ML20039F134
| ML20039F134 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 12/14/1981 |
| From: | Barrett L Office of Nuclear Reactor Regulation |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| CON-NRC-TMI-81-070, CON-NRC-TMI-81-70 NUDOCS 8201120035 | |
| Download: ML20039F134 (7) | |
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DISTRIBUTION TMIPO HQ r/f TMI SITE r/f 4 "" TRAL FILE NRC PDR LOCAL PDR December 14, 1981 Site Operations File
-NRC/lMI-81-070 MEMORANDUM FOR:
Harold R. Denton, Director Office of Nuclear Reactor Regulation Bernard J. Snyder, Program Director TMI Program Office FFTI:
Lake H. Barrett, Deputy Program Director TMI Program Office
SUBJECT:
WRC TMI PROGRAM OFFICE WEEKLY STATUS REPORT Enclosed is the status report for the period of December 6,1981 - to Dececher 12, 1981. Major items included in this report are:
Liquid Effluent Releases NRC and EPA Environmental Data 5
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N Radioactive Haterial and Radweste Shipments O
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Submerged Domineralizer System Status Q
g EPICOR II B-8g Reactor Building Entries 9
jJ m \\a v Emergency Drill Public Meetings
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?2 H. Daqcf Lake H. Barrett Deputy Program Director TMI Program Office Enclosure : As stated
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Harold R. Denton December 14, 1981 Bernard J. Snyder cc w/ encl:
EDO OGC Office Directors Commissioner's Technical Assistants NRR Division Directors NRR A/D's Regional Directors IE Division Directors TAS EIS TMI Program Office Staff (15)
PHS EPA DOE Projects Br. #2 Chief, DRPI, RI DRPI Chief, RI Public Affairs, RI State Liaison, RI
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NRC TMI PROGRAM 0FFICE WEEKLY STATUS REPORT December 6 - December 12, 1981
_ Plant Status 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 term cooling "B" (once through steam generator-B).
j-RCS Pressure Control Mode: Standby pressure control (SPC) system.
Backup Pressure Control Modes: Mini decay heat removal (MDHR) system.
Decay heat removal (DHR) system.
Major Parameters (as of 0500, December 11,1981) (approximate values)
Average Incore Thermocouples: 111 F Maxitrum Incore Thermocouple:
136 F RCS Loop Temperatures:
(The last cycle of natural circulation occurred in the "B" loop on 12/9/81 and in the "A" loop on 12/11/81)
A B
Hot Leg 104 *F 107 F Cold Leg (1) 70 F 81 F (2) 70 F 87 F RCS Pressure: 95 psig i
Reactor Building: Tempera ture :
62 F Water level:
Elevation 287.2 ft. (4.7 ft. from floor) via penetration 401 manometer Pressure:
-0.2 psig Concentration : 5.3 x 10-6 uCi/cc Kr-85 (Sample taken 12/9/81) l Effluent and Environmental (Radialogical) 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 December 4,1981, through December 10,1981, the effluents contained no detectable radioactivity at the discharge point and individual effluent sources which originated within Unit 2 contained no detectable radioactivity.
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2.
Environmental Protection Agency (EPA) Environmental Data.
Results from EPA monitoring of the environment around the TMI site were as follows:
3 The EPA measured KR-85 concentrations (pCi/rn ) at several environmental monitoring stations and reported the following results :
Location November 6 - November 20, 1981 3
(pCi/m )
Goldsboro 22 Observation Center 23 Middletown 30 Yorkhaven 30 All of the above levels of Kr-85 are considered to be background level s.
No radiation above normally occurring background levels was detected in any of the samples collected from the EPA's air and gamma rate networks during the' period from December 2,1981, through December 10, 1981.
3.
NRC Environmental Data. The Environmental Protection Agency's counting system on which the NRC's air samples are counted is out of service for repairs.
Analytical results will be reported in a future weekly
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status report when they become available.
4.
Licensee Radioactive Material and Radwaste Shipments.
On Monday, December 7,1981, three packages each containing one liter samples from the Unit 1 waste evaporator condensate storage tank were mailed to Teledyne Isotopes, Westwood, New Jersey.
On Monday, December 7,1981, an EPICOR II dewatered resin liner (F-14) was shipped to U.S. Ecology, Hanford, Washington.
