ML20154J537
| ML20154J537 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 03/03/1986 |
| From: | Travers W Office of Nuclear Reactor Regulation |
| To: | Harold Denton, Miraglia F Office of Nuclear Reactor Regulation |
| References | |
| CON-NRC-TMI-86-021, CON-NRC-TMI-86-21 NUDOCS 8603100647 | |
| Download: ML20154J537 (5) | |
Text
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! arch 3, 1985 NRC/T;11-86-0?1 f1EMORANDUff FOR:
Harold R. Denton, Director Office of Huclear Reactor Regulation Frank J. fliraglia, Director Division of PWR Licensing-B FRO?l:
Willian D. Travers, Director THI-2 Cleanup Project Diractorate SU3 JECT:
NRC THI-? CLEANUP PROJECT DIRECTORATE WEEKLY STATUS REPORT FOR FEBRUARY 24 - MARCl! 3, 1936
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1.
DEFUELING As of March 3, 1986, 18 defueling ca,isters have been transferred from the reactor vessel to the spent fuel pool storage racks. Total weight of fuel debris and structural material transferred out of tha reactor vessel is about 16,000 lbs. The estinated total weight of fuel debris and structural materials originally in the reactor vessel af ter the accident was 308,000 lbs.
Defueling by pick-and-place with a spide-bucket tool continued.
On February 28, 1986, an operational test of the modified vacuum defueling system was done. The modified nozzle has a larger opening to reduce plugging and uses a water jet to " fluff" the debris bed as in underwater raining operations. During the test, the vacuun system filter canister was bypassed, as previous experience with the system showed rapid plugging of the filtor. The testing showed no improvemn t.
Visibility in the reactor vessel continues to be poor because of biologic growths. To counter the problem, the licensee operated a Tenporary Reactor Vessel Water Filtration Systen. Tho fil tra tion system has baen removed from service because of a need to reevaluate the systen design.
In addition, beginning on March 2,10Rf,, the licensee is exchangirg 55,000 gallons of reactor coolant by a feed-and-bleed opr* ration. The RCS level was drawn down to the vessel flinge level, then refilled to the 3?7' level. Raactor coolant is now being withdrawn to the "B" Reactor Coolant Bleed Tank N
(PC3T) and replenished by borated processed water from the "A" RCBT.
The organic growth in the RCS has progressed to the point where a self-sustaining comunity exists. The growths vary from algae in
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2 March 3, 1986 Frank J. fliraglia flRC/Till-36-021 suspension through fungi and bacteria to aerobic and anaerebic organisms in the low?r vessel. The proposed biocide that was to be used to treat the RCS was shown by laboratory testinq to be ineffective at concentrations that would be acceptable. The licensee continues to study the problen with the assistance of outside experts in the field. A long tern treatment plan is not expected for several weeks.
2.
PLANT STATUS The reactor remains in long tem cold shutdown, vented to atmosphere.
The reactor vessel heid is in storage on the 347' elevation. The plenum is on its storage stand in the deep end of the fuel transfer canal. A dan is installed between the deep and shallow ends of the transfer canil, pemitting a 20 foot depth (about 5 feet nyer the top of the plenun).
Reactor Coolant Systen (RCS) cooling is by natural heat loss to the reactor building atmosphere. Calculated reactor decay heat is 10.7 kilowatts.
Incore thermocouple readings range fron 72*F to 9PF, avnraging 81"F.
The average reactor building tenp 3rature is 55"F.
Th' reactor building airborne activity at the defueling platfom is 2.0 E-8 uCi/cc Trition and 5.4 E-11 UCi/cc particulates, predoninately Cesium-137 The reactor vnsal and modified internals indaxing fixtura are flooded to the 327'6* elevation which is 15} fact above the core region top. Th$ defueling platfom is mounted above the internals indexing fixture.
3.
1.'ASTE MA!!AGEMElli The Submerged Demineralizer Systen (505) continued processing bitch 127. Fuel Transfer Canal Recycle through both trains.
