ML20024F082
| ML20024F082 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 08/29/1983 |
| From: | Barrett L Office of Nuclear Reactor Regulation |
| To: | Harold Denton, Snyder B Office of Nuclear Reactor Regulation |
| References | |
| CON-NRC-TMI-83-055, CON-NRC-TMI-83-55 NUDOCS 8309080200 | |
| Download: ML20024F082 (10) | |
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p August 29, 1983 NRC/THI-83-055
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HEMORANDUM FOR:
Harold R. Denton, Director Office of Nuclear Reactor Regulation Bernard J. Snyder, Program Director TMI Program Office FROH:
Lake H. Barrett, Deputy Program Director
_THI Program Office
SUBJECT:
NRC THI PROGRAM 0FFICE WEEKLY STATUS REPORT FOR AUGUST 21 - AUGUST 27, 1983
- Data from effluent and environmental monitoring systems indicated no plant releases 1 ~ a in excess of regulatory limits. Waste shipments and water processing tasks continued on a routine basis. Plant parameters showed no significant changes.
Preparations for head lift (early 1984) continued. The reactor coolant system is depressurized and RCS level remains at 321'6".
Data' acquired during underhead characterization activities are being analyzed and preparation for mapping of core topography is underway.
The major activity this week was the evaluation of GPU's polar crane submittals.
Other activities included: underhead characterization operations "A" spent fuel pool refurbishment and procedure review. Decontamination of auxiliary and fuel handling building surfaces and cubicles progressed at a reduced pace. Three reactor building entries were made in support of miscellaneous tasks.
(For more details see appropriate paragraphs below.)
Significant items-included in the enclosure are:
Reactor Building Activities Polar Crane Status -
-Spent Fuel Pool "A" Refurbishment
- Auxiliary and Fuel Handling Building Activities Waste Management Activities Public Meetings Data summary sheets included in this report are:-
Liquid Effluents Environmental Data g-Radioactive Material /Radwaste Shipment Data Water Processing Data 4
Plant-Status Data
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ENCLOSURE j
REACTOR BUILDING ACTIVITIES:
Three reactor building entries wereicompleted during the week of August 21, 1983. The underhead characterization study continued this week with the Reactor Coolant System (RCS) water level at the 321.5 ft. level.
(See Weekly Status Report for 8/22/82, Appendix 6).
Closed circuit televisicn (CCTV) inspection of the dry upper surface of the plenum (a 55-ton cylinder 10 feet high and 12 feet in diameter which holds the fuel in place and contains control rod guide tubes) and the underside of the head was completed this week.
Careful review of this and earlier video tapes showed a fine coating of sediment on the plenum and support tube surfaces. The dried sediment appeared to form an uneven layer textured by ridges in some areas and looking similar to a dry river bed in other areas. Bright flecks dispersed in this material may be condensed globules of low vapor point metals produced during the accident e.g. silver from control rods.
Leadscrew surfaces were also examined. These exhibited a wide variation in condition from encrusted, scaly surfaces to clean, shiny surfaces. The inner and outer surfaces of the support tubes showed a water mark a few inches from the top probably caused by the RCS while it was at the 324.5 ft. level.
Preliminary radiation data from the thermoluminescent dosimeters (TLDs) showed no unexpected aberrations and dose rates were within the expected range at all levels.
This 321.5 ft. level data (no plenum shielding by the RCS) correlated well with calculated projections and the data taken last week with RCS at the 324.5 ft. level. Analysis of this data continues and final figures will be available in future Weekly Status Reports.
Ultrasonic mapping of the core with computer image reconstruction is the next planned task in the sequence of the underhead characterization s+.Jy.
This task should be completed the first week of September.
Data from the underhead characterization is essential in planning the removal
.of the r'eactor head (early 1984) and subsequent plenum removal and defueling.
NOTE:
Video tapes of the plenum inspection and other cleanup activities are available for viewing by the general public at the NRC Middletown Office, 100 Brcwn Street, on Wednesday evenings.
The NRC Middletown Office hours are Tuesdays - 12:00-2:00 PM, Wednesdays - 5:00-8:00 PM and Thursdays -
3:00-5:00 PM.
