ML101970292: Difference between revisions
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| number = ML101970292 | | number = ML101970292 | ||
| issue date = 06/16/2010 | | issue date = 06/16/2010 | ||
| title = | | title = Tritium Document | ||
| author name = | | author name = | ||
| author affiliation = - No Known Affiliation | | author affiliation = - No Known Affiliation | ||
| Line 16: | Line 16: | ||
=Text= | =Text= | ||
{{#Wiki_filter:Quad Cities Tritium Late in 2007, Quad began investigating slightly elevated tritium levels in wells associated withy its Groundwater Protection Initiative (GPI). At the time of the initial GPI sampling, the licensee believed that the tritium levels were associated with historical leaks and spills that had residual tritium contamination. | {{#Wiki_filter:Quad Cities Tritium Late in 2007, Quad began investigating slightly elevated tritium levels in wells associated withy its Groundwater Protection Initiative (GPI). At the time of the initial GPI sampling, the licensee believed that the tritium levels were associated with historical leaks and spills that had residual tritium contamination. However, after additional wells were placed, the licensee clearly identified that tritium was entering the groundwater via an ongoing leak associated with the condensate storage tank (CST) or underground piping. Wells placed near that area yielded results in the millions of picocuries per liter (pCi/I). The licensee's samples have not identified any other isotopes (i.e., gamma emitting radionuclides) in the groundwater. Perimeter wells near the site boundary have not detected any radioactivity leaving the restricted area; however, the licensee will need to closely evaluate its well placement based on the current plume and potentials for channeling. | ||
However, after additional wells were placed, the licensee clearly identified that tritium was entering the groundwater via an ongoing leak associated with the condensate storage tank (CST) or underground piping. Wells placed near that area yielded results in the millions of picocuries per liter (pCi/I). The licensee's samples have not identified any other isotopes (i.e., gamma emitting radionuclides) in the groundwater. | Recently, the licensee began excavating soil near the Reactor Building, where it suspected the leakage. The radiation protection (RP) staff was surveying the area, as the soil was removed (intermittent surveys based on excavation). The licensee was using a vehicle with a suction device and multiple filtration systems.to capture the soil and sediment (see example picture below). | ||
Perimeter wells near the site boundary have not detected any radioactivity leaving the restricted area; however, the licensee will need to closely evaluate its well placement based on the current plume and potentials for channeling. | The licensee had three persons working the excavation. Two visitor-badged individuals (no TLD/ED) were using shovels to loosen the soil, and one badged (w/TLD) was manipulating the arm that has the suction end. All should be considered radiation workers, and the individuals were trained qualified during the most recent outage. The two were badged as visitors for security purposes only. The area was -not a designated RCA or RMA, so no formal RP controls were in place. Essentially, the RP staff performed routine surveys as the excavation occurred and instructed the workers to stop work if they ideihtified water or anything abnormal. The 6' | ||
Recently, the licensee began excavating soil near the Reactor Building, where it suspected the leakage. The radiation protection (RP) staff was surveying the area, as the soil was removed (intermittent surveys based on excavation). | |||
The licensee was using a vehicle with a suction device and multiple filtration systems. to capture the soil and sediment (see example picture below).The licensee had three persons working the excavation. | II ýC individuals were instructed to walk through the building to the RCA entrance and monitor through the PCMs at the end of the day. | ||
