IR 05000525/2006002
| ML20125B533 | |
| Person / Time | |
|---|---|
| Site: | Crane, 05000525  |
| Issue date: | 06/03/1985 |
| From: | Travers W Office of Nuclear Reactor Regulation |
| To: | Harold Denton, Snyder B Office of Nuclear Reactor Regulation |
| References | |
| CON-NRC-TMI-85-039, CON-NRC-TMI-85-39 NUDOCS 8506110446 | |
| Download: ML20125B533 (4) | |
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June 3, 1985
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NRC/THI-85-039
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MEMORANDUM FOR:
Harold R. Denton, Director Office of Nuclear Reactor Regulation Bernard J. Snyder, Program Director TMI Program Office t ~
FROM:
William D. Travers, Deputy Program Director THI Program Office
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SUBJECT:
NRC TMI PROGRAM 0FFICE WEEKLY STATUS REPORT FOR MAY 25, 1985 - JUNE 2, 1985
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1.
_ PLANT STATUS The facility remains in long term cold shutdown with the Reactor
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Coolant System (RCS) vented to the reactor building atmosphere and the reactor vessel head and plenum assembly removed.
RCS cooling is by natural heat loss to the reactor building ambient
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atmosphere..Incore thennocouple readings range from 72*F to 92*F with an average of 81*F. Average cold leg temperature is 57*F.
Calculated reactor decay heat is less than 14 kilowatts.
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The modified internals indexing fixture is installed on the reactor
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vessel flange and is flooded to elevation 327 feet 6 inches (151 feet above the top of the core region).
The average reactor building temperature is 59 F.
The reactor
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building airborne activity is 4.7 E-8 uC1/cc tritium, and 6.9 E-11 uC1/cc particulate, predominantly cesium 137..
The reactor vessel plenum has been removed from the reactor. vessel
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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 i
depth of about 20 feet (about 5 feet above the top of the plenum).
2.
WASTE MANAGEMENT No EPICOR II or Submerged Demineralizer System (SDS) processing
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occurred this week.
Total volume processed through SDS to date is 2,875,999 gallons, and
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the total volume processed through EPICOR II.is 2,447,788 gallons.
Fifteen shipments of radioactive material / waste were sent from the
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site during the month of May:
May 1,1985.- a contaminated laundry shipment of 102 barrels and.
j 3 boxes was sent to Royersford, Pennsylvania..
--May_3,;1965_- aJnitishipmenLof 16,steekboxes-of-f41ter-cake material whs sent to Ridhland, Washington.
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L f4 H'arold R. Denton
Juna 3, 1985
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Bernard J. Snyder NRC/TMI-85-039
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Hay 6, 1985 a Unit 1 shipment of radioactive waste samples was
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sent to Rockville, Maryland.
Hay 8,1985 - a contaminated laundry shipment of 83 drums and 2 boxes was sent to Royersford, Pennsylvania.
May 9,1985 - a Unit I waste shipment of 14 boxes of filter cake
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was sent to Hanford, Washington.
May 13, 1985 - liquid samples from Unit I were sent to Westwood, c4 New Jersey.
May 15, 1985 - a shipment of Unit 2 scrap steel was sent to Oak Q-Ridge, Tennessee.
Ilay 15, 1985 - a contaminated laundry shipment of 117 drums and
4 boxes was sent to Royerford, Pennsylvania.
Hay 17, 1985 - Unit I sent four steel liners on two trucks
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filled with solidified evaporator bottoms to Richland, C'
p flay 20,1985 - a Unit 1 shipment of dewatered resins was sent to Barnwell, South Carolina.
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!!ay 22; 1985 - a contaminated laundry shipment of 75 drums and 1 O
box was sent to Royersford, Pennsylvania.
Hay 28,1985 - a Unit 2 shipment of scrap steel and depleted sN acid was sent to Oak Ridge, Tennessee..
C Hay 28, 1985 - a contaminated laundry shipment of 67 drums and 4
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boxes was sent to Royersford, Pennsylvania.
