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| issue date = 03/30/2009
| issue date = 03/30/2009
| title = Pbrf Laboratory Quality Assurance Report 2008
| title = Pbrf Laboratory Quality Assurance Report 2008
| author name = Case R C, Stoner W
| author name = Case R, Stoner W
| author affiliation = US National Aeronautics & Space Admin (NASA)
| author affiliation = US National Aeronautics & Space Admin (NASA)
| addressee name =  
| addressee name =  
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=Text=
=Text=
{{#Wiki_filter:[[I I I I I I I PBRF LABORATORY ASSU , RANCE January to December 2008 FIFT H EDI TIO N March 30, 2 009 RODERIC K C. C AS E PBRF LABORATORY M A NAG E R W I LL IAM S TO NER N A SA P ROJECT RADIA TION SAFETY OFFICER NASA Plum Brook Reactor F acility 6100 Columbus Aven ue Sandu sk y, Ohio 44870 t .. .. ...[1 [I I I I I I I I I I , PBRF LABORATORY QUALITY ASSU , RANCE REPORT January to December 2008 FIFT H EDI TIO N March 30, 2 009 RODERIC K C. C AS E PBRF LABORATORY M A NAG E R W I LL IAM S TO NER N A SA P ROJECT RADIA TION SAFETY OFFICER NASA Plum Brook Reactor F acility 6100 Columbus Aven ue Sandu sk y, Ohio 44870 I -
{{#Wiki_filter:~~------------------------------~
TABLE OF SECTION PAGE 1.0  
  ~          ,P PBRF BRF LABORATORY QUALITY
  ~                                      ASSU,RANCE REPORT
    ~J                                        January to December 2008
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[~)
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[I
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I                                                                 ------~
I     FIFTH EDITION III      March 30, 2009 RODERICK C. CASE PBRF LABORATORY MANAGER I
WILLIAM STONER I  NASA PROJECT RADIATION SAFETY OFFICER NASA Plum Brook Reactor Facility 6100 Columbus Avenue Sandusky, Ohio 44870 I
II ~~~~-
_~~-~
It .- .
      ~      -'" .! !--"! !I ! !~
                                ~~-----------
                                ! ! ! ! ~.- ~--------------------~          ...
 
TABLE OF CONTENTS SECTION                                                                                                                               PAGE I 1.0  


==SUMMARY==
==SUMMARY==
  ..........................................................................................................................  
  .......................................................................................................................... 1 I


==2.0 INTRODUCTION==
==2.0   INTRODUCTION==
................................................................................................................2 I 3.0  DiSCUSSiON ......................................................................................................................2 I 4.0                                    .. .............................................................................................. 3 LABORATORY PROGRAM ................................................................................................
I 5.0  INTER-LABORATORY & INTRA-LABORATORY COMPARISON ANALYSIS .................. 4 TABLE 1 -INTRA-LABORATORY COMPARISON (REPLICATE) RESULTS ................................................. 5 I      TABLE 2 -INTER-LABORATORY COMPARISON (REPLICATE) RESULTS .............................................. 17 TABLE 3 - SAMPLE RESOLUTION AND RATIO AGREEMENT CRITERIA. ............................................... 21 I
6.0  QUALITY CONTROL CHECKS ........................................................................................21 I


................................................................................................................3.0 DiSCUSSiON
==7.0  BACKGROUND==
.........................................
DETERMINATIONS ...............................................................................22 I 8.0   BLANK SAMPLE ANALySiS ............................................................................................22 I 9.0   CROSS-CHECK PROGRAM ............................................................................................23 I 10.0 LABORATORY/SAMPLE DEVIATION REPORTS ........................................................... 23 I 11.0 ATIACHMENTS ...............................................................................................................23 I
.............................................................................4.0 LABORATORY PROGRAM .. ..............................................................................................5.0 INTER-LABORATORY  
I I
&INTRA-LABORATORY COMPARISON ANALYSIS .................. TABLE 1 -INTRA-LABORATORY COMPARISON (REPLICATE)
I
RESULTS ................................................. TABLE 2 -INTER-LABORATORY COMPARISON (REPLICATE)
RESULTS .............................................. TABLE 3 -SAMPLE RESOLUTION AND RATIO AGREEMENT CRITERIA.
............................................... 6.0 QUALITY CONTROL CHECKS ........................................................................................


==7.0 BACKGROUND==
1.0  


DETERMINATIONS
==SUMMARY==
............................................................................... 8.0 BLANK SAMPLE ANALySiS ............................................................................................ 9.0 CROSS-CHECK PROGRAM ............................................................................................ 10.0 LABORATORY/SAMPLE DEVIATION REPORTS ........................................................... 11.0 ATIACHMENTS
............................................................................................................... TABLE OF CONTENTS SECTION PAGE I 1.0


==SUMMARY==
I    1 1.1
..........................................................................................................................
