ML20032A219
| ML20032A219 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 10/09/1981 |
| From: | Barrett L Office of Nuclear Reactor Regulation |
| To: | Harold Denton, Snyder B Office of Nuclear Reactor Regulation |
| References | |
| CON-NRC-TMI-81-057, CON-NRC-TMI-81-57 NUDOCS 8110280521 | |
| Download: ML20032A219 (8) | |
Text
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DISTRIBUTION TMIP0 HQ r/f TMI TE r/f RAL FILE t
NRC PDR October 9,1981 LOCAL PDR NRC/TMI-81-057 Site Operations File HE!!0RANDifi FOR:
Harold R. Denton, Director Office of Nuclear Reactor Regulation Bernard J. Snyder, Program Director THI Program Office FROM:
Lake H. Barrett, Deputy Program Director 1111 /rogram Office
SUBJECT:
N:
.hI PROGRAM OFFICE WEEKLY STATUS REPORT Enclosed is the status report for the period of October 4-9, 1 931.
Major items included in this report are:
1.
Liquid Effluent Releases 2
NRC and EPA Environmental Data 3.
Radioactive Material and Radwaste Shipments D
W.i k E ((g f]
1 4
Submerged Domineralizer System Status 5
EPICOR II Status
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-p somam 6
Incore Thermocouple Temperatures y
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7.
Radiological Protection Program Evaluation g
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Lake H. B Deputy Program Director THI Progran Office Enclosure : As stated kDRllpK050002e9 O
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7 Harold R. Denton October 9,1981
' ' b Bernard J. Snyder cc w/ enc 1:
EDO OGC Office Directors Commissioner's Technical' Assistants NRR Division Directors NRR A/D's -
Regional Directors IE Division Directors TAS EIS TMI Program Office Staff (15)
PHS EPA DOE Projects Br. #2 Chief, DRPI, RI DRPI Chief, RI Public Affairs, RI State Liaison, RI omcq TMIPO TMIPO
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h NRC TMI PROGRAM 0FFICE WE.KLY STATUS REPORT E
Week of October 4-9, 1981
'i.
Plant Status
+
. L _._
Core Cooling Mode: Heat transfer from the reactor coolant system (RCS) loops toxreactor building ambient.
Available Core Cooling ~ Modes:
Decay beat 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 0500, October 9,1981) (approximate values)
Ai/erage Incore Thermocouples :
ll4*F Maximum Incore Thermocouple:
145 F RCS Loop Temperatures:
A B
Hot Leg 109 F 112*F Cold Leg (1) 69 F 72*F (2),
70 F 70 F RCS Pressure:
90 ' psi g m
n Reactor Building:
Temperature:
62*F m
Water level :.. Elevation 289.5 ft. (7.0 ft. from floor).
..Q
- _ 0.52 psig -..via penetration *01 manometehD
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j s
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? R4 Pressure :..
Concentration:,4.3 x 10-6 uCi/cc Kr-85 (Sample 'taken,!, ~
f 9/28/81.
Weekly reactor buildirig" air'.
m' l
sampling has been discontinued while' l
the sampling system is modified for
,, continuous sampling capability.)l, 4 I
Effluent and Enyironmental (Radiological) Information
(
a l
1.
Liquid effluents from the TMI site released to the Susquehanna l
River after processing, were made within the regulatory limits andl in accordance with NRC requirements and City of Lancaster Agreement i
j dated February 27,.1980.
1 During the period October 2,1981 through October 8,1981, 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 2 millionths (0.000002) of a curie of beta emitting radionuclides were discharged.
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2.
Envi_ronmental Protection Agency (EPA) Environmentai Data.
Resul ts from EPA. monitoring of, the environment around the TM1 site were as 3
follows:
3 The EPA measured Kr-85 concentrations (pCi/m ) at several environmental monitoring stations and reported the.following -
. i resul ts :
- ry
~,..
~
September 11 - September 25, 1981 Location (pCi/m3) y Gol dsboro 26 Observation Center 21
)
Middletown 27 i
Yorkhaven Incomplete - will be reported when available i
All of the above levels of Kr-85 are considered to be background level s.
3 No radiation above normally occurring background levels was 3
detected 'in any of the samples collected from the EPA's air and gamma rate networks during the period from October 1,1981, through October 8, 1981.
- I 3.
NRC Environmental Data _.
Results from NRC monitoring of the environment j
around Ethe TMI site were as follows:.
