ML19340F190
| ML19340F190 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 01/05/1981 |
| From: | Barrett L Office of Nuclear Reactor Regulation |
| To: | Harold Denton, Snyder B Office of Nuclear Reactor Regulation |
| References | |
| CON-NRC-TMI-81-001, CON-NRC-TMI-81-1 NUDOCS 8101210264 | |
| Download: ML19340F190 (5) | |
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%, v -lf January 5, 1981 NRC/TitI-81-001
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MEMORANDUM FOR:
Harold R. Dention, Director, Office of Nuclear Reactor Regulation Bernard J. Snyder, Program Director, TMI Program Office FROM:
Lake H. Barrett, Acting Program Director, 1
TMI Program Office SdBJECT:
NRC TMI PROGRAM 0FFICE WEEKLY STATUS REPORT Enclosed is the status report for the period of December 21, 1980 -
January 3,1981 as discussed in the last status report.
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c-Lake H. Barrett Acting Deputy Program Director r, TMI Program Office t
Enclosure:
As stated cc:
EDO OGC Office Directors Commissioner's Technical Assistants NRR Division Directors NRR A/D's Regional Directors IE Division Directors XOOS X0MA TMI Program Office Staff (15)
HEW EPA R0&NS Branch Chief, Region I FF&MS Branch Chief, Region I Public Affairs, Region I T. Elsasser 3101210 M
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NRC TM1 PROGRAM 0FFICE WEEKLY STATUS REPORT Week of December 21, 1980-January 3, 1981 Plant Status Core Cooling Mode:
Cyclic natural circulation in the "A" reactor coolant system (RCS) loop via the "A" once through steam generator (OTSG), steaming to the main condenser, and RCS loop-A and B cyclic natural circulation to reactor building ambient..
Available Core Cooling Modes: 0TSG "B" steaming to the main condenser; long-term cooling "B" (OTSG-B); decay heat removal.
RCS Pressure Control Mode: Standby Pressure Control (SPC) System.
Backup Pressure Control Mode:
One of two decay heat removal pumps to supply pressure in conjunction with variable recirculation back to the borated water storage tank (BWST) to provide control of pressure.
Major Parameters (As of 0500, January 5,1981) (approximate values)
Average Incore Thermocouples:
119 F Maximum Incore Thermocouple:
153 F RCS Loop Temperatures:
A B
Hot Leg 118 F 121 F 3
i Cold Leg (1) 79 F 86 F (2) 77 F 99 F r,
RCS Pressure:
95 psig (DVM)
Pressurizer Temaerature:
69"F Reactor Building:
Temperature: 65 F
' Water level:
Elevation 290.5 f t. (8.0 ft. from floor) via penetration 401 manometer Pressure:
-0.4 psig (Hgise)
Concentration:
1.1 x 10-* uCi/cc (Kr-85) (sample taken 1/2/81) j Effluent and Environmental (Radion gical) Information Liquid effluents frem TMI site released to the Susquehanna River after processing, were made within the regulatory limits and in accordance with NRC recuirements and City of Lancaster Agreement dated February 27, 1986.
The concentrations of radioactive material in the discharged effluent during this weekly period were less than the Lower Limits of Detection (LLD).
2 2.
EPd Environmental Data.
Results from EPA monitoring of the environment around the TMI site were as follows:
3 The EPA measured Krypton-85 (Kr-85) concentrations (pCi/m ) at several environmental monitoring stations and reported the following results:
Location December 12-December 19, 1980 3
(pCf/m )
Bainbridge 25 Goldsboro 20 g
Observation Center 27 Middletown 16 All of the above levels of Kr-85 are considered to be back-ground levels.
No radiation above normally occurring backgroun'd-levels were detected in any of the samples collected from EPA's air and gamma rate networks during the period from December 17 through December 31, 1980.
3.
NRC Environmental Data.
Results from NRC monitoring of the environment around tne TMI site were as follows:
The following are the NRC air sample analytical results for the onsite continuous air sampler:
1-131 Cs-137 Period (uCi/cc)
(uCi/ccir
_Samole HP-247 December 17-December 23, 1980
<10.3 E-14
<10.3 E-14 HP-248 December 23-December 30, 1980
<8.8 E 14
<8.8 E-14 4.
Licensee Radioactive flaterial and Radwaste Shipments.
The following snipments were mace:
On Monday, December 29,1980, two 40 ml Unit 2 reactor coolant samples were sent to Babcock and Wilcox (B&W), Lynchburg, Virginia.
On Monday, December 29, 1980, 20 metal. boxes of Unit i non-compacted waste were shipped to the Chem-Nuclear site, Barnwell, South Carolina.
Major Activities 1
Reactor Decay Heat Removal.
Decay heat removal continues to be removed by steaming (unoer vacuum conditions) in the "A" Once Through Steam Generator (OTSG) and by heat transfer from reactor coolant system to reactor building anbient.
The onsite staff has approved the licensee's proposal (procedure) to use the loss to ambient mode as a means of decay i
heat removal.
Implementation of the licensee's procedures is expected next week.
3 2.
_ Scent Resin Storage Status.
Sixty-six spent resin liners generated
' f rom EPICOR 1 and II are stored in "A" longterm waste storage modult.
Six of the occupied cells contain stacked 4' x 4' liners (two per storage cell).
The "B" longterm waste storage module is holding seven spent resin liners with a holding capacity equivalent to Module "A" (60 cells).
The licensee has continued to relocate liners from the temporary interim storage facility.
Only five of the twenty-eight spent resin storage cells hold liners.
The final transfers are scheduled for the month of January,1981
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4 Me5 tings Attended On Tuesday, December 30, 1980, L. Barrett attended the TMI Advisory Panel 4
meeting at the William Penn !!useum in Harrisburg. The topic of discussion was the disposition of processed radioactive liquids.
Presentations were given by Mr. R. Arnold, Chief Operating Executive, GPU, and Mr. G. Hovey, Director TMI-Unit 2, GPU.
The panel listened to GPU's plans to decouple the processing of contaminated wate* and the discharge of the processed water.
GPU stated that the processed water could be safely stored on si,te and no formal proposal for final disposition of processed water would be presented to the NRC before 1982.
Panel members discussed the urgency of processing the containment sump water, relative environmental impacts of releasing tritium in airborne or !iquid form, and the definition of accident related water.
Future Meetings On Thursday, January 22, 1981, L. Barrett will attend a public briefing in Harrisburg sponsored by the Department of Environmental Resources on the scatus of decontamir:ation at Three Mile Island. Following the presentation, the Nuclear Regulatory Commission, the Environmental Protection Agency and Metropolitan Edison will be available to answer questions.
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