        .1 Gamma Spectroscopy Systems I          1.1.1  During the report period of January 1, 2008 and December 31, 2008, PBRF Laboratory personnel performed 4190 gamma spectroscopy sample analyses of 3006 samples. PBRF performed a total of 1547 quality I                  assurance analyses. They include:
1 I
* 29 blank analyses on 29 samples I
* 615 Quality Control (QC) checks I
* 615 Background checks 15 Cross-check Program sample analyses on 3 samples I
* 24 inter-laboratory comparison (replicate) analyses on 12 samples
* 249 intra-laboratory comparison (replicate) analyses on 132 samples I          1.1.2  Of all the QA samples that were analyzed on the PBRF Gamma Spectroscopy Systems, there were 4 discrepancies that required I                  documentation of a Sample Deviation Report (SDR).
1.2  Liquid Scintillation Analyzer I          1.2.1  PBRF laboratory personnel performed 523 tritium sample analyses during this report period. PBRF performed a total of 1789 analyses of quality I                  assurance (QA) samples. They include:
* 612 analyses on 3 reference standards I
* 227 analyses on 227 blank samples I
* 454 analyses on 2 background samples
* 454 analyses on 2 QC Check samples I
* 8 Cross-check Program sample analyses on 2 samples I
* 20 inter-laboratory comparison (replicate) on 20 samples
* 14 intra-laboratory comparison (replicate) on 14 samples I          1.2.2  Of all the QA samples that were analyzed on the PBRF Liquid Scintillation Analyzer, there were no discrepancies that required documentation of a I                  Sample Deviation Report .
* 1


==2.0 INTRODUCTION==
I~------------------------------~
I 1.3  Four Sample Deviation Reports were completed as a result of deficiencies found I          during this report period. Two were associated with MAPEP Series 18 Co-60 failures. Two were failures to attain agreement between intra-laboratory replicate analyses of K-40. These failures were investigated by the Laboratory Manager and I          corrective actions were documented. Refer to Section 10.0 of this report.
2.0 INrRODUCTION I      2.1  This report has been prepared by the PBRF Radiological Laboratory Manager in accordance with PBRF procedure RP-060, PBRF Radiological Laboratory Quality I          Assurance/Quality Control Program. It provides a summary and interpretation of PBRF Laboratory QA Program for the period of January 1, 2008 to December 31, 2008.
I  3.0 DISCUSSION I      3.1  A QA program is an essential part of any radiological monitoring program. It provides reasonable assurance that the results of radiation measurements are valid. To be effective, elements of QA must be evident in all phases of the I          monitoring program. These include, but are not limited to, sample collection, preservation and shipment, receipt of samples by the laboratory, preparation and analysis of samples and data review and reporting. An effective QA program will I          allow for the identification of deficiencies in all monitoring processes so that appropriate investigative and corrective actions can be implemented.
I      3.2  The United States Nuclear Regulatory Commission (USNRC) published Regulatory Guide 4.15, "Quality Assurance for Radiological Monitoring Programs (Normal Operations) - EfHuent Streams and the Environment", which defines an acceptable I          QA program. The guidance contained in Regulatory Guide 4.15 and NRC 10CFR50, Appendix B, "Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants" has been adopted by the PBRF Facility. Procedures I          have been written and implemented to meet the objectives of these position documents.
I      3.3  Samples are typically analyzed only once because of workload constraints.
Therefore, laboratory personnel must be confident in the analytical results which are reported. One means of achieving confidence in the results is through the analysis I          of QA samples. This report provides the analytical results of various QA samples processed by the PBRF laboratory during this period.
I      3.4  Quality Control checks are performed on at least 5% of all samples analyzed on the PBRF Gamma Spectroscopy Systems and/or Liquid Scintillation Analyzer. For the purpose of comparing results, these samples may be analyzed in duplicate by an I          independent laboratory (inter-laboratory comparison) or by PBRF (intra-laboratory comparison) in their entirety or split to perform multiple analyses. The original analytical results are then compared with the replicate analysis results for I          agreement.
I                                              2


................................................................................................................
I~------------------------------~
2 I 3.0 DiSCUSSiON
I      3.5 The PBRF laboratory participates in the United States Department of Energy Mixed Analyte Performance Evaluation Program (MAPEP) and the Eckert & Zeigler Analytics cross check programs. Blind spike samples are sent to the PBRF I          Laboratory for gamma spectroscopy and tritium analysis approximately twice a year. Results are submitted via the Internet and evaluated for agreement.
......................................................................................................................
I      3.6 Blank samples are analytical control samples, usually distilled water or verified clean (non-radiological) sand or soil, used to demonstrate that reported analytical results are not the result of Laboratory and/or Sample Processing Facility I          contamination. They are used to evaluate the entire analytical procedure (sample preparation and analysis) and are prepared at the PBRF Facility for analysis in conjunction with batches or groups of regular samples.
