ML20235M529

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TMI-2 Cleanup Program Status Update
ML20235M529
Person / Time
Site: Three Mile Island Constellation icon.png
Issue date: 01/11/1989
From:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
Shared Package
ML20235G974 List:
References
NUDOCS 8902280295
Download: ML20235M529 (88)
v • d • e


Text

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.9 4 TMI - 2 CLEAN L"P PROGRAM i

STATUS UPDATE JANUARY 11,1989 I

Vl-2 C _EAN U 3 P 70 GRAVI STATUS U 3 JATE N7C REG ON January 1 ~ ,1989

MEETINC WITH NRC REGION I AGENDA Subject Presenter Tine Introduction M. B. Roche 5 min.

Schedule and Budget M. B. Roche 15 min.

Defueling Status S. Levin 15 min.

Defueling Completion Report J. J. Byrne 5 min.

Water Disposal Status 3. A. Kuehn 15 min.

SNM Measurement Program J. S. Schork 15 min.

Radiological Conditions D. W. Turner 15 min.

PDMS (Mode 4) Proposal R. E. Rogan 30 min.

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> OTHER ACTIVITIES START PROCESSED WATER EVAPORATION FEB. 28,1989 COMPLETE PROCESSED WATER EVAPORATION MAR. 31,1990 I COMPLETE TRANSFER OF SNM ACCOUNTABILITY SEPT. 30,1990 COMPLETE MONITORED STORAGE PREREQUISITES OCT. 31,1990

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l g- & OR WN RV FNAL CLEANUP. NSPECTION, is >__

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ACCESS 19 20 I

OCTlNOV.DEC JAN FEB . MAR APR MAY JUN JUL AUG SEP OC-1988 1989

I I

1 p

t.

I L

T V -2 JE:UE_ \G COVP_E O\

RE DO T 1

l i

l l

l 1

l l

l HISTORY OF DEFUELING COMPLETION REPORT l

l . 04-23 TSCR 53 SUBMITTED FOR NRC REVIEW AND APPROVAL PROPOSED TO i ESTABLISH MODES 1,2, AND 3. ,

. 09-18 MEETING WITH NRC TO DISCUSS TSCR

53. (i.e., INCLUDES DEFUEUNG COMPLETION REPORT.

. 10-26 GPU NUCLEAR SUBMITS REVISION 1 TO TSCR 53 IN RESPONSE TO NRC COMMENTS. TECH. SPEC.1.3, " MODE,"

IS REVISED TO REQUIRE A DEFUELING COMPLETION REPORT BE SUBMITTED WITHIN 30 DAYS PRIOR TO MODE CHANGE.

l

. 01-13 NRC ISSUED THE NSHC FOR TSCR 53 WHICH RESTATES REQUIREMENT FOR 30-DAY REPORT.

L 05-:27 NRC LICENSE AMENDMENT NO,30 l ISSUED APPROVING. NRC REQUIRES REPORT TO BE SUBMITTED WITHIN 60 DAYS PRIOR TO MODE CHANGE.

4

_ _ _ _ - _ _ - _ _ - _ __ 1

y t

DEFUELING COMPLETION REPORT l

L L

  • CRITICALITY ANALYSIS ADDRESSING EACH SEPARATE QUANTITY OF RESIDUAL FUEL. INCLUDES:

- Estimate of the quantity of residual fuel

- Its location and dispersion with the location

- Physicalform

- Mobility

- Presence of any moderator or reflecting l material e CRITICALITY ANALYSIS MUST DEMONSTRATE THAT DEFUELING HAS PROGRESSED SUFFICIENTLY THAT l

INADVERTENT CRITICALITY IS PRECLUDED (i.e., LONG-TERM SUBCRITICALITY IS ASSURED).

. REPORT DOES NOT REQUIRE NRC APPROVAL.

i i

I s-I l

I t

TV -2 1

i

(-

ACC JE \~ G E \ E 7A~E 3 WA~E 7 J S3OSA_ i 1.

