ML20004C125
| ML20004C125 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 05/22/1981 |
| From: | Barrett L Office of Nuclear Reactor Regulation |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| CON-NRC-TMI-81-030, CON-NRC-TMI-81-30 NUDOCS 8106010573 | |
| Download: ML20004C125 (8) | |
Text
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DISTRIBUTION TMI Program Office /HQ r/f TMI SITE r/f i
HHmTRAL FILE NRC PDR LOCAL PDR Y
Site Operations file P
P00R ORIGINAL MEMDRANDtM FOR:
Harold R. Denton, Director.
Office of _ Nuclear Reactor Regulation
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Bernard J.' Snyder, Prcgram Director, l
TMI Program Office FROM:
Lake H."Barrett, Acting Deputy Frvv.
- Director, THI Program Office i
SUBJECT:
MRC TMI'PiiOGRAM OFFICE WEEK 1.Y STA11]S REPORT Enclosed is the status report for the period of May 17 - 22, 1981.
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1 Lake H. Barrett
-l Acting Deputy Progres Director TMI Program Office o
Enclosure:
As stated cc: EDO "I
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f Office Directors c}3' (gK 1./ %j yI h
l Commi ssioner's Technical. Assistants NRR Division Directors NRR A/D's 9
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i Regional Directors d I!A'f 2 81981 m.
IE Division Directors Ej u.s, % %
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li X0MA TMI Program Office Staff.(15) d' l }l l
Projects Br. No. 2 Chief. DPRI, RI l
DPRI Chief, RI
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Public Affairs, RI T. Elsasser 810 n n, n 573
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NRC TMI PROGRAM 0FFICE WEEKLY STATUS REPORT Week of May 17 - 22, 1981 Plant Status Core Cooling Mode: Heat transfer from the reactor coolant system (RCS) loops to Reactor. Building ambient.
Available Core Cooling Modes: Long-term cooling "B" (once through steam generator-B); decay heat removal systems.
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 0400, May 22,1981) (approximate values)
Average Incore Thermocouples: 116 F Maximum Incore Thermocouple:
142 F RCS Loop Temperatures:
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A B
Hot Leg 111 F 114 F Cold Leg ((1) 65*F 66*F 2) 66*F 66*F RCS Pressure: 9" psig l
Reactor Building: Temperature: 67 F Water level:
Elevation 290.8 ft. (8.3 ft. from floor) via penetration 401 manometer Pressure:
-0.4 psig Concentration: 1.1 x 10-5 uCi/ml Kr-85 (Sample taken 5/18/81)
Efrauent 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 May 15, 1981, through May 21, 1981, the effluents contained no detectable radioactivity at the discharge point although individual effluent sources which originated within Unit 2 contained minute amounts of radioactivity.
Calculations indicate that less than 1 millionth (0.000001) of a curie of Cs-137 was discharged. This represents less than 0.00001% of the permissable total liquid activity as specified in Technical Specifications for operational commercial
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reactors.
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. 2.
Airborne effluents from the TMI site released to the environment, f.
after processing, were made within the regulatory limits and in
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- accordance with NRC requirements p,
s During the reporting period January 1,1981 - March 31,1981, the i
licensee reported the following gaseous releasas:
Curies
(
Noble' Gases 25.3 h
Particulates
.0.000015 Tritium 33.0
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I The above release represent a small f. action of the allowable E
regulatory limits.
The instantaneous airborne effluents are measured y
on a continuous basis, however for accurate calculation of total b
curies released,. effluent samples are analyzed in the laboratory E
and the data evaluated.
On the basis of the data from these samples, i
a draft effluent report is' issued monthly by the licensee. Airborne i
effluent information will be provided in the weekly status report on a monthly basis.
i 3.
Environmental Protection Agency (EPA) Environmental Data.
Results i
from EPA monitoring of the environment around the TMI site were as f
follows:
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The EPA measurad Kr-85 concentrations (pCi/m ) at several b
environmental monitoring stations and reported the following f
j results:
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l Location May 8 - May 15, 193l
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(pCi/m )
g c-l Goldsboro 22 Observation Center 33 k
Mi.ddletown
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29-l Yorkhaven 27
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All of the above levels of Kr-85 are considered to be back-1 l
ground levels.
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3 The installation of tritium (H ) monitoring devices has been
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l completed at the above listed locations.
It is expected that
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H3 environmental results will be routinely reported by EPA in P
about four to six weeks.
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No radiation above normally occurring background levels was detected in any of the samples collected from the EPA's air s
and ganna rate networks during the period from May 14, 1981,.
f through May 21, 1981.
