ML20128P931
| ML20128P931 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 05/24/1985 |
| From: | Travers W Office of Nuclear Reactor Regulation |
| To: | Harold Denton, Snyder B Office of Nuclear Reactor Regulation |
| References | |
| CON-NRC-TMI-85-038, CON-NRC-TMI-85-38 NUDOCS 8506040009 | |
| Download: ML20128P931 (4) | |
Text
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iay 24, 198S NRC/THI-85-038 MEMORANDUM FOR:
Harold R. Denton, Director Office of Nuclear Reactor Regulation Bernard J. Snyder, Program Director TMI Program Office FROM:
William D. Travers Deputy Program Director TMI Program Office
SUBJECT:
NRC Till PROGRAM 0FFICE WEEKLY STATUS REPORT FOR MAY 20, 1985 - MAY 24, 198S 1.
PLANT STATUS The facility remains in long tern cold shutdown with the Reactor Coolant Systen (RCS) vented to the reactor butiding atmosphere and the reactor vessel head and plenual assembly removed.
RCS cooling is by natural heat loss to the reactor building ambient atmosphere.
Incore thermocouple readings range frcm 72*F to 92'F with an average of 81*F. Average cold leg temperature is 59 F.
Calculated reactor decay heat is less than 14 kilowatts.
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).
The average reactor building temperature is 60 F.
The reactor building airborne activity is 4.7 E-8 uCi/cc tritium, and 6.1 E-10 uC1/cc particulate, predominantly costum 137.
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).
2.
WASTE MANAGEMENT No EPICOR II or Submerged Demineralizer System (SDS) processing occurred this week.
Total volume processed through SDS to date is 2,875,999 gallons, and lyh[
the total volume processed through EPICOR II is 2,447,788 gallons, g-
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3.
DOSE REDUCTION /DECONTAMINATI0ll ACTIVITIES General cleanup continued in the control and service building basement.
Shielding of the auxiliary building elevator shaf t was completed.
Cleanup is in progress in the 'A' RCBT cubicle.
Decontamination is in progress in the tendon access gallery.
Average general area radiation dose rate is 36 mrem per hour on the 347' level of the reactor building and is 160 mrem per hour on the 305' level of the reactor building.
c 4.
ENVIR0flMENTAL 110NITORING 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 Hay 5, to !!ay 11,1985. A gamma scan detected no reactor related radioactivity.
THI water samples taken by the US Environmental Protection Agency at
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the plant discharge to the river consisted of seven daily composite samples taken from Hay 4, to Hay 11, 1985. Gamma scans detected no 4
. reactor related radioactivity.
The fiRC outdoor airborne particulate sampler at the THI Site collected a sample between May 16, and May 23, 1985. fio reactor related radioactivity was detected. Analysis showed I-131 and Cs-137 concentrations to be less than the lower limits of detectability.
The above EPA sample analysis results show Till site liquid effluents to be in accordance with regulatory limits. NRC requirements, and the City of Lancaster Agreement.
5.
REACTOR BUILDING ACTIVITIES Future work in the reactor building will be focused on preparations for the first phase of defueling in Septec5er 1985. The near term defueling preparations include installation of a 5-ton service crane r
over the refueling canal and completion of the Defueling Water Cleanup System.
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 take about one month.
7.
IIRC EVALUATIONS IN PROGRESS Defueling Water Cleanup System Technical Evaluation
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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 nan.mg %ty Ey31mtf en
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