ML19317H329
| ML19317H329 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 05/12/1980 |
| From: | Jay Collins Office of Nuclear Reactor Regulation |
| To: | Harold Denton, Snyder B Office of Nuclear Reactor Regulation |
| References | |
| CON-NRC-TMI-80-086, CON-NRC-TMI-80-86 NUDOCS 8005280013 | |
| Download: ML19317H329 (6) | |
Text
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NRC/TMI-80-086 MEMEORANDUM FOR:
H. R. Denton, Director, 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 0FFICE WEEKLY STATUS REPORT Enclosed is the status report for the week of May 3-9, 1980.
/
d John T. Collins Deputy Program Director THI Program Office
Enclosure:
As stated cc:
EDO 0GC Office Directors Commissioner's Technical Assistants NRR Division Directors NRR A/D's Regional Directors IE Division Directors I
X00S X0MA HEW EPA Public Affairs, RI T. Elsasser TMI Program Staff 1
I 8005280019
tiRC TMI PROGRAM 0FFICE WEEXLY STATUS REPORT Week of: May 3 - 9,1980
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.- r 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: OTSG "B" to the main condenser; long tenn cooling "B" (OTSG-B); decay heat removal.
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 1600, May 9,' 1980) (approximate values)
Average Incore Thermocouples: 153*F Maximum Incore Thermocouple:
189*F RCS Loop Temperatures:
A B
Hot Leg 146*F 149*F Cold Leg (1) 84*F 10l*F (2) 82*F 103*F RCS Pressure:
78 psig (Heise) 83 psig (DVM - now controlling)
Pressurizer Temperature:
268*F (Saturation Pressure 26 psig)
Reactor Building:
Temperature:
79 F Pressure:
-1.4 psig (Heise)
Water level: Elevation 290.6 ft. (8.1 ft. from floor) via decay heat system j
Elevation 290.2 ft. via penetration 401 manometer Environmental & Effluent Information 1.
Liquid effluents from THI-l released to the Susquehanna River, after processing, were within the limits specified in Technical Specifications.
2.
fio liquid effluents were discharged from TMI-2.
3.
Results from EPA monitoring of the environment around the TMI site were:
EPA environmental stations registered background levels for air particulate and water samples.
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Gas / Air (KR-85) sample results during tha period April 25 3
Center - 22 pCi/m3,,Middletown 21 pCi/m3,pCi/m, THI Observation through May.2,1980 were: Goldsboro - 19 and Bainbridge'-
21 pCi/m3 The EPA states that the Kr-85 background concentration in the vicinity of TMI to be betwe n 20 and 40 pCi/m3, Instantaneous direct radiation readings showed no levels above natural background (average 0.015 mR/hr) at the 18 environ-mental monitoring stations.
4.
NRC Environment:1 Data The West Screen House continuous air sample (HP-215) for the sampling period April 30 through May 7, 1980, has been delivered to the EPA Coordination Center for analysis. The most current results received from the EPA for air sample HP-210 taken April 2-9, 1980, indicated that no reactor related radioactivity was detected.
Results of the environmental TLD measurements for the period March 18 to April 30, 1980, indicate no gama levels above natural ~ background.
Fifty-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.
5.
Radwaste shipments offsite were as follows:
On Monday, May 5,1980, a Unit 2 reactor coolant sample was sent to the Babcock and Wilcox facility, Lynchburg, Virginia, for chemical and radiochemical analysis.
On Friday, May 9, 1980, the licensee made one LSA shipment of low level waste, to Barnwell, South Carolina.
NRC personnel surveyed the shipment and inspected shipping documents prior to granting approval.
6.
EPICOR II Processing Status:
(auxiliary building approximate quantities)
Amount processed this week:
8,000 gallons Amount processed to date:
255,000 gallons Amount to be processed:
194,500 gallons l
Major Activities (Past and Present) 1.
Reactor Coolant System (RCS) Pressure Reduction. On April 15, 1980, RCS pressure was reduced from 300 psig to 190 psig. The pressure l
was further reduced to 135 psig on April 29, 1980. The pressure was reduced to 90 psig on May 9, 1980. The primary system responded predictably to the pressure reductions. Water samples drawn from the letdown system on May 5,1980, indicate that dissolved gas concentrations in the RCS will remain below saturation at 100 psig.
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However, due to limited water. circulttion, it is assumed that gas saturated water and gas' pockets do exist in portions of the RCS.
The following gas pocket volumes versus primary pressure have been calculated:
RCS pressure Gas volume 300 psig 50 cubic feet 190 psig 57 cubic feet 135 psig 106 cubic feet 100 psig 138 cubic feet The above pressure / volume relations have been verified during several pressure changes by comparing the amount of makeup / letdown to the resultant RCS pressure changes.
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The RCS pressure reductions have not produced a noticeable effect, on the secondary system.
Both 'A and B loops continued to " burp" periodically. The A loop " burp" interval increased from 21 to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. The B loop " burps" sporadically every 80 to 110 hours0.00127 days <br />0.0306 hours <br />1.818783e-4 weeks <br />4.1855e-5 months <br />.
The decreased " burp" frequency in the A loop is attributed to higher heat loses to the reactor building atmosphere.
The reactor building evaporative cooling system was activated on April 15, 1980, to reduce the reactor building pressure. The " burp" frequency decreased after the reactor building cooling system was activated.
