ML19322D557

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Forwards Executive Summary of Facilities Radioactive Liquid & Gaseous Releases from 790328 Accidents.Jy Lee & Jt Collins Prof Qualifications Encl
ML19322D557
Person / Time
Site: Crane  
Issue date: 01/31/1980
From: Swartz L
NRC OFFICE OF THE EXECUTIVE LEGAL DIRECTOR (OELD)
To: Lewis M
AFFILIATION NOT ASSIGNED
References
NUDOCS 8002150235
Download: ML19322D557 (8)


Text

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January 31, 1980 Marvin I. Iewis 6504 Bradford Terrace Philadelphia, Pennsylvania 19149

Dear Mr. Iewis:

Pursuant to our telephone conversation today, I am enclosing copies of the original Executive Summary of TMI-l and TMI-2 radioactive liquid and gaseous releases as a result of the TMI-2 accident on March 28, 1979 These copies are more legible than the ones sent with our response to your interzugatories on January 28, 1980.

I am also enclosing the signed affidavits to accompany those interrogatories.

Sinc,erely, f

Q(, l GC (,10 CL AfCv's V:iki'C Incinda Iow Swartz 7

Enclosures:

As stated cc with enclosures: Service Iist 8002150

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Jay Y. Lee Senior Nuclear Engineer NRC/THI Technical Support Staff ONRR/NRC b 'bN /

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V John T. Collins Deputy Director NRC/TMI Technical Support Staff ONRR/NRC p.

Sworn and subscribed before me, a Notary Public in ar.d for the County of Dauphin, Commonwealth of Pennsylvania, this a8 day of Ji ;uary 1980.

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Jay Y. Lee f,.

Professional Qualifications

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Till Technical Support HRC Recovery Operations Office Office of Nuclear Reactor Regulation My name is Jay Y. Lee.

I am a senior nuclear engineer in the TMI Technical Support of the NRC Recovery Operations Office at the Three Mile Island Nuclear Station.

I was detailed to this position on April, 1979 as a member of the Task Force for TMI Support.

In this position, I perform technical reviews, analyses, and evaluations of the recovery operations for Till-2, the restart programs for T111-1, and the TMI-2 Reactor Containment Building entrance program.

Prior to this assignment, I was a senior nuclear engineer in the Effluent Treatment Systems Branch in the Office of Nuclear Reactor Regulation, I was responsible for Technical reviews, analyses, and evaluations of reactor plant systems and equipment for fission product removal and treatment of radioactive wastes, as to the adequacy of provisions in meeting the applicable regulations.

I am also responsible for the derivation of models used in the calculation of source terms to estimate the radiological impact on the environment, the adequacy of the instrumentation provided for maintaining radioactive discharges from nuclear power plants and for providing technical bases for guides and standards.

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I received a Bacnelor of Science degree in Chemical Engineering from the University of Minnesota in 1962 and a Master of Science dageree in Nuclear Engineering from the Catholic University of America.

My professional experience totals approximately 17 years of design, construction, start-up, operation, and licensing of central station nuclear power plants.

From 1962 to 1966, I was employed as the plant chemical engineer by Northern States Power Company at Pathfinder Atomic Power Plant (decommissioned).

In this position, I was responsible for operation and maintenance of radwaste treatment systems and for the implementation of the occupational health and effluent and environmental monitoring programs.

From 1966 to 1969, I was a nuclear systems engineer with Bechtel Corporation at 'an Francisco.

In tt}is position, I was responsible for technical review of t.e design and construction of reactor plant systems of central station nuclear power plants.

From 1969 to 1974, I was employed as the senior chemical engineer by Sacramento l

Municipal Utility District at Rancho Seco Huclear Generating Station.

In this l

position, I was responsible for design reviews, construction, and start-sp l

operation of the radwaste treatment systems and the plant secondary system.

In 19'4, I accepted the position of senior nuclear engineer with the U. S. Nuclear Regulatory Commission.

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John T. Collins, Jr.

Professional Qualifications NRC Recovery Operations Office Office of Nuclear Reactor Regulation i

My name is John T. Co.llins, Jr.

I am the Deputy Director of the NRC Recsvery Opera-i tions Office at the Three Mile Nuclear Station.

I was appointed to this position on May 31, 1979, as part of the interim organization within the Office of Nuclear Reactor Regulation.

