ML20138R847
| ML20138R847 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 11/08/1985 |
| From: | Travers W Office of Nuclear Reactor Regulation |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| CON-NRC-TMI-85-088, CON-NRC-TMI-85-88 NUDOCS 8511190126 | |
| Download: ML20138R847 (5) | |
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November 8, 1985 NRC/THI-85-088
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liEMORANDUM FOR:
Harold R. Denton, Director 1,
Office of Nuclear Reactor Regulation
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FROM:
William D. Travers Acting Director j?~
TMI Progran Office
SUBJECT:
HRC THI PROGRAM 0FFICE HEEKLY STATUS REPORT FOR
- i NOVEMBER 4,1985 - NOVEMBER 8,1985 i
- c 1.
DEFUELING Six entries were made during the week for movement of fuel debris. The objective was to excavate an area in the debris bed such that the CanisterPositioningSystem(CPS),whenloadedwithdefuelingcanisters, can rotate without interference. Approximately 2,000 lbs. of debris, 4
consisting mainly of end fittings and attached fuel rods, were moved from the northern quadrants within the reactor vessel to the southern regions.
By the end of the final defueling entry this week, it appeared that the objective had been accomplished. During next week's entry for defueling, video inspections will be made to verify the clearance for the CPS. Any remaining partial assemblies or rods that may still be sticking up above the debris bed (308' elevation) will be removed.
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4.
The average dose rate to each defueling worker was about 25 to 35 mrem j
per entry or about 10 mrem per hour. This indicates that fuel movement has not increased the dose rates in areas of the building occupied by 1
j defueling workers. Air samples also indicate no significant increase in i
airborne activity. The NRC is closely monitoring the defueling activities to ensure that o with applicable procedures.perations are, conducted safely in accordance k
2.
PLANT STATUS
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The facility remains in long term cold shutdown with th~e Reactor
- 1 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 2m 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 i
of the plenum).
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. Ilarold R. Denton 2
tiovenber 8,1985 NRC/THI-35-083 The modified internals indexing fixture is installed on the reactor vessel flange and is flooded to elevatico 327 feet 6 inches (151 feet above the top of the core region). The defueling platform is installed over the Internal Indexing Fixture in preparai. ion for defueling.
Calculated reactor decay heat is less than 12 kilowatts.
RCS cooling is by natural heat loss to the reactor buildiqg anbient atmosphere.
Incore themocouple readings range fron 71'F to 95"F with an average of 83*F.
The average reactor building temperature is 53"F.
The reactor building airborne activity at the Westinghouse platforn is 1.8 E-7 uCi/cc Tritium and 1.1 E-9 uCi/cc particulate, predominantly Cesium 137.
Spent Fuel Pool "A" is flooded to a depth of 20 feet. About 6 feet of water is over fuel canister storage racks.
3.
WASTE f1AtlAGEl1ENT The Submerged Demineralizar Systen (SDS) completed processing batch 125 Fuel Transfer Car.al through Train flo.1. A total of 203,369 gallons was processed in Batch 125.
Processing nf batch 126 conr.enced, Fuel Transfer Canal recycle through both Trains and "B" cation sand filter.
EPICOR II is temporarily shutdown while changing out liners.
Total volume processed through SDS to date is 3,174,794 gallons, and the total volume processed through EPICOR II is 2,700,73/ gallons.
4.
DOSE REDUCTION / DECONTAMINATION ACTIVITIES Decontamination activities are continuing on the 231' level of the auxiliary building. Scabbling of reactor coolant bleed tank cubicles is in progress.
Average general area radiation dose rate is 40 mrem per hour on the 347' level of the reactor building and is 67 mren per hour on the 305' level of the reactor building.
Decontamination of the pressurizer and "A" D-ring is in progress.
5.
ENVIRON 9 ENTAL HONITORING US Environnantal Protection Agency (EPA) sanple analysis results show THI site liquid effluents to be in accordance with regulatnry limits, URC requiremants, and the City of Lancaster Agreenant.
THI
- tater samples taken by EPA at the plant discharge to the river consisted of seven daily composite sampics taken from October 20 through October 26, 1985. A garxia scan detected no reactor related activi ty.
The Lancaster water sample taken at the water Works intake and analyzed by EPA consisted of a seven day composited sample taken from October 20 through October 26, 1935. A gmna scan detected no reactor relatad radioactivity, o"'M.........................
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- 1. R ECO R D C O P Y
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Novenbar 8, 1985 URC/T;11-85-088
'The NRC outdoor airborne particulate sampler at the THI Site collected a sample between October 30 and November 7, 1935.
.o reactor related r/ loactivity was detected. Analysis showe.
Iodine-131 and Ces um-137 concentrations to be less than the lower limits of detectability.
6.
REACTOR BUILDING ACTIVITIES The initial phase of dafueling the reactor core is in proaress.
Defueling llater Cleanup Systen (DWCS) preoperational testing and modification continued.
Installation of the vacuum defueling system is in progress.
Work is 16 progrash on the canister positioning system.
An integrated test of the canister handling bridges of the Reictor Building and th; Fuel llandling Guilding and the Fuel Transfer Canal is in progrese,. Ifhis will be accomplished by transfer of a canister from the Fue's Trh.sfer Canal to the Spent Fuel Paol through each of the Fuel Transfei Tubes.
7.
AUXILIARY AND FUEL HANDLING BUILDING ACTIVITIES Installation of the DilCS continued. Partial DWCS turnov'er for processing RCS durin.) early defueling is expected to be completed in October.
Spent Fuel Pool has been flooded to a depth of about 20 feet (about 6 feet above the top of the fuel canister storage racks).
8.
JjRC EVALUATIONS IN PROGRESS Technical Specification Change Request number 49.
a Recovery Operations Plan Change number 31.
Defueling Safety Evaluation.
SDS Technical Evaluation and Systen Description Update.
Core Stratification Sample Safety Evaluation.
Heavy Load Handling Safety Evaluation Report.
Defueling Water Cleanup System Technical Evaluation Ceport, Revision 7.
Containment Air Control Envelope Technical Evaluatica Report, Revision 5.
9.
PUBLIC tiEETING The next weting of the Advisory Panel is scheduled for 11:00 AM, Hovember 19, 1935, in Washington, DC, before th.' fiRC Commissiov es. The l
next necting in the TiiI area is scheduled for December 12,1985, at the llarrisburg, PA lloliday Inn, 23 South Second Street, liarrisburg, PA, frm 7:00 Pfl to approximately 10:00 PH.
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OFFICIAL RECORD COPY
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. il5r'oldR.Denton 4
flovember 8,1985 fiRC/ Tit!-85-088 Perscos desiring the opportunity to speak before the Panel are asked to contact fir. Thomas Smithgall at 717-291-1012 or write to him at 2122 ik,rietta Avenue, Lancaster, Pennsylvania,17603.
CAfGlHAt. $10NED Bfi Wi&m D. Travers Williaa D. Travers Acting Director Till Program Office OF dlCE )
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flovenber 8,1935 NRC/TIII-85-038 INTERNAL DISTRIBUTION EDO OGC Office Directors Conaissioner's Technical Assistants NRR Division Directors GRR A/D's Regional Adrainistrators IE Division Directors TAS EIS TMI Progran Office Staff (10)
PHS EPA DOE RI Division Directors Public Affairs, RI State Liaison, RI T!!IPO ilQ r/f Till SITE r/f CENTRAL FILE NRC PDR LOCAL PDR THI-2 Project Section File
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