ML20004C331
| ML20004C331 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 06/01/1981 |
| From: | Barrett L Office of Nuclear Reactor Regulation |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| CON-NRC-TMI-81-031, CON-NRC-TMI-81-31 NUDOCS 8106030193 | |
| Download: ML20004C331 (5) | |
Text
DISTRIBUTION
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TMJ,, SITE r/f (GENTRAL FILE NRC PDR LOCAL PDR June 1, 1981 Site Operations file NRC/TMI-81-031 W
MEMORANDW FOR:
Harold R..'Denton, Director, Office of, Nuclear Reactor Regulation Bernard J. Snyder, Program Director.
TMI Program Office FR(M:
lake !!. 'Barrett, Acting Deputy Program Director, IMI Progras Office StBJECT:
NRC TMI PliOGRAM OFFICE WEEKLY STMUS REPORT
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Enclosed is the status report for the period of May 23 - 30, 1981.
Original signed by Lake H. Barrett /
Lake H. Barrett Acting Deputy Pr%.
Director i
TMI Program Office
Enclosure:
As stated
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NRR Division Directors.
NRR A/D's Regional Directors IE Division Directors XOOS X0MA TMI Program Offica Staff.(15)
PHS EPA DOE Projects Br. No. 2 Chief. DPRI, RI DPRI Chief, RI D00D gn Alta A I Public Affairs RI T. Elsasser I1UUn
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.g NRC TMI P!!0 GRAM OFFICE WEEKLY STATUS REPORT Week of May 23 - 30, 1981 Plant Status Core Cooling Mode: Heat transfer.from the reactor coolant system (RCS) loops to Reactor Building ambient.
Available Core Cooling Modes: Long-term cooling "B" (once through:
steam generator-B); decay heat removal systens.
RCS Pressure Control Mode: Standby Pressure Control (SPC) System.
Backup Pressure Control Modes: Mini Decay Heat Removal (MDHR) System.
Decay Heat Removal (DHR) System /
Major Parameters (as of 0400, May 29,1981) (approximate values)
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Average Incore Thermocouples: 117 F Maximum Incore Thermocouple:
144*F RCS Loop Temperatures:
A B
Hot Leg 113 F ll6*F Cold Leg 1)'
67*F 67*F 2) 68*F 67*F RCS Pressure: 98 psig Reactor Build' ng: Temperature: 72*F i
Water level: Elevation 290.8 ft. (8.3 ft from floor) via penetration 401 manometer Pressure:
-0.5 psig Concentration: 2 3 x 10-5 uCi/ml Kr-85 (Sample taken 5/ 25/81)
Effluent and Environmental (Radiological) Information L
1.
Liquid effluents from the TMI site released to the Susquehanna River after processing, were made wfthin the regulatory limits and in accordance with NRC requirements and City of Lancaster Agreement dated February 27, 1980.
During the period May 22, 1981, through May 28, 1981, the effluents I
contained no detectable radioactivity at the discharge point although individual effluent sources which originated within Unit 2 contained minute amounts of radioactivity.
Calculations indicate that less l
than 1 millionth (0.000001) of a curie of Cs-137 was discharged. This represents less than 0.00001% of the pennissable total liquid activity as specified in Technical Specifications for operational commercial reactors.
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2.
Airborne effluents are reported'on a monthly basis.
3.-
Environmental Protection Ager.cy (EPA) Environmental Data.
Results from EPA monitoring of the environment.around the TMI site were as follows:
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.The EPA measured Kr-85 concentrations (pC1/m ) at several environmental monitoring _ stations and reported the following
- resul ts:
Location
- May 15 '- May 22,1981 (pCi/m3)
Goldsboro 25 Observation Center 29 Middletown 28 Yorkhaven 22 All of the above levels of Kr-85 are considered to be back-ground levels.