In my present capacity as the senior NRC official onsite I am responsible for the supervision of all technical activities performed by the onsite professional staff of the Office of Nuclear Reactor Regulation and for the supervision of all sur-veillar.ce and enforcement activities performed onsite by the professional staff of t

the Office of Inspection and Enforcement.

In addition to this assignment, I am also Chief of the Effluent Treatment Systems i

Branch in the Office of Nuclear Reactor Regulation.

In this position I am responsible

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for planning, organizing, directing and supervising the activities of the branch in performing technical reviews, analyses and evaluations of reactor plant systems and l

equipment for fission product removal and treatment of radioactive wastes, as to the adequacy of provisions in meeting the applicable regulations.

I am also responsible for the derivation of models used in the calculation of source terms to estimate the radiological impact on the environment, the adequacy of the instrumentation provided for maintaining radioactive discharges :from nuclear power plants and for providing technical bases for guides and standards.

I attended Idaho State University and Pennsylvania State University majoring in gen-eral engineering.

I also took special courses in ventilation engineering and industrial hygiene engineering at Michigan State University and North Carolina State University.

My professional experience totals approximately 25 years of which more than 21 have i

been concerned with occupational health and safety and treatment of radioactive wastes.

1 From 1954-1957, I was employed as a laboratory technician by Goodyear Atomic Corpora-tion at the Portsmouth Gaseous Diffusion Plant.

From 1957:.1963, I held the position ofIndustrialHygieneEngineerintheNuclearDivisionof-lt(e'BerylluimCorporation, Hazelton, Pennsylvania.

In this position, I was responsible for the design, instr.1-lation, operation and maintenance of filtration and waste

  • treatment systems and for the implementation of the occupational heal.th and effluent and environmental monitor-ing programs.

c In 1963, I accepted the position of Industrial Hygiene Engineer with the AEC's Idaho Operations Office, Idaho Falls, Idaho.

In this capacity, I was responsible for the appraisal of AEC contractor's programs at the National Reactor Testing Station in the areas of occupational health, pollution abatement, waste management and effluent monitoring.

In April 1971, I transferred to the Division of Waste Management and Transportation, AEC Headquarters, Washington, DC, as a Materials and Process Engineer.

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In November 1971 I was detailed to the Regulatory Bivision as Lead Nuclear Engineer in the Effluent Treatment Systems Branch, Directorate of Licensing.

In April 1975, I was appointed Chief of the Effluent Treatment Systems Branch.

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J I am a member of the American Industrial Hygiene Association and the American Nuclear Society.

I have served on various ANS Working Groups for the development of ANSI Standards related to systems for the processing of radioactive liquid ari gaseous wastes.

I am presently a member of ANS 40.1 Working Group to develop a standard for volume reduction systems for use in nuclear power plants.

I am also a member of the ASME Radwaste Committee and serve on the Committee on Nuclear Air & Gas Treatment Systems.

In addition, I am a member of NCRP Scientific Committee-41, Radiation Generated In Nuclear Fuel Cycle Facilities.

Over the past five years I have served on various IAEA Technical Committees and presently serve on the Committee on Removal, Storage and Disposal of Gaseous Radionuclides from Airborne Effluents from Nuclear Facilities.

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Pega 1 of 3 EXECUTIVE

SUMMARY

i THREE MILE ISLAND UNITS I and II LIQUID and. CASEOUS RELEASES ist Incident 2nd Quarter Period Quarter 1/1/79 to 3/28/79 to 4/1/79 to 5/1/79 to 6/1/79 to 4/1/79 to

,DISCHARCE PATHWAYS 3/31/79 3/31/79 4/30/79 5/31/79 6/30/79 6/30/79 Liquid Released:

a) Discharge less Tritium:

1)

Concentration (UCi/cc) 1.29E-8 (a) 7.44E-8 (a) 1.75E-7 (a) 2.89E-8 (a) 2.84E-8 (a) 8.63E-8 (a) 2)

Total Activity (C1) 0.277E0 (b) 1.00E-1 (b) 1.62E0 (b) 2.2LE-1 (b) 1.8CE-1 (b) 2.03E0 (b) b)

Iodine-131 Released:

1)

Concentration (VCi/cc) 4.97E-9 (a) 7.16E-8 (a) 1.70E-8 (a) 2.25E-9 (a) 5.60E-10 :(a) 7.57E-9 (a)

2) Total Activity (C1) 0.107E0 9.62E-2 1.57E-1 1.72E-2 3.70E-3 1.78E-1 c)

Tritium Released:

1)

Concentration (VC1/cc) 4.83E-6 (a) 5.13E-7 (a) 8.45E-7 (a) 7.05E-7 (a) 4.60E-7 (a) 6.77E-7 (a)

2) Total Activity (C1) 104.lE0 0.69E0 7.80E0 5.38E0 3.04E0 1.59El II.