POLAR CRANE STATUS:
The TMIPO staff is continuing the review of all licensee documents related to the reactor building polar crane.
This includes approximately 40 component inspection reports and evaluations. Mr. Thomas Stickley, the NRC's expert crane consultant was on site from August 23 - 25, 1983, to continue his safety review of NRC polar crane documents. The NRC will continue its review of all polar crane related documents. The NRC's conclusions, in a safety evaluation report, will.be docketed, forwarded to the licensee and made available to the public. The TMIP0 staff expects to complete this activity in September. The Office of Investigation has also indicated a similar completion date for their report.
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2 The TMIP0 has also recei.ved.a copy of a highly technical report prepared by an NRC staff member who was assisting the Office of Investigation in their review of the polar crane allegations.
This report is being made available to the public. The information contained in this report will be included in the polar crane safety evaluation.
SPENT FUEL P0OL "A" REFURBISHMENT:
The removal of concrete shield blocks from around the side of the tank farm is waiting for completion of testing and qualification of the equipment to be used to transfer the blocks to the truck bay.
Block removal is expected to resune early next week.
The licensee has drafted a procedure for load testing the 14 repaired lifting lugs on the four northern shield slabs above the tank farm.
Following review and approval of the procedure, the test is, scheduled to occur in late October.
Other issues curr&ntly being resolved effect the lifting lug on an off-gas drier (see Weekly Status Report for August 8, 1983) and the beam to be used to extend the lifting range of the fuel handling building crane to include the four northern most shield slabs.
The NRC continues to review the Safety Evaluation Report (SER) for the "A" spent fuel pool refurbishment and the revised Technical Evaluation Report (TER) for the SDS changes.
AUXILIARY AND FUEL HANDLING BUILDING ACTIVITIES:
L Decontamination activities in the. auxiliary and fuel handling buildings continued at a reduced pace.
The recently decontaminated walls in the reactor coolant evaporator room were painted this week.
The floor decontamination will begin next week with scabbling (abrasive removal of a thin surface layer). Three other auxiliary building cubicles on the 282 ft. elevation are scheduled for similar decontamination operations within the next four weeks.
Scabbling activities in the fuel handling building of open areas and corridors continued this week with completion scheduled for next week.
I WASTE MANAGEMENT ACTIVITIES:
1.
SDS Liner Shipments.
Shipment of the thirteenth SDS waste liner (D-20029) will occur Tuesday, August 30, 1983. This liner is the last of the SDS vessels used to process the accident generated reactor building sump water. The licensee is planning a ceremony with invited guests to mark the occasion.
Plans to ship the other lower activity SDS waste liners (used to process RCS water) are being developed.
2.
EPICOR Demineralizer Shipments.
EPICOR demineralizer F-31 was shipped from TMI to Hanford, Washington on August 26, 1983.
F-32 is scheduled to be shipped August 30, 1983.
Cemineralizers F-37, F-22, F-29 have all been dewatered and are being prepared for shipment.
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3 PUBLIC MEETit:GS:
Past Meeting:
On August 23, 1983, Lake H. B'arrett met with the Concerned Mothers of Middletown to discuss cleanup oper'tions at TMI-2. They expressed their a
concern that TM1 Unit 1.should not be restarted prior to completion of the Unit 2 cleanup.
Future Meetings:
- 1.
On September 16, 1983, the Three Mile Island Unit 2 Advisory Panel will meet with the NRC Commissioners in their Washington office at 1717 H Street, Washington, DC 20555. The public is invited to observe the meeting.
2.
On September 28, 1983, the Three Mile' Island Unit 2 Advisory Panel will meet from 7:0.0 PM to 10:00 PM in the Holiday Inn, 23 South Second Street, Harrisburg, Pennsylvania. The meeting will be open to the public. The major topic for the meeting will be polar crane issues.
Persons or groups that have questions pertaining to the TMI-2 cleanup that would like to have them considered or addressed by the Advisory Panel can send these questions to Mr. John Minnich, Chairman, Dauphin County Courthouse, P.O.
Box 1295, Harrisburg, PA 17108.