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May 30, 1985 - a Unit I waste shipment of 15 boxes of filter cake was sent to Richland, Washington.
May 31, 1985 - three 15,000
'l-(an oversized load shipment) gallon internally contaminated tanks
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were sent to Idaho National
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Engineering Laboratories at Scov111.e, Idaho.
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DOSE REDUCTION /DEC0tlTAMINATION ACTIVITIES
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General cleanup continued in the control and service building
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bas'ement.
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Average general area radiation dose rate is 36 mrem per hour on the
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.347' level of the reactor building and is 160 mrem per hour on the
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305' level of the reactor building.
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ENVIRONMENTAL MONITORING
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The Lancaster water sample taken at the water works intake and
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analyzed by the US Environmental Protection Agency consisted of a seven day composite sample taken from May 12, to llay 18, 1985. A g
ganaa scan detected no reactor related radioactivity.
THI water samples taken by the US Environmental Protection Agency at
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the plant' discharge to the' river consisted of seven daily composite
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samples taken from May 11. to Hay 18,-1985. Gamma scans detected no reactor related radioactivity.
The NRC outdoor airborr.a' particulate ' sampler at the THI Site
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collected a sample between May 23, and May 30, 1985. No reactor related radioactivity was detected. Analysis showed I-131 and Cs-137 concentrations to be less than the lower limits of detectability.
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NRC FORM 318 (10-80) N9CM 0240 OFFICIAL RECORD COPY
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.H:rold R. Denton.
June 3, 1985
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Bernard J. Snyder NRC/THI-85-039 i
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The above EPA sample analysis results show TMI site liquid effluents
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to be in accordance with regulatory limits, NRC requirements, and the City of Lancaster Agreement.
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5.
REACTOR BUILDING ACTIVITIES
' [E Future work in the reactor building will be focused on preparations
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' for the first phase of defueling in September 1985. The near term
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defueling preparations include installation of a 5-ton service crane
{V over the refueling canal, completion of the Defueling Water Cleanup
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,y System and modifications to the auxiliary fuel handling bridge.
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6.
AUXILIARY AND FUEL HANDLING BUILDING ACTIVITIES Installation of the Defueling Water Cleanup System (DWCS) continued.
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Boration of the processed water storage tank number 1 is in progress.
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The chemical addition will take about one month, e
The auxiliary building elevator has been decontaminated to general n
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R access levels (below 1,000 dpm/100 cm2; below 2.5 mR/hr).
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7.
HRC EVALUATIONS'IN PROGRESS
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i j 712 Defueling Water Cleanup System Technical Evaluation
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4" Technical Specification Change Requests numbers 46 and 48.
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Equipment Hatch Removal Safety Evaluation f'-
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Recovery Operations Plan Change numbers 27 and 29
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Fuel Canister Technical Evaluation
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Fuel Handling Senior Reactor Operator Training Program
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Defueling Safety Evaluation
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PROJECTED SCHEDULE OF FUTURE EVENTS
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Start of Defueling: September 1985
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ORIGINAL SIGNED BY
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William D. Travers
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Deputy Program Director L' _f 1).
THI Program Office s
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- NRC FORM 318 (10 80) NRCM 0240 OFFICIAL RECORD ~ COPY -
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.IaroldR.Denton
June 3, 1935 Bernard J. Snyder tiRC/TIII-85-039
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IllTERilAL DISTRIBUTION EDO
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OGC Office Directors Corxitssioner's Technical Assistants liRR Division Directors flRR A/D's Regional Administrators IE Division Directors TAS EIS TiiI Program Office Staff (10)
PHS EPA DOE RI Division Directors Public Affairs, RI State Liaison, RI THIPO !!Q r/f Till SITE r/f CENTRAL FILE NRC POR LOCAL PDR Tril-2 Project Section File
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NRC F _ RM 318 (10 80) NRCM O240 OFFICIAL RECORD COPY t