Two visitor-badged individuals (no TLD/ED) were using shovels to loosen the soil, and one badged (w/TLD) was manipulating the arm that has the suction end. All should be considered radiation workers, and the individuals were trained qualified during the most recent outage. The two were badged as visitors for security purposes only. The area was -not a designated RCA or RMA, so no formal RP controls were in place. Essentially, the RP staff performed routine surveys as the excavation occurred and instructed the workers to stop work if they ideihtified water or anything abnormal. | On about May 27, the workers encountered water and debris near the line and stopped work (about 10 feet of depth). When they monitored via the PCMs, the licensee identified contamination on the workers' clothing. No contamination was on the skin. The levels were in the 10K ballpark. The licensee will be sending the TLD out for processing and has also collected a bioassay from the individual, who is suspected to be the maximally exposed. The other two workers were rotating in-and-out of the area with their shovels, while the individual with the TLD was constantly working with the suction end of the truck. Very preliminarily, the licensee has estimated the maximum, effective dose field to be about 40 mrem/hr, with a bounding exposure time of about 45 - 60 minutes. Consequently, the upper bound would be about 40 mrem. The licensee will contact Wayne Slawinski and/or Steve Orth with the TLD results later in the week. | ||
The 6' | The RP department surveyed the excavation area and identified very elevated levels of radiation, well beyond that seen anywhere else in the industry. The most recent survey documents external levels of up to 170 millirem per hour (mrem/hr) at contact and 140 mrem/hr at 30 cm. The RP staff is controlling and posting the area as a high radiation area. The area is tented off with plastic covering. The licensee is also posting the truck as a radiation area and will be bringing it into the building for evaluation and potential decontamination. The licensee performed surveys at the exhaust of the truck and verified that no contamination was present, validating that the filtration system was effectively containing the material. | ||
No contamination was on the skin. The levels were in the 10K ballpark. | Soil in the area has very significant dose rates (see survey). Most of the radiation is from a very small area of soil, but the licensee has to determine the full characteristics (including depth). A bucket of soil has dose rates of up to 70 mrem/hr on contact. The gamma spectroscopy results indicate very high levels of cobalt-60 (2.7E-3 micocuries per gram) and cesium-137 (1.3E-2 microcuries per gram). The licensee estimates that the leak must have been active for a number of years to accumulate that level of contamination, based on source term in the tank and the decay of the nuclides. The licensee has not had significant levels of those nuclides in the tank for at least 10 years. The licensee indicated that the material consists of very, very fine silt that appears to have provided very effective filtration of the leakage. | ||
The licensee will be sending the TLD out for processing and has also collected a bioassay from the individual, who is suspected to be the maximally exposed. The other two workers were rotating in-and-out of the area with their shovels, while the individual with the TLD was constantly working with the suction end of the truck. Very preliminarily, the licensee has estimated the maximum, effective dose field to be about 40 mrem/hr, with a bounding exposure time of about 45 -60 minutes. Consequently, the upper bound would be about 40 mrem. The licensee will contact Wayne Slawinski and/or Steve Orth with the TLD results later in the week.The RP department surveyed the excavation area and identified very elevated levels of radiation, well beyond that seen anywhere else in the industry. | The licensee plans to continue work in the area under very rigorous RP controls. The tented area will have access from the Reactor Building airlock. The workers will be donning protective clothing and full dosimetry/RWP controls. The licensee plans to have air sampling within the tented area and outside to monitor for any potential airborne release (to workers or environment). Based on the weather, the work will begin in the next-few days., | ||
