ML20198B547
| ML20198B547 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 10/28/1985 |
| From: | Travers W Office of Nuclear Reactor Regulation |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| CON-NRC-TMI-85-081, CON-NRC-TMI-85-81 NUDOCS 8511060519 | |
| Download: ML20198B547 (4) | |
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.o October 28, 1985 tiRC/THI-85-081 HEHORANDUM FOR:
Harold R. Denton, Director Office of fluclear Reactor Regulation FROM:
William D. Travers, Deputy Program Director THI Program Office
SUBJECT:
itRC TMI PROGRhi 0FFICE WEEK!.Y STATUS REPORT FOR
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OCTOBER 21, 1985 - October 27, 1985 1.
PLANT STATUS The facility remains in long term cold shutdown with the Reactor Coolant System (RCS) vented to the reactor building atmosphere and 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 i
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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).
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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 preparation for defueling.
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Calculated reactor decay heat is less than 12 kilowatts.
RCS cooling is by natural heat loss to the reactor building ambient atmosphere.
Incore thennocouple readings range from 72*F to 95'F L
with an average of 83*F.
The average reactor building temperature is 56*F. The reactor i
c building airborne activity is 4.4 E-8 uCi/cc Tritium and 3.7 E-10 t
uCi/cc particulate, predominantly Cesium 137.
1 Spent Fuel Pool "A" is flooded to a depth of 20 feet. About 6 feet of water is over fuel canister storage racks.
2.
WASTE MANAGEMENT
~J" The Submerged Demineralizer System (SDS) commenced processing batch
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125, Fuel Transfer Canal through Train fio.1. To date a total of A
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33,940 gallons has been processed.
gp EPICOR II is temporarily shutdown while changing out liners.
F-Total volume processed through SDS to date is 3,022,533 gallons, and [/gj,b(
the total volume processed through EPICOR II is 2.700,737 gallons.
10 CFR 61.55 Exemption approval was given by flRC which authorized the licensee to classify EPICOR II liners containing 1 microcuries per cubic centimater of Strontium 90 as Class A waste.
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Harold R. Denton 2
October 28, 1985 Bernard L Snyder - -
liRC/Tl11-85-081 3.
DOSE REDUCTION /DECCliTAMIllATION ACTIVITIES Decontaninatio9 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 mren par hour on the 305' level of the reactor building.
Removal of insulation and decontamination of the pressurizer is in progress.
4.
ErlVIR0ffi!EllTAL M0fiITORifiG US Environmental Protection Agency (EPA) sample analysis results show Till site liquid effluents to be in accordance with regulatory limits, flRC requirements, and the City of Lancaster Agreement.
Till water sampics taken by EPA at the plant discharge to the river consisted of seven daily composite samples taken from October 5 through October 12, 1985. A ganna scan detected no reactor related activity.
The Lancaster water sample taken at the water works intake and analyzed by EPA consisted of a sevan day composited sample taken from October 6 through October 12, 1985. A gaan scan detected na reactor related radioactivity.
The flRC outdoor airborne particulate sampler at the Ti1I Site collected a sample between October 16 and October 23, 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.
DEFUELIrlG OPERATI0 tis TO BEGIri The initial phase of defueling the damaged reictor core at Three Mile Island Unit 2 is scheduled to begin this week.
The defueling will involve the use of specially designed tools and equipment and 1
will be performed by operators specially trained and licensed by liRC in defueling procedures. This phase of defueling will involve manipulation of the partial fuel assemblies in preparation for loading into canisters designed for storage and shipment of the damged fuel. Shipping of the loaded canisters by rail to the Idaho flational Engineering Laboratory is scheduled for next spring.
6.
REACTOR BUILDIllG ACTIVITIES Defueling Water Cleanup System (DWCS) preoperational testing and modification continued.
Installation of the vacuum defueling system is in progress.
Work is in progress on the canister positioning system.
Conister handling bridge indexing and load testing is in progress.
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H:rold R. Danton -
3 October 28, 1985 Bernard r S~nyder hRC/TMI-85-081 7.
AUXILIARY AND FUEL llAflDLING BUILDING ACTIVITIES Installation of the DWCS continued. Partial DUCS turnover for processing RCS during early defueling is expected to be completed in October.
Spent Fuel Pool has been flooded to a depth of about 20 feet (about 6 feet above the top of the fuel canister storage racks).
8.
liRC EVALUATI0llS Ill PROGRESS Technical Specification Change Requests nunber 48, 49, 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.
lieavy Load Handling Safety Evaluation Report.
Defueling Water Cleanup Systen Technical Evaluation Report, Revision 7.
Early Defueling Safety Evaluation Report, Revision 4.
Containment Air Control Envelope Technical Evaluation Report, Revision S.
9.
PUBLIC itEETING L
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The next raeeting of the Advisory Panel is scheduled for 11:00 AM, l
November 19, 1985, in Washington, DC, before the NRC Comissioners. The i
next meeting in the Till area is scheduled for Decenber 12, 1985, at th?
l Ilarrisburg, PA Holiday Inn, 23 South Second Street, Harrisburg, PA, from j
7:00 Pil to approximately 10:00 Pfl.
j Persons desiring the opportunity to speak before tha Panel are asked to i
contact lir. Thomas Snithgall at 717-7.91-1042 or write to him at 2122 itarietta Avenue, Lancaster, Pennsylvania 17603.
onioNM SiONED We I
William D. Travers Williara D. Travers Deputy Program Director T!11 Program Office I
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liarold R. Denton 4
October 28, 1985
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Bernard J. Snyder NRC/TMI-85-081
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