ML20041B458
| ML20041B458 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 02/01/1982 |
| From: | Barrett L Office of Nuclear Reactor Regulation |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| CON-NRC-TMI-82-005, CON-NRC-TMI-82-5 NUDOCS 8202240015 | |
| Download: ML20041B458 (10) | |
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, "'"hDR(('ALFILE February 1,1982 NRC/TMI-82-005 LOCAL PDR Site Operations File N Sic.
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MEMORANDUM FOR:
liarold R. Denton, Director Office of Iluclear Reactor Regulation s\\
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Bernard J. Snyder Program Director TMI Program Office FROM:
Lake H. Barrett, Deputy Pro Jram Director TMI Program Office
SUBJECT:
NRC TMI PROGRAM OFFICE WEEKLY STA11]S REPORT Enclosed is the status report for the period of January 24, 1982 to January 30, 1982. Major items included in this report are:
Liquid Effluent Releases NRC and EPA Environmental Data Radioactie Material and Radwaste Shipments
'S Submerged Domineralizer System Status iW i
g EPICOR II 6
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Reactor Building Entries EE,9
'YU 79 1 EPICOR II Prefilter Status k#a Public Meetings b
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Lake H. Barrett Deputy Program Director TMI Program Office
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Enclosure : As stated OF FICE k
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PDR ADOCK 05000320 R
PDR NRC FORM 318110 8 01 N R C M O 2 4 0 OFFICIAL RECORD COPY
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ED0 OGC Office Directors Comissioner's Technical Assistants NRR Division Directors NRR A/D's Regional Directors IE Division Directors TAS EIS TMI Program Office Staff (15)
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NRC FORM 318110 80l N R C M O 2 4 0 OFFICIAL RECORD COPY
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NRC TMI PROGRAM 0FFICE WEEKLY STATUS REPORT January 24, 1982 - January 30, 1982
_ Plant Status g
Coce Cooling Mode: Heat transfer from the reactor coolant syst (RCS) loops to reactor building ambient.
Available Core Cooling Modes: Decay heat removal systems.
Long term cooling "B" (once through steam generator-B).
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 0600, January 29,1982) (approximate values)
Average Incore Thermocouples : 106 F Maximum Incore Thermocouple:
136'F RCS Loop Temperatures:
A B
Hot Leg 97 F 100"F-Cold Leg (1) 77 F 80 F (2) 80 F 84 F RCS Pressure: 96 psig Reactor Building: Temperature :
61 F Water level :
Elevation 285.2 ft. (2.7 ft. from floor)
Pressure :
-0.15 psig Airborne Radionuclide Concentrations :
<5.0 x 10-6 Kr85
<5.7 x 10-9 H3 (samples taken 1/28/82)
Effluent and Environmental (Radiological) Information 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 January 22, 1982, through January 28, 1982, 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 one millionth (0.000001) of a curie;of cesium was discharged.
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_ 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 seve al
-E environmental monitoring stations and reported the folfowing resul ts :
Location December 28. l__981 - January 31,1982 (pCi/m3)
Goldsboro 29 Observation Center 22 Middletown 27 Yorkhaven 22 All of the above levels of Kr-85 are considered to be background level s.
No radiation above normally occurring background levelr. vas detected in any of the samples collected from the EPA's air and gamma rate networks during the period from January 20,1982, through January 28, 1982.
3.
NRC Environmental Data.
Results from NRC monitoring of the environment around the TM1 site were as follows:
The following are the NRC air sample analytical results for the onsite continuous air sampler:
I-1 31 Cs-137 Sample Period (uCi/cc)
(uCi/cc)
HP-304 January 20, 1982 - January 28, 1982
<5.4 E-14 <5.4 E-14 4.
Licensee Radioactive Material and Radwaste_ Shipmentis.
On Tuesday, January 26, 1982, one drum containing two,1-foot sections of Unit 1 steam generator tubes was shipped to Battelle-Columbus Laboratory, Columbus, Ohio.
On Wednesday, January 27, 1982, 34 one liter Unit 1 samples, taken from various tanks and locations, e.g. core flood tanks, bleed tanks, reactor building spray pumps, etc., were shipped in 14. containers to Babcock and Wilcox (B&W), Lynchburg, Virginia.
On Wednesday, January 27, 1982, one drum containing four,1-foot sections of Unit I steam generator tubes was shipped to Babcock and Wilcox (B&W), Lynchburg, Virginia, d
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On Wednesday, January 27, 1982, seven drums and one LSA. container (box), containing steam generator inspection and repair equipment, were returned to Babcock and Wilcox (B&W)
Lynchburg, Virginia.
A Major Activities T
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Submerged Demineralizer System (SDS).
Processing of batch 17 was completed on January 29, 1982.
On January 30,1982, the transfer of batch 18 from the reactor building sump was commenced.
SDS performance parameters for batch 17 are included in Attachment 1.
The radioactivity in the spent fuel pool water is now approximately 6 x 10-3 uc/ml (gross 8-y activity).
The supplemental spent fuel pool cleanup system is expected to become operational during the next report period.
