ML20203H635
| ML20203H635 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 07/28/1986 |
| From: | Travers W Office of Nuclear Reactor Regulation |
| To: | Harold Denton, Miraglia F Office of Nuclear Reactor Regulation |
| References | |
| CON-NRC-TMI-86-076, CON-NRC-TMI-86-76 NUDOCS 8608050046 | |
| Download: ML20203H635 (4) | |
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July 23, 1986 NRC/THI-86-076 MEMORANDUtl FOR:
Harold 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
SUBJECT:
NRC THI-2 CLEANUP PROJECT DIRECTORATE WEEKLY STATUS REPORT FOR JULY 21 - JULY 27, 1936 1.
DEFUELING j
l The licensee continued core boring to acquire core stratification I
samples in positions D-4, 0-7, and 0-9.
Encased stratification samples were removed and placed in defuelir.g canisters for eventual l
shipment to Idaho National Engineering Laboratories. Video inspections were made through the access ports left by the drilling operations. The licensee has concluded core stratification sampling. A total of 10 sampling penetrations have been made.
Preparations are being made to systematically drill the core using a l
solid face bit. Such drilling is designed to facilitate bulk defueling by aiding in size reduction of fused core debris.
1 2.
SilIPMENT The first fuel shipping cask arrived at Idaho National Engineering Labora tory. There was a brief delay in route prior to entering the I
State of Nebraska in response to concerns by that State's governmental officials. Upon resolution to the concerns, the balance of the trip was uneventful.
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 6.2 E-7 uC1/cc Tritium and 1.6 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 l
core region and 6 feet over the carousel holding the defueling canisters.
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Harold R. Denton 2
July 28, 1986 Frank J. Hiraglia NRC/THI-86-076 4.
WASTE MANAGEMENT The Submerged Demineralizer System (SDS) completed processing batch S-135, 19,603 gallons from the neutralizer tank.
EPICOR II completed processing batch 302, 1,580 gallons from UDL-T-118 and batch 303, 23,312 gallons from CC-T-1.
Total volume processed through SDS to date is 4,084,856 gallons, and F
the total volume processed EPICOR II to date is 3,055,238 gallons.
5.
ENVIRONt1 ENTAL HONITORING 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 July 6 - 12, 1986. A gama scan detected no activity that could be attributed to THI-2.
THI 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 July 5 - 12, 1986. A gamma scan detected no activity that could be attributed to THI-2.
The EPA analysis of the NRC outdoor air sample for the period July 16 - 24, 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.
i Reactor Building Sump Criticality Safety Evaluation Report.
Defueling Canister Technical Evaluation Report, Revision 2.
Heavy Load Safety Evaluation Report, Revision 3.
e On July 24, 1986 the NRC staff approved a portion of the defueling activities described in GPUN's Defueling Safety Evaluation Report, Revision 10. This includes bulk defueling activities above the grid support structure and the use of solid face bit drilling operations in non-instrumented core locations using the core drilling rig. The remainder of the above Safety Evaluation Report is still under review.
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Harold R. Denton 3
July 28, 1986 Frank J. Miraalia HRC/TMI-86-076 f
8.
PUBLIC 11EETIllG The Advisory Panel-for the Decontamination of Three Mile Island Unit 2 will meet on August 13,1986 from'7:00 Pit 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.
Persons desiring to speak before the Advisory Panel are requested to contact Mr. Thomas Smithgall at 717-291-1042, or write him at 2122 Marietta Avenue, Lancaster, PA 17603.
ORIGINAL SQED %
William Ll. fr.: vast William D. Travers Director TMI-2 Cleanup Project Directorate ov nce >
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July 28, 1986 Frank J. F11raglia NRC/TMI-86-076
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