ML19277H295
| ML19277H295 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 07/09/1984 |
| From: | Grant P Office of Nuclear Reactor Regulation |
| To: | Harold Denton, Snyder B Office of Nuclear Reactor Regulation |
| References | |
| CON-NRC-TMI-84-050, CON-NRC-TMI-84-50 NUDOCS 8407160127 | |
| Download: ML19277H295 (11) | |
Text
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July 9,19f!4 i
NRC/TMI-84-050 MEMORANDuit FOR:
Harold R. Denton, Director Office of Nuclear Reactor Regulation I
l Bernard J. Snyder Progran Director l
TMI Program Office I
i FROM:
Philip J. Grant, Acting Deputy Program Director TM1 Program Office
SUBJECT:
NRC THI PROGRAM OFFICE WEEKLY STATUS REPORT FOR July 1, 1984 - July 7, 1984 i
On July 5 and 6,1984, all reactor pressure vessel (EPV) studs were loosened, removed and stored in racks in the rear < r building.
No conditions withir, the RPV were affectec and there was no leakage since the reactor coolarit s.ystem has ban drained down to approximately one foot below the interfacc between the RPV arid the RPV head. Data from effluent and environniental monitoring systems indicated no plant releases in excess of regulatory limits. Weste processing continued on a ruutine basis. Plant parameters have shown no significant changes. The reactor coolant system is depressurized with the primary system water level draincd to the 321'6" elevation.
(fer more details see appropriate paragraphs below.)
Significant items covered in the enclosure are:
Reactor Building Activities Auxiliary and Fuel Handling Building Activities Waste Management l
Public Meetings Data sumnary sheets included in this report are:
Liquid Effluent Data Environmental Data Radioactive Material /Radwaste Shipment Data Plant Status Data i
ORIGINAL SIGNED BY:
i Philip J. Grant I
Acting Deputy Program Director
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TMI Program Office D
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Enclosure:
As stated
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ENCLOSURE REACTOR TUILDING ACTIVlilES:
On July 5,1984, the licensee successfully completed the loosening of the 58 reactor pressure vessel (RPV) stuos which are threaded into the RPV.
This activity did involve the use of liquid nitrogen and an impact wrench to free one of the studs.
The configuration of the head on the RPV was not altered because stud detensioning and stud loosening only involved relaxation of the studs and nuts.
The reactor coolant system (RCS) has been partially drained down to a level about one foot below the interface between the RPV and the head, and no leakage resulted from the detensioning.
On July 6, 1984, all studs were removed from the RPV and stored in racks in the reactor building.
The reactor vessel head studs were removed from the reactor vessel flange ahead of schedule.
In general, preparatory ectivities for the reactor vessel head lif t are being completed ahead of schedule, which is tentatively scheduled for August 8, 1984.
Reactor building entries are continuing at a rate of six entry days per week.
During entries next week (week of July 8,1984), new head lif t rigging will be transferred into the reactor building, shielding will be installed around the control rod drive mechanisms on the reactor vessel head, and modifications to the internals indexing fixture (IIF) will continue.
The IIF will serve as a mini refueling canal on top of the reactor vessel following the head lift.
AUXILIARY AND FUEL HANDLING BUILDING ACTIVITIES:
Hydrostatic testing of lines associated with the makeup and purification demineralizer elution system was completed satisfactorily on July 5,1984.
Work continued on the "A" fuel pool refurbishment.
Additional structural steel was removed from the fuel pool tanks.
The licensee is studying methods of final disposition of the tanks, including onsite decontamination of the internals, and sale to others for contaminated or non-contaminated use.
Decontamination activities continued in the buildings.
WASTE MANAGEMENT ACTIVITIES:
The submerged demineralizer system (SDS) completed processing batch 95 from the "C" reactor coolant bleed tank (RCBT).
This processing took place from June 23 to July 1, 1984, and consisted of 56,050 gallons of water.
SDS began processing water directly from the reactor building sump (batch 96) on July 3, 1984.
Processing of this batch was stopped on July 4, when high Sr-90 conce'ntrations were detected in the effluent and subsequently a zeolite vessel was changed out.
A total of 7,897 gallons was processed to the "A" monitor tank be' fore the strentium breakthrough occurred.
SDS will continue processing batch 93 from the lower tank farm in the "A" fuel pool. The water has been generated as a result of the ongoing decontamination of the lower tank farm.
EPICOR 11 has been shutdown since the completion of batch 215 on June 23, 1984.
2 PUBLIC MEETINGS:
1.
On July 12, 1984, Phil Grant will meet with Mayor Robert Reid of Middletown to discuss head lift activities.
2.
On July 12, 1984, the Advisory Panel for the Decontamination of Three Mile Island Unit 2 will meet from 7:00 PM to 10:00 PM in the Holiday Inn, 23 South Second Street, Harrisburg, Pennsylvania.
The mee'.ng will be open to the public.
Persons that have questions pertaining to the TMI-2 cleanup that would like to have them considered or addressed by the Advisory Panel are asked to contact, in writing, Mayor Arthur Morris,120 Duke 5treet, Lancaster, PA 17602.
Persons desiring the opportunity to speak before the panel are asked to contact Mr. Thomas Smithgall at 2122 Marietta Avenue, Lancaster, PA 17603 (telephone 717-291-1041).
At this meeting the Panel will be briefad by Dr. W. Kirk, Environmental Protection Agency, on the results of the interagency radiation monitoring program review.
Representatives from GPU Corporation will discuss facility decontamination alternatives after fuel removal, and funding for the cleanup for 1984 and beyond.
The status of the Edison Electric Institute TMI-2 voluntary funding program will also be presented.
