ML20138C077
| ML20138C077 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 12/09/1985 |
| From: | Travers W Office of Nuclear Reactor Regulation |
| To: | Harold Denton, Miraglia F Office of Nuclear Reactor Regulation |
| References | |
| CON-NRC-TMI-85-098, CON-NRC-TMI-85-98 NUDOCS 8512120454 | |
| Download: ML20138C077 (6) | |
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,7-December 9, 1985 NRC/THI-85-098 it g
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'V HEHORANDUM FOR:
Harold R. Denton, Director lf Office of Nuclear Reactor Regulation ip Frank J. Miraglia, Director ya Division of PWR Licensing-B v
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William D. Travers, Director THI-2 Cleanup Project Directorate
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SUBJECT:
NRC TMI-2 CLEANUP PROJECT DIRECTORATE WEEKLY STATUS l;
REPORT FOR DECEMBER 2, 1985 - DECEMBER 8, 1985 li.
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1.
DEFUELING I
On December 4,1985, the licensee completed cutting the tangled and
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damaged fuel rods and rod-bundles on top of the debris bed. The licensee A
plans to load this material into special debris buckets and then place
'A the loaded buckets into the fuel canisters. This effort should improve
'N fuel loading efficiency and increase the amount of fuel loaded into a canister. On December 5,1985, the licensee surveyed the debris bed and l.'
made debris height measurements. These actions were performed to locate l1=
and count damaged endfittings for future planning and identify
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' appropriate locations to place debris loading buckets.
yl9 On December 5,'1985, a small. fire occurred when an unsecured light bulb
- i at the railing of the defueling platform tool slot ignited paper towel
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material wrapped around the bulb. The light bulb was deenergized and the fire was extinguished in less than one minute. There were no personnel contaminations or increases in airborne activity in the building. NRC
' personnel at the defueling coordination center observed that the g
4 licensee's actions were appropriate. Precautions to prevent a recurrence
- 3 have been taken by the licensee.-
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Beginning December 9,1985, defueling activity will be increased to three f:~
team entries from two team entries per day. During the past week,
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in-reactor building defueling time was increased to almost 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> per jN entry team from the previous average of about 3 - 31 hours3.587963e-4 days <br />0.00861 hours <br />5.125661e-5 weeks <br />1.17955e-5 months <br />.
In part, Q
this increase was due to the elimination of respirator requirements (see t7 Weekly Status Report of November 25 - November 30,1985). Since the f
occupational dose due to transits remains the same per entry, the W
' increase in defueling time per team should result in an overall man-rem i4-
-savings.
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OFFICIAL RECORD COPY
Harold R. Denton 2
Decenber 9, 1985
. Frank J.411raglia flRC/Tf11-85-098 2.
PLAilT STATUS The facility remains in long term cold ishutdown with the Reactor Coolant System (RCS) vented torthe react' or building atmosphere and thereactorvesselheadandplekuaassemblyremovedfromthereactor vessel.
W Theplenunisonitsstoragesta('nstalledbetweenthedeepand d in the deep end of the fuel transfer canal. A dam has been i 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 feet above the top of the core region). The defueling platform is installed over the internals indexing fixture for defueling.
Calculated reactor decay heat is less than 12 kilowatts.
RCS cooling is by natural heat loss to the reactor building ambient atmosphere.
Incore thermocouple readings range from 69 F to 94 F with an average of 83'F.
The average reactor building temperature is 56 F.
The reactor building airborne activity at the Uestinghouse platform is 1.1 E-7 uCi/cc Tritium and 6.4 E-10 uCi/cc particulate, predominantly Cesiun 137.
Spent Fuel Pool "A" is flooded to a depth of 20 feet. About 6 feet of water is over the fuel canister storage racks.
3.
WASTE MAllAGEMEllT Backwashing of the Defueling Water Cleanup System (DUCS) filters was unsuccessful in producing any useful extension of the filter life.
The cause of the filter plugging is believed to be very finely divided particulate contamination consisting mainly of iron compounds that blind the sintered metal filter media. The licensee is evaluating the use of a filter precoat naterial to alleviate the problen.
The kill of algae by addition of hydrogen peroxide in the spent fuel pool was successful in reducing turbidity. Hydrogen peroxide was added to the fuel transfer canal this week. Additional hydrogen peroxide additions to both the spent fuel pool and the fuel transfer canal are being evaluated.
Subnerged Demineralizer System (SDS) is temporarily shutdown.
EPICOR II is temporarily shutdown while changing out liners.
Total volume processed through SDS to date is 3,598,397 gallons, and the total volume processed through EPICOR II is 2,700,737 gallons.
The licensee has begun construction of a Unit 2 Solid Waste Handling Facility within the Unit 2 owner controlled area. The facility technical evaluation report is being reviewed by the TMICPD.
Completion is expected in summer 1936.
