ML20198R430
| ML20198R430 | |
| Person / Time | |
|---|---|
| Site: | Crane |
| Issue date: | 06/02/1986 |
| From: | Travers W Office of Nuclear Reactor Regulation |
| To: | Harold Denton, Miraglia F Office of Nuclear Reactor Regulation |
| References | |
| CON-NRC-TMI-86-053, CON-NRC-TMI-86-53 NUDOCS 8606100066 | |
| Download: ML20198R430 (4) | |
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I June 2, 1986 NRC/THI-86-053 HEMORANDUM FOR:
Harold R. Denton, Director Office of fluclear Reactor Regulation Frank J. Miraglia Director Division of PWR Licensing-B v
FR0H:
William D. Travers, Director THI-2 Cleanup Project Directorate
SUBJECT:
NREJ11-2 CLEANUP PROJECT DIRECTORATE WEEKLY STATUS REPORT FOR HAY 24 - June 1, 1986 V
i 1.
DEFUELING
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Pick and place defueling activities continued. The number of Q
canisters transferred to the fuel pool remains at 42.
On Sunday, June 1, 1986, video tape of the core was taken.
~t The sixth and final batch in the current campaign of Reactor Coolant System (RCS) drain and refill was completed on Saturday, May 31, 1986.
The Defueling Water Cleanup System (DWCS) was restarted on Saturday, May 31, 1986 and ran until Sunday evening June 1,1986.
2.
PLAtlT STATUS
.The reactor remains in long term cold shutdcwn, vented to the a tmosphere. Core cooling is by natural heat loss to ambient building atmosphere. The average incore thennocouple reading is 84 F; reactor vessel water temperature as measured by resistance temperature detectors (RTD's) is 78*F.
Water visibility is approximately 4 - 5 feet.
The airborne radioactivity on the defueling platform is about J
3 E-7 uCi/cc Tritium and 8 E-11 uC1/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.
WASTC HANAGEMENT 4
E t The Submrged Demineralizer System (SDS) and EPICOR II remain in temocrary shutdown. The SDS has processed 3,954,097 gallons through 8606100066 860602 DR ADOCK 0500 0
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DAT O une reau na no-soi sacu ono OFFICIAL RECORD COPY
iferold R. Denton 2
June 2, 1986 Frank J.111raglia flRC/TMI-86-053 batch S-131.
EPIC 0R II has processed 2,925,820 gallons through batch 287. Tha next processing will be the RCS drain-down water frca 8 and C Bleed Tanks, about 75,000 gallons.
To assure a naximun kill-off of the microbial growths throughout the water storage and processing systeas, the licensee plans a tank-by-tank application of hydrogen peroxide. This will include the processed water storage tanks, the EPICOR II discharge and feed tanks, the neutralizer tanks, and the miscellaneou; waste holdup tank.
4.
ENVIRONMENTAL 110flITORING 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 from May 10 - 17, 1986. A ganma scan detected no reactor related activity.
THI water samples taken by EPA at the plant discharge (includes Units 1 and 2) to the river consisted of seven daily composite samples taken from itay 10 - 17, 1986. A gamma scan detected a trace amount of Iodine-131 in the May 15 - 16, 1986 sample.
The EPA analysis of the NRC outdoor sampler for the period May 22 -
29, 1986 showed that concentrations of Cs-137 and I-131 were below the lower limit of quantitative detectability for the system, i.e.,
less than 1.1 E-13 microcuries/cc. A trace of I-131 was detected in the sample. The unquantifiably small traces of I-131 are probably from the Cherncbyl occident.
5.
AUXILIARY AND FUEL HANDLING BUILDIflG ACTIVITIES Water flushing was performed in the Westinghouse Valve Room (281' Auxiliary Building) over the past week. This room abuts the annulus and is the location of the mini-decay heat cooling systen. This is the first major decontanination of the room.
Assembly of the Desludging system continued.
On May 30, 1986, one of the rail shipping casks was moved into the fuel handling truck bay to assist in lining up the cask unloading st,.cion framing.
The testing program continues on the transfer shield.
6.
NRC EVALUATIONS IN PROGRESS Technical Specification Change Request number 49, and 51.
Recovery Operations Plan Change number 31, 33, 35, and 36 Solid Waste Facility Technical Evaluation Report.
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i Harold R. Denton 3
' June 2,1986 Frank J. Miraglia NRC/TitI-86-053 5.-~._~___
Reactor Building Sump Criticality Safety Evaluation Report.
Canister llandling and Preparation for Shipment Safety Evaluation Report.
Defueling Canister Technical Evaluation Report, Revision 2.
On liay 28, 1986 the NRC approved GPUN's safety evaluation report for Core Stratification Sample Acquisition, Revision 3.
7.
PUBLIC MEETING The Advisory Panel for the Decontantination of TMI-2 will meet with the NRC Comissioners on June 11, 1986 at 11:00 AM. The meeting will be held at the NRC conference room at 1717 11 Street, N.W., Washington, DC.
DNGWI3;Gtm tir, Wirt:m D. Im m William D. Travers Director TMI-2 Cleanup Project Directorate
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l sne ronv ais no soi nncu om OFFICIAL RECORD COPY
Harold R. Denton 4
June 2, 1986 Frank J. iiiraglia liRC/Till-86-053 INTERNAL DISTRIBUTION CENTRAL FILE NP'; POR LOCAL PDR EDO OGC Office Directors Comissioner's Technical Assistants NRR Division Directors NRR A/D's Regional Administrators IE Division Directors TAS EIS PHS EPA DOE RI Division Directors Public Affairs, RI State Liaison, RI TMI HQ r/f Till SITE r/f THI-2 Project Section File THI Cleanup Project Directorate (10)
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