The most recent survey documents external levels of up to 170 millirem per hour (mrem/hr) at contact and 140 mrem/hr at 30 cm. The RP staff is controlling and posting the area as a high radiation area. The area is tented off with plastic covering. | The licensee will be evaluating the cause of the line leakage and the extent of the condition. | ||
The licensee is also posting the truck as a radiation area and will be bringing it into the building for evaluation and potential decontamination. | Very preliminary thoughts are that debris was left in the area while the High Radiation Sampling System building was installed post-TMI. The debris rubbed against the stainless steel piping from vibrations from the Turbine Building and mechanically damaged the piping n-Th'nsee will be investigating further, and the-PantSUpport-Te-am lc osely. | ||
The licensee performed surveys at the exhaust of the truck and verified that no contamination was present, validating that the filtration system was effectively containing the material.Soil in the area has very significant dose rates (see survey). Most of the radiation is from a very small area of soil, but the licensee has to determine the full characteristics (including depth). A bucket of soil has dose rates of up to 70 mrem/hr on contact. The gamma spectroscopy results indicate very high levels of cobalt-60 (2.7E-3 micocuries per gram) and cesium-137 (1.3E-2 microcuries per gram). The licensee estimates that the leak must have been active for a number of years to accumulate that level of contamination, based on source term in the tank and the decay of the nuclides. | I-' | ||
The licensee has not had significant levels of those nuclides in the tank for at least 10 years. The licensee indicated that the material consists of very, very fine silt that appears to have provided very effective filtration of the leakage.The licensee plans to continue work in the area under very rigorous RP controls. | |||
The tented area will have access from the Reactor Building airlock. The workers will be donning protective clothing and full dosimetry/RWP controls. | 021 PROTECTED AREA SURVEY 021 U-1 HVEI 4s 5- 594 eyv. PQaddition /Cr I of Heflow rate.A....scfme dose raites legend U-2 %WVE, Z | ||
The licensee plans to have air sampling within the tented area and outside to monitor for any potential airborne release (to workers or environment). | # @ head He oftitIonv jý' off | ||
Based on the weather, the work will begin in the next-few days., The licensee will be evaluating the cause of the line leakage and the extent of the condition. | "*"'-@ ches't H& flow rot~e....&.-.scfmi T knee o 4t = contact 1 fet. amp'lper *____ | ||
Very preliminary thoughts are that debris was left in the area while the High Radiation Sampling System building was installed post-TMI. | ravin0 not for construction Date / TIme putted. | ||
The debris rubbed against the stainless steel piping from vibrations from the Turbine Building and mechanically damaged the piping n-Th'nsee will be investigating further, and the-PantSUpport-Te-am lc osely.I-' | .... i S E R "v"IC E A. 66W L YAW BU ILDIN U L - - - | ||
021 | ~A~c-~-4'~ | ||
-~ ZrP/4'A~-SE | -~ ZrP/4'A~- | ||
,ZURENT DATE: 7.',.. | SE | ||
,ZURENT DATE: 17: 7.',.. | |||
STATION NAME: QUAD-CITIES L!AS-ND FROM TRI TVJM LEAK | |||
.. : 27-MAY-2008 16:28:03.97 j% I-ELARSED LIVE TIM ...-.... 0 00:10:00.00 ELAPSED REAL TIME ........ 0 00:57:12.67 | : 1. L, A;, | ||
..u +02 Cm -',*u SUB PERFORMED | ......... *.;t*:,_........................... | ||
