096, Vol. II, General American Transportation Corporation, Niles, Illinois, December 1965.
(Coauthor)..
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" Wave Interaction of a Viscoelastic Medium with an Elastic Cylindrical
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Shell"', Journal of. the Acoustical Society of America, Vol. 40, No. 6, pp. 1496-1500, December 1966. (Coauthor).
" System Vulnerabilities to Craters-and Ejecta", (U) Proceedings of the
. Symposium on" Nuclear Craters and Ejecta, Vol. I, SAMSO-TR-65~107, November 1967 'S-RD).
ProceedinrJs of the Symposium on Nuclear Cra' N and Ejecta, (U) Vol. I and II, SAMSO-TRm68-107', November 1957 ?^ , . . (Coeditor).
"A Theoretical and Experimental Study of Detonations in Connection with Decoupling," DASA 12505,' Physics International Company, San Leandro, California, November 1969. (Coauthor).
Deep Based Sanguine System Survivability" (U) PIFR-327, Physics International Company, San:Leandro, California, August 1971 (S-RD).
(Coas.tthor) . <
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" Estimated SPRINT II Ground Motions" PITR 350-4,_ Physic International-
, Comparyy,wSan Leandro, California, March 1972 (S-3) . '(Coauthor) .
" Relative'5ffectivedess of Energy; Conservation Measures Taken in the Pacific Northwest,?' Aerospace Report No, ATR-74(8166)-1, January 1974.
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" Emergency Core Cooling Systens for Light Water Reactors," EQL Report No. 9, California Institutt>ofl Technology, Environmental Quality
.w Laboratory, May /1975. ,, . . .
" Report to the Americ_an Physical Socie ty'by the Study Group on Light-Water Reactor Safety, Reviews o FMcdern Physics, Volume 47, Supplement No. 1, Summer 1975-.
(Coauthor).r' ,
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" Integrated Solar / Geothermal Power Systems Conceptual Design and
- Analysis", ATR -75 (7512)-1,5 July'.fl975. . (Ceauth'or) . -
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" Nuclear Reactor Safety: . ) View fiort th' e -Outside", Bulletin of . the s- & Atomic Scientists, September 1975J pp. 20-25. -
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e^ " Review of)the NRC/ERDA Loss-of-Fluid Test Facility", 19 November.
D75, "pp.67-108 of Enclosure Ahito This Country's Most Exnensive Light Water Reactor' Safety' Facility, GAO documentrRED-76-68 A,3 May-26, 1976.
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] " Effectiveness of Safeguards Program for the LWR Plutonium Recycling
{ Industry", ATR-76 (6879)-1, April 1976. (Coauthor) .
" Poor Management of a Nuclear Light Water Reactor Safety Project,"
, GAO document EMD-76-4, 25 August 1976. (Coauthor). Documentation of review of ERDA/NRC Plenum Fill Experiment Program.
" Transportation Risks for New and Spent Fuels and Radioactive Wastes with Respect to Road Accident Hazards and Purposeful Diversion", Direct Testimony, SDG&E Sundesert NOI Hearings, 30 November 1976.
" Technical Brief - Issues of Record Related to Plans for Protection Against Sabotage and Diversion of Nuclear Materials for the Sundesert Nuclear Power Plant", SDG&E Sundesert NOI Proceedings, 29 December 1976.
" Technical Brief - Issues of Record Related to Transportation Risks for Neu and Spent Reactor Fuels and Radioactive Waste", SDG&E Sundesert NOI Proceedings, 30 December 1976.
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" Control Room Human Engineering Influences on Operator Performance",
l Proceedinos of Topical Meetina on Thermal Reactor Safetv. CONF-770708, Sun Valley, Idaho, 31 July - 4 August 1977.
" Systems Management Support for ERCDC Study of Undergrounding and Berm Containment: Interim Report, Preliminary Program Assessment and Follow- '
r on Program Development", ATR-77(7652-01)-1, August 1977. (Coauthor) .
Review and Critique of Draft " Report to the U.S. Congress on NRC's Plans for Research Directed Toward the Improvement of Light-Water Nuclear Power Plant Safety", Letter report, 22 February 1978.
l i " Evaluation of the-Feasibility, Economic Impact, and Effectiveness of
, Underground Nuclear Power Plants - Final Technical Report", ATR-78 (7652-14)-1, May 1978. (Coauthor) .
" Underground Siting of Nuclear Power Reactors - An Analysis of the California Energy Commission Study", Transactions of the American Nuclear Society, Vol. 32, 1979 Annual Meeting, Atlanta, GA., June 3-7, 1979, pp. 553, 554. (Coauthor),
" Human Engineering Influences on t: 2 Performance of Nuclear Power Plant Operators", Testimony for the record of the'May 22-24 1979 Hearings on '
Nuclear Power Plant Safety Systems, Committee on Science and Technology, U.S. House of Representatives. U.S. Government Printing Office, 1979, pp. 255-270.
I "Rcaidential Photovoltaic Systems-- A Review and Comparative Evaluation ~
4 of Four Independent Studies of Potential Concepts", ATR-8.0(7823)-1, December 1979 (also published as SAND 80-7010,. Sandia~ National Labora-tories, October 1980). '
, " Review of Rogovin Special Investigative Group Staff Report on Human Factors Evaluation Related to the Three Mile Island Accident", Letter Report, 30 November 1979.
