ML20039F022
| ML20039F022 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 12/21/1981 |
| From: | Barrett L Office of Nuclear Reactor Regulation |
| To: | Harold Denton, Snyder B Office of Nuclear Reactor Regulation |
| References | |
| CON-NRC-TMI-81-073, CON-NRC-TMI-81-73 NUDOCS 8201110728 | |
| Download: ML20039F022 (7) | |
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DISTRIBUTION TMIPO HQ r/f TMI SITE r/f December 21, 1981 ENTRAL FILE NRC/TMI-81-073 NRC PDR LOCAL PCR Site Operations File HEMORANDUM FOR:
Harold R. Denton, Director 3
U Office of Nuclear Reactor Regulation g
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Bernard J. Snyder, Program Director S.N TMI Program Office
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RECElVED NIOOIb FROM:
Lake H. Barrett, Deputy Program Director
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SUBJECT:
NRC TMI PROGRAM 0FFICE WEEKLY STATUS REPORT g
f Enclosed is the status report for the period of December 13; 1981 to December 19, 1981. Major items included in this report are:
Liquid Effluent Releases NRC and EPA Environmental. Data Radioactive Material and Radwaste Shipments TMI Occupational Exposure
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Submerged Domineralizer System Status EPICOR II Reactor Building Entries Spurious Siren Activation Public Meetings Original sididf Lake 8t.Barrett Lake H. Barrett Deputy Program Director TMI Program Office
Attachment:
As stated 8201110728 811221 PDR ADOCK 05000320 i
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ED0 OGC Office Directors Comnissioner's Technical Assistants NRR Division Directors HRR A/D's Regional Directors IE Division Directors TAS EIS THI Program Office Staff (15)
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Projects Br. #2 Chief, DRPI, RI DRPI Chief, RI Public Affairs, RI State Liaison, RI l TMIPO P
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NRC TMI PROGRAM 0FFICE WEEKLY STATUS REPORT
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y; December 13 - December 19, 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)..
RCS Pressure Contro'l Mode: Standby pressure control (SPC) system.
Backup Pressure Control Modes: Mini decay heat reaoval (MDHR) system.
Decay heat removal (DHR) system.
h Major Parameters (as of 0500, December 18,1981) (approximate values)
Average Incore Thermocouples : 109 F Maximum Incore Thermocoupie:
133*F RCS Loop Temperatures:
(The last cycle of natural circulation occurred in the "B" loop on 12/13/81 and in the "A" loop
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on 12/11/81)
A B
Hot Leg 795 F 100 F Cold Leg (1) 70*F 88*F (2) 88 F 90 F RCS Pressure: 95 psig; Reactor Building: Timperature:
63 F
' Water level:
Elevation 287.2 ft. (4.7 ft. from floor) via penetration 401 manometer i
Pressure :
-0.2 ps g Concentration: 5.3 x 10-6 uCi/cc Kr-85 l
~(Sample taken 12/9/81)
Effluent and Environmental (Radiological) Infonnation 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 Dccember 11,1981, through December 17,1981, 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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Environmental Protection Agency (EPA) Environmental Data. Results from 2.
EPA monitoring of the environment around the TMI site were as follows:
EPA Kr-85 sample results were not available due to delays in reporting analytical results.
Area Kr-85 concentrations will be reported in a future report.
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 9,1981, through De'cember 17, 1981.
3.
NRC Environmental Data.
Results from NRC monitoring of the environment around the TMI site were as follows:
The folloning are the NRC air sample analytical results for the onsite continuous air sampler:
I-1 31 Cs-137 (uCi/cc)
(uCi/cc)
Sampl e_
Period HP-295*
November 18, 1981 - November 24, 1981
<9.2 E-14 <9.2 E-14 l
HP-296 November 24, 1981 - December 2,1981
<5. 9 E-14 <5.9 E-14 l
HP-297 December 2 1981 - December 10, 1981
<6.1 E-14 <5.1 E-14 HP-298 December 10, 1981 - December 17,1981
<7.3 E-14 <7.3 E-14
- Error in last report.