.....BK~kGND SUBTRACTION FILE.-NALYST'S INITIALS ...... ; MJH 31- COLLECTOR'S INITIALS..: | SPECTRUM FILE ........... : SYS$SYSDEVICE: [CRU.SAMP]DTP787 SAMtP_763.CNF;l NUE-IDE LIBRARY ..... : GE NLIQ | ||
MS... | :bAK SEARCH SENS iTIVITY. : -. 66000 SAMPLE DATE AND TIME .... ; 27-MAkY-2008 13:30:00.00 " - | ||
mr'n rMr Dt'77 EOMETRY............. | ACQUISITION DATE/TIME. .. : 27-MAY-2008 16:28:03.97 j% I-ELARSED LIVE TIM ...-.... 0 00:10:00.00 ELAPSED REAL TIME ........ 0 00:57:12.67 o.-.t t%,Lt COs-r- | ||
ENERGY CAL_-S GAIN ....... : 4.99904E-01 ENERGY CALIB OFFSET ..... 4.865607v-011 E.ZFICIENCY PARAMETER I. .: 9.6204&E+02 EFFICIENCY PARAMETER 2..: -3.97559E-00 EFFICIENCY PARAMETER 3..: 9.83220E-01 EFFICIENCY PARAMETER 4.. -2.09274E-0i EFF-ICIENiCY PARAMETER 5..: -3.33778E-01 EFFICIENCY PARAMNSTER 6..: 4.10867E-02 EFFICIENCY PARAMETER | DRiATION OF DE:AY :03.97 ODAD TrrVE. 82. 521. !_4L) .-v. | ||
?..: -1.15125E-01 | ... L. 1sJfVOLUrE/ 'LAs...S....: .. u +02 Cm - | ||
:E.MA RK ................. | ',*u SUB PERFORMED ..... | ||
BK~kGND SUBTRACTION FILE. | |||
NUCLIDE LIBRARY .........PEAK SEARCH SENSITIVITY.. | -NALYST'S SERI*AL | ||
SAMPLE.DATE AND TIME....: | ->,FTECTOR INITIALS ...... | ||
ELAPSED LIVE TIME .......IAýPSED REAL TIME......... | N'UMBER. .: ; MJH 31-DTP787 COLLECTOR'S INITIALS..: MS...AR22RY........ | ||
DURATION OF DECAY ......,DETAD TTME ............. | mr'n rMr Dt'77 EOMETRY............. | ||
SAMPLE VOLUME/MASS | ENERGY CAL_-S GAIN ....... : 4.99904E-01 ENERGY CALIB OFFSET ..... 4.865607v-011 E.ZFICIENCY PARAMETER I. . : 9.6204&E+02 EFFICIENCY PARAMETER 2..: -3.97559E-00 EFFICIENCY PARAMETER 3..: 9.83220E-01 EFFICIENCY PARAMETER 4.. -2.09274E-0i EFF-ICIENiCY PARAMETER 5..: -3.33778E-01 EFFICIENCY PARAMNSTER 6..: 4.10867E-02 EFFICIENCY PARAMETER ?..: -1.15125E-01 | ||
...... | :E.MA RK ................. . | ||
BKGND SUBTRACTION FILE., ANALYST'S INITIALS ......-E'TEC&OR SERTAL NUMBER.-: | -nalvsr Review: 1.1sf Date: 5C -. 9 Chemist Revzew: .41. Date: . t C-F | ||
:umaryv of Nuclide Activity Tot:J number of lines in spectrum Number Of unidentified lines 8 Number of lines tentatively identified by MID 7 46.67% | |||
Nttciide Type : AP~ t en WdMa Wtd Mean W,-d Mean Uncorrected Decay Corr Decay Corr 1 - Si om'a Nucide Hlike eca OCi/gm UCI/gm i-Sigma Error %Error Fle.'cm 1N-54 212.14D !.00 3.865E-06 5.867E-06 2.1375-06 36,42 0,3 5.27Y 1.00 2.681E-03 2.681E-03 k15!E-03 55.62 | |||
~' ~ 2.%2 Z~l .3/4e~-o~s ~ 0Z~jI1. 208E-03 YE .80 | |||
;- 615 243.90D 1.00 2.222E-05 2.222E-05 0.601E-05 27.04E r Tote! Activity : 3 173E-03 9, U W Cb | |||
*'02E-03 | |||
......... - e FP Wtd Mean Wtd Mean Uncorrected Decay Corr Decay Corr 1 -S~3igm NucLicie Nf* e Decay UCI/gm UCi/gm I-Sigma Error | |||
: | -".00Y 1.00 !.331E-02 Si.331E-02 0.079E-02 5. 90 Total ActiJviy : 1.331E-02 1.331E-02 Total Activity : 2.149E-02 2. 2G2E- 02 | ||
':EŽ7-T T DATE: 2?-MAYv,-003 10:-1:15.6' STATION NAME: QUAD-CITIES CONT, CONDENSATE STORAGE TANK SPECTRUMi FILE ........... SYS$SYSDEVICE: [CRU. SAMP] DTP787_SAYMP(8502 CNF ;12 NUCLIDE LIBRARY ......... GENLIQ PEAK SEARCH SENSITIVITY.. 4.66000 SAMPLE.DATE AND TIME....: 29-MAY-2008 09:45:00.00- O ACQ!TUSrTION DATE/TIME...: 29-MAY-20C8 09:50:46A49/ ;-eV ELAPSED LIVE TIME ....... o 00.:00:00.00-C IAýPSED REAL TIME......... 0 01O00: 0 5 . 3 6 er e , , Y'A Cpu 7 ! | |||
DURATION OF DECAY ...... 0 00:05:46,.9,lr | |||
,DETAD TTME ............. 0.14866 -7 SAMPLE VOLUME/MASS ...... 5 0O00OE'l 2 grm - | |||
2KGND SUB PERFORMED-...... N It)~7k BKGND SUBTRACTION FILE., | |||
ANALYST'S INITIALS ......- im COLLECTOR'S INITIALS. .. : JM "" | |||
E'TEC&OR SERTAL NUMBER.-: DT9787-' GEOMETRY .................... : XXMROs ENERGY CALIB GAIN .......- 4.99958E-01" MENERGY CALIS OFFSET.....: 4.7057,3FE-0 EFFICIENCY PARAMETER 1..: 9.62049E+02 EFFICIENCY PARAMETER 2..: -4.I2303-e0I | |||
..... | :- EIZ -CYPAR AMETER 3 ... 9.32381E-Q1 EFFICIENCY PARA24ETER 4..: -95!970E-02 EFFICIENCY PARAMETER 7 .. : -2.17916E-01 EFFICIENCY PARAMETER 6..: 2.42600E-0J | ||
