ML20134L206
| ML20134L206 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 08/26/1985 |
| From: | Travers W Office of Nuclear Reactor Regulation |
| To: | Harold Denton, Snyder B Office of Nuclear Reactor Regulation |
| References | |
| CON-NRC-TMI-85-065, CON-NRC-TMI-85-65 NUDOCS 8509030127 | |
| Download: ML20134L206 (4) | |
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August 26, 1985 NRC/Till-85-065 HEMORAHOUM 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 4:
THI Program Office
SUBJECT:
NRC TMI PROGRAM 0FFICE WEEKLY STATUS REPORT FOR AUGUST 19, 1985 - AUGUST 25, 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 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 tc a depth of about 20 feet (about 5 feet above the top
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of the plenum).
The modified internals indexing fixture is installed on the reactor i
l 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.
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RCS cooling is by natural heat loss to the reactor building ambient j
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atmosphere.
Incore therr.ioccuple readings range from 70*F to 92*F with an average of 80*F. Average cold leg temperature is 54*F.
The average reactor building temperature is 60*F. The reactor building airborne activity is 2.8 E-7 uCi/cc Tritium and 1.6 E-9
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uCi/cc particulate, predominantly Cesium 137.
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WASTE liANAGEMENT l
The Submerged Domineralizer System (SDS) and EPICOR II were shutdown s
this period.
Total volume processed through SDS to date is 2,963,375 gallons, and
[1 the total volume processed through EPICOR II is 2,547,671 gallons.
Preparations are being made to transfer the contents of condensate
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tank 1A (C0T-1A) to EPICOR II. The tank will be desludged and used as a storage tank for borated makeup water.
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August 26, 1985 Bernar NRC/THI-85-065 s
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3.
DOSE REDUCTION / DECONTAMINATION ACTIVITIES Decontamination activities are continuing on the-281' level of the Auxiliary Building.
Average general area radiation dose rate is 40 mrem per hour on the 347' level of the reactor building and is 67 mrem per hour on the 1
305" level of the reactor building.
4.
ENVIRONWENTAi. HONITORING EPA sample analysis results show THI site liquid effluents to be in accordance with regulatory. limits, NRC requirements, and the City of Lancaster Agreement.
THI water sampics taken by the US Environmental Protection Agency at the plant discharge to the river consisted of seven daily composite samples taken from August 3 to August 10, 1935. Gamma scans detected no reactor related radioactivity.
The Lancaster water sample taken at the water works intake and analyzed by the US Environmental Protection Agency consists of a seven day composite sample taken from August 4 to August 10, 1985.
A gacna sr.an detected no reactor related radioactivity.
The NRO outdoor airborne particulate sampler at the THI Site collected a sample between August.15 and August 22, 1985. No reactor related radioactivity was detected. Analysis showed I-131 and Cs-137 concentrations to be less than the lower limits of detectability.
5.
REACTOR BUILDING ACTIVITIES Installation of the rotating work platform and service platform (over the reactor vessel) has been completed. Work on the north platform is in progress.
Installation of tool racks for defueling tools continues. The "D" tool rack is nearly complete; work is beginning on the "B" tool rack.
Defueling Water Cleanup System (DWCS) preoperational testing continued this week. The reactor vessel cleanup portioa of the g
system is expected to be operational by mid-September.
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6.
AUXILIARY AND FUEL HANDLING BUILDING ACTIVITIES
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.f Installation of the DWCS continued. Partial DWCS turnover for processing RCS during early defueling is expected to be completed in mid-Septerrber.
The second of four fuel canister racks is on site with the remaining two scheduled for delivery. in late August.
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August 26, 1985 Bernard J.' Snyde NRC/THI-85-065 d
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HRC EVALUATIONS IN PROGRESS Technical Spacification Change Requests numbers 48, 49, and 50.
Recovery Operations Plan Change numbers 29, 31, 32, and 34.
Fuel Canister Technical Evaluation.
Fuel Handling Senior Reactor Operator Training Program was completed August 22, 1935.
Defueling Safety Evaluation.
Application for seismic. exemption.
jff SDS Technical Evaluation and System Description Update 8.
PROJECTED SCHEDULE OF FUTURE EVENTS Start of Defueling: October 1985 9.
PUBLIC NEETING The next meeting of the Advisory Panel' for-the Decontamination of Three Mile Island Unit 2 is scheduled for September 11, 1985. The meeting will be at the Environmentai Matters Committee Room (Room 160) House Office Building, College Avenue, Annapolis, Maryland from 6:00 to 9:00 PM. The purpose of the meeting is to inform.the public:of progress being made in the THI-2 cleanup and to allow the public to voice concerns and make comments on any aspects of the cleanup. The status of the processed j
water will also be discussed.
2 Persons desiring the opportunity to speak before'the Panel are asked to contact Mr. Thomas Smithgall at 717-291-1042 or write to him at 2122 Marietta Avenue, Lancaster, Pennsylvania 17603.
Original signed by Philip Grant for William D.= Travers Deputy Program Director THI Prcgram Office t
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ilarold R. Denton 4
August 26, 1985 Bernard J. Snyder NRC/TMI-85-065
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