ML20038C430
| ML20038C430 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 11/23/1981 |
| From: | Barrett L Office of Nuclear Reactor Regulation |
| To: | Harold Denton, Snyder B Office of Nuclear Reactor Regulation |
| References | |
| CON-NRC-TMI-81-064, CON-NRC-TMI-81-64 NUDOCS 8112110025 | |
| Download: ML20038C430 (8) | |
Text
DISTRIBUTION:-
TMIPO HQ r/f TMI Site r/f A ntral File
NRC PDR Local PDR Site Operations File November 23.-1981 NRC/THI-81-064 MEMORANDUM FOR:
Harold R. Denton, Director Office of Nuclear Reactor Regulation Bernard J. Snyder, Program Director THI Program Office FROM:
Lake H. Barrett, Deputy Program Director THI Program Office
SUBJECT:
NRC TMI PROGRAM OFFICE WEEKLY STATUS REPORT Enclosed is the status report for the period of November 15-21, 1981.
Major items included in this report are:
2 Liquid Effluent Releases Airborne Effluent Releases NRC and EPA Environmental Data 4
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Radioactive Material and Radwaste Shipments o
TMI Occupational Exposures 2]
$ QJ, Submerged Demineralizer System Status 00
,N EPICOR II Qe: > -
9 Reactor Building Entries Emergency Preparedness Public Meetings There will be no weekly status report issued next week due to the Thanksgiving holiday.
Original ~signoHf r.-w H.Barrett /
Lake H. Barrett Deputy Program Director THI Program 0 ffice
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""*'~*'""C" OFFICIAL RECORD COPY l
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s 34RC TMI PROGRAM 0FFICE WEEKLY STATUS REPORT Week of November 15-21, 1981
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Plant Status Core Cooling Modei Heat tran'sfer from the reactor coolant system (RCS) loops to reacto.- building ambient.
s Available Core Cooling Modes:
Decay' heat removal systems.
Long term
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cooling "B" (once through steam generator-B).
s 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, November 20,1981) (approximate values)
Average Incore Therihocouples : 112"F Maximum Incore Thermocouple:
140*F RCS Loop Temperatures :
(A cycle of natural circulation occurred in the "B" loop on IT/18/81)
A B
Hot Leg 106*F 108 F s
Cold Leg (1) 68*F 78 F (2) 68 F 76 F JCS' Pressure:, 96 psig x
Reactor Building: Temperature :
64 F Water level :
Elevation 287.8 ft. (5.3 ft. from floor) via penetration 401 manometer J'
Pressure :
-0.15 psig less than 6 x 10-8 uCi/cc Kr-85 C, Concentration :
w (Sample taken 11/17/81) s s
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' November 13, 1981, through November 19,1981, 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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Airborne Effluents.
Airborne effluents released to the environment were within the regulatory limits.and in accordance with NRC requirements.
The licensee reported the following gaseous releases:
August September October Noble Gases (Ci) 94.3 53.1 14.8 Particulates (Ci) 9.29x10-7 2.49x10-6 1.84x10-6 Tritium (Ci) 2.52 0.815 3.26 The above releases represent a small fraction of the allowable regulatory limits.
These quantities are consistent with previous releases associated with routine operations.
The downward trend in noble gas releases can be attributed to recent refinements in evaluating monitoring instrument output data.
Based upon an Environmental Protection Agency (EPA) analysis of a vent sample and comparison with HPR-219A readings during the month of August, it was concluded that the HPR-219A gas channel was indicating larger than actual noble gas releases due to low level instrument noise and temperature effects.
3.
Environmental Protection Agency (EPA) Environmental Data.
Resul ts from EPA monitoring of the environment around the TMI site were as follows :
3 The EPA measured Kr-85 concentrations (pCi/m ) at several environmental monitoring stations and reported the following i
resul ts :
Location October 23 - November 6,1981 (pCi/m )
3 Gol dsboro 23 Observation Center 23 Middletown 30 Yorkhaven 23 All of the above levels of Kr-85 are considered to be background level s.
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 November 13, 1981, l
through November 19, 1981.
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NRC Environmental Data.
Results from NRC monitoring of the environment around the TMI-sitt 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-294 November 12, 1981 - November 18, 1981
<9.7 E-14 <9.7 E-14 5.
Licensee Radioactive Material and Radwaste Shipments.
On Monday, November 16, 1981, one Unit 1 solidified powdex resin liner (precoat in HN-600 liner number 28) was shipped to Chem Nuclear System Inc., Barnwell, South Carolina:
On Monday, November 16, 1981, one Unit 1 solidified powdex resin liner (precoat in HN-600 liner number 29) was shipped to Chem Nuclear Systems Inc., Barnwell, South Carolina.
On Friday, November 20, 1981, seven Unit 2 SDS (Submerhed Demineralizer System) liquid samples, each 60 ml., were shipped to Oak Ridge National Laboratory, Oak Ridge, Tennessee.
6.
TMI Occupational Exposure.
Licensee TLD (Thermoluminescent Dosimeter) records indicate the following Unit 2 total occupational radiation exposure for 1981 :
October 1981 11 man-rem Total 1981 (January-October) 110 man-rem Major Activities 1.
Submerged Demineralizer System (SDS). ' Processing of batch number 10 was completed on November 19, 1981.
