ML19318A358
| ML19318A358 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 06/09/1980 |
| From: | Jay Collins Office of Nuclear Reactor Regulation |
| To: | Harold Denton, Snyder B Office of Nuclear Reactor Regulation |
| References | |
| CON-NRC-TMI-80-097, CON-NRC-TMI-80-97 NUDOCS 8006190690 | |
| Download: ML19318A358 (6) | |
Text
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UNITED STATES U[,__
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NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 U
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June 9,1980 4
NRC/TMI-80-097 d
iiEM0RANDUM FOR:
H. R. Denton, Director, P
Office of Nuclear Reactor Regulation B. J. Snyder, Program Director, TMI Program Office FROM:
J. T. Collins, Deputy Program Director, TMI Program Office
SUBJECT:
NRC TMI PROGRAM OFFICE WEEKLY STATUS REPORT Enclosed is the status report for the week of May 31 - June 6, 1980.
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' John T. Collins Deputy Program Director TMI Program Office
Enclosure:
As stated cc:
EDO OGC Office Directors Commissioner's Technical Assistants NRR Division Directors NRR A/D's Regional Directors IE Division Directors X00S X0MA HEW EPA Public Affairs, RI T. Elsasser TMI Program Staff 8006100 fo O
NRC TMI PROGRAM 0FFICE WEEKLY STATUS REPORT Week of: May 31-June 6, 1980 Plant Status Core Cooling Mode: Cyclic natural circu;ation 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 4
reactor building ambient.
Available Core Cooling Modes: 0TSG "B" to the main condenser; long term cooling "B" (OTSG-B); decay heat removal.
l RCS Pressure Control Mode:
Standby Pressure Control (SPC) System.
Backup Pressure Control Mode:
Makeup system in conjunction with letdown flow (Emergency use only due to suspected leaks in the seal injection system).
Major Parameters (As of 0500, June 6,' 1980) (approximate values)
Average Incore Thennocouples: 156 F Maximum Incore Thermocouple:
194 F RCS Loop Temperatures:
A B
Hot Leg 150 F 154 F Cold Leg (1) 103 F 98 F (2) 95 F 94 F RCS Pressure: 82 psig (Heise) 94 psig (DVM controlling)
Pressurizer Temperature:
95 F Reactor Building:
Temperature:
80 F Pressure:
-0.8 psig (Heise)
Water level:
Elevation 290.3 ft. (7.8 ft.
from floor) via penetration 401 manometer Environmental & Effluent Information l
1.
Liquid effluents from TMI-l released to the Susquehanna River, after processing, were within the _ limits specified in Technical Specifications.
2.
No liquid effluents were discharged from TMI-2.
i 3.
Results from EPA monitoring of the environment around the TMI site were:
r.
2 EPA environmental stations registered background levels for air particulate and water samples. Gamma scan results for all sampling locations were negative.
Gas / Air (Kr-85) sample results during thg period May 16 through May 23, 1980 were:
Goldsboro - 24 pCi/M TMI Observation Center 320 pCi/M, Middletown - 19 pCi/MS and Bainbridge -
3 20 pCi/M..The EPA states that the Kr-85 background concentration 3
in the vicinity of TMI to be in the range of 20 and 40 pCi/M.
A Instantaneous direct radiation readings showed an average level of 0.014 mrem /hr.at the 17 monitoring stations.
The
- measurements are all attributed to naturally occurring radio-activity.
4.
NRC Environmental Data The West Screen House continuous air sample (HP-218) for the sampling period May 28 through June 4,1980, has been delivered to the EPA Coordination Center for analysis.
The following are the NRC air sample analytical results for the onsite continuous air sampler:
Sample Period I-131 Cs-U/
(uCi/cc)
(uCi/cc)
HP-216 May 15-May 21, 1980
<5.4E-14
<5.4E-14 HP-217 May 21-May 28, 1980
<4.9E-14
<4.9E-14 No reactor-related radioactivity was detected.
~ The licensee provided the following nonthly inventory of Kr-85 releases for 1980:
January-80Ci, February-80 Ci, March 63 Ci, April-69 C1, and May 85 Ci. Total = 377 Ci.
Results of the environmental TLD measurements for the period March 18 to April 30, 1980, indicate no gamma levels above natural background.
Fif ty-eight TLD's registered doses ranging from 0.09 mR/ day to 0.18 mR/ day.
Average dose was 0.13 mR/ day.
These dose rates are consistent with natural background radiation in the TMI area.
On June 5 and 6, 1980, the NRC and the licensee obtained separate air samples of the reactor building atmosphere. These samples were first analyzed independently to determine the concentration of Kr-85 present.
Subsequently, the licensee's sample was then analyzed by the NRC to determine the degree of correlation.
The licensee's results were in agreement with those of the NRC.
Airborne Kr-85 concentration in-the reactor building was verified to be about 0.8 uCi/ml.
i
3 5.
Radioactive Material and Radwaste Shipments offsite were as follows:
On Monday, June 2,1980, a Unit 2 reactor coolant sample was sent to the Babcock and Wilcox (B&W) facility, Lynchburg, Virginia for chemical and radiochemical analysis.