-7.18664E-02 RE KA...... ............... | |||
Analyst Review: -/ Date : * - ? ) | |||
Chemist Review: Date:- A-__ | |||
Summary of Nucide Actai Total number I- lines in spectrum 13 Number of unidentified lines 3 Number of centa;ively identified | |||
: | -ines by N!D i0 76 . 92% | ||
PYuc2.ide Tyne : | |||
* Wtd Mean Wtd Mean Unco recteed Decay Corr Decay Corr z'kuc2ide Hiife Decay UC /gm UCI/gm 1-Sigma Error &2rrom' = | |||
MN 54 312 .14D i .00 .7.2 5E-08 7.255E-08 1. 176E-08 16.21 | |||
: 70. 82D _ 00 2.4 0E-08 2.4202-08 1.068E-08 44.11 5,27Y 1.00 2.0 2E-07 2.062E-07 0. 164E-07 7. 96 1U, -6 243 .90D 1 .00 2.3 6E-07 2,306E-07 0.407E-07 17.63 Total Accivicy 5.3 6E-07 5. 336E-07 Nruc2.ide Type : FP Wtd Mean Wtd Mean Unco rected Decay Corr Decay Corr 1 - Sicgu.ii lucl ide H-iife Decay UC /gm UCI/gm 1-Sigma Error %Error XE -133 5 .24D 1.00 5.9 1E-07 S .011E-07 0.563E-07 tE-l3 3 2,.346E-0B | |||
................. | : 1. 05 2.454E-08 0.844E-08 34-39 | ||
.. | : 30. 00Y 1.00 3.79 -.- '08 1.047E-08 27.38 Total Activitv : 6.60 ; -07 6,6362-07 | ||
DZcAS..: EFFRCITNC. | *"\ I 6URRENT DATE; 28-NAY-200S 12;06:391i1 STATION NAME: QUAD-CITIES TRITIUM PIT kIR SAMPLE / | ||
TAr......R 7.,: | SPECTRUM FILE ......... SYS$SYSDEVICE: [CRU.SAM/P] DTP787 SA*iP 812 ,CNF;Z | ||
-NUCLIDE LISRARY ......... : PARTICULATE PEAK 5EA-.RCH. SENSITIVITY. : 466000 | |||
.A.CQ..ISTI.ON DATE/TIME ...... 23-NAY-2008 11:56:08.74 ELAP-SED LIVE TIME.........: 0 00:10:00.00 b-.LIAPSED REAL TIME ... 0 00:10:01L95 | |||
: | -JP-ZkTION OF DECAY .......... 0 02:36:08.74 - | ||
:DEAD TIME............... :O 2w 2395 VOLME/LMS UM-. ...... S VA.4990E-0G6 CC AM-i?7S 'L-' ON........... 2. 8300 SAMPLE FLOW OFF .......... 2.8300-- | |||
*PL, TIME ON........... 28-MAY-2008 0 1/412:00 00" MPLE TIME OFF .......... 28-MAY-2008 09:20:00.00' AIZ"LYST' S INITIALS....... : PD COLLECTOR'S INITIALS ...... CE2-DETECTOR SERIAL NUMBER..: DTP787-'* G;EOMETRY ................. .. 03;O:NT ENERGY CALIB GAIN ........ 4.998062-01 ENERGY CALIB OFFSET......: 5. 036%4?-0S EFFICIENCY PARAMETER 1.: 9.47800E402 EFFICIENCY PARAMETER 2..: -4 .66"603+00 EFFICIENCY PARAM[ETER 3..: 7.99261E-01 EFFICIENCY PARAMETER 4..: 4.00788E-03 EFFCTrENCY ?ARAMETER 53.: | |||
3.49018E-02 EFFICIENCY PARAMETER 6..: -3 .744722-04 | |||
.. z',~T;.;- DZcAS..: | |||
EFFRCITNC. TAr......R 7.,: -1.447082-02 | |||
*[E | |||
*Lh K ................. | |||
Analyst Review: _________________ 7- Da te: 5-2Z-? | |||
Chiemisc Review:,a Aci*iv tv T-* | |||
* are no nuclides meeti ng summary criteria . | |||
erL | |||
;' acs:,<'K" fKeyline not found ,'li"=Manually accepted 2= Maually edited : Nuclide IN specific abrn. Iimn Post-NID Peak Search Report | |||
***** No peaks found ***** | |||
I' wthedO}} | |||
Latest revision as of 16:04, 13 November 2019
| ML101970292 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 06/16/2010 |
| From: | - No Known Affiliation |
| To: | Office of Information Services |
| References | |
| FOIA/PA-2010-0209 | |
| Download: ML101970292 (6) | |
Text
Quad Cities Tritium Late in 2007, Quad began investigating slightly elevated tritium levels in wells associated withy its Groundwater Protection Initiative (GPI). At the time of the initial GPI sampling, the licensee believed that the tritium levels were associated with historical leaks and spills that had residual tritium contamination. However, after additional wells were placed, the licensee clearly identified that tritium was entering the groundwater via an ongoing leak associated with the condensate storage tank (CST) or underground piping. Wells placed near that area yielded results in the millions of picocuries per liter (pCi/I). The licensee's samples have not identified any other isotopes (i.e., gamma emitting radionuclides) in the groundwater. Perimeter wells near the site boundary have not detected any radioactivity leaving the restricted area; however, the licensee will need to closely evaluate its well placement based on the current plume and potentials for channeling.