1 SYSTE V U 3]A~E 4

1 1

1

WATER DISPOSAL STATUS DIVISION OF RESPONSIBILIN PACIFIC NUCLEAR Design Fabrication Install Test Operate Remove Equipment GPUN Provide water complying with influent criteria Ship solid waste Provide Rad Con services Chemistry Support Safety evaluation, licensing

F ,

i l

SCHEDULE 1 L

- SHOP TESTS JANUARY 16 MOBILIZE TO LANCASTER JANUARY 23

(

MECHANICAL / ELECTRICAL FEBRUARY u-15 TEST MOBILIZE AT TMI FEBRUARY 21 e

COMPLETE ASSEMBLY /- MARCH 30 ERECTION l

ACCEPTANCE TESTING APRIL 3 AVAILABLE FOR APRIL 10 OPERATIONS 1

l L-___________ >

[

( VENDOR'S TEST PROGRAM t

- SHOP TESTING DEMONSTRATES OPERABILITY (INCLUDING DF)

OF EVAPORATOR AND VAPORIZER l

MECHANICAL / ELECTRICAL TEST DEMONSTRATES PROPER FUNCTION OF l

INSTRUMENTS, INTERLOCKS, MECHANICAL l FIT-UP OF ALL VENDOR SUPPLIED EQUIPMENT l

- ACCEPTANCE TESTING l OPERABILITY OF ALL EQUIPMENT USING NON-RADIOACTIVE WATER

CURRENT STATUS

(

VENDOR - TEST PLANNED FOR WEEK OF JANUARY 16,1989 TO OPERATE EVAPORATOR AND VAPORIZER.

j KEY PURPOSE IS TO DETERMINE BORON DF.

l SITE -

CONCRETE PAD AND PRIMARY ELECTRICAL COMPLETE I -

FLUID SYSTEM TIE-INS AND

( ASSOCIATED ELECTRICAL EQUIP-1 MENT BEING WORKED ..

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POST DEFUELING SURVEY )

l 1

FOR.

l SPECIAL NUCLEAR MATERIAL L ACCOUNTABILITY 4 t

e D

. BACKGROUND CURRENT CORE STATE PRECLUDES NORMAL FUEL ACCOUNTABILITY PROCESS AS REQUIRED BY 10 CFR 70.51(d) AND 10 CFR 70.53 LACK OF SOPHISTICATED ONSITE HOT CELL FACILITIES PRECLUDE ACCURATE ACCOUNTABILlW OF FUEL SHIPPED TO DOE /INEL IN FUEL CANISTERS IN OCTOBER,1985 THE NRC ISSUED GPU NUCLEAR AN EXEMPTION FROM THE REQUIREMENTS OF 70.51(d)

AND 70.53 AND NOTED THE GPU NUCLEAR / DOE AGREEMENT ON THE USE OF AN ANNOTATED DOE /NRC FORM 741 FOR USE IN MEETING THE TRANSFER REQUIREMENTS OF 10 CFR 70.54 THEREFORE GPUN MUST ANNOTATE A DOE /NRC FORM 741 FOR EACH CANISTER SHIPMENT TO INDICATE THAT QUANTIFICATION OF SNM ON A PER CANISTER BASIS IS NOT POSSIBLE AND A FINAL ACCOUNTING OF SNM WILL BE PERFORMED AT THE COMPLETION OF DEFUEUNG AT WHICH TIME A POST DEFUELING SURVEY WILL QUANTIFY THE RESIDUAL FUEL INVENTORY i

l l

l FINAL SNM ACCOUNTABILITY CURRENT INVENTORY (DECAY CORRECTED)

- SNM SHIPPED AS RADWASTE AND SAMPLES .

FINAL PLANT INVENTORY AS DETERMINED BY THE POST DEFUELING SURVEY

= SNM SHIPPED TO DOE /INEL IN CANISTERS l

l

SNM MEASUREMENT TECHNIQUES GAMMA SPECTROSCOPY 1 Sodium lodide High Purity Germanium NEUTRON DETECTION Metal Foll Activation BF3 Neutron Detectors Active Neutron Interrogation ALPHA DETECTION Cylindrical Gas Proportional Detector VISUAL INSPECTION i

Remote inspection via boroscope, fiberscope, Rees Camera and normai television camera SAMPLING Verification of ratio of tracer isotopes to fuel Uranium

, content ratio

i POST DEFUELING SURVEY SNM MEASUREMENTS .

1 SNM measurements conducted as part of the Post Defueling Survey will be performed to quantify for final SNM accountability the residual SNM inventory with the facility in the draindown configuration.

The results of some measurements performed for the purpose of fuel characterization and/or for the Defueling Completion Report may be used in conjunction with the Post Defueling Survey Measurements The results of the Post Defueling Survey will be documented in the PDSR Notebook. Two(2) of the Post Defueling Survey Reports ,which are part of the .

