ML20041E900
| ML20041E900 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 03/05/1982 |
| From: | Barrett L Office of Nuclear Reactor Regulation |
| To: | Harold Denton, Snyder B Office of Nuclear Reactor Regulation |
| References | |
| CON-NRC-TMI-82-013, CON-NRC-TMI-82-13 NUDOCS 8203150236 | |
| Download: ML20041E900 (7) | |
Text
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DISTRIBUTION TMIPO HQ r/f TMI SITE r/f
--CETTRAL FILE NRC PDR
!! arch 5,1982 LOCAL PDR flRC/TMI-32-013 Site Operations File MB40RNiDtil FOR:
Harold R. Denton, Director Office of fluclear Reactor P.egulation Bernard J. Snyder, Program Director THI Program Office FROM:
Lake H. Barrett, Deputy Program Director THI Program Office
SUBJECT:
liRC TMI PROGRN4 0FFICE WEEKLY STATUS REPORT Enclosed is the status report for the period of February 28,1982 to March 5,1932. thjor items included in this report are:
Liquid Effluent Releases Airborno Effluents C
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!!RC and EPA Environmental Data b
RECBygg Radioactive Material and Radwaste Shipments 5
AMR oaqu 2 Submerged Demineralizer System Status
~Eg EPICOR II 1
Q s
Reactor Building Entries Public Meetings l
Lake H. Barrett l
Deputy Program Director l
THI Program Office Ent.losure : As stated I
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Office Directors Commissioner's Technical Assistants fiRR Division Directors flRR A/D's Regional Directors i
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Public Affairs, RI l
State liaison, RI I
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NRC TMI PROGRAM 0FFICE WEEKLY STATUS REPORT February 28,1982
' March 5,1982 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).
i 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. March 5,1982) (approximate values)
Average Incore Thermocouples : 103*F Maximum Incore Thermocoup1e:
133 F RCS Loop Temperatures:
A B
Hot Leg 95*F 98*F Cold Leg (1) 80*F 82*F (2) 86 F 87 F RCS Pressure:
96 psig Reactor Building: Temperature :
63 F Water level:
Elevation 283.1 ft. (0.4 ft. from floor)
Pressure :
-0.2 psig Airborne Radionuclide Concentrations:
4.0 E-6 uCi/cc H3 (sample taken 3/1/8?)
7.5 E-6 uCi/cc Kr 5 8
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(sample taken 3/1/82)
Effluent and Environmental (Radiological) Information 1.
Liquid effluents from the TMI site released to the Susq'uehanna 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 February 26, 1982, through March 4,1982, 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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Airborne Effluents.
Airbrne releases to the environment, as measured by licensee installed monitors at discharge stacks, are listed below.
The airborne releases were well within regulatory limits.
January 1982 l
_ Unit II
_EPICOR II Noble Gases (Ci)
<l.60 x 102
<2.13 Particulates (Ci) 4.85 x 10-5 9.76 x 10-7 Tritium (C1) 6.78 3.06 x 10-2
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Environmental Protection Agency (EPA) Environmental Data.
The EPA Middletown Office has not received tha analytical results for Kr-85 measurements around the TMI site from the EPA's Counting Laboratory at Las Vegas, Nevada.
When these results become available, they 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 February 24, 1982 through March 4, 1982.
4.
NRC Environmental Data._ Results from NRC monitoring of the environment around the TM1 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-309 Februa'ry'24,1982 - March 3,1982
<6.0 E-14 <6.0 E-14 5
License Radio _ active Material and Radwaste Shipments.
On Tuesday, March 2,1982, four one liter EPICOR II samples from Unit 2 were shipped to the State of Maryland Laboratory and Research Facility, Baltimore, Maryland.
On Thursday, March 4,1982, six liquid samples from Unit 2 (various plant locations) were shipped to the Westinghouse Electric Corp.- Laboratory, Waltz Mills, Pennsylvania.
Major Activities l
1.
Submerged Demineralizer System (SDS).
Processing of batch 22 continued f
during the week. Batch 23 will process accumulated auxiliary j
building bleed tank water and is scheduled for rpt week after completion of batch 22.
SDS will then enter an obtage prior to processing of reactor coolant system water, now scheduled for May.
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2.
EPICOR II.
The EPICOR II system continued to process SDS effluents during the week, Performance parameters are included in Attachment 1.
3.
Reactor Buil_ ding Entries.
Four reactor building (RB) entries were conducted during the past week.
Entries were originally scheduled 4
for Tuesday, Wednesday, and Thursday (March 2, 3, and 4,1982).
Due to mechanical problems, all the scheduled gross decontamination experiment tasks were not completed during the entries and an additional entry was made on Friday in an attempt to get back on schedule.
l On Friday, minor operational problems arose with the high pressure pump which supplies flush water to the RB and the entry was i
terminated.
Despite the problems, a low pressure flush of the 305 ft. elevation surfaces was completed and some decontamination was performed on the polar crane.
l The pump leak is being repaired and it is expected that the gross decontamination experiment will continue next week.
The following list of decontamination tasks will be performed when the pun.p is r
repaired:
1.
low pressure flush of the polar crane l
2 low pressure flush of the refueling pool 3
low and high pressure flush of the 347 ft. elevation surfaces 4.
high pressure f'ush of the 305 ft. elevation surfaces The effectiveness of the completed low pressure flush of the 305 ft.
elevation is being evaluated from the data collected before and 1
after the decontamination.
Prior to the start of the gross decontamination experiment, the water level in the RB was pumped down to approximately six inches.(40,000 gallons) above the RB sump.
The decrease in water depth from approximately eight feet to six inches did not produce a detectable change in the RB ambient radiation levels.
The decontamination experiment in l
addition to removing some of the loose surface contamination, will dilute the radioactive water remaining in the RB basement. Several i
thousand gallons of water will be added to the sump during the decontamination experiment.
The sump water will be eventually i
processed with the SDS.
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4-Future Meetings 1.
On Saturday, March 13, 1982, Lake Barrett will address the Society of Manufacturing ' Engineers in Williamsport, PA, on the cleanup of TMI and general aspects of nuclear power.
2.
On Wednesday, April 14, 1982, Lake Barrett will be the keynote speaker for the Southern Pennsylvania Association of Occupational Health Nurses, to be held at the Holiday Inn in York, r
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6 ATTACHMENT 1 t
EPICOR II Performance February 23, 1982 to March 1,1982 Average Average Average Radion_uclide Influent Effluent DF (uc/ml )
Tic /ml)
Cesium 137 7.4 x 10-4 5.4 x 10-7 1.4 x 103 Strontium 90 6.0 x 10-3
<1.6 x 10-5
>3.7 x 102 Antimony 125 1.0 x 10-2
<4.2 x 10-7
>2.4 x 104 s
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