ML20136H130

Submits TMI Program Ofc Weekly Status Rept for Wk of 851109-17

ML20136H130
Person / Time
Site:	Three Mile Island
Issue date:	11/18/1985
From:	Travers W Office of Nuclear Reactor Regulation
To:	Harold Denton Office of Nuclear Reactor Regulation
References
CON-NRC-TMI-85-091, CON-NRC-TMI-85-91 NUDOCS 8511250039
Download: ML20136H130 (5)

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i November 18, 1985 NRC/THI-85-091

_g, v.c HDiORAUDUM FOR: Harold R. Denton, Director

.- Office of Nuclear Reactor Regulation fl FROM:- William D. Travers, Acting Director mi THI Program Office 7

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SUBJECT:

( NRC TMI PROGRAM OFFICE WEEKLY STATUS REPORT FOR NOVEMBER 9, 1985 - NOVEMBER 17, 1985 q.

~ 1. DEFUEUNG

, Following the successful integrated testing of the defueling canister

& transfer systems in the Reactor Building and the Fuel Building, two fuel 6 canisters were load 2d into the sleeves of the Canister Positioning System

?(. M (CPS). The debris bed in the region of the CPS has been excavated such that the CPS is free to rotate with the canister bottoms at the 308'6" elevation. The Defueling Water Cleanup System (DWCS) is functioning with its four filter canisters installed in the deep end of the fuel transfer

>' canal. On November 12, 1985, General Public Utilities Nuclear (GPUN)-

Corporation received pennission from the NRC onsite staff to load the fuel canisters with fuel debris. Using the vise grip tool, the defueling workers placed into a fuel canister the first piece of debris, a broken piece of fuel rod.- On November 14, 1985, defueling workers picked and placed the first piece of endfitting into the fuel canister.

s Difficulties were encounted with endfittings which are fused together, r

Fused endfittings have to be separated in order to fit into the fuel

' canisters. The licensee is evaluating methods to separate these. fused g; endfittings.

g m A typical defueling team consists of a radiation control technician, two m tool operators, an equipment controls panel operator, a camera operator, G and an NRC licensed fuel handling senior reactor operator who is in

& continuous direct corinunication with the rest of the team. NRC staff ft: observations indicate that licensee performance to date has been f excellent. Defueling operators have demonstrated a thorough knowledge of procedures and safety precautions.

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[. 2. PLANT STATils b

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.

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4 Harold R. Denton 2 flovember 18, 1985

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ffRC/THI-85'-091 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 veosel 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 for defueling.

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 95 F with an average of 83"F.

The average reactor building temperature is 60*F. The reactor building airborne activity at the Westinghouse platform is 1.2 E-7 uC1/cc Tritium and 8.9 E-10 uCi/cc particulate, predominantly Cesium 137.

Spent Fuel Pool "A" is flooded to a depth of 20 feet. About 6 feet of water is over fuel canister storage racks.

3. HASTE t'.ANAGEMEf!T One train of the reactor vessel filtration portions of DHCS was started on flovember 13, 1985. The system operated for about 11 hours1.273148e-4 days <br />0.00306 hours <br />1.818783e-5 weeks <br />4.1855e-6 months <br /> before being shutdown when filter differential pressure reached the procedural limit. It .s believed that the filters plugged micron) particles quickly when initiallyloaded with the very in suspension in the fineRCS. (less than It was 0.5then operated intermittently at reduced flow rates until !!ove.aber 15, 1985. The short period of operation substantially improved the RCS water clarity. The DUCS filter effluent turbidity remained at 0.1 to 0.2 NTV's. On fiovember 15, 1985, the second train was placed in operation.

Processing of batch 126 continues, Fuel Transfer Canal recycle through both Trains and "B" cation sand filter. A total of 181,155 gallons has been processed in batch 126 to-date.

EPICOR II is tenporarily shutdown while changing out liners.

Total volume processed through SDS to date is 3,373,117 gallons, and the total volume processed through EPICOR II is 2,700,737 gallons.

4. DOSE REDUCTION /DECONTN11 NATION ACTIVITIE Decontaminaticn activities are continuing on the 281' level of the auxiliary building. Scabbling of reactor coolant bleed tank cubicles 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.

Decontamination of the pressurizer and "A" D-ring is in progress.

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% Hovember 18, 1985 N HRC/T!!I-85-091

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5. ENVIRONMENTAL' MONITORING ,-

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m; US Environmental Protection Ager.cy (EPA) sample analysis results' show THI' site liquid effluents to be in accordance with regulatory

,'~ A limits,--NRC_ requirements, and the City of Lancaster Agreement.

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. TW, water samples taken by EPA at th.9 plant discharge to the river v cohsisted of seven daily composite samples taken from October 27

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through. November 2,1985. A gamma scan detected no reactor related s - . activity.

N # The Lincaster i water sample taken at the water works. intake and analyzed by EPA' consisted of. a seven day composited sample taken d from October 27 through Novembar 2,1985. A gamma scan detected no 3~ Areactor related radioactivity.

~The HRC outdoor airborne particulate sampler at thet f14I sit *

/ collected a sample between November 7 and November 13, 1985. No

$ reactor related radioactivity was detected. Analysis showed Iodine-131 and Cesium-137 concentrations to be.less than the lower limits of ' dei.actability.

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[6. REACTOR' BUILDIN(i ACTIVITIES p, The initial phase of defueling the* reactor core is in progress. _..

Installation of the vac~ uum defueling system is in progress.

7. AUXILIARYANDFUELHANDLINGBUILDINGACTIVITIES-Installation of the balance DWCS continued.

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Spent Fuel Pool has been flooded to a depth of about 20 feet (about J G feet above the topy of the fuel canister storage racks).

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-8. NRC EVALUATIONS IN PROGRESS

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Technical Specification Change Request number 49. '

Recovery 0perations Plan Change number 31.  %

SDS Technical Evaluation and Systett Description Update. '

. Core Stratification Sample Safety Evaluation. ..

Defueling Water Cleanup Systen Technical Evaluation Report, Revision ,

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Contairst Air Control Envelope Technical Evaluation Report, Revisiod S.

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Solid Waste Facility Techrifcal Evaluation Report, ,

!9.- PUBLI.C'MEETIE s

- s m  % ThYnext ' meeting of the Advisory Fanel is schedulcd!for 11:00 Afl, November 19, 1985, in Washington, DC, before the NRC Comissioners. The

. next meeting in the THI area is scheduled for Decertbar 12, 1985, at the Harrisburg, PA Holiday Inn, 23 South Second Street, Harrisburg, PA, from y 7:00 PH to approximately 10:00 PM. ,

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. Harold RDenton. 4 November 18, 1985 NRC/TMI-85-091 Persons desiring the opportunity to speak before the Panel are asked to contact fir. Thomas Smithgall at 717-291-1042 or write to him at 2122 liarietta Avenue, Lancaster, Pennsylvania 17603.

-signed by P.J. Grant for-7

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Villiam D. Travers Acting Director Tli! Program Office t

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Harold R. Denton 5 November 18, 1985 NRC/THI-85-091

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INTERNAL DISTRIBUTION

~EDO OGC Office Directors Commissioner's Technical Assistants NRR Division Directors NRR A/D's Regional Administrators IE Division Directors y TAS

, EIS X. THI Program Office Staff (10)

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, EPA 4 DOE L< RI Division Directors Public Affairs, RI H- . State Liaison, RI THIP0 HQ r/f -

TMI. SITE r/f CENTRAL FILE HRC PDR LOCAL PDR

THI-2 Project Section File 4

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