Airborne Iodine Released:

a)

Quarterly Release Rate (pC1/sec) 5.8E-1 5.8E-1 1.20E0 9.89E-3 2.12E-5 1.22E0 b) Total Iodine-131 Released (C1) 4.57E0 4.57E0 9.48E0 7.8E-2 1.67E-4 9.6E0

!II. Noble Cases Released:

a)

Quarterly Release Rate (C1/sec) 1.12E0 1.12E0 1.4.E-1 1.81E-4 9.5E-5 1.41E-1 b) Total Noble Cases Released (C1) 8.83E6 8.'83E6 1.llE6 1.43E3 7.50E2 1.llE6 FOOTNOTES:

a)

Concentrations are based upon actual MDCT flows. These are' concentrations in the effluent averaged over the period.

b) This data includes Iodine-131 released to the Susquehanna River as a regult of the TMI Unit II accident on March 28, 1979.

Page 2 of 3 EXECUTIVE

SUMMARY

THREE MILE ISLAND UNITS I and II LIQUID and CASE 0US RELEASES 3rd Quarter 7/1/79 to 8/1/79 to 9/1/79 to 7/1/79 to DISCHARGE PATHWAYS 7/31/79 8/31/79 9/30/79 9/30/79 I.

Liquid Released:

a)

Discharge less Tritium:

1)

Concentration (pCi/cc) 1.12E-8 (a) 2.66E-9 (a) 2.33E-9 (a) 5.18E-9 (a)

2) Total Activity (Ci) 7.85E-2 (b) 1.89E-2 1.78E-2 1.13E-1 b)

Iodine-131 Released:

1)

Concentration (pC1/cc) 4.57E-10 (a) 9.10E-ll (a) 8.62E-11 (a) 2.07E-10 (a)

2) Total Activity (C1) 3.20E-3 6.46E-4 6.59E-4

'4.51E-3 c)

Tritium Released:

1)

Concentration (pC1/cc) 7.20E-7 (a) 3.20E-7 (a) 3.34E-7 (a) 4.53E-7 (a) 2)

Total Activity (C1) 5.04E0 2.27E0 2.55E0 9.86E0 II.

Airborne Iodine Released:

a)

Quarterly Release Rate (pCi/sec) 1.58E-6

<MDA

<MDA 1.58E-6 b)

Total Iodine-131 Realease (C1) 1.24E-5

<MDA

.<KDA 1.24E-5

III, Noble Gases Released:

a)

Quart'erly Release Rate (C1/sec) 1.27E-5 1.14E-5 8.88E-6 3.30E-5 b) Total Noble Cases Released (C1) 100 90 70 260 FOOTNOTES:

a)

Concentrations are based upon actual MDCT flows. ?;hese are concentrations in the effluent averaged over the period.

b)

This data includes Iodine-131 released to the Susquehanna River as a result of the TMI Unit II accident on March 28, 1979.

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Page. 3 of 3

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EXECUTIVE

SUMMARY

THREE MILE ISLAND UNITS I and II LIQUID and CASE 0US RELEASES 4th Quarter

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10/1/79 to 11/1/79 to 12/1/79 to 10/1/79 to i

DISCllARGE PATHWAYS 10/31/79 11/30/79 12/31/79 12/31/79 I.

Liquid Released:

a)

Discharge less Tritium 1)

Concentration ( C1/cc) 1.25E-9

2) Total Activity (Ci) 9.29E-3 b)

Iodine-131 Released-1)

Concentration ( Ci/cc) 4.89E-ll

2) Total Activity (C1) 3.62E-4 c) Tritium Released:

i 1)

Concentration ( Ci/cc) 7.61E-7 2)

Total Activity (C1) 5.64E0 d) MDCT Flow For Month (cc) 7.41E-12 II.

Airborne Iodine Released:

a)

Quarterly Release Rate ( Ci/sec)

<MDA b) Total Iodine-131 released (C1)

<MDA III. Noble Gases, Released:

a)

Quarterly Release Rate (C1/sec) 9.51E-6 b) Total Noble Cases released (C1) 75 FOOTNOTES:

a)

Concentrations are based upon actual MDCT flows.

These are concentrations in the effluent averaged over the period.

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