ML20009F251
| ML20009F251 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 07/20/1981 |
| From: | Barrett L Office of Nuclear Reactor Regulation |
| To: | Harold Denton, Snyder B Office of Nuclear Reactor Regulation |
| References | |
| CON-NRC-TMI-81-041, CON-NRC-TMI-81-41 NUDOCS 8107300205 | |
| Download: ML20009F251 (4) | |
Text
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1.0 CAL PDR July 20,1981 Site Operations fi e NRC/TMI-81-041 iN 4 Y.
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c) y do MEMORANDUN FOR:
Harold R. Denton, Director
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Office of. Nuclear Reactor Regulation A
Bernard' Ji Snyder, Program Director THI Program Office FROM:
take H. Ba'rrett, Acting Deputy Program Director THI Program Office
SUBJECT:
HRC THI' PROGRAM OFFICE WEEKLY STATUS REPORT Enclosed is the status report for the period of July 12 - 18, 1981.
ORIGINAL ~ SIGNED BY-Ronald R. Bel Tamy for Lake H. Barrett Acting Deputy Program Director THI Program Office
Enclosure:
As stated cc: EDO OGC Office Directors Commissioner's Technical Assistants NRR Division Directors HRR A/D's Regional Directors IE Division Directors TAS EIS TMI Program Office Staff,(IS)
PHS EPA DOE Projects Br. #2 Chief DRPI, RI DRPI Chief, RI Public Affairs, RI T. Elsasser s
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NRC TMI PROGRAM 0FFICE WEEKLY STATUS REPORT Week of July 12 18, 1981 Plant Status Core Cooling Mode: Heat transfer from the reactor coolant syrtem (RCS) loops to Reactor Building ambient.
Available Core Cooling Modes:
Decay heat. rem' val systems.
Long term o
cooling "B" (once through steam generator-B)
RCS Pressure Control Mode: Standby Pressure Control (SPC) System.
Backup Pressure Control Modes: Mini Decay Heat Removal (MDHR) System.
Decay Heat Removal (DHR) Sy-tem.
Maj.1r Parameters (as of 0600, July 16,1981) (approximate values)
Average Incore Thermocouples: 120*F Maximum Incore Thermocouple:
144 F RCS Loop Temperatures:
A B
Hot Leg 119 F 122 F
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Cold Leg (1) 73 F 75 F (2) 74 F 74 F RCS Pressure:
97 psig Reactor Building:
Temperature: 75 F Water level:
Elevation 290.9 ft. (8.4 ft. from floor) via penetration 401 manometer Pressure:
-0.3 psig Concentration: 9.3 x 10-6 uCi/ml Kr-85 (Sample taken 7/9l81)
Effluent and Environmental (Radiological) 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 July 10, 1981, through July 16, 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.
The EPA announced on July 6,1981 that, due to a new shipping procedure for Kr-85 samples to the laboratory, the results for the Kr-85 environ-mental monitoring stations around TMI will not always be available on a weekly basis.
The NRC will report these results as they become available.
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 periua from July 2,1981, through July 16, 1981.
3.
NRC Environmental Deta.
Results from NRC monitoring of be environ-ment 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) "(uC1/cc)
H P-276 July 8,1981 - July 15,1981
<8. 5 E-14 <8. 5 E-14 4.
Licensee Radioactive Mat'eria' and.Radwaste Shipments.
On Monday, July l'i,1981, a 40 ml Unit 2 reactor coolant sample was sent to Babcock and Wilcox (B&W), Lynchburg, Virginia.
On Tuesday, July 14,1981, a Unit 1 one liter Waste Evaporator Condensate Storage Tank (WECST) composite sample was sent to Teledyne Isotopes, Westwood, New Jersey.
On Tuesday, July 14,1981, a Unit 1 solidified precoat was shipped to Chem-Nuclear Systems Incorporated, Barnwell, South Carolina.
Major Activities 1.
Submerged Demineralizer System (SDS).
Processing of the first batch (approximately 50,000 gallons) of Reactor Coolant Bleed Tank (RCBT) water continued.
As of 7 :00 a.m., July 17, 1981, approximately 32,300 gallons had been processed.
The licensee expects to complete the processing of this first batch during the week of July 19, 1981.
Preliminary results indicated that cesium 137 and strontium 90 loadings on the zeolite-filled processing vessels, as of July i6,1931, are: 180 curies Cs-137 and 84 curies.Sr-90.
The loadings are primarily on the number one vessel in the filter line-up, and represent greater than 99% removal of these radioactive materials from the process stream.
r 2.
Containment Entry.. Tha thirteenth reactor buildir.g containment entry is schedul.e'd for July 23, 1981.
The activities planned during this entry include:
Maintenance of the closed circuit TV system, Removal of crystalline and water samples.
Removal of core flooding tank transducers, Photographs of parts of the reactor fluid make-up systex.
Resurveying the north side of the reactor vessel head and the deep end of the refueling p301, Obtaining a 100 ml sample of water from the neutron shield tank, and Installation of a continuous air monitor and an area radiation monitor.
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