ML20023D622
| ML20023D622 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 05/09/1983 |
| From: | Barrett L Office of Nuclear Reactor Regulation |
| To: | Harold Denton, Snyder B Office of Nuclear Reactor Regulation |
| References | |
| CON-NRC-TMI-83-029, CON-NRC-TMI-83-29 NUDOCS 8305240603 | |
| Download: ML20023D622 (7) | |
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DISTRIBUTION TMIP0 HQ r/f c
TM1 SITE r/f CENTRAL FILE C NRC PDR LOCAL PDR TMI-2 Project itay 9, 1983 Section File NRC/Tl!I-83-029 Office of huclear, DirectorReactor Regulation Harold R Denton HEMORANDUM FOR:
Bernard J. Snyder, Program Director THI Program Office FROM:
Lake H. Barrett, Deputy Program Director TMI Program Office
SUBJECT:
NRC TMI PROGRAM 0FFICE WEEKLY STATUS REPORT Enclosed is the status report for the period of !!ay 1,1983, through May 7, 1983.
Major items included in this report are:
i Liquid Effluents EPA and NRC Environmental Data Radioactive Material and Radwaste Shipments TitI Occupational Exposure Submerged Demineralizer System Status EPICOR II Status SDS Liner Shipments EPICOR II Prefilter Shipments Reactor Building Entries f
Polar Crane l
Public Meeting Lake H. Barrett Deputy Program Director TMI Program Office '
Enclosure:
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Harold R. Denton 2
May 9, 1983
-Bernard J. Snyder cc w/ enc 1:
EDO OGC Office Directors Commissioner's Technical Assistants NRR Division Directors NRR A/D's Regional Administrators IE Division Directors TAS EiS ThI Program Office Staff (15)
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V NRC TMI PROGRAM 0FFICE WEEKLY STATUS REPORT May 1, 1983 - May 7, 1983 j
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P11 c. Status j
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Core Cooling Mode: Heat transfer from the reactor coolant system (RCS) to reactor building ambient.
Availabe.CoreCoolingMode: Mini Decay Heat Removal (MDHR) system.
RCS Pressur,e Control Mode:
Standby Pressure Control System.
Major-Parameters-(as of 5:00 AM, May 6, 1983) (approximate values) 1 Average Incore Thermocouples*:
91*F Maximum Incore Thermocouple *:
134*F Lif iRCS Loop Temperatures:
A B
Hot Leg 87'F 85'F
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ColdLeg(1) 76*F 76*F L
(2) 77'F 76 F l
lo RCS Pressure: 64 psig L,
Reactor Building: Temperature:
70*F o
Pressure:
-0.1 psig Airborne Radionuclide Concentrations:
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1.8 E-7 uCi/cc H A.
(sample taken 5/5/83) y 1.1 E-9 uCi/cc particulates
>*j (sample taken 5/5/83)
L'1 1.
Effluent and Environmental (Radiological) Information 3
Liquid effluents from the TMI site rel*esecl to the Susquehanna River, s.
after sampling and monitoring, were di', ?.n the regulatory limits and in
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accordance with NRC requirement' ?;' Ci y of Lancaster Agreement.
I During the period April 29,196, thrup May 5,1983, the effluents contained no detectable radioactivity at the discharge point and o
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individual effluent sources, which originated within Unit 2, contained minute amounts of radioactivity.
Calculations indicate that less than seventeen-millionths (0.000017) of a curie of cesium was discharged.
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- Uncertainties exist as to the exact location and accuracy of tiiese readings.
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2.
Environmental Protection Agency (EPA) Environmental Data The EPA Middletown Office has not received the environmental Kr-85 analytical results for the samples which were taken subsequent to April 15, 1983, from the EPA's Counting Laboratory at Las Vegas, Nevada. These results will be included in a subsequent report.
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 April 27, 1983, through May 5, 1983.
3.
NRC Environmental Data 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-368 April 28 - May 5, 1983
<7.3 E-14
<7.3 E-14 4.
Licensee Radioactive Material and Radwaste Shipments On May 2,1983, two boxes containing steam generator repair equipment taken from Unit I were shipped to Babcock and Wilcox, Lynchburg, Virginia.
On May 2, 1983, two separate shipments of one 20 WC-4 shipping cask a
containing a Unit 2 makeup and purification sample were made to Oak l
Ridge National Laboratories, Oak Ridge, Tennessee.
4 On May 3, 1983, one-CNSI 8-120-3 shipping cask (Type B) containing i
Unit 2 EPICOR prefilter No. PF-23 was shipped to EG&G, Scoville, Idaho.
f On May 4, 1983, 93 drums containing contaminated laundry-from i
Units 1 and 2 were shipped to Interstate Uniform, New Kensington, Pennsylvania.
