ML20040D106
| ML20040D106 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 01/11/1982 |
| From: | Barrett L Office of Nuclear Reactor Regulation |
| To: | Harold Denton, Snyder B Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8201300188 | |
| Download: ML20040D106 (8) | |
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-C9ITRAL FILE NRC PDR LOCAL PDR January ll,1982 Site Operations File NRC/THI-82-001 0
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f1ECal/ED MEMORANDUM FOR:
Harold R. Denton, Director Z
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Office of Nuclear Reactor Regulation b asummrm%
2 Bernard J. Snyder, Program Director EmmaaYr TMI Program Office g
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FROM:
Lake H. Barrett, Deputy Program Director fG TMI Program Office
SUBJECT:
liRC THI PROGRAM OFFICE WEEKLY STATUS REPORT Enclosed is the status report for the period of December 27,1981 to January 9,1982. Major items included in this report are:
Liquid Effluent Releases NRC and EPA Environmental Data Radioactive Material and Radwaste Shipments Submerged Domineralizer System Status EPICOR II Reactor Building Entries Unit 2 Unusual Event
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PUC Rate Change Approval Public Meetings Original s!cced.by L*0 H+ Barnttf Lake H. Barrett Deputy Program Director TMI Program Office
Enclosure:
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fiRC Tiu PROCEAM OFFICE '.;EEKLY STATUS REPORT December 27, 1981 - January 9,1982 Plant Status Core Cooling Mode: Heat transfer from the reactor coolant system (RCS) loops to' reactor building ambient.
^Avrllable Core ' Cooling Modes :
Decay heat removal systems.
Long te'rm cooling "B" (once through steam generator-B).
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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, January 8,1982) (approximate values)
Average Incore Thermocouples : 117 F Maximum Incore Thermocouple:
135 F
-c RCS Loop Temperatures:
A B
-e Hot Leg 99*F 103*F-Cold Leg (1) 80 F 83*F
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(2) 86 F 91 F RCS Pressure: 96 psig Reactor Building:
Temperature :
63*F Water level:
Elevation 285.8 ft. (3.3 ft. from floor)
Pressure :
-0.2 psig 3
Airborne Radionuclide Concentrations: 2.5 x 10-7 uCi/cc H 4.8 x 10-6 uCi/cc Kr85 (Sample taken 12/16/81) l l
Effluent and Environmental (Radiological) Information
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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 December 25, 1981 through January 7,1982, 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 ten thousandth (0.0001) of a curie of l
tritium was discharged.
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2.
Environ *. ental Protection Acency (EPA) Environmental Data.
The EPA Middletown Office has not received the analytical results for Kr-85 measurements around the TMI site from the EPA's Counting Laboratory at Las Vegas, Nevada. When these results become available, they will be included in a subsequent report.
No radiation above normally occurring background levels was
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- detected in any of the ' samples collected from EPA's air and gamma rate networks during the period from December 21, 1981,
',q through January 7,1982.
3.
NRC Environmental Data.
Results from NRC monitoring of the environment around the TMI site were as follows:
The following are the NRC air sample analytical results for the onsite continuous air sampler:
-c I-1 31 Cs-137 S amp,l_e Period (uCi/cc)
(uCi/cc)
-G HP-300 December 23, 1981 - December 30, 1981
<6.3 E-14 x6.3 E-14 HP-301 December 30, 1981 - January 8,1982
<6.5 E-14 <6.5 E-14 4.
Licensee Radioactive Material Radwaste Shipments.
On Thursday, January 7,1982, three 250 mi samples of effluent from EPICOR II batch 60 were mailed to Science Applications Inc. (SAI), Rockville, Maryland.
On Friday, January 8,1982, two 250 mi samples of SDS effluent were mailed to SAI, Rockville, Maryland.
On Friday, January 8,1982, a 'one liter sample of Unit 1 Waste Evaporate Condensate Storage Tank (WECST) was mailed to Teledyne Isotopes Inc., Westwood, New Jersey.
Major Activities 1.
Submerged Demineralizer System (SDS).
Processing of batch 14 was completed on December 27, 1981.
From December 27,1981 to December 28, 1981, approximately 43,000 gallons of water (batch 15) were transferred from the reactor building sump.
Processing of batch 15 commenced on December 29, 1981 and was completed on January 4,1982.. From January 5,1982 to January 6,1982, approximately 19,000 gallons df water (batch 16) were transferred from the reactor building sump.
Processing of batch 16 commenced on January 6,1982.
The total amount of water transferred from the reactor building sump as of January 8,1982, is approximately 400,000 gallons.
SDS performance parameters for batch 14 and 15 are attached.
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2.
EPICOR II.
Epicor 1: processing of SDS effluent continued this week.
h The latest performance parameters for EPICOR II are attached.
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3.
Reactor Building Entries.
Reactor building (RB) entriec 27 and 28 1
were completed on January 5 and 7,1982.
The major task during i
both entries was the installation of supports for an electrically powered lift which will be used to transport personnel and equipment
.from the refueling floor (347 ft;. elevation) to the polar crane..
After the decontamination experiment, a small section of the 347 ft.
L elevation floor will be removed to enable the lift to reach down to the 305 ft. elevation.
Additional RB tasks which were completed i
this week include testing of source range neutron monitor, N1-2; sampling for iodine 129; and area radiation surveys.
