ML19345H047
| ML19345H047 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 04/20/1981 |
| From: | Barrett L Office of Nuclear Reactor Regulation |
| To: | Harold Denton, Snyder B Office of Nuclear Reactor Regulation |
| References | |
| CON-NRC-TMI-81-025, CON-NRC-TMI-81-25 NUDOCS 8104300159 | |
| Download: ML19345H047 (4) | |
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LOCAL PDR April 20,1981 Site Operations file NRC/TMI-81-025 s"
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HENDRANDLM FOR:
Hamid R. Denton, Director,
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l-gr Bernard J. Snyder, Program Director, A
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TMI Program Offica M
FROM:
Lake H. Barrett, Acting Deputy Program Director, TMI Program Offica
SUBJECT:
MRC THI' PROGRAM OFFICE WEEXLY STATUS REPORT Enclosed is the status report'for the period of April 12-18, 1981.
ORIGINAL SIGNED 3Y:
R. R. Bella=y for/
Laka H. Barrett Acting Deputy Program Director TMI Program Offica
Enclosure:
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NRC TMI PROGRAM 0FFICE WEEKLY STATUS REPORT Week of April 12-18,1981 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 systems.
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, April 17,1981) (approximate values)"--
Average Incore Thermocouples: ll7'F -
Maximum Incore Thermocouple: 146*F.
r RCS Loop Temperatures:
A B
Hot Leg 115'F 118*F 1) 67'F 67*F Cold Leg ((2) 67*F 66*F RCS Pressure: 99 psig Reactor Building: Temperature: 66'F Water level: Elevation 290.7 ft. (8.2 ft. from floor) via penetration 401 manometer Pressure:
-0.25 psig Concentration: 1.4 x 10-5 uCi/cc (Krypton-85 (Kr-85)).-
(sample taken 4/13/81)
Effluent and Environmental (Radiological) Infonnation 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 10, 1987, through April 16, 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 indicate that less than 1 millionth (0.000001) of a curie was discharged. This represents less than 0.00001% of the permissable total liquid activity as specified in Technical Specifications for operational caninercial reators.
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 results:
Location April 3 - April 10,1981 3
(pCi/m )
Goldsboro 26 Observation Center 29 Middletown 36 Yorkhaven 29 All of the above levels of Kr-85 are considered to be back-ground levels.
No radiation above nonnally cccurring background levels was a
detected in any of the samples collected from the EPA's air and gama rate networks during the period from April 10, 1981, through April 17, 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 onsite continuous air sampler:
.n I-131 Cs-137 Sample Period (uCi/cc)
(uCi/cc) l HP-263 April 8,~1981 - April 15,1981
<8.7 E-14 <8.7 E-14 4.
Licensee Radioactive Material and Radwaste Shipments. The following shipments were made:
On Monday, April 13,1981, a 40 ml Unit 2 reactor coolant sample was sent to Babcock and Wilcox (B&W), Lynchburg, l
i On T r ry, April 14,1981, one 6' x 6' 'Ef ICOR-I dewatered resin ifne-Oiner N14) from Unit I was shipped to the Chem-Nuclear Site, Barnwe., South Carolina.
On Tuesday, Ag 14,1981, a Unit 2 shipment of 30 drums of laundry was sent to Tri-State Industrial Laundries, Utica, New York.
On Thursday, April 16, 1981, one 6' x 6' EPICOR-I dewatered resin liner (liner P-15) from Unit 1 was shipped to J e Chem-Nuclear Site, Barnwell, South Carolina.
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3 Major Events l.
Submerged Demineralizer System (SDS).
Region I and TMI Program Office inspections of the SDS are continuing.
Preparation of the i
Safety Evaluation Report (SER) by the TMI Program Office is in progress although some necessary information has not yet been received. The licensee has submitted a schedule for providing the needed information.
j The licensee is performing functional tests of the SOS components to verify that the equipment will operate as designed. The testing does not involve processing of contaminated water.- The fuel pool ~
in which the SDS is located is~ expected to be filled.by the end of April. The fuel pool will be filled with water that was previously processed by EPICOR-II.
2.
Reactor Building Entry. The next entry into the Unit 2 reactor l
building (RB) is scheduled for Thursday, April 30, 1981. The licensee has redesignated the entry numbering sequence. A 40 minute j
R8 entry which took place on. April.8,1981, was initially called an.
c entry 8 pre-entry. The 40 minute entry has now been redesignated as entry 8 and the April 30th entry has been designated as entry 9.
During entry 9, the licensee will perform a decontamination experiment on the 305 ft elevation of the RB. Approximately 2,000 square feet of horizontal and vertical surfaces will be decontaminated using low and high pressure water sprays. Pre-and post-decontamination radiation surveys will be used to evaluate the effectiveness of the techniques. The low and high pressure water sprays are techniques which proved effective in decontaminating the auxiliary building.
In preparation for the decontamination experiment, the licensee has submitted a proposal to modify R8 penetration R-561. The R-561 penetration is a flanged,10 inch diameter pipe through the R8 wall which was originally installed for use with the chemical cleaning system. The licensee plans to install packing glands in the outer flange of the penetration. Water spray and breathing air hoses will be routed into the R8 through the packing glands in the outer flange. The inner flange of the penetration will be removed.
The onsite NRC staff is reviewing the proposed penetration modification.
A floating sump pump is also scheduled to be installed during entry 9.
This pump is being installed to remove stanp water from the R8 in preparation for processing in the SDS. The pump will be lowered into the sump water from the 305 ft elevation through the open stairway access. The pump discharge Will be routed out of the R8 through penetration R-626 on the 347 ft, elevation. The NRC staff is reviewing a licensee proposal. to install the sump pump discharge pipe tnrough penetration R-626.
t i
f Future Meeting i
On Tuesday, April 21, 1981, Lake Barrett will. meet with area mothers to discuss various issues related to the decontamination of TMI-2.
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