The RCS leak rate appears to have decreased as a result of the
~ pressure reductions. Quantitative leak rate data will be provided after additional leak / makeup volumes are compiled.
Pressurizer heaters will not be used now that pressure is reduced to 100 psig. The cycling of the heaters produced pressure fluctuations.
The heaters had been used to maintain the water in the pressurizer just below the saturation temperature.
In this condition, the pressurizer was a potential source of pressure for the RCS in the event of an unplanned pressure reduction.
The hazards associated with an unplar.aed depressurizatica have decreased with the decrease in thermocouple temperatures below ambient boiling.
2.-
Decay Heat Removal System Valves, DH-V-1 and DH-V-171. A meeting bett.een the TMI Program Office staff and licensee representatives has been scheduled for Monday, May 12, 1980, to discuss the potential problems which may be encountered. after DH-V-1 and DH-V-171 are opened. When open, the valves will provide a flow path from the reactor coolant system (RCS) to the mini decay heat removal (MDHR) system in the auxiliary building.
The rising water level in the reactor building is expected to cover the valve operators in the near future; this may preclude the option to close the valves.
When open, the valves expose the decay heat removal system to RCS pressure and as a result, RCS pressure must be maintained below approximately 370 psig to prevent exceeding the decay heat removal system relief valve setting. After the valves are cpened, radiation levels may increase in some sections of the auxiliary building.
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Reactor Building Entry. The reactor building entry which was scheduled for April 24, 1980, was postponed when the National Institute of Occupational Safety and Health (NIOSH) inspected the Bio Marine Bio Pac 60 breathing units and found that unauthorized modifications had been made. The Bio Pac 60 has a service life of 60 minutes and was selected to be used by the reactor building entry team.
The licensee has rescheduled the entry for May 20, 1980, and is revising procedures to either use the Bio Pac 60, if NIOSH recertifies the unit, or to use the Mine Safety Appliance Company (MSA) Model 401 breathing apparatus.
The MSA unit has a service life of only 30 minutes and as a result, would require shortening the entry to 15 minutes. The TMI Program Off!ce staff is reviewing the proposed changes.
4.
Mini Decay Heat Removal (MDHR) System. The licensee contracted a private consulting firm to review the design of the MDHR system.
The consulting firm recommended numerous modifications to the existing system.
If implemented, the proposed modifications could delay system completion for 12 months. The original system was scheduled to be operational by May 23, 1980. The consulting finn's j
l recommendations will be reviewed by the licensee and the NRC THI Program Office.
5.
Ground Water Monitoring Program. A total of 15 ground water monitoring wells are being used to monitor activity in the ground water around the THI-2 reactor building.
Water samples are taken weekly.
No new sample analysis results have been received since the last weekly status report.
Representatives of the Commonwealth of Pennsylvania have recommended that all water pump"d from the monitoring wells should be released through site discharge point 001 to the river. All water discharged through point 001 is continuously monitored and recorded.
The licensee is opposed to this recommendation on the grounds that it unnecessarily complicates the sampling process and would prefer to release the water to the storm drains which discharge to the holding pond which is sampled on a weekly basis. The TMI Program l
Office would support either course of action since both are monitored release points. The issue remains unresolved at this time.
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Meetings Held with Public Officials and Interested Groups _
- 1. ' On May 5,1980, J. Collins addressed the 9th grade Civic Classes at East Junior High School, Harrisburg.
2.
On May 5,1980, at 7:00 p.m., J. Collins, T. Els sser and M. Bills, EPA, conducted a briefing in Manchester for officials invited from the following communities:
Conewago Township (West Shore), Dover Township, East Manchester Township, Hellam Township, Manchester, Manchester Township, Mount Wolf, Springettsburg, Warrington Township, and York Haven. A total of 22 officials wera invited; 3 attended.
3.
On May 7,1980, J. Collins appeared on a talk program on WAHT radio, Lebanon, called "Two Way Radio" to answer questions from listeners concerning the cleanup operations.
4.
On May 7,1980, at 7:30 p.m., Comissioner Hendrie, H. Denton, J. Collins, B. Snyder and M. Bills, EPA, met in Harrisburg with representatives of TMI Alert to discuss cleanup operations at THI-2.
5.
On May 8,1980, J. Collins addressed the Lower Swatara Lions Club at 6:30 p.m. at the Skyways Inn.
G.
On May 9,1980, J. Collins and A. Fasano met with B. Grier and J. Allen to discuss the Inspection and Enforcement Program at THI-1 and THI-2.
Future Meetings 1.
On May 12, 1980, J. Collins will participate in the graduation cermany for the Comunity Monitoring Program to be held at the Penn State Capitol Campus.
2.
On Ilay 13, 1980, the Atmoic Safety and Licensing Board will conduct hearings concerning the Restart of TMI-l at the Federal Building in Harrisburg.
3.
On May 14,1980, at 7:30 p.m., J. Collins will meet with the Lower Swatara Board of Comissioners to discuss the cleanup operations at
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Ti!I-2.
4.
On June 9,1980, J. Collins will meet with the Pennsylvania Arson Association in Lancaster to discuss clean-up operations at TMI-2.
5.
J. Collins will present an invited paper entitled, "URC Involvement During the THI Accident" at the 1980 Annual Meeting of the American Nuclear Society, June 8-13, 1980, in Las Vegas, Nevada.
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