ML19345E621
| ML19345E621 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 01/19/1981 |
| From: | Barrett L Office of Nuclear Reactor Regulation |
| To: | Harold Denton, Snyder B Office of Nuclear Reactor Regulation |
| References | |
| CON-NRC-TMI-81-004, CON-NRC-TMI-81-4 NUDOCS 8102050314 | |
| Download: ML19345E621 (6) | |
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UNITED STATES Q) 7 [h y 7p e.( 'h NUCLEAR REGULATORY COMMISSION WASWNGTON, D. C. 20555 3yy
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January 19, 1981 NRC/TMI-81-004
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MEMORANDUM FOR:
Harold R. Denton, Director, Office of Nuclear Reactor Regulation Bernard J. Snyder, Director, TMI Program Office
.2 FROM:
Lake H. Barrett, Acting Program Director, TMI Program Office
SUBJECT:
NRC TMI PROGRAM 0FFICE WEEKLY STATUS REPORT Eaclosed is the status report for the period of January 11 - 17, 1981.
Lake H. Barrett Acting Deputy Program Director TMI Program Office
Enclosure:
As stated cc w/ encl:
ED0 OGC Office Directors Commissioner's Technical Assistants NRR Division Directors l
NRR A/D's Regional Directors IE Division Directors X00S X0MA TMI Program Office Staff (15)
HEW EPA RO&NS Branch Chief, Region I FF&MS Branch Chief, Region I Public Affairs, Region I I
T. Elsasser l
l l
1 8102050314 p
s t4RC TMI PROGRAM OFFICE t:EEKLY STATUS REPORT Week of January 11-17, 1981 Plant _ Status Core Cooling Mode:
Cyclic natural circulation in the reactor coolant system (RCS) loops with heat transfer to reactor building 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 Mode: One decay heat removal pump to supply pressure in conjunction with variable recirculation back to the borated water storage tank (BWST).
Major Parameters (as of 0500, January 16, 1981) (approximate values)
Average Incore Themocouples: 122 F Maxieum Incore Thermocouple:
154*F RCS Loop Tempratures:
A B
Hot teg il9*F 122*F Cold Leg (1) 83*F 66*F (2) 85'F 68*F RCS Pressure:
104 psig (DVM)
Pressurizer Temperature: 69'F Reactor Building: Temperature: 62*F Water level: Elevation 290.5 ft. (8.0 ft. from floor) via penetration 401 manometer Pressure:
-0.3 psig (Heise)
Concentration:
1.5 x 10-4 uCi/cc (Kr-85) (sample taken 1/14/81)
Effluent and Environmental (Radiological) Information 1.
Liquid effluents from TMI site released to the Susquehanna River after processing, were made within the regulatory limits and in accordance with f;RC requirements and City of Lancaster Agreement dated February 27, 1980.
During the semi-annual reporting period, July 1,1980, :.
December 31, 1980, the licensee reported that minute amounts of contamination with an origin from Unit 2 was discharged from the TMI site. The liRC TMI Program Office staff verified that no accident related water, as defined in.the City of Lancaster Agreement dated February 27, 1980, was discharged from Unit 2.
Although the
2 concentraQons, of radioactive effluent were not detectable at the.
discharge 7oint, calculations indicated that less'than one ten thousandth (0.0001) of a curie of Cesium 137 (Cs-137) was discharged.
This represents less than 0.001". of the permissable total liquid effluent activity as specified in Technical Specifications for other operational comercial power reactors.
2.
EPA Environmental Data. Results from EPA monitoring of the environment around the iM1 site were as follows:
3 The EPA measured Krypton-85 (Kr-85) concentrations (pCi/m ) at several environmental monitoring stations and reported the following results:
Location
- January 5 -_ January 9, 1981 (pCi/m3)
Bainbridge 25 Goldsboro 23 Observation Center 22 Middletown 24 All of the above levels of Kr-85 are considered to be b'ack-ground levels.
No radiation above nomally occurring background levels were detected in any of the samples collected from the EPA's air and gama rate networks during the period from January 7,1981, through January 15, 1981.
3.
NRC Environmental Data. Results from NRC monitoring of the environment 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-250 January 8,1981-January 15, 1981
<9.4 E-14 <9.4 E 4.