Ly
.w m
. f The following are the NRC air sample analytical results for i,~;-
1. m&.
the onsite continuous air sampler:.
vy
,2 r
?
l } :iMh1@'g J
I-1 31 Cs-137:
Sampl e_
Period '
(uCi/cc)
(uCi/cc)- ~
l HP-288 September 30, 1981 - October 7,1981
<8.0 E.-14 <8.0 E-14
_ c, ; p<:
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Licensee Radioactive Material'and Radwaste Shipments..
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- t On Monday, Oc.tober-5,1981, a 40 ml Onit 2 reactor coolant sample was sent to Babcock and Wilcox (B&W), Lynchburg, f
On Tuesday, October 6, 1981, 20 steel boxes containing Unit 1 noncompacted trash were shipped to U.S. Ecology, Richland, Washington.
On Wednesday, October 7,1981, an EPICOR II F-1 (pre-filter) dewatered resin liner was shipped to U.S. Ecology, Richland, Washington.
e 1
~
Major Activiti_es 1.
Submerged _Demineralizer System (5051 processing of batch number 6 was completed on October 4,1981.
Transferring batch number 7 from the reactor building sump commenced on October 4,1981, and was completed on October 6,1981.
The transfer was interrupted for i
about one full day when a'few drops of radioactive water were noted on a flush connection to the transfer piping.
The leaky fitting
~
was repaired and the~ transfer continued.
The leak was limited to only.a few drops and confined to a very small area of the fuel handling building.
fio offsite releases occurred.
In :.he process of identifying the radioacti';e leak, one individual received minor skin contamination, which was successfully removed.
As o f 8 :00 AM, on October 9,1981, approximately 115,000 gallons had been transferred from the reactor building sump and a total of 65,000 gallons of reactor building sump water had been processed through the SDS. shows the SDS processing status as of October 9,1981.
2.
EPICOR II. Further processing of the SDS effluent through EPICOR II continued this week.
As of October 9,1981, approximately 125,000 gallons of SDS effluent (65,000 gallons of RB sump water) has been decontaminated.
A processing summary of the EPICOR II performance'is provided in" Typically, EPICOR II is removing greater than 99% of the Cesium-137 and Strontium-90 from SDS effluent.
To date, four of the first stage EPICOR II liners (F-1, 2, 4 and 5) and one of the third stage (K-2) liners have been removed from service due to resin bed exhaustion.
Two of the above mentioned liners (F-1 and F-2) have been d: utered and shipped to Richland, Washington for.
disposal at a commercial burial facility. -
3..
Incore Thermocouple Temperatures.. Approximately 115,000 gallons of water have been. transferred. from the reactor building (RB) basement ff to the SDS. This transfer of water lowered the water level in the f.
7 RB basement by approximately 18 inches.
Follo' wing the transfer of
^
D 4
the first 65,000 gallons of water, it was noted that reactor incore thermocouple temperatures increased (see Weekly Status Report for week ending October 3,1981).
The hottest thermocouple.(located in the center of the core) increased by 12*F and the average thermocouple temperature (average of.44 thermocouples) increased by 2. F.
The temperature increase was attributed to a. decrease.in the heat s
transfer coefficient between the primary system and the RB environment.
Prior to the transfer of the first 65,000 gallons of water, the lower dome of the reactor vessel was in contact with the sump water.
As the water level in the basement was lowered below the reactor vessel, incore temperatures increased.
The thermocouple temperatures appear to have stabilized at the new higher values and the transfer of the most recent 50,000 gallon batch of water from the basement has not affected thermocouple temperatures.
Some primary system components (RCS cold legs) extend to approximately the 285 foot elevation in the RB.
The licensee and the tiRC staff will continue to monitor the incore temperatures closely to see whether additional water level changes in the basement influence the core temperatures.
_#n H
i 4.
Radiological Protection Program Evaluation.
In November 1979 the f
NRC appointed a special technical group to examine and determine the effectiveness of the T.MI'-2 Radiological Protection Program.
As a result of the special technical group (Blue Ribbon Panel) examination, several inadequacies were identified in the TMI-2 Radiological
~~^
Protection Program.
The findings of the Blue Ribbon Panel were published in NUREG-0640 which recommended that certain improvements
~
in the licensee's Radiological Protection Program should be implemented y,.
'~ ~
prior to commencing major recovery activities.
The TMI Program Office Radiation Specialist staff conducted several inspections and evaluations of the licensee's Radiological Protection Program during 1980-1981.