2 I 4.0 LABORATORY PROGRAM ................................................................................................
I     3.7 This report is divided into the following sections:
3 I 5.0 INTER-LABORATORY
I
& INTRA-LABORATORY COMPARISON ANALYSIS ..................
* Section 4.0 - Laboratory Program
4 I I I I I I I I I I I
* Section 5.0 - Inter-laboratory and Intra-laboratory Comparison Analysis I
* TABLE 1 -INTRA-LABORATORY COMPARISON (REPLICATE)
* Section 6.0 - Quality Control Checks I
RESULTS .................................................
* Section 7.0 - Background Determinations
5 TABLE 2 -INTER-LABORATORY COMPARISON (REPLICATE)
* Section 8.0 - Blank Sample Analysis I
RESULTS ..............................................
* Section 9.0 - Cross-check Program I
17 TABLE 3 -SAMPLE RESOLUTION AND RATIO AGREEMENT CRITERIA.
* Section 10.0 - Laboratory/Sample Deviation Reports
...............................................
* Section 11.0 - Attachments I          Brief discussions and summaries as well as applicable acceptance criteria are included for each section. Analytical results, which did not meet the specified I  4.0 acceptance criteria, are noted and discussed.
21 6.0 QUALITY CONTROL CHECKS ........................................................................................
LABORATORY PROGRAM I      4.1  The PBRF Radiological Laboratory is designed to support the analytical requirements of decommissioning work activities, environmental program, and Final Status Survey. The laboratory consists of three high resolution gamma I          spectroscopy units, one liquid scintillation counter, and three gas flow proportional alphalbeta counters. The laboratory is operated by qualified personnel with I          documented training on all of the laboratory equipment. Sample processing is performed in accordance with site procedures and chain of custody is maintained for all samples. There were no significant laboratory program changes during this I          period.
21
I I                                                3


==7.0 BACKGROUND==
I~------------------------------~
I  5.0 INTER-LABORATORY & IN"rRA-LABORATORY COMPARISON ANALYSIS 5.1  For this report period, 24 gamma spectroscopy comparison analyses were I          performed on 12 inter-laboratory samples and 249 gamma spectroscopy comparison analyses were performed on 132 intra-laboratory samples. This equates to approximately 6.5% of the total gamma spectroscopy sample analysis I          performed during the report period. Two intra-laboratory comparison results were not in agreement and a Sample Deviation Report was completed for each. All of the remaining comparison analyses performed in this period were in agreement.
I      5.2  Air filter and smear samples are not typically sent to an off site laboratory for gross activity comparison analysis. In addition, the PBRF laboratory does not perform I          gross activity analysis on water or soil samples. Therefore, no inter-laboratory or intra-laboratory gross alpha/beta comparative analyses were performed during this period.
I      5.3  For this report period, 14 intra-laboratory tritium comparative analyses were performed on 14 samples and 20 inter-laboratory tritium comparative analyses I          were performed on 20 samples. This is approximately 6.5% of the total tritium sample analysis performed during the report period. All of the comparative analyses performed in this period were in agreement.
I I
I I
I I
I I
I I
I                                              4
 
-------------------                                                                      TABLE 1 INTRA-LABORATORY COMPARISON (REPLICATE) RESULTS c:
                                                                                                                                      .2 c:  SDR Gamma Log                    Sample ID                        Replicate                                          Original          0
(])
Number Acquisition Sample                                  Original Replicate              S          E Number                    Number Date    Type Analysis  Nuclide    Units                        2 Sigma    (5    ~    (])  SDR SDR-Result    Result                If)  ~    ~
(Original)                (Replicate)                    Performed By                                        Uncertainty    (])
Ol    08 08-
                                                                                                                                      ~          <t:  ###
Paint PBOS-00020                  PBOS-00021  111012008              PBRF      K-40
                                                                                    -40    pCilg  6.7SE+02  9.09E+02  3.20E+02    4.0  0.75 YES    N/A Chips Paint PB08-00020                  PB08"()0021 PB08"()00  1/10/2008              PBRF      Co-60 0-60    pCilg  S.02E+01  S.10E+01  2.44E+01    7.0  0.99 YES    N/A Chips I~~~~
PBOB"()0040                PBOS"()0041 PBOS"()OO  1/14/200B    Puck      PBRF      K-40      pCilg  9.40E+00  B.60E+00 200E~
2.60E+00    7.0  1.09 1.09 YES    N/A NI PBOS-00040                  PBOS-00041  1/14/200S    Puck      PBRF      Co-60    pCilg  1.35E+01  1.32E+01  B.20E"()1 B.20E      33.0  1.02 YES    N/A PBOB-00040                  PBOB-00041  1/14/200B    Puck      PBRF    Cs-137    pCi/g  2.30E+00  2.70E+00  3.90E"()1  1.
