ML20050S739
| ML20050S739 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 04/05/1982 |
| From: | Barrett L Office of Nuclear Reactor Regulation |
| To: | Harold Denton, Snyder B Office of Nuclear Reactor Regulation |
| References | |
| CON-NRC-TMI-82-019, CON-NRC-TMI-82-19 NUDOCS 8204140542 | |
| Download: ML20050S739 (7) | |
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DISTRIBUTION TMIP0 HQ r/f TMI SITE r/f W RAL FILE NRC PDR LOCAL PDR April 5,1982 Sita Operations File NRC/THI-82-019 d*
q HEM 0HANDUM FOR:
Harold R. - Denton, Director IlECE!V<ID B
Office of Naclear Reactor P.egulation 0
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( 8 tem mraEu" Bernard J. Snyder, Program Director
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FROM:
Lake H. Barrett, Deputy Program Director
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THI Program Office
SUBJECT:
NRC TMI PROGRAM OFFICE WEEKLY STATUS REPORT Enclosed is the status report for the period of March 28,1982 to April 3,1982 flajor items included in this report are:
Liquid Effluents NRC and EPA Environmental Data Radioactive Material and Radwaste Shipments Submerged Domineralizer System Status EPICOR TI Reactor Building $ntries Reactor Coolant Systiem Water Processing Public Meetings original signed by A. Fasano Lake H. Barrett Deputy Program Director i
THI Program Office
Enclosure:
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I NRC TMI PROGRAM 0FFICE WEEKLY STATUS REPORT March 28,1982 - April 3,1982 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 Control Mode: Standby pressure control (SPC) ' system.
Backup Pressure Cont'rol Modes: Mini decay heat removal (MDHR) system.
Decay heat removal (DHR) system.
Major Parameters (as of 0500, April 2,1982) (approximate values)
Average Incore Thermocouples : 103*F Maximum Incore Thermocouple:
131 F RCS Loop Temperatures:
A B
Hot Leg 96 F 99*F Cold Leg (1) 90*F 83*F (2) 84 F 82*F RCS Pressure: 95 psig Reactor Building:
Temperature :
67*F Water level:
Elevation 283.2 ft. (0.5 ft. from floor)
Pressure:
-0.27 psig Airborne Radionuclide Concentrations :
2.0 E-7 uCi/cc H3 (sample taken 3/31/82)
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4.1 E-6 uCi/cc Kr85 (sample taken 3/30/82) 1.
Effluent and Environmental (Radiological) Information Liquid effluents from the TMI site released to the Susquehanna River after processing, were made within the regulatory limits and i
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in accordance with NRC requirements and City of Lancaster Agreement
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dated February 27, 1980.
During the perio'd March 26, 1982, through April 1,1982, 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) E_nvironmental Data.
Resul ts from EPA monitoring.of the environmen't around the TMI site were as follows:
The EPA measured Kr-85 concentrations (pCi/m3) at several environmental monitoring stations and reported the following resul ts :
Location February 26,1982 - March 12,1982 (pC1/m3)
Gol ds boro 25 Observation Center 29 Middletown 29 Yorkhaven 29 All of the above levels of Kr-85 are considered to be background l evel 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 March 24, 1982-through April 1,1982.
3.
NRC Environmental Data Results from NRC monitoring of the environment around the TMI 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 (uCi/cc)
(uCi/cc)
HP-313 March 24,1982 - April 1,1982
<5.6 E-14 <5.6 E-14 4.
Licensee Radioactive Material and Radwaste Shipments On Tuesday, March 30, 1982, an internally contaminated piece of equipment from the Unit 1 waste gas system was shipped to the Babcock and Wilcox Research Center, Lynchburg, Virginia.
On Wednesday, March 31, 1982, 18 samples (smears) from the Unit 1 control drive lead screw were shipped to the Babcock and Wilcox Research Center, Lynchburg, Virginia.
3 On Wednesday, March 31, 1982, eight liquid samples from the Unit 2 submerged demineralizer system were shipped to Oak Ridge National Laboratory, Oak Ridge, Tennessee.
- i On Thursday, April 1, 1982, 43 drums contuining Unit 1 and Unit 2 contaminated laundry were shipped to Tri-State Industrial Laundries, Utica, New York.
Major Activities 1.
Submerged Demineralizer System (SDS).
The SDS is shutdown for minor maintenance.
2.
EPICOR II.
The EPICOR II System is shutdown because of lack of water
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to be processed.
3.
Reactor Building Entries.
A preliminary review of data gathered during the gross decontamination experiment indicates t. hat based on swipe surveys for both beta and gamma, the decontamination factors (DF= pre-decon surveys The floor surface DF'ys ) on floor surfaces averaged between post-decon surve s based on contact beta measurements averaged between 2 and 10.
These figures indicate that the techniques used during the decontamination experiment were effective in removing loose surface contamination.
Breathing zone air (BZA) samplers from entry team members indicated that airborne activity decreased by a factor of approximately 5 following the decontaminati'on experiment.. Although this calculation is based on a very limited number of BZA samples and therefore may be premature, it does support the conclusicn that the gross decontamination experiment was effective in removing loose surface contamination.
The area gamma dose rates, however, did not decrease significantly following the decontamination experiment.
An average area pamma DF on the reactor building floor surfaces was approximately 1.3.
The disparity in the relatively high swipe / contact beta DF's and the relatively low area gamma DF's appears to indica,te that the gamma radiation fields in the reactor building are due to sourc,es other than loose surface contamination.
The comparison of pre and post decontamination collimated gamma spectrometer measurements and the analysis of surface bore samples have not been completed.
When available, this information should provide indications of whether the gamma dose rates are coming from fixed surface contamination or from other sources.
The next reactor building entry is scheduled for Wednesday, April 7,1982 During this entry, work will commence on the installation of a pump which will be used to pump the remaining water from the 282 ft.
elevation floor to the SDS.
It is expected that the pump will be ready for service later this month.
There are still approximately 30,000 gallons (six inches) of water on the floor of the 282 ft, elevation.
It is believed that the radionuclides in the water and/or on the surfaces of the 282 ft. elevation constitute a major source of radiation in all areas of the reactor building.
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4 Reactor Coolant System (RCS) Processing.
Engineering efforts are still in progress for processing the RCS.
Fabrication and construction efforts are underway for needed hardware modifications.
The NRC TMI/P0 site office has approved approximately 25 percent of the procedures needed for 'RCS processing.
The remaining procedures are under review.
The NRC TMI/PO is awaiting receipt of a request by the licensee to revise the Recovery Operations Plan to incorporate changes to accomodate RCS processing.
RCS processing is scheduled to begin in June 1982.
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? future Meetings 1.
On Wednesday, April 14, 1982, Lcke Barrett will be the keynote speaker i.,
,for the Southern Pennsylvania Association of Occupational Health Nurses, to.be held at the Holiday Inn in ' York.
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0n Thursday, April 22, 1982, the TMI Advisory Panel for the decontamination
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' of T!fd Unit 2-will hold a meeting in Harrisburg at the Holiday Inn
' located at Second and Chestnut Street, to discuss issues related to the
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