Recently, the licensee began excavating soil near the Reactor Building, where it suspected the leakage. The radiation protection (RP) staff was surveying the area, as the soil was removed (intermittent surveys based on excavation). The licensee was using a vehicle with a suction device and multiple filtration systems.to capture the soil and sediment (see example picture below).
The licensee had three persons working the excavation. Two visitor-badged individuals (no TLD/ED) were using shovels to loosen the soil, and one badged (w/TLD) was manipulating the arm that has the suction end. All should be considered radiation workers, and the individuals were trained qualified during the most recent outage. The two were badged as visitors for security purposes only. The area was -not a designated RCA or RMA, so no formal RP controls were in place. Essentially, the RP staff performed routine surveys as the excavation occurred and instructed the workers to stop work if they ideihtified water or anything abnormal. The 6'
II ýC individuals were instructed to walk through the building to the RCA entrance and monitor through the PCMs at the end of the day.
On about May 27, the workers encountered water and debris near the line and stopped work (about 10 feet of depth). When they monitored via the PCMs, the licensee identified contamination on the workers' clothing. No contamination was on the skin. The levels were in the 10K ballpark. The licensee will be sending the TLD out for processing and has also collected a bioassay from the individual, who is suspected to be the maximally exposed. The other two workers were rotating in-and-out of the area with their shovels, while the individual with the TLD was constantly working with the suction end of the truck. Very preliminarily, the licensee has estimated the maximum, effective dose field to be about 40 mrem/hr, with a bounding exposure time of about 45 - 60 minutes. Consequently, the upper bound would be about 40 mrem. The licensee will contact Wayne Slawinski and/or Steve Orth with the TLD results later in the week.
The RP department surveyed the excavation area and identified very elevated levels of radiation, well beyond that seen anywhere else in the industry. The most recent survey documents external levels of up to 170 millirem per hour (mrem/hr) at contact and 140 mrem/hr at 30 cm. The RP staff is controlling and posting the area as a high radiation area. The area is tented off with plastic covering. The licensee is also posting the truck as a radiation area and will be bringing it into the building for evaluation and potential decontamination. The licensee performed surveys at the exhaust of the truck and verified that no contamination was present, validating that the filtration system was effectively containing the material.
Soil in the area has very significant dose rates (see survey). Most of the radiation is from a very small area of soil, but the licensee has to determine the full characteristics (including depth). A bucket of soil has dose rates of up to 70 mrem/hr on contact. The gamma spectroscopy results indicate very high levels of cobalt-60 (2.7E-3 micocuries per gram) and cesium-137 (1.3E-2 microcuries per gram). The licensee estimates that the leak must have been active for a number of years to accumulate that level of contamination, based on source term in the tank and the decay of the nuclides. The licensee has not had significant levels of those nuclides in the tank for at least 10 years. The licensee indicated that the material consists of very, very fine silt that appears to have provided very effective filtration of the leakage.
The licensee plans to continue work in the area under very rigorous RP controls. The tented area will have access from the Reactor Building airlock. The workers will be donning protective clothing and full dosimetry/RWP controls. The licensee plans to have air sampling within the tented area and outside to monitor for any potential airborne release (to workers or environment). Based on the weather, the work will begin in the next-few days.,
The licensee will be evaluating the cause of the line leakage and the extent of the condition.
Very preliminary thoughts are that debris was left in the area while the High Radiation Sampling System building was installed post-TMI. The debris rubbed against the stainless steel piping from vibrations from the Turbine Building and mechanically damaged the piping n-Th'nsee will be investigating further, and the-PantSUpport-Te-am lc osely.
I-'
021 PROTECTED AREA SURVEY 021 U-1 HVEI 4s 5- 594 eyv. PQaddition /Cr I of Heflow rate.A....scfme dose raites legend U-2 %WVE, Z
- @ head He oftitIonv jý' off
"*"'-@ ches't H& flow rot~e....&.-.scfmi T knee o 4t = contact 1 fet. amp'lper *____
ravin0 not for construction Date / TIme putted.
.... i S E R "v"IC E A. 66W L YAW BU ILDIN U L - - -
~A~c-~-4'~
-~ ZrP/4'A~-
,ZURENT DATE: 17: 7.',..
STATION NAME: QUAD-CITIES L!AS-ND FROM TRI TVJM LEAK
- 1. L, A;,
......... *.;t*:,_...........................