12.0  0.85 YES    N/A PB08-00060                  PBOB-00061  1/15/200B    Soil      PBRF      K-40      pCi/g  1.35E+01  1.19E+01  1.95E+00  14.0  1.13 YES    N/A I~~            ~~~~~~~~~~~- !~~~~
PBOS"()OOBO                PBOB-000B1  1/161200S    Air      PBRF      K-40    uCi/ml I 1.44E-09  1.60E-09  4.30E-10    7.0  0.90 YES    N/A PB08"()0100                PB08-00101  1/1712008    Soil      PBRF      Co-60    pCilg  2.50E+02  2.47E+02  B.30E+00  60.0  1.01 YES    N/A
                ~~~~~~~-      ~~
PBOS-00100                  PBOB"()0101 1/17/200S    Soil      PBRF    Cs-137    pCilg  1.40E+04  1.38E+04  4.50E+02 4.S0E+02    62.0  1.01 YES    N/A PBOS"()0120                PBOS-00121  1/231200S    Air      PBRF      K-40    uCilml  2.60E"()9 2.20E-09  6.90E-10    8.0  1.18 YES    N/A PBOB-00140                  PBOS-00141  1/2B1200B  Puck      PBRF    Ag108m    pCilg  1.20E+00 E+OO  1.20E+00  1.50E"()1 1.S0E"()1  16.0  1.00 YES    N/A PBOB-00140                  PBOS-00141  1/2S/200B  Puck      PBRF    Cs-137    pCi/g  7.50E-01 7.S0E-01  9.30E-01  2.30E-01    7.0  0.81 YES    N/A PBOS-00160                  PBOS-00161  1/2S/2008  Water      PBRF      K-40      pCi/g  S.50E-01 S.SOE-01  9.70E-01  3.40E-01    5.0 S.O  0.88 YES    N/A
          ~~~~~~---
PBOS-00160                  PBOB"()0161  112S12008  Water      PBRF    Cs-137    pCi/g    6.BOE-01  6.00E-01  9.00E-02  15.0 1S.0  1.13 YES    N/A PB08-00160                  PBOS-00161  112B1200B  Water      PBRF      Co-60    pCi/g    1.40E-01  1.20E-01  4.00E-02    7.0  1.17 YES    N/A
      ----~~~~~~~-  ~~~~----
                    ~~~~----
PBOS-00160                  PBOB-00161  1/2S1200B  Water      PBRF        H3    pC' pCilml  9.44E+01  8.96E+01  4.22E+00    45.0 4S.0  1.05 1.0S YES    N/A N/A E
PBOB-00180                  PBOB-001S1  1/221200B  Water      PBRF      K-40    pCilg    6.40E-01  7.30E-01  2.60E"()1  5.0  0.88 YES Y
      ----~~------
PBOB-001BO                  PBOB-001B1  1/221200S  Water      PBRF        H3    pCilml  1.00E+00  4.00E-01  1.00E+00    2.0  2.50 2.S0 Y YES    N/A PBOB-00200                  PBOB-00201  1/30/200B    Air      PBRF      K-40    uCi/ml  7.11E-10  7.00E-10  1.BOE-11  79.0  1.02 YES    N/A PBOB-00220                  PBOS-00221    2/512008 2/S12008    Soil      PBRF      K-40    pCilg    6.10E+00  3.S0E+00  1.70E+00    7.0  1.61 YES    N/A
                                                                                                                                                ~
PBOB-00220                  PBOS"()0221  2/512008 2/S12008    Soil      PBRF    Cs-137    pCilg    1.00E+00  1.10E+00  2.70E-01    7.0  0.91 YES    N/A 5
 
-------------------                                                      TABLE 1 (Continued)
INTRA-LABORATORY COMPARISON (REPLICATE) RESULTS c:          'E  SDR 0            Q)
Gamma Log              Sample ID                        Replicate                                                Original    :p      0        Number Acquisition Sample                                      Original  Replicate                :::I        E Number              Number Type Analysis  Nuclide      Units                          2 Sigma    (5    ~      Q)  SDR SDR-Date                                                  Result      Result                fI)  n:::  ~
(Original)          (Replicate)                      Performed By                                            Uncertainty    Q)          Cl  08 08-n:::        ci  ###
PB08-00240            PB08-00241    2/6/2008    Air      PBRF      K-40        uCilml  7.44E-10    8.10E-10  2.00E-10    7.0    0.92  YES    NIA PB08-00260            PB08-00261    2/6/2008    Soil      PBRF      K-40        pCilg    2.31E+01  2.10E+01  4.10E+00  11.0    1.10  YES    N/A Y~
