ML20138L276
| ML20138L276 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 12/16/1985 |
| From: | Travers W Office of Nuclear Reactor Regulation |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| CON-NRC-TMI-85-099, CON-NRC-TMI-85-99 NUDOCS 8512190220 | |
| Download: ML20138L276 (5) | |
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.pn e-lhj Decenter 16, 1985 NRC/THI-85-099 HEHORANDUM FOR:
Harold R. Denton, Director Office of Nuclear Reactor Regulation m
Frank J. Miraglia, Director i
Division of PWR Licensing-B x'
FROM:
William D. Travers, Director c
THI-2 Cleanup Project Directorate r
SUBJECT:
NRC TilI-2 CLEANUP PROJECT DIRECTORATE WEEKLY STATUS REPORT FOR DECEMBER 9,1985 - DECB18ER 15,1935
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1.
DEFUELING g;
N On December 11, 1985, the licensee completed filling the first fuel canister.
It was filled with approximately 350 lbs. of debris consisting of about 12 pieces of fuel assembly end-fittings, control rod spiders,
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.f and small pieces of partial fuel assemblies. The exact weight of the sc loaded debris will be measured when the canister is closed, dewatered, P
and readied for transfer out of the reactor vessel. Filling of the second fuel canister was completr I on the morning of December 14. It contains about 9 end-fittings anc pieces of partial fuel assemblies.
e Filling of the third fuel canister began on December 14. At about 7:30 Pfl on December _14, with the canister about half-filled, an end-fitting was inserted into the canister and appeared to jam before being fully lowered into the canister. Operators attempted 7
unsuccessfully to tap the stuck end-fitting into the canister with a long handled tool. They then attempted to remove the end-fitting by grappling it with a J-hook attached to the one ton jib crane. When lifting with q-
- the crane, the canister positioning system (CPS) canister sleeve I
apparently became unlatched, the canister and sleeve lifted out of the W
CPS and dropped about 11 feet to the debris pile. On December 15, after R
special training for the evolution, the canister and sleeve were B
retrieved using the 5 ton service crane and was successfully reinstalled
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in the CPS. Preliminary video survey showed no damage to the cenister.
Z the sleeve, or the CPS. However, load cells on the 5 ton service crane M
1r.dicated a dead weight of the canister and sleeve of about 2200 lbs.
Thus, the one ton rating of the jib crane may have been exceeded. The jib crane (one of two) has been removed from service. This event is T
under review by the licensee and the NRC staff to assess any damage to V
the CPS and corrective actions to prevent future recurrence.
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liarold R. Denton 2
December 16, 1985 Frank J. Miraglia NRC/THI-35-099 A video survey of the core has determined that there are about 40 standing peripheral fuel assemblies with their end-fittings attached. About 40 to 50 single end-fittings were seen in the debris bed. The remainder of the 177 end-fittings are either fused together in aggregates of 2 to 4 or are hidden from view under other debris. The licensa does not believe that the presence of the fused end-fittings will hinder access for the vacuum defueli19 test.
The licensee expects to test the vacuum defueling system in the reactor vessel in early January 1986.
2.
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 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 vessel flange and is flooded to elevation 327 feet 6 inches (151 feet above the top of the core region). The defueling platfom is installed over the internals indexing fixture.
Calculated reactor decay heat is lese than 12 kilowatts.
RCS cooling is by natural heat loss to the reactor building ambient atmosphere.
Incore thermocouple readings range from 63*F to 93 F with an average of 82.5*F.
The average reactor building temperature is 57'F.
The reactor building airborne activity at the Westinghouse platfom is 6.2 E-8 uC1/cc Tritium and 2.6 E-10 uCi/cc particulate, predominan'tly Cesium 137.
Spent Fuel Pool "A" is flooded to a depth of 20 feet. About 6 feet of water is over the fuel canister storage racks.
3.
WASTE MANAGEMENT The "B" train of the DWCS reactor vessel filtration system was operated at reduced flow intermittent as needed to naintain RCS clarity for defueling operations. The licensee is still studying the DLlCS filter fouling problems and is planning to conduct tests to evaluate the use of filter precoat materials to alleviate the problem.
