ML19347D111
| ML19347D111 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 03/02/1981 |
| From: | Barrett L Office of Nuclear Reactor Regulation |
| To: | Harold Denton, Snyder B Office of Nuclear Reactor Regulation |
| References | |
| CON-NRC-TMI-81-017, CON-NRC-TMI-81-17 NUDOCS 8103110070 | |
| Download: ML19347D111 (5) | |
Text
AR RfC UNITED STATES
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8 NUCLEAR REGULATORY COMMISSION o
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WAEHINGTON, D. C. 20555
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March 2, 1981 NRC/TMI-81-017 s
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I47 0g MEMORANDUM FOR:
Harold R. Denton, Director,
'#3 Office of Nuclear Reactor Regulation 9
D Bernard J. Snyder, Program Director, O
6 TMI Program Office FR0il:
Lake H. Barrett, Acting Deputy Program Director, TMI Program Office
SUBJECT:
NRC TMI PROGRAM 0FFICE WEEKLY STATUS REPORT Enclosed is the status report for the period of February 22-28, 1981.
f /a w G a W Lake H. Barrett Acting Deputy Program Director Till 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 l
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X0MA TMI Program Office Staff (15) l PHS EPA
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Projects Br. No. 2 Chief, DDRI, RI DPRI Chief, RI Public Affairs, RI T. Elsasser 81081100 70
NRC TMI PROGRAM 0FFICE WEEKLY STATUS REPORT Week of February 22-28, 1981 Plant Status Core Cooling Mode: Heat transfer from the reactor coolant system (RCS) loeps to reactor building ambient.
Available Core Cooling Modes: Long-term cooling "B" (or.ce through steam generator-B); decay heat removal systems.
RCS Pressure Control Mode: Standby Pressure Control (SPC) System.
Backup Pressure Control Mode: Mini Decay Heat Removal (MDHR) System.
MajorParameters(asof0500, February 27,1981) (approximate values)
Average Incore Thermocouples: 118 F Maximum Incore Thermocouple:
151 F RCS Loop Temperatures:
A B
Hot Leg 116*F 119 F 1) 66*F 66 F ColdLeg((2) 66 F 65 F RCS Pressure: 99 psig Reactor Building: Temperature: 61 F Water level: Elevation 290.6 ft. (8.1 ft. from floor) via penetration 401 manometer Pressure:
-0.4 psig (Heise)
Concentration: 6.7 x 10-b uCi/cc (Kr-85)
(sample taken 2/24/81)
Effluent and Environmental (Radiological) Irformation 1.
Liquid effluents from 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 February 20, 1981, to February 26, 1981, the effluents contained no detectable radioactivity at the discharge point although individual effluent sources which originated within Unit 2 contained minute amounts of activity. Calculations indicate that less than two millionths (0.000002) of a curie of cesium-137(Cs-137) was discharged.
This represents less than 0.00002% of the permissable tetal liquid activity as specified in Technical Specifications for operational coninercial reactors.
2 2.
EPA Environmental Data. Results from EPA monitoring of the environment around the TMI 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 February 13 - February 20, 1981 3
(pCi/m )
Bainbridge 21 Goldsboro 22 Observation Center 28 Middletown 25 All of the above levels of Kr-85 are considered to be background levels.
No radiation 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 February 18, 1981, through February 26, 1981.
3.
NRC Environmental Data. Results from NRC monitoring of the environment around the TMI site were as follows:
The folloaing are the NRC air sample analytical results for the onsite continuous air sampler:
1-131 Cs-137 Sample Period (uCi/cc)
(uCi/cc)
HP-256 February 18, 1981-February 25, 1981
- Sc.mple results are not available due to a temporary outage of EPA counting equiphant. EPA reported that the counting equipment will be restored to service by March 2, 1981. NRC air monitoring results will be reported in the next status report.
4.
Licensee Radioactive Material and Radwaste Shipments. The following shipments were made:
On Monday, February 23, 1981, a 40 ml Unit 2 reactor coolant sample was sent to Babcock and Wilcox (B&W), Lynchburg, j
I 1
On Friday, February 27, 1981, 55 drums containing Unit 2 contaminated laundry were shipped to Tri-State Industrial j
Laundries, Utica, New York.
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3 Major Activities 1.
Submerged Demineralizer System (SDS). SDS construction is approximately 84% complete.
Initial testing of completed portions is in progress while construction is ongoing. The testing verifies the proper operation of equipment and does not involve processing radioactive water. The licensee is preparing an update to the Technical Evaluation Report which should be available for NRC review by the middle of March (thereporthasbeendelayedapproximatelytwoweeks).
2.
Contaminated Building Expansion Joint. During the period Feburary 21-23, 1981, there were intermittent and sometimes heavy rains in the TMI area.
The air intake tunnel sump filled with water, and some water seeped past the doorway from the tunnel to the service building. Contamination had previously been fcund in the cork building-expansion joint in this area, so a sample of the seepage was taken by the licensee.
Later, a water sample was taken in a previously sampled expansion joint in the auxiliary building.
Both of these samples, together with an expansion joint sample taken in the control building after the previous heavy rain (on February 11,1981) are being analyzed for radioactive contamination.
3.
Reactor Building Entry and Purge. The seventh entry into the Unit 2 reactor building has been delayed until March 11, 1981. The rescheduling was necessitated by delays in constructing equipment which is to be used during the entry. The equipment includes a device to pass sump water through a zeolite column and collect the effluent for analysis and a second device which will be used to obtain four samples of sump water for off site analysis. Additional tasks which are scheduled for the seventh entry include the servicing of valves, additional radiation surveys, polar crane inspection, and intercom telephone repairs. Twelve men are scheduled to participate in the entry which will extend over a two day period.
Prior to the entry, a reactor building purge will be conducted to reduce the concentration of Kr-85 gas. Calculations indicate that there will be less t'ian 6 curies of Kr-85 released during the purge.
4 Meeting Attended On Tuesday, February 24, 1981, Lake Barrett had a spontaneous meeting at the NRC's Middletown.0ffice with area mothers, They expressed their feelings that TMI Unit 1 should not be restarted while Unit 2 is being cleaned up. They also felt that the NRC Commissioners were not adequately considering the stress that would be created in some area residents if Unit I was restarted. Lake Barrett assured them that their concerns would be communicated to the Commissioners and other appropriate !!RC staff. He also mentioned that they could express their concerns on a more formal' basis, in writing or orally, before the Atomic Safety and Licensing Board on March 5.1981, at 7:00 p.m. in Harrisburg at the William Penn Museum.
Future Meeting On Tuesday, March 10, 1981, Lake Barrett will meet with area mothers to discuss various issues related to the decontamination of TMI Unit 2.
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