ML20009D374
| ML20009D374 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 07/13/1981 |
| From: | Barrett L Office of Nuclear Reactor Regulation |
| To: | Harold Denton, Snyder B Office of Nuclear Reactor Regulation |
| References | |
| CON-NRC-TMI-81-039, CON-NRC-TMI-81-39 NUDOCS 8107240006 | |
| Download: ML20009D374 (5) | |
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THI Program Office /HQ r/f F
NRC PDR July 13,1981 LOCAL PDR NRC/THI-81-039 Site Operations file t
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HO40RANDUM FOR:
Harold 5. Denton, Director,
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'O Office ofJuclear Reactor Regulation tj o
Bernard'J. Snyder, Program Director,
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Lake H. 'Barrett, Acting Deputy Program Direc$or,l",
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SUBJECT:
NRC TMI PROGRAM 0FFICE WEEKLY STATUS REPORT l
Enclosed is the status report for the period of July 5 - 11, 1981.
ORIGIN 6LSIGNEDBf:
A. N. rasano Tor Lake H. Barrett
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Acting Deputy Program Director Till Program Office
Enclosure:
As statad cc: EDO OGC Office Directors Commissioner's Technical. Assistants NRR Division Directors.
NRR A/D's Regional Directors IE Division Directors a
TM EIS TMI Program Office Staff.(15)
PHS EPA DOE Projects Br. #2 Chief, DRPI, RI DRPI Chief, RI Public Affairs, RI T. Elsasser 8107240006 810713 PDR ADOCK 05000320 R
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OFFICIAL RECORD COPY
NRC TMI PROGRAM 0FFICE WEEKLY STATUS REPORT Week of July 5 - 11, 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 systen%
Long term 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) System.
Major Parameters (as of 0500, July 10,1981) (approximate values)
Average Incore Thermocouples: 120 F Maximum Incore Thermocouple:
145 F RCS Loop Temperatures:
A B
Hot Leg 119 F 122 F Cold Leg (1) 72 F 74 F (2) 73 F 74 F RCS Pressure: 96 psig Reactor Building: Temperature: 77 F Water level: Elevation 290.9 ft. (8.4 ft. frca floor) via penetration 401 manometer Pressure:
-0.3 psig Concentration:
1.2 x 10-5 uC1/ml Kr-85 (Sample taken 7/1/81 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 July 6,1981, through July 10, 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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2.
51r' borne effluents from the TMI site released to the environment, after processing, were made within the regulatory limits and in accordance-with NRC requirements.
During the reporting period May 1-31, 1981, the licensee reported the following gaseous releases:
Curies Noble Gases 42.0 Particulates 0.0000013 Tritium 1.7 The above releases represent a small fraction of the allowable regulatory limits.
The noble gas (Kr.-85) release for the month of
-May, although well within limits and insignificant for environmental considerations, was higher than anticipated. A portion of the release can oe attributed to Reactor Building (RB) purges, and the licensee is-currently examining the potential origin of the remainder.
Airborne effluent infonnation will continue to be provided on-a monthly basis.
3.
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 environmental monitoring stations around TMI will not always be available on a k
weekly Sasis.
The NRC will report these results as they become
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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 period from July 2,1981, through July 9, 1981.
4.
NRC Er.vironmental Data.
Results from NRC monitoring of the 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)
(uCi/cc)
HP-275 July 2,1981 - July 8,1981
<9.9 E-14 <9.9 E-14 Environmental TLD measurements for the period April 30 - June 3,1981, around THI indicated gamma radiation to be at the natural background levels.
Fifty-nine TLD's registered doses ranging from 0.1 mR/ day to 0.3 mR/ day.
The average dose was 0.2 mR/ day.
These dose rates are consistent with natural background radiation in the TMI area.
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5.
Licensee Radioactive Material and Radwaste Shipments On Monday, July 7,1981, a 40 ml Unit 2 reactor coolant sample was sent to Babcock and Wilcox (B&W), Lynchburg, Virginia.
On Wednesday, July 8, 1981, one cash containing 17 drums of Unit 2 LSA compacted and noncompacted waste was shipped to U.S. Ecology, Richland, Washington.
(This shipment was previously reported as having occurred on Wednesday, July 1,1981; however, due to vehicle weight restrictions, it was delayed.)
On Thursday, July 9, 1.981, 55 drums containing Unit 2 contaminated laundry were shipped to Tri-State Industrial Laundries, Utica, New York.
On Friday, July 10, 1981, one drum containing five smears of control rod drive mechanisms from Unit 2 was shipped to Science Applications, Inc., Rockville, Maryland.
Major Activities Submerged Demineralizer System (SDS).
Processing of the first batch of Reactor Coolant Bleed Tank (RCBT) water through the SDS commenced July 10, 1981.
The water is being processed through two zeolite beds composed of two parts cesium -- specific zeoiite (designated IE-96) tv one part strontium --
specific (designated as Linde A) zeolite.
The processed water is being returned to the RCBT's for sampling to determine if additional processing is necessary and to determine if the water will be reused as flush water or placed in storage.
As of 12:00 midnight, July 11, 1981, 1,800 gallons have been processed.
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Meeting Attended On Thursday, July 9,1981, the TMI Citizens Advisory Panel for the Decontamination of TMI Unit 2 held a public meeting in the Holiday Inn, 23 South Second Street, Harrisburg.
The panel received comments from the audience which incl -ded opinions on various solutions to the Unit 2 cleanup financial problems, questions on hydrogen generation, questions on Unit 1 reactor vessel embrittlement, emergency planning, notification of meetings, and requests for additional non-NRC and non-GPU expert discussion of issues.
GPU and NRC representatives responded to the panel's and the public's questions on ultimate disposition of TMI cleanup wastes and the general status of the cleanup program.
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