ML20042B141
| ML20042B141 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 03/15/1982 |
| From: | Barrett L Office of Nuclear Reactor Regulation |
| To: | Harold Denton, Snyder B Office of Nuclear Reactor Regulation |
| References | |
| CON-NRC-TMI-82-014, CON-NRC-TMI-82-14 NUDOCS 8203250020 | |
| Download: ML20042B141 (6) | |
Text
._
s
-[
DISTRIBUTION 0*
TMIP0 HQ r/f TMI SITE r/f W TRAL FILE NRC PDR LOCAL PDR
!! arch 15,1932 Site Operations File flRC/THI-82-014 So,:230 HEHORAllDust FOR:
llarold R. Denton, Director Office of Nuclear Reactor Regulation Bernard J. Snyder Program Director THI Program Office FRGi:
Lake 11. Barrett, Deputy Program Director THI Prograu Office
SUBJECT:
fiRC THI PROGRN! 0FFICE llEEKLY STATUS REPORT Enclosed is the status report for the period of March 6,1982 to fiarch 13, 1932 Major items included in this report are:
Liquid Effluents liRC and EPA Environmental Data Radioactive Haterial and Radwaste Shipaents ro O
Submerged Demineralizer System Status x
W CTn g:0 4
EPICOR II Milgy Reactor Building Entries "87% ear 2A
~
Groundsater Monitoring Program e
s
/.
Control Red Drive Removal Practice W
Public fleetings Orf 81nal signed by Mo H. Barrett Lake 11. Barrett Deputy Program Director TliI Program Office Enclosure : As stated j
-f..............
B$b3250020 B20315 PDR ADOCK 05000320 d
Egg-]
OFFICIAL RECORD COPY
Harold R. Denton March 15,1982 Bernard J. Snyder cc w/enci:
E00 OGC Office Directors Commissioner's Technical Assistants NRR Division Directors NRR A/D's Regional Directors IE Division Directors TAS EIS THI Program Office Staff (15)
PHS E'< A DOE Projects Dr. #2 Chief, DRPI, RI DRPI Chief, RI Public Affairs, RI State Liaison, RI su=~4ur) n/jes R
e MShdnbaKy
.(
I.
..... g..
I TMIPO
..M.I.,PO T
T omer p
.pg.g..
o RBe lamy pa t.
I'
. 3// /,82
[ uuc ron= 3i.. io so, ~acu o2' OFFICIAL RECORD COPY
NRC TML PROGRAM OFFf CE WEEKLY STATUS REPORT March 6,1982 - March 13,1982 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).
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 12,1982) (approximate values)
Average Incore Thermocouples: 103*F Maximum Incore Thermocouple:
133*F RCS Loop Temperatures:
A B
Hot Leg 94'F 97*F Cold Leg (1) 77'F 80'F (2) 81
- F 85*F RCS Pressure: 96 psig Reactor Building: Temperature:
60'F Water level:
Elevation 283.1 ft. (0 4 ft. from floor)
Pressure:
-0.2 psig Airborne Radionuclide Concentrations:
3 2.1 E-7 uCi/cc H (sample taken 3/8/82) 1.5 E-6 uCi/cc Kr85 (sample taken 3/1/82)
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 March 5,1982, through March 11,1982, the effluents contained no detectable radioactivity at the discharge point and individual effluent sources, which originated within Unit 2, contained no detectable radioactivity.
2.
Environmental Protection Agency (EPA) Environmental Data.
The EPA Middletown Office has not received the 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 repo rt.
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 March 3,1982 through March 11, 1982.
3.
NRC Environmental Data.
Resuli.s from NRC monitoring of the environment around the TML site were as follows:
The following are the NRC air sample analytical results for the onsite continuous air sampler:
I-l 31 Cs-137 "Sampl e Period (uCi/cc)
(uCi/cc)
HP-310 March 3,1982 - March 10,1982
<6.2 E-14 <6.2 E-14 4
License Radioactive Material and Radwaste Shipments.
On Friday, March 5, 1982, 45 drums containing contaminated laundry from Unit 1 and Unit 2 were shipped to Tri-State Industrial Laundries, Utica, New York.
On Tuesday, March 9,1982, fourteen liquid samples from Unit 2-(various plant locations) were shipped to the Westinghouse Electric Corp. Laboratory, Waltz Mills Site, Madison, Pennsylvania.
On Thursday, March 9,1982, one package (Unit 2 air sample HPR 221 B) was mailed to Science Applications Inc., Rockville, Maryl and.