PB08-00280          PB08-00281    2/612008    Soil      PBRF      K-40        pCi/g    1.35E+01    1.79E+01  2.90E+00    9.0    0.75  YES    N/A PB08-00303          PB08-00304    211112008    Soil      PBRF      K-40        pCilg    1.88E+01    1.73E+01  3.20E+00  12.0    1.09  YES    N/A PB08-00320 PB08-00321 2112/2008    Soil      PBRF      K-40        pCi/g  I 1.84E+01  2.05E+01  3.20E+00  12.0    0.90  YES YE    N/A PB08-00340            PB08-00341  2/1312008    Soil      PBRF      K-40        pCi/g    2.23E+01    1.60E+01  3.60E+00  12.0    1.39  YES    N/A PB08-00360            PB08-00361  2113/2008    Soil      PBRF      K-40        pCi/g pCilg    1.62E+01    1.96E+01  3.10E+00  10.0    0.83  YES    NIA PB08-00380            PB08-00381  211212008    Air      PBRF      K-40        uCilml  2.20E-11    2.90E-11  6.20E-12    7.0    0.76  YES    NIA N/A pc~
PB08-00422            PB08-00423  2/2012008    Water      PBRF      K-40        pCilg    1.02E+00    7.10E-01  3.30E-01  6.0    1.44
: 1. YES    N/A PB08-00422            PB08-00423  2120/2008 0/2008  Water      PBRF        H3        pCi/g    2.00E-01 E-01    2.00E-01  1.17E+00    0.3    1.00  YES    N/A PB08-00440            PB08-00441  2/21/2008 2121/2008    Soil      PBRF      K-40        pCilg pC      1.66E+01
                                                                                                  .66E+01    1.73E+01  3. 1 1OE+OO OE+OO  11.0    0.96  YES    N/A NIA PB08-00460            PB08-00461    2121/2008    Soil      PBRF      K-40        pCilg    1.56E+01    1A2E+01  3.00E+00  10.0    1.10  YES    N/A NIA PB08-00480 08-00480        PB08-00481    212212008    Air      PBRF      K-40        uCi/ml  5.90E-10    6.50E-10  1.50E+10    0.0    0.91  YES    N/A NIA PB08-00500            PB08-00501 PB08-0050    212512008    Soil      PBRF      K-40        pCilg    1.61E+01    1.50E+01  2.90E+00  11.0    1.07  YES    N/A PB08-00534            PB08-00535 PB08-005    2/27/2008    Soil      PBRF      K-40        pCilg P        1.71E+01  1.59E+01  3.10E+00  11.0    1.08  YES    N/A 08-00540 PB08-00540            PB08-00541    2/2712008    Soil      PBRF      K-40        pCilg    4.40E+00  5.00E+00  1AOE+OO 1 AOE+OO  6.0    0.88  YES    N/A 11.0~
~------
PB08-00560            PB08-00561    2/2712008    Soil      PBRF      K-40        pCilg    1.39E+01  1.57E+01 157E+lli      5OE +OO 2.50E+00  11.0    0.89  YES    NIA N/A PB08-00580            PB08-00581    2/2912008 212912008  Water      PBRF      K-40        pCilg    7.80E-01    7.50E-01 7.50E-0  1.70E-01 1 .70E-01  9.0    1.04  YES    N/A r-------
r--------
PB08-00580            PB08-00581    2/29/2008 212912008  Water      PBRF        H3        pCilg pCi/g    4.00E-01  1.00E+00  7.00E-01    1.1    0040  YES    N/A NIA I    PB08-00600            PB08-00602    3/3/2008  Puck      PBRF      K-40        pCilg pCi/g    7.90E+00  7.70E+00  2 AOE+OO    7.0    1.03  YES  N/A NIA 6


DETERMINATIONS
-------------------                                                                            TABLE 1 (Continued)
...............................................................................
INTRA-LABORATORY COMPARISON (REPLICATE) RESULTS Gamma Log Number Sample 10 Number Acquisition      Sample Replicate Analysis Nuclide Units Original Replicate Original 2 Sigma
22 8.0 BLANK SAMPLE ANALySiS ............................................................................................
                                                                                                                                                  .2 t:
22 9.0 CROSS-CHECK PROGRAM ............................................................................................
                                                                                                                                                  "5 Ratio t:
23 10.0 LABORATORY/SAMPLE DEVIATION REPORTS ...........................................................
Q)
23 11.0 ATIACHMENTS
E Q)
...............................................................................................................
