ML20138G822
| ML20138G822 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 10/21/1985 |
| From: | Travers W Office of Nuclear Reactor Regulation |
| To: | Harold Denton, Snyder B Office of Nuclear Reactor Regulation |
| References | |
| CON-NRC-TMI-85-079, CON-NRC-TMI-85-79 NUDOCS 8510280013 | |
| Download: ML20138G822 (5) | |
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October 21, 1985 NRC/Tlil-85-079 i
11EMORANDull FOR:
Harold R. Denton, Director Office of Nuclear Reactor Regulation
. c Bernard J. Snyder, Program Director e
THI Program Office FROM:
William D. Travers, Deputy Program Director
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THI Program Office s,
[i SUSJECT:
NRC THI PROGRAM 0FFICE WEEKLY STATUS REPORT FOR OCTOBER 12, 1985 - October 20, 1985 EpW 1.
PLANT STATUS p;.
rid 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 from the reactor
- vessel, g;
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 2',
. 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 Internal Indexing Fixture in preparttion for defueling.
Calculated reactor decay heat is less than 12 kilowatts.
RCS cooling is by natural heat loss to the reactor building ambient fl;,
atmosphere.
Incore thermocouple readings range from 71"F to 93*F P-with an average of 81 F.
The average reactor building temperature is 58*F. The reacter building airborne activity is 1.5 E-7 uC1/cc Tritium and 2.0 E-10
,g uC1/cc particulate, predominantly Cesium 137.
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WASTE MANAGEMENT The Submerged Demineralizer System (SDS) completed processing batch f
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124 from neutralizer tanks (WDL-T-8 A/B) to SDS monitor tanks
'h (SDS-T-1 A/B). : A: total of 25,218 gallons was processed in this f(
e batch.
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NRC FORM 318 (10-80) NRCM 0240 OFFICIAL RECORD COPY l
Harold R. Denton 2
October 21, 1985
,brnardA._Snyder 14RC/Till-35-079
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EPICOR II completed processirg batch 269, 10,578 gallons from SDS-T-1A to CC-T-2.
Comence d processing batch 270 frem SDS-T-1B to CC-T-2.
This process was placed in temporary shutdown due to high radioactivity chenistry results on all liners after processing 5,835 gallons.
Total volume processed through SDS to date is 2,988,593 gallons, and the total volume processed through EPICOR II is 2,700,737 gallons.
3.
_00SE REDUCTION /DECONTAMI!!ATI0ff ACTIVITIES Decontamination activities are continuing on the 281' level of the auxiliary building.
Average general area radiation dose rate is 40 arem per hour on the 347' level of the reactor building and is 67 mren per hour on the 305' level of the reactor building.
Pressurizer airror insulation is being recoved prior to characterization.
4.
ENVIRONMEllTAL fiONITORIf!G US Environmental Protection Agency (EPA) sample analysis results show Tf I site liquid effluents to be in accordance with regulatory limits, NRC requirements, and the City of Lancaster Agreement.
T!!I water samples taken by EPA at the plant discharge to the river consisted of seven daily composite samples taken from September 28 through October 5,1985. A gar,wa 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 September 29 through October 5,1985. A ganna scan detected no reactor related radioactivity.
The fiRC outdoor airborne particulate sampler at the TMI Site collected a sample between October 9 and October 16, 1985. No reactor related radioactivity was detected. Analysis showed Iodine-131 and Cesium-137 concentrations to be less than the lower limits of detectability.
5.
REACTOR BUILDING ACTIVITIES Defueling Uater Cleanup Systen (DUCS) preoperational testing and modification continued.
Installation of the vacuum defueling system is in progress.
Work is in progress on the canister positioning system.
Canister handling bridge indexing is in progress.
Lower vessel debris samples have been shipped to Idaho National Engineering Laboratories for analyses.
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........-....l NRC FORM 318 (10 80) NRCM 0240 OFFICIA RECORD COPY
Harold R. Denton 3
October 21, 1985 Bernard J. Snyder NRC/TMI-85-079
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6.
AUXILIARY AND FUEL HANDLIMG BUILDING ACTIVITIES Installation of the DWCS continued.
Partial DWCS turnover for processing RCS during early defueling is expacted to be completed in October.
Spent fuel pool was cleaned and filling with borated water is in progress.
Fuel canister handling bridge indexing has been completed.
7.
HRC EVALUATIONS IN PROGRESS Technical Specification Change Requests numbers 43 and 50.
Recovery Operations Plan Change numbers 29, 31, and 32.
Fuel Canister Technical Evaluation, Revision 1.
Defueling Safety Evaluation.
Application for seismic exemption.
SDS Technical Evaluation and System Description Update.
Core Stratification Sample Safety Evaluation.
Heavy Load Handling Safety Evaluation Report.
Boron Dilution Hazard Report Defueling Water Cleanup System Technical Evaluation Report, Revision 7.
Early Defueling Safety Evaluation Report, Revision 4.
8.
PUBLIC MEETING On the evening of October 16, 1935, the Advisory Panel for the Decontamination of Three Mile Island Unit 2 held a public meeting at the Public Safety Building in Lancaster, PA. At this meeting, the Panel was briefed by Dr. B. J. Snyder, Director, Three Mile Island Progran Office (TilIPO), on the impending reorganization of TMIPO.
Dr. H. f. Muller, State Health Secretary, Pennsylvania Departnient of Health, provided a detailed sumary of a recent study released by his department entitled, " Cancer Mortality and Morbidity (Incidence) Around TdI." The results of the Department of Health study, including both mortality and morbidity data, do not present evidence of an increased risk of developing cancer by local rasidents living near the TMI facility. Dr. Muller answered questions from the public.
Mr. F. Standerfer, Vice President / Director, GPU Huclear Corporation, provided a status report on the licenste's efforts to begin fuel removal.
The licensee expects to begin the early pbcses of fuel removal called
" pick and place" by the end of October.
The next meeting of the Advisory :'anel is scheduled for 11:00 AM, November 19, 1985, in Washington, DC, before the NRC Cor.nissioners. The next meeting in the TMI area is scheduled for December 12, 1985, at the Harrisburg, PA Holiday Inn, 23 South Second Street, Harrisburg, PA, from 7:00 PM to approximately 10:00 PM.
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NRC FORM 318 (10 80) NRCM O240 OFFICIAL. RECORD COPY
liarold R. Denton 4
October 21, 1985
- Bernard J. Enyder fiRC/Till-85-079 Persons desiring the opportunity to speak before the Panel are asked to contact fir. Thomas Smithgall at 717-291-1042 or write to him at 2122 (1arietta Avenue, Lancaster, Pennsylvania 17603.
ORiOINAI. SIGNED B%
Wi!!Iem O Tervers ililliam D. Travers Deputy Program Director TMI Program Office OF FICE )
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NRC FORM 318 (10-80) NRCM O24 OFFICIAL RECORD COPY
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Harold R. Denton' 5
October 21, 1985
'j tBernard J. Snyder r:
NRC/TMI-85-079 INTERNAL DISTRIBUTION EDO OGC Offic.e Directors Comissioner's Technical Assistants NRR Division Directors NRR A/D's Regional Administrators IE Division Directors TAS EIS TMI Program Office Staff (10)
PHS EPA DOE RI Division' Directors Public Affairs, RI State Liaison, RI THIP0 HQ r/f THI SITE r/f CENTRAL FILE NRC PDR LOCAL PDR THI-2 Project Section File b
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