Persons or. groups desiring the opportunity to speak before the Advisory Panel on TMI-2 cleanup related items are asked to contact in writing, Mr. Joel Roth, 4705 Carlisle Pike, Mechanicsburg, PA 17055.
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APPENDIX-1
. LIQUID EFFLUENT DATA GPU Nuclear Based on sampling and monitoring, liquid effluents from the TMI site released to the Susquehanna River were determined to be within regulatory limits and in accordance with NRC requirements and the City of Lancaster Agreement.
During the period August 19, 1983, through August 25, 1983, the effluents contained no' detectable radioactivity at the discharge point.- Individual effluent sources originating within Unit 2 contained minute amounts of-radioactivity.
Calculations indicate that'less than 3.0 E-8 (0.00000003). of a curie of Cs-137 wa's discharged.
T Environmental Protection Agency i
Lancaster Water Samples:
6 samples Period Covered:
August 1 - August 6, 1983 Results:
Gamma Scan Negative TMI Water Samples:
6 samples
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Peri'od Covered:
August 6 - August 13, 1983 Results:
Gamma Scan Negative 4
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ENVIRONMENTAL DATA EPA Environmental Data The EPA Middletown Office has not received the environmental Kr-85 analytical results for the samples which were taken subsequent to August 5,1983, from the EPA's Counting Laboratory at Las Vegas, Nevada.
These results will be included in a subsequent report.
No radiation above normally occurring background levels was detected in any of the samples collected from the. EPA's air and gamma rate networks during the period from August 16, 1983 through August 24, 1983.
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NRC Environmental Data Results from the NRC continuous air sampler monitoring of the TMI site environ-ment are as follows:
I-131 Cs-137 Sample Period (uCi/cc)
(uCi/cc)
HP-381 August 17, 1983 - August 24, 1983
<6.4 E-14
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APPENDIX 3 RADIOACTIVE MATERIALS /RADWASTE SHIPMENT DATA
- On August 23, 1983, one HN-100 cask containing solidified resins from Unit 1 was shipped to Chem Nuclear Systems, Inc., Barnwell, South Carolina.
On August 24, 1983, a drum containing Radiation Monitor HP-R 214 conduit and cable samples, from Unit 2 was shipped to Sandia National Labs, Albuquerque, New Mexico.
On August 25, 1983, 88 drums of contamina.ted laundry from Unit 1 and 2 were shipped to Interstate Uniform Service, New Kensington, Pennsylv'ania.
On August 26, 1983, one 14-190 type A cask containing EPICOR liner F-31 was shipped to Hanford burial site, Richland, Washington.
On August 26, 1983, 128 drums of Units 1 and 2 compacted and non-compacted waste was shipped to Hanford burial site, Richland, Washington.
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APPENDIX 4 i
WATER PROCESSING DATA i
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- Submerged Demineralizer System (SDS) i SDS was shutdown during the week for maintenance..
EPICOR II EPICOR II was shutdown during the week.
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APPENDIX 5 PLANT STATUS t
- Core Cooling Mode: Heat transfer from the reactor coolant system (RCS) to Reactor Building ambient.
Available Core Cooling Mode: Mini Decay Heat Removal (MDHR) system.
RCS Pressure Control Mode:
N/A (system is depressurized).
Major Parameters (as of 6:15 AM, August 26,1983)(approximatevalues)
Average Incore Thennoc.ouples*:
114 F**
Maximum Incore Thermoc~ouple*:
133 F RCS Loop Temperatures:
A B
Hot Leg Cold Leg (1) 88'F 85 F (2) 88 F 85 F RCS Pressure: O psig Reactor Building: Temperature:
82 F Pressure:.
-0.15 psig Airborne Radionuclide Concentrations:
4.5 E-8 uCi/cc H3 (Tritium)
(sample taken 8/23/83) 6.2 E-9 uCi/cc particulates (predominatelyCs-137)
(sampletaken8/23/83)
- Uncertainties exist as to the exact location anh accuracy of these readings.
- Manual calculation. The computer generated average thermocouple temperature is typically 5 lower.
- Since the RCS draindown, hot leg temperature detectors are above water level.
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