ML20137G768

TMI-2 Cleanup Project Directorate Weekly Status Rept for 860105-12

ML20137G768
Person / Time
Site:	Three Mile Island
Issue date:	01/13/1986
From:	Travers W Office of Nuclear Reactor Regulation
To:	Harold Denton, Miraglia F Office of Nuclear Reactor Regulation
References
CON-NRC-TMI-86-004, CON-NRC-TMI-86-4 NUDOCS 8601210204
Download: ML20137G768 (6)

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gp , January 13, 1986 NRC/TMI-86-004 w" HEl10RANDUM FOR:. Harold R. Denton, Director Office of Nuclear Reactor Regulation w

g Frank J. Miraglia Director V- Division of PWR Licensing-B y

FROM: Willian D. Travers, Director K[ THI-2 Cleanup Project Directorate e

SUBJECT:

NRC THI-2 CLEANUP PROJECT DIRECTORATE HEEKLY STATUS p _ REPORT FOR JANUARY 5 - 12, 1936 3

h3 1. DEFUELING - First Core Debris Removed from Reactor Vessel

't On January 12, 1986, at approximately 1:00 PH, the licensee transferred the first three loaded fuel canisters out of the Reactor Building (RB) into the Fuel Handling Building (FHB). The canisters were, beginning on a October 30, 1985, loaded with core debris (e.g., end-fittings, . control

_p rod spiders, fuel pins). The canisters were sealed. dewatered and

'. individually transferred from the reactor vessel by a snielded canister

1. handling bridge to tb fuel transfer canal inside the RB. The canisters were then transported to the FHB via a modified fuel transport system and ec placed in underwater fuel canister storage racks located in the "A" fuel i6 ' pool. The highest direct radiation level on the surface of the transfer ,

P: shield during transfer was 20 mR/hr. There was no increase in airborne  :

!? contamination levels in the RB and FHB as a result of these activities.

NRC site radiation specialist inspectors witnessed the transfer

, P. activities.

, Q' 1. On January 6,1985, GPUN completed initial performance testing of the vacuum defueling' system. The knock-out (K/0) canister, as measured on January 9,1986, had a gross weight of 1,880 lbs. whicn corresponds to a

.. net fuel debris loading of about-1,500'lbs. Loading of the finer debris in the filter canister is only about 20 to 30 lbs. b addition, the gf- differential pressure across the filter canister increased towards the '

end of the vacuuming test, restricting the vacuuming flow rate to below f<e U -

100 gpm. The filter canister was bypassed during the final two hours of

_ the test. Waf.er clarity degraded when the filter canister was bypassed.

Overall, the test successfully demonstrated the ability to load debris.

4 although the debris pickup rate and the filter canister performance tere -

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'less than expected. The licensee.is evaluating modifications'to-improve-

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A _ On January 8.1986, GPUN compinted loading fof- fuel canister D-139 with 9; -fuel assembly end-fittings. This is the canister involved in the g

W t inadvertent drop event (see Weekly'. Status Report of. 12/9..12/15,'1985).

-Loading of this canister has been-restricted to those end-fittings with -

.M ino attached fuel rods; On: January 9,1986,.GPUN- completed loading of' ~

v fuel canister D-140. Each fuel canister contains about 350 lbs, of- _

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%@ex ~ material consisting of 12 pieces of end-fittings and control rod spiders. '

!;[ .By January 10, 1986,- there were four loaded fuel canisters 'and one loaded -

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- K/0 canister in the Canister Positioning ' System inside the. reactor.

vessel. On January 12,~ 1986, three of the. fuel canisters were closed,

dewatered, and transferred to the storage . racks in the "A" spent fuel l{ pool.

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2.. PLANT STATUS '

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The' facility remains in long term cold shutdown with the. Reactor Coolant System (RCS)' vented to the. reactor' building atmosphere and Is' the reactor vessel: head and plenum assembly removed from the reactor -

% vessel.

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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 C with water to a' depth of about 20 feet (about 5 feet above thel top  :

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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 61.nches -(150 "

'A feet above the top of the core region). . The defueling platfom is .

M installed over the internals indexing fixture.

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Calculated reactor decay heat'is less than 12 kilowatts. _

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RCS cooling is by ' natural heat loss to the reactor building ambient-1 W atmosphere. Incore thermocouple readings range from 68'F to 95'F -

pf with an average of 82*F. _

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The average reactor building temperature is 57'F. The reactor. 1

[ building airborne activity at the Westinghouse-platform is :3.4 E-8 "

jn uCi/cc Tritium and 1.6 E-10 uC1/cc' particulate, predominantly Cesium N -137.

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iQ - Spent Fuel Pool "A" is flooded to a depth of 20 feet.t About.6 feet n

of water is over the fuel canister storage racks. -i

,3- -3. WASTE MANAGEMENT. -

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- vThe Submerged Demineralizer System (SDS) and.EPICOR II remained -

shutdown this week.

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. Total volume processed through SDS. to date is 3,598,397 ga17ons, and j

the total volume processed through~EPICOR:II_is.2,776,536 gallons..

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4 4. RADI0 ACTIVE MATERIAL / WASTE SHIPMENTS sth

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On December 2,1985, three Unit.2 shipments consisting of. depleted

& EPICOR II resin liners in. shields were sent to U.S. Ecology, 8 Richland, WA for burial.

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On December 4,'1985, ~a ccmbined unit contaminated . laundry shipment 41% of 44 drums and 3 boxes were:sent .to Royersford, PA.' .