2 EPICOR II.
The EPICOR II system continued to process SDS effluent during the week.
Performance parameters are enclosed.
3.
Reactor Building Entries.
One of two scheduled reactor building (RB) entries was completed during the last week in January.
Tasks performed during the completed entry included video taping of areas in the RB and additional testing of neutron source range monitor, NI-2.
The scheduled load test of the crane mounted supports for the power lift was not perfonned.
The second of the two scheduled entries was cancelled after the RB purge was secured due to problems in the purge train electrical power supply.
The electrical problems in the RB purge system have been repaired and RB entries are scheduled to resume during the first week in February.
In addition to. load testing, the power lift supports during the entries next week, the power lift will be assembled in the RB and work will commence to ensure that fire fighting stations inside the RB.are operable.
A site NRC Radiation Specialist with the TMI Program Office will participate in the next reactor building entry.
The inspector will perform independent radiological measurements to verify the licensee's information.
Also, an independent verification of general conditions in the RB will be made.
The licensee performance and compliance with radiological safety requirements will be verified under actual working conditions in the RB.
4.
_EPICOR II Prefilter Status.
Forty-nine first stage prefilter (PF)
EPICOR II liners are currently stored in the onsite solid waste
. storage facility.
These 4' x 4' PF liners were generated during the processing of auxiliary building water (approximately 5.00,000 gallons) after the March 28, 1979 accident.
Typically these liners contain 40 ft3 of fon exchange media with radioactivity loadings from 200 to 1,300 curies predominately as cesium-137.
A drawing of the solid waste storage facility witt liner locations is included as.
l DOE, through the July 1981 memorandum of understanding with NRC, has agreed to accept these 49 EPICOR II PF for R&D purposes and for final disposition.
One of the higher activity liners (PF-lj6 was shipped by DOE to Battelle Columbus Laboratories on May 19, 1981, for detailed analysis.
These analysis indicated no signifficant 5-degradatiun of liner integrity nor ion exchange media. Measurable amounts of hydrogen gas generation in the pre filter were confirmed; however, oxygen which is necessary for a comSustible mixture, was also confirmed to be depleted to a level to preclude any internal combustion or explosion. Because of the hydrogen inventory, GPU has instituted procedural controls and monitoring to assure no flammable condition nor ignition sources exist at the storage module area.
The licensee's current program for shipping these 49 prefilters includes steps for inerting, sampling and integrity inspection. A special inerting tool has been developed and tested at the Idaho National Laboratory for use by GPU.
This tool, which is scheduled for shipment to TMI in early February, will both purge the excess hydrogen gas and inert the liner with a nitrogen cover gas.
After inerting and leak testing, the liners will be shipped individually to the Idaho National Laboratory in standard type "B" shipping casks which are designed to withstand transportation accidents.-
GPU is currently developing support hardware and procedures for the inerting and handling evolutions. The first EPICOR II prefilter (PF-2) inerting is tentatively scheduled to begin in late April 1982.
Shipments should begin in early May 1982.
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I 1 i Meetings Held 1.
The NRC'.s Advisory Panel for.the Decontamination of TMI. Unit 2 met on.
January 28, 1982, in Harrisburg.
Status reports were given-by GPU, NRC, EPA, DOE, and comments were offered by several members;of the
__ public.
EPA representatives stated that their Agency was npt reducing operations at.IMI despite nationwide reductions in many of EPA's programs.
Dauphin County Commissioner Larry Hachendoner supported decoupling the Unit 1 startup from the Unit 2 cleanup by applying the Deferred Energy Surcharge which is due to expire in June 1982, toward the cleanup.
No date has been set for a future meeting.
2 On Friday, January 29, 1982, Lake Barrett met with a group of area mothers to discuss various TMI issues, including the status of Unit 1 steam generator tube conditions, the forthc.aing decontamination experiment, and the financial problems.
Future Meetings 1.
On Friday, February 26, 1982, Lake Barrett will be speaking for the dinner meeting being held by the Engineers Week Joint Planning Council to honor Lehigh Valley's Engineer of the Year and Young-Engineer of the Year.
2.
On Saturday, March 13, 1982, Lake Barrett will address the Society of Manufacturing Engineers in Williamsport, PA, on the cleanup of TMI and general aspects of nuclear power.
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.I ATTACHMENT I a
_I Yb SDS Performance for Batch Number 17 Average Average Average Radionuclide_
Influent Effl uent DF (uc/ml)
(uc/ml)
Cesium 137 94 9.1 x 10-4
- 1. x 105 Strontium 90 3.0 7.6 x 10-3 4,o;x 102 l
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EPICOR II Perfonnance l
January 11,1982 to January 28, 1982 Average Average Average Radionuclide Influent Effluent DF (uc/ml)
(uc/ml )
Cesium.137 9.6 x 10-4
<2.6 x 10-7
>3.4 x 103 Strontium 90 6.2 x 10-3 4.8 x 10-6 1.3 x 103 Antimony 125 1.1 x 10-2
<4.1 x 10-7
>2.5 x 104 l
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