ML20207H024
| ML20207H024 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 07/21/1986 |
| From: | Travers W Office of Nuclear Reactor Regulation |
| To: | Harold Denton, Miraglia F Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8607240011 | |
| Download: ML20207H024 (4) | |
Text
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.m July 21, 1986 NRC/TMI-86-071 MEMORANDUM FOR:
liarold R. Denton, Director Office of Nuclear Reactor Regulation Frank J. Miraglia, Director Division of PWR Licensing-B FROM:
William D. Travers, Director THI-2 Cleanup Project Directorate h EC M LEANUP PROJECT DIRECTORATE WEEKLY ST
SUBJECT:
REPORT FOR JULY 14 - JULY 20, 1986 1.
DEFUELING l
l During the report period, the licensee continued core boring to acquire core stratification samples in positions G-12, K-9, D-8, and K-6.
Encased stratification samples were removed and placed in defueling canisters for eventual shipment to Idaho National Energy Laboratories. An extended drilling operation was performad in the i
K-9 position on July 16, 1986 to characterize core debris found on the lower reactor vessel head.
Video inspections were made through the access ports left by the drilling operations. The video tapes l
l from these examinations are presently being reviewed and analyzed.
The licensee is re-indexing the drilling rig over core position D-4.
l 2.
SHIPMENT The first fuel shipping cask left the site by train during this report period. Prior to release, the NRC site staff verified that the shipment was in compliance with NRC and 00T radiological requirements.
3.
PLANT STATUS The reactor remains in long tem 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 uCi/cc Tritium and 2.9 E-11 uCi/cc particulates, predominately Cesium-137 and Strontium-90. The platfom 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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8607240011 860721 PDR ADOCK 05000320 H
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Harold R. Denton' 2
July 21, 1986 FrankJ.Miraglia)
NRC/Till-86-071 4.
WASTE MANAGEMENT The Submerged Demineralizer System (SDS) began processing batch S-135 from the neutralizer tank.
EPICOR II completed processing batch 300, 10,668 gallons from the monitor tanks, and batch 301, 1,296 gallons from the Chemical Cleaning Building sump. The system began processing batch 302.
Total volume processed through SDS to date is 4,084,8F6 gallons, and the total volume processed EPICOR II to date is 3,031,926 gallons.
5.
ENVIR0f01 ENTAL MONITORING US Environmental Protection Agency (EPA) sample analysis results show that TMI site liquid effluents are in accordance with regulatory limits, HRC 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 29 - July 5, 1986. A gamma scan detected no activity that could be attributed to THI-2.
TMI water samples taken by EPA at the plant discharge (includes Units 1 and 2) to the river consisted of seven daily composite samples taken from June 28 - July 7,1986. A gacuna scan detected no activity that could be attributed to TMI-2.
The EPA analysis of the NRC outdoor air sample for the period July 10 - 16, 1986 showed that concentrations of Cs-137 and I-131 were below the lower limit of quantitative detectability for the system.
6.
AUXILIARY AND FUEL HANDLING BUILDING ACTIVITIES Assembly of the desludging system continued.
7.
NRC EVALUATIONS IN PROGRESS Technical Specification Change Request number 49, and 51.
Recovery Operations Plan Change number 31 and 36.
Solid Waste Facility Technical Evaluation Report.
Reactor Building Sump Criticality Safety Evaluation Report.
Defueling Canister Technical Evaluation Report, Revision 2.
Heavy Load Safety Evaluation Report, Revision 3.
Defueling Safety Evaluation Report, Revision 10.
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Harold R. Denton 3
July 21, 1986 Frank J. Miraglia NRC/THI-86-071 f
7.
PUBLIC MEETING The Advisory Panel 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 Chambet s,- 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 Huclear and a briefing on the licensee's plans for disposal of the processed water generated from the j,
accident.
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Persons desiring to speak before the Advisory Panel are requested to i
contact Mr. Thomas Smithgall at 717-291-1042, or write him at 2122 Harietta Avenue, Lancaster, PA 17603.
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ORIGINAL SIGle BVe W IBio m D. Y m vers i
I llilliam D. Travers Director
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Harold R. Denton 4
' July 21, 1986 Frank J. Miraglia NRC/THI-86-071 U
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