ML19341A077
| ML19341A077 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 01/12/1981 |
| From: | Barrett L Office of Nuclear Reactor Regulation |
| To: | Harold Denton, Snyder B Office of Nuclear Reactor Regulation |
| References | |
| CON-NRC-TMI-81-003, CON-NRC-TMI-81-3 NUDOCS 8101220039 | |
| Download: ML19341A077 (5) | |
Text
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UNITED STATES
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January 12, 1981 h
NRC/TMI-81-003 a
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~~75 MEMORANDUM FOR:
Harold R. Denton, Director, Office of Nuclear Reactor Regulation EG w
Bernard J. Snyder, Program Director, TMI Program Office FROM:
Lake H. Barrett, Acting Program Director, TMI Program Office
SUBJECT:
NRC TMI PROGRAM 0FFICE WEEKLY STATUS REPORT Enclosed is the status report for the period of January 4 - 10, 1981.
M AM h
.Lake. Barrett Acting Deputy Program Director TMI Program Office
Enclosure:
As stated cc:
ED0 OGC Office Directors Commissioner's Technical Assistants NRR Division Directors NRR A/D's Regional Directors IE Division Directors X005 X0MA TMI Program Office Staff (15)
HEW EPA RO&NS Branch Chief, Region I FF&MS Branch Chief, Region I Public Affairs, Region I T. Elsasser i
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NRC TMI PROGRAM 0FFICE WEEKLY STATUS REPORT Week of January 4 - 10, 1981 Plant S_t_atus_
Core Cooling Mode: Cyclic natural circulation in the reactor coolant system (RCS) loops with heat transfer to reactor building ambient.
Available Core Cooling Modes: Once Through Steam Generator (OTSG) "A" and/or "B" steaming to the main condenser; long-term cooling "B" (OTSG-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 9,1981) (approximate values) 0 Average Incore Thermocouples:
125 F 0
Maximum Incore Thermocouple:
159 F RCS Loop Temperatures:
A B
Hot Leg 1220F 125 F 0
0 Cold Leg (1) 690F 69 F 0
(2) 680F 69 F RCS Pressure: 95 psig (DVM) 0 Pressurizer Temperature: 69 F 0
Reactor Building:
Temperature: 64 F Water level: Elevation 290.6 ft. (8.1 ft. from floor) via penetration 401 manometer Pressure:
-0.4 psig (Hgise)
Concentration:
1.2 x 10-* uCi/cc (Kr-85) (sample taken 1/7/81)
Effluent and Environmental 1 Radiological) Informa_ tion 1.
Liquid effluents from TMI site released to the Susquehanna River after processing, were made within the regulatory limits and in i
accordance with NRC requirements and City of Lancaster Agreement dated February 27, 1980.
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2 2.
EPA En_vironmen_tal Data. Results from EPA monitoring of the environment
'around the INI site were as follows:
The EPA measured Krypton-85 (Kr-85) concentrations (pC1/m3) at several environmental monitoring stations and reported the following results:
Location Decem__ber 19 - December 29 1980 1
(pC1/m3)
Bainbridge 18 Goldsboro 25 Observation Center 18 Middletown 25 December 29, 1980_- January 5,19_81__
(pC1/m3)
Bainbridge 19 Goldsboro 20 Observation Center 29 Middletown 27 I
All of the above levels of Kr-85 are considered to be back-ground levels.
No radiation above normally occurring background levels were detected in any of the samples collected from the EPA's air and gamma rate networks during the period from December 30, 1980, through January 8,1981.
3.
NRC Env_ironmental Data. Results from NRC monitoring of the environment arolind th~e TMI site were as follows:
The following are the NRC air sampic analytical results for the onsite continuous air sampler:
I-131 Cs-137 Sample feriod MM _(uCi/ccl HP-249 December 30, 1980-January 8, 1981
<6.9 E-14 <6.9 E-14 4.
Licensee Radioactiv_e Materia _1 and Radwaste Shipments.
The following shipment was made:
On Monday, January 5, 1981, a 40 ml Unit 2 reactor coolant sample was sent to Babcock and Wilcox (B&W), Lynchburg, Virginia.
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3 Ma,ior Activities 1.
Reactor Decay Heat Removal. On January 5,1981, tbc licensee stopped steaming the "A" OTSG by shutting a turbine bypass valve.
This put the RCS in a " Loss to Ambient" mode of cooling which is heat transfer of reactor decay heat from both ICS loops to the a
reactor building ambient.
2.
Reactor Building Purge /_E_ntry.
Reactor building entries with associated purging is scheduled to start en January 27, 1981. At that time two entries are scheduled to occur on two separate days.
The onsite staff is reviewing the scheduled work items for these entries.
3.
Ground Water konitoring Status.
The licensee continued their well water monitoring program. The licensee eported to the NRC that a 4
sample taken from well No. 2 on October !,1980, contained trace
,l quantities of Cesium-137 (Cs-137) (34 + 6.3 pCi/1) and Cs-134 (12.8 1 5.5 pC1/1). Subsequent analysts of well No. 2 water samples taken on October 8,15, and November 5,1980, did not l
contain detectable levels of either Cs-134 or Cs-137.
Independent analysis of well No. 2 water is being performed by the NRC and EPA. The analytical results will be reported in the next weekly status report.
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4 futureMeeting On Thursday, January 22, 1981, L. Barrett 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 :tatus of decontamination at Three Mile Island.
Following the presentation, the NRC, the EPA and Metropolitan Edison will be available to answer questions.
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