ML20199J186
| ML20199J186 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 06/30/1986 |
| From: | Travers W Office of Nuclear Reactor Regulation |
| To: | Harold Denton, Miraglia F Office of Nuclear Reactor Regulation |
| References | |
| CON-NRC-TMI-86-063, CON-NRC-TMI-86-63 NUDOCS 8607080161 | |
| Download: ML20199J186 (4) | |
Text
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June 30, 1985 NRC/Till-86-063 4
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MEHORANDUM FOR:
Harold R. Denton, Director Office of Nuclear Reactor Regulation Frank J. Miraglia, Director Division of PLIR Licensing-B FR0il:
William D. Travers, Director THI-2 Cleanup Project Directorate
SUBJECT:
NRC TMI-2 CLEANUP PROJECT DIRECTORATE WEEKLY STATUS REPORT FOR JUNE 23 - JUNE 29,1986-6.
1.
DEFUELING
'E The first rail-mounted shipping cask was loaded with seven defueling canisters leaving 36 canisters stored in the fuel pool. The total weight of the debris contained in the seven canisters is 2400 lbs.
Approximately 51,670 lbs, of debris have been loaded into canisters and transferred to the fuel storage pool to date.
L The shielded work platform on top of the reactor vessel is currently dedicated to core stratification sample acquisition (core bore) activities. The core boring rig was being aligned as of Honday, June 30, 1986. The core bore is designed to obtain full length samples of the reactor core from the debris bed to the elliptical p- -
flow distributor plate.
Informati6n ydined Troia drilling regarding 1:
the hardness, ductility, and friability of the core material will be used to aid future defueling activities. The infornation will be useful to defueling tool development and defueling strategy. The core bore samples (approximately 21" in diameter and 8 ft. long) will be shipped to the Idaho National Engineering Laboratory for examirstion. Core bore activities are currently planned to continue for approximately four weeks.
On June 21 - 26, 1986, NRC's Vendor Inspection Branch performed a t
special inspection at Nuclear Pacific Corporation, Federal Way, P
Washington, of activities and records pertaining to non-destructive examination and testing of the two NUPAC 125-B fuel debris shipping sh containers. A representative of the THI-2 Cleanup Project Directorate participated in this effort. Areas reviewed included
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leak testing, radiography, ultrasonic testing, penetrant testing, 7'
and pressure testing of the containers. Vendor Inspection Branch will publish a report of the details of the inspection in approximately three weeks.
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8607080161 860630 PDR ADOCK 05000320 R
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Harold R. Denton 2
June 30, 1986 Frank J. Miraglia NRC/THI-86-063 4
2.
PLANT STATUS The reactor remains in long term cold shutdown, vented to the atmosphere. Core cooling is by natural heat loss to anbient building atmosphere. The average incore thermocouple reading is 78*F.
m The airborne radioactivity on the defueling platform is about 3 E-7 uC1/cc Tritium and 1.1 E-11 uCi/cc particulates, predominately Cesium-137 and Strontium-90. The platform is mounted above the modified internals indexing fixture which is mounted over the reactor vessel. These provide about 15 feet of water over the core region and 6 feet over the carousel holding the defueling canisters.
3.
WASTE MANAGEMENT The Submerged Demineralizer System (SDS) completed processing batch 5-133. SDS processing to date has been 4,098,333 gallons.
ti EPICOR II completed processing batch 293, 294, 295, and 296. The ij-system has processed 3,002,840 gallons to date.
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4.
ENVIRONMENTAL MONITORING US Environmental Protection Agency (EPA) sample analysis results show that TMI site liquid effluents are in accordance with regulatory limits, NRC requirements, and The City of Lancaster Agreement.'
The Lancaster water sample taken at the water works river intake and analyzed by EPA consisted of a seven day composite sample taken June
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8 - 14, 1986. A gamma scan detected no reactor related activity.
THI water samples taken by EPA at the plant discharge (includes
'Jnits 1 and 2f to the river consisted of seven daily composite samples taken from June 7 - 14, 1986. A gamma scan detected no reactor related activity.
The EPA analysis of the NRC outdoor air sample for the period June 19 - 26, 1986 showed that concentrations of Cs-137 and I-131 were below the lower limit of quantitative detectability for the system.
5.
AUXILIARY AND FUEL HANDLING BUILDING ACTIVITIES Assembly of the desludging system continued.
Hands-on decontamination was conducted in the Westinghouse Valve Room at the 281 ft elevation of the Fuel Handling Building.
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i NRC FORM 318 (10 80l NRCM O24 OFFICIAL RECORD COPY i
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Harold R. Denton 3
June 30, 1986 Frank J. Miraglia NRC/TMI-86-063 6.
NRC EVALUATIONS IN PROGRESS Technical Specification Change Request number 49, and 51.
Recovery Operations Plan Change number 31 and 36.
Solid Waste Facility Technical Evaluation Report.
Reactor Building Sump Criticality Safety Evaluation Report.
Defueling Canister Technical Evaluation Report, Revision 2.
Extended Core Stratification Sample Acquisition Activity.
Heavy Load Safety Evaluation Report, Revision 3.
Defueling Safety Evaluation Report, Revision 10.
original signed by Curt Cowgill for:
William D. Travers Director THI-2 Cleanup Project Directorate OFFICE) su"~= >
NRC FORM 318 (10 80) NRCM 0240 OFFICIAL RECORD COPY
t lc Harold R. D*nton 4
June 30, 1986 Frank J. Miraglia HRC/THI-86-063 INTERNAL DISTRIBUTI0fl CENTRAL FILE ilRC PDR LOCAL PPR EDO OGC Office Directors Connissioner's Technical Assistants NRR Division Directors HRR A/D's Regional Administrators L
IE Division Directors TAS EIS PilS EPA DOE RI Division Directors Public Affairs, RI State Liaison, RI Tft1 HQ r/f THI SITE r/f Till-2 Project Section File T;1I Cleanup Project Directorate (10) o
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