Submergad Demineralizer System (SDS) is temporarily shutdown.
EPICOR II is temporarily shutdt while changing out liners.
Total volume processed through SDS to date is 3,598,397 gallons, and the total volume processed through EPICOR II is 2,700,737 gallons, enCE >
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OFFICIAL RECORD COPY
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" Harold R..Denton 3
December 16, 1985 Frank J. Miraglia NRC/TMI-85-099 4 -
4.
DOSE REDUCTION /DECONTAf11 NATION ACTIVITIES Decontamination activities are continuing on the 281' level of the auxiliary building. Scabbling of reactor c. slant bleed tank cubicles is completed.
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 "A" D-ring is in progress.
Preparations are in progress to Kelly-Vac the auxiliary building elevator pit and the underside of the elevator car.
5.
ENVIRONMENTAL MONITORING US Environmental Protection Agency (EPA) sample analysis results show Till site liquid effluents to be in accordance with regulatory limits, NRC requirements, and the City of Lancaster Agreement.
TMI water samples taken by EPA at the plant discharge to the river consisted of seven daily composite samples taken from November 23 through November 30, 1935. 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 November 24 through November 30, 1985. A gamma scan detected no reactor related radioactivity.
No sample was collected by the NRC outdoor airborne particulate sampler at the TMI Site during this period due to personnel error in sampler operations. A thorough review of plant strip chart recorders by NRC personnel determined that there were no abnormal
. releases of radioactivity from the site.
6.
REACTOR BUILDING ACTIVITIES The initial phase of defueling the reactor core is in progress.
Installation of the vacuum defueling system is in progress.
The pressurizer manway cover has been removed, the access port shielded, and TLD's and cameras lowered into the pressurizer.
Preliminary video and TLD surveys indicated that there is little fuel deposition in the pressurizer.
Further examination 'is in t
progress.
7.
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).
q 8.
NRC EVALUATIONS Ill PROGRESS Technical Specification Change Request number 49.
- Recovery Operations Plan Change _ number 31.
NRC FORM 318 (1080) NRCM 0240 OFFICIAL _ RECORD COPY.
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' Harold R. Denton 4
Deceaber 16, 1985 Frank J. Miraglia NRC/THI-35-099 SDS Technical Evaluation and System Gescription Update.
Core Stratification Sample Safety Evaluation.
Defueling Water Cleanup System Technical Evaluation Report, Revision 7.
Containment Air Control Envelope Technical Evaluation Report, Revision 5.
Solid W4ste Facility Technical Evaluation Report.
9.
PUBLIC MEETINGS The Adviscry Panel for the Decontamination of Three !!ile Island Unit 2 net on December 12, 1985. At the meeting the panel heard a presentation by fir. and firs. Aamodt on health effects in the area surrounding the Three flile Island (THI) facility. The Aamodts criticized the Pennsylvania State Department of Health and its recent study of cancer incidence around THI.
The panel also received briefings from GPUll on progress of the cleanup and from the flRC staff on the status of regulatory activities. Members of the public were afforded an opportunity to coinnent on cleanup related issues.
The next meeting of the panel is scheduled for February 12, 1986 in tha liarrisburg area from 7:00 p.m. to 10:00 p.m. at a place to be determined.
ORIGNAE SIONED Bis William D. Trouess Uilliam D. Travers Director TMI-2 Cleanup Project Directorate t
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Harold R. Denton 5
Decer,ber 16, 1985
- Frank J. Miraglia NRC/T41-85-099 l
INTERNAL DISTRIBUTIOrt EDO OGC Office Directors Conmissioner's Technical Assistants NRR Division Directors NRR A/D's Regional Administrators IE Division Directors TAS EIS THI Cleanup Project Directorate (10)
PHS EPA DOE RI Division Directors Public Affairs, RI State liaison, RI TMIPO HQ r/f TMI SITE r/f CEllTRAL FILE NRC POR LOCAL PDR Till-2 Project Section File OF FICE p TM l
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