ML20199D685
| ML20199D685 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 03/17/1986 |
| From: | Travers W Office of Nuclear Reactor Regulation |
| To: | Harold Denton, Miraglia F Office of Nuclear Reactor Regulation |
| References | |
| CON-NRC-TMI-86-025, CON-NRC-TMI-86-25 NUDOCS 8603240312 | |
| Download: ML20199D685 (4) | |
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liarch 17, 1986 HRC/TMI-86-025 MEMORANDUM FOR:
Harold R. Denton, Director Office of Nuclear Reactor Regulation JN Frank J. Miraglia, Director Division of PWR Licensing-B FR0ft:
William D. Travers, Director THI-2 Cleanup Project Directorate r
SUBJECT:
dgC_TBI-2CLEANUPPROJECTDIRECTORATEWEEKLYSTATUS REPORT FUlIMARCH 10 - MARCH 16, 1986 1.
DEFUELING As of March 16, 1986, 25 canisters with an approximate net weight of f
26,490 lbs have been transferred from the reactor vessel to the spent fuel pool storage racks.
Defueling remains hampered by 900r visibility in the reactor vessel because of biologic growths.
The " mature colony" contains aerobes, 4
anaerobes, fungi, algae and bacteria. Research continues in an effort to identify treatments to remove the growths. This colony is about the same as found in river water.
Early in the week the debris bucket hanger apparently became Jamed in the canister positioning system, preventing movement. Upon removal and inspectien, the canister system was unloaded, and a Quality Assurance (QA) inspection of the systen was conducted. Upon QA release, the canister-system was reloaded with five empty fuel canisters and defueling resumed. The pick and place operation now uses a wide-mouthed funnel to guide debris into the canister opening with a resultant increase in loading efficiency.
f 2.
PLANT STATUS The reactor remains in long term cold shutdown, vented to J
atmosphere. Core cooling is by natural heat loss to ambient building atmosphere. Calculated decay heat is 10.7 KW.
Incore themocouples average is 81*F.
The defueling platform 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 8603240312 860317 PDR ADOCK 05000320 ome= >
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11 arch 17,1936 Frank J. Miraglia NRC/Tl1I-86-025 the reactor vessel. The airborne radioactivity on the platform is C
8.9 E-8 uCi/cc Tritium and 2.8 E-11 uC1/cc particulates, predominately Cesium-137.
3.
WASTE MANAG84ENT The Submerged Denineralizer System (SDS) completed processing batch i
129, (neutralizer tanks) to the monitor tanks (8,579. gallons) and began processing batch 130 ("C" recctor coolant bleed tank) to the monitor tanks. SDS total processed to date is 3,842, 869 gallons.
EPICOR II completed processing batch 277 (10,877 gallons); batch 278 (9,763 gallons); and batch 279 (8.937 gallons) from the SDS monitor tanks.to CC-T-2.
EPICOR II total processed to date is 2,854,371 I
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gallons.
4.
ENVIRONMENTAL HONITORING US Environmental Protection Agency (EIA) sample analysis results 47 show THI site liquid effluents to be in accordance with regulatory limits, NRC requirements, and the City of Lancaster Agreement.
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' TMI water samples taken by EPA at the plant discharge to the river consisted of seven daily composite samples taken from February 22 through March 1,1986. A gamma scan detected no reactor related activity.
The Lancaster water sample taken at the water works intake and analyzed by EPA consisted of a-seven da composited sample taken from February 22 through March 1,198G. A gamma scan detected no reactor related radioactivity.
The NRC outdoor airborne particulate sampler at the THI site collected a sample between March 5, and 13,1986. No reactor related radioactivity was detected. Analysis showed Iodine-131 and Cesium-137 concentrations to be less than the loyier limits of detectability.
1 5.
AUXILIARY AND FUEL HANDLING BUILDING ACTIVITIES i
Installation of the balance of Defueling Water Cleanup System (DWCS) continued.
Preparations are being made' for decontamination in the Seal' Injection Room, 281' auxiliary building.
6.
NRC EVALUATIONS IN PROGRESS i.
l Technical. Specification Change Request number 49.
Recovery Operations Plan. Change nunter 31.
SDS Technical Evaluation and System Description Update.
Core Stratification Sample Safety Evaluation.
Containment Air Control Envelope Technical Evaluation Report, Revision 5.
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Harold R. Denton 3
March 17, 1986 Frank J. lif raglia NRC/THI-86-025 Solid Maste Facility Technical Evaluation Report.
Reactor Building Sump Criticality Safety Evaluation Report.
THI-2 Temporary Reactor Vessel Filtration System Safety Evaluation Report, Revision 1.
ouKHNAL SiONED BY.
WMiam D. Irovas William D. Travers Director THI-2 Cleanup Project Directorate FFICE)
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