SPECTRUM FILE ........... : SYS$SYSDEVICE: [CRU.SAMP]DTP787 SAMtP_763.CNF;l NUE-IDE LIBRARY ..... : GE NLIQ
- bAK SEARCH SENS iTIVITY. : -. 66000 SAMPLE DATE AND TIME .... ; 27-MAkY-2008 13:30:00.00 " -
ACQUISITION DATE/TIME. .. : 27-MAY-2008 16:28:03.97 j% I-ELARSED LIVE TIM ...-.... 0 00:10:00.00 ELAPSED REAL TIME ........ 0 00:57:12.67 o.-.t t%,Lt COs-r-
DRiATION OF DE:AY :03.97 ODAD TrrVE. 82. 521. !_4L) .-v.
... L. 1sJfVOLUrE/ 'LAs...S....: .. u +02 Cm -
',*u SUB PERFORMED .....
BK~kGND SUBTRACTION FILE.
-NALYST'S SERI*AL
->,FTECTOR INITIALS ......
N'UMBER. .: ; MJH 31-DTP787 COLLECTOR'S INITIALS..: MS...AR22RY........
mr'n rMr Dt'77 EOMETRY.............
ENERGY CAL_-S GAIN ....... : 4.99904E-01 ENERGY CALIB OFFSET ..... 4.865607v-011 E.ZFICIENCY PARAMETER I. . : 9.6204&E+02 EFFICIENCY PARAMETER 2..: -3.97559E-00 EFFICIENCY PARAMETER 3..: 9.83220E-01 EFFICIENCY PARAMETER 4.. -2.09274E-0i EFF-ICIENiCY PARAMETER 5..: -3.33778E-01 EFFICIENCY PARAMNSTER 6..: 4.10867E-02 EFFICIENCY PARAMETER ?..: -1.15125E-01
- E.MA RK ................. .
-nalvsr Review: 1.1sf Date: 5C -. 9 Chemist Revzew: .41. Date: . t C-F
- umaryv of Nuclide Activity Tot:J number of lines in spectrum Number Of unidentified lines 8 Number of lines tentatively identified by MID 7 46.67%
Nttciide Type : AP~ t en WdMa Wtd Mean W,-d Mean Uncorrected Decay Corr Decay Corr 1 - Si om'a Nucide Hlike eca OCi/gm UCI/gm i-Sigma Error %Error Fle.'cm 1N-54 212.14D !.00 3.865E-06 5.867E-06 2.1375-06 36,42 0,3 5.27Y 1.00 2.681E-03 2.681E-03 k15!E-03 55.62
~' ~ 2.%2 Z~l .3/4e~-o~s ~ 0Z~jI1. 208E-03 YE .80
- - 615 243.90D 1.00 2.222E-05 2.222E-05 0.601E-05 27.04E r Tote! Activity
- 3 173E-03 9, U W Cb
......... - e FP Wtd Mean Wtd Mean Uncorrected Decay Corr Decay Corr 1 -S~3igm NucLicie Nf* e Decay UCI/gm UCi/gm I-Sigma Error
-".00Y 1.00 !.331E-02 Si.331E-02 0.079E-02 5. 90 Total ActiJviy : 1.331E-02 1.331E-02 Total Activity : 2.149E-02 2. 2G2E- 02
':EŽ7-T T DATE: 2?-MAYv,-003 10:-1:15.6' STATION NAME: QUAD-CITIES CONT, CONDENSATE STORAGE TANK SPECTRUMi FILE ........... SYS$SYSDEVICE: [CRU. SAMP] DTP787_SAYMP(8502 CNF ;12 NUCLIDE LIBRARY ......... GENLIQ PEAK SEARCH SENSITIVITY.. 4.66000 SAMPLE.DATE AND TIME....: 29-MAY-2008 09:45:00.00- O ACQ!TUSrTION DATE/TIME...: 29-MAY-20C8 09:50:46A49/ ;-eV ELAPSED LIVE TIME ....... o 00.:00:00.00-C IAýPSED REAL TIME......... 0 01O00: 0 5 . 3 6 er e , , Y'A Cpu 7 !
DURATION OF DECAY ...... 0 00:05:46,.9,lr
,DETAD TTME ............. 0.14866 -7 SAMPLE VOLUME/MASS ...... 5 0O00OE'l 2 grm -
2KGND SUB PERFORMED-...... N It)~7k BKGND SUBTRACTION FILE.,
ANALYST'S INITIALS ......- im COLLECTOR'S INITIALS. .. : JM ""
E'TEC&OR SERTAL NUMBER.-: DT9787-' GEOMETRY .................... : XXMROs ENERGY CALIB GAIN .......- 4.99958E-01" MENERGY CALIS OFFSET.....: 4.7057,3FE-0 EFFICIENCY PARAMETER 1..: 9.62049E+02 EFFICIENCY PARAMETER 2..: -4.I2303-e0I
- - EIZ -CYPAR AMETER 3 ... 9.32381E-Q1 EFFICIENCY PARA24ETER 4..: -95!970E-02 EFFICIENCY PARAMETER 7 .. : -2.17916E-01 EFFICIENCY PARAMETER 6..: 2.42600E-0J
-7.18664E-02 RE KA...... ...............