EPICOR II remained shutdown.
Total volunn processed through SDS to date is 3,800,906 qallons, and the total volume processed through EPICOR II is 2.8?2,963 gallons.
4.
RADI0 ACTIVE NATERIAL/k!ASTE SHIPMENT On February 5, 1936, 85 barrels and 4 boxes of ceta"ilnatad loundry were sent to Royersford, PA.
On February 5,1986, Unit I sarples were sent to k!ostwood. 4J, and Rockville, MD, for analysis.
Oa February 12, 1985, 13 barrels and 4 boxes of contaninated laundry were sent to Royersford, PA.
On February 13, 1986, a deplated, dewatered EPICOR II rnsin liner w)s sent to Richland,llA.
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NRC FOHM 318 (10 806 NHCM 024 OFFIClR RECORD COPY
l Harold R. Denton 3
f!irch 3,1936 Frank J. Miraglis '
f1RC/ Trit-85-021 On February 19, 1986, 82 barrels and 2 boxes of conta'ninated laundry were sent to Royersford, PA.
On February 21, 1986, a combined unit waste shipnent was sent to Richland WA. The shipmnt consisted of 60 barrals and 2 boxes.
On February 25, 1936, Unit 1 sanples were sent to Westwood, NJ and Rockville, itD for analysis.
On February 26, 1985, 83 barrels and 4 boxes of contaminated laundry were sent to Royersford, PA.
5.
DOSE REDUCTION /0EC0ftTNilflATT0fl Average general area radiation dose rate is 40 nren per hour on tho 347' level of the reactor building and is 67 nran per hour on the 305' level of the reactor building. The average dose rate to workers on the defueling work platfern is 8 nren per hour.
6.
EllVIRC'lMEflTAL it0'llTORif;G US Environmental Protection Agency (EPA) sanple analysis results show T:1I site liquid effluents to be in accordance with regulatory limits, f!RC require.vnts, and the City of Lancaster Agrantv.at.
Ti!I water sanales taken by EPA at the plant discharge to the river consisted of seven daily compcsite samples talten fron Februarv 8 through February 15, 1935. A gma scan detrcted no reactor related i
activity.
The Lancaster water smple taken at the water works intake and l
analyzed by EPA consisted of a sevan day composited sample takan i
from Fcbruary 9 through February 15, 1936. A gaan scan detected no reactor related radioactivity.
The NRC outdoor airborne pirticulate sampler it the Till site l
collected a sanple between February 19, and Februiry 26, 1936. fio reactor related radioactivity was detectad. Analysis showed Iodine-131 and Cesium-137 concentrations to be less th3n the Iowar limits of detectability.
7.
REACTOR GUILDifiG ACT!YITIES Initial defueling of the reactor core is in progress.
l 8.
AUXILif#Y AjlD FifEL llANDLillG BUILDING ACTIVITIES Installation of tha balance of Dafueling Water Claanup Systen (0WCS) continued.
Propirations are being mde for decnntaninstion in the Seal injection Room, 281' auxiliary building.
Kelly vacuuaing of the Pat' elevition tuel handling building continund.
Startup testing of the canister dewitoring systen is in progress.
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OFFICIAL RECORD COPY j
O Harold R. Denton 4
flarch 3, 1986 Frank J. Itiraglia NRC/Till-86-021 9.
NRC EVALUATI0flS IN PROGRESS Technical Specification Change Request number 49.
Recovery Operations plan Change number 31.
SDS Technical Evaluition and Systen Description Update.
Core Stratification Sample Safety Evaluation.
Defueling Water Cleanup Systen Technical Evaluation Report, Revision 7.
Containment Air Control Envelope Tr.chnical Evaluation Report, Revision 5.
Solid Waste Facility Technical Evaluation Report.
Reactor Building Sump Criticality Safety Evaluation Report.
Original signed by John Thomas for:
hillian D. Travers Director T?II-2 Cleanup Project Directorate
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'NRC/THI-8G-021
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