IR 05000831/2009008
| ML20135D781 | |
| Person / Time | |
|---|---|
| Site: | Crane, 05000831  |
| Issue date: | 09/09/1985 |
| From: | Barrett L Office of Nuclear Reactor Regulation |
| To: | Harold Denton, Snyder B Office of Nuclear Reactor Regulation |
| References | |
| CON-NRC-TMI-85-069, CON-NRC-TMI-85-69 NUDOCS 8509160184 | |
| Download: ML20135D781 (5) | |
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September 9, 1985 NRC/THI-85-069 MEHORANDUM FOR:
Harold R. Denton, Director Office of fluclear Reactor Regulation Bernard J. Snyder, Program Director THI Program Office FR0it:
William D. Travers, Deputy Program Director TM1 Program Office SUBJECT:
NRC THI PROGR#1 0FFICE WEEKLY STATUS REPORT FOR AUGUST 31, 1985 - SEPTEMBER 8, 1985 1.
PLANT STATUS The facility remains in long term cold shutdown with the Reactor
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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
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transfer canal. A dan 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 oftheplenum).
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 feet above the top of the core region).
Calculated reactor decay heat is less than 12 kilowatts.
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RCS cooling is by natural heat loss to the reactor building arrhient
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atmosphere.
Incore thenaccouple readings range from 70*F to 91*F with an average of 80*F.
. Average cold leg temperature is 53*F.
The average reactor building tenaerature is 59"F.
The reactor
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building airborne activity is 9.5 E-9 uCi/cc Tritium and 3.8 E-10 uCi/cc particulate, predominantly Cesium 137,
2.
WASTE MANAGEMENT The Submerged Demineralizer System (SDS) was shutdown during this
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period. EPICOR II began processing the 61,000 gallon batch from Condensate Tank 1A (C0T-1A) on September 6,1985.
g Total volume processed through SDS to date is 2,963,375 gallons, and Go
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the total volume processed through EPICOR II is 2,547,671 gallons.
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2-September 9,'1985 NRC/THI-85-069 About 61,000 gallons of water had been transferred from COT-1A to
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CCT-1 in preparation for processing through EPICOR II.. After an additional batch is transferred, COT-1A will be desludged and used for storage of borated makeup water.
3.
DOSE REDUCTION /DECONTAHINATION ACTIVITIES Decontamination activities are continuing on the 281' level of the
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Auxiliary Building.
Average general area radiation dose rate is 40 mrem per hour on the
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347' level of the reactor building and is 67 mrem per hour on the 305' level of the reactor building.
4.
ENVIROM4 ENTAL HONITORING
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EPA sample analysis results show THI site liquid effluents to be in
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accordance with regulatory limits, NRC requirements, and the City of Lancaster Agreement.
THI water samples taken by the US Environmantal Protection Agency at
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the plant discharge to the river consisted of seven daily composite samples taken from August 17 to August 24, 1985.- Gamma scans detected no reactor related radioactivity.
The Lancaster water sample taken at the water works intake and
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analyzed by the US Environmental Protection Agency consists of a seven day composite sample taken from August 18 to August 24, 1985.
A gama scan detected no reactor related radioactivity.
The NRC outdoor airborne particulate sampler at the THI Site
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collected a sample between August 29 and September 4,1985. No reactor related radioactivity was detected. Analysis showed I-131 and Cs-137 concentrations to be less than the lower limits of detectability.
5.
REACTOR BUILDING ACTIVITIES
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Work continued on installation of the north end platform and the
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.defueling tool racks.
Defueling Water Cleanup System preoperational testing continued.
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Installation of cable tray shielding is in progress.
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Work continued on staging of reactor building sump recirculation
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system components into the building. System testing is in progress.
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6.
AUXILIARY AND FUEL HANDLING BUILDING ACTIVITIES Installation of the DWCS' continued. Partial DWCS turnover for
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l processing RCS during early defueling is expected to be ~ completed in late September.:
- The third of four canister storage racks is onsite with the
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remaining rack scheduled for delivery by mid-September.
Inspection and repairs to' cracked welds in the racks is currently under evaluation.
(See Section 8 - Defueling Preparations)
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RC FORM 318 00 80) NRCM 02M OFFICIAL RECORD COPY
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J!arold.R.~~Denton
Septeuber 9, 1985
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Bernard J. Snyder NRC/Tl11-85-069 7.
