ML20041B675
| ML20041B675 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 02/08/1982 |
| From: | Barrett L Office of Nuclear Reactor Regulation |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| CON-NRC-TMI-82-007, CON-NRC-TMI-82-7 NUDOCS 8202250044 | |
| Download: ML20041B675 (14) | |
Text
{{#Wiki_filter:- DISTRIBUTION TMIP0 HQ r/f ~ * ' TMI SITE.r/f -CENTRAL FILE NRC PDR LOCAL PDR February 8,1982 Site Operations File NRC/T!!I-82-007 MEMORANDUM FOR: Harold R. Denton, Director Office of Nuclear Reactor Regulation Bernard J. Snyder, Program Director TMI Program Office FROM: Lake 4 Barrett, Deputy Program Director THI Program Office
SUBJECT:
HRC TMI PROGRAM 0FFICE WEEKLY STATUS REPORT Enclosed is the status report for the period of January 31,1932 to February 6,1982. Hajor items included in this report are: Liquid Effluent Releases NRC and EPA Environmental Data Radioactive Material and Radwaste Shipments t~. Submerged Demineralizer System Status o 4 EPICOR II RECEVED Reactor Building Entries E FEBI11982* $ TMI Unit 1 Developments 8% y Public Meetings / A> _S-Lake 11. Barrett Deputy Program Director I 1NI Program Office Enclosure : As stated i s wm>,,,,,,,,,,,,,,,, e202250044 82020e ~... I our> PDR ADOCK 05000320 =$ R PDR .... ~ NRC FORM 318 MO-80) NRCM ONO OFFICIAL RECORD COPY
l r p-liaroid R. Denton February 8,1982 Bernard J. Snyder cc w/ encl: EDO OGC Office Directors Commissioner's Technical Assistants HRR Division Directors NRR A/D's Regional Directors IE Division Directors TAS EIS THI Program Office Staff (15) PHS EPA DOE Projects Br. #2 Chief, DRPI, RI DRPI Chief, RI Public Affairs, RI Stato Liaison, RI i I .m,I Pp,,,,,,,,,,,,,,M MIP f . IP0h TMI TI mna GKalman/jes R e MSha ba y sano RBe la y sua m om >2/ /82 2/ 82 2 ..../. /.82 ...... -{ 2/ 82 2/ 2/ /82 g-- / NRC FORM 318 (10-80) NRCM 0240 OFFICIAL RECORD COPY
9 4 NRC TMI PROGRAM 0FFICE WEEKLY STATUS REPORT January 31, 1982 - Febr uary 6,1982 4 Plant Status l Core Cooling Mode: Heat transfer from the reactor coolant system (RCS) loops to reactor building ambient. Available Core Cooling Modes : Decay heat removal systems. Long '.erm cooling "B" (once through steam generator-B). i RCS Pressure Control Mode: Standby pressure control (SPC) system. Backup Prer.sure Control Modes : Mini decay heat renoval (MDHR) system. Decay heat removal (DHR) system. Major Parameters (as of 0500, February 5,1982) (approximate values) l Average Incore Thermocouples: 103"F Maximum Incore Thermocouple: 135'F i RCS Loop Temperatures: A B Hot Leg 96*F 98'F Cold Leg (1) 81 F 78*F (2) 89'F 83 F 1 RCS Prer.sure: 97 psig Reactor Building: Temperature : 60 F Water level: Elevation 284.6 ft. (2.1 ft. from floor) Pressure: -0.27 psig Airborne Radionuclide Concentrations: 2.7 x 10-7 uCi/cc H3 (sample taken 2/4/82) 85 1.5 x 10-6 uCi/cc Kr (sample taken 2/1/82) Effluent and Environmental (Radiological) Information 1. Liquid effluents from the TMI site released to the Susquehanna River after processing, were made within the regulatory limits and in accordance with NRC requirements and City of Lancaster Agreement dated February 27, 1980. During the period January 29, 1982, through February 4,1982, the effluents contained no detectable radioactivity at the discharge point although individual effluent sources which originated i within Unit 2 contained minute amounts of radioactivity. Calculations l indicate that less than three millionths (0.000003) of a curie of cesium was discharged. l l
s8 . r 2. Environmental Protection Agency (EPA) Environmental Data. The EPA Middletown Office has not received the analytical results for Kr-85 measurements around the TMI site from the EPA's Counting Laboratory at Las Vegas, Nevada. When these results become available, they will be included in a subsequent report. The EPA is currently collecting environmental air samples for tritium (H-3) analysis from three sampling stations near the site and one control station near Reading. EPA has informed the NRC that the air tritium samples are being analyzed and the collected data is being reviewed and evaluated prior to publishing r - mrt on the H-3 sampling around TMI. The NRC will repor -3 analytical results once they become available LPA. o No radiation above normally occurring background levels was detected,in any of the samples collected from EPA's air and gamma rate networks during the period from January 27, 1982 through February 4,1982. 3. NRC Environmental Data. Results from NRC monitoring of the environment around the TM1 site were as follows: The following are the NRC air sample analytical results for the onsite continuous air sampler: I-1 31 Cs-137 Sampl e Period (uC1/cc) (uCi/cc) HP-305 January 28, 1982 - February 3,1982 <8.1 E-14 <8.1 E-14 4. Licensee Radioactive Material and Radwaste Shipments. On Thursday, February 4,1982, two drums, each containing seven SDS (Submerged Domineralizer System) samples from Unit 2, were shipped to Oak Ridge National Laboratory, Oak Ridge, Tennessee. On Thursday, February 4,1982, a Unit 1 one liter composite sample (waste evaporator condensate storage) was shipped to Radiation Management Corporation, Phil.adelphia, Pennsylvania. On Friday, February 5, 1982, 127 drums of Unit 1 and Unit 2 compacted LSA trash were shipped to U.S. Ecology Inc., Richland, Washington.