On Thursday, March 9,1982, two liquid samples from Unit 1 (precoat A) were shipped to the Westinghouse Electric Corp.
Laboratory, Waltz Mills Site, Madison, Pennsylvania.
Major Activities 1.
Submerged Demineralizer System (SDS).
Processing of batch 22 was completed on March 6, 1982 The batch 22 process parameters are included in.
Processing of batch 23 (bleed tank water) continued throughout the week.
After batch 23 is processed, the SDS will be secured for minor maintenance.
Reactor coolant system water processing through the SDS is scheduled to commence in May.
1
2.
EPICOR II.
The EPICOR II system continued to process SDS effluents during the week.
Performance parameters are included in Attachment 1.
3.
Reactor Building Entries.
The gross decontamination experiment has proceeded on schedule during the past week.
The following surfaces have been flushed with water in various combinations of pressure and temperature: 305 ft, elevation floors, 347 ft, elevation floors, polar crane surfaces and the refueling pool.
Approximate 1y' 6,000 gallons of processed water have been used for the flushes.
The effectiveness of the flushes in removing surface contamination and decreasing ambient radiation levels will be evaluated after the post decontamination surveys are completed.
The flushing and data gathering phase of the experiment is scheduled to be completed during four reactor building entries next week.
4.
Groundwater Monitoring Program.
Based on the most recent test boring samples, tritium concentrations in the ground wates haJe remained essentially in the same range as reportsd in previous Weekly Status Reports. Attachment 2 contains a skeNh of the test boring locations with the most recent tritium concentrations in pCi/ liter annotated next to each boring. Weekly water samples are taken from borings 1, 2, 3,10,16, and 17. The other test borings are sampled monthly.
Except for tritium, there have been no other radioisotopes detected in the latest water samples.
5.
Control Rod Dri_ve Removal Practice.
A proposed technique for inspecting the interior of the Unit 2 reactor vessel with a television camera will be practiced on Monday and Tuesday, March 15 and 16,1982, in the Unit 1 reactor building.
The technique was proposed by the Technical Assistance and Advisory Group (TAAG) and involves removing a control rod drive lead screw to make an opening in the top of the reactor vessel head for television camera insertion.
It is expecte'd that this technique will permit a visual inspection of the top of several fuel assemblies.
The entire procedure will be implemented on the Unit 1 reactor in conjunction with the Unit i examination of primary system components for signs of possible deterioration.
The Unit I lead screw removal, visual inspection of the reactor vessel interior, and lead screw replacement is scheduled to be performed over the two day period,
Past Meeting On Saturday, March 13, 1982, Lake Barrett addressed the Society of Manufacturing Engineers in Williamsport, PA.
The major topics of discussion were nuclear power, the accident at TMI, TMI cleanup, waste management, risks of alternate energy production and public confidence in nuclear energy.
Future Meetings On Wednesday, April 14, 1982, Lake Barrett will be the' keynote speaker J
for the Southern Pennsylvania Association Occupational Health Nurses, to be held at the Holiday Inn in York.
e
...n..-
..,w
.e n,
ATTACHMENT 1 SDS Performance for Batch Number 22 Average Average Average Radionuclide In fluent Effluent DF (uc/ml)
(uc/ml)
Cesium 137 1.2 x 102 5.4 x 10-4 2.3 x 105 Strontium 90 4.7 5.7 x 10-3 8.3 x 102 EPICOR II Performance March 2,1982 to March 8,1982-Average Average Average
~
Radionuclide In fl uent_
Ef fluent DF (uc/ml)
(uc/ml)
Cesium 137 4.8 x 10-4 1.8 x 10-7 2.7 x 103 Strontium 90 5.4 x 10-3
<l. 3 x 10- 5
>4.2 x 102 Antimony 125 5.0 x 10-3
<2.8 x 10-7
>1.8 x 104
m h
\\
1 m
R w
a k
A$
\\
- \\c 4
t*
W 8
6 9
a R
s R
h.
?%
N E
TS b$$
s' Q
Q "c y W
A v,
6 sgg om smesau.
gz u
y
!> R 9
0 g
D a >r4 &
m$e (a m
Q
. n\\.
a g' g g
wwwa
.Q 9
3-z R
m
.n,s
\\p swns I
2<w N
\\
/
hed -
l p
A.e g
i' N
?
6 3
'e a w!
a ja 3
(*
b P
q 9gJ u,
LJ lh (o*o R
\\ \\
2m o
N N
\\
3 O
q s
U sw
%.