NRC EVALUATIONS IN PROGRESS Technical Specification Change Requests numbers 43, 49, and 50.
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Recovery Operations Plan Change numbers 29, 31, and 32.
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Fuel Canister Technical Evaluation.
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Defueling Safety Evaluation.
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Application for seismic exemption.
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SDS Technical Evaluation and System Description Update
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Core Stratification Sample Safety Evaluation
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Recovery Operations Plan (ROP) Change No. 30 which implements R0P
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Change Request No. 24 was issued September 3,1985.
8.
DEFUELING PREPARATIONS The licensee's integrated schedule for the TMI-2 project shows initial defueling beginning in October 1985. Delivery of several key defueling system components has been delayed and could impact the defueling schedule.
Initial delivery of defueling canisters was scheduled for July 1985.
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This schedule has been delayed due to Quality Assurance (QA)
probleas at the canister vendor's facility. The vendor is Nuclear Energy Services Manufacturing (NES) located in Greensboro, North Carolina. A report of an NRC inspection at the facility, issued on July 26, 1985, identified specific QA probleus which require corrective action. NRC approval of the licensee's planned use of the defueling canisters is contingent upon satisfactory resolution of vendor QA problems.
Delivery of the fuel canister transfer shields has been delayed due
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to difficulties at the vendor's (IIES) facility. A portion of one shield was dropped in July during its construction and the component was scrapped because of the damage and had to be refabricated.
Delays as a result of the progrannatic QA deficiencies noted above have also occurred. One of the two shields was delivered this week, the other is scheduled for delivery the week of September 9,1985.
This is about one month behind the origin 11 projected schedule.
Delays have occurred in the delivery of fuel canister storage racks
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for the Fuel Handling Building. A temporary hold was placed on the racks during their fabrication at NES because of programatic QA problems noted above. Three of the four racks have since been delivered to the TMI site.
Inspections by GPU personnel identified cracks in several structural welds in two of the racks. GPU has attributed the cracking to fatigue, failure due to transportation induced vibrations during shipping. Further inspections and repair of the racks is in progress at the site. The fourth rack is scheduled for delivery in the near future.
Installation of the racks in the "A" spent fuel pool was originally scheduled for late August.
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OFFICIR RECORD COPY
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NRC FOQM 318 00 80) NRCM O240
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Harold R. Denton
Septecher 9,1985 Bernard J. Snyder NRC/Till-85-069
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NRC licensing review of the proposed fuel shipping cask is in
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progress. The license application for the NUPAC-125B cask, which is designed to withstand transportation accidents, was submitted in June.
Initial NRC review of the application identified issues relating to the structural and criticality analyses of the package.
Resolution of the technical issues is in progress and is not expected to have a significant impact on the fuel shipping schedule.
However, cccraencenant of defueling is contingent upon resolution of these t ransportation issues. The licensee currently projects the first fuel shipment to occur in March 1986.
9.
PUBLIC MEETING The next meeting of tha Advisory Panel for the Decontamination of Three Mile Island Unit 2 is scheduled for September 11, 1985. The recting will be at the Environmental Matters Coaaittee Room (Room 160), House Office building, College Avenue. Annapolis, Maryland froa 6:03 to 9:00 PH. The purpose of the treting is to infonn the public of progress being made in the THI-2 cleanup and to allow the public to voice concerns and make comments on any aspects of the cleanup. The status of the processed water will also be discussed.
Persons desiring the opportunity to speak before the Panel are asked to contact Mr. Thoraas Smithgall at 717-291-1042 or write to him at 2122 Marietta Avenue, Lancastar,-Pennsylvania 17603.
oRIGNAL m BY, Wilnam D. Travers William D. Travers Deputy Program Director TMI Program Office
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OFFICIAL RECORD CUI NRC FOHM318 (10 80) NRCM O240
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Harold R. Denton
September 9,1985 Bernard J. Snyder NRC/THI-85-069
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INTERNAL DISTRIBUTION EDO OGC Office Directors Comissioner's Technical Assistants NRR Division Directors NRR A/D's Regional Adzainistrators IE Division Directors TAS EIS-THI Program Office Staff (10)
RI Division Directors Public Affairs. RI State Liaison, RI THIPO HQ r/f THI SITE r/f CENTRAL FILE HRC PDR LOCAL PDR Till-2 Project Section File l
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