ML20202H543
| ML20202H543 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 07/14/1986 |
| From: | Travers W Office of Nuclear Reactor Regulation |
| To: | Harold Denton, Miraglia F Office of Nuclear Reactor Regulation |
| References | |
| CON-NRC-TMI-86-069, CON-NRC-TMI-86-69 NUDOCS 8607160357 | |
| Download: ML20202H543 (3) | |
Text
so-sw July 14, 1986 NRC/THI-86-069 MEl%)RANDUM FOR:
Harold R. Denton, Director Office of Nuclear Reactor Regulation Frank J. fliraglia, Director Division of PWR Licensing-B FROM:
William D. Travers, Director TilI-2 Cleanup Project Directorate
SUBJECT:
NRC THI-2 CLEANUP PROJECT DIRECTORATE WEEKLY STATUS REPORT FOR JULY 7 - JULY 13,1986
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l 1.
DEFUELING f
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Core boring activities continued. Core positions fi-12 and G-8 were
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drilled and video examinations of the holes were performed. Core samples froa holes at core locations N-5, N-12, and G-8 are 3/
currently stored in fuel canisters in the canister positioning I
system.
I Information obtained from core bore operations to dtte has shown l
that fuel assemblies N-5 and N-12, which are near the core periphery, are largely intact below the rubble bed. Fuel assembly G-8, which is nearer to the core center consists largely of a fused l
mass.
1 No relocated core material was encountered during drilling from the assemblies' lower end fittings to the lower flow distributor, however, relocated core material was seen in adjacent assemblies during video examinations.
Drilling of core position G-12 is in progress.
k 2.
PLANT STATUS i
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 81'F.
The airborne radioactivity on the defueling platform is about 5.0 E-7 uC1/cc Tritium and 4.6 E-11 uCi/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 8607160357 e60714 DR ADOCK 0500 O
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-core-region and 6 feet over the carousel holding the defuelingN canisters, s
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WASTE PWlAGEMENT f
The Submerged.Demineralizer System (SDS) completed proce'ssing batch S-134, which consisted of about 14,000 gallons from the neutralizer tank.
EPICOR II completed processing batch 298, 8,500 gallons from the monitor tanks, and batch 299, 7,000 gallons from the monitor tanks.
j The system began processing batch 300.
Total volsme prJcessed through' SDS to date 'is 4,061,103 gallons, and the total. voldme. processed EPICOR II to date is 3,029,050 gallons.
1 4.
_ ENVIRONMENTAL MONITORING US Environmental Protection Agency (EPA) sample analysis results show that TMI site liquid effluents are in accordance with regulatory limits, NRC requirements, and The-City of Lancaster Agreement.
The Lancaster water sample taken at the water works river intake and analyzed by EPA consisted of a seven day composite sample taken June 22 - 28, 1986. A gamma scan detected no reactor related activity.
THI water samples taken by EPA at the plant discharge (includes Units 1 and 2) to the river consisted of seven dtily composite samples taken from June 22 - 28, 1986. A gamma scan detected no reactor related activity.
The EPA analysis of the NRC outdoor air sample for' the period July 3
- 10, 1986 showed that concentrations of Cs-137' and I-131 were below the -lower limit of quantitative detectabi?ity for the system.
5.
AUXILIARY AND FUEL HANDLING BUILDING ACTIVITIES Assembly of the desludging system continued.
,4 6.
NRC EVALUATIONS IN PROGRESS Technical Specification Change Request-no 3 6e 49, and 51.
J Recovery Operations Plan Change number ai a d 35.
i' Solid Waste Facility Technical Evalnoli n c; aort.
i, Reactor Building Sump Criticality ',af 4f.' < luation Report.
Defueling Canister Technical Evaluation keport, Revision 2.
Extended Core Stratification Sample Acquisition Activity.
Heavy Load Safety Evaluation Report, Revision 3.
Defueling Safety Evaluation Report, _ Revision 10.
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July 14, 1986
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PUBLIC MEETING
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The Advisory Parel ~ for the Decontamination of Three Mile Island Unit 2 will meet on August 13, 1986 from 7:00 PM to 10:00 PM at the Lancaster Council Chambers, Public Safety Building, 201 North Duke Street, Lancaster, PA.- At the meeting the panel will receive a status report on the progress of defueling-from GPU Nuclear and a briefing on the licensee's plans for disposal of the processed water generated from the accident.
i Persons desiring to speak before the Advisory Panel are requested to contact Mr.' Thomas Smithgall at 717-291-1042, or write him at 2122 Harietta Avenue, Lancaster, PA 17603.
OmeMAE mee We i
Wik e D. Desem William D. Travers..
Director TMI-2 Cleanup Project Directorate d
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