SDR Number SDR SDR-Date              Type        Performed                    Result    Result                "0 (Original)              (Replicate)                                                                                      Uncertainty I/)
23 I I I I I I I I I I I I I
Q)
I I 1.0
                                                                                                                                                                  ~    08 08-C)
By                                                        0::            <<  ###
PB08-00620                PB08-00621        313/2008            Soil          PBRF      K-40  pCilg pCiI  1.60E+01  1.97E+01  2.95E+00 E+OO  11.0    0.81    YES  N/A PB08-00640                PB08-00641        3/412008            Soil          PBRF      K-40  pCilg  1.27E+01  1.17E+01  2.60E+00    10.0    1.09    YES  N/A PB08-00660                PB08-00661        3/4/2008            Soil          PBRF      K-40  pCilg  1.72E+01  1.64E+01  2.90E+00    12.0    1.05    YES  N/A PB08-00683                PB08-006B4        3/5/2008              Air          PBRF      K-40  uCi/ml 5.50E-10  4.20E-10  1.50E-10    7.0    1.31    YES  N/A
-~~~~~~~
PB08-00683                PB08-00684        3/512008              Air          PBRF      Cs-137  uCilml 2.10E-11  1.10E-11  7.80E-12    5.0    1.91    YES  N/A PB08-00700                PB08-00701        3/612008              Air          PBRF      K-40  uCilml 6.60E-10  6.50E-10  1.90E-10    7.0    1.02 2    YES  N/A c-~~~~                          ----------
PB08-00720                PB08-00721      3/10/2008            Soil          PBRF      K-40  pCilg  1.59E+01  1.B4E+01  2.90E+00    11.0    0.86    YES  N/A PB08-00740                PB08-00741      3/1012008            Soil          PBRF      K-40  pCi/g  1.86E+01  2.13E+01  3.30E+00    11.0  0 0.87    YES  N/A r~~~~        ~~~~~~~~-~~~-
PB08-00764                PB08-00765      3/1212008            Soil          PBRF      K-40  pCilg  1.38E+01  1.35E+01  2.70E+00    10.0    1.02    YES  N/A PB08-00764                PB08-00765      3/1212008            Soil          PBRF      Cs-137  pCilg  2.70E-01  1.60E-01  9.40E-02    6.0    1.69    YES  N/A PB08-00780                PB08-00781      3112/2008            Soil          PBRF      K-40  pCi/g  1.49E+01  1.30E+01  2.70E+00    11.0    1.15    YES  N/A PB08-00800                PB08-00801      3/13/2008            Soil          PBRF      K-40  pCilg  1.05E+01 1.0SE+01  1.52E+01  2.60E+00    8.0    0.69    YES  N/A PB08-00800                PB08-00801      3/1312008            Soil          PBRF      Cs-137  pCi/g  2.40E+00  2.10E+00  5.40E-01    9.0    1.14    YES YES  N/A
                                              -~~                                                                                    ---------
PB08-00820                PB08-00821      3/1412008            Soil          PBRF      K-40  pCi/g  1.64E+01  1.98E+01  2.98E+00    11.0    0.83    YES  N/A
-~~~~
PB08-oo840                PB08-00841      3/1712008 Puck          PBRF K-40  pCilg  1.50E+01  1.61 E+01  2.90E+00    10.0    0.93  I YES  N/A PB08-00860                PB08-00861      3118/2008            Puck          PBRF      K-40  pCi/g  1.46E+01  1.70E+01  3.20E+00    9.0    0.86    YES  N/A PB08-00877                PB08-00878      3/19/2008            Soil          PBRF      K-40  pCi/g  1.11E+01  1.53E+01 1.S3E+01  2.40E+00    9.0    0.73    YES  N/A
~~~~~~~~
PB08-00900                PB08-00901      3/19/2008            Soil          PBRF      K-40  pCi/g  1.26E+01  1.35E+01  2.S0E+00 2.50E+00    10.0    0.93    YES  N/A PB08-00920                PB08-00921      3/1912008 Soil          PBRF      K-40  PCVg~+oo pCi/g  4.70E+00  2.90E+00  1.50E+00    6.0    1.62    YES  N/A PB08-00940                PB08-00941      312012008          Water          PBRF      K-40  pCi/g  7.30E-01  6.60E-01  2.BOE-01    5.0 S.O    1.11    YES  N/A 7


==SUMMARY==
-------------------                                  TABLE 1 (Continued)
INTRA-LABORATORY COMPARISON (REPLICATE) RESULTS c:        'E    SDR Replicate                                                        .2            (I)
Gamma Log    Sample 10                                                                        Original                            Number Acquisition    Sample  Analysis                  Original Replicate                    "5            E Number      Number                                    Nuclide  Units                        2 Sigma          (5    Ratio  (I)  SDR-SDR Date        Type  Performed                  Result    Result                        r/)        ~
(Original) (Replicate)                                                                      Uncertainty          (I)              OB OB-By                                                            a:::        :f    ###
PBOB-00960  PBOB-00961  3/20/200B        Soil  PBRF    K-40    pCi/g 1.65E+01  1.60E+01  3.00E+OO        11.0    1.03  YES    N/A PBOB-009BO  PBOB-009B1  3124/200B        Soil  PBRF    K-40
                                                                  ~+O1 pCi/g 1.22E+01  1.2BE+01  2.50E+00        10.0    0.95  YES    N/A PBOB-01000 B-01000 PBOB-01020 PBOB-01001 PBOB-01021
                        ~
3/24/200B 3/25/200B Soil Puck PBRF PBRF K-40 K-40 PpCi/g pCi/g 1.32E+01 9.60E+00 1.55E+01 7.50E+OO 7.50E+00 2.50E+00 3.40E+00 11.0 6.0 0.B5 1.2B YES YES N/A N/A PBOB-01020 PBOB-01042 PBOB-01021 PBOB-01043 3/25/200B 3/25/200B Puck Puck PBRF PBRF Cs-137 K-40 pCi/g pCi/g 1.B9E+01 1.02E+01 1.73E+01 9.10E+00 1.40E+OO 4.20E+OO 27.0 5.0 1.09 1.12 YES YES
                                                                                                                                    ~I N/A N/A
                        ~~k PBOB-01042  PBOB-01043  3125/200B      Puck    PBRF    Cs-137    pCi/g 1.25E+02  1.22E+02  5.BOE+OO        43.0    1.02  YES    N/A PB08-01060  PBOB-01061  3/261200B      Puck    PBRF    K-40    pCi/g 7.70E+00  B.60E+00  3.00E+00          5.0    0.90  YES    N/A PBOB-01060  PBOB-01061  3/26/200B      ....