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" Industrial Process Heat Applications of Solar and Geothermal Energy and Human Engineering Influences on the Performance of Nuclear Power Plante", ATR-79 (9538)-1, September 1979.
" Emergency Planning Zones for Serious Nuclear Power Plant Accidents",
State of California - Office of Emergency Services, November 1980.
(Coauthor).
"The Technical Basis for Emergency Planning Zones for, Serious Accidents at Nuclear Power Plants in California", ATR-81(7870)-1, November 1980.
" Report of the LOFT Special Review Group", U.S. Nuclear Regulatory Commission, NUREG-0758, February 1981. (Coauthor).
"The Feasibility and Effectiveness of Underground Nuclear Power Plants -
a Review of the California Energy Commission's Study", pp. 19-33, Proceedings of the Symposium on Underground Siting of Nuclear Power Plants, Hanover, West Germany (16-20 March 1981), E Schweizerbart' sche Verlagsbuchhandlung (Nagele u Obermiller) Stuttgart, 1982.
" Development of Emergency Planning Zones for Nuclear Accidents in California", American Nuclear Society Transactions, 1981 Annual Meeting, liiami, Florida, June 7-11, 1982, TANSAO 38 1-776 (1981), June 1981, pp. 124-126.
" Basis for Selection l of Emergency Planning Zones from the Shoreham Nuclear Power Plant, Suffolk County, New York," F.C. Finlayson &
Associates, October, 1982 (Coauthor with Edward P. Radford, M.D.)
" Impact and Application of Suppression Pool Scrubbing Capability to Emergency Planning," Future Resources Associates, Inc., December, 1982. (Coauthor with Robert J, Budnitz)
" Nuclear Power Safety Reporting System, Vol. I: Feasibility Analysis,"
U.S. Nuclear Regulatory Commission, NUREG/CR-3119 (Vol. I), February, 1983. (Coauthor with J.R. Ims)
" Nuclear Power Safety Reporting System, Vol. II: Concept Description,"
U.S. Nuclear Regulatory Commission, NUREG/CR-3119 (Vol. II),1 April, 1983
" Nuclear Power Safety Reporting System - Feasibility Analysis and Concept Description," Transactions of the lith Water Reactor Safety Research Information Meeting, NUREG/CP-0047, October 1983. (Coeuthor with J.R. Ims and T.A. Hussman)
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ATTACHMENT 2 f
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- PROFESSIONAL QUAI.ITICATIONS OF GREGORY C. MINOR -
GRECORY C. MINOR -
MHB Technical Associates 1723 Hamilton Avenue Suite K -
San Jose, California 95125 (408) 266-2716 EXPERIENCE: ,
1976 to PRESENT -
Vice-Prssident - MHB Technical Associates, San Jose, California i
Engineering and energy consultant to state, federal, and private organizations and individuals. Major activities include studies of safety and risk involved in energy generation, providing technical consulting to legislative, regulatory, public and private groups and expert witness in
, behalf of state organizations and citizens' groups. Was co-editor of a critique of the Reactor Safety Study (WASE-1400) for -the Union of Concerned .
Scientists and co-author of a risk ant. lysis of Swedish reactors for the Swedish Energy Consnission. Served on the Peer Review Group of the NRC/TMI Special Inquiry Group (Rogovin comunittee). Actively involved in the Nuclear Power Plant Standards Committee work for the Instrument Society of America (ISA).
1972-1976 Manager, Advanced Control and Instrumentation Engineering, General Electric
, Company, Nuclear Energy Division, San Jose, California -
Managed a design and development group of thirty-four engineers and support personnel designing systems for use in the measurement, control and operation of nuclear reactors. Involved' coordination with other reactor design organizations, the Nuclear Regulatory Commission, and customers, both overseas and domestic. Responsibilities included c6ordinating and i
canaging and design and development of control systems, safety systems, and.
new control concepts for use on the next generation of reactors. The
( position included respo,nsibility for standards applicable to control and instrumentation,'as well as the design of short-term so".utions to field problems. The disciplines involved included electrical and mechanical
. engineering, seismic design and process computer control / programming, and equipment qualification. -
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Manager, Reactor Control Systems Design, General Electric Company, Nuclear
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Energy Division, San Jose, California Managed a group of seven engineers and two support personnel in the design
, and preparation of the detailed system dracings and control documents
- relating to safety and emergency systems ~for nuclear reactors. -
Responsibility rsquired coordination with other design organizations and interaction with the customer's engineering personnel, as well at
, regulatory personnel.
1963 - 1970 Design Engineer, General Electric Company; Nuclear Energy Division, San Jose, California Responsible for the design of specific control and instrumentation systems for nuclear reactors. Lead design respon'sibility for various subsystems of instrumentation used to measure neutron flux in the reacter during startup
, and intermediate power operation. Performed lead system design function in the design of a major system for measuring the power generated in nuclear reactors. Other responsibilities included on-site checkout and testing.of a complete raaetor control system at an experimental reactor in the j Southwest. Received patent for Nuclear Power Monitoring System.