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- 4. ~ NRC Environmental Data.
Results from NRC monitoring of the environ-h',
ment around the TMI site were as follows:
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e 3-The following are the NRC air sample analytical results for the onsite continuous air sampler:
-Cs-137 Sample Period Luci/cc)
(uCi/cc).
4 May 13,1981 - May 20,1981
<8.8 E-14 <8.8 E-14 HP-268 c
5.
Licensee Radioactive Material and Radwaste Shipments
.On Monday, May 18 1981, a 40 ml Unit 2 reactor coolant sample was sent to Babcock and Wilcox (B&W) Lynchburg, Virginia.
On Tuesday, May 19, 1981, the U.S. Department of' Energy (DOE) shipped an EPICOR-II resin line" (PF-16) from Unit 2 to Battelle Columbus Laboratories in Columbus, Ohio. (The liner and resin will undergo examination and testing at the laboratory.)
On Wednesday (, May 20,198f, one 4' x 4' EPICOR-II dewateredliner DF-resin liner Richland, Washington.
Major Activities i
1.
Submerged Demineralizer System-(SDSl.
Preparation of the Safety Fvaluation Report (SER) by the TMI.'rogram Office is in progress although some necessary information has not yet been received. On i
May 13,1981, the licensee submitted a revised schedule for providing
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the needed information. The revised schedule indicates the information will be provided by May 29, 1981.
Functional tests are complete with the exception of a few items which are undergoing engineering evaluation and further testing.
Operator training on components not involved with the outstanding functional testing has been initiated. The operator. training does not involve processing of contacinated water.
2.
Shipmen 5 of EPICOR-II Prefi-iter (F.'-16) to Battelle Colunbus Laboratories (BCL). As part of a 00~ sponsored resin characterization stuay, PF-15 was shipped to :he BCL in Hest Jefferson, Ohio, on May 19,1981.
This research effort is to supplement the development of technology for safely processing contaminated resins and to evaluate liner material compatability.
PF-16.was part of the 1st
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stage EPICOR-II treatment process for the accident generated water collected in the Auxiliary Building.
Prior to shipment, special preparations were made to ensure that PF-16 did not contain significant quantities of nonradioactive gases that could be generated by organic resin degradation (e.g.,
H, hydrocarbon gases, etc.) While gas generation was indicated 2
(a result of the approximately 16 month on-site storage period),
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No increase the PF-16 lirar pressure was reduced to atmospheric.in
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The liner was then placed in a type "B" shipping cask wh cThe shipping cask designed to withstand a transportation accident.
The PF-16
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weighs 32 tons and is constructed of steel and lead.
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liner is constructed of steel with thickness ranging
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i The shipment arrived safely at BCL without incident after the one day
- E The research effort will start innediately and is expected trip.
to last over a 21/2 year period.
f The eleventh entry into the Reactor Building (RB) Entry and Purge.
- 28. -1981. ' Tentative plans
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3.
Unit 2 RB is scheduled for Thursday, May call for the completion of six tasks:
-1 Installation of safety equipment on the polar crane.
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Installation of a portable, shielded gama spectrometer system.
Troubleshoot and repair of the Gai-Tronics (an installed comunications system within the Containment Building).
Survey of the "O Ring" area, preventive mainten valve)..
Complete the hose connections to the SDS surface suction pump.
Troubleshoot and repair an electrical panel (lighting) on the 347' elevation.
Complete Iff all tasks are attempted,18 men will enter the RB.
plans for all proposed tasks will be reviewed by the TMI Program Office prior to the entry.
It is expected An RB purge will consnence one day prior to entry.that le t'
purge.
The licensee continues i
Solid Waste Staging Facility Sump Contamination.
i to collect weekly samples of water from the solid waste stag 4.
contents as a method for early indication of liner degradation.
facility sump.
To date the results of the analysis has'been stable and do not indicate liner degradation.
The "A" staging module, in service.since January 1980, now has 55 spent-resin liners; the B module, in service 'since December 1 I
Graphic displays of Modules A and B now has 18 spent-resin liners.
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are attached.
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Future Meetings On Thursday, June 4, 1981, the Advisory Panel for the Decontamination of.
TMI Unit 2 will meet from 7:00 p.m. to 10:00 p.m. in the City Council Chambers, Kendig C. Bare Public Safety Building, 208 North Duke Street, Lancaster. At this meeting, which is open or public observance, the Panel will discuss Radiation Worker Exposut t and Health Effects.
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