ML20009B387
| ML20009B387 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 07/06/1981 |
| From: | Barrett L Office of Nuclear Reactor Regulation |
| To: | Harold Denton, Synder B Office of Nuclear Reactor Regulation |
| References | |
| CON-NRC-TMI-81-038, CON-NRC-TMI-81-38 NUDOCS 8107150351 | |
| Download: ML20009B387 (5) | |
Text
-;
DISTRIBUTION TMI Program Office /HQ r/f TMI SJTE r/f WENTRAL FILE iNRC.PDR A LOCAL PDR July 6, 1981 Site Operations file HRC/TMI-81-038
~
9.-
HENORANDUM FOR:
ilarold R. Denton, Director, Office of, Nuclear Reactor Regulation Bernard J. Snyder, Program Director, 111I Program Office FROM:
Lake H. B5rrett, Acting Deputy Program Director, THI Program Office
^
SUBJECT:
HRC THI PE0GRN! 0FFICE WEEKLY STATUS REPORT 4
Enclosed is the status repoht.for the period of June 28 - July 5,1981.
3
+
~
~
p _.
Lake 11. Barrett Acting Deputy Program Director TMI Program Office
^
Enclosure:
As stated
[
cc: EDO
~
OGC Office Directors Comissioner's Technical.. Assistants q
7rk?
HRR Division Directors
.E N %. ft NRR A/D's eE Regional Directors gg 3.DN *.
IE Division Directors fa M M P [gi TAS Program Office Staff (15)
^
EPA DOE Projects Br. No. 2 Chief, DPRI, RI.
DRPI Chief, RI Public Affairs, RI' r
T. Elsasser 8107150351 010706 PDR ADOCK 05000320
_. 3 PDR
-HmI:eyjg..mIqn en...Tn.I.:e.qttg...Tn.I.;.eq.yjpj.yngllamy 11 g....
sunm>GKalnidn/ imp RCo MShanbaky AFasano RB L
om>/((/81 7/. /. '..'). 81f)..[../. 8l.......... y.h.. [. 7. 8E
~'
- f../../. 81.......
7h,/81 nne ronu ass no rm uncu o2*
OFFIClAL RECORD COPY
llRC 1MI PROGRAM OFFICE WEEKLY STATUS REPORT Week of June 28 - July 5,1981
_P_lant 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 lleat Removal (MDliR) System.
Decay lleat Removal (DilR) System.
Major Parameters (as of 0400, July 2,1981) (approximate values)
Average Incore Thermocouples: 119 F Maximum Incore Thermocouple:
145 F RCS Loop Temperatures:
A 8
Ilot leg 118 F 121 F Cold Leg 71 F 73 F 72 F 73 F RCS Pressure:
96 psig Reactor Building:
Temperature:
77 F Water level:
Elevation 290.8 ft. (8.4 ft, from floor) via penetration ~401 manometer Pressure:
-0.4 psig Concentration:
4.9 x 10-6 uCi/ml Kr-85 (Sample taken 7/ 1/81 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 f4RC requirements and City of Lancaster Agreement dated February 27, 1980.
During the period June 28, 1981, through July 5,1981, the effluents contained no detectable radioactivity at the discharge point and individual effluent sourcs which originated within Unit 2 contained no detectable radioactivi.y.
. 2.
_ Environmental Protection Agency (EPA) Environmental Data.
Results from EPA monitoring of the environment around the TM1 site were as follows:
3 The EPA measured Kr-85 concentrations (pCi/m ) at several environse.a.tal monitoring stations and reported the following results:
Location June 19
. June 26, 1981 3
(pCi/m)
Goldsboro 20-Observation Center 20 Middletown Yorkhaven 20
- Results not available due to procedural difficulty.
All of the above levels of Kr-85 are considered to be back-ground levels.
No radiation above normally occurring background levels..was detected in any of the samples collected from the EPA's air and ganma rate networks during the period from June 25, 1981, through July 2, 1981.
3.
NRC Environmental Data.
Results from NRC monitoring of the environ-ment around the TM1 site were as follows:
The following are'the NRC air sample analytical results for
~
^
the onsite continuous air sampler:
1-131 Cs-137 Sample Period
_(uCi/cc)
(uCi/cc)
HP-274 June 24,1981 - July 2,1981
<8.2 E-14 <8.2 E-14 4.
Licensee Radioactive Material and Radwaste Shipments On Monday, June 29,1981, a 40 ml Unit 2 reactor coolant sample was sent to Babcock and Wilcox (B&W), Lynchburg, Virginia.
On Wednesday, July 1, 1981, one cask containing 17 drums of Unit'2 LSA compacted and noncompacted waste was shipped to U.S. Ecology,' Richland, Washington.
