ML20052A218
| ML20052A218 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 03/29/1982 |
| From: | Barrett L Office of Nuclear Reactor Regulation |
| To: | Harold Denton, Snyder B Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20052A219 | List: |
| References | |
| CON-NRC-TMI-82-016, CON-NRC-TMI-82-16 NUDOCS 8204280017 | |
| Download: ML20052A218 (8) | |
Text
DISTRIBUTION TMIPO HQ r/f TMI SITE r/f N AL FILE NRC PDR LOCAL PDR Site Operations FPe March 29,1982 flRC/TitI-82-016 co v
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b MEMORANDul4 FOR:
Harold R. Denton, Director
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Office of Huclear Reactor Regulation il #
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Bernard J. Snyder, Program Director 71
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7 TMI Program Office 4
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Lake H. Barrett, Deputy Program Director
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e TMI Program Office
SUBJECT:
fiRC Till PROGRAM 0FFICE WEEKLY STATUS REPORT Enclosed is the status report for the period of March 21,1982 to March 27,1982. Major items included in this report are:
Liquid Effluents NRC and EPA Environmental Data Radioactive flaterial and Radwaste Shipments TMI Occupational Exposure Submerged Domineralizer System Status EPICOR II Reactor Building Entries Reactor Coolant System Water Processing Purt fication System Filter Removal Public Meetings Lake 11. Barrett Deputy Prograu Director TdI Program Office
Enclosure:
As stated 820428 oo17
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liarold R. Denton March 29, 1982 Bernard J. Snyder cc w/enci:
EDO OGC Office Directors Coenaissioner's Technical Assistants NRR Division Directors NRR A/D's Regional Directors IE Division Directors T/d EIS THI Program Office Staff (15)
PHS EPA DOE Projects Br. #2 Chief, DRPI, RI DRPI Chief, RI Public Affairs, RI State Liaison, RI o,,,c, p.TMI PO TMIPO TMIPO TMIPO TMIPO TMIP0 G Ka l....../j......
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NRC TMI PROGRAM 0FFICE WEEKLY STATUS REPORT March 21,1982 - March 27,1982 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 Control Modes: Mini de' cay heat removal (MDHR) system.
Decay heat removal (DHR) system.
Major Parameters (as of 0500, Perch 26,1982) (approximate values)
Average Incore Thermocouples : 101 *F Maximum Incore Thermocouple:
133*F RCS Loop Temperatures:
A B
Hot Leg 95 F 98 F Cold Leg (1) 79*F 82*F (2) 82'F 89 F RCS Pressure: 100 psig Reactor Building: Temperature :
64 F Water level:
Elevation 283.2 ft. (0.5 ft. from floor)
Pressure :
-0.15 psig Airborne Radionuclide Concentrations :
1.1 E-6 uCi/cc H3 (sample taken 3/24/82)
<7.5 _E-6 uCi/cc Kr85 (sample taken 3/1/82) 1.
Effluent and Environmental (Radiological) Information Liquid effluents from the TMI site released to the Susquehanna r
River after processing, were made within the regulatory limits and in accordance with NRC requirements and City of Lancaster Agreement dated February 21, 1980.
During the period March 19, 1982, through March 25,1982, the effluents contained no detectable radioactiv.ity at the discharge point and individual effluent sources, which originated.within Unit 2, contained no detectable radioactivity.
2.
Environmental Protection Agency (EPA) Environmental Data The EPA Middletown Office has not received the analytical i
results for Kr-85 measurements around the TMI site from the EPA's Counting Laboratory at Las Vegas, Nevada.
These results will be included in a subsequent report.
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 March 7,1982 through March 25, 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 Sample Period (uCi/cc)
(u Ci / c_c_)
H P-312
- March 17,1982 - March 24,1981
<6.1 E-14 <6.1 E-14
(*The NRC sample number reported for the week of March 10-17, 1982, was in error.
HP-311 is the correct identification number.)
4.
Licensee Radioactive Material and Radwaste Shipments On Monday, March 22; 1982, seven liquid samples from Unit 1 (various plant locations) were shipped to the Westinghouse Electric Company Laboratory, Madison, Pennsylvania.
On Monday... March 22, 1982, 72 drums and six metal containers of Low Specific Activity (LSA) waste from Unit I were shipped to them-Nuclear Systems, Inc., Barnwell, South Carolina.
On Wednesday, March 24, 198'2, two liquid samples from Unit 1 were shipped to the Westinghouse Electric Company Laboratory, Madison, Pennsylvania:
On Wednesday, March 24, 1982, fourteen liquid samples from the Unit 2 SDS (Submerged Demineral.izer System) were shipped to Oak Ridge National Laboratory, Oak Ridge, Tennessee.
On Thursday, March 25, 1982, an internally contaminated piece of equipment from the Unit 2 SDS was shipped to the Westinghouse Electric Company, Forest Hills Site, Pittsburgh, Pennsylvania.
5.