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1960 - 1963 Advanced Engineering Program, General Electric Company; Assignments in Washington, California, and Arizona Rotating assignments in a variety of disciplines: ,
Engineer, reactor maintenance and instrument design, KE and D reactors, Hanford, Washington, circuit design and equipment maintenance coordination.'
Design' engineer, Microwave Department, Palo Alto, California. Worked on design of cavity couplers ,for Microwave Traveling Wave Tubes (TWT).
Design engineer, Computer Department, Phoenix, Arizona. Design of'
. core driving circuitry.
l Design engineer, Atomic Power Equipment Department, San Jose, California. Circuit desisp and analysis. .
Design engineer, Space Systems Department, Santa Barbara, California.
Prepared control portiono 'f satellite proposal. -
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Technical Staff - Tec.hnical Military Planning operation. (TEMPO),
Santa Barbara, California. Prepara analyses of missile exchanges.
During this period, completed three-year General Electric program of extensive education in advanced engineering principles of higher mathematics, p'obability r and analysis. Also completed courses in Kepner-Tregoe, Effective Presentation, !
Management Training Program, and various technical seminars.
EDUCATION University of California at Berkeley, BSEE, 1960. .
Advanced Course in Engineering - three-year curriculum, Ceneral Electric Company, 1963.
Stanford University, MSEE, 1966.
HONORS AND ASSOCIATIONS Tau Beta Pi Engineering Honorary Society Co-holder of U.S. Patent No. 3,565-760, " Nuclear Reactor Power Monitoring System," February, 1971.
. .,- Member: American Association for Advance of Science.
Member: Nuclear Power Plant Standards Committee, Instrument Society of America. .
PERSONAL DATA
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Born: June 7, 1937 Married, three children Residence: San Jose, California '
PUBLICATIONS AND TESTIMONY,
- 1. C. C. Minor, S. E. Moore,'" Control Rod Signal Multiplexing," IEEE Transaccidas on Nuclear Science, Vol. NS-19, February, 1972.
- 2. C. C. Minor,.W. G. Milan, "An Integrated Control Room System for a Nuclear -Power Plant," NEDO-10658,' presented at International Nuclear l Industries Fair and Technical Meetings, October, 1972,'Basle, -
Switzerland. .
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- 3. The above' article was also published in the German Technical Magazine, NT, March, 1973.
- 4. Testimony of G. C. Minor, D. C. Bridenbaugh, and R. B. Hubbard before
-the Joint Committee on Atomic Energy, Hearing held February 18, 1976, and published by the Union of Concerned Scientists, Cambridge, Massachusetts. .
- 5. Testimony of G. C. Minor, D. G. Bridenbaugh, and R'. B. Hubbard before the California State Assembly Committee on Resources, Land Use, and .
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Energy, March 8, 1976.
- 6. Test'inony of G. C. Minor and R. B. Hubbard before the California State Senate Committee on Public Utilities. Transit, and Energy, March 23, 1976.
- 7. Testimony of C. C. Minor regarding the Grafenrheinfeld Nuclear Plant, March 16-17, 1977, Wurzburg, Germany. -
- 8. Testimony of G. C. Minor before the Cluff Lake ' Board of Inquiry, ;
Regina, Saskatchewan, Canada, Department 21, 1977.
- 9. The Risks of Nuclear Power Reactors: A Review of the NRC Reactor Safety Study WASH-1400 (NUREC-75/0140), R. Kendall, et al, edited by G. C. Minor and-R. B. Hubbard for the Union of Concerned Scientists, August, 1977. .
- 10. Swedish Reactor Safety Study: Barseback Risk Assessment, HEB Technical Associates, January, 1978. (Published by Swedish Department of Industry as Document SdI 1978:1)
- 11. Teselmony by G. C. Minor before the Wisconsin Public Service Commission, February 13, 1978, Loss of Coolant Accidents: Their Probability and Consequence. .
- 12. Testimony by G. C. Minor before the California Legislature Assembly' Committee on Resources, Land Use, and Energy, AB 3108, April 26, 1978,
. Sacramento, California.
- 13. Presentation by G. C. Minor before the Federal Ministry for~ Research and_ Technology (BMFT).. Meeting on Reactor Safety Research, Man / Machine Interface 'in Nuclear Reactors, August 21, and September 1,1978, Bonn, Germany. ,
I 14. Testimony of G. C. Minor, D. G. Bridenbaugh,- and R.. B. Hubbard, before I
the Atomic Safety and Licensing Board, September 25, 1978, in th6 matter of Black Fox Nuclear Power Station Constructier Permit Hearings, Tulsa,~ Oklahoma.
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- 15. Testimony of C. C. Minor. ASLB Hearings Related to TMI-2 Accident.
Rancho Seco Power Plant, on behalf of Friends of the Earth', September 13, 1979.
- 16. Testimony of G. C. Minor before the Michigan State Legislature, special Jcint Committee on Nuclear Energy, Implications of Three Mile Island Accident for Nuclear Power Plants in Michigan, October 15, 1979.-
- 17. A Critical View of Reactor Safety, by G. C.' Minor, paper presented to the American Association for the Advancement of Science, Symposium on Nuclear Reactor Safety, January 7, 1980, San Francisco, California.