2 PUBLICMEpINGS:
1.
On Jul3 12, 1984, Phil Grant will meet with Mayor Robert Reid of Middletown to discuss head lift activities.
2.
On July 12, 1984, the Advisory Panel for the Decontamination of Three Mile Island Unit 2 will meet from 7:00 PM to 10:00 PM in the Holiday Inn, 23 South Second Street, Harrisburg, Pennsylvania.
The meeting will be open to the public.
Persons that have questions pertaining to the TMI-2 cleanup that would like to have them considered or addressed by the Advisory Panel are asked to contact, in writing, Mayor Arthur Morris,120 Duke Street, Lancaster, PA 17602.
Persons desiring the opportunity to speak before the panel are asked to contact Mr. Thomas Smithgall at 2122 Marietta Avenue, Lancaster, PA 17603 (telephone 717-291-1041).
At this meeting the Panel will be briefed by Dr. W. Kirk, Environmenta'.
Protection Agency, on the results of the interagency radiation monitoring program review.
Representatives from GPU Corporation will discuss facility decontamination alternatives after fuel removal, and funding for the cleanup for 1984 and beyond.
The status of the Edison Electric Institute TMI-2 voluntary funding program will also be presented.
o APPENDIX 1 LIQUID EFFLUENT DATA GPU Nuclear Based on sampling and monitoring, liquid effluents from the TMI site teleased to the Susquehanna River were determined to be within regulatory limits and in accordance with NRC reqrirements and the City of Lancaster Agreement.
During the period June 29 through July 5,1984, tnere were no liquid effluents released from TMI-2.
Environmental Protection Acency Lancaster Water Samples:
7 samples Period Covered:
June 17 - 23, 1984 Results:
Gamma Stan Negative TMI W6ter Samples:
7 samples Period Covered:
June 16 - 23, 1984 Results:
Gamma Scun Negative 6
4
APPENDIX 2 ENVIRONMENTAL DATA NRC Environmental Data The NRC operated continuous outdoor air sampler at the TMI site did not detect any reactor related radioactivity.
The air sampler analysis results are listed below.
1-131 Cs-137 Sample Period Volume (uCi/cc)
(uCi/cc) 3 HP-426 June 27 - July 5, 1984 315.3 m
<1.1 E-13
<1.1 E-13
APPENDIX 2 ENVIRONMENTAL DATA NRC Environmental Data The NRC operated continuous outdoor air sampler at the TMI site did not detect any reactor related radioactivity. The air sampler analysis results are listed below.
1-131 Cs-137 Sample Period Volume (uCi/cc)
(uCi/cc) 3 HP-426 June 27 - July 5, 1984 315.3 m
<1.1 E-13
<1.1 E-13 6
APPENDIX 3 RADIDACTIVE MATERIALS /RADWASTE SHIPMENT DATA On July 3, 1984, a Unit I sample from the waste evaporator condensate storage tank was sent to Teledyne isotopes, Westwood, New Jersey.
On July 5, 1984, a combined Unit I and 2 shipment consisting of radio-actively contaminated laundry was f ent to Interstate Nuclear Services at New Kensington, Pennsylvania.
/
S 4
APPEf1Dlx 4 PpitT STATUS Core Cooling Mode:
Heat transfer from the reactor coolant system (RCS) to reactor building ambient Available Core Cooling / Makeup Sources:
Standby pressure control (SPC) system Reactor coolant bleed tank (RCBT) water transfer system Mini decay heat removal (MDHR) system RCS pressure control is no longer applicable since the RCS is vented to the reactor building atmosphere Major Parameters as of 5:30 AM, June 29, 1984 (approximate values):
Average Incore Thermocouples*:
98 F Maximum incore Thermocouple *:
135*F RCS Loop Temperatures:
A B
Hot Leg **
72 F 78'F Cold Leg (1) 72*F 75 F (2) 72 F 75*F Reactor Core Decay Heat:
16.5 kilowatts RCS Pressure:
O psig (open to reactor building atmosphere)
Reactor Building:
Temperature:
68 F P rc..s u re :
-0.01 psig Airborne Radionuclide Concentrations:
4.3 E-7 uCi/cc H (tritium)
(sample taken 7/5/84) 3.0 E-9 uCi/cc particulates (predominately Cs-137)
(sample taken 7/5/84)
- Uncertainties exist as to the exact location and accuracy of these readings.
i APPEf: Dix 4 PLANT STATUS Core Cooling Mode:
Heat transfer from the reactor coolant system (RCS) to reactor building ambient Available Core Cooling / Makeup Sources:
Standby pressure control (SPC) system Reactor coolant bleed tank (RCBT) water transfer system Mini decay heat removal (MDHR) system RCS pressure control is no longer applicable since the RCS is vented to the reactor building atmosphere Major Parameters as of 5:30 AM, June 29, 1984 (approximate values):
Average Incore Thermocouples*:
98'F Maximum Incore Thermocouple *:
135"F RCS Loop Temperatures:
A B
Hot Leg **
72*F 78'F Cold Leg (1) 72*F 75'F (2) 72'F 75*F Reactor Core Decay Heat:
16.5 kilowatts RCS Pressare: O psig (open to reactor building atmosphere)
Reactor Building:
Temperature:
68'F Fressure:
-0.01 psig Airborne Radionuclide Concentrations:
4.3 E-7 uCi/cc H3 (tritium)
(sample taken 7/5/84) 3.0 E-9 uti/cc particulates (predominately Cs-137)
(sample taken 7/5/84)
'Uncertaintis, exist as to the exact location and accuracy of these readings.