Major Activities 1. Submerged Demineralizer System (SDS). Processing of batch 18 commenced on January 31 1982, and completed on February 6,1982. 3 SDS performance parameters for batch 18 are enclosed. The radioactivity in the spent fuel pool water is now approximately 5.9 x 10-3 uc/ml (gross S-y activity). The supplemental spent fuel pool cleanup system, designed to remove the radioactive materials leaked through a faulty "0"-ring at a connection to an SDS vessel on January 20, 1982, became operational on February 2,1982. The DF for this cleanup system averaged 2.6 x 103 during the report period. 1 Five SDS zeolite vessels are currently stored under 23 feet of water in spent fuel pool "B". Four of these 10 ft3 stainless steel sessels contain from 25,000 to 56,000 curies, predominately as cesium-137.134, and strontium-90. One additional vessel, which was generated from processing RC bleed tank water, contains approx. imately 4,800 curies of radioactive ma terials. DOE has agreed to 4 accept the 10-20 highly loaded SDS zeolite vessels for R&D disposal 4 j demonstration. 3 The licens,ee's program for handling and shipping the anticipeted 10 to 20 SDS vessels is being finalized. As expected, measurable l, amounts of hydrogen and oxygen gas have been detected in the spent SDS vessels as a result of radiolysis of residual water. These zcolite vessels, which have been physically dewatered, are nomally vented to an off-gas system to eliminate hazardous gas mixtures. Radioactive containment requirements during shipment preclude i continuous vessel venting during transit. Currently GPU, with technical assistance from DOE's contractors at the Idaho National Engineering Laboratory and Rockwell Hanford, is pursuing engineering designs to either minimize the radiolysis of water or to recombine the hydrogen and oxygen in compliance with applicable Federal Regulations. The potential engineering desigrs which include a vacuum drying concept and in-vessel recombiner, are being fabricateo. This work is estimated to be completed over the next four to six months. 4 2. EPICOR II. The EPICOR II system continued to process SDS effluent: during the report period. Performance parameters are enclosed. 3. Reactor Building Entries. Two entries were made into the Unit 2 reactor building (RB) diring the first week in February. Tasks completed during the entries included a load test of the polar crane mounted supports for a power lift, assembly of the power lift platform on the 347 ft. elevation of the RB, and work commenced to replace fire hoses on RB fire stations. An NRC THUG Radiation Specialist entered the RB for an independent radiation survey and inspection of accessible areas. No RB entries are scheduled for the week of February 7,1982.
4 x 1
- .]j Unit 1 Developments 1.
On February 4 and 5,1982, the NRC sponsored a workshop in McLean, Virginia, on psychological stress in the TMI area. The participants for the workshop were 11 professional psychiatrists, psychologists and research experts with 4 additional expert witnesses and a professional facilitator to lead the discussion. A list of the initial participants and agenda for the meeting is included as. A verbatim transcript of the workshop was kept and will be available for reading in the THIFG Middletc3:n Office. The Mitre Corporation is under contract to the NRC to prepare a sunnary report of the results of the workshop. This report stould be completed in early March and will also be available in the Middletown office. 2. The NRC has received a draft report entitled, " Chronic and Acute Stress Associated with the Three Mile Island Accident and Decontaminstion: Preliminary Findings of a Longitudinal Study", from its contractor, Dr. Andrew Baum, a medical psychology professor at the Uniform Services University. The draft report concluded that residents in the TMI area experienced low but measurable levels of stress when compared to control groups in other areas. The draft report is available for reading in the Middletown office. t i l L- --- ------ ------ --
5-g Future Meetings l. On Friday, February 26, 1982, Lake Barrott will be speaking for the dinner meeting being held by the Engineers Week Joint Planning Council to honor ishigh Valley's Engineer of the Year and Young Engineer of the Year. t 2. On Saturday, March 13, 1982, Lake Barrett will address the Society of Manufacturing Engineers in Williamsport, PA, on the cleanup of TMI and general aspects of nuclear power. i K l I L i I 1 l 1 r 'd l
.,t ATTACHMENT 1 l SDS Performance for Batch Number 18 Average Average Average Radionuclide Influent Ef fluent DF (uc/ml) (uc/ml) 2 Cesium 137 1.1 x 10 6.2 x 10-4 1.8 x 105 Strontium 90 4.2 8.1 x 10-3 5.2 x 102 EPICOR II Performance January 29, 1982 to February 1,1982 Average Average Average Radionuclide Influeat Effluent OF j (uc/ml) (uc/ml) Cesium 137 1.1 x 10-3 2.3 x 10-7 4.8 x 103 1 Strontium 90 1.2 x 10-2 3.2 x 10-6 3.8 x 103 4 . Antimony 125 1.1 x 10-2 <3.6 x 10-7 >3.1 x 10 l 1 l l
u 4g. ATTACHMENT 2 WORKSHOP OBJECTIVE The purpose of this workshop is to obtain answers from the expert community to the following questions: Can we infer or extrapolate, from existing concepts and o retrospective or longitudinal studies, the range of stress responses that will be exhibited among the population in the vicinity of TMI to a restart of TMI-17 What is the scientific basis for prediction of the types o and ranges of these responses to the psychological stress associated with a restart of TMI-l? o What, if any, gaps must be filled in order to increase your confidence, as an expert, in these predictions? How might these be filled? e o G e O e 0
.;L Workshop on Psychological Setess Agenda Thursday, 4 February 1982 9:00 - 9:30 Opening Remarks NRC MITRE 9:30 - 10:30 Psychological Effects of Nuclear Power nature and causes of stress associated d with nuclear power distinction from stress associated with other causes observed stress responses associated with nuclear power 10:30 - 10:45 Break 10:45 - 12:00 Studies of Psychological Stress in the Vicinity of TML objectives sample methods findings conclusions t l 12:00 - 1:00 Lunch I i l r a
- h6 1:00 - 2:45 Concepts, causes and Consequences of Stress Which May Be Applicable to TMI-l Restart general definitions of stress which may be related to the TMI-1 restart specification and clarification of differences in terminology and concepts identification of stimulus conditions from non-TMI studies which may be applicable to the TMI-1 restart context.
What studies? l identification of consequences of stress from non-TMI situations which may be appli-cable to the TMI-1 restart context. What studies? modarating or intervening factors 2:45 - 3:00 Break 3:00 - 3:45 Evaluation of Methods Used in Identification and Measurement of Stress and Stress Responses techniques for measurement (surveys, interviews, medical records, etc.) of stressors, intervening variables and outcomes validity, reliability and relevance of ~ methods used 3:45 - 4:30 Ability to Extrapolate from Existing Studies to TMI-l Restart similarities / dissimilarities in stressor events, populations, etc. l other confounding factors to be considered 4:30 - 5:00 Focus for Tomorrow's Session
4 . es-Friday, 5 February 1982 9:00 - 10:30 Continue and Conclude Discussion of Issues Identified at Close of Thursday Session 10:30 - 10:45 Break 10:45 - 12:15 Technical Considerations for Predictina Psychological Stress Associated with a Restart of TMI-l 12:15 - 1:15 Lunch 1:15 - 2:00 Identification of Additional Near Tern Efforts Needed to Fill Caps in Existing Concepts and Studies benefit gained in terms of increased confidence in predictions 2:00 - 5:00 Summation of Workshop in' Terms of Objectives O i
6 NRC WORKSHOP PARTICIPANTS Andrew Baum, Ph.D. Associate Professor Uniformed Services University 1 Bethesda, Maryland Evelyn Bromet, Ph.D. Associate Professor of Psychiatry and Epidemiology University of Pittsburg Pittsburg, Pennsylvania Robert Dupont, M.D. President Institute for Behavior and Health Rockville, Maryland Kai T. Erikson, Ph.D. Professor of Sociology and American Studies Yale University New Haven, Connecticut Peter Houts, Ph.D. As'sociate Professor of Behavioral Science ' Milton S. Hershey Medical Center Hershey, Pennsylvania Stanislaw Kasl, Ph.D. Professor Epidemiology Yale University School of Medicine New Haven, Connecticut Ronald Perry, Ph.D. Research Scientist Battelle Human Affairs Research Centers Seattle, Washington Captain Richard Rahe, M.D. Director of Clinical Services Naval Regional Medical Center Long Beach, California Jon Rolf, Ph.D. Director of Prevention Research Center for Studies of Prevention Clinical Research Branch National Insititute of Mental Health Rockville, Maryland l l
. re. ~ - 4 Paul Slovic, Ph.D. Research Associate Decision Research Eugene, Oregon t George Warheit, Ph.D. Professor of Sociology and Psychiatry University of Florida Gainesville, Florida I ? i I i l e m Y 9 e 4 e +. O I i ) l l = l .}}