IR 05000930/2010006

Submits TMI Program Ofc Weekly Status Rept for Wk of 850930-1006

ML20133G421
Person / Time
Site:	Three Mile Island, 05000930
Issue date:	10/07/1985
From:	Travers W Office of Nuclear Reactor Regulation
To:	Harold Denton, Snyder B Office of Nuclear Reactor Regulation
References
CON-NRC-TMI-85-075, CON-NRC-TMI-85-75 NUDOCS 8510150439
Download: ML20133G421 (5)

Text

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October 7, 1985

NRC/THI-85-075 p- 2,8 i  ;

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s 50- 3g HEliORANDUM FOR: Harold R. Denton, Dfirector

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Office of Huclear Reactor Regulation Bernard J. Snyder, Program Director

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FP,0H: William D. Travers, Deputy Program Director THI Program Office q SUBJECT: NRC THI PROGRAM OFFICE WEEKLY STATUS REPORT FOR

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SEPTEMBER 30, 1985 - October 6,1985

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, PLANT STATUS

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The facility remains in long term cold shutdown with the Reactor

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i Coolant System (RCS) vented to the reactor building atmosphere and

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'y the reactor vessel head and plenum assembly removed from the reactor a: vesse :. -

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

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t 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

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vessel flange and is flooded to elevation 327 feet 6 inches (151 n feet above the top of the core region). The defueling platform is

y installed over the Internal Indexing Fixture in preparation for

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1 defuelin Calculated reactor decay heat is less than 12 kilowatt RCS cooling is by natural heat loss to the reactor building ambient

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atmosphere, Incore thermocouple readings range from 70*F to 91*F with an average of 79 F. Average cold leg temperature will no

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The average reactor building temperature is 56*F. The reactor

,', building airborne activity is 4.8 E-9 uC1/cc Tritium and 1.5 E-10

, , ;.. uCi/cc particulate, predominantly Cesium 137, WASTE MANAGEMENT if -

.The Submerged Demineralizer System (SDS) commenced processing batch 7 124 from neutralizer tanks (WDL-T-8 A/B) to SDS monitor tanks (SDS-T-l'A/3). To date 3,036 gallons from this batch have been

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processe , \> .

'M 8510150439 851007 PDR ADOCK 05000320 R PDR

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c NRC FORM 318 (IO-80) NRCM 0240

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Harold R,,Denton >  % October 7,1935-teni5WIJ. Snyder ~ ~ ' ~

MC/THI-SS-075

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EPICOR II comacaced processing batch 267 frem CC-T-1 to CC-T- To date 16,296 gallons from this batch have been processe Total volume processed through SDS to date is 2,631,270 gallons, and the total volume processed through EPICOR II is 2,96o,411 gallon . DOSE REDUCTIO!l/DECONTAhl4ATION ACTIVITIES

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Decontamination activities are continuing on the 281' level of the auxiliary buildin Average general area radiation dose rate is 40 meen per hour on the 347' level of the reactor building and is 67 mrea per hour on the 305' level of the reactor buildin . STRONTIUM-90 INSPECTION

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A special inspection was conducted on Septercher 30 through October 2,1935 to review the licensee's report that due to nisinterpretation of a calibration procedure, the Strontium-90 (Sr-90) activities reported for some solid waste shipments were one-half the actual activities. The inspectors also reviewed the licensee's efforts to determine the extent of the corrections which may be needed. The licensee agreed to perform an independent assessment of the chemistry Quality Assurance / Quality Control (QA/QC) program; inplement a formalized QA/QC program; ard to assure that all procedures used at TMI-2 for Sr-90 analyses are clear and accurat . ENVIRONMENTAL i;0NITORI!!G

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US Environmental Protection Agency (EPA) sample analysis results show THI site liquid effluents to be in accordance with regulatory linits, NRC requirements, and the City of Lancastar Agreemen TMI water sacples taken by EPA at the plant discharge to the river consisted of seven daily composite samples taken from Septeober 14 through September 21, 1985. A gama scan detected no reactor related activit The Lancaster water sample taken at the water works intake and analyzed by EPA consisted of a sesen day composited sample taken frco Septenber 15 through September 21, 1985. A garna scan detected no reactor related radioactivit The NRC outdoor cirborne particulate sampler at the THI Site collected a sample between September 25 and October 2,1985. Ilo reactor related radioactivity was detected. Analysis showed lodine-131 and Cesium-137 concentrations to be less than the lower limits of detectabilit "'CE > ........... ............. ............ .............. ............. ............. .............

