ML20052J032
| ML20052J032 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 05/17/1982 |
| From: | Barrett L Office of Nuclear Reactor Regulation |
| To: | Harold Denton, Snyder B Office of Nuclear Reactor Regulation |
| References | |
| CON-NRC-TMI-82-031, CON-NRC-TMI-82-31 NUDOCS 8205240342 | |
| Download: ML20052J032 (9) | |
Text
e DISTRIBUTION TMIPO HQ r/f TMI SITE r/f CE!:'"',^,L FILE NRC PDR llay 17, 1982 LOCAL PDR NRC/TitI-82-031 Site Operations File DO-3 ftE!!ORANDUM FOR:
Harold R. Denton, Director Office of Nuclear Reactor Regulation Bernard J. Snyder, Program Director THI Program Office FR0ft:
Lake H. Barrett, Deputy Program Director T!!I Program Office
SUBJECT:
NRC TMI PROGRAM OFFICE WEEKLY STATUS REPORT Enclosed is the status report for the period of flay 9,1982 to May 15,1982.
Major items included in this report are:
Liquid Effluents Airborne Effluents a
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4 NRC and EPA Environmental Data Radioactive Material and Radwaste Shipments I
NED 4
MAYg Submerged Demineralizer System Status p
f EPIC 0R 11 g
<3 Reactor Coolant System Water Processing A
u Reactor Building Entries Graundwater Monitoring Public licetings Originals W W mye H. PaM Lake H. Barrett Deputy Program Director-Till Program Office i
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Enclosure:
As stated i
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EDO OGC Office Directors Comissioner's Technical Assistants NRR Division Directors HRR A/D's Regional Directors IE Division Directors TAS EIS TMI Progran Office Staff (15)
PHS EPA DOE Projects 3r. #2 Chief, DRPI, RI i
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OFFICIAL RECORD COPY
liRC Tiil PROSP.AM 0FFICE WEEKLY STATUS REPORT May 9,1982 - May 15,1982 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 (DHR) s'ystems, Mini DHR(MDHR) system.
j RCS Pressure Control Mode:
Standby pressure control (SPC) system.
Backup Pressure Control Modes: MDHR and DHR system.
Major. Parameters (as of 0500, May 14,1982) (approximate values)
Average Incore Thermocouples:
103 F Maximum Incore Thermocouple:
129 F RCS Loop Temperatures:
A B
Hot Leg 98 F 10l*F Cold Leg (1) 85*F 84*F (2) 90*F 86 F Pressure:
96 psig Reactor Building:
Temperature:
72*F Water level:
Elevation 282.8 ft.
(0.15 ft. from floor)
Pressur2:
-0.35 psig Airborne Radionuclide Concentrations:
3 4.5 E-7 uCi/cc H (sample taken 5/4/82) 85 7.8 E-6 uCi/cc Kr (sample taken 5/4/82) 5.3 E-10 uti/cc particulates (sample taken 5/13/82) 1.
Effluent and ' Environmental (Radiological) Information
. Liquid effluents from the TMI si e released to the Susquehanna River t
after processing, were made within the regulatory limits and in accordance with fiRC requirerents and Ci'y of Lancaster Agreenent dated February 27, 1980.
During the period May 7, 1982, through May 13, 1982, the effluents contained no detectable radioactivity at the discharge point and individual effluent scurces, which originated within Unit 2, contained no detectable radioactivity.
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Airbcrne Effluents Airborne releases to the environment as measured by licensee installed monitors at discharge sta'Cks are listed below.
These releases were well w; thin regula: cry limits.
April 1982 Unit II EPICOR 11 I
I t<oble Gases (Ci)
<2.29 x 10 2.97 x 10 Particulates (Ci) 1.50 x 10-6 3.15 x 10-7 Tritium (C1) 1.80 2.30 x 10'3 3.
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 April 16, 1982, through May 7, 1982, 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 netv.orks during the period from May 5, 1982 through May 13, 1982.
4.
NRC Environmental Data Results from i4RC monitoring of the environment around the TMI site were as follows:
The following are the NRC air sample analytical results for the onsite continuous air sampler:
1-131 Cs-137 Sample Periq (uCi/cc) luCi/cc)
HP-319 May 5, 1982 - May 8, 1982*
< l.4 E-13 <,1.4 E-13
- Note:
The NRC continuous air sampling equipment was placed out-of-service.on.MAy.J#.1982.
Repairs to the equipment are in progress' and-the unit is expected to be returned to service on May 19, 1982'.
5.
Licensee Radioactive Material and Radwaste Shipment On Friday, May 7,1982, five 250 milliliter lliqisid samples from ~
Unit 1 were maileo to Westinghouse Corporation, Madison, Pennsylvania.
On Tuesday, May 11, 1982, 10 drums containing Unit 2 miscellaneous.
submerged demineralizer system (SDS) samples were shipped to Oak Ridae National Laboratories, Oak Ridge, Tennessee.
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. Major Activities 1.
Submerged Demineralizer System- (SDS).
Processing of SDS batch 26 (reactor coolant bleed tank water) was completed on May 8, 1982.
The performance parameters for this batch are included in Attachment 1.
The SDS system is now secured for minor maintenance in preparation for processing of reactor coolant system (RCS) water (see RCS processing).
Preparations are being made for the first shipment of an SDS vessel to Richland, Washington.