- 18. The Effects of Aging on Safety of Nuclear Power Plants;, paper.
presented at Forum on Swedish Nuclear Referendum, Stockholm, Sweden, March 1, 1980.,
- 19. Minnesota Nuclear Plants Caseous' Emissions Study, MEB Technical
- Associates, September, 1980, prepared for the Minnesota Pollution Control Agency. Roseville, MN.
- 20. Testimony of G. C. Minor and D. G. Bridenbaugh before the New York State Tublic Service Commission, Shoreham Nuclear Plant Construction Schedule, in the matter of Long Island Lighting Company Temporary Rate
- Case, September 22, 1980.
~
- 21. Te'stimony of G. C. Minor and D. G. Bridenbaugh before the New Jersey Board of Public Utilities, Oyster Creek 1980 Refueling Outage Investigation, in the matter of Jeresey Central Power and Light Rate Case, February 19, 1981.
- 22. systems Interaction and Single Failure Criterion, HEB Technical Associates, January,1981, prepared for and availabla from the Swedish Fuclear Power Inspectorate, Stockholm, Sweden.
' 23. Systems Interaction ano ? ingle Failure Criterion: Phase II Report, MHB Technical Associates, February 1982, prepared for and available
. from the Swedish Nuclear Power Ihspectorate, Stockholm, Sweden.
- 24. Testimony of G. C. Minor and ' D. G. Bridenbaugh on PORV's and Pressurizer Heaters. Diablo Canyon Operating License hearing before
(,
ASLB, January 11, 1982.
- 25. Testimony of.G. C. Minor and R. B. Hubbard on Emergency Response Planning. Diablo Canyon Operating License hearing befor,e ASLB, January 10, 1982.
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- 26. Testimony of G. C. Minor, R. - B. Hubbard, M. W. Goldsmith, S. J.
Narwood on behalf of Suffolk County, before the Atomic Safety and Licensing Board, in the matter of Long Island Lighting Company,
'Shoreham Nuclear Power Station, Uni't 1, regarding Contention 73, safety Classification and Systems Interaction, April 13, 1982.
- 27. Testimony of C. C. Minor and D. C. Bridenbaugh on behalf of Suffolk County, before the Atomic Safety and Licensing Poard, in the matter.of Long Island Lighting company, Shoreham Nuclear Power Station, Unit 1, regarding Suffolk County Contention 1_1, Passive Mechanical Valve Failure, April 13, 1982.
- 28. Testimony of G. C. Minor and R. B. Hubbard on behalf of Suffolk -
County, before the Atomic Safety and Licensing Board, in the matter of Long Island Lighting company, Shoreham Nuclear Power Station, Unit 1, regarding Suffolk County Contention 27 and SOC Contention 3, -
Post-Accident Monitoring, May 25, 1982.
- 29. Testimony of G. C. Minor and D. G. Bridenbaugh on behalf of Suffolk County, before the Atomic Safety and Licensing Board, in the matter of Long Island Lighting Company, Shoreham Nuclear Power Station, Unit 1, regarding Suffolk County Contention 22, SRV Test Program, May 25, 1982.
~ '
- 30. Testimony of G. C. Minor and D. G. Bridenbaugh on behalf of Suffolk County, before the Atomic Safety and Licensing Board, in the matter of Long Island Lighting Company, Shorehen Nuclear Power Station, Unit.1, regarding Suffolk County Contention 28(a)(vi) and SOC Contention 7A(6), Reduction of SRV Challenges, June 14, 1982.
- 31. Testimony of G. C. Minor on behalf of Suffolk County, before the Atomic Safety and Licensing Board, in the matter of Long Island Lighting Company, Shoreham Nuclear Power Statiou Unit 1, regarding Environmental Qualification, January 18, 1983.
- 32. Testin.ony of C. C. Minor and D. G. Bridenbaugh before the Pennsylvania Public Utility Commission, on behalf of the Office of Consumer Advocate, Regarding the Cost of Constructing the Susquehanna Steam Electric Station, Unit 1. Re: Pennsylvania Power and Light, March 18, 1983.
. 33. Supplemental testimony of C. C. Minor, R. B. Hubbard,'and M. W.
Goldsmith ha behalf of Suffolk County, before the Atomic Safety and Licensing' Board, in the matter of Long Island Lighting Company, Shoreham Nuclear Power Station, Unit 1, regarding Suffolk County Contention 73, Safety Classification and Systems Interaction, March 23, 1983.
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- 34. Testimony before the District Court Judge in the case of Sierra Club et al. vs. DOE regarding the clean-up of Uranium Hi11' Tailings. ' June 20, 1983.~
- 35. Systems Interaction and Single railure Criterion: Phase 3 Report, MHB Technical Associates, June, 1983, prepared for and available from the Swedish Nucisar Power Inspectorate, Stockholm, Sweden. ,
- 36. Systematic Evaluation Program: Status Report and Initial Evaluation, MHB Technical Associates, June, 1983, prepared for and available from the Swedish Nuclear Power' Inspectorate, Stockholm, Sweden.