Based on these inspections and evaluatfons, i
the TMI Program Office concluded that the licensee has taken the necessary corrective actions to upgrade the Radiological Protection Program by implementing the recommendations of the NRC's Blue Ribbon Panel (NUREG-0640) to the extent that the program is now adequate to support major cleanup activities.. This conclusion is contingent upon the licensee continuing to emphasize commitments to '
program implementation and expanding the radiological control and training staffs as the pace of the cleanup accelerates.
An upgrading of the personnel dosimetry program is also required.
The onsite'..
TMI Program Office -Radiation. Specialist staff will continue to examine progress on these items and will continually assess the licensee's performance relative to the Radiological Protection Program.
+
Future Meetings 1.
On Tuesday, October 13, 1981, Lake Barrett will address. the Downing-town Rotary Club to give an update on the cleanup efforts at TMI
,'ai-y
}
- j and discuss the functions of the NRC._
1 2.
The NRC's Advisory Panel for the Decontamination of Three Mile O
Island Unit 2 will ' meet October 21,1981, in York, Pennsylvania and s
Ryember 16, 1981, in Lebanon, Pennsylvania.
At both meetings, the
~
panel phns to discuss the current status of cleanup activities at
~.
Three Mile I: land.
h The October 21 meeting will be held at 7:00 PM to 10:00 PM in the Hotel Yorktown, 48 Easi. Market Street, York.
The November 16 meeting will be held from 7:00 PM to 10:00 PM in the Municipal Building, 400 South 8th Street, Lebanon.
Both meetings are open to the public.
3.
On Saturday, November 14,1981, at 8:00 PM, Lake Barrett will participate in a panel. discussion at the Elizabethtown Public Library on the government's response to the TMI accident.
4 ATTACHMENT 1 l
SDS PROCESSING
SUMMARY
AS OF OCTOBER 9, 1981 l
i Gallont Processed:
65,000 Gallons Flow Rate:
5 GPM Source:
Reactor Building Sump Water System Configuration:
1 Process Train ;
~
1 l
4 Zeolite Vessels in Path Ion Exchange Media:
Homogeneous Mixture 3
IONSIV IE 96: 4.8 ft per vessel 3
LINDE A: 3.2 ft per vessel I
Performance; (ConcentrationsinuC/ml)
I l
' EFFLUENT PERCENT REMOVED DECONTAMINATION FACTOR RADI0IS0 TOPE INFLUENT 4
Cesium 134 10 2.3 x 10-4 99.999 4.3 x 10 6.5 x 10-4 99.999 1.5 x 105 Cesium 137 100,
l Strontium 90 3.4 l1.4.x.10-2 99.59 2.4 x 102
- Antimony 125
<7.7 x 10-1 1.l?x 10-2
- Ruthenium 106
<8.9 x 10-1
<3.9,x 10-4l 2
.x
' 5.6.x.10-1
-<4.3;x 10-4'
'~
~
- Cerium 144
- Cobalt 60
<3.4 x 10-2 1.<2.3.x'10 -
7:e
- Not Expected to Change Appreciably J j, m
6 1
m.-
rb i
e i
4il) y.
.i Q.
uww.F a.
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3
l ATTACHMENT 2 t
EPICOR II PROCESSING Sut9(ARY THRU OCTOBER 9, 1981 Gallons Processed:
125,000 Fiow Rate:
10 GPM J
Source:
SDS Effluent System Configuration:
3 Resin Liners in 5e^ ries l
Ion Exchange Media:
Organic Resins 3
1st 6x6 Liner:
Cation (s120 ft )
3 2nd 6x6 Liner:
Cation / Anion (s12p ft )
3rd 4x4 Liner:
Mixed Bed (s40 ft-)
.. = -
Performance:
(ConcentrationinuCi/ml)
RADI0IS0 TOPE INFLUENT EFFLUENT PERCENT REMOVED DECONTAMINATIONJFACTOR Cesium 134 2.3 x 10-4 9.6(-7) 99.6 240 Cesium 137 6.5 x 10-4 5.0 (-6 99.3 150 l
Strontium 90 1.4 x 10-2 3.2 (-5 99.8 440 Antimony 125 1.1 x 10-2.
2.0 (-6 99.9 5500 4
Ruthenium 106
<3.9 x 10 4
<6
(-7)
<4.3 x 10-1.8. -
<2.3 x 10-5
<3 e
e e
g g
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