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OFFICIAL RECORD COPY
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Harold R. Denton 3
December 9, 1985 Frank J.111raglia NRC/THI-85-098 The facility will prepare waste for movement to the shipping / storage facility (Interim Solid !!aste Storage Facility) and will store no waste. The facility will house disassembly and cutting equipoent for shipment preparation of large equipment pieces. A barrel compactor will be located in the facility. Non-compactible waste will be loaded into barrels or boxes.
The facili;v will also house an equipment decontamination facility to complemanc the temporary decontamination facility in the Unit 2 Auxiliary Building.
Liquid radwaste solidification will be performed in the Unit 2 Fuel Handling Building using the newly installed cement and barrel tumbling unit.
4.
RADI0 ACTIVE MATERIAL / WASTE SHIPHENTS November 1 - Unit 2, EPICOR II dewatered resin liner ship,nent to Hanford, WA.
November 1 - Unit 2 radioactive samples sent to Rockville, MD.
November 5 - Unit 2 laundry shipment of 69 drums and 3 boxes of protective clothing to Royersford, PA.
November 6 - Unit 2 reactor coolant systen samples sent to Oak Ridge, Tfl.
Noveaber 7 - Unit 2 radioactive samples sent to Rockville, MD.
November 12 - Unit 2 EPICOR II dewatered resin liner shipment to Hanford, WA.
November 13 - Unit 2 laundry shipment of 44 drums and 3 boxes of protective clothing to Royersford, PA.
Noven.ber 13 - Unit 2 EPICOR II dewatered resin liner shipment to Hanford, PA.
November 14 - Unit 2 liquid radioactive sample sent to Rockville, VD.
November 15 - Unit I liquid radioactive sample sent to Rockville, MD.
November 18 - Unit 2 EPICOR II dewatered resin liner shipment to Hanford, WA.
November 19 - Unit 2 laundry shipment of 61 drums and 1 box of protective clothing to Royersford, PA.
tlovember 22 - Unit 2 EPICOR II dewatered resin liner shipment to Hanford, WA.
November 22 - Unit 1 liquid radioactive sample sent to Rockville, MD.
November 25 - Unit 1 one solidified evaporator bottoms liners and two dewatered resin liners to Barnwell, SC.
Novenber 27 - Unit 2 check source sent to Forked River, NJ.
November 27 - Unit 2 EPICOP. II dewatered resin liner shipment to Hanford, IIA.
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NRC FORM 318 (10 80) NRCM 024 OFFICIAL. RECORD COPY
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Harold R. Denton 4
December 9, 1985 Frank J. Miraglia NRC/TMI-85-098 5.
DOSE REDUCTION / 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 mrem per hour on the 347' level of the reactor building and is 67 mrem par hour on the 305' level of the reactor building.
Decontamination of the pressurizer and "A" D-ring is in progress.
6.
ENVIRONMENTAL MONITORING r
. US Environmental Protection Agency (EPA) sample analysis results show THI site liquid effluents to be in accordance with regulatory limits, NRC requirements, and the City of Lancaster Agreement.
TMI water samples taken by EPA at the plant discharge to the river consisted of seven daily composite samples taken from November 16 through. November 23, 1985. A gamma scan detected no reactor related activity.
The Lancaster water sample taken at the water works intake and analyzed by EPA consisted of a seven day composited sample taken from November 17 through November 23, 1985. A gamma scan detected no reactor related radioactivity.
The NRC outdoor airborne particulate sampler at the THI Site collected a sample between November 27 and December 5,1985. No reactor related radioactivity was detected. Analysis showed Iodine-131 and Cesium-137 concentrations to be less than the lower limits of detectability.
7.
REACTOR BUILDING ACTIVITIES The initial phase,of defueling the reactor core is in progress.
Installation of the vacuum defueling system is in progress.
8.
AUXILIARY AND FUEL llANDLING BUILDING ACTIVITIES Installation of the balance of DWCS continued.
Spent Fuel Pool "A" has been flooded to a depth of about'20 feet (about 6 feet above the top of the fuel canister storage racks).
9.
NRC EVALUATIONS IN PROGRESS Technical Specification Change Request number 49.
Recovery Operations Plan Change number 31.
SDS Technical Evaluation and System Description Update.
Core Stratification Sample Safety Evaluation.
.Defueling Water Cleanup System Technical Evaluation Report, E
Revis' ion 7.
Containment Air Control Envelope Technical Evaluation Report, Revision 5.
Solid Waste Facility Technical Evaluation Report.
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e fiarold -R.- Denton 5
Decenber 9,1935 W
Frank J. Miraglia NP,C/Tril-85-098
- 10. PUBLIC MEETING The next meeting of the Advisory Panel is scheduled for December 12, 1935, at the Holiday Inn, 23 South Second Street, Harrisburg, PA, from 7:00 Pli to 10:00 Pil.
At that meting 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 the Panel are asked to contact Mr. Thomas Smithgall at 717-291-1042 or write to him at 2122 Marietta Avenue, Lancaster, Pennsylvania 17603.
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William D. Travers Director Till-2 Cleanup Project Directorate
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NRR Division Directors HRR A/D's Regional Administrators IE Division Directors TAS EIS THI Progran Office Staff (10)
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