ML20033C770
| ML20033C770 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 11/16/1981 |
| From: | Barrett L Office of Nuclear Reactor Regulation |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| CON-NRC-TMI-81-063, CON-NRC-TMI-81-63 NUDOCS 8112040148 | |
| Download: ML20033C770 (8) | |
Text
DISTRIBUTION TMIPO HQ r/f TMI SITE r/f a
CE4 TRAL FILE NRC PDR I.0 CAL PDR November 16, 1981 Site Operations File NRC/THI-81-063
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MEMORANDUM FOR:
Harold R. Denton, Director Office of Nuclear Reactor Regulation NOV10 1981=- ~g
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,a m Bernard J. Snyder Program Director a
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- 1NI Program Office
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Lake H. Barrett Deputy Program Director
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TMI Program Office
SUBJECT:
NRC TMI PROGRNi 0FFICE WEEKLY STATUS REPORT Enclosed is the status report for the period of November 8-14, 1981.
Major items included in this report are:
Liquid Effluent Releases NRC and EPA Environmental Data Radioactive Material and Radwaste Shipments Submerged Demineralizar System Status EPICOR II Reactor Building Entries In-Core Thermocouple Status Public Heatings
'Driginal signed by Jake H. BazTotg Lake H. Barrett Deputy Program Director TMI Program Office
Enclosure:
As stated 8112040148 811116
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PDR ADOCK 05000320,,
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- u. no..o sac = oi' OFFICIAL RECORD COPY
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Harold R. Denton -
'lovember 16, 1981 Bernard J. Snyder cc w/ Encl:
EDO OGC Office Directors Commissioner's Technical Assistants NRR Division Directors NRR A/D's Anjional Directors IE Division Directors TAS EIS TMI Program Office Staff (15)
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EPA l
DOE Projects Br. #2 Chief, DPRI, RI DPRI Chief, RI Public Affai;s, RI i
State Liaison, RI 1
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NRC TMI PROGRAM 0FFICE WEEKLY STATUS REPORT Week of November 8-14, 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 systems.
Long term cooling "B" (once through steam generator-B).
RCS Pressure Control Mode: Standby pressure control (SPC) system, c
Backup Pressure Control Modes: Mini decay heat removal (MDHR) system.
Decay heat removal (DHR) system.
Major Parameters (as of 0500, November 13,1981)[(approximate values)
Average Incore Thermocouples:
108*F Maximum Incore Thermocouple:
139*F RCS Loop Temperatures:
A B
Hot Leg 105 *F 108'F Cold Leg (1) 82*F 75'F (2) 93*F 73*F RCS Pressure: 96 psig Reactor Building: Temperature :
66*F Water level:
Elevation 287.8 ft. (5.3 ft. from floor) via penetration 401 manometer Pressure :
-0.15 psig Concentration : 8.6 x 10-6 uCi/cc Kr-85 (Sample taken 11/4/81) s Effluent and Envir,opmental (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' November 6,1981, through November 12,1981, the effluents contained no detectable radioactivity at the discharge point and individual effluent sources which originated within Unit 2 contained no detectable radioactivity.
6 The EPA Environmental Protection Agency (EPA) Environmental Data.
2.
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 y
environmental moni,toring 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 l
detected in any of the samples collected from the EPA's a.ir I
and gamms rate networks during the period from November 4,1981, I
through November 12, 1981.
Results from NRC monitoring of the environment f
3.
NRC Environmental Data.
6 around the TMI site were as follows:
The following are the NRC air sample analytical results for the onsite continuous. air sampler:
(uCi/cc)__
Sampl e_
Period _
HP-293 November 4,1981 - November 12, 1981
<7.8 E-14.<7.8 E-14
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4.
Licensee Radioactive Material an'd Radwaste Shipments.
On Monday, November 9,1981, a 250 m1 sample, Unit 1 Decay.
Heat B, was mailed to Teledyne Isotopes, Westwood, New Jersey.
On Friday, November 13,1581, one EPICOR II dewatered resin liner (liner.F-10) was shipped to U.S. Ecology, Richland, i
I On Friday, November 13, 1981, one EPICOR II dewatered resin p
i liner (liner F-ll) was shipped to U.S. Ecology, Richland, 6
1; I
On Friday, November 13, 1981, six samples taken during reactor building entry number 20.(11:00 AM 11/13/81) were
. shipped' to Massachusetts Institute.of Technology, Cambridge, Massachusetts for biological.testingt-On Friday, November 13, 1981, one EPICOR II dewatered resin liner (liner F-12) was shipped to U.S. Ecology, Richland, Washington.
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Major Activities _
Submerged Dcmineralizer Systemt(SDS)_./ frocessing of batch number 9 1.-
was completed on November 9,1981.
During November 11-12, 1981, q g 9
approximately 50,000 gallons of reactcr building sump water were M:
i transferred to the SDS feed tanks in the fuel handling building.
p This transfer brings the amount of water transferred from the p
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s reactor building sump to a total of hpproximately.255,000 gallons.
i Processing of batch number 10 commenced on November 12,1981. As of
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Q November 12, 1981, approximately 205,000' gallons of reactor building N
sump water had been processed.
SDS performance parameters for
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4x batch 9 are attached.
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EPICOR II.
Processing of SBS effluent' through the EPICOR II system As of November 12.,1981,.approximately
[
icontinued this week.
gallons of reactor building Sump waterchad been polished.