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I ATTACHMENT 3 I
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CURRICULUM VITAE Name: Edward Parish Radford, M.D. Social Security No.: 022-16-4231 Birthdate: February 21, 1922 Telephone (office): (412) 624-3009 Birthplace: Springfield, Massachusetts -
Citizenship: U.S.A.
- Business Address -
Department of Epidemiology Graduate School of Public Health University of Pittsburgh -
Pittsburgh, PA 15261 l
EDUCATION AND TRAINING
- Undergraduate Massachusetts Institute of Technology, 1940-43 Biology Graduate l Harvard Medical School 19.43-46 Medicine M.D. 1946
, APPOINTMENTS AND POSITIONS Academie 1949-50 Teaching Fellow, Department of Physiology, Harvard' Medical School ~
1950-52 Instructor, Department of Physiology, Harvard Medical School 1952-55 Associate, Department of Physiology, Harvard School of Public Health 4
1959-65 Associate Professor Physiology, Harvard School of Public Health 1965-68 Professor and Director, Department of Environmental Health
- Director of Kettering Laboratory: Professor of Physiology, College of Medicine, University of Cincinnati
'1968-77 Professor of Environmental Medicine, School of Hygiene and Public
, Health, Johns Hopkins University
- 1 1975-76 Visiting Professor, Department of Regius Professor of Medicine, University of Oxford, Oxford, England 1977- Professor of Environmental Epidemiology, Graduate School of Public Health, University of Pittsburgh, Pittsburgh, PA 1979- Director, Center for Environmental Epidemiology; Graduate School of Public Health, University of Pittsburgh, Pittsburgh, PA. ..
Nen-Academic Positions '
1947-49 Active Duty, U.S. Air Force .
i i
Chief of Medical Service, Maxwell Air Force Base, Montgomery, Alabama *
- Radiological Health Officer, Atomic Bomb Tests, Eniwetak Ar.oll 1948 1955-59 Physiologist, Ha'skell Laboratory for Toxicology and Industrial. Medicine, E.I. duPont deNemours and Company, Newark, Delaware
. l
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MEMBERSHIPS IN PROFESSIONAL AND SCIENTIFIC SOCIETIES ,
- American Physiological Society - -
Radiation Research Society . -
American Public Health Association Society for Envir,onmental and Occupational Health Society for Epidemiologic Research l t
SERVICE 'ON COMMITTEES OR OIMER PROFESSIONAL ACTIVITIES Member: Physiology Training Committee, National Institute of General Medical l Sciences, 1967-70 . .
Member: National Academy *of Sciences Advisory Committee on the Biological Effects '
of Ionizing Radiation, 1970-72 -
Member: Health Research Facilities Scientific Review Committee, National Institutes of Health, 1970-73 -
Chairman: Power Plants and Human Health and Welfare Studies Group Department of Natural Resources, State of Maryland, 1972-73 Member: The Governor's Advisory Council on Nuclear Reactors, State of Pennsylvania, 1973-74 Consultant in Occupational Health, State of Maryland, Division of Labor and Industries, 1973-75 Medical Consultang to Council on Environmental Quality, Washington, DC, 1975 ,
Giairman: National Academy of S,ciences Advisory , Committee on the Biological Effects of Ionizing Radiation; Chairman; Subcommittee on Somatic Effects, 1977-80 Member: United States Environmental Protection Agency Administrator's Toxic Substances Advisory Committee, 1977-80 i Member: Amerfaan Public Health Association Technical Panel on Environmental
. Bazards, 1977- ,
4 Medical Consultant to Westvaco Corporation, New York, NY
'hsearch and Traininst (Current Research) 8/1/80-7/31/81 - Investigation of Le,ad, Carbon Monoxide and Thiocyanate in' Blood
, Samples from the Third National Health and Nutrition Evaluation Survey (HANES III). Department of Energy - $63,250 9/15/79-9/30/82 -Center for Environmental Epidemiology, Environmental Protection .
Agency, $1,346,000 Other Activities Editorial board Environmental Research Refereeing: New England J Med Science
- Arch Env Health Environmental Research prvice, University - !
Departmental Ad' missions. Committee Curriculum Committee, Graduate. School of Public Health Honors ,
.1943-46 National Scholar, Harvard Medical School -
-1975-76. Macy Faculty Scholar Award . -
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PUBLICATIONS * ,
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- 1. Radford, EP, Jr. Method for estimating respiratory surface arenof mammalian Proc Soc Exp Biol Med 87:58-61, lungs from their physical characteristics.
1954. .
Clinical use of a nonogram*to
- 2. Radford EP, Jr. , Ferris BG, Jr. , Kriete BC. N Eng1 J Med estimate proper ventilation during artificial respiration. '
251:877-884, 1954.
- 3. Radford IP, Jr.. Ventilation standards for use' in artificial respiration.
J Apol Physiol 7:451-460, 1955.
