ML20210S280
| ML20210S280 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 05/12/1986 |
| From: | Travers W Office of Nuclear Reactor Regulation |
| To: | Harold Denton, Miraglia F Office of Nuclear Reactor Regulation |
| References | |
| CON-NRC-TMI-86-048, CON-NRC-TMI-86-48 NUDOCS 8605200490 | |
| Download: ML20210S280 (4) | |
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May 12, 1985 HRC/Ti1I-86-048 MEPORANDU;1 FOR:
Harold R. Denton, Director Office of Nuclear Reactor Regulation Frank J. tif raglia, Director Division of PWR Licensing-B FROM:
William D. Travers, Director Ti11-2 Cleanup Project Directorate SU3 JECT:
NRC Tl11-2 CLEANUP PROJECT DIRECTORATE WEEKLY STATUS REPORT FOR MAY 5 - 11, 1986 1.
DEFUELING No core defueling occurred during this week. The number of canisters transferred to the fuel pool remains at 42.
Efforts to remove the biological contamination from the Reactor Coolant System (RCS) continued. Two batches of borated water treated with hydrogen peroxide were added to the RCS via the Standby Pressure Control System. The licensee established an initial 200 ppm residual concentration of peroxide as a biocide to kil! the micro-organisms. Operation of the high pressure pump and hydrolance, and the Temporary Reactor Vessel Water Filtration System continued in parallel with the hydrogen peroxide addition.
Approximately 50% of the reactor vessel annular area has been hydrolanced and scrubbed. The RCS water turbidity was 37 NTU as of May 11, 1986. The next step in the treatment program will include the drawing of about 15,000 gallons of water from the RCS to the bleed tanks and replenishment with clean RCS grade water. About four batches will be let down in this manner with the drained water being processed through the Submerged Demineralizer System (SDS) and EPICOR.
2.
PLANT STATUS The reactor remains in long term cold shutdown, vented to atmosphere. Core cooling is by natural heat loss to ambient building atnosphere. The average incore thermocouple reading is 101*F. The increase is attributed to the heat generated by pressurizing RCS water with the Elliot pump. Water visibility is nearly 2 feet.
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Harold R. Denton 2
itay 12, 1986 Frank J. Miraglia NRC/TMI-86-048 The airborne radioactivity on the defueling platform is about.7.0 E-7 uCi/cc Tritium and 1.9 E-11 uCi/cc particulates, predoninately Cesium-137. The platform is mounted above the modified internals indexing fixture which is mounted on the reactor vessel flange.
These provide water coverage of 151 feet over the core region. This water level is about 5 feet over the top of any debris canisters in the reactor vessel.
3.
UtsSTE MANAGEMENT Tha SDS total processed to date is 3,937,698 gallons.
EPICCR II is shutdown. EPICOR II total processed to date is 2,891,476 gallons.
4.
ENVIRONMENTAL MONIT0i<ING 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.
TiiI water samples taken by EPA at the plant discharge (includes THI-1 and THI-2) to the river consisted of seven daily composite samples taken from April 20 - 26, 1986. A gama scan detected no reactor related activity above the lower limit detectability.
The Lancaster water sample taken at the water works intake and analyzed by EPA consisted of a seven day composited sample taken from April 20 - 26, 1986. A gama scan detected no reactor related radioactivity.
The NRC cutdoor airborne particulate sampler at the TMI site collected a sample between May 1 - 8, 1986. No reactor related radioactivity was detected. Analysis showed Iodine-131 and Cesium-137 concentrations to be less than the lower liaits of detectability.
5.
AUXILIARY AND FUEL HANDLING BUILDING ACTIVITIES Scabbling of floor areas on the 281' elevation continued.
Vacuum cleaning of the 281' elevation continued.
6.
PUBLIC MEETING The Advisory Panel on the Decontamination of THI-2 will maet with the NRC Commissioners on June 11, 1986 at 11:00 AM. The meeting will be held at the NRC conference room at 1717 H Street, fl.W., Washington, DC.
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i Harold R. Denton 4
fiay 12, 1986 Frank J. !!iraglia flRC/Tf11-85-048 l
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IflTERflAL DISTRIBUTI0ft s
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OGC Office Directors Comissioner's Technical Assistants NRR Division Directors idRR A/D's
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Harold R. Denton 3
flay 12,1986 Frank J.111raglia NRC/TMI-86-048 7.
flRC EVALUATIONS IN PROGRESS Technical Specification Change Request number 49, and 51.
Recovery Operations Plan Change nuraber 31, 33, 35, and 36.
Core Stratification Safety Evaluation (Revision 3).
Solid Uaste Facility Technical Evaluation Report.
Reactor Building Sump Criticality Safety Evaluation Report.
Canister !1andling and Preparation for Shipment Safety Evaluation Report.
Defueling Canister Technical Evaluation Report, Revision 2.
This past week the NRC approved GPUN's safety evaluation reports for Core Stratification Sample Acquisition (Revision 1) and ffodification to Penetration 536.
original signed by Curt Cowgill for:
Willian D. Travers Director TMI-2 Cleanup Project Directorate SURNNW k
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