PDSR Notebook, have been issued.  !

l

-_____--__-__m_ . _ - . _ . _ _ _ _ . _ _

. i CURRENT STATUS

1. The TMI-2 SNM Accountability Plan has been l reviewed , approved and issued by GPU Nuclecr. '

L 2. An integrated residual fuel measurement plan ,

l which describes the status of Individual SNM measurements, is prepared and issued on a monthly basis.

3. Measurement of residual fuel quantities in the Auxilary and the Fuel Handling buildings is in process.

Nine (9) of fourty four (44) cubicles have been completed.

4. Measurement of the residual fuel quantities in the Reactor building locations and Reactor Coolant l

System components outside of the Reactor Vessel is nearing completion. ,

5. SNM measurements required to support submission of the Defueling Completion Report will be completed by the end of the second quarter of 1989.
6. SNM measurements required to support the completion of the Post Defueling Survey and final SNM accountability will be finished after the end of fuel shipping activities.

s f

1 QUALITY ASSURANCE FOR SNM 1 ACCOUNTABILITY

)

SNM ACCOUNTABILITY PLAN ,

Based upon QA/QC input, review and comment MEASUREMENTS QA approved measurement procedures and equipment calibration procedures ANALYSES 1

All analyses are documented in accordance with the TMI-2 Engineering Calculations procedure ,which includes a requirement for independent verification 1

j l

ALARA FOR SNM ACCOUNTABILITY Limit SNM measurements to only those essential Use previous fuel characterization measurements where possible Perform each measurement in the most dose conservative manner

i e e

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i TMI - 2 3

i RADIOLOGICAL CONTROLS ,

I I

UPDATE

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POST-DEFUELING STORAGE (MODE 4) l December 2,1986 GPU Nuclear Submitted A Plan To NRC For Information  !

I March 11,1987 GPU Nuclear Submitted An Environmental Evaluation i

April 27,1988 NRC Draft PElS Issued For i Comment August 16,1988 Safety Analysis Report Submitted To NRC For Approval l

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N E

D SOP E I I on r e NT UT tctia l I

C iaets C ADIAINIV I

ant eoia a t

A GN ET RCInWW EOLC RCCA . . . . .

BASIS FOR TRANSITION TO FACILITY MODE 4

= THE REACTOR VESSEL AND THE REACTOR COOLANT SYSTEM HAVE BEEN DEFUELED AND THE CORE MATERIAL HAS BEEN SHIPPED OFFSITE.

. DECONTAMINATION HAS BEEN COMPLETED T@ THE EXTENT THAT FURTHER MAJOR DECONTAMINATION PROGRAMS ARE NOT JUSTIFIED ON THE BASIS OF WORKER DOSE.

. A CONDITION OF STABILITY AND SAFETY HAS BEEN ESTABLISHED SUCH THAT THERE IS NO RISK TO PUBLIC HEALTH AND SAFETY.

1 CONCEPTUAL. APPROACH TO PDMS (MODE 4) l l

i e NOT A COMMITMENT TO DECOMMISSIONING e MODE 4 CONDITIONS SHALL PROVIDE A i MARGIN OF SAFETY WHICH EXCEEDS j EXISTING REGULATIONS FOR OFFSITE {

EXPOSURE (10 CFR 50, APPENDIX l} )

. MODE 4 CONFIGURATION SHALL BE ACCEPTABLE FOR EXTENDED PERIOD, E.G., UP TO TIME OF TMI-l DECOMMISSIONING

. MODE 4 CONFIGURATION SHALL BE ESSENTIALLY A PASSIVE, MINIMUM MAINTENANCE CONFIGURATION MAXIMlZING USE OF EXISTING SYSTEMS

\

J 1

l 1

l MODE 4 PROVIDES LAYERS OF PROTECTION

= INHERENT STABILITY e EFFECTIVE CONT,AINMENT

= POSITIVE CONTROL i i

INHERENT STABILITY i

. THE PLANT WILL BE STABLE AND NOT OPEN TO TRANSIENTS.

. OVER 99% OF THE FUEL WILL HAVE BEEN i REMOVED. A NUCLEAR CHAIN REACTION '

WILL NOT BE POSSIBLE.

. CONTAMINATION WILL HAVE BEEN '

REMOVED TO THE EXTENT THERE CAN BE NO HAZARDOUS RELEASE OF RADIOACTIVITY.

. WA ER RE OVED FROM PLANT SYSTEMS I

. FEW COMBUSTIBLES, LOW FIRE POTENTIAL. I

. NO PRESSURIZED SYSTEMS.

o  ;

{. . ..

