ML20205S752
| ML20205S752 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 06/09/1986 |
| From: | Travers W Office of Nuclear Reactor Regulation |
| To: | Harold Denton, Miraglia F Office of Nuclear Reactor Regulation |
| References | |
| CON-NRC-TMI-86-056, CON-NRC-TMI-86-56 NUDOCS 8606120827 | |
| Download: ML20205S752 (4) | |
Text
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June 9, 1936 NRC/TMI-86-056 HENORANDUM FOR:
Harold R. Denton, Director Office of Nuclear Reactor Regulation b
Frank J. litraglia, Director Division of PWR Licensing-B FROM:
William D. Travers, Director TMI-2 Cleanup Project Directorate
SUBJECT:
NRC TMi-2 CLEANUP PROJECT DIRECTORATE WEEKLY STATUS
~ REPORI rdh JUNE 2 - JUNE 8,1986 1.
DEFUELING Core stratification sampic acquisition (core boring) training is complete. The drilling,ig -fil be disassembled this week then reassembled in the reactor building. Core boring is expected to start during the week of June 23, 1986.
Pick and place defueling activities continued. These activities were conducted principally to assure that the core bore drilling locations were ready to commence drilling. The number of canisters transferred to the fuel pool remains at 42.
f The testing of the heavy duty spade bucket tool was inconclusive due to bending of the vertical jaw.
The Reactor Coolant System (RCS) turbidity was approximately 2 NTU 4
(6 - 8 feet) as of Honday, June 2, 1986.
2.
PLANT STATUS The reactor remains in long term cold shutdown, vented to the atmosphere. Core cooling is by natural heat loss to ambient building atmosphere. The average incore thermocouple reading is 80*F; reactor vessel water temperature as raeasured by resistance temperature detectors (RTD's) is 73*F.
't The airborne radioactivity on the defueling platform is about f
3 E-7 uC1/cc Tritium and 5 E-11 uC1/cc particulates, predominately Cesium-137 and Strontium-90. The platform is mounted above the modified internals indexing fixture which is mounted over the reactor vessel. These provide about 15 feet' of water over the core region and 6 feet over the carousel holding the defueling canisters.
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2 June 9, 1985 Frank J.1;tiraglja'
'WC/TMI-86-056 3.
WASTE MANAGEliEf(T EPICOR II remains shutdown. The Submerged Demineralizer System (SDS) started processing the "B" reactor coolant bleed tank on Saturday, June 7, 1986.
4.
EllVIRONiiEflTAL MollITORIllG DJ Environmental Protection Agency (EPA) sample analysis results show that Tl11 site li@id effluents are in accordance with regulatory limits, NRC requirements, and The City of Lancaster Agreement.
The Lancaster water smple taken at the water works river intake and -
analyzed by EPA consisted of a seven day composite sample taken May 18 - 24, 1986. A gamma scan detected no reactcr related activity.
THI water sacples ta'en by EPA at the-plant discharge (includes K
Units 1 and 2) to the river consisted of seven daily composite samples taken from May 18 - 24, 1985. A ganma scan detected a trace amount of Iodine-131 in the May 21 - 22, 1986 sample. While no reactor activity was measured, trace amounts of I-131 were detected in water at both the Unit 1 intake and the site discharge, indicating that the activity is probably not Till related.
The EPA analysis of the NRC outdoor air saaple for the period May 26
- June 6,1986 showed that concentrations of' Cs-137 and I-131 were below the lower limit of quantitative detectability for the system, i.e., less than 1.1 E-13 microcuries/cc. A trace of I-131 was detected in the sample.
The unquantifiably small traces of I-131 in both these samples are probably related to the Chernobyl accident.
E,.
AUXILIARY AND FUEL HANDLIflG BUILDING ACTIVITIES Water flushing continued in the Westinghouse Valve Room (281' Auxiliary Building) over the past week. This room abuts the annulus and is the location of the mini-decay heat cooling system.
Assembly of the Desludging system continued.
The testir j program continues on the transfer shield.
6.
NRC EVALUATIONS IN PROGRESS Technical Specification Change Request number 49, and 51.
Recovery Operations Plan Change number 31, 33, 35, and 3C.
Solid Haste Facility Technical Evaluation Report.
su" DATE) unc ronv ais noso> wncu o2" OFFICIAL RECORD COPY
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lbrold R, Denton 3
June 9, 1986 Frank J. Hiraglia flRC/Ti11-86-056 Reactor Bui3 ding Sump Criticality Safety Evaluation Report.
Cani::ter flandling and Preparation for Shipment Safety Evaluation Report Defueling Canister Technical Evaluation Report, Revision 2.
On dur.c 2,1986, GPtjil submitted a request to test three defueling tools over en approximate 2 week period. The tools were a heavy duty tong tool, heavy duty spade bucket, and hydraulic impact chisel. The use of this equipment was previously under flRC staff revirw as part of the fiay 15, 1986 defueling SER.
The staf f approved the use of the three tools on June 4, 1936.
7.
PijBLIC HEETif?G The !kivisory Panel for the Decontamination of THI-2 will meet with the flRC Conrnissioners on June 11. 1936 at 11:00 Afl. The necting will be held at the NRC conference room at 1717 I! Street,it.ll., Washington, DC.
I o moe ML SIONED BYa William D. %
William D. Travers Director T!!I-2 Cleanup Project Directorata l
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W Harold R. Denton 4
June 9, 1986 Frank J. Miraglia NRC/Tl11-86-056 IflTERilAL DISTRIBUTI0fi
'CEllTRAL FILE IIRC PDR LOCAL PDR EDO CGC Office Directors Cocnissioner's Technical Assistants flRR Division Directors flRR A/D's Regional f.dministrators IE Division Directors TAS EIS PHS EPA DOE RI Division Directors Public Affairs, RI State Liaison, RI THI HQ r/f Till SITE r/f THI-2 Project Section File T!!I Cleanup Project Directorate (10)
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