- 4. Radford EP, Jr., Lefcoe NM. Effect of bronchoconstriction on elastic prop-erties of excised lungs and bronchi. Am J Physiol 180:479-484, 1955. ,
Measurement' of lung
- 5. McIlroy MB, Mead J. Selverstone NJ, Radford EP, Jr. J Appl tissue viscous resistance using gases of equal kine =atic viscosity. ,
Physiol 7:485-490, 1955.
- 6. Otis AB, McKerrow CB, Bartlett RA, Mead J, McIlroy MB, Selverstone NJ, Radford, EP, Jr. Me'chanical f actors ,in distribution of pulmonar'y ventilation.
J Appl Physiol 8:427-443, 1955. l
- 7. Radford EP, Jr. Recent studies of mechanical properties of ma=malian lungs.
In: Tissue Elasticity. JW Remington, ed. Am Physiol Soc., Washiogton, DC, ~ -
. 1957, pp. 177-190.
- 8. Mead J, Whittenberger JL, Radford EP, Jr. Surface tension as e factor in pulmonary volume-pressure hysteresis. J Appi Physiol 10:191-196, 1957.
- 9. Frank NR, Radford EP, Jr., Whittenberger JL. Static volume-pressure inter-relations of the lungs and pulmonary blood' vessels in excised cats' lungs.
J Appl Physiol 14:167-173, 1959.
- 10. Radford, EP, Jr. Factors modifying water metabolism in rats fed dry diets.
Am J Physiol 196:1098-1108, 1959. .
Brouha L, Radford EP, Jr. The cardiovascular system in muscular activity. In:
11.
Science and Medicine of Exercise and Sports. Harper and Brothers, New York, . ,
NY, 1960 pp 178-206. ,
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- 12. Radford EP, Jr. Interrelationships between water and el'ectrolyte metabolism in rats. Am J Ca:diol 8:863-869, 1961.
- 13. Radford EP, Jr. , Whititenberger JL. Mechanical methods. In: Artificial Respiration: Theory and Applications. JL Whittenberger, ed. Hoeber Medical utvision, tiarper and Row, New York, RY,1962, pp 147-172.
- 14. Radford EP, Jr. Mechanical stability'of the lung. Arch Environ Health' ~
6:134-138, 1963. .
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- 15. Radford EP, Jr.', Hunt VR, Sherry D. Analysis of teeth and bones for alpha-
- emitting elements. Radiat Res 19:298-315, 1963. -
16.
Hunt VR, Radford EP, Jr., Segall AJ. Comparison of concentrations of alpha-emitting elements in teeth and bones. Int J Radiat Biol 7:277-287, 1963.
- 17. Radford EP, Jr., Hunt VR. Polonium-210: A volatile radio-element in cigarettes.
Science 143:247-249, 1964.
- 18. Kleinman LI, Radford EP, Jr. Ventilation standards for small ==mm=1s. J Appl Physiol 19:360-362, 1964. .
- undisturbed rats. J Appi Physiol 19:179-186, 1964. .
i .
- 20. Radford, EP, Jr., Hunt VR. Cigarettes and Poleaium-210. Science 144:247-249, 1964.
- 21. Laver MB, Morgan J, Bendixen HH, Radford EP, Jr. Lung volume, compliance and
) a rterial oxygen tensions during controlled ventilation. J Appl Physiol 19: '
725-733, 1964.
- 22. Little JB, Radford EP, Jr. Effects of ionizing radiation and their importance in anesthesiology. Anesthesiology 25:479-489, 1964.
- 23. Little JB, Radford EP, Jr. Circulating antidiuretic hormone in rats: Effects of dietary electrolytes and protein. Am J Physiol 207-821-825, 1964.
- 24. Radford EP, Jr. The physics of gases. In: Handbook of Physiology, Sec. 3
. Respiration, Vol I. WO Fenn and H R Rahn, eds. Am Physiol Soc, Washington, DC, 1964, pp 125-152. .
1
- 25. Radford EP, Jr. Static mechanical properties of '====11an lungs. In:Haridbook
, of Physiology, Sec. 3 Respiretion, Vol 1.~ WO. Fenn and H Rahn, eds. Am Physiol Soc, Washington, DC. 1964, pp 429-449.
- 26. Radford EP, Jr., Hunt'VR, Little JB. Polonium-210 in cigarettu smokers.
Science 146:86-87, 1964.
- 27. Radford EP, Jr. Static mechanical properties of' lungs in-relation to age.- In':
Aging of the Lung. L Cander and JH Moyer, eds. Grune and Stratton, New Ycrk.
NY, 1964. pp.152-155.
- 28. Kleinman LI, Radford EP, Jr., Torelli G. Urea and inulin clearances in un-di.eturbed, unanesthetized rats. Nun J Physiol 208(3):578-584, 1965. .
- 29. Hedley-Whyte J. Radford EP, Jr., Laver MB. Nomogram for temperathre correction 02 measurements. J Appl Physiol 20:785-786,
.of electrode calibration during P 1965'.