3 Th-installation of tritium (H ) monitoring devices has been cgmpleted at the above listed locations..It is expected that H3 environmental results will be routinely reported by EPA in about three to five weeks.
i No radiation above normally occurring background levels was detected in any of the samples collected from the EPA's air and gama rate networks during the period from May 21, 1981, through May 28, 1981.
4.
NRC Environmental Data. Results from NRC monitoring of the environ-ment around the TMI site were as follows:
t The following are the NRC air sample analytical results for the onsite continuous air sampler I-1 31 Cs-137 l
Sample Period (uCi/cc)
(uCi/cc)
HP-269 May 20, 1981 - May 27, 1981
<8.2 ::-14 <8.2 E-14 5.
Licensee Radioactive Material and Radwaste Shipments On Friday, May 22, 1981, one 4' x 4' EPICOR-II dewatered resin l
liner (liner DF-15) from Unit 2 was shipped to U.S. Ecology, l
Richland, Washington. This shipment was r.ot reported in the i
t status report for the period of May 17-22, 1981.
l On Tuesday, May 26,1981, a 40 ml Unit 2 reactor coolant sample was sent to Babcock and Wilcox (B&W) Lynchburg, Virginia.
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28, 1981, 54 drums and 8 metal boxes of On Thursday, May compacted and non-compacted Unit 1 low specific activity (LSA) waste were shipped to' the Chem-Nuclear Site, Barnwell, South Carolina. _
On Thursday, May 28, 1981, an empty. shipping cask used in Unit. 2 was shipped to the Chem-Nuclear Site, Barnwell, South Carolina.
- Major Activities 1.
Submerged Demineralizer System (SDS).
Preparation of the Safety Evaluation Report (SER) by the TMI Program Office is in progress although some necessary information has not yet been received. On May 13, 1981, the licensee submitted a revised schedule for providing the needed information. The outstanding -infonnation will be provided in early June 1981.
. Functional tests are complete with th'e exception of a few items which are undergoing engineering evaluation and further testing.
Operator training on components not involved with the ~ outstanding functional testing has been initiated. The operator training does not involve processing of contaminated water.
2.
Reactor Building (RB) Purge 'and Entry. The eleventh entry into the Unit 2 RB was completed on Thursday, May 28, 1981.
All the tasks scheduled for the entry were compleud. The entry tasks included the following:
Polar crane personnel safety equipment installation.
Sump survey with portable gamma spectrometer.
Lighting relay repair, Replacement of an inoperable radiation monitor, Repair on the RB intercom system, Surveillance, servicing, photography, and radiation surveys of l
components in the vicinity of the pressurizer,
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Floating sump pump discharge hose connection to the SDS.
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The radiation survey of the area near the pressurizer indicated l
that the ambient radiation levels on top of the pressurizer was i
approximately 3 R/hr (gamma). Radiation hot spots were detected at boron deposits under valves on top of the pressurizer which apparantly leaked at one time. There was no indication of recent leakage (the primary system is depressurized to less than 100 psig). The radiation levels at the hot spots were 8 to 10 R/hr (ganna) and approximately t-30 Rad /hr (beta). Ambient radiation levels below the plane of the pressurizer top were approximately 1 R/hr. A contact reading of the insulation.on the tope of the "A" steam gederator was approximately 1 R/hr.
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.,s A cursory radiation survey on the polar crane indicated 80 mr/hr (ganna) and 80 mrad /hr (beta). An electrical / mechanical inspection and a thorough radiation survey of the polar crane is planned'for the next entry.
The next RB entry is tentatively scheduled for June 25,1981.
Future Meeting
. On Thursday, June 4,1981, the Advisory Panel for the Decontamination.of TMI Unit 2 will meet from 7:00 p.m. to 10:00 p.m. in the City Council Chambers, Kendig C. Bare Public Safety Building, 208 North Duke Street, Lancaster. At this meeting, which is open for public observance, the Panel will discuss Radiation Worker Exposure and Health Effects.
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