1 EFFECTIVE CONTAINMENT l REMAINING RADIOACTIVITY ISOLATED FROM THE ENVIRONMENT BY P.ROTECTIVE STRUCTURES:

i e CLOSED PlPING SYSTEMS

  • SEALED CUBICLES l
  • LOCKED REACTOR CONTAINMENT BUILDING l
  • SECURE AUXILIARY AND FUEL HANDLING BUILDINGS l

i

r. ,

POSITIVE CONTROL

.. RADIOLOGICAL AND ENVIRONMENTAL MONITORING e PLANT PROTECTION SYSTEMS, SUCH AS FIRE PROTECTION

+ PLANT SECURITY l

l

_ _ - - - _ _ - - - - - - - )

l 1

\

l l

PDMS (MODE 4) LICENSE CONDITION l

. CONTINUE LICENSE UNDER 10 CFR PART 50 " POSSESSION ONLY"  ;

e NEW NRC-APPROVED TECHNICAL SPECIFICATIONS FOR FACILITY MODE 4 ,

. COMPLY WITH CURRENT RADIATION PROTECTION REGULATIONS - 10 CFR PART 20

. OFFSITE DOSE A SMALL FRACTION OF 10 CFR PART 50, APPENDIX l LIMITS l

l

PREREQUISITES FOR FACILITY l MODE 4 l

1

. THERE IS NO CREDIBLE POSSIBLITY OF NUCLEAR I l

CRITICALITY. THIS CONDITION HAS BEEN ASSURED BY REMOVAL OF SUBSTANTIALLY ALL OF THE FUEL AND ELIMINATION OF ALL )

POTENTIALLY CRITICAL CONFIGURATIONS. 4 l

l

. ALL FUEL AND CORE DEBRIS WHICH HAVE BEEN REMOVED FROM THE REACTOR VESSEL AND i ASSOCIATED SYSTEMS HAS BEEN SHIPPED ,

OFFSITE.

l l

. ANY POTENTIAL FOR A SIGNIFICANT RELEASE OF RADIOACTIVE MATERIAL HAS BEEN ELIMINATED. RADIOACTIVE MATERIAL HAS l BEEN REMOVED AND RESIDUAL SOURCES OF RADIOACTIVITY HAVE BEEN ISOLATED SO THAT ANY POTENTIAL RADIOACTIVE RELEASE WILL l BE WITHIN 10 CFR 50 APPENDIX l GUIDELINES FOR OFFSITE DOSE CONSEQUENCES.

l

,y,v. ,

I EREREQLilSITES FOR FACILITY MODE 4 (CONTINUED) .

. TO THE EXTENT PRACTICAL, THE REACTOR ]

COOLANT SYSTEM AND THE FUEL TRANSFER i

CANAL HAVE BEEN DRAINED, AND THE SPENT FUEL-TRANSFER TUBES HAVE BEEN ISOLATED. i

.TO THE EXTENT THAT THE SPENT FUEL POOLS ARE NEEDED TO SUPPORT ACCIDENT GENERATED. WATER DISPOSAL ACTIVITIES, WATER MAY REMAIN IN THESE POOLS SUBSEQUENT TO TRANSITION TO MODE 4.

. ALL RADIOACTIVE WASTE FROM THE MAJOR CLEANUP ACTIVITIES HAS BEEN SHIPPED OFFSITE OR HAS BEEN PACKAGED AND STAGED FOR SHIPMENT OFFSITE.

  • RADIATION WITHIN THE FACILITY HAS BEEN REDUCED, CONSISTENT WITH ALARA PRINCIPLES, TO LEVELS WHICH WILL ALLOW NECESSARY PLANT MONITORING ACTIVITIES, THE PERFORMANCE OF REQUIRED MAINTENANCE, AND ANY NECESSARY I

INSPECTIONS.

