ML20126M691
| ML20126M691 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 06/10/1985 |
| From: | Travers W Office of Nuclear Reactor Regulation |
| To: | Harold Denton, Snyder B Office of Nuclear Reactor Regulation |
| References | |
| CON-NRC-TMI-85-041, CON-NRC-TMI-85-41 NUDOCS 8506200429 | |
| Download: ML20126M691 (4) | |
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June 10, 1985 NRC/THI-85-041 NEMORANDUM FOR:
11arold R. Denton, Director
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Office of fluclear Reactor Regulation Bernard J. Snyder, Program Director THI Program Office FR0!i:
William D. Travers, Deputy Program Director TMI Program Office
SUBJECT:
NRC THI PROGRAM OFFICE WEEXLY STATUS REPORT FOR JUNE 3, 1985 - JUNE 9, 1985 1.
PLANT STATUS l
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 i
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 93*F with an average of 81*F. Average cold leg temperature is 55"F.
The average reactor building temperature is 59'F.
The reactor building airborne activity is 5.4 E-8 uC1/cc tritium, and 2.8 E-10 uti/cc particulate, predominantly cesium 137.
2.
WASTE MANAGEMENT
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No EPICOR 11 or Submerged Demineralizer System (SDS) processing occurred this week.
Total volume processed through SDS to date is 2.875,999 gallons, and
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h the total volume processed through EPICOR II is 2,447,788 gallons.
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Bernard J. Snyder NRC/THI-85-041
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DOSE REDUCTION / DECONTAMINATION ACTIVITIES m
Average general area radiation dose rate is 36 mrem per hour on the 347' icvel of the reactor building and is 160 mrem per hourion:the 305' level of the reactor building.
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ENVIRONHENTAL MONITORING s'
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 19, to May 25, 1985. A L
gamma 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 ccmposite
_ samples taken from Hay 18, to May 25, 1985. Gamma scans detected no reactor related radioactivity.
The NRC outdoor airborne particulate sampler at the TMI Site collected a sample between May 30, and June 5, 1985. Ho reactor related radioactivity was detected. Analysis showed I-131 and Cs-137-concentrations to be less than the lower limits of
. di detectability.
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The above EPA sample analysis results show TMI site liquid effluents to be in accordance_ with regulatory limits, NRC requirements, and the City of Lancaster Agreement.
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REACTOR BUILDING ACTIVITIES t
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Future work in the reactor building will be focused on preparations for the first phase of defueling in September 1985. The near term defueling preparations include installation of a_5-ton service crane a
over the refueling canal, completion of the Defueling Water Cleanup
}3 System and modifications to the aux 1,11ary fuel handling bridge.
6.
AUXILIARY AND FUEL HANDLING BUILDING ACTIVITIES Installation of the Defueling Water Cleanup System (DWCS) continued.
.c Boration of the processed water storage tank number 1 is in progress. -The chemical addition will be completed in June.
7.
NRC EVALUATIONS IN PROGRESS e
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Defueling Water Cleanup System Technical Evaluation Technical Specification Change Requests. numbers 46 and 48 i-Equipment Hatch Removal Safety Evaluation Recovery Operations Plan Change numbers 27 and 29 s
Fuel Canister Technical Evaluation n
Fuel Handling Senior Reactor 0perator Training Program
~ Defueling Safety Evaluation
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]DATE) j unc rogu ais tio sai nncu o24o OFFICIAL RECORD COPY
Harold R. Denton 3
June 10, 1985 Bernard J. Snyder NRC/TMI-85-041 8.
PROJECTED SCllEDULE OF FUTURE EVENTS Start of Defueling: September 1985 9.
PUBl.IC MEETING The Advisory Panel for the Decontamination of Three Mile Island Unit c
2 will meet with the NRC Comissioners on June 20, 1985, at 11:00 AM, in Washington, D.C.
ORIGINAL SIGNED BY PHIL GRANT William D. Travers Deputy Program Director THI Program Office suR- >
DATE)
NRC FORM 318 (10 80) NRCM O240 0FFICML RECORD COPY
!!arold R. Denton 4
June 10, 1985 Barnard J. Snyder HRC/Tlil-85-041 INTERNAL DISTRIBUTION EDO
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OGC Office Directors Comissioner's Technical Assistants NRR Division Directors NRR A/D's Regional Adrainistrators IE Division Directors TAS EIS TMI Program Office Staff (10)
PHS EPA DOE RI Division Directors Public Affairs, RI State Liaison, RI TilIPO HQ r/f Till SITE r/f CENTRAL FILE NRC PDR LOCAL PDR THI-2 Project Section File 4
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