On May 5, 1983, 8 drums and 8 boxes containing compacted and non-1
' compacted trash from Unit 1 and 2 were shipped to U.S. Ecology, Hanford burial site, Richland, Washington.
t On May 6, 1983, one box containing Unit 2 reactor building vibration and monitor sensors was mailed to Sandia National Laboratory, Albuquerque, New Mexico.
On May 6, 1983, three separate shipments of.two Unit. 1 solidified evaporator bottoms were made to U. S. Ecology, Hanford burial site, Richland, Washington.
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5.
TMI Occupational Exposure
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Licensee TLD (Thermoluminescent Dosimeter) records indicate the following Unit 2 occupational radiation exposures for 1983:
March 1983 41 man-rem Total 1983 (January-March) 133 man-rem Man-rem is an expression for the summation of whole body doses to indivi-duals in a group. Thus, if each member of a population group of 1,000 people were to receive a dose of 0.001 rem (1 millirem), or if two people were to receive a. dose of 0.5 rem (500 millirem) each, the total man-rem dose in each case would be 1 man-rem.
Major Activities i
1.
Submerged Demineralizer System (SDS).
SDS began processing the tenth batch of reactor coolant system (RCS) water on May 4, 1983. This batch, comprised of approximately 36,000 gallons, had been staged to the "C" reactor coolant bleed tank by the RCS feed and bleed process.
(See Weekly Status Report of May 17, 1982, for feed and bleed process description.) SDS performance parameters will be included with the report for May 16, 1983.
1 2.
EPICOR II.
EPICOR II is currently in a shutdown mode.
3.
SDS Liner Shipments. The licensee is making preparations for shipment of the ninth SDS waste liner (D10014). This zeolite liner, which contains approximately 59,800 curies, will be vacuum dried, loaded with a catalytic recombiner and monitored to demonstrate non-combustible gas conditions prior to shipment. Shipment is tentatively scheduled for May 17, 1983.
4.
EPICOR II Prefilter (PF) Shipment. One EPICOR II prefilter (PF-23) was shipped from TM1 to the Idaho National Engineering Laboratory (INEL) on May 3, 1983. This shipment arrived in Scoville, Idaho, on May 6, 1983.
This represents a total of 37 prefilters (in a group of 50) that have been shipped by the Department of Energy to INEL.
No shipments are scheduled for next week.
l 5.
Reactor Building Entries. Five reactor building entries were completed l
during the week of May 1, 1983.
The work effort during the entries was focused on localized decontamination and dose reduction tasks.
A procedure to calibrate the source range neutron monitors using a Am Be neutron source was rescheduled for the week of May 8, 1983.
Five reactor building entries are scheduled for the week of May 8, 1983. The major work effort will again be focused on localized decontamination and dose reduction tasks.
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Two personnel from the NRC TMI:P0 conducted an inspection inside the reactor building on Thursday, May 5, 1983. The inspection scope included:
(1) effectiveness.of dose reduction measures, (2) industrial safety / fire protection, (3) evaluation of potential hazards during polar crane operations, (4) vulnerability of incore instrumentation pressure boundaries to damage during recovery operations, and (5) inspection of components and systems needed for reactor disassembly.
Several areas requiring follow-up action were identified and these are i.
being pursued with cognizant licensee personnel.
Significant issues identified in the inspection will be addressed in the inspection report issued monthly by the NRC Region I office. The whole body dose accumulated by the NRC personnel during the 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> 15 minute inspection t
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'was 196 mrem to one individual and 286 mrem to the other.
6.
Polar Crane Activities. Except for a task to reset trolley travel limit switches, no work was performed on the polar crane this week.
Polar crane load testing and subsequent operations are still delayed pending resolution of NRC procedural comments. There~is no schedule, at the-present time, to resume activities to requalify the polar crane until comments are resolved. The polar crane requalification is a prerequisite activity for reactor head removal and reactor disassembly. The next phase of the underhead data acquisition, control rod drive mechanism removal and underhead visual inspection, was also dependent on the use of the polar crane. However, because of uncertainties in the crane refurbishment schedule, engineers have commenced work on procedures to remove the control' rod drive mechanism without use of the polar crane.
Information on this approach will be included when GPU finalizes their plans.
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5 Past Meeting On May 2, 1983, Lake H. Barrett met with the Concerned Mothers of Midd to discuss cleanup operations at TMI-2.
Unit 1 should not be restarted prior to completion of the Unit 2 cleanup.
Fut'are Meeting Lake H. Barrett will ineet with the Concerned Mothers of
'On May 16, 1983, Middletown to discuss TMI related issued.
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