- 30. Laver MB, Murphy AJ, Seifen A. Radford,EP, Jr.- Blood 0 9' content measurements using the oxygen electrode. J Appl Physiol 20
- 1063-1069, 1965. . '
I
- 31. Fregly MJ, Harper JM,Jr., Radford EP, Jr. Regulation of Sodium Chloride intake in Rats. Am J of Physiology' 209:287-292, 1965. *
~
l 210 in pulmonary tissue of cigarette smokers. N Engl J Med 273:1343-1351, 1965. l
- 33. Pontoppidan.H., Hedley-Whyte J. Bendixen HH, Laver MB, Radford EP, Jr'. Ventilation and oxygen requirements during prolonged artifical ventilation in pat (ents with respiratory failure. N Engl J Med 273-401-409, 1965.
- 34. Little JB, Klevay LM, Radford EP,'Jr., McCandy RB. Antidiuretic hormone in-activation by isolated perfused rat liver. Am J Physiol 211:786-792, 1966. .
- 35. Vierling AF, Little JB, Radford EP,'Jr. Antidiuretic hormone bio-assay in rats with hereditary.hypothalamic diabetes insipidus (Brattleboro strain).
EndocrinoloRv 80:211-214, 1967.
- 36. Little JB, Radford EP, Jr. Polonium-210 in bronchial epithelium of cigarette smokers. Science 155:606-607, 1967. -
- 37. Torelli G, Radford EP, Celentano, F, d'Angelo E. Effetto della concentrazione dell' emoglobina sulla curva di dissociazione con l'0 . B 11 Soc Ital di Biol Sper. 44:1447-1449, 1967. 2
- 38. Radford EP, Torelli G. Celentano F, Cortili G. Pcssibilita di interazioni intermolecola,r1 durante l'ossigenazione dell'emoglobina. Boll Soc Ital di Biol Sper. 44:1449-1452, 1967.
- 39. Bingham E Pfitzer EA, Barkley W, Radford EP. Alveolar macrophages: Reduced number in rats after prolonged inhalation of lead sesquiozide. Science 162:
1297-1299, 1968. . .
- 40. Vierling AF,.Radford EP, Little JB. Circulating antidiuretic hormone in the X-irradiated rat. Radiat Res 36:441-453, 1968.
- 41. Radford EP. Biological aspects of synergisms. In: Environmental Problems.
BR Wilson, ed. JB Lippincott Co. , Philadelphia, PA,1968. pp 160-173. -
, 42. Friberg LT (Chairman) and Radford EP (Vice-Chairman). Report of the first Karolinska Institute Symoosium on Environmental Health. " Maximum allowable concentrations of mercury compounds." Arc.h Env Health 19:891-905, 1969.
Science 165:312, 1969. -
. . 44'. . Tepper LB, Radford EP.
Pulmonary reactions due t6 the inhalation'of noxious seents. In: Harrison's Principles of Internal Medicine. 6th edition. . -
1 M Wintrobe ana uw Inorn, ecs. neuraw-u111 new Iorm, NY,1970, pp.1322-27.
- 45. Goldsmith JR, Radford EP., Medical aspects of air pollution. In: Harrison's Principles of Internal Medicine, 6th edition. MM Wintrobe and GW Thorn, eds.
McGraw-Hill, New York; NY, 1970, pp 1329-1332. -
- 46. Hunt VR, Radford EP, Segall AJ. Naturally occurring concentrations of alpha-emitting isotopes in a New England population. Health Phys 19:235-243, 1970.
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- 47. Radford EP (ChaiIrman),Cederlof R, Epstein FH, Friberg LT, Hrubec z . Repo.rt of the 2nd Karolinska Institute Symposium on Environmental Health. " Twin registries in the study of chronic disease." Acta Med Scand Suppl 523, 1971, pp. 1-4c f 43. Radford EP. Envirpnmental issues and the medical profession. New Physician 20:230-232, 1971.
- 49. Small KA, Radford EP, Frazier JM, Rodkey FL, Collison H. A rapid method for simultaneous measurement of carboxy-and mathemoglobin in blood. J Appl Physiol 31:154-160, 1971.
- 50. Lindvall T Radford EP. Report of the 4th Karolinska Insitute Symposium on Environmental Health. " Measurement of annoyance due to exposure to environinental factors." Environ Res 6:1-36, 1973. -
- 51. Whorton MD, Radford EP, Pierce J0. A program for control of occupational' health hazards in Maryland. Report for the Division of Labor and Industry, State of Maryland, 1973,
- 52. Radford EP.
M&canismes d' action des polluants adriens, particulidrment le plomb, les oxydes d' azote et les alddhydes. Rev Epidam Mda Soc et Santa Publ 22:673-686, 19J4.
- 53. Radford EP, Neuberger JS.
Review of human health criteria for ambient air quality standards in Maryland. Report to the Bureau of Air Quality Control, State of Maryland, 1-61, 1974.
54'. Euller LH, Radford EP, Swif t D, Perper J, Fisher R. The relationship between ambient carbon monoxide, levels, post mortem carboxydemoglobin, sudden death and myocardial infarction. Arch Environ Health 30:477-482, 1975.
- 55. Halpin BM, Radford EP, Fisher RF, Caplan Y. A fire fatality study. Fire Journal 69(3):11-13,98-99, 1975.
'56. Whorton MD, Levine MS, Radford EP. A preventabl'e death from an electrical hand tool malfunction. J Occ Med 17(9):589-591, 1975. .