During November 20-21, 1981, approximately 40,000 gallons of reactor building sump water were transferred to the SDS feed tanks in the fuel handling building.
This transfer brings the amount of water transferred from the reactor building sump to a total of approximately 295,000 gallons.
Processing of batch number 11 commenced on November 22, 1981.
As of November 20, 1981, approximately 255,000 gallons of reactor building sump water had been processed.
SDS performance parameters for batch 10 are attached.
2.
EPICOR II.
Processing of SDS effluent through the EPICOR II system continued this week.
As of November 20, 1981, approximately 245,000 gallons of reactor building sump water had been polished.
Recent performance parameters for EPICOR II are attached.
3.
Reactor Building Entries.
Reactor building (RB) entries 21 and 22 were completed on November 1.7 and 20,1981.
These entries I
are part of an accelerated program during which large scale decontamination f-e experiments will be conducted.
Tasks during the entries were performed in preparation for the gross decontamination experiment.
Specific (1) work commenced tasks accomplished during the two entries were:
on the polar crane to obtain a detailed assessment of damage, an.d to evaluate repair requirements; (2) 6xtensive still photography documentation of areas on the 305 ft. elevation and the 347 ft.
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elevation; (3) testing of video equipment to be used for video tape i
documentation of the reactor building; and (4) placement of a l
battery powered high reach platform in containment for use during t.
the decontamination test.
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l Work on the polar crane was tenninated earlier than planned when one j
'of the workers inspecting the polar crane reported that he felt hot
'and stated that he desired to exit the RB.
The entire four man polar I
crane team was ordered to leave the RB by personnel controlling the During the descent from entry from a command center outside the RB.
the crane, the individual who reported the apparent heat problem stopped
-on a platfonn and loosened his full face respirator.
The man appeared exhausted and immobile tt, personnel in the command center who were l
monitoring the descent on closed circuit television. A back-up worker was sent into the RB to assist.
The full face respirator and some protective clothing were removed from the exhausted individual and he The man was was assisted down from the platfonn and out of the RB.
examined by doctors on site and was released.
The individual had small areas of hair and skin contamination which were decontaminated prior l
to release.
A whole body radionuclide count indicated approximately 50 nanocurias of activity.
This amount of activity is insignificant
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from personal health concerns, but is higher than the natural radio-l activity in the human body.
The occurrence is being evaluated by the NRC staff.
The RB entry scheduled for the week of November 23, 1981, has been cancelled.
The next entry is tentatively scheduled for December 3,1981.
On December 2 and 10,1981, the licensee 4.
plans to.. conduct a " dress rehearsal" drill and annual exercise, respectively, to test the implementation of the TMI-2 Emergency Plan.
Work-up drills were conducted in the past three months in preparation 3'
for these exercises.
The NRC on-site staff plans to participate in both drills.
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, Meetings Held 1.
The NRC's Advisory Panel for the Decontamination of TMI Unit 2 met on November 16, 1981, in Lebanon.
The major topic of discussion was the financial problems that are hindering the pace of the cleanup of Unit 2.
The panel heard various groups expressing their opinions on cost sharing approaches and the restart of TMI Unit I reacto r.
The panel decided to obtain and discuss additional economic information during future meetings before taking a position on any of the various proposed resolutions to the financial problem.
s The panel unanimously passed a resolution uncoupling the restart of Unit I from future Unit 2 financial discussions by stating that "the restart of Unit 1 should be based solely on health, safety and technological consiiderations and not on economic cansiderations of the cleanup of. Unit 2".
The panel also authorized Chairman Minnich to send a letter to the NRC Commissioners urging them to further emphasize the safety significance of continued cleanup delays to convince national groups, e.g. Congress, that the TMI financial problem is not only a local issue, but is also one of national importance requiring prompt resolution.
The next meeting is scheduled to be held on December 10,1981, from 7:00 to 10:00 PM in Lancaster, 208 North Duke Street.
Additional meetings are scheduled for January 13, and January 28, 1982, at the Holiday Inn in Harrisburg.
2.
On Thursday, November 19, 1981, Lake Barrett met with a group of area mothers to discuss the forthcoming reactor building decon-tamination experiment, the status and plans to ship EPICOR II y
prefilters, reactor vessel imbrittlement, inadequate core cooling instrumentation, and operator licensing examinations.
They expressed their opinion that Unit 1 should not be restarted prior to the completion of the Unit 2 cleanup.
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ATTACHMENT l
l SDS Performance for Batch Number 10 Average Average Average i
Radionuclide Influent Effluent DF (uc/ml)
(uc/ml) 5 Cesium 137 1.2 x 102 9 2 x 10-4
.l.3 x 10 2
Strontium 90 5.3 8.9 x 10-3
,6.0 x 10 e
EPICOR II Performance for Reactor Building Sump Water Novemb_er 11, 1981, to November 18, 1981 Average Average Average Radionuclide Influent Effluent DF (uc/ml)
(uc/ml)
Cesium 137 1.0 x 10,3 2.6 x 10-7 3.8 x 103 Strontium 90 1.4 x 10-2 1.4 x 10-5 1.0 x 103 Antimony 125 1.4 x 10-2 3.5 x 10-7 4.0 x 104
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