On Thursday, June 5,1980, a Unit 2 LSA resin liner (type B) was shipped to NEC0, Richland, Washington.
On Thursday, June 5,1980, a Unit I LSA resin liner (type B) was
' shipped to CNSI, Barwell, South Carolina.
On Friday, June 6,1980, compacted and solidified waste from Unit II was shipped to NEC0, Richland, Washington.
6.
EPICOR II Processing Status:
(auxiliary building approximate quantities)
Amount processed this week:
20,000 gallons Amount processed to date:
331.000 gallons Amount to be processed:
146,000 gallons (This value increased from last week due to tank flushing using EPICOR II processed water.)
Major Activities (Past and Present) 1.
Reactor Building Purge.
On June 2, 1980, the NRC staff recommended approval by the Commission of the decontamination of the reactor building atmosphere by controlled purging to the environment.
The recommendation was contained in the Final Environmental Assessment issued this week and discussed in a Commission meeting on June 5,1980.
The Commission will meet again on Tuesday, June 10 to consider the staff's recommendations.
2.
Unit 2 Exit Interview. An exit interview was conducted on June 4, 1980, with Unit 2 management to discuss findings from the inspection period April 27 - May 31,1980.
Three items of noncompliance were discussed.
Details of these findings will be documented in the Office of Inspection and Enforcement Inspection Report No. 50-320/80-09.
3.
Reactor Building Entry.
No further progress was made in resolving the failure of the inner door for personnel airlock (No. 2) to open.
A jammed safety lock is one of several possible causes so far identified.
The safety lock was probably activated, as designed, during the accident but is jammed into place because of a malfunction.
Other possibilities continue to be corrosion, as previously identified, and other malfunctions associated with the door closure mechanism.
4 All possible causes are being examined.
A new schedule for manned entry will not be established until the licensee makes a final detennination of the causes, which is expected to take about three weeks.
The licensee has not submitted a formal proposal on the next course of action since several plans are being reviewed.
The TMI Program Office staff is continuing to monitor the licensee's progress in this regard.
4.
Plant Vent (Stack) Uncapping.
Plans are underway for removing the metal plate installed on the 160 f t. plant stack in May 1979, (tenned
" uncapping the stack").
The cap ensured thnt all ventilation air passed through the supplementary filters installed on the auxiliary building roof af ter the March 28 event.
These filters are no longer needed due to the efficient operation of the filters located inside the auxiliary and fuel handling buildings.
Uncapping the stack is scheduled for June 10, 1980, based on a proposal by the licensee and this proposal is being reviewed by the TMI Program Office staff.
5.
Long Term Spent Resin Storage Facility.
Fif ty eight (58) of the sixty (60) spent resin storage cells in the Module "A" Long Term Waste Storage Facility contain 17 (6 x 6) liners and 42 (4 x 4) liners.
The Module B is still scheduled for completion on August 5,1980.
Based on current liner generation rate and liner stacking procedure, it does not appear the EPICOR II operations will be interrupted for lack of spent resin storage space.
6.
EPICOR 11 Processing Status.
Effective June 9 through June 15, 1980, EPICOR 11 system will be in an unscheduled outage for system maintenance.
The major maintenance items include replacement of a control valve (ALC-242),
installation of hard line piping between the EPICOR II sump and the system inlet header, and resetting of the liner water level controllers.
The licensee has completed draining of the TMI-2 condensate storage tank water and the required modifications to isolate the tank from the condensate storage system to receive EPICOR 11 processed water.
7.
(Temporary) Nuclear Sampling System (SNSl. Operation of this system was delayed due to calibration not yet performed on certain instruments for the associated ventilation system.
The operational problem (RCS guage isolation) reported last week was corrected by appropriate changes to the operating procedure.
This event was also the subject of last week's exit interview.
5 8.
Gaseous _ Effluent Monitor Calibration.
In preparation for the Unit 2 reactor building purge, the supplemental ventilation system, which was installed on the top of Unit 2 auxiliary building after the accident, will be taken out of service.
During the Unit 2 reactor building purge, gaseous effluent will be discharged through the Unit 2 vent stack. The gaseous effluent monitors at the modified ventilation system will be calibrated by the licensee.
The licensee's calculations indicate that about five to ten curies of krypton will be discharged during the monitor calibration.
The monitor calibration procedures are currently being reviewed by the NRC TMI Program Office staff.
Meetings Attended with Public Officials and Interested Groups 1.
On June 5,1980, H. Denton, B. Snyder and J. Collins attended a meeting held by the NRC Commissioners on the Final Environmental Assessment on the cleanup of the TMI-2 reactor building.
Future Meetings 1.
On June 11, 1980, J. Collins will address the Appleton Papers Management Club at 6:30 p.m. at Hardings Restaurant in Camp Hill.
2.
On June 10, 1980, H. Denton, B. Snyder and J. Collins will attend a meeting to be held by the NRC Commissioners on the issue of purging the TMI-2 reactor building.
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