L

NUCLEAR CORE DEBRIS PROJECTIONS DAMAGED CORE PLUS STRUCTURE = 296,900 LB

. DAMAGED CORE 134,050 KG

. REMOVE AND SHIP - > 132,700 KG

+ RESIDUAL FUEL (UO2 ) < 940 KG e RESIDUAL CORE DEBRIS < 1,340 KG

k l

TMI-2 CLEANUP PROGRAM  :

RADIOLOGICAL GOALS GENERAL AREA DOSE RATE R/HR REACTOR BUILDING Refueling Canal <0.015 El. 347' & Above <0.03 (except D-rings)

El. 305' to 347' <0.07 Basement (El. 282') Asis AUXILIARY BUILDING Corridors <0.0025 Other Areas <0.05 ,

l i

TMI-2 CLEANUP PROGRAM RADIOLOGICAL GOALS (CONTINUED) gel \ERAL AREA DOSE RATE R/HR l

FUEL HANDLING BUILDING Corridors <0.0025 Other Areas <0.05 OTHER BUILDINGS Turbine Building <0.0025 Chemical Cleaning Bldg. <0.0025 (except EPICOR ll area to be left operable)

Service Building Containment <0.0025 Tank Area

O EXT! MATED DOSE COMMITMENTS ROUTINE AND UNANTICIPATED CONDITIONS DURING MODE 4

1. POPULATION DOSES PERSON-REM / YEAR Routine Airborne Releases:

Bone Dose 0.27 Total Body Dose 0.07 Routine Liquid Releases:

Bone Dose 0.09 Total Body Dose 0.02 Total Population Dose:

Bone Dose 0.36 Total Body Dose 0.09

ESTIMATED DOSE COMMITMENTS ROUTINE AND UNANTICIPATED CONDITIONS DURING MOD 14 (CONTINUED)

2. DOSES TO MAXIMALLY EXPOSED MREM / YEAR INDIVIDUAL Routine Airborne Releases:

Bone Dose 0.06 Total Body Dose 0.02 Routine Liquid Releases:

Bone Dose 0.005 Total Body Dose 0.002

3. MAXIMUM UNANTICIPATED RELEASE Dose to maximally exposed individual from unanticipated release (bone dose limiting) 4.8 mrem

RADIOLOGICAL AND ENVIRONMENTAL MONITORING

. SURVEYS CONDUCTED ON A REGULAR BASIS

. MONITOR BOTH LIQUID AND GASEOUS EFFLUENTS

. MAINTAIN ENVIRONMENTAL MONITORING PROGRAM (REMP)

. MONITORING AND ENVIRONMENTAL REPORTS TO THE NRC

r ,

i TMI-2 FACILITIES & SYSTEMS l

. Original

. Recovery

( ,

All Placed in One of Two Classifications r 3 r 3 OPERABLE DEACTIVATED These include: These include:

r 3 r 3 Mothballed for Future Use Mode 4 Succort Systems and Facilities for Systems and Facilities which steps have been taken kept operational full time to preserve availability for or available to operate to future use support Mode 4 activities L >

k >

r 3 Not Preserved Systems and Facilities safe, Site Succort Svstems but with no action taken to Systems and Facilities preserve future availability; made available to support some systems may be site operations partially or wholly dismantled L J t J k ) L J

~5. OSSIFICATION OF FACILITIES AND SYSTEMS

d FACILITIES AND SYSTEMS (FACILITY MODE 4)

. TMI-2 BOUNDARY Included within TMI protected area External security equivalent to operating plant

. REACTOR BUILDING Normally locked but accessible Containment maintained Ventilation system operable Sump systems operable

. AUXILIARY AND FUEL HANDLING BUILDINGS Normally locked but accessible Exhaust systems operable Sump systems operable

\

O MODE 4 ACTIVITIES

. MONITORING AND SURVEILLANCE

. DECONTAMINATION

. ' RADIOACTIVE WASTE HANDLING

. SNM ACCOUNTABILITY

. WATER PROCESSING

-AGW

- Other

ENVIRONMENTAL EVALUATION FOR TMI-2 POST-DEFUELING MONITORED STORAGE (FACILITY MODE 4)

CONCLUSIONS

1. POTENTIAL OFFSITE CONSEQUENCES DURING MODE 4 DEMONSTRATE THREAT TO PUBLIC HEALTH AND SAFETY HAS BEEN ELIMINATED.
2. OFFSITE CONSEQUENCE ESTIMATES FOR MODE 4 CONFIRM PEIS CONCLUSION THAT POTENTIAL ENVIRONMENTAL CONSEQUENCES ARE DOMINATED BY OCCUPATIONAL EXPOSURES.
3. OCCUPATIONAL EXPOSURES DURING CLEANUP EXPECTED TO BE SUBSTANTIALLY LOWER THAN REVISED PEiS ESTIMATES; MAY BE WITHIN RANGE OF ORIGINAL ESTIMATES.
4. MODE 4 ACTIVITIES RESULT IN INSIGNIFICANT INCREASE IN TOTAL OCCUPATIONAL EXPOSURE.
5. OCCUPATIONAL EXPOSURE DURING RECOMMISSIONING / DECOMMISSIONING WILL BE REDUCED DUE TO NATURAL DECAY AND IMPROVED TECHNOLOGY.

