ML20053D698
| ML20053D698 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 05/28/1982 |
| From: | Barrett L Office of Nuclear Reactor Regulation |
| To: | Harold Denton, Snyder B Office of Nuclear Reactor Regulation |
| References | |
| CON-NRC-TMI-82-035, CON-NRC-TMI-82-35 NUDOCS 8206070223 | |
| Download: ML20053D698 (7) | |
Text
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DISTRIBUTION TMIPO HQ r/f TMJ SITE r/f J iTRAL FILE NRC PDR LOCAL PDR Si rations
!!ay 28,1982 Y
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NRC/Till-82-035 g
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itE!!0RAllDUll FOR:
liarold R. Denton, Director macas mumm -11 Office of Nuclear Reactor Regulation anspu b
Bernard J. Snyder, Program Director Tiil Program Office N
FROH:
Lake 11. Barrett, Deputy Program Director TMI Program Office
SUBJECT:
NRC Till PROGRAll 0FFICE WEEKLY STATUS REPORT Enclosed is the status report for the period of flay 23, 1982 to May 28,1982.
11ajor items included in this report are:
Liquid Effluents NRC and EPA Environmental Data Radioactive !!aterial and Radwaste Shipments TMI Occupational Exposure Submdrged Demineralizer System Status EPICOR II Reactor Coolant System Water Processing Reactor Building Entry Subnuged Domineralizer System Vessel Shipment Public Meetings Odginta signedby s e3.Barrd t r Lake H. Barrett Deputy Program Director Till Program Office
Enclosure:
As stated l
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4 Ilarold R. Denton 14ay 28, 1982 Bernard J. Snyder cc w/ enc 1:
EDO OGC Office Directors Comissiuncr's Technical Assiltants NRR Division Directors NRR A/D's Regional Directors IE Division Directors TAS EIS THI Program Office Staff (15)
PilS EPA DOE Projects Br. #2 Chief, DRPI, RI DRPI Chief, RI Public Affairs, RI State Liaison RI
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t NRC TMI PRO $ RAM 0FFICE WEEKLY STATUS REPORT May 23, 1982 - May 28, 1982 Plant Status CoreCoolingNode:
Heat transfer from the reactor coolant system (RCS) 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.
NOTE:
During Reactor Coolant System feed and bleed, pressure will be maintained with a Reactor Coolant Bleed Tank Pump. Automatic back up pressure' control will be provided by the standby pressure control system.
Backup Pressure Control Modes:
MDHR and DHR system.
Major Parameters (as of 0535, May 28, 1982) (approximate values)
Average Incore Thermccouples:
100*F Maximum Incore Thermocouple:
129*F RCS Loop Temperatures:
A B
Hot Leg 96*F 99'F Cold Leg (1) 82*F 83*F (2) 85'F 88'F Pressure:
73 psig NOTE:
During reactor coclant system feed and bleed, pressure is maintained at approximately 70 psig.
' Reactor Building: Temperature:
70*F Pressure:
-0.6 psig Airborne Radionuclide Concentrations:
3 5.7 E-7 uCi/cc H (sample taken 5/25/82) 85 1.7 E-6 uCi/cc Kr (sample taken 5/25/82) 9.1 E-10 uCi/cc particulates
_(sample taken 5/26/82)
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l 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 in accordance with NRC requirements and City of Lancaster Agreement dated l
February 27, 1980.
During the' period May 21, 1982, through May 27, 1982, the effluents contained no detectable radioactivity at the discharge point although individual effluent sources which originated within Unit 2 contained minute amounts.of radioactivity.
Calculations indicate that less than one ten-thousandth (0.0001)of a curie of tritium was discharged.
2.
Environmental Protection Agency (EPA) Environmental Data The EPA Middletown Office has not received the gnvironmental Kr-85 analytical results for the samples which were taken April 16, 1982, through May 21, 1982, 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 the EPA's air and gamma rate networks during the period from May 19, 1982 through May 27, 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-131 Cs-137 Sample Period (uCi/cc)
(uCi/cc)
HP-320 Mav 17, 1982 - May 26, 1982
<5.3 E-14 < 5.3 E-14 4.
Licensee Radioactive Material and Radwaste Shipment On Monday, May 24, 1982, 20 metal boxes containing Unit i non-compacted trash (Low Specific Activity, LSA) were shipped to Chem Nuclear Systems, Inc., Barnwell, South Carolina.
On Monday, May 24, 1-982, 63 drums ?nd 6 metal boxes containing Unit 1 compacted and non-compacted trash (LSA) were shipped to Chem Nuclear Systems, Inc., Barnwell, South Carolina.
On Thursday, May 27, 1982, 53 drums containing Unit 1 and Unit 2 contaminated laundry were shipped to Tri-State Industrial Laundries,-
Utica, New York.
5.
THI Occupational Exposure Licensee TLD (Thermoluminescent Dosimeter) records indicate the following Unit 2 occupational radiation exposure for 1982:
April 1982 19 man-rem *
~ ~ - 120 man-rem Total 1982 (January-April)
- 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 regeive 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-rem.
Major Activities 1.
Submerged Demineralizer System (SDS).
Processing of the first batch of Reactor Coolant System (RCS) water is continuing.
As of 11:59 PM on May 28, 1982, the total amount of RCS water processed was approximately 40,000 gallons.
SDS processing parameters will be provided following completion of the batch.
No unanticipated problems have occurreo.
2.
EPICOR II.
The EPICOR II system is shutdown because no water is ready for processing.