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' NRC FORM 318 00 80) NRCM O240 OFFICIAL RECORD COPY

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ha rol d .D.. Denton 3 ' October 7 1985

-' Bernard J. Snyder tiRC/T111-85-075

^ ~ ~ ~ REACTOR BUILDIliG ACTIVITIES

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Defueling Water Cleanup System (DWCS) preoperational testing and modification continue Work is in progress on the canister positioning systen and canister handling bridg Installation of the vacuum defueling system is in progres . AUXILIARY AND FUEL HANDLING BUILDING ACTIVITIES

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Installation of the D'.lCS continued. Partial DWCS turnover for processing RCS during early defueling is expected to be co@leted in Octobe All four of the fuel canister storage racks have been inspecte Three of the four fuel canister storage racks have been positioned in the spent fuel pool "A" and their position is being adjuste The fourth rack has been installed into the fuel poo . NRC EVALUATIONS IN PROGRESS

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Technical Specification Change Requests numbers 43 and 5 Recovery Operations Plan Change numbers 29, 31, and 3 Fuel Canister Technical Evaluation, Revision Defueling Safety Evaluatio Application for seismic exenptio SDS Technical Evaluation and System Description Updat Core Stratification Sample Safety Evaluatio lieavy Load llandling Safety Evaluation Repor Baron Dilution Hazard Report

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Defueling Water Cleanup System Technical Evaluation Report, Revision flRC Vendors Progran Branch has completed an inspection at Joseph Oat Corporation which is fabricating fuel canisters. A report of the inspection findings will be issued in a few week . PUBLIC MEETING The next meeting of the Advisory Panel is scheduled for October 16, 1935 in Lancaster, Pennsylvania at /:00 Pit. The meeting will be held in the Lancastar Council Chambers at 201 florth Duke Street. Dr.11. Arnold Muller, Secretary, Department of Health will review the results of the llealth Department's recently completed epidemiology studie "'C'> ........... ............. ... ....... . ............. ............. . ........... .............

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P!RC FORM 318 (10 80) NRCM O240 OFFICIAL. RECORD COPY j

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_~11AcqlAJLJenton'p 4 ~ ~0ctober 7, 1985 Bernard .J. Snyder I;RC/TT11-85-01.5 _ . -

Persons desiring the opportunity to speak before the Panel are asked to i contact fir. Thoraas Smithgall at 717-291-1042 or write to him at 2122 i

l!arietta Avenue, Lancaster, Pennsylvania 17603.

casoe w 810p m BY.

1-William D. Travers William D. Travers

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Deputy Program Director 3- Till Program Office j:

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l PSRC FORM 318 (10 80) NRCM O240 OFFICIAL RECORD COPY c

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Harold P.. Denton 5 October 7,1985 Bernard J. Snydcr NRC/Till-85-0/5 INTERiiAL DISTRIBUTION EO OGC Office Directors Coaaissioner's Technical Assistants HRR Division Directors NRR A/D's Regional Administrators IE Division Directors TAS .

EIS Till Prograa Office Staff (10)

PHS EPA 00E RI Division Directors Public Affairs, RI State Liaison, RI TliIPO ilQ r/f Till SITE r/f CENTRAL FILE NRC PDR LOCAL PDR THI-2 Project Section File

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RC FORM 318 (10 80) NRCM 024 OFFICIAL _PECORD COPY 3