O ABSTRACT DRAFT PElS SUPPLEMENT 3 THE NRC STAFF HAS CONCLUDED, BASED ON THIS EVALUATION, THAT THE LICENSEE'S PROPOSED PLAN AND THE NRC STAFF IDENTIFIED ALTERNATIVES FOR COMPLETION OF CLEANUP ARE WITHIN THE APPLICABLE REGULATORY LIMITS AND COULD EACH BE IMPLEMENTED WITHOUT A SIGNIFICANT ENVIRONMENT IMPACT. NO ALTERNATIVE WAS FOUND TO BE CLEARLY PREFERABLE FROM AN ENVIRONMENTALIMPACT PERSPECTIVE.

O ABSTRACT DRAFT PEIS SUPPLEMENT 3 THE NRC STAFF HAS CONDUCTED THAT THE LICENSEE'S PROPOSAsL TO PLACE THE FACILITY IN A MONITORED STORAGE CONFIGURATION WILL NOT SIGNIFICANTLY AFFECT THE QUALITY OF THE HUMAN ENVIRONMENT. FURTHER, ANY IMPACTS FROM THE LONG-TERM STORAGE OF THE FACILITY ARE OUTWEIGHED BY ITS BENEFITS.

E POST-DEFUELING STORAGE (MODE 4)

SAFETY ANALYSIS REPORT SUBMITTED AUGUST 16,1988 SUBMITTAL INCLUDES:

. Proposed License Change "To Possess" Only

. Proposed Technical Specifications For Facility Mode 4

. Supporting Safety Analysis Report OTHER LICENSING BASIS DOCUMENTS

= Security Plan, Revision 26

. Emergency Plan, Revision 2

. QA Plan e Organization Plan

h g y 4 6 i

SUMMARY

THE FACILITY MODE 4 (PDMS) CONFIGURATION PROVIDES A SECURE, MONITORED TMI-2 PLANT THAT DOES NOT PRESENT A HAZARD TO WORKERS OR TO PUBLIC HEALTH AND SAFETY.

E

. RESIDUAL FUEL

. HIGH LEVELS OF RESIDUAL CONTAMINATION

. FUTURE PLANT DISPOSITION

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a ATTACHMENT 2 TMI-2 CLEAN-UP STATUS MEETING JANUARY 11, 1989 ATTENDANCE LIST GPUN D. Bedell, Manager, Public Information, TMI J. Byrne, Manager, TMI-2 Licensing R. DeSantis,'TMI-Communications G. Eidam, Project. Planning and Analysis (PP&A), TMI-2 -

J. Kuehn, Site Operations Director, TMI S. Levin, Director, TMI-2 Defueling R. Rogan, Directer, Licensing and Nuclear Safety, TMI-2 J. Schork, Task' Manager, Post-Defueling Survey and Special Nuclear Material (SNM)'

D.~ Turner, Director, Radiological Controls, TMI-2

~

'NRC c W. Baunack, Project Engineer, Division of Reactor Projects (DRP), Region I,(RI)

RL Bellamy, Chief, Facilities Radiological Safety & Safeguards Branch (FRSS),

Division of Safety-and Safeguards (DRSS), RI L. Bettenhausen, Chief, Projects Branch No. 1, DRP, RI C. Cowgill,, Chief, Reactor Projects Section 1A, DRP, RI A. Della Ratta, Safeguards Auditor,'DRSS, RI S. Ebneter, Director, DRSS, RI D. Johnson,' Resident Inspector (TMI), RI W. Johnston, Deputy Director, DRSS, RI S. Jeurgens, NRR Intern, Office of Nuclear Reactor Regulation (NRR)

W. Kane, Director, DRP, RI K. Kolaczyk, Reactor Engineer, DRP, RI T. Martin, Director, Division of Reactor Safety (DRS), RI M. Masnik, Project Manager (TMI 2), NRR T. Moslak, Resident Inspector (TMI), RI M. Shanbaky, Chief, Facilities Radiation Protection Section, DRSS, RI L. Thonus, Project Manager (TMI-2), NRR R. VanHouten,-Accident Evaluation Branch, Office of Nuclear Regulatory Research h

4 l

q i

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