On Tuesday, December 8,1981, an EPICOR II dewatered resin liner (F-15) was shipped to U.S. Ecology, Hanford, Washington.
On Wednesday, December 9, 1981, 20 metallic boxes of Unit 1 LSA waste were shipped to U.S. Ecology, Hanford, Washington.
On Friday, December 11, 1981, an EPICOR II dewatered resin j
liner (F-16) was shipped to U.S. Ecology, Hanford, Washington.
On Friday, December 11, 1981, two Unit 1 solidified evaporator bottoms were shipped to U.S. Ecology, Hanford. Washington.
On Saturday, December 12, 1981,105 55 gallon drums of Unit II l.
laundry were shipped to Utica, New York.
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l Major Activities 1.
Submerged Demineralizer System (SDS).
Processing of batch number 12 was completed on December 9,1981.
During December 9,1981, to December 11, 1981, approximately 50,000 gallons of reactor coolant bleed tank water (batch number 13) were transferred to the SDS feed
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tanks in the fuel handling building.
To date, approximately 290,000 gallons of reactor building sump water have been transferred from the reactor building sump and processed.
Transfers of reactor building sump water are expected to continue following the processing of batch number 13.
SDS performance, parameters for batch 12 are attached.
I 2.
EPICOR II.
Processing of SDS effluent through the EPICOR II system continued this week.
Approximately 290,000 gallons of reactor
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building sump water have been polished.
Recent performance parametsrs l
for EPICOR II are attached.
3.
Reactor Building Entries.
Reactor building entry 24 was completed on December 9,1981.
Tasks were performed in preparation for the gross decontamination experiment.
Specific tasks accomplished were (1) placement of splash covers over various equipment including the Power Operated Relief Valve (PORV) and the block valve, (2) an inventory of transient combustible materials, (3) repair and
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repositioning of closed
- cuit television cameras, (4) fixed point radiological surveys and a4 sampling, and (5) placement of thermo-luminescent dosimeters and.? dine samplers.
The entry scheduled for December ll,1981, has been cancelled.
The next entry is tentatively scheduled for December 15, 1981.
l 4.
Emergency Drill.
On December 10, 1981, the licensee conducted the annual exercise of the TMI-2 Emergency Plun by simulating a site emergency. NRC onsite staff also participated in the drill.
Preliminary results from the licensee conducted critique indicate a satisfactory drill.
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4 Meetings Held The NRC's Advisory Panel for the decontamination of TMI Unit 2 met on
- December 10, 1981, in Lancaster. The major topic of discussion was the financial problems that are hindering the pace of the cleanup of Unit _2.
Presentations were made by GPU, NRC and EPA on the status of their activities.
Comments on the' progress of various proposed _ solutions to the financial impasse were presented by GPU, Edison Electric' Institute (EEI), TMI Alert and Lancaster Environmental Action Federation (LEAF).
The next meeting will continue the discussion on the financial situation.
i Future Meetings L
1.
On Friday, February 26, 1982, Lake Barrett will be speaking for the -
dinner meeting being held by the Engineers Week Joint Planning Council to honor Lehigh Valley's Engineer of the Year and Young Engineer of the Year.
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.
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3.
The NRC's Advisory Panel for the Decontamination of TMI Unit 2-is i
scheduled to meet on January 13 and January 28, 1982, at the Holiday Inn, 2nd and Chestnut Street, Harrisburg, PA, from 7:00 to 10:00 PM.
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ATTACHMENT SDS Performance for Batch Number 12 (Reactor Coolant Bleed Tank Water)
Average Average Average Radionuclide Influent Effluent DF (uc/ml )
. (uc/ml )
Cesium 137 19.0 3.3 x 10-3 5.7 x 103 Strontium 90 0.92 2.2 x 10-2 4.1 x 101 EPICOR II Performance for Reactor Coolant Bleed Tank Water December 2,1981 to December 9,1981 Average Average Average Radionuclide Influent Effluent DF (uc/ml )
(uc/ml) i Cesium 137 3.7 x 10-3 3.9 x 10-7 9.5 x 103 Strontium 90 2.1 x 10-2 1.6 x 10-5' l.3 x 103 Antimony 125 5.5 x 10-3 3.8 x 10-7 1.4 x 104
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