Due to delays with hardware modifications, the gross decontamination RB experiment has been rescheduled for early February 1982.
The mjor RB tasks for the entries will continue in January'u. remainder of the month will inc1 de continued w
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.m lift device and the installation of a high pressure water hose and an air line through a RB penetration.
During the entries this week it was verified that the area radiation e
level in the enclosed stairway at the 305 ft elevation increased-from 8 R/hr (measured when sump water level was at approximately
,l the 291 ft. elevation) to 18 R/hr (measured when the sump water level was at approximately the 286 ft. elevation).
Eight fixed points on the 305 ft, elevation have been monitored regularly for l
changes in, radiation levels sinc,e the RB sump processing began.
Except for the radiation increase in the enclosed stairway, no significant changes in area or airborne radiation levels have been On November 16, 1981, it was reported in the Weekly Status g
noted.
4 Report that there was an apparent radiation level increase in an area above the reactor coolant drain tank, however, subsequent measurements indicated that the radiation level in the area has remained essentially constant.
The cause of the radiation level, increase in the enclosed stairway is being invastigated.
The open stairway is now being used for normal access to the 347 ft. elevation.
Particulate Radioactivity Increase in Unit _ 2 Auxiliary and Fuel j
4.
Handling Buildings (Unusual Event).
At 9:53 AM on January 8,1982, I
the licensee declared an Unusual Event as a result of an indication l
of increased airborne radioactivity in the Unit 2 Auxiliary and f
Fuel Handling Buildings.
Persennel working in the butidings were The licensee's initial invrtigation of immediately evacuated.
this event indicated that the increased airborne radioactivity in the buildings could have resulted from blowdown of the service air lines into'a potentially contaminated floor drain.
The licensee reported a slight increase in the plant airborne effluent monitor (HPR-219).
Initial offsite dose calt.ulations i
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boundaries, indicated a minute fraction of a millirem, at the s te d
An offsite which is indistinguishable from natural backgroun.
7 h of the TMI L; iiE survey team took measurements at about 0.5 mile sout ffsite.
- 3,J)2 Visitors Center and confirmed no detectable radioactivity o d at 1
The possible source of this airborne activity was isolate All in-plant monitors and effluent monitors were trending sii:4 r4 The licensee terminated,the 10:00 AM.
down to nprmal readings at 10:48 AM.ite staff continues to examine
, Unusual Event at 11 :30 AM. HRC onsthe cause.and circumstan
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On Friday, January 8,1982, Pennsylvania tiated between PUC Rate Change Approval.
Public Utilities Commission approved a settlemen Met-Ed and 5.
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Penelec on rate requests.
the first in January, the
'I d the plant change to Met-Ed's rate structure:
second if NRC authorizes normal operation at Un h 7,Z tive hours, and the third in the May/ June period.
Central cleanup, if New Jersey takes a similar action for Je year
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for TMI-2 l
will be generated by rate payer revenues specifical y An accelerated cleanup level will require approximately l
-c million a year so that other elements of funding will.be.
cleanup.
The net result of the hich also involve
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$120-130 necessary to supplement the $50 million.
rate changes on Metropolitan Edison rate payers, w i
tion of expected reduction in purchase power costs and ter
'P' GPU also June 1982'will be about the same as in December 1981.
tion projects that the revenues produced by the proposed rate ac f
curred in would avert a possible cash shortage that might ha i
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5 Public Meetings l
I 1.
On Monday, January 11, 1982, Lake Barrett will participate in a television (WPIK Channel ll, Pittsburg) program to discuss the TMI situation as it pertains to the national and Pennsylvania l
energy situation.
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2.
The.NRC's Advisory Panel for t'he Decontamination of TMI Unit 2 will be meeting on January 13, 1982, and January 28,.1982, from 7:00 PM to 10:00 PM at the Holiday Inn, 23 South Second Street in
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Harrisburg.
The meetings will be open for public observation.
At both meetings, the Panel will discuss alternative strategies for
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assuring financial resources to complete the TMI-2 cleanup.
3.
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.
4.
On Saturday, March 13, 1982, Lake Barrett will address the Society
-C of Manufacturing Engineers in Williamsport, PA, on the cleanup of TMI and general aspects of nuclear power.
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ATTACHMENT SDS Performance for Batch Number 14
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Average
' Average Average Radio'n'uck i dk'.
Infl uent Effluent _
DF T
(uc/ml)
(uc/mi) 4 Cesium 137 82 1.3 x 10 3 6.3 x 10 2
Strontium 90 2.7
(
8.3 x 10-3 3.2 x 10 e
SDS Performance for Batch Number 15
-G Average Average Average Radionuclide Infl uent_
Effluent DF (uc/ml)
(uc/ml )
{
5 Cesium 137 92 8.3 x 10-4
-1.1 x 10 Strontium 90 3.0 7.6 x 10-3
- 3. 9' x 102 EPICOR II Pe'rformance
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December 17, 1981 to January 5,1982 l
Average Average Average i
Radionuclide Influent Effluent DF (uc/ml)
(uc/ml) 4 f
Cesium 137 2.1 x 10-3
<1.7 x 10-7
>1.2 x 10 3
Strontium 90 8.8 x 10-2
<1.1 x 10-5
>1.5 x 10 4
Antimony 125 8.8 x 10-3
<3.6 x 10-7
>2.5 x 10 e
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