ML20134N592
| ML20134N592 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 08/30/1985 |
| From: | Travers W Office of Nuclear Reactor Regulation |
| To: | Harold Denton, Snyder B Office of Nuclear Reactor Regulation |
| References | |
| CON-NRC-TMI-85-067, CON-NRC-TMI-85-67 NUDOCS 8509050208 | |
| Download: ML20134N592 (4) | |
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NRC/THI-85-067 y
HEMORANDUM FOR:
Harold R. Denton, Director
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Office of Nuclear Reactor Regulation 4'
Bernard J. Snyder, Program Director THI Program Office i
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William D. Travers, Deputy Program Director 1 t J(
TNI Program Office
SUBJECT:
HRC THI PROGRAM 0FFICE WEEKLY STATUS REPORT FOR AUGUST 26, 1985 - AUGUST 30, 1985 1.
PLANT STATUS
..p-The facility rema.ns in long term cold shutdown with the Reactor Coolant System (RCS) vented to the reactor building atmosphere and Q
the reactor vessel head and plenum assembly removed from the reactor vessel.
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 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 i
vessel flange and is flooded to elevation 327 feet 6 inches (151 feet above the top of the core region).
Calculated reactor decay heat is less than 12 kilowatts.
RCS cooling is by natural heat loss to the reactor building ambient atmosphere.
Incore thermocouple readings range from 71'F to 92*F O
with an average of 80'F. Average cold leg temperature is 55'F.
The average reactor building temperature is 59 F.
The reactor building airborne activity is 2.6 E-7 uCi/cc Tritium and 7.4 E-10 uC1/cc particulate, predominantly Cosium 137.
h 2.
WASTE HAHAGEMENT u
The Submerged Demineralizer System (SDS) and EPICOR II were shutdown
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,c this period.
Total volume processed through SDS to date is 2,963,375 gallons, and J'
the total volume processed through EPICOR II is 2,547,671 gallons.
h About 61,000 gallons of water has been transferred from condensate f
4 tank 1A (C0T-1A) to CCT-1 in preparation for processing chrough j
EPICOR II. COT-1A will be desludged and used for stora je of borated /g A
makeup water.
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The project to solidify waste for shipment to the Hanford, l
Washington burial site was ccmpleted. One 110 gallon drum with an l'
encapsulated resin column, one 4x4 liner (50 cubic feet) with cement i
solidified sand from SDS prefilters, and three 6x6 liners (170 cubic feet each) with a cement solidified mixture of sand from SDS prefilters and resin from EPICOR II were generated. Two additional 6x6 liners were prepared for solidification but were not completed due to mechanical failures in the portable solidification system.
These liners, containing a mixture of sand and resin, were returned to storage _and will be stabilized for shipment in the future.
3.
DOSE REDUCTION /DECONTAi1INATION ACTIVITIES
'I Decontamination activities are continuing on the 281' level of the Auxiliary Building.
Average general area radiation dose rate is 40 mrem per hour on the 347' level of the reactor building and is 67 mrem per hour on the 305' level of the reactor building.
4.
-ENVIRONMENTAL MONITORING EPA sample analysis results show TriI site liquid effluents to be in accordance with regulatory limits, NRC requirements, and the City of Lancaster Agreement.
THI water samples taken by the US Environmental Protection Agency at the plant discharge to the river consisted of seven daily composite k
samples taken from August 10 to August 17, 1985. Gar.ma scans 1'
detected no reactor related radioactivity.
The Lancaster water sample taken at the water works intake and analyzed by the US Environmental Protection Agency consists of a seven day composite sample taken from August 11 to August 17, 1985.
A gamma scan detected no reactor related radioactivity.
The HRC outdoor airborne particulate' sampler at the Ti1I Site collected a sample between August 22 and August 29, 1985. No reactor related radioactivity was detected. Analysis showed I-131 t-and Cs-137 concentrations to be less than the lower limits of detectability.
,9 5.
REACTOR BUILDING ACTIVITIES Work continued on installation of the north end platform and the defueling tool racks.
Defueling Water Cleanup System preoperational testing continued.
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Installation of cable tray shielding is in progress.
Work began on staging of reactor building sump recirculation system l
components into the building.
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NRC FORM 318 0080) N RCM ONO OFFICIAL RECORD COPY
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Harold R. Denton
.3 August 30, 1985
-~~ Bernard Jr$nydera NRC/TMI-85-067 6.
AUXILIARY AND FUEL HANDLING BUILDING ACTIVITIES A
Installation of the DWCS continued.
Partial DWCS turnover for processing RCS during early defueling is expected to be completed in
. late. September.
The second of four fuel canister racks is on site with the remaining two scheduled for delivery the first two weeks of September.
7.
HRC EVALUATIONS IN PROGRESS F
Technical Specification Change Requests numbers 48, 49, and 50.
_ Recovery Operations Plan Change numbers 29, 31, 32, and 34.
Fuel Canister Technical Evaluation.
Defueling Safety Evaluation.
Application for seismic exemption.
SDS Technical Evaluation and System Description Update 8.
- LICENSEE-PROJECTED SCllEDULE OF FUTURE EVENTS Start of Defueling: October 1985 9.
PUBLIC MEETING The next meeting of the Advisory Panel for the Decontamination of Three
,1 tilla Island Unit 2 is scheduled for September 11, 1985. The neeting will be at the Environmental flatters Committee Room (Room 160), House Office
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Building, College Avenue, Annapolis, Maryland from 6:00 to 9:00 PM. The purpose of the meeting is to inform the public of progress being made in
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o the Tlil-2 cleanup and to allow the public to voice concerns and make l
comments on any aspects of the cleanup.
The status of the processed water will also be discussed.
Persons desiring the opportunity to speak before the Panel are ' asked to
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contact Mr. Thomas Smithgall at 717-291-1042 or write to him at 2122 i
Itarietta Avenue, Lancaster, Pennsylvania 17603.
OIUGINAL SlODED BYs Wmiam D. Travess l-William D. Travers Deputy Program Director TMI Program Office yr 4
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August 30, 1985 P-Bernard J. Snyder NRC/Tl11-85-067 INTERNAL DISTRIBUTIO!!
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