ML20128M347
| ML20128M347 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 07/01/1985 |
| From: | Travers W Office of Nuclear Reactor Regulation |
| To: | Harold Denton, Snyder B Office of Nuclear Reactor Regulation |
| References | |
| CON-NRC-TMI-85-045, CON-NRC-TMI-85-45 NUDOCS 8507110682 | |
| Download: ML20128M347 (4) | |
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l-4 July 1, 1985 NRC/THI-85-045 MEHORANDUM FOR:
liarold R. Denton, Director i ~
Office of Nuclear Reactor Regulation Bernard J. Snyder, Program Director l7 THI Program Office FR0H:
Wilitam D. Travers, Deputy Program Director l,,
Till Program Office
SUBJECT:
HRC THI PROGRAM OFFICE WEEKLY STATUS REPORT FOR JUNE 24, 1985 - JUNE 30, 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 renoved.
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 a
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 atmosphere.
Incore thermocouple readinos range from 71*F to 92"F with an average of 82*F. Average cold leg temperature is 56*F.
The average reactor building temperature is 62*F. The reactor butiding airborne activity is 2.0 E-9 uCf/cc tritium, and 6.6 E-10 uC1/cc particult.te, predominantly cesium 137.
2.
WASTE HANAGEMENT t
The Submerged Demineralizer System (SDS) was shutdown during this period.
EPICOR II processed batch 257(10,937 gallons).
Total volume processed through SDS to date is 2,898,836 gallons,and the total volume processed through EPICOR II is 2.480,774 gallons.
Seventeen shipments of radioactive material / waste were made from the site during the period Hay 21 - June 26,1985:
lf Contaminated laundry was sent to Royersford, Pennsylvania:
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June 5; 89 drums, 3 boxes
,J,/% f June 11; 102 druas, 4 boxes June 19; 90 drums, 3 boxes l
June 26; 67 drums, 4 boxes
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Harold R. Denton 2
July 1, 1985 Bernard J. Snyder fiRC/THI-85-045 May 21, 1985 - A Unit 1 gas sample to Oak Ridge, Tennessee.
Hay 24,19J5 - Unit 1,16 boxes of filter material to Hanford, Washington.
Hay 30,1985 - Unit 1,15 boxes of filter material to Hanford, Washington.
June 10,1985 - A Unit 2 tank was sent to Buchanan, flew York.
June 13, 1985 - A combined shipment of non-compacted waste was sent to llanford Washington.
June 14, 1985 - A Unit 1 sample shipment was sent San Jose, California.
June 17, 1985 - A combined shipment of 112 drums was sent to llanford, Washington.
June 19, 1985 - Two Unit I sample shipments were sent to San Jose, California.
June 19, 1985 - A Unit 1 sample was sent to Rockville, Maryland.
June 20, 1985 - A combined shipment of non-compacted waste in 18 boxes was sent to Richland, Washington.
June 21, 1985 - A Unit 1 shipment of two depleted resin liners was sent to Richland, Washington.
June 26,1985 - A Unit 2 shiptaent, three spent resin liners and 8 steel boxes were sent to llanford, Washington.
June 26, 1985 - A Unit 2 shipment of cable samples was sent to llanford, Washington.
3.
DOSE REDUCTI0ti/DEC0flTNIIrlATIO!1 ACTIVITIES Shielding of the reactor building air coolers is in progress.
Average general area radiation dose rate is 36 mren per hour on the 347' level of the reactor building and is 160 aren per hour on the 305' level of the reactor building.
4.
ENVIR01.HE!1TAL N0:11TORIllG EPA sample analysis results shew Tiil site liquid effluents to be in dCCordance with regulatory limits, f1RC 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 fron June 8, to June 15, 1985. 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 consisted of a seven day composite sample taken from Junc 9, to June 15, 1985. A gattna scan detected no reactor related radioactivity.
The NRC outdoor airborne particulate sampler at the Till Site collected a sample between June 19, and June 27, 1985. No reactor related radioactivity was detected. Analysis showed I-131 and Cs-137 concentrations tn be less than the lower limits of detectability.
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liarold R. Denton i
3 July 1, 1985 g
Bernard J. Snyder NRC/THI-85-045 5.
REACTOR BUILDIfiG ACTIVITIES Future work in the reactor building is focused on preparations for the first phase of defueling in September 1985 The 5-ton service crane was load tested and certified for use in the reactor building.
This crane will be used in preparation for installation of defueling equipment but will not be used to transfer loaded fuel canisters.
Additional near teru defueling preparations include installation of defueling platform, completion of the Defueling Water Cleanup System (DUCS) and modifications to the auxiliary fuel handling bridge.
6.
AUXILIARY AND FUEL NNIDLING BUILDING ACTIVITIES Installation of the DWCS continued. Partial DUCS turnover for processing RCS during early defueling is scheduled to be completed in late August.
Boration of the processed water storage tank Hunber 1 is continuing.
This tank, which will be used to ficod the "A" spent fuel pool during defueling, contains water at a baron concentration of 4,580 ppm.
7.
NRC EVALUATIONS Ill PROGRESS DefuelingWaterCleanupSystemTechnicalEvaluation(including
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Revision 6)
Technical Specification Change Requests numbers 46, 48, and 50 Equipment Hatch Removal Safety Evaluation Recovery Operations Plan Change numbers 27, 29. and 32 Fuel Canister Technical Evaluation Fuel Handling Senior Reactor Operator Training Program Defueling Safety Evaluation 8.
PROJECTED SCHEDULE OF FUTURE EVENTS Start of Defueling: September 1985 9.
PUBLIC MEETING The next meeting of the Advisory Plan is scheduled for 7:00 Pll, July 18, 1985, at the Public Service Dutiding, 201 North Duke Street,
.c Lancaster, PA.
Om0M41 We e W.
Wmiom D. Travers
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William D. Travers
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Deputy Program Director Till Program Office
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July 1, 1985 Bernard J. Snyder tiRC/T!!!-85-045 IllTERilAL ~0!STRIBUTI0rl EDO OGC Office Directors Comissioner's Technical Assistants llRR Division Directors flRR A/D's Regional Adninistrators IE Division Directors TAS EIS TI-II Program Office Staff (10)
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