Puck    PBRF    Cs-137    pCi/g 3.24E+02  3.14E+02  1.25E+01        52.0    1.03  YES    N/A
                                                                                                                              ~
PBOB-010BO  PB08-01081 PBOB-010B1  3/26/200B 3/26/2008        Soil  PBRF    K-40    pCi/g  1.35E+01  1.45E+01  2.BOE+OO        10.0    0.93  YES    N/A PBOB-01080  PBOB-010B1  3/26/2008 3/26/200B        Soil  PBRF    Cs-137  pCi/g  9.50E-01  1.20E+00  2.10E-01          9.0    0.79  YES    N/A PB08-010BO  PBOB-010B1  3/26/200B        Soil  PBRF    Co-60  pCi/g  3.10E+00  3.70E+00  3.20E-01        19.0    0.84  YES    N/A PBOB-01103  PBOB-01104  4/1/200B 4/1/2008          Air  PBRF    K-40    uCi/ml 3.20E-10  3.00E-10  9.00E-11          7.0    1.07  YES    N/A PBOB-01120  PBOB-01121  4/1/2008 4/1/200B      Puck    PBRF    K-40    pCi/g  6. BOE+OO 9.30E+00  2.10E+00          6.0    0.73  YES    N/A PBOB-01143  PBOB-01144  4/2/200B 4/2/2008          Air  PBRF    K-40    uCi/ml 7.60E-10  7.20E-10  2.50E-10          6.0    1.06  YES    N/A PBOB-01143  PBOB-01144  4/2/200B          Air  PBRF    Cs-137  uCi/ml 3.50E-11  2.30E-11  1.70E-11        4.0    1.52  YES    N/A PBOB-01160  PBOB-01161    4131200B      Puck    PBRF    K-40    pCi/g  1.23E+01  B.30E+00 B.30E+OO  2.20E+00        11.0    1.4B  YES    N/A PBOB-01160  PBOB-01161  4/3/200B      Puck    PBRF    Cs-137  pCi/g  1.90E-01  1.00E-01  9.00E-02        4.0    1.90  YES    N/A PBOB-011BO  PBOB-011B1    4/3/200B        Soil  PBRF    K-40    pCi/g 1.73E+01  1.9BE+01  3.00E+00        12.0    0.B7  YES    N/A PBOB-011BO  PBOB-011B1    4131200B        Soil  PBRF    Cs-137    pCi/g 4.00E-01  3.40E-01  1.40E-01        6.0    1.1B  YES    N/A PBOB-01200  PBOB-01201    4/7/200B      Puck    PBRF    K-40    pCi/g  9.90E+OO  9.60E+00  2.60E+00          B.O 8.0    1.03 1.03= YES    N/A 8


===1.1 Gamma===
-------------------                                            TABLE 1 (Continued)
Spectroscopy Systems During the report period of January 1, 2008 and December 31, 2008, PBRF Laboratory personnel performed 4190 gamma spectroscopy sample analyses of 3006 samples. PBRF performed a total of 1547 quality assurance analyses.
INTRA-LABORATORY COMPARISON (REPLICATE) RESULTS Gamma Log Number Sample 10 Number Acquisition  Sample Replicate Analysis Nuclide      Units Original Replicate Original 2 Sigma c
They include:
0
* 29 blank analyses on 29 samples
:s(5  Ratio c:
* 615 Quality Control (QC) checks
c:
* 615 Background checks
Q.)
* 15 Cross-check Program sample analyses on 3 samples
E Q.)