SDS vessel number D-15 contains approximately 4,800 curies of predominately cesium 137 and strontium 90. A special Type B shipping cask has been provided for this shipment.
The SDS vessel and the shipping cask cavity will be inerted with nitrogen in order to meet the requirements of the Certificate of Compliance (C0C) for shipping.
The actual shipment is scneduled to start on May 21, 1982 with arrival at Richland expected on May 25, 1982.
The receiver, Pacific Northwest Laboratory (PNL), will use this vessel as part of their DOE-sponsored vitrification research and development program.
2.
EPICOR II.
The EPICOR 11 system continued to process SDS effluents during the week and its performance parameters are included in 3.
Reactor Coolant System (RCS) Water Processina.
Eng.ineering and construction efforts by the licensee in preparation for RCS processing have been completed.
Recovery Operations Plan Change 12, which addresses chemistry specifications for chlorides, dissolved oxygen, and dissolved hydrogen, has been approved by the NRC/TMIPO site office and the Chemical Engineering Branch of Nuclear Reactor Regulation.
The functional test of i
modifications and sampling systems for RCS processing is completed.. RCS processing through SDS will occur on an approximately 14 day cycle. The l
first seven days of the cycle will consist of'RCS letdown to the "C"
reactor coolant bleed tank (RCBT), concurrent with makeup to the RCS from the "A" RCBT, until approximately 50,000 gallons of RCS water are in the "C"
RCBT.
The next seven days of the' cycle will constitute actual processing of the 50,000 gallon batch:from the "C" RCBT through the SDS system. The process will bypass the SDS feed tanks.
This seven ' day feed and bleed cycle followed by the seven day SDS cycle will continue until all the RCS water.has.beert.orocessed.
The RCS processing operation is scheduled tn begin on May 17, 1982.
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4.
Reactor Buildino Entries.
The next reactor building entry is scheduled for Thursday, May 20, 1982.
Supporting activities for the control rod drive lead screw removal will commence during this entry.
Scheduled -
tasks includs radiation surveys of reactor coolant system high point vents and the in containment nitrogen supply system.
A dose rate monitoring device will be lowered into various areas inside the "D-rings" (reactor coolant system radiation barriers) to determine whether the radiation levels in the "D-rings" will permit personnel access to attach a tygon tube type water level monitor to the reactor coolant system.
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. Prior to lead screw removal, the reactor coolant system will be depressurized and the prihary water level will be lowered below the tops i
of the control rod drive housings.
The lead screw removal and closed circuit television inspection of the reactor vessel upper internals is scheduled for July.1982.
5.
Groundwater Monitoring. The elevated tritium concentrations in groundwater in the vicinity of the borated water storage tank have remained in essentially the same ' range as identified in previous Weekly Status Reports. includes a sketch of the groundwater sampling locations (test borings) with the most recent tritium analysis results annotated next to each test boring.
The tritium activities noted for wells 2, 3, 10, 16 and 17 were obtained from water samples taken on l
l May 11, 1982. Water samples from the remaining wells were obtained on April 13, 1982 and analyzed by an independent offsite laboratory.
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_5 Past Meetings 1.
On May 11, 1982, Lake Barrett participated in a panel discussion on TMI issues, which was locally televised in the Central Pennsylvania area.
Other panelists included Susan Shanaman, Chairman, Pennsylvania State Public Utilities Commission; General Dewitt Smith, Director, Pennsylvania Emergency Management Agency; Mr. Philip Clark, Executive Vice-President, General Public Utilities; Mr. Steven Sholly, Union of Concerned Scientists; Ms. Kathy McCaughin, Bipartisian Committee to Vote "No", and Mr. Earl Peters, Friends and Family of TMI.
The moderator for the panel discussion was Representative James Wright, Chairman of the House Select Committee on TMI.
The purpose of the discussion was to provide information to residents of the Dauphin, Cumberland and Lebanon counties, which have referendums on May 18th to answer yes or no to the following question:
"Do you favor the restart of TMI Unit 1, which was not involved in the accident of March 28, 1979?"
2.
On May 11, 1982, Lake Barrett met with a group of Middletown mothers to discuss various TMI Unit I and Unit 2 issues.
They expressed their opinion that Unit 1 should not be restarted until Unit 2 is cleaned up.
Future Meetings 1.
On May 19,1982, Lake Barrett will meet in the.Middletown Office with several Middletown area residents to discuss TMI issues.
?.'
On May 20, 1982, Harold Denton, Bernard Snyder and Lake Barrett will testify in Washington, DC, before Senator Alan K. Simpsons' Senate Subcommittee on Nuclear Regulation, Environment and Public Works Committee.
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t ATTACHME!;T 1 I
SDS PERFORl'ANCE F0k BATCH NUMBER 26 Average Average Average Radionuclide Influent Effluent DF (uc/ml)
(uc/ml )
3 Cesium 137 1.5 1.5 x 10-3 1.0 x 10 Strontium 90 9.1 x 10-2 9.8 x 10-3 9.3 t
EPICOR II PERFORMANCE May 7, 1982 - May 14, 1982 t
Average Average Average Radionuclide Influent Effluent DF (uc/ml)
(uc/ml) i 3
Cesium 137 1.5 x 10-3 4.5 x 10-7 3.3 x 10 6.2 x 10-3~
<1.1 x 10-5
> 5.6 x 102 Strontium 90 3
Antimony 125 3.0 x 10~4
< 3.4 x 10-7
> 1.0 x 10 i
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