ML20155K247
| ML20155K247 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 05/19/1986 |
| From: | Travers W Office of Nuclear Reactor Regulation |
| To: | Harold Denton, Miraglia F Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8605270422 | |
| Download: ML20155K247 (4) | |
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May 19, 1986 HRC/Till-86-050 ItEl:0RANDUM FOR:
Harold R. Denton, Director Office of Nuclear Reactor Regulation Frank J. fliraglia, Director Division of PHR Licensing-B FR0ft:
William D. Travers, Director THI-2 Cleanup Project Directorate
SUBJECT:
NRC TMI-2 CLEANUP PROJECT DIRECTORATE WEEKLY STATUS REPORT FOR MAY 12 - 18, 1986 1.
DEFUELING No core defueling occurred during this week. The number of canisters transferred to the fuel pool remains at 42.
Biccide addition to the RCS and hydrolancing of the reactor vessel components has been completed. Letdown and refill of the RCS is in progress.
Four batches will be letdown in which about 15,000 gallons of water will be drained and then replaced with clean borated water treated with hydrogen peroxide. Draining of 15,000 gallons of water will leave the RCS level at about elevation 310'8" which is 26 ft. above the top of the vessel flange.
On may 12, 1986 during operations supporting rotation of the rotating work platform the trolley on the number one jib crane disengaged and fell into the reactor vessel. An operator was struck by a portion of the falling apparatus and received a scalp laceration. Approximately one half of the trolley was recovered from the vessel and examined to determine the failure mechanism.
The trolley on the number one jib crane has been replaced with another of a different design. The number two jib crane which still has the original design trolley has been inspected. No deficiencies were observed.
It remains out of service pending completion of licensee investigation, review, and modification.
2.
PLANT STATUS The reactor remains in long tem cold shutdown, vented to atmosphere. Core cooling is by natural heat loss to ambient building atmosphere. The average incore thermocouple reading is 99'F.
Water visibility is approximately one foot.
The airborne radioactivity on the defueling platfom is about 7.0 E-7 uC1/cc Tritium and 2.6 E-12 uti/cc particulates, predominately Cesium-137. The platform is mounted above the modified internals 8605270422 860519 ome=>
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Harold.R.'Denton 2
May 19, 1986 Frank J.111raglia NRC/Tl11-86-050 indexing fixture which is mounted on the reactor vessel flange.
These provide water coverage of 151 feet over the core region.
3.
WASTE 11ANAGEMENT The Submerged Demineralizer System (SDS) has processed 71,238 gallons of batch S-131 from "B" Reactor Coolant Bleed Tank. The SDS total to Jate is 3,954,097 gallons.
EPICOR II bas processed batch 287; 10,710 gallons from the SDS monitor tanks.
EPICOR II has processed 2,925,820 gallons to date.
4.
ENVIRONMENTAL MONITORING US Envircnmental Protection Agency (EPA) sample analysis results show tha. THI site liquid effluents are in accordance with regulatory limits, NRC requirements, and the City of Lancaster Agreement.
Till water samples taken by EPA at the plant discharge (includes TilI-1 and TMI-2) to the river consisted of seven daily composite samples taken from April 26 - May 3, 1985. 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 26 - May 3, 1986. A gamma scan detected no reactor related radioactivity.
The NRC outdoor airborne particulate sampler at the THI site collected a sample between May 8 - 15, 1986. The results were not available and will be reported in next weeks status report.
5.
AUXILIARY AND FUEL HANDLING BUILDING ACTIVITIES A robot entry was made into the highly contaminated Seal Injectio'n i
Valve Room on the 281' elevation of the Auxiliary Building. Gamma dose rates up to 300 R/hr at hot spots and general area _ dose rates ranging from 30 - 75 R/hr were observed. All operations were remotely controlled from outside the room. The beta component has not yet been determined.
6.
PUBLIC MEETING The Advhory Panel on the Decontamination of THI-2 will meet with the NRC Cocnissioers on June 11, 1986 at 11:00 AM. The meeting will.be held at the NRC coference room at 1717 H Street, N.W., liashington, DC.
7 NRC EVALUAY, IONS _I" PP0GRESS Technical Specification Change Request' number 49, and 51.
Recovery Operations Plan Change number 31, 33, 35, and 36.
Core Stratification Safety Evaluation (Revision 3).
Solid liaste Facility Technical Evaluation Report.
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Harold R. Denton 3
May 19, 1986 Frank J. Miraglia flRC/TMI-85-050 Reactor Building Sump Criticality Safety Evaluation Report.
Canister Handling and Preparation for Shipment Safety Evaluation Report.
Defueling Canister Technical Evaluation Report, Revision 2.
ORIGitML S;cNED BY:
yelliam D. Travers William D. Travers Directer TMI-2 Cleanup Project Directorate
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