Licen_s_ee Radioactive Material and Radwaste Sh_ipm__ents. The following shipment was mace:
On Monday, January 12,1981, a 40 ml Unit 2 reactor coolant sample was sent to Babcock and Wilcox (B&W), Lynchburg, Virginia.
On Tuesday, January 13, 1981, a drum containing a section of HPR-211 cable from Unit 2 was shipped to EG&G Idaho, Inc.,
3 On Tuesday, January 13, 1981, a drum containing two vibra; ion amps and a section of HPR-211 cable from Unit 2 was shipped to Sandia National dboratory, Albuquerque, New Mexico.
On Wednesday, January 14,1981, a Unit 1 1,000 ml waste evaporator condensate storage tank (WECST) monthly composite and a 1,000 ml decay heat."A" sample were sent to Teledyne Isotopes, Westwood, New Jersey.
On Thursday, January 15,1981, Unit 2 compacted and non-compacted low specific activity (LSA) waste was shipped to Nuclear Engineering Company, Richland, Washington.
Major Activities 1
Reactor _ Decay Heat Removal.
Reactor decay heat continues to be removed by neat transfer from the RCS to reactor building ambient.
The secondary plant is being put in a long tem layup condition.
Since steaming was secured on the "A" 0TSG one period of RCS flow occurred on January 14, 1981 No further reporting in this area will be made unless a change in cooling mode occurs.
2.
Rea_ctor Buil_ ding Purge / Entry. The sixth reactor building entry is scneduleo for February 3 and 5,1981.
The major activities to be perfomed include installation of. a closed circuit television system, work on the source range monitor, and a decontamination test. The day between the entries will be used to perform circuit checks and prepare personal equipment needed by members of the entry team.
3.
Contaminated Building Expansion Joi_nt. The licensee is finalizing a status report on efforts to cetemine the extent of contamination of building expansion joints previously reported on December 27, 1980.
This report is due to the onsite NRC staff early next week.
4.
Ground _ Water Monitoring Status. The licensee continued their well monitoring program and investigation into the possible source of the trace cesium contamination in well No. 2 located near the BWST (see attached figure).
Samples taken from well No. 2 on January 7,1981, were independently analyzed by the EPA, PA DER and NRC, confiming trace levels of Cs-137 in the 20 to 50 pCi/l range. The PA DER also reported less than detectable levels of strontium-90. These levels are less than EPA drinking water standard concentrations.
The licensee also reported that additional well No. 2 samples taken during December and early January indicated an average Cs-137 concentration of approximately 30 pCi/1.
Licensee and NRC investigations are centinuing. On January 15, 1981, the licensee inspected the 15 well locations including the area near well No. 2 and the BWST, accompanied by the NRC.
Preliminary conclusions proposed by the licensee indicate that the source of the trace cesium contamination could have resulted from previous leakage of contaminated ~ water from the BWST into the soil. This
4 conclusion is supported by the analysis of free-standing water the licensee collected from an excavation ditch near the RWST on January 12, 1981.
Although not part of the well monitoring program, ana'ijses indicated Cs-134 and Cs-137 concentrations of 220+85 pCi/1 and 870+120 pCi/1, respectively.
It is also important to note that the level at which this free-standing water was collected is above the level of water in the containment sump. The licensee is continuing the well monitoring program including expedited sample analyses for well No. 2.
Future Meetings 1.
On Thursday, January 22, 1981, L. Barrett and R. Conte will attend a public briefing in Harrisburg at the Forum, beginning at 7:30 p.m.,
sponsored by the Department of Environmental Resources concerning the status of decontamination at Three Mile Island.
Following the presentation, the NRC, EPA and Metropolitan Edison Company will be available to answer questions.
2.
The NRC's Advisory Panel for the Decontamination of Three Mile Island, Unit 2, will hold meetings in Harrisburg, on February 4,11 and 19,1981. The public is invited to~ observe all three of these meetings, which will be held at the Forum of the Education Building on Connonwealth and Walnut Streets.
Each of these. meetings are scheduled to begin at 7:00 p.m. and end at 10:30 p.m..
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