On Thursday, July 2,1981, two Hittman steel liners containing Unit 1 solidified evaporator bottoms were shipped to U.S. Ecology, Richland, Washington.
f
,e g y
y
^ 4 Major Activities 1.
Submerged _Demineralizer System (SDS).
The first waste water transfer from the Reactor Coolant Bleed Tank (RCBT) "B" to the' SDS ifeed tanks commenced on June 30, 1981.
The RCBT "B", which contains waste water generated during the decontamination of the Unit 2 Auxiliary Building, is scheduled to be processed in two 50,000 gallon-
' batches. Transfer of one batch was completed July-5,1981.
RCBT "B" water was transferred through two_-particulate filters (pre and
[_
final) into the SDS feed tanks.
After minor startup problems, the evolution proceeded. smoothly.
Processing through ion exchange i
vessels is tentatively scheduled to begin during the week of
- July 6, 1981.
i -
_The-TMI Program Office has currently approved 21 of the 37 required
' procedures to operate the SDS.
These 21 procedures were required to be; approved prior to RCBT "B" transfer to the SDS feed tanks.
-The remaining procedures need NRC approval prior to SDS processing.
Functional testing of the remaining parts of the SDS' have been -
completed with the exception of the zeolite vessel trains.
Operator training for processing feed tank water through the SDS is.
continuing.in conjunction with system functional testing and' 7 zeolite vessel loadings.
2.
EPICOR-II' Liner Di sposal.
On June 30, 1981, the last 2 (of 22) i second and third stage EPICOR-II liners reached the burial site in Hanford, Washington.
These liners were generated during the
_ processing of contaminated water through the EPICOR-II system.
The EPICOR-II system was used to process Auxiliary Building water (approximately 500,000 gallons) from the March 28, 1979 accident.
~ Forty-nine first stage prefilter (PF) EPICOR-II liners are still I
stored on site.
The-best method of disposal for these higher activity liners is being evaluated at the present time.
One of the higher activity liners (PF-16)_ wa", shipped to Battelle Northwest 6
Laboratories for analysis on May 19, 1981.
3.
Reactor Building Entry.
Four Fen inspected and surveyed the Unit 2
-Reactor Building (RB) polar crane during a RB entry on July 1,1981.
3 f
Six of the 14 polar crane motor: were.meggered during the two hour inspection.
The resistance between the motor phases and ground, as
. measured at a coninon junction-box, ranged between 0.2 and 0.5 megohms.
The licensee-is evaluating the significance of these measurements, although the low resistance suggests that the motors may be damaged.
Insulation on some crane power cables was damaged to the extent that bare conducting wires were visible.
The padding on the seat of the crane operator's chair was burned and charring in the crane cab appeared to indicate-the presence of flames during the March 28, 1979, accident. ' Crane mechanical components appeared undamaged although patches 'of. rust were evident.
The licensee is evaluating what repairs will be necessary before the crane can be used to remove the Lreactor vessel head.
4
=
. Upon exiting the RB, the entry team underwent routine " frisking" for radioactive contamination.
Contamination was found on the skin of all four individuals.
The primary areas of contamindtion included the buttocks, elbows, and knees.
Personnel decontamination procedures were initiated and after several hours, three of the four individuals were decontaminated on July 1,1981.
The buttock of the fourth individual was not completely decontaminated until the following day.
The skin contamination apparently resulted from climbing on con-taminated crane surfaces in persperation soaked protective clothing.
Following several instances of personnel exhaustion during RB entries, the licensee relaxed tne criteria for use of plastic protective clothing in the RB to reduce fatigue and the crane inspection team was wearing only two sets of protective clothing.
The outer layer of protective clothing was advertised by the manufacturer as water impermeable.
The same type of protective clothing had been worn durir.g the initial climb on the crane with
.no instances of skin contamination.
The second crane climb was physically more demanding and all team members exited from the RB exhausted with the inner layer of protective clothing completely soaked.
The licensee is evaluating the available information to determine what combination of protective clothing is required for future entries.
The next RB entry is scheduled for July 23, 1981.
e 6
k.
.. Meeting Held On Wednesday, July 1,1981, Lake Barrett met with area mothers to discuss various subjects related t TMI.
Topics included gas generation
.I
.in stored EPICOR-II prefilters, how the NRC audits licensee radiological analyses by independent measurements, SDS and cleanup progress.
Future Meeting On Thursday, July 9,1981, the Advisory Panel for the Decontamination of Three Mile Island, Unit 2 will be meeting from 7:00 p.m. to 10:00 p.m.
in the Holiday Inn, 23 South Second Street in Harrisburg, to discuss the current status of cleanup activities at TMI.
This meeting will be open for public observation.
e 49 W-i
\\
_.