205,000 Ja Liners F-10, F-ll, and F-12 were shippedito a commercial burial facility ~.near Richland, Washington for disposal.
Recent perfonnance
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4 parameters for EPICOR II are attached. m
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- 3.. Reactor ' Building Entry. Durino the past week, only one of the two scheduled reactor bui1 ding (RB) entries was undertaken.. "En'try 20 Entries 21 and 22 are was completed on Friday, November 13,h1981.
l scheduled for November 17 and 20,1981.
I During entry 20, a solenoid valve and 'an area radiation monitor.
HPR-212, were removed for generic evaluation of equipment subjected nN to accident conditions.
Reactor building air and water samples were taken for biological analysis and preparations continued for s
the decontamination experiment.
Initially, plans called for replacing s-HPR-212 with an operable sensor, however, these plans were abandoned f
when it was determined that the wiring between the sensor and the l
indicator outside the RB was degraded.
e There are no operable fixed radiation monitors inside the RB.
Since RB sump water processing commenced, every entry is preceded Ig No by a survey of radiation levels in accessible areas of the RS.
changes in airborne or area radia a levels were noted until a
The radiation survey p. eeding entry 20 identified an entry 20.
apparent increase in the area radLition level on the 305 ft.
l The elevation in the area above the reactor coolant drain tank.
gamma radiation field in this area increased-from approximately 1..
1.1 R/hr to 1.6 R/hr.
This increase most.likely resulted from the transfer of 255,000 gallons of RB sump water to the SDS which lowered the sump water level by approximately three feet, thereby I
changing the relative geometries of radiation sources and self-shielding characteristics in the basement.
As the water. level is
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lowered, further changes are likely.
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During the entries next week, personnel are scheduled to commence work on the polar crane in support of the power lift installation i
which will allow men and equipment to be lifted up to the polar crane.
To. imorove their mobility, workers on the polar crane wear full face' respirators with particulate filters (protection factor 50) rather than the powered air filters (protection factor 1,000) which are nonnally worn in the RB.
It is expected that airborne radioactivity at the polar crane will be below 10 CFR 20 maximum permissible concentration (MPC), however, to increase worter protection, the RB purge has remained on through the weekend and will operate continuously throughout the week.
Based on samples inside the RB, all air activity is below MPC and the environmental significance of the continuous purge is minimal.
4.
In-Core Thennocouple_ Status.
Following. pumping of 50,000 gallons of water from the reactor building' sump on' November 11-12, 1981, the 'rcactor coolant system (RCS) temperatures exhibited changes which indicate natural cir'culation flow occurred through the RCS loops.
During the period of natural circulation, the thermocouple indicating the highest in-core temperature decreased to 139*F 2
(2*F-decrease) and the calculated average in-core temperdture The RCS hot leg temperat.ures T )
decreased to 107'F (6 F decrease).
change 1 little during this period but the cold leg temperatures d C)
, increased significantly as the natural circulation pushed the Jcooler water out of the cold legs and replaced it with warmer water A" loop TC-4 increKsed to.98*F (30*F incr(ease); the The "A" loop Tc-2 increased to 82*F 12*F from the hot legs.
increase)iC-2 increased to 75'F (3*F. increase); and the "B" loop the "B" loop TC-4 increased to 73*F (5*F increase).
The temperature changes which occurred do not adversely affect the condition and safety of the core.
The mixing of water which occurs
- as a result of natural circulation is beneficial because core temperatures are reduced and RCS water samples (taken on a weekly basis) will be more representative of the water which is present in
. the core.
The ThlPO is monitoring the temperature changes closely
.as additional water is removed from the reactor building, h
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Meetings Held On Saturday, November 14, 1981, Lake Barrett participated in a panel discussion at the Elizabethtown Public Library on the government's response to the TMI acci~ dent.
The primary topics of. discussion were the emergency plans for coping with any possible futura accident at TMI.
Representatives from GPU, State of Pennsylvania, and Elizabethtown were also on the panel to make brief statements and respond to questions from members of the public.
Most questions were addressed towards the adequacy of the emergency plans.
Future Meetings c
1.
The NRC's Advisory Panel for the Decontamination of Three Mile Island Unit 2 will meet November 16,1981, from 7:00 p.m. to 10:0b p.m.
in the Municipal Building, 400 South 8th Street, Lebanon.
At tha meeting, the panel plans to discuss cleanup financial problems and the current status of cleanup activities at Three Mile Island.
The meeting is open to the public.
l 2.
On Thursday, November 19,198J, Lake Sarrett wtll be meeting. with' l
local mothers to discuss the decontarir.ation experiments and other l
related TMI-2 issues.
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ATTACHMENT SDS Performance for Batch Number 9 Average Average Average Radionuclide Influent Effluent DF (uc/ml)
.(uc/ml )
e Cesium 137-7.8 x 101 7.3 x 10-4 1.1 x 105 Stron51umf90 2.9 17.4 x 10-3 3.9 x 102 4.
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EPICOR II Performance for Re_a_ctor Building Sump Water November 6,1981, to November 11, 1981 Average Average Average Radionuclide Influent Effluent DF (uc/ml )
(uc/ml)
Cesium 137 7.9 x 10-4 3.6 x 10-7 2.2 x 103 Strontium 90 7.7 x 10-3 1.6 x 10-5 4.8 x 102 Antimony 125 1.1 x 10-2 4.4 x 10-7 2.5 x 104 e
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