ML20004E816
| ML20004E816 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 06/08/1981 |
| From: | Barrett L Office of Nuclear Reactor Regulation |
| To: | Harold Denton, Snyder B Office of Nuclear Reactor Regulation |
| References | |
| CON-NRC-TMI-81-032, CON-NRC-TMI-81-32 NUDOCS 8106150320 | |
| Download: ML20004E816 (5) | |
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DISTRZBUTZON TMI Program Office /HQ r/f TMI SITE r/f cf2dTRAL FILE NRC PDR LOCAL PDR f
June 8,1981 Site Operations file NRC/TMI-81-032 e
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0 MEMORANDl34 FOR:
Harold R. Denton, Director.
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Bernard 'Jl Snyaer, Program Director.
TMI Progras Office y
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Lake H. Barrett, Acting Deputy Program Director.
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TMI Program Office
SUBJECT:
NRC TMI PROGRAM OFFICE WEEXLY STATUS REPORT Enclosed is the status repokfor the period of May 31 - June 6,1981.
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LakeH.Barrett Lake H. Barrett ij Acting Deputy Program Director TMI Program Office l
Enclosure:
As stated cc: EDO l!
i OGC ii Office Directors l
Cassaissioner's Technical, Assistants._
NRR Division Directors. _
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Regional Directors j
IE Division Directors j
x00S xoMA TMI Program Office Staff l(15)
PHS EPA DOE Projects Br. No. 2 Chief. DPRI, RI i!
DPRI Chief, RI j
Public Affairs, RI i
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NRC TMI PROGRAM 0FFICE WEEKLY STATUS REPORT Week of May 31 - June 6,1981 Plant Status Core Cooling Mode: Heat transfer from the reactor coolant system (RCS) loops to Reactor Building ambient.
Available Core Cooling Modes: Decay heat removal systems.
Long-term cooling "B" (once through steam generator-B)
RCS Pr+ssure Control Mode: Standby Pressure Control (SPC) System.
Backup Pressure Control Modes: Mini Decay Heat Removal (MDHR) System.
Decay Heat Removal (DHR) System.
Major Parameters (as of 0400, June 5,1981) (approximate values)
Average Incore Thermocouples: 117 F Maximum Incore Thermocouple: 143 F RCS Loop Temperatures:
A B
Hot Leg IIS F 118 F F
Cold Leg (1) 68 F 69 F (2) 68 F 69 F RCS Pressure: 98 psig Reactor Building: Temperature: 67 F Water level: Elevation 290.8 ft. (8.3 ft. from floor) via penetration 401 manometer i
Pressure:
-0.3 psig Concentration: 7.9 x 10 6 uCi/ml Kr-85 (Sample taken l
6/ 2/81 )
Effluent and Environmental (Radiological) Information 1.
Liquid effluents from the TMI site released to the Susquehanna River after processing, were made within the regulatory limits and in accordance with NRC requirements and City of Lancaster Agreement l
I dated February 27, 1980.
During the period May 29, 1981, through June 4,1981, liquid effluents contained no detectable radioactivity at the discharge point and l
individual effluent sources which originated within Unit 2 contained no detectable radioactivity.
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Airborne effluents.are reported on a monthly basis.
3.
Environmental Protection Agency (EPA) Environmental Data.
Resul ts from EPA monitoring of the environment around the TMI site were as follows:
3 The EPA measured Kr-85 concentrations (pCi/m ) at several environmental monitoring stations and reported the following resul ts:
Location May 22 - May 29,1981 3
(pCi/m )
Goldsboro 30 Observation Center 27 Middletown
- 22 Yorkhaven 23 All of the above levels of Kr-85 are considered to be back-ground levels.
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 May 28, 1981, through June 4, 1981.
4.
NRC Environmental Data.
Results from NRC monitoring of the environ-ment around the TMI site were as follows:
The following are the NRC air sample analytical results for
' the onsite continuous air sampler:
Sample Period (uCi/cc)
(uCi/cc),
HP-270 May 27, 1981 - June 3, 1981
<8. 7 E-14 <8. 7 E-14 5.'
Licensee Radioactive Material and Radwaste Shipments On Monday,'Ju~ne 1,1981, a 40 ml Unit 2 reactor coolant sample was sent to Babcock and Wilcox (B & W), Lynchburg, Virginia.
On Monday, June 1,1981, one 6' x 6' EPICOR II dewatered resin liner (liner DS-3) from Unit 2 was shipped to U. S. Ecology, l
l Richland, Washington.
On Friday, June 5,1981, two 6 M containers and one 17 H container (total of nine reactor building sump samples from Unit II) were shipped to EGG. Idaho, Inc., Idaho Falls, Idaho.
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Major Activities
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1.
Submerged Demineralizer System (SDS). Preparation of the Safety Evaluation Report (SER) by the TMI Program Office is in progress.
All information requested from the licensee has been received although some items require minor clarification.
These items will be handled on a case by case basis. The staff review is expected to be completed this month.
2.
Emergency Drill at TMI-1.
The NRC site staff participated in the emergency drill on June 2,1981, which was conducted to demonstrate the emergency preparedness capability at Three Mile Island Unit 1.
Other federal agencies and several state agencies, counties and
-local municipalities also participated in the 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> exercise.
The drill was critiqued in Harrisburg on June 4,1981 jointly by the NRC, the Federal Emergency Management Agency (FEMA), and representatives of the Federal Ragional Assistance Committee.
Preliminary FEMA findings included no apparent significant deficiencies.
A final FEMA report is expected within two weeks.
The NRC drill observers considered the emergency preparedness at TMI-l to exceed federal standards, based on the conduct of the exercise. A more detailed NRC assessment of THI-l emergency preparedness plans, procedures, facilities and equipment is scheduled for July 1981.
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Meeting Held On Thursday. June 4,1981, the Advisory Panel for the Decontamination of TMI Unit 2 held a public meeting in the Lancaster City Council Chambers.
The topics of discussion were radiation worker exposure health effects and disposal of high activity wastes.
Panel member Dr. Cochran extensively discussed with NRC staff members, Dr. Congel and Dr. Gotchy, the numerical estimates of genetic defects and cancers that could result to workers involved with decontamination of Unit 2 and their offsprings.
Dr. Cochran stated his opinion that the larger health impact of the Unit 2 decontamination would be to workers doing the cleanup and not to the members of the public exposed to radioactive effluents. He also stated his opinion that it would have been better if NRC staff had expressed occupational radiation risks in a range of projected incidences of genetic defects and cancers in the text of the PEIS rather than the use of single mean values in the text with inclusion of the range values in an Appendix to the text.
The NRC staff stated that the PEIS text clearly agreed with Dr. Cochran that the relative impacts of the cleanup were greater for the workers than for the public, and that the use of mean values in the text with ranges in the Appendix were reasonable representations of the impacts.
It was also announced at the meeting that the Department of Energy (DOE) had responded in writing to NRC inquiries concerning the ultimate disposition of high activity wastes generated by the submerged demineralizer system (see item 1 above).
DOE stated that their fiscal 1982 budget request to Congress had proposed to take the high activity Submerged Demineralizer System wastes and never return the wastes to TMI.
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