Sample number was reported as.HP-294.
4 Licensee Radioactive Material and Radwaste Shipments.
b On. Tuesday, December 15~ ~ t '1981 one EPICOR II dewatered' resin 1
liner (liner F-3) was ship' ped,to U.S. E'cologi,'Richla'nd, l
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On Tuesday, December 15, 1981, one EPICOR II dewatered resin liner (liner F-17) was shipped to U.S. Ecology, Richland, Washington.
On Thursday, December 17, 1981, 35 drums containing Unit 1 an'd Unit 2 contaminated laundry were shipped to Tri-State Industrial l
l Laundry Inc., Utica, New York.
On Friday, December 18,1981, ten 60. ml SDS (Submerged Demineralizer i
l System) samples from Unit II were shipped to Oak Ridge National l
L Laboratory,.0ak Ridge, Tennessee.
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THI Occupational Exposure.
Licensee TLD (Thermoluminescent Dosimeter) records indicate the following Unit 2 total occupational radiation exposure for 1981.
November 1981 16 man-rem **
Total 1981 (January-November) 126 man-rem Man-rem is an expression for the summation of whole body doses to individuals in a group.
Thus, if each member of a population group of 1,000 people were to receive a dose of 0.001 rem (1 millirem), or if two people were to receive a dose of 0.5 rem (500 millirem) each, the total man-rem dose in each case would be one man-rcm.
Major Activities 1.
Submerged Demineralizer System (SDS).
Processing of batch number 13 was completed on December 18, 1981.
Batch 13 contained miscellaneous contaminated water which was staged in the reactor' coolant bleed tank for processing.
Reactor building sump water processing will recommence after filter media change out and some minor repairs to the SDS.
To date, 290,000 gallons of reactor building sump water have been processed. SDS performance parameters for batch number 13 are attached.
2.
EPICOR II_.
EPICOR II processing of SDS effluent continued this week. The latest performance parameters for EPICOR II are attached.
3.
Reactor Building Entries.
Reactor building entries 25 and 26 were completed on December 15 and 17,1981.
During these entries an extensive characterization of surface contamination was completed in preparation for the decontamination experiment.
Surface con-tamination samples were taken from 48 locations in the reactor building.
The sampling technique included a vacuuming device for collecting loose surface contamination and a boring machine in conjunction with the vacuum for collecting fixed contamination.
Reactor building air samples were taken; a survey was made of certain areas where there was evidence of high temperatures during the accident.
Reactor building entries will continue after the holidays.
Decon-tamination experiment water washes inside the reactor building are scheduled to commence in mid January 1982.
4.
Spurious Siren Activation.
On December 17, 1981, between 5:00 and 6:00 PM several early warning sirens in the vicinity of TMI sounded
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inadvertently.
The licensee reported that the siren activation was caused by a decoding device malfunction.
The sirens were installed by the licensee as a part of the area emergency preparedness network.
Control of the sirens is scheduled to be turned over to the local counties by next week.
4-t Future Meetings 1.
On Friday, February 26, 1982, Lake Barrett will be speakiEg 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.
3.
The NRC's Advisory Panel for the Decontamination of TMI Unit 2 is 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 13 (Reactor Coolant Bleed Tank Water)
Average Average Average Radionuclide Influent Effluent DF (uc/ml )
(uc/ml )
4 3
i Cesium 137 5.7 4.8 E-3 1.2 x 10 I
i Strontium 90
.59 2.0 E-2 2.9 x 10 l
EPICOR II Performance for Reactor Coolant Bleed Tank Water l
December 9,1981 to December 16, 1981 l
Average Average' Average l
Radionuclide Influent Effluent DF (uc/ml)
(uc/ml)
Cesium 137 5.1 x 10-3 2.4 x 10-7 2.2 x 104 Strontium 90 2.5 x 10-2
< 1.1 x 10-5
> 2.3 x 103 Antimony 125 3.5 x 10-3 3.9 x 10-7 9.0 x 103 l
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