ML20137P507

Submits TMI Program Ofc Weekly Status Rept for Wk of 851118-25

ML20137P507
Person / Time
Site:	Three Mile Island
Issue date:	11/25/1985
From:	Travers W NRC
To:	Harold Denton Office of Nuclear Reactor Regulation
References
CON-NRC-TMI-85-094, CON-NRC-TMI-85-94 NUDOCS 8512050038
Download: ML20137P507 (5)

Text

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November 25, 1985 t

NRC/THI-85-094 MEMORAriDUM FOR: Harold R. Denton, Director Office of Nuclear Reactor Regulation FROM: William D. Travers, Acting Director THI Program Office E

SUBJECT:

NRC THI PROGRAM 0FFICE WEEKLY STATUS REPORT FOR NOVEMBER 18, 1935 - NOVEMBER 24, 1985 3

1. DEFUELING On November 18, 1985, the licensee modified their imediate defueling strategy from that of pick and place to that of cutting the distorted fuel rods. Defueling progress has been slow due to interferences and inability to separate fused endfittings. The licensee is cutting fuel rods to reduce the interference and improve packing density in the fuel canisters. A problem developed during the week with the defueling tools hydraulic system. Boron in the system plated out on system filters which caused the system to be shutdown on high filter differential pressure.

The fluid is being replaced by an alternate approved hydraulic fluid that

,' has boron in solution. Defueling should recomence on flovember 26, 1985.

Photographic mapping of the debris bed has been accomplished during the delay. NRC staff observations indicate licensee is continuing to aggressively pursue problem areas and is making improvements that should enhance overall defueling efficiency.

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2. PLANT STATUS The facility remains in long term cold shutdown with the Reactor Coolant System (RCS) vented to the reactor huflding atmosphere and the reactor vessel head and plenum assembly rtmoved 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 4

with water to a depth of about 20 feet (about 5 feet above the top of the plenum).

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The modified internals indexing fixture is installed on the reactor vessel flange and is flooded to elevation 327 feet 6 inches (151 i [Jj h feet above the top of the core region). The defueling platfonn is installed over the Internal Indexing Fixture for defueling. P

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throld R. Denton 2 November 25, 1985 NRC/TMI-85-094 Calculated reactor decay heat is less than 12 kilowatts.

RCS cooling is by natural heat loss to the reactor building ambient atnosphere. Incore thermocouple readings range from 71*F to 95"F with an average of 83 F.

The average reactor building temperature is 56 F. The reactor building airborne activity at the llestinghouse platform is 1.2 E-7 uCi/cc Tritium and 2.5 E-10 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 IWlAGENEfiT Both trains of the reactor vessel filtration portions of the defueling water cleanup systen (DWCS) have been shutdown when the filter differential pressure reached the procedural linit.

Evaluation is in progress of the particulate suspension in the RCS.

A procedure has been approved to backwash the filters.

Submerged Demineralizer System (SDS) processing of batch 126 continues, Fuel Transfer Canal recycle through both Trains and "B" cation sand filter. A total of 319,705 gallons has been processed in batch 125 to date.

EPICOR II is tenporarily shutdown while changing out liners.

Total volume processed through SDS to date is 3,511,667 gallons, and the total volume processed through EPICOR II is 2,700,737 gallons.

4. DOSE REDUCTI0il/ DECONTAMINATION ACTIVITIES Decontamination activities are continuing on the 281' level of the auxiliary building. Scabbling of reactor coolant bleed tank cubicles is in progress.

Average general area radiation dose rate is 40 mren per hour on the 347' level of the reactor building and is 67 mren per hour on the 305' level of tha reactor building.

Decontamination of the pressurizer and "A" D-ring is in progress.

5. ENVIRONMENTAL fl0NITORING US Environmental Protection Agency (EPA) sample analysis results show TMI site liquid effluents to be in accordance with regulatory limits, fiRC requiremants, and the City of Lancaster Agreement.

THI uater samples taken by EPA at the plant discharge to the river consisted of seven daily composite samples taken from November 3 through Noveaber 9, 1985. A ganna scan detected no reactor related activity.

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NRC FORM 318 (10 90) N RCM O240 OFFICIR RECORD COPY

Harold R. Denton 3 flovember 25, 1985 fiRC/Tl1I-85-094 The Lancaster water sample taken at the water works intake and analyzed by EPA consisted of a seven day composited sample taken from flovenber 3 through November 9,1985. A ganma scan detected no reactor related radioactivity.

The t4RC outdoor airborne particulate sampler at the TMI Site collected a sample between lloveuber 13 and tiovember 20, 1985. fio reactor related radioactivity uis detected. Analysis showed Iodine-131 and Cesium-137 concentrations to be less than the lower limits of detectability.

6. REACTOR BUILDIllG ACTIVITIES The initial phase of defueling the reactor ccre is in progress.

Installation of the vacuum defueling system is in progress.

7. AUXILIARY AND FUEL HANDLIllG BUILDIflG ACTIVITIES Installation of the balance DWCS continued.

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. NRC EVALUATI0ilS Ifl PROGRESS Technical Specification Change Request number 49.

Recovery Operations Plan Change number 31.

SDS Technical Evaluation and System Description Update.

Core Stratification Saaple Safety Evaluation.

Defueling Hater Cleanup System Technical Evaluation Report, Revision 7.

Containment Air Control Envelope Technical Evaluation Report, Revision 5.

Solid Maste Facility Technical Evaluation Report.

9. PUBLIC tiEETING The Advisory Panel for the Decontamination of T!11-2 met with the Commissioners in Washington, DC on flovember 19, 1935. At that meeting the Panel informed the Comaission of their recent briefings by GPUfl on defueling plans. Additional topics of discussion included: (1) licensee measures to prevent criticality during defueling, (2) licensee schedule for conducting defueling activities, (3) panel activities related to Tl11-2 accident health effects issues, and (4) status of licensee plans for disposition of processed accident water.

The Panel also informed the Coranission of its plans for discussing issues at future panel meeting.

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itarold R. Denton 4 riovember 25, 1985 flRC/Till-85-094 -

The next meeting of the Advisory Panel is scheduled for Deceniber 12, 1985, at the lioliday Inn, 23 South Second Street, liarrisburg, PA, from 7:00 Pit to 10:00 PM.

At that meeting GPUN will provide a status of defueling activities and Mr. and Mrs. Aamodt will provide information regarding their health effects evaluations.

Persons desiring the opportunity to speak before tha Panel are asked to contact Mr. Thomas Smithgall at 717-291-1042 or write to hin at 2122 Marietta Avenue, Lancaster, Pennsylvania 17603, wto w ! EG C Oa'

am D. Dt3*2 Willian D. Travers Acting Director TMI Program Office s'm^"c> ........ ... .......... .. ..... ... . ............ ..... ..... . . ........... .............

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NRC FORM 318 (10 80) NRCM 024 OFFICIAL RECORD COPY

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• Harold .R. Denton 5 November 25, 1985

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NRC/Till-85-094 ItiTER'1AL DISTRIBUTI0ii E00

, OGC Office Directors Comissioner's Technical Assistants flRR Division Directors liRR A/D's Regional Ad.ministrators IE Division Directors TAS

! EIS j Till Prograa Office Staff (10)

PHS EPA DOE 1

RI Division Directors Public Affairs, RI 4

State Liaison, RI

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,  !!RC PDR LOCAL PDR l TitI-2 Project Section File 1

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