- 57. Radford EP. Biomedic&l aspects of trace metals. AIChE Symposium Series -
71:39-46, 1976.
- 58. Radford EP. Health aspects of housing. J Occ Med 18:105-108, 1976.
- 60. Radford EP. Cancer mortality in the steel industry. Ann NY Acad Sci 271:228-238, 1976.
- 61. Radford EP,.Levine MS. 0ccupational exposures to carbon monoxide in fire-fighteis. J Occ Med 18:62d-632, 1976.
- 62. Radford EP, Pitt B,',Halpin B, Caplan Y, Fisher R, Schweda P. Study cf' fire deaths in Maryland. In Physiological and Toxicological Aspects of Combustion -
Products. International Symposium conducted by Committee. on Fire Research Commission on Sociatechnic'al Systems. National Academy Sciences, Washington, '
DC, 26-35, 1976. ,
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6). Radford EP, Martell EA. Polonium-210: Lead-210 ratios as an index of residence times of insoluble particles from cigarette smoke in bronchial epithelium.
Inhaled Particles IV. Edited by WH Walton, Pergamon Press, Oxford,1977, pp 567-580. .
- 64. Radford EP, Doll R. Saith PG. Mortality among patients with ankylosing spondylitis not given X-ray therapy. New Engl J Med 297:572-576, 1977.
~
- 65. Smith PG, Doll R, Radford EP. Cancer mortality among patients with 5nkylosing l j spondylitis not given X-ray therapy. Br J Radiol 50:728-734, 1977. :
- 66. Levine M, Radford EP.- Fire victims: Medical outcomes and demographic character- - l 1stics. Am J Public Health 67:1077-1079, 1977..
- 67. Laver MB, Jackson E, Sherperel M, Tung C, Tung W, Radford, EP. Hemoglobin-02affinity regulati n: DPG, monovalent anions and hemoglobin concentration.
J Appl Physiol 43:632-642, 1977. ,
- 68. Torelli G. Celentano F. Cortili G, .D' Angelo E, Cazzaniga A, Radford, EP.
Hemoglobin-oxygen equilibrium at different hemoglobin and 2,3-diphosphoglycerate
- concentrations. Physiol Chem & Phvsics 9i21-38, 1977. -
- 69. Levine M, Radford EP. Occupational exposures tp cyanide in Baltimore fire l
fighters. J Occ Med 20:53-56, 1978,. ~
, 70. Spivey GH, Radford EP. Inner-city housing and respiratory disease in children--
a pilot study. Arch Environ Health 34(1):23-30, 1979. '
~
. and cyanide on cerebral circulation and metabolism. Arch Environ Health 34(5)354-359, 1979. ,
- 72. Radford, EP. , Health effects o f ionizing radiation. Symposium on Energy and Human Health: Human Costs of Electric Power Generation. EPA-600/9-50-030, U.S. Environmental Frotection Agency, Washington, u.c. , May 1980. pp.365-379.
- 73. Radford, EP. Impacts on human health from the coal and nuclear fuel cycles ,
and other technologies associated with electric power generation and transmission.
Report'to the Ohio River Basin Energy Study, U.S. Environmental.Protectica Agency., Washington DC, May 1980.
- 74. Radford, EP. Health effects of ionizing radiation. In: Health and Implications of New Energy Technologies. William N. Rom and Victor E. Archer, Eds. Ann Arbor.
Science, Ann Arbor, MI,1980, pp 67-77.
, 75.' Radford, EP. Human health effects of low doses of ionizing radiation: The
)
- BEIR III C.ontroversy. Radiation Res, '84:369-394,1980.
- 76. Radford, EP. Radr 7ghters in the induction of lung gancer in underground miners.
Banbury Report 9: .ntification of Occupational Cancer. Cold Spring Harbor Lab. ,.
Cold Spring Harbor, NY. ,1981, - pp 151-163. (In press.) -
- 77. hadford, EP. Sensitivity on health-end' points: Effects on conclusions of studies.
' Environmental Health Perspectives. 42:45-51, 1982. (Iu' press.)
I
United States,- 1976-80. Advancedata Report, National Center for Health Statistics, No. 76, March 17, 1982.
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TABLE 1 TYPE OF SHELTER. CHANCES OF RECEIVING HEALTH THREATENING DOSES *
(Shielding Factors) AT GIVEN DISTANCES FROM THE PLANT
>j 3 0 Rem *>j 100 Rem >, 2 0 0 Rem 1-2 mi. 10 mi. 1-2 mi. 10 mi. 1-2 mi.
LILCO Average for 30% 12% 9% ~ 1% 2%
Long Island Housing (0.7 cloud,'O.2 ground) '
Wood Frame 30% 15% 20% 1% ~2%
without Basement (0.9-cloud, 0.4 ground)
Masonry or Brick 30% 8% 5% < 1% *
- lt
'l/2 with Basement (0.5 cloud, 0.1 ground)
Vehicles 35% 15% ( 1%
(1.0 cloud, 0.7 ground) 1 0 . Calculated'for a 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />' exposure except for vehicles where 2 hrs. exposure was used
- . 1% chance of doses exceeding 100 rems at 5-miles e
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