ML20127E981
| ML20127E981 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 06/17/1985 |
| From: | Travers W Office of Nuclear Reactor Regulation |
| To: | Harold Denton, Snyder B Office of Nuclear Reactor Regulation |
| References | |
| CON-NRC-TMI-85-043, CON-NRC-TMI-85-43 NUDOCS 8506240734 | |
| Download: ML20127E981 (4) | |
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June 17, 1985 NRC/THI-85-043 NEMORANDUM 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 JUNE 10, 1985 - JUNE 16, 1985 t
1.
PLANT STATUS The facility remains in long term cold shutdown with the Reactor Coolant System (RCS) vented to the reactor building atmosphere and the reactor vessel head and plenum assembly removed.
The reactor vessel plenum has been removed from the reactor vessel and placed 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 modified internals indexing fixture is installed on the reactor vessel flange and is flooded to elevation 327 feet 6 inches (151 feet above the top of the 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 thennocouple readings range from 71*F to 92*F with an average of 81*F. Average cold leg temperature is 56*F.
The average reactor building temperature is 58*F.
The reactor building airborne activity is 1.3 E-8 uC1/cc tritium, and 2.0 E-10 uCi/cc particulate, predominantly cesium 137.
2.
WASTE MANAGEMENT Submerged Demineralizer System (SDS) processed batch S-121 f
(4,223 gallons) and EPICOR II processed batch 255 (11,046 gallons).
ffg Total volume processed through SDS to date is 2,880,428 gallons, and yh the total volume processed through EPICOR II is 2,458,834 gallons.
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3.
DOSE REDUCTION / DECONTAMINATION ACTIVITIES
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A water flush of the contaminated valve alley on the 281' elevation 1
of the Fuel Handling Building was performed.
Average general area radiation dose rate is 36 mrem per hour on the F
347' level of the reactor building and is 160 mrem per hour on the
-f 305' level of the reactor building.
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4.
ENVIRONMENTAL HONITORING 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 May 2b. to June 1, 1985. A gama scan detected no reactor related radioactivity.
TMI water samples taken by the US Environmental Protection Agency at the plant discharge to the river consisted of seven daily composite samples taken from May 25, to June 1, 1985. Gama scans detected no reactor related radioactivity.
l The NRC outdoor airborne particulate sampler at the Tit! Site collected a sample between June 5, and June 13, 1985. No reactor related radioactivity was detected. Analysis showed I-131 and t
Cs-137 concentrations to be less than the lower limits of
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detectability.
The above EPA sample analysis results show TMI site liquid effluents to be in accordance with regulatory limits, NRC requirements, and f
the City of Lancaster Agreement.
5.
REACTOR BUILDING ACTIVITIES Future work in the reactor building riill be focused on preparations for the first phase of defueling in Sep1. ember 1985. The near term defueling preparations include installation of a 5-ton service crane over the refueling canal, completion of the Defueling Water Cleanup System and modifications to the auxiliary fuel handling bridge.
6.
AUXILIARY AND FUEL HANDLING BUILDING ACTIVITIES Installation of the Defueling Water Cleanup System (DWCS) continued.
Boration of the processed water storage tank Number 1 is in progress. The chemical addition will be completed in June.
A 7.
NRC EVALUATIONS IN PROGRESS 1
Defueling Water Cleanup System Technical Evaluation Technical Specification Change Requests numbers 46 and 48 Equipment Hatch Removal Safety Evaluation Recovery Operations Plan Change numbers 27 and 29 Fuel Canister Technical Evaluation Fuel Handling Senior Reactor Operator Training Program Defueling Safety Evaluation
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PROJECTED SCHEDULE OF FUTURE EVENTS 4
f, Start of Defueling: September 1985 9.
PUBLIC HEETING
' s-The Advisory Panel for the Decontamination of Three Mile Island Unit 2 will meet with the NRC Comissioners on June 20,1985, at 11:00 AM, in Washington, D.C.
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