ML19331B762
| ML19331B762 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 08/04/1980 |
| From: | Jay Collins Office of Nuclear Reactor Regulation |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| CON-NRC-TMI-80-120 NUDOCS 8008130070 | |
| Download: ML19331B762 (5) | |
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NUCLEAR REGULATORY Commission
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August 4, 1980 NRC/TMI-80 120 MEMORAN9UM 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 July 27-August 2,1980.
John T. Collins Deputy Program Director a
TMI Program Office
Enclosure:
As stated cc:
EDO OGC Office Directors Comissioner's Technical Assistants NRR Division Directors NRR A/D's Regional Directors IE Division Directors X00S X0MA RO&NS Branch Chief, Region I HEW EPA Public Affairs, RI T. Elsasser TMI Program Staff T
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s NRC TMI PROGRAM OFFICE WEEKLY STATUS REPORT Week of July 27-August 2,1980 Plant Status oCore Cooling Mode:
Cyclic natural circulation in the "A" reactor coolant system (RCS) loop via the "A" once through steam generator (OTSG), steaming tn 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 term 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 0600, August 1,1980) (approximate values)
Average Incore Thermocouples: 141 F Maximum Incore Thermocouple:
187 F RCS Loop Temperatures:
A B
Hot Leg 140 F 143 F Cold Leg (1) 104 F 82 F (2) 115 F 84 F RCS Pressure: 94 psig (Heise) 97 psig (DVM-controlling)
Pressurizer Temperature:
91 F Reactor. Building:
Temperature:
88*F
' {F Water level:
Elevation 290.3 ft. (7.8 ft. from floor) via penetration 401 manometer Pressure:
-0.5 psig (Heise)
Noble Gas Concentration: 3.43 x 10-3 uCi/cc (Kr-85)
Environmental & Effluent Information 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:
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meNare ce e e eew
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s EPA environmental stations registered background levels for i
air particulate and water samples. Gamma scan results for all sampling locations were negative.
_ Instantaneous direct radiation readings showed an average level of 0.012 mrem /hr at the 17 monitoring stations.
An apparent increase in gamma radiation was noted from 3:00 - 4:00 p.m. on Monday, July 28, 1980, at the TMI North gate monitoring station.
The maximum reading was approximately 10 times the normal readings for that station.
The air sample that was taken at the same location and time was examined by gamma spectrostupy and showed no evidence of reactor related radioactive material. The gamma radiation recorder in use at that station failed during the next sampling period.
Invest-igation into the cause of the elevated reading is continuing but at this time EPA believes that the most probable cause is instrument malfunction.
The TMI Program Office staff has inspected the licensee's effluent records and operation logs and found no correlation between the licensee's evolutions and the elevated reading.
4.
NRC Environmental Data The following are the NRC air sample analytical resuits for the onsite continuous air sampler:
I-1 31 Cs-137 Sample Period (uCi/cc)
(uCi/cc)
HPR-226 July 23-July 30, 1980
<4.8E-14
<4.8E-14 No reactor related radioactivity was detected.
The licensee provided the following monthly inventory of Kr-85 releases for 1980:
January-80 Ci, February-80 Ci, March-63 Ci, April-69 Ci, May-85 Ci, June-447 Ci, and July (to midnight
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July 10) 42,615 Ci. This results in a total Kr-85 release of 43,439 Ci, as of midnight July 10, 1980.
The licensee stated that the uncertainty for Kr-85 released during the purge is + 10%.
l Environmental TLD measurements for the period May 29, to July 2,1980, indicate gamma radiation to be at the natural background levels.
Fifty-nine TLD's registered doses ranging frcm 0.10 mR/ day to 0.20 mR/ day. Average dose was 0.13 mR/ day.
These dose rates are consistent with natural background radiation in the TMI area.
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5 Radioactive Material and Radwaste Shipments were as follows:
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On Monday, July 28,1980, a 40 ml Unit 2 reactor coolant sample was shipped to Babcock & Wilcox (B&W) Lynchburg, Virginia.
On Thursday,' July 31, 1980, an EPICOR I dewatered resin liner (017) was shipped to Nuclear Engineering Company (NECO),
Richland, Washington.
On Friday, August 1,1980, an EPICOR I dewatered resin liner (D-14) was shipped to Nuclear Engineering Company (NECO),
Richland, Washington.
Major Activities 1.
EPICOR II System. A scheduled two week outage for this system is to start on August 11, 1980.
The major work effort on this system is various maintenance items to improve personnel safety.
2.
Reactor Building Purge.
During the week the reactor building concentration results continued to indicate offgassing of Kr-85 from the reactor building sump water.
On Friday, August 1,1980, a purge of the reactor building atmosphere was conducted for two hours and 23 minutes releasing a HPR-219A monitor readings.pproximately 57 Ci of Kr-85, based.on Weekly purges on Friday afternoons are planned.
NRC review of data for prepurge and postpurge analytical results on reactor building atmosphere samples is being monitored.
3.
Reactor Building Entry.
The next scheduled entry into the reactor building is during the week of August 15, 1980.
A data package on the previous entry is being prepared by the licensee.
4.
Mini Decay Heat (MDH) System.
During the week the licensee submtted proposed Technical Specifications for operation of the MDH system.
Associated surveillance requirements (Recovery Operating Plan) as yet were not submitted.
Major outstanding items for system operation are: Replace carbon steel filter housings with stainless steel
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filter housing; perform the functional test of the system; complete operator training; and issue associated operating procedures; to address MDH system operation.
The system startup is expected late August 1980.
5.
Ground Water Monitoring Program.
A map showing the locations of the 15 ground water sampling wells annotated with the latest, July. 7,1980, tritium concentraticas in picocuries per liter is attached. The highest tritium concentration was detected in 0W-17.
This well is located approximately 20 feet from the borated water storage tank valve manifolds which are known to have leaked periodically.
Wells MW-1 and 0W-15 were drilled at each end of the island to I
serve as indicators of the riormal background tritium activity.'
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