ML20199L651
| ML20199L651 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 07/07/1986 |
| From: | Travers W Office of Nuclear Reactor Regulation |
| To: | Harold Denton, Miraglia F Office of Nuclear Reactor Regulation |
| References | |
| CON-NRC-TMI-86-065, CON-NRC-TMI-86-65 NUDOCS 8607090526 | |
| Download: ML20199L651 (3) | |
Text
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4 July 7, 1986 NRC/TMI-86-065 MEMORANDUM FOR:
Harold R. Denton, Director Office of Nuclear Reactor Regulation Frank J. Miraglia. Director Division of PWR Licensing-B FROM:
William D. Travers, Director s
THI-2 Cleanup Project Directorate
SUBJECT:
NRC LEANUP PROJECT DIRECTORATE WEEKLY STATUS REPORT FOR JUNE 30 - JULY 6,1986
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1.
DEFUELING
[:
On July 3,1986 the licensee comenced core boring to acquire core f
stratification samples in position N-5.
The core boring operation was
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successful and an encased stratification sample was removed and placed in a defueling canister on July 5,1986.
It tcak approximately 14 hours1.62037e-4 days <br />0.00389 hours <br />2.314815e-5 weeks <br />5.327e-6 months <br /> to 1
make the boring through the lower end fitting. The boring operation was completed on July 4, 1986. An extended drilling operation was perfonned i
to the lower flow distributor. No relocated core material was encountered during the extended drilling operation. A video inspection was made through the access port left by the drilling operations in 1'"
location N-5.
The TV tapes from these explorations are presently being reviewed and analyzed. The licensee is relocating the drilling rig over core position N-12.
2.
PLANT STATUS The reactor remains in long tenn cold shutdown, vented to the atmosphere. Core cooling is by natural heat loss to ambient building atraosphere. The average incore thermocouple reading is 79*F.
The airborne radioactivity on the defueling platform is about L
3.9 E-7 uCi/cc Tritium and 7 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 arovide about 15 feet of water over the core region and 6 feet over the carousel holding the defueling canisters.
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July 7, 1986 Frank J. Miraglia NRC/THI-86-065 3.
WASTE ftANAGEMENT The Submerged Demineralizer System (SDS) remained shutdown.
EPICOR II completed processing batch 297. The system has peccessed 3,004,846 gallons to date.
4.
ENVIRONMEflTAL HONIT0l(ING US Environmental Protection Agency (EPA) sample analysis results show that THI 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 15 - 21, 1986. A gama scan detected no reactor related activity.
TMI water samples taken by EPA at the plant discharge (incit. des Units 1 and 2) to the river consisted of' seven daily composite samples taken from June 16 - 21, 1986. A gama scan detected no reactor related activity in the samples of June 16 - 18, 1986. The gama scan of June 19 - P.1,1986 detected a small amount of Iodine-131 at the intake and the site discharge, indicating that the activity is probably not TMI related.
The EPA analysis of the NRC outdoor air sample for the period June 26 - July 3, 1986 showed that concentrations of Cs-137 and I-131 were below the lower limit of quantitative detectability for the system.
5.
AUXILIARY. AND FUEL HA'lDLING BUILDING ACTIVITIES Assembly of the desludging system continued.
Hands-on decontamination was conducted in the Westinghouse Valve Room at the 281 ft. elevation of the Fuel Handling Building.
I 6.
NRC EVALUATI0llS 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.
Extended Core Stratification Sample Acquisition Activity, Heavy Load Safety Evaluation Report, Revision 3.
j Defueling Safety Evaluatinn Report, Revision 10.
original signed by l
Curtis Cowgill for:
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Willian D. Travers Director l
TMI-2 Cleanup Project Directorate l
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July 7, 1986 Frank J. Miraglia NRC/Ti1I-86-055 INTERNAL DISTRIBUTION CENTRAL FILE NRC PDR LOCAL PDR ED0 OGC EPA DOE.
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