ML20210K475
| ML20210K475 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 04/21/1986 |
| From: | Travers W Office of Nuclear Reactor Regulation |
| To: | Harold Denton, Miraglia F Office of Nuclear Reactor Regulation |
| References | |
| CON-NRC-TMI-86-037, CON-NRC-TMI-86-37 NUDOCS 8604280318 | |
| Download: ML20210K475 (4) | |
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April 21,1986 NRC/THI-36-037 11EMORANDUM FOR:
Harold R. Denton, Director Office of Nuclear Reactor Regulation
'4 Frank J. Miraglia, Director Division of PWR Licensing-B ii' FROM:
William D. Travers, Director y
THI-2 Cleanup Project Directorate
SUBJECT:
N M 9 CLEANUP PROJECT DIRECTORATE WEEKLY STATUS c
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REPORT FOR APRIL 14 - April 20,1986 A
1.
DEFUELING y.,
As of April 20, 1986, a total of 41 defueling canisters have been a
loaded with fuel debris and transferred to the canister storage racks in the "A" Spent Fuel Pool in R.e Fuel Handling Building. The 4
total weight of debris transferred out of the reactor vessel is 50,170 lbs representing 16% of the 308,000 lbs. estimated to be in the vessel.
On April 20, 1986, operation of the newly modified Temporary Reactor Vessel Filtration System (TRVFS) began. The modifications to the system consist of a larger diatomaceous.carth filter media capacity,
- i higher flow rates, and the use of a fuel debris knockout canister as
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a discharge vessel. The modified TRVFS is one subsystem of the new Reactor Vessel Water Cleanup System (RVWCS) designed to cleanse the reactor vessel water of bio-organism growths. The other subsystem
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includes a positive displacement pump which will destroy the bio-organisms by high pressure.
i A thorough inspection of the Vacuum Defueling System (VDS) was conducted. During the inspection, the connect assembly between the l
knockout canister and the pumping station was found to be damaged.
Repair of the connect assembly consisted of replacement of the gripper subassembly which was found to be distorted. Completion of-e l
- q other miner maintenance including load cell'and back flush flow meter repair is scheduled this week. A vacuum defueling test will 2;
be conducted after completion of all repairs and-improvement in' visibility in the reactor vessel.
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Harold R. Denton 2
April 21, 1985
,y Frank J. Miraglia NRC/THI-85-037 2.
RAIL SHIPPING CASKS APPROVAL On April 11, 1986, the NRC issued Certificate of Compliance flumber 9200 to the Department of Energy (DOE)..This Certificate' approves the use of HUPAC-125B railcar mounted fuel debris shipping casks. DOE will.use two of these casks to transport the THI-2 core debris from the site to the Idaho National Engineering Laboratories for storage and research.
3.
PLANT STATUS The reactor remains in long term cold shutdown, vented to atmosphere. Core cooling is by natural heat loss to ambient building atmosphere. The average incore thermocouple reading is 79*F.
The airborne radioactivity on-the defueling platform is about 1.7 E-7 uCi/cc Tritium and 5.6 E-11 uCi/cc predominately Strontium-90.
The platfom is mounted above the modified internals indexing fixture which is mounted on the' reactor vessel flange. These provide water coverage of 151 feet over the core region. This water level is about 5 feet over the top of any debris canisters in the reactor vessel.
4.
tlASTE MANAGEMErlT TheSubmergedDemineralizerSystem(SDS)isshutdown. SDS total processed to date is 3,885,859 gallons.
EPICOR II was in temporary shutdown this week. EPICOR II total processed to date is 2,854,371.
5.
E!!VIRONMENTAL MONITORING US Environmental Protection Agency (EPA) sample analysis results show that THI site liquid effluents are in accordance with regulatory limits, NRC requirements, and the City of Lancaster Agreement.
THI water samples taken by EPA at the plant discharge (includes THI-1 and THI-2) to the river consisted of seven daily composite samples taken from liarch 29 through April 5,1986. A gamma scan detected no reactor related activity above the lower limit detectability. Trace indications of Cesium-137 may be present but are not in sufficient quantities to be quantified or clearly identified.
The I.ancaster water sample taken at the water works intake and analyzed by EPA consisted of a seven day composited sample taken from March 30 through April 5, 1936. A gamma scan detected no reactor related radioactivity.
The flRC outdoor airborne particulate sampler at the THI site collected a sample between April 10 - 17, 1986. No. reactor related
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t radioactivity was detected. Analysis'showed Iodine-131 md Cesium-137 concentrations to be less than the lower limits of detectability.
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NQC FORM 318 (10-80) NRCM O240 OFFICIE RECORD COPY
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' Harold R.'Denton 3
April 21, 1986 r
Frank J. Hiraglia NRC/T!!I-86-037 6.
AUXILIARY AND FUEL HAtlDLIflG BUILDING ACTIVITIES b
Scabbling and painting of the floors in the neutralizer tank' rooms were done this week.
Scabbling was done in the reclaimed boric acid tank rooms.
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Steam cleaning was completed in.the tendon access gallery.
7.
NRC EVALUATIONS IN PROGRESS Technical Specification Change Request number 49, and 51.
Recovery Operations Plan Change number 31, 33, 35, and 36.
Core Stratification Safety Evaluation.
Solid Waste Facility Technical Evaluatien Report.
Reactor Building Sump Criticality Safety Evaluation Report.
Underhead High Pressure Decon Safety Evaluation Report.
Canister Handling and Preparation for Shipment Safety Evaluation Report.
Defueling Canister Technical Evaluation Report, Revision 2.
Penetration 536 llodification Safety Evaluation Report original signed by J'4 Curt Cowgill for:
q Hilliam D. Travers 4-Director p
TMI-2 Cleanup Project Directorate e
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4 April 21, 1986
-Frank J. !!iraglia NRC/TMI-86-037 v
INTEPJIAL DISTRIBUTION
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Comissioner's Technical Assistants NRR Division Directors NRR A/D's Regional Administrators IE Division Directors TAS EIS TMI Cleanup Project Directorate (10)
PHS EPA DDE RI Division Directors lI Public Affairs, RI State Liaison, RI THIPO HQ r/f TMI SITE r/f CENTRAL FILE
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