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On December 5, 1985, a-Unit 2.. advance notification-shipment was_sent; }

IM, to U.S.L Ecology, Richland, WA for burial.. '

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On December 6,1985, a Unit 2 sample shipment of electrical .. ,

'2' . equipment was _ sent to Westinghouse - Hanford, Richland,-WA for ' ;'

examination.

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On December 9,1985, two Unit 2 shipments consisting of depleted

!K EN EPICOR II' resin liners in shields were_sent to U.S. Ecology, Richland, WA for burial.  ;

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On December 9.1985, a Unit I shipment-(dry solid waste) was sent to' PP U.S. Ecology, Richland,'WA for disposal. ,

}; c On' December 9,1985, a Unit 1 shipment (twoLsolidified evaporator .

ij- bottoms) was sent to Barnwell, SC for disposal.

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On December 10, 1985, Unit 1 liquid samples were sent to Rockville,

{g1 MD for analysis. .' '

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On December 10, 1985, a combined unit contaminated laundry shipment W

of 49 drums and 2 boxes was sent to Royersford, PA.-  ;

!4 On December 10,1985, a Unit 2 shipment' consisting of an EPICOR II;

'W resin liner was sent to U.S. Ecology, Richland WA for burial. -

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U On December 11, 1985, a Unit 2 shipment-(a depleted EPICOR IILresin_

liner) was sent to Richland, WA for burial. -;

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On December 12, 1985, a Unit 1. gas sample was'sent:to Rockville, MD-MJ for analysis.

Q On December 13, 1985, a Unit 2 shipment (an' EPICOR II. depleted-resin *

,b liner) was sent to Richland, WA for Durial. -

3h OnDecember-16,1985,'aUnit2-shipment'(anEPICORII'depletedresinn liner) was se.it to Richland, WA foriburial. -

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On December 18, 1985, a combined unit shipment of 81, drums and.4 =  :.

iX boxes of contaminated laundry was sent- to Royersford, PA..

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On December 19, 1985, a combined unit; shipment of 16 steel-boxes.of jf contaminated waste ras sent to Richland, WA for burial. _

On December 19, 1985, a combined unit shipment consisting of six; p steel boxes and three depleted resin, liners was Lsent to Richland, WA  :

.C for burial. ' '

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On December 20, 1985,. a combined unit shipment of 117 drums was senti

!?A to Hanford, WA for burial. *

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On December 20, L1985, a combined unit shipment of,72 dnses was sent 97 . to Richland, WA for burial.

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On December. 26,11985,'a Unit .1 shipment (miscellaneous li, quid

& samples) was sent to San Jose,L CA for analysisi On December 26,l1985, a combined unit shipment of contaminated gi: ' laundry of 57 drums and 2 boxes was sent to Richland,.WA for burial.' _

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y H:rold R. Dentrn 4 Janaury 13, 1986 Frank J. Miraglia NRC/TMI-86-004 I

, 5. DOSE REDUCTION / DECONTAMINATION Decontamination activities are continuing on the 281' level of the auxiliary building. Kelly-vac cleaning of the decay heat vaults is in progress.

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.

6. ENVIRONMENTAL MONITORING US Environmental Protection Agency (EPA) sample analysis results show TitI site liquid effluents to be in accordance with regulatory limits NRC requirements, and the City of Lancaster Agreement.

Ti1I water samples taken by EPA at the plant discharge to the river consisted of seven daily composite samples taken from December 21 through December 28, 1985. A gamma scan detected no reactor related activity.

The Lancaster water sample taken at the water works intake and analyzed by EPA consisted of a seven day composited sample taken from December 22 through December 28, 1985. A gama scan detected no reactor related radioactivity.

The NRC outdoor airborne particulate sampler at the T!!I site collected a sample between January 2, and January 8,1986. No reactor related radioactivity was detected. Analysis showed Iodine-131 and Cesium-137 concentrations to be less than the lower limits of detectability.

7. REACTOR BUILDING ACTIVITIES Initial vacuum defueling of the reactor core is in progress.

The pressurizer manway cover has been removed and the access port shielded. Sludge samples have been removed from the pressurizer and further examination is in progress.

8. AUXILIARY AND FUEL HANDLING BUILDING ACTIVITIES Installation of the balance of DWCS continued.

Spent Fuel Pool "A" has been flooded to a depth of about 20 feet (about 6 feet above the top of the fuel canister storage racks).

9. NRC EVALUATIONS IN PROGRESS Technical Specification Change Request number 49.

Recovery Operations Plan Change number 31.

SDS Technical Evaluation and System Description Update.

Core Stratification Sample Safety Evaluation.

Defueling Water Cleanup System Technical Evaluation Report, Revision 7.

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Harold R.-Denton .5 lJanaury 13, 1986 Frank J. Miraglia NRC/TMI-86-004 L

3E Containment Air Control Envelope Technical Evaluation Report,-

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Solid Waste Facility Technical Evaluation Report.

I 10. PUBLIC !!EETINGS On January 8,1986, William D. Travers, Director of the Till-2 (p Cleanup Project Directorate, gave a presentation on rfsk assessment y; to the GPUN Education Advisory Panel. The panel is composed of educators from the Harrisburg area who review GPU educational

'O programs proposed to be presented in area schools.

The next meeting of the Advisory Panel is scheduled for February 12e 1986 at the Holiday Inn, 23 South Second Street, Harrisburg, PA from 7:00 PM to 10:00 PM.

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Persons desiring the opportunity to speak before the panel are asked to contact Mr. Thomas Smithgall at 717-291-1042 or write to him at 2122 Marietta Avenue, Lancaster, Pennsylvania 17603.

guad4Ai. 200m sire Wimm D. Traers William D. Travers Director THI-2 Cleanup Project Directorate Y

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