ML19347F392
| ML19347F392 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 05/04/1981 |
| From: | Barrett L Office of Nuclear Reactor Regulation |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| CON-NRC-TMI-81-027, CON-NRC-TMI-81-27 NUDOCS 8105190149 | |
| Download: ML19347F392 (6) | |
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f MEMORANDU t FOR:
Harold R. Denton, Director, Office of Nuclear Reactor Regulation Bernard J. Snyder, Program Director, TMI Program Office FROM:
Lake H. Barrett, Acting Deputy Program Director, TMI Program Office
SUBJECT:
NRC TMI PROGRAM 0FFICE WEEKLY STATUS REPORT Enclosed is the status report for tne period of April 26-May 2,1981.
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Lake H. Barrett Acting Deputy Program Director 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 X005 X0MA TMI Program Office Staff (15)
PHS EPA DOE Projects Br. No. 2 Chief, DPRI, RI DPRI Chief, RI Public Affairs, RI T. Elsasser 8105190 M(L
liRC TMI PROGRAM 0FFICE WEEKLY STATUS REPORT i
Week of April 26.- May 2,1981 Plant Status Core Cooling Mode: Heat transfer from the reactor coolant system (RCS) loops to reactor bt.ilding ambient.
Available Core Cooling Modes: Long-term cooling "B" (once through steam generator-B); decay heat removal systems.
RCS Pressure Control Mode:
Standby Pressure Control (SPC) System.
Backup Pressure Control Modes: Mini Decay Heat Removal (MDHR) System.
Decay Heat Removal (OHR) System.
Major Parameters (as of 0430, May 1,1981) (approximate values)
Average Incore Thermocouples: ll4*F Maximum Incore Thermocouple:
141*F RCS Loop Temperatures:
A B
Hot Leg ll2*F ll5'F Cold Leg (1) 66*F 65'F (2) 66 F 65*F RCS Pressure: 99 psig Reactor Building: Temperature: 64*F Water level: Elevation 290.7 ft. (8.2 ft. from floor) via penetration 401 manometer Pressure:
.6 psig Concentration: Less than LLD (4.3 x 10 6)
(sample taken 4/30/81)
Effluent and Environmental (Radiological) Information 4
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 dated February 27, 1980.
During the period April 24, 1981, through April 30,1981, the effluents contained no detectable radioactivity at the discharge point although individual effluent sources which originated within Unit 2 contained minute amounts of radioactivity.
Calculations i
indicate that less than 2 millionths (0.000002) of a curie was discharced.
This represents less than 0.00002% of the pemissable total liquid activity as specified in Technical Specifications for operational commercial reactors.
2 2.
Environmental Protection Agency-(EPA) Environmental Data.
Results 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 retal ts :
Location April 17 - April 24,1981 (pci/m4)
Goldsboro 22 Observation Center 25 Middletown 33 Yorkhaven 25
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All of the above levels of Kr-85 are considered to be back-ground levels.
No radiatiori 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 April 24, 1981, through April 30, 1981.
3.
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 ensite centinuous air sampler:
I-131 Cs-137 Sample Period (uCi/cc)
(uCi/cc)
HP-264 April 15,1981 - April 22,1981
< 8.5 E-14
<8.5 E-14 HP-265 April 22,1981 - April 29,1981
< 8.6 E-14
<8.6 E-14 Environmental TLD measurements for the period February 5 to March 12,1981 around TMI, and the Island stations for the period November 28, 1980 to March 13, 1981, indicated gamma radiation to be at the natural background levels.
Fi f ty-eight TLD's registered doses ranging from 0.17 mR/ day to 0.32 mR/ day.
Average dose was 0.24 mR/ day.
These dose rates are consistent with natural background radiation in the TMI area.
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Licensee Radioactive Material and Radwaste Shipments On Monday, April 27,1981, a 40 ml Unit 2 reactor coolant i
sample was sent to Babcock and Wilcox (B&W), Lynchburg, Virginia.
i On Monday, April 27,1981, one 4' x 4' 'EPICOR II dewatered resin liner (liner DF13) from Unit 2 was shipped to U. S.
Ecology, Richland, Washington.
On Tuesday, April 28,1981, one 4' x 4' EPICOR II dewatered l
resin liner (liner DF-4) from Unit 2 was shipped to U. S.
l Ecology, Richland, Washington.
4 29,1981, one 4' x 4' EPICOR II dewatered On Wednesday (, Aprilliner DF-7) from Unit 2 was shipped to U. S.
resin liner Ecology, Richland, Washington.
Major Events 1.
Reactor Building Entry.
The ninth entry into the Unit II reactor building (RB) was completed on Thursday, April 30, 1981.
During i
this entry preparations were completed for a decontamination experiment which will be performed on the next entry.
Additionally, a floating i
pump was placed in the R8 sump water.
This pump will be used to pump sump water to the submerged demineralizer system.
Eight persons entered the RB during the entry and based on preliminary indicators i
(dosimeters), the maximun individual exposure was 618 millirem.
