ML20151Y787
| ML20151Y787 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 02/03/1986 |
| From: | Travers W Office of Nuclear Reactor Regulation |
| To: | Harold Denton, Miraglia F Office of Nuclear Reactor Regulation |
| References | |
| CON-NRC-TMI-86-011, CON-NRC-TMI-86-11 NUDOCS 8602130157 | |
| Download: ML20151Y787 (5) | |
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.r Yf February 3,1985 NRC/THI-86-011 MDiORANDutt FOR:
Harold R. Denton, Director Office of Nuclear Reactor Regulation Frank J. Hiraglia, Director Division of PWR Licensing-B FRCH:
William D. Travers, Director TMI-2 Cleanup Project Directorate
SUBJECT:
NRC THI-2 CLEANUP PROJECT DIRECTORATE WEEKLY STATUS REPORT FOR JANUARY 27 - FEBRUARY 2, 1986 1.
DEFUELING The licensee had intended to perform a video inspection of the void E,
remaining after removing an 8 fcot long section of fuel assembly P-4 (refer to Weekly Status Report dated January 27,1935). This will not be feasible, as adjacent rubble has fallen into and nearly filled the void. A future attempt will be made to dislodge an intact peripheral assembly, access the void with a camera, and assess the core conditions beneath the rubble pile.
The licensee has increased the actual defueling time from 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> per day to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> by using three defueling teams instead of two teams per day.
It is expected that next week, the licensee will increase to four teams per day.
A debris bucket hanger has been installed on the hfelded work platform that allows an attached debris bucket to follow the platform's rotation. This alleviates the need to reposition the in-use debris bucket each time the platform is rotated.
.Four side-loading debris buckets were filled this week. Three of c
them were filled to an average underwater weight of about 70 lbs with sections of fuel pins. A fourth weighed 500 lbs.
The two new filters installed in the "B" train of the Defueling Water Cleanup Systems (DWCS) have become plugged after a throu';hput of only 45,000 gallons. The licensee is still studying the arcblems
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of biological growth in the reactor coolant system which is )elieved cy, 3 to be causing the f11ter plugging.
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February 3,1986 Frank J. Miraglia NRC/THI-S$-011 2.
_ PLANT STATUS The facility remains in long tem cold shutdcun with the Reactor Coolant System (RCS) vented to the reactar building atmsphere and the reactor vessel head and plenum assembly renoved from the reictor vessel.
The plenum is on its storage stand in the deep end of the fuel transfer canal. A dan has been installed betu3en the deep and shallow ends of the fuel transfer canal. The deep ond is filled with water to a depth of about 20 feet (about 5 feet above the top of the plenum).
The nodified internals indexing fixture is installed on the reictor 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 less than 12 kilowatts.
RCS cooling is by nature.1 heat loss to the reactor building imbient atmosphere.
Incore themoccuple readings range froin 73'F to 95"F with an average of 82'F.
The average reactor building temperature is 58"F.
The retctor building airborne activity at the Westinghouse platfom is 1.5 E-7 uC1/cc Tritium and 5.4 E-11 uCi/cc particulate, predoninantly Cesiua 137.
Spent Funl Poal "A" is flood'd to a depth of 20 feet. About C feet of water is over the fuel canister storaqe racks.
3.
!!ASTE MANAGE!iEH, The Submrged Deninaralizer System (SDS) and EPICOR II were shutdawn this week.
Total volume processed through SDS to date is 3,5%,397 gillons, and the total volume processed through EPIC 0p II is 2,822,963 gallons.
The "A" train of the D'.lCS was started up to filter the RCS at about 6:15 PM, February 1, 1986.
About 90 ninutes later, the oper',p well.
ting puap shutdown automtically due to low water level in tha pu The operators noted a slight decrease in RCS level and mnu. illy secured the systen.
Investigation detemined that a hose supplying water from the pump discharge manifold to the filters h3d ruptured, causing leakaga of about 600 gillons of water from the PC3 to tha fuel transfer canal.
The ruptured hose was replaced and the systen restarted. The system response to the hose rupture was as designed, and the casualty caused no radiological hizards or uncontained spills. The cause of the hose rupture is under investiqation.
4.