3.
Reactor Coolant System (RCS) Feed and Bleed.
A reactor coolant system (RCS) sample was taken on May 24, 1982. Analysis results of this sample along with the analysis results of previous samples which were taken before and during the first feed and bleed cycle are listed in.
The second feed and bleed cycle is expected to commence during the week of May 30, 1982.
4.
Reactor Building Entry (May 26,1982).
Radiation surveys and valve inspections were performed inside the "D-rings" (primary system radiation barriers) to support the planned depressurization and partial draining of the reactor coolant system (RCS).
The surveys and inspections were made at high point vent valves which will be used initially to vent the primary system components and then to inert the primary system with nitrogen as the RCS water is drained to a level which will. permit opening a control rod drive mechanism (CRDM).
The CRDM disassembly and CRD lead screw removal is sequenced to support a closed circuit television inspection of the reactor vessel upper internals in July 1982. The I
closed circuit television camera will be lowered into the reactor vessel through the disassembled CRDM.
A two man team surveye'd and inspected the valves in the A "D-ring".
Radiation readings in the vicinity of most of the va,1ves were in the 300 mR/hr range.
Corrosion was observed on the vent valves. The inspection team descended to a platform below the pressurizer and the primary pumps (308 ft. elevation).
The radiation levels were in the 3 R/hr range in this area.
The isolation valve on a one inch drain valve e
from the RCS cold leg indicated 20 R/hr on contact.
This one inch drain line would typically be ushd as a connection point for a tygon tube level indicator during refuelings. A tygon tube was observed in the vicinity of the drain line.
No signs of heat damage to the tygon tube were apparent.
From the 308 ft. elevation the team had a clear view of the 282 ft. elevation floor (floor of the basempnt inside the "D-ring). The floor looked like a dried river bed witti deposits of solids that were estimated to be one inch thick in places.
A remote radiation surNy was performed inside the B "D-ring".
This was the first survey inside th.e B "D-ring" and the results will be verified during subsequent entries. The survey result indicated that the radiation levels in the B "D-ring" were substantially higher than in the A "D-ring" (the pressurizer is in the A "D-ring").
Radiation levels on a 356 ft. elevatiun platform in the B "D-ring" (between the top of the steam generator and the top of the hot leg) were 32 R/hr.
The area radiation levels near most of the vent valves were in the 10 R/hr range.
The radiation levels appeared to decrease with distance away from the steam generator.
Prior to exiting the reactor building (RB) the B "D-ring" survey team lowered a remote survey detector to the floor of the RB basement in the area below the open stairwell. The radiation levels increased gradually from 2 R/hr to 45 R/hr as the detector was lowered from the 305 ft.
elevation to the 282 ft. elevation.
Residue on the tio of the detector (the detector physically contacted the 282 ft. elevation floor) looked like wet sand.
Following fire system repairs, smoke detectors inside the reactor building were tested during the RB entry on May 26, 1982.
The fire detectors activated fire protection circuitry outside the RB, 'however, the fire protection system was not fully operable (some local alarms did not activate and a ventilation damper failed to close).
The problems appear to be associated with circuitry outside the RB and technicians are working to correct the problems.
The next RB entry is scheduled for Thursday, June 3, 1982.
Scheduled
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tasks next week include an in-containment inventory of CRDM disassembly tools.
The RB CCTV cameras will be repositioned to monitor the CRDM's.
5.
Submerged Demineralizer System Vessel Shipment.
The first DOE shipment of a spent SDS waste vessel (D10015) arrived safely at Richland, Washington on May 24,1982. As reported in last week's status report, research and development characterization and glass vitrification testing will be performed on the. inorganic ion exchange (zeolite) waste material.
Confirmatory sample analyses have been taken at the DOE facility to ensure the waste package met Federal shipping and transport requirements.
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Past Meetings 1.
On May 24, 1982, Lake Barrett and Richard Bangart, Effluent Treatment Systems Branch, presented a panel discussion and keynote speech on NRC I
Radwaste Policies and the TMI Accident and resulting radwaste problems for an advanced study course at the Memphis,~ State University Center for
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Nuclear Studies in Memphis, Tennessee.
2.
On May 26, 1982, Mr. B. Rusche, Dr. F. Coffman and Mr. H. Feinroth briefed the NRC Commissioners on DOE activities at TMI.
3.
On Thursday, May 27,1982," Ronald Bellamy addressed the fifth graders in the Derry Township Elementary School, Hershey, PA.
Topics discussed included basic radiation and nuclear reactor principles and the cheating incident at Unit 1.
Future Meetings
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1.
On May 28, 1982, Lake Barrett will meet with the Concerned Mothers group to discuss TM1 issues.
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ATTACHME'NT l
RCS Feed and Bleed of 50,000 Gallons Start 5/17/82 Stop 5/20/82 Date_ Time Cs-137 (uc/ml) Sr-90 (uc/ml)
Sb-125 (uc/ml) Turbidity'(NTU)*
5/10 1000 14 18 5/17 1300 13 16 8.4 x 10-2 28 5/17 2000 16 17 9.3 x 10-2 36 5/18 2000 8.7 16 23 5/19 0900 8.2 11 6.5 x 10-2 24 5/19 2030 8.3 7.9.
6.7 x 10-2 23 5/24 1000 5.9 10 5.5 x 10-2
- Nephelometric Turbidity Units - An empirical measure of turbidity based on i
measurement of the light-scattering characteristics (Tyndall eff,ect) of the particular matter in the sample.
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