Analyst Review: -/ Date : * - ? )
Chemist Review: Date:- A-__
Summary of Nucide Actai Total number I- lines in spectrum 13 Number of unidentified lines 3 Number of centa;ively identified
-ines by N!D i0 76 . 92%
PYuc2.ide Tyne :
- Wtd Mean Wtd Mean Unco recteed Decay Corr Decay Corr z'kuc2ide Hiife Decay UC /gm UCI/gm 1-Sigma Error &2rrom' =
MN 54 312 .14D i .00 .7.2 5E-08 7.255E-08 1. 176E-08 16.21
- 70. 82D _ 00 2.4 0E-08 2.4202-08 1.068E-08 44.11 5,27Y 1.00 2.0 2E-07 2.062E-07 0. 164E-07 7. 96 1U, -6 243 .90D 1 .00 2.3 6E-07 2,306E-07 0.407E-07 17.63 Total Accivicy 5.3 6E-07 5. 336E-07 Nruc2.ide Type : FP Wtd Mean Wtd Mean Unco rected Decay Corr Decay Corr 1 - Sicgu.ii lucl ide H-iife Decay UC /gm UCI/gm 1-Sigma Error %Error XE -133 5 .24D 1.00 5.9 1E-07 S .011E-07 0.563E-07 tE-l3 3 2,.346E-0B
- 1. 05 2.454E-08 0.844E-08 34-39
- 30. 00Y 1.00 3.79 -.- '08 1.047E-08 27.38 Total Activitv : 6.60 ; -07 6,6362-07
- "\ I 6URRENT DATE; 28-NAY-200S 12;06:391i1 STATION NAME: QUAD-CITIES TRITIUM PIT kIR SAMPLE /
SPECTRUM FILE ......... SYS$SYSDEVICE: [CRU.SAM/P] DTP787 SA*iP 812 ,CNF;Z
-NUCLIDE LISRARY ......... : PARTICULATE PEAK 5EA-.RCH. SENSITIVITY. : 466000
.A.CQ..ISTI.ON DATE/TIME ...... 23-NAY-2008 11:56:08.74 ELAP-SED LIVE TIME.........: 0 00:10:00.00 b-.LIAPSED REAL TIME ... 0 00:10:01L95
-JP-ZkTION OF DECAY .......... 0 02:36:08.74 -
- DEAD TIME............... :O 2w 2395 VOLME/LMS UM-. ...... S VA.4990E-0G6 CC AM-i?7S 'L-' ON........... 2. 8300 SAMPLE FLOW OFF .......... 2.8300--
- PL, TIME ON........... 28-MAY-2008 0 1/412:00 00" MPLE TIME OFF .......... 28-MAY-2008 09:20:00.00' AIZ"LYST' S INITIALS....... : PD COLLECTOR'S INITIALS ...... CE2-DETECTOR SERIAL NUMBER..: DTP787-'* G;EOMETRY ................. .. 03;O:NT ENERGY CALIB GAIN ........ 4.998062-01 ENERGY CALIB OFFSET......: 5. 036%4?-0S EFFICIENCY PARAMETER 1.: 9.47800E402 EFFICIENCY PARAMETER 2..: -4 .66"603+00 EFFICIENCY PARAM[ETER 3..: 7.99261E-01 EFFICIENCY PARAMETER 4..: 4.00788E-03 EFFCTrENCY ?ARAMETER 53.:
3.49018E-02 EFFICIENCY PARAMETER 6..: -3 .744722-04
.. z',~T;.;- DZcAS..:
EFFRCITNC. TAr......R 7.,: -1.447082-02
- [E
- Lh K .................
Analyst Review: _________________ 7- Da te: 5-2Z-?
Chiemisc Review:,a Aci*iv tv T-*
- are no nuclides meeti ng summary criteria .
erL
- ' acs
- ,<'K" fKeyline not found ,'li"=Manually accepted 2= Maually edited : Nuclide IN specific abrn. Iimn Post-NID Peak Search Report
- No peaks found *****
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