RADI0 ACTIVE I4ATERIAL/rIASTE SHIP !E!!TS Contminated laundry was sent to Royersford, PA in th?se quantitias in.lanuary 1986:
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Harold R. Denton 3
February 3,1986 Frank J. Miraglia flRC/T 11-86-011 January 2, 44 druns a nd 1 box January 7, 42 drums and 5 boxes January 15, 69 drums January 22, 69 druns and 2 boxes January 28, 67 drum? and 4 boxes Combined unit non-conoacted waste in 16 steel boxes was sent to disposal at Richland, !!A ot,.]ariuary 3.
A Unit 2 shipment of fuel rod segments was sent in a shielded cask to Scoville, ID cn January 10 A Unit 1 monthly liquid sample was sent to Rockville, !!0 for analysis on January 13.
A Unit 2 shipment of a whole body counter radioactive calibration source was sent to Susquehanna Stcan Electric Station on January 14 A Unit 2 reactor coolant waste sample was sent to Pittsburgh, PA on January 16 A combined unit shipment of radioactive waste in 107 drums was sent to disposal at Richland, ilA on January 24.
5.
DOSE REDUCTI0'l/DEC01TA'11NATIOri Decontanination flusing of the 231' annulus area is in progress.
Average general area radiation dose rate is 40 nren per hour on the 347' level of the reictor building and is 67 nren per hour on the 305' level of the reactor building. The averige dose rate to workers on the defueling work platform is a teen par hour, 6.
EfiVIRON::EitTAL I 0iiITORIltG US Environnental Protection Agency (EPA) sample analysis results show Ti11 site liquid effluents to be in accordance with regulatory linits, iiRC requironents, and th? City of Lancaster Agreenent.
Ti!! water samples taken by EPA at the plant discharqe to the river consisted of seven daily composite sanples taken fron January 11 through January 18, 1936. A gan,a scan detected no reactor related activity.
The Lancaster water smple taken at the water works intake and analyzed by EPA consisted of a seven day cor1 posited sample taken fron January 12 through January 18, 1985. A ganro scin detected no reactor relatrd r1dioactivity.
The imC outdoor airborne particulate sampler at the TMI site collected a sanole betwean January ??, and Janu3r/ 29,1986, tio reactor related radioactivity was detected. Analysis showed Iodina-131 and Cesiun-137 concentrations to ba less than the lower limits of detectability.
7.
RECTOR mlILDIliG ACTIVITIES Initial defueling of the reactor cor" is in progress.
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Febnnry 3,1986 Frank J. iliraglia IFIC/TMI-86-011 8.
AUXILIARY AflD FUEL HAtlDLitlG BUILDifiG ACTIVITIES Installation of the balance of DMCS and canister dowatering system 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.
_fiRC EVALUATIONS Ifl PROGRESS _
Technical Specification Change Request number 49.
Recovery Operations Plan Change number 31.
SDS Technical Evaluation and System Description Update.
Core Stratification Sample Safety Evaluition.
Defueling thter Cicanup System Technical Evaluation Report, Revision 7.
Containmant Air Control Envelope Technical Evaluition Renart, Revision 5.
Solid Maste Facility Technical Evaluation Report.
Reactor Building Sunp Criticality Safety Evaluation Roport.
- 10. PUBLIC flEETitlGS The next m?oting of tho Advisory Panel is scheduled for February 19, 1996 at the Holiday Irn, 23 South Second Street, Harrisburg, PA f rom 7:00 Pli to 10:00 PM.
At this pecting the Panel will receive a presentation by tn, US Department of Enered (00E) on plans for tha shipmnt of fuel removed f rom the damaged THI-2 reactor to a DOE facility for interin storaqe.
Tha Panel will also receive a status report on the progress of defueling fron
.GPU f;uclear Corporation. fla.abers of the public will be given tha opportunity to address the Panel.
On January 29, 1985 in Washington, D.C., representatives from GPU,'l and the flRC staff, in separate presontations, provided a briefing on THI-2 recriticality issues to the Advisory C'mittee on Reactar Safeguards (ACRS) Subenmittee on Core Performance.
The ACRS full cemittee will be briefed en February 13,1985 (3:15 PH - 5:15 PM) at fiRC offices at 1717 H Streat,'hshington D.C.
Persons d? siring the opportunity to speak befora th? Advisory Panal are asked to contact Mr. Thoms Snithgall at 717-291-1042 or write to him at 2122 lbrietta Avenua, Lancaster, Pennsylvania 17603.
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