* 24 inter-laboratory comparison (replicate) analyses on 12 samples
SOR Number SOR SOR-Date      Type  Performed                          Result    Result                  VI        ~
* 249 intra-laboratory comparison (replicate) analyses on 132 samples Of all the QA samples that were analyzed on the PBRF Gamma Spectroscopy Systems, there were 4 discrepancies that required documentation of a Sample Deviation Report (SDR). 1.2 Liquid Scintillation Analyzer PBRF laboratory personnel performed 523 tritium sample analyses during this report period. PBRF performed a total of 1789 analyses of quality assurance (QA) samples. They include:
(Original)  (Replicate)                                                                             Uncertainty      Q.)        C>    OB OB-By                                                            a::          <<    ###
* 612 analyses on 3 reference standards
PBOB-0122B    PBOB-01229      4/B/200B      Soil  PBRF        K-40        pCi/g  1.27E+01  1.26E+01  2.70E+00 OE+OO    9.0    1.01  YES    N/A PBOB-0122B PBOB-01228    PBOB-01229      4/B/200B      Soil  PBRF      Cs-137        pCilg  3..10E-01 1OE-01 3.30E-01  1.20E-01    5.0    0.94  YES    N/A PB08-01250    PBOB-01251      4191200B      125    PBRF       K-40        pCi/g  4.50E+00  5.70E+00  1.60E+00    6.0    0.79  YES    N/A PBOB-012BO    PBOB-01281 PBOB-012B1      4115/200B      Soil  PBRF        K-40        pCi/g  1.36E+01  1.45E+01  2.70E+00  10.0    0.94  YES    N/A PBOB-01307    PBOB-01310      4/171200B      Air    PBRF       K-40        uCilml 3.30E-10  2.15E-10  7.9BE-11    B.O    1.53  YES    N/A PBOB-01320    PBOB-01321      41171200B      Soil  PBRF       K-40        pCilg  6.00E+00  9.90E+00  2.60E+00    5.0    0.61  YES    N/A PBOB-01320    PB08-01321 PBOB-01321      4/17/200B      Soil  PBRF      Cs-137        pCilg  4. 1 1OE-01 OE-01 4.90E-01  1.20E-01    7.0    0.B4  YES    N/A PBOB-01340    PBOB-01341      4/22/200B      Air    PBRF        K-40        uCilml uC    4.70E-10  B.10E-10  1.50E-10    6.0    0.5B  YES    N/A PBOB-01360    PBOB-01361      4/24/200B      Air    PBRF        K-40        uCi/ml 7.60E-10  5.70E-10  1.70E-10    9.0    1.33  YES    N/A PBOB-013BO    PBOB-013B1      4128/2008    Water  PBRF        K-40        pCi/g  5.60E-01  5.50E-01  1.70E-01    7.0    1.02  YES    N/A PBOB-013S0 PBOB-013BO    PBOS-013S1 PBOB-013B1      412S1200S 412B1200S      Water  PBRF          H3        pCilml  <MOA      <MOA        N/A    N/A      N/A  YES    ...
* 227 analyses on 227 blank samples
N/A PB08-001400 PBOS-001400 PBOB-001420 PBOB-001440 PB08-001401 PBOS-001401 PBOS-001421 PBOB-001421 PBOB-001441 51112008 5/6/200B 5/B/200B Air Air Air PBRF BRF PBRF PBRF K-40 K-40 K-40 uCilml uCilml uCi/ml 4.30E-10 4.BOE-10 9.90E-10 5.30E-10 6.B5E-10 9.12E-10 9.30E-11 1.40E-10 2.50E-10 9iE' 9.0 7.0 B.O 0.S1 0.70
* 454 analyses on 2 background samples
                                                                                                                                .70 1.09 YES YES YES N/A N/A N/A PBOB-001460  PBOB-001461    5/13/200B      Puck    PBRF        K-40        pCi/g  9.40E+00  9.70E+00  2.40E+00    B.O    0.97  YES    N/A PBOB-001480  PB08-0014B1 PB08-001481      5/131200S 5/131200B    Puck    PBRF       K-40        pCilg  1.17E+01  9.40E+00  2.B5E+00 2.S5E+00    B.O    1.24  YES    N/A C~'~
* 454 analyses on 2 QC Check samples
                                                                                                                                                -----~
* 8 Cross-check Program sample analyses on 2 samples
PBOB-001480 PB08-0014S0  PBOB-0014B1 PBOB-001481      5/131200B 5/1312008    Puck    PBRF      Cs-137        pCilg  2.10E+03  2.10E+03  7.30E+01  5B.0    1.00 YES    N/A PBOB-0014BO  PBOB-001481      511312008    Puck    PBRF      Co-6 Co-60        Ci/g pCi/g  2.40E+00  2.10E+00  3.10E-01  15.0    1.14  YES    N/A 9
* 20 inter-laboratory comparison (replicate) on 20 samples
* 14 intra-laboratory comparison (replicate) on 14 samples Of all the QA samples that were analyzed on the PBRF Liquid Scintillation Analyzer, there were no discrepancies that required documentation of a Sample Deviation Report . 1 I I I I I I I I I I I I I I
I I
* 1.0  


==SUMMARY==
-------------------                                                                TABLE 1 (Continued)
1 .1 Gamma Spectroscopy Systems 1.1.1 During the report period of January 1, 2008 and December