ML20135G706
| ML20135G706 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 09/16/1985 |
| From: | Travers W Office of Nuclear Reactor Regulation |
| To: | Harold Denton, Snyder B Office of Nuclear Reactor Regulation |
| References | |
| CON-NRC-TMI-85-072, CON-NRC-TMI-85-72 NUDOCS 8509230015 | |
| Download: ML20135G706 (5) | |
Text
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September 16, 1985 NRC/TM1-85-072 NEHORANDUit FOR:
Harold R. Denton, Director Office of Nuclear Reactor Regulation Bernard J. Snyder, Program Director THI Program Office FROM:
William D. Travers, Deputy Program Director TMI Program Office
SUBJECT:
NRC TMI PROGRAM 0FFICE WEEKLY STATUS REPORT FOR SEPTEMBER 9, 1985 - SEPTEMBER 15, 1985 1.
PLINT STATUS The facility remains in long term cold shutdown with the Reactor Coolant System (RCS) vented to the reactor building atmosphere and the reactnr vessel head and plenum assembly removed from the reactor vessel.
The plenum is on its storage stand in the deep end of the fuel transfer canal. A dam has been installed between the deep and shallow ends of the fuel transfer canal. The deep end is filled with water to a depth of about 20 feet (about 5 feet above the top of the plenum).
The codified internals indexing fixture is installed on the reactor vessel flange and is flooded to elevation 327 feet 6 inches (15i feet above the top of th* core region).
Calculated reactor decay heat is less than 12 kilowatts.
RCS cooling is by natural heat loss to the reactor building ambient atmosphere.
Incore thermocouple readings range from 70 F to 91"F with an average of 79"F.
Average cold leg tecoerature is 54"F.
The average reactor building temperature is 58*F.
The reactor building airborne activity is 1.0 E-8 uC1/cc Tritium and 2.8 E-10 uC1/cc particulate, predominantly Cesium 137.
2.
WASTE MANAGEMENT The Submerged Demineralizer System (SDS) was shutdown during this period.
EPICOR II completed processing batch 265, which was about 59,000 gallons from Condensate Tank 1A (C0T-1A).
Total volume processed through SDS to date is 2,963,375 gallons, and
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,J the total volurce processed through EPICOR If is 2,605,982 gallons.
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3.
DOSE REDUCTION /DECONTN11hATIO!! ACTIVITIES Decontamination activities are continuing on the 281' level of the auxiliary building.
The licensee recently released about 2,000 square feet of the auxiliary building from contamination control and has exceeded the 1985 decontamination goal of 10,009 square feet in the auxiliary building.
Average general area radiation dose rate is 40 mrem per hour un the 347' level of the reactor building and is 67 mrem per hour on the 305' level of the reactor building.
4.
ENVIR0hMENTAL MONITORING EPA saaple analysis results show TMI site liquid effluents to be in accordance with regulatory limits, liRC requirements, and the City of Lancaster Agreement.
Till water samples taken by the US Environmental Protection Agency at the mt discharge to the river consisted of seven daily composite samples taken from August 24 to August 31, 1935. One 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> composite sanple taken between August 29 and 30,1985 detected 3 E-9 uC1/cc of Iodine-131.
Essentially the same concentration of Iodine-131 was detected by an upstream sampler. This indicates that the Iodine-131 was taken into the plant from the river and the plant was not the scurce. No reactor related activity was detected. The detected concentration of Iodine-131 was 1% of the HP,C allowable limit for release to unrestricted areas.
The Lancaster water sample taken at the water works intake and analyzed by the US Environmental Protection Agency consisted of a seven day composite sample taken from August 25 to August 31, 1985.
A gama scan detected no reactor related radioactivity.
The NRC outdoor airborne particulate sampler at the T!il Site collected a sample between September 4 and Septeuber 11, 1985. No reactor related radioactivity was detected. Analysis showed 1-131 and Cs-137 concentrations to be less than the lower limits of detectability.
5.
REACTOR BUILDIflG ACTIVITIES Work continued on installation of the defueling tool racks.
Defueling Water Cleanup System (DUCS) preoperational testing and modification continued.
Installation of cable tray shielding continued.
Preoperational testing of the reactor building sump recirculation system conponents is in progress. Two of the three pumps failed the preoperational test and the pump vendor has been called to assist in troubleshooting.
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Septe:.:ber 16, 1935 Bernard J. Snyder tiRC/THI-85-072 6.
AUXILIARY AND FUEL HAftDLING BUILDIf;G ACTIVITIES Installation of the DWCS continued. Partial DWCS turnover for processing RCS during early defueling is expected to be completed in late September.
All four of the fuel canister storage racks have been delivered to the THI site.
Insp::ctions by GPU personnel identified cracks in several structural welds in the first two of the racks where the racks had engaged the shipping dunnage. Liquid penetrant examination of sinflar welds in the third fuel canister rack did not identify any crack indications. The fourth fuel rack is currently being inspected. Further inspections and repair of the racks is in progress at the site. A completion date has not been established.
7.
NRC EVALUATIONS IN PROGRESS Technical Specification Change Requests numbers 48, 49, and 50.
Recovery Operations Plan Change numbers 29, 31, and 32.
Fuel Canister Technical Evaluation, Revision 1.
Defueling Safety Evaluation.
Application for seismic exerption.
SDS Technical Evaluation and System Description Update.
Core Stratification Sample Safety Evaluation.
Heavy Load Handling Safety Evaluation Report.
8.
PUBLIC MEETING On the evening of Septenber 11, 1985, the Advisory Panel for the Decontamination of Three Mile Island Unit 2 held a public meeting at the House of Delegates Office 3uilding in Annapolis, Maryland. At this meeting, the Panel received a status report on the defueling progran by Mr. Frank Standerfer, Vice President / Director, GPU Uuclear Corporation.
ifr. Standerfer also provided an update on the cleanup funding situation.
Mr. Frank Miraglia, Deputy Director, Division of Licensing, i:RR, and Dr.
Bernard J. Snyder, Director, TMIP0:f4RR, described the IRC plan for the reorganization of the Office of Nuclear Reactor Regulation (URR) and discussed the resulting changes in the THI Program Office.
Dr. Willis Bixby, nanager, DOE TMI site office, provided an overview of DOE's role in the cleanup.
Dr. Willian Kirk, Director, THI Field Station EPA, provided a summary of environmental monitoring in the vicinity of TMI.
Dr. Tom Magette, Director of the Maryland Power Plant Siting Program, discussed environmental nonitoring of the Susquehanna River conducted by his office.
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September 16, 1985 Berpard J. Snyder fiRC/T111-85-072 Hr. Jack Devine, GPUtic, presented information on the status of processed water generated during the cleanup and provided the licensce's schedule for determining the ultimate disposition of the water.
The next meeting of the Advisory Panel is scheduled for October 1985 in Harrisburg, Pennsylvania. Exact date and location for this aceting will be anncunced at a later date.
-fe Willian D. Travers Deputy Program Director THI Progran Office
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