ML20051E007
| ML20051E007 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 05/10/1982 |
| From: | Barrett L Office of Nuclear Reactor Regulation |
| To: | Harold Denton, Snyder B Office of Nuclear Reactor Regulation |
| References | |
| CON-NRC-TMI-82-029, CON-NRC-TMI-82-29 NUDOCS 8205170001 | |
| Download: ML20051E007 (8) | |
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DISTRIBUTION TMIP0 HQ r/f TMI SITE r/f/CENTRALu FILE flRC PDR LOCAL PDR Site May 1G, 1982 Operations File NRC/TMI-82-029 h
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N' MEliORANDtEl FOR:
Harold R. Denton, Director 0) gfifD b
Office of fluclear Reactor Regulation 9
Berreard J. Snyder, Program Director
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/f TMI Prograa Office tC A
y FROM:
Lake H. Barrett, Deputy Program Director ry TMI Program Office
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SUBJECT:
fiRC Till PROGRA!! 0FFICE WEEKLY STATUS REPORT
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Enclosed is the status report for the period of May 2, 1982 to May 8, 1982.
Major itens included in this report are:
Liquid Effluents
- 1RC and EPA Environmental Data Radioactive l'aterial and Radwaste Shipments
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Subnerged Demineralizer System Status EPICOR II Reactor Coolant System llater Processing Reactor Building Entries Unit 1 Developments a
Public Meetings originale M Este 8. & Y Lake H. Barrett Deputy Program Director 7
TMI Program Office
Enclosure:
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Harold R. Dinton May 10, 1982
. Bernard J. Snyder l-cc w/cncl:
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' Office Directors Conaissioner's Technical Assistants NRR Division Directors l
NRR A/D's Regional Directors IE Division Directors TAS EIS I'
T111 Program Office Staff (15)
PHS EPA DOE Projects Br. #2 Chief, DRPI, RI DRPI Chief, RI Public Affairs, RI State Liaison, RI i
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OFFICIAL RECORD COPY
URC T".1 iROGRiE OFFICE WEEKLY STATUS REPORT May 2., 1982 - May 8, 1982 Plant Status Core Cooling Mode:
Heat transfer from the reactor coolant system (RCS)'
J loops to reactor building ambient.
Available Core Cooling Modes: Decay heat removal (DHR) systems, Mini DHR (MDHR) system.
RCS Pressure Control Mode:
Standby pressure control (SPC) system.
Backup Pressure Control Modes:
MDHR and DHR system.
Major Parameters (as of 0500, May 7, 1982) (approximate values)
Average Incore Thermocouples:
102 F Maximum Incore Thermocouple:
128'F RCS Loop Temperatures:
A B
Hot Leg 96 F 100*F Cold Leg (1) 80*F 84*F (2) 83*F 90*F RCS Pressure:
96 psig Reactor Building: Temperature:
67*F Elevation 282.9 ft.,)
Water level:
(0.2 ft. from floor Pressure:
-0.10 psig Airborne Radionuclide Concentrations:
3 4.5-E-7 uCi/cc H
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(sample taken 5/4/82) 85 7.8 E-6 uCi/cc Kr (sample taken 5/4/82) 1.8 E-9 uCi/cc particulates
.(sample taken 5/5/82) 1.
Effluent and Environmental (Radiological) Information Liquid' effluents from the T'MI 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 April 30, 1982, through May 6, 1982, the effluents contained no detectable radioactivity at the discharge po, int although individual effluent sources which originated within Unit 2 contained minute amounts of radioactivity. Calculations indicate that less than
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eleven millionths (0.000011) of a curie of tritium was discharged.
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Environmental Protection Agency (EPA) Environrental Data Results from EPA monitoring of the environment around the TMI site were as follows:
3 The EPA measured Kr-85 concentrations (pCi/m ) at several environmental monitoring stations and reported the following results:
Location April 2, 1982 - April 16, 1982 3
(pCi/m)
29 Observation Center 23 Middletown 32
'Yorkhaven (problem with laboratory analysis) 3.
NRC Environmental Data Results from NRC monitoring of the environment around the TMI site were as
.follows:
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The following are the NRC air sample analytical results for the onsite continuous air sampler:
1-131 Cs-137 Sample Period (uCi/cc)
(uC1/cc)
HP-318 April 28, 1982 - May 5, 1982
< 6.6 E-14 < 6.6 E-14 4.
Licensee Radioactive Material and Radwaste Shipment On Tuesday, May 4, 1982,.two drums containing Unit 1 smear samples and miscellaneous equipment were shipped to Babcock and Wilcox, Lynchburg, Virginia.
On Thursday, May 6, 1982, 73 drums containing Unit 1 and Unit 2 contaminated laundry were shipped to Tri-State Industrial Laundries, Utica, New York.
The State of Washington banned Three Mile Island Unit 2, from use of the U.S.
Ecology, Richland, Washington, burial site and suspended the TMI-2 burial permit effective 12:00 (noon), May 5,1982.
This action occurred after U.S, Ecology received a TMI-2 shipment (shipped April 29, 1982) of 74 Low Specific Activity (LSA) waste containers; one container, a 55 gallon drum, had a broken locking ring, and the drum was found open.
The drum contained compacted rags and plastic material with a total activity of approximately 0.11 curies.
The LSA solid waste-was packaged into a plastic material which was intact upon arrival at the site.
The State of Washington inspector at the U.S. Ecology site performed radiological and contamination surveys on the package and found
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. that the material within the 55 gallon drum was intact.
No loose contamination was detectsd and the radiation levels on the drum were'as specified on the shipping documents.