TMI Occupational Exposure Licensee TLD (Thermoluminescent Dosimeter) records indicate the following Unit 2 total occupational radiation exposure for 1982:
February 1982 29 man-rem Total 1982 (January-February) 46 man-rem Major Activities 1.
Submerged Demineralizer System (SDS).
The SDS is secured for minor maintenance.
2 EPICOR II.
The EPICOR 11 system processed the last of the SDS effluent and also the EPICOR II building sump.
Performance parameters are enclosed in Attachment 1.
3.
Reactor Building Entries.
Except for sample analysis and data interpretation, the gross decontamination experiment.was concluded with.three reactor building entries during the week of March 21,1982.
The following tasks were performed in the reactor building this week (week of March 21,1982);
Decontamination of a 150 ft2 section of the reactor building floor using a detergent and mechanical scrubber.
Decontamination of a 150 ft2 section of the reactor building floor using a phosphoric acid solution and a mechanical scrubber, Decontamination of a 500 ft2 section of the reactor building floor using a strippable coating, Portable gamma spectrometer survey of the 305 ft. and 347 ft.
elevations, Concrete bore samples obtained, Radiation survey of polar crane, Still and motion picture photography.
The effectiveness of the gross decontamination techniques will be reported in future Weekly Status Reports.
One reactor building entry is scheduled for the week of March 28, 1982.
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4.
R_e_ actor Coolant System (RCS) Processing.
Engineering efforts are still in progress for processing the RCS.
The NRC TMI/P0 site office has received and is reviewing the first of the procedures needed for RCS processing.
The majority of the procedures are expected.to be received during the next two weeks.
5.
Purification System Filter Removal _.
A team of eight technicians removed the remaining four filters from'the letdown and makeup systems (purification system).
Two of the filters had been removed from the system earlier (1981).
Filters upstream and downstream of.
the purification demineralizers and filters on the discharge of the high pressure makeup pumps were removed last week.
Following the filter removals, technicians used' vacuum cleaners to remove debris from the filter. housings.
The filters are scheduled to be shipped in April to a DOE contractor for analysis.
On Monday, March 22, 1982, the licensee declared an unusual event when control room operators noticed that excessive makeup was going to the reactor coolant system during the filter removal operation.
It was determined that the problem was caused by leakage through a reach rod operated filter isolation valve.
When technicians opened the filter housing, approximately 150 gallons of makeup system (SPC system) water spilled onto the floor of the filter cubicl e.
The water was vacuumed off the floor into 55 gallon drums..The highest dose rate measured on contact with any of the drums was 350 mr/hr.
Operators later rerouted the 90 psig makeup water flow and closed additional valves in series to stop the leak.
The total personnel exposure for the filter removal and cleanup operation was approximately one man-rem.
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N Meeting Held On Tuesday, March 23, 1982, the TMI Advisory Panel met with the NRC Commissioners in Washington, DC.
The Advisory Panel asked the Commission to increase its efforts to resolve the political / financial problems that are delaying the cleanup.
The Commission has written to U.S. Senator James McClure, Chairman of the Energy Subcommittee, Representative Alan Simpson, Chairman of the Subcommittee on Nuclear Regulation, and Representative Morris Udall, Chairman of the Subcommittee on Energy and the Environment, to urge that " greater federal participation in assuring financial viability is a prerequisite to an acceptably rapid (cleanup) program."
A copy of the letter to Sena, tor McClure is enclosed as Attachment 2.
Advisory Panel Chairman John Min ^nich, wrote Chairman Palladino on March 17,1982, with the Panel's second report, concluding.that there is as yet no significant financial commitment to fund the cleanup.
The report also concludes that "given the long-term serious hazards posed by TMI-2," the Commission should proceed expeditiously to insure the cleanup.
A copy of Chairman Minnich's letter is enclosed as Attachment 3.
The citizen's advisory panel made several suggestions to the Commissioners at the March 23, 1982 meeting that are being considered which are:
1.
Urge President Reagan to appoint a White House staff member to serve as a focal point to resolve TMI problems.
2.
Work to convince its utility companies to contribute funds for the TMI cleanup, e.g. implement the Edison Electric Institute recommendation.
3.
Hold a Commission meeting on the cleanup in the Harrisburg area, to hear public comments on the cleanup plans.
Future Meeting On Wednesday, April 14, 1982, Lake Barrett will be the keynote speaker for the Southern Pennsylvania Association Occupational Health Nurses, to be held arthe~ Holiday Inn in York.
3 l'
r ATTACHMENT 1 i
EPICOR 11 Performance March 16,1982 to March 22, 1982 Average Average Average Radionuclide Influent Effluent DF (uc/ml)
(uc/ml)
- 1. 3 x 10- 2 2.8 x 10-7 4.7 x 104
>8.2 x 102 Strontium 90 1.4 x 10-2
<7. 5 x 10-5,
I Antimony 125 2.7 x 10-3
<2. 9 x 10-7
>9.4 x 103 i
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