The next RB entry is tentatively scheduled for May 14, 1981.
The RB was purged prior to the entry to reduce airborne Krypton concentrations.
Air samples taken before and after the purge indicate that approximately three curies of Krypton-85 were released to the environment.
2.
Ground Water Monitoring. Test boring two was placed on an accelerated sample analysis schedule when minute annunts of radioactive cesiun were detected in the water samples taken during the months of December through March. The cesium activit the lower limit of detection (LLD)y subsequently decrea:ed tc below on the most recent analysis results available from test boring two from samples taken on April 22, 1981.
Tritium activity in the test borings has remained in the same range as j
previously reported. An exception has been test boring nine. Samples taken from test boring nine on February 25, 1981, indicated an increase in tritium activity to 6310 picocuries per liter (pci/L).
Samples taken on March 4,11, and 18,1981, indicated 3660, 2940 and 3310 pCi/L of tritium respectively. Test boring nine is located adjacent to the borated water storage tank (BWST).
During the time when tritium actively increased in test boring nine, excavation work was in progress around the BWST.
The excavation may have altered the normal flow paths of the ground water.
Leaks from the BWST associated valves and fittings may have been the source of the ground water contamination.
The licensee has constructed a trough and a rain cover around ti.e potentially leaky BWST components.
The weekly monitoring of the grounc water activity will continue.
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4 3.
Submerged Demineralizer System (SDS).
Preparation of the Safety Evaluation Report (SER) by the IMI Program Office is in progress although some necessary information has not yet been received.
On April 30,1981, the licensee submitted a revised schedule for providing the needed information.
The licensee is performing functional tests of the SDS components to verit'y that the equipment will operate as designed. The testing does not involve processing of contaminated water.
The licensee has pumped approximately 112,000 gallons of EPICOR II processed water into the fuel pool.
The fuel pool will be completely filled when the functional testing allows and concerns raised about airborne trittura concentrations are resolved (this item is discussed in the next paragraph).
4.
Elevated Tritium levels in Fuel Handling Building.
At approximately 10:00 p.m. on April 29, 1981, licensee representatives obtained analytical results for an airborne concentration of 3.1 x 10-b uCi/cc (tritium, H-3) for a greb sample taken between 2:00 p.m. to 7:00 p.m. earlier in the day.
The sampling process was perfonned while EPICOR II processed water, which contained 0.22 uCi/ml of H-3, was transferred to partially fill the "B" Spont Fuel Pool, which will be und to shield the Submerged Demineralizer System during its operatie.. The sample was taken inside the pool.
Subsequent samples were immediately taken at the 347' elevation (working area) of the Fuel Handling Building (FHB) adjacent to the "B" pool.
The second sample resgits became available at 4:45 a.m., April 30,13C1, and showed 2.2 x 10 - uCi/cc (H-3).
The 347' elevation was subsequently declarea an airborne radioactivity area.
The transfer process was secured at 2:30 a.m., April 30, 1981.
At approximately 10:00 a.m., a sample analysis indicated 1.2 x 10-6 uCi/cc, (H-3) and personnel entry into the area was resumed since the airborne (H-3) concentration was reduced to below 2S percent of MPC (occupational maximum permissible concentration per 10 CFR 20).
Licensee analytical results of a grab sample taken at 0553 to 0740 cn April 30, 1981, from the FHB exhaust indicated an H-3 concentration of less than the Lower Limit for Detection (LLD < 4.5 x 10-9 uCi/cc).
The NRC resident staff have compared the monthly H-3 effluent and determined that the H-3 airborne releases during April (2.8 Cl) were essentially the same as March (2.7 Ci).
Based on the monthly effluent data it appears that the slightly elevated and localized H-3 rencentrations in the FHB during April 29 and 30,1981, has not contributed to any significant increase in the plant monthly H-3 effluent.
Further, the licensee initiated a bioassay for selected personnel present at tr.e 347' elevation area of the FHB during the period of the apoarent increase in H-3 airborne concentrations.
The source of the apparent localized H-3 concentrations is still being examined by the onsite staff.
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Meeting Held On Thursday, April 30, 1981, Harold Denton and Lake Barrett attended the annual convention of the Pennsylvania Osteopathic Medical Association at the Host Farm in Lancaster.
Mr. Denton addressed the convention at its opening session followed by an open question session. The majority of the questions centered around general issues regarding the cleanup program of TMI Unit 2, and the recent Japanese event at Tsuruga Nuclear Power Plant.
Future Meetings 1.
On Tuesday, May 5,1981, Lake Barrett will conduct a plant tour for area mothers.
2.
On Wednesday, May 13, 1981, Lake Barrett and Oliver Lynch will participate in a meeting with the Susquehanna Valley Alliance on the Programmatic Environmental Impact Statement.
The meeting will be held at 7:30 p.m., in the Friends Meeting House in Lancaster at 110 Tulane Terrace.
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