Although no loose radioactive contamination was evidenced, the opening of the 55 gallon drum lid was identified as a violation of the Department of Transportation (DOT.).
regulations, and prompted the banning action.-
Major Activities 1.
Submerced Demineralizer System (SDS).
Processing of SDS batch 24 (reactor coolant bleed tank water) was completed on April 29, 1982, and its performance parameters are included in Attachment 1.
Transfer of remaining reactor building sump water to the SDS feed tanks commenced on April 29, 1982 and was terminated on May 2,1982, when the uppe'r limit of differential pressure (AP) across the SDS prefilter was reached.
This limit was reached after. transfer of approximately 36,000 gallons of sump water.
The SDS feed prefilter and final filter have been changed to accomodate reactor coolant system (RCS)
. processing and the SDS system has been flushed to remove residual chemica.1 contaminants.
The water from the reactor building sump will be held in the SDS feed tanks until a. sufficient time period is avcilable to process the water without interfering with reactor coolant system processing (see RCS processing).
2.
EPICOR II.
The EPICOR II system continued to process SDS effluents during the week and its. performance parameters are included in Attachment 1.
3.
Reactor Coolant System (RCS) Water Processino.
Engineering and construction efforts by tne licensee are continuing in preparation for RCS processing.
NRC/TMIPO review of RCS water processing procedures is complete.
Recovery Operations Plan Change 14, which addresses chemistry specifications for chlorides, dissolved oxygen and dissolved hydrogen is currentJy under review.
A functional test for RCS processing through SDS will be performed on May 10, 1982. This is to be a full demonstration test of all modifications and sampling systems for RCS processing.
The current target date to commence RCS water proce,ssing is May 17,.1982.'
4.
Reactor Buildino Entries.
A' radiation survey in the reactor building (RB) following the removal of approximately 36,000 gallons of water from the casement indicated that the water removal did not significantly reduce the general radiation levels on the 305 ft. elevation.
Areas on the 305 ft.
elevation which are not well shielded from the basement (stairwells and metal gratings) did show a substantial gamma dose rate decrease following the water removal.
These areas were previously identified as hot spots with dove rates ranging from 5 R/hr to 28 R/hr.
The latest measurements in these areas ranged from 2.2 R/hr to 15 R/hr.
The technician who surveyed the 305 ft. elevation accumulated 105 mR in 14 minutes while performing the survey.
The water level in the basement decreased from approximately six inches to one inch when the 36,000 gallons were pumped from the basement to the submerged demineralizer system (SDS) feed tanks. The water transfer was terminated when the feed tank prefilter plugged.
The water level in the RB basement is
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4 expected to increase gradually from react (/ coolant system leakage (approximately 100 GPD).
Air samples during the last RB entry indicated that airb'orne particulate activity was below the maximum permissible concentration (MPC) for workers.
l Nex$1eekRBentriesarescheduledforMondayandThursday,May10 and 13,1982.
The majority of containment ' time will be spent assessing the repair requirements on the polar crane.
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Unit 1 Developments. The licensee has d9cided~to tube expand and reseal virtually all of the 31,000 tubes in the upper ~ tube sheet section of both Once Through Steam Generators'.' The additional work 6ill,be performed because
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further testing has indicated that}otential difects were found with a special d and developed for examining the very testinstrumentspecificallydesign(sshowindicationsof.damageatthetop,
. ends of tubes.
Not all 31,000 tube but the licensee feels"it will be more' efficient to' reseal all of them, whether or not defects were indicatdbin the te'ts. ';A total of 500 to 700 s
tubes in the.two generators are likely to beslugged and taken out of service l permanently.- ~
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- The rep 3 r1:nethod involves the usa of controlled explosive charges to expand i
the tubes.
The licensea report' the-technique was previously used both in newly constructed heht er,cht
..snd tube repairs in the utility industry (sincelate1960's)5 Thq4ength of the tubes'ta be expanded will be the upper 10 inches of the tube in the upee'r tube th6Et~ area which will extend several inches below the area effected-by co'eriision. Unitalqeactor vessel and core internal inspection is' continuing. m 5
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o 5-l Future Meetinas 1.
On May 11, 1982, Lake Barrett will meet with a group of Middletown mothers to discuss issues and concerns related to the cleanup program at TMI Unit 2 and the status of Unit 1.
2.
On May 11, 1982, Lake Barrett will participate in a panel discussion on TMI issues to be aired on cable television in the Central Pennsylvania area. The discussion is sponsored by the West Shore Council of Governments. Other panelists include, Susan Shanaman, Chairman of State Public utility Commission; General DeWitt Smith, Director of Pennsylvania Emergency Management Agency; Representative James Wright, Chairman House Select Committee on THI; representatives from Union of Concerned Scientists; Bipartisan Committee to Vote No; GPUN, and TMI Friends and Family.
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ATTACHMENT 1 SDS PERFORMANCE FOR BATCH NUMBER 24 Average Average Average Radionuclide Influent Effluent DF
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(uc/ml)
(uc/ml)
Cesium 137 1.4 8.3 x 10-4 1.7 x 103 Strohtium 90 5.7 x 10-2 7.5 x 10~3 7.6 EPICOR II PERFORMANCE April 28, 1982 to May 1, 1982 Average Average Average Radionuclide Influent Effluent DF (uc/ml)
(uc/ml)
Cesium 137 7.9 x 10~4 4.5 x 10-7 1.7 x 103 Strontium 90 8.2 x 10-3
<1.0'x 10-5
>;B.2 x 02 Antimony 125 6.5 x 10-4
<3.8 x 10-7
>1.7 x 10 3
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