ML20128K146
| ML20128K146 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 05/20/1985 |
| From: | Travers W Office of Nuclear Reactor Regulation |
| To: | Harold Denton, Snyder B Office of Nuclear Reactor Regulation |
| References | |
| CON-NRC-TMI-85-037, CON-NRC-TMI-85-37 NUDOCS 8505310095 | |
| Download: ML20128K146 (4) | |
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May 20, 1985 NRC/THI-85-037
' HE110RANDUM 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 THI PROGRAM 0FFICE WEEKLY STATUS REPORT FOR MAY 13, 1985'- MAY 19, 1985 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.
RCS cooling is by natural heat loss to the reactor building ambient atmosphere.
Incore thermocouple readings range from 72*F to 92*F with an average of 81'F. Average cold leg temperature is 58*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 1.3 E-9 uC1/cc tritium, and 5.0 E-10 uC1/cc particulates, predominantly cesium 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.
2.
WASTE MANAGEMEllT' The Submerged Demineralizer System (SDS) completed processing batch h/
S-118, consisting of 12,217 gallons of miscellaneous waste frcm the t
neutralizer tanks.-
No EPICOR.II processing occurred this week.
p-Total volune' processed through SDS to date is 2,875,999 gallons, and
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the total volume processed through EPICOR II is 2,447,788 gallons.
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DOSE REDUCTION /DECONTAf11 NATION ACTIVITIES General cleanup continued in the control and service building.
Decontamination of the auxiliary building elevator shaft continued.
Cleanup is in progress in the 'A' RCBT cubicle.
Decontamination is in progress in the tendon access gallery.
Average general area radiation dose rate on the 347' level of the reactor building is 36 mrem per hour. Average dose rate on the 305' level is 160 mrem per hour.
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4.
ENVIRONMENTAL MONITORING 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 April 28, to May 4, 1985. A gama scan detected no reactor related radioactivity.
Tiil water samples taken by the US Environmental Protection Agency at the plant discharge to the river consisted of seven daily composite samples taken from April 27, to May 1,1985. Gamma scans detected no reactor related radioactivity.
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The NRC outdoor airborne particulate sampler at the TMI Site collected a sample between 11ay 8, and May 16, 1985. No 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 THI site liquid effluents to be in accordance with ryulatory limits, NRC requirements, and the City of Lancaster Agreement.
5.
REACTOR BUILDING ACTIVITIES The plenum assembly was removed from the reactor vessel and transferred to storage in the deep end of the fuel transfer canal on May 15, 1985. The maximum measured dose rate, 31 feet directly below the plenum, was 80 R/hr. Radiation levels in the refueling canal returned to pre-transfer levels once the plenum was stored under 6 feet of water in the deep end of the canal.
Future work in the reactor building will be focused on preparations for the first phase of defueling in September 1985. The near tenn defueling preparations include installation of a 5-ton service crane 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.
Testing of the fuel transfer system and upenders has been completed in the 'A' spent fuel pool.
Boration of the processed water storage tank number 1 is in progress.
The chemistry of this water is being adjusted to provide a source of RCS quality water for flooding of the 'A' spent fuel pcol. The chemical addition will take about one month.
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NRC EVALUATIONS IN PROGRESS I
Defueling WaterLCleanup System Technical Evaluation Technical Specification Change Requests numbers 46 and 48 Equipment Hatch Removal Safety Evaluation g
Recovery Operations Plan Change number 27 Fuel Canister Technical Evaluation Fuel Handling Senior Reactor Operator Training Program 1
Defueling Safety Evaluation a
8.
PROJECTED SCHEDULE OF FUTURE EVENTS m
Start of Defueling: September 1985 9.
PUBLIC NEETING The Advisory Panel for the Decontamination of Three Mile Island Unit 2 met on May 16,198S. At the meeting, which was open to the public, the Panel discussed their position on the level of the Panel's s
3E4 inquiry into health effect studies and data related to the radio-
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active release during the THI-2 accident. The Panel received a 3.
presentation from representatives of General Public Utilities Nuclear Corporation on plans for reactor fuel removal and storage. The Department of Energy briefed the Panel on the current status of fuel shipping casks that will be used for offsite transport of fuel:and n
debris removed from the reactor. The NRC staff provided the Panel with an update on the status of HRC investigations and enforcement actions. The date and location of the next Panel meeting will be announced in the future.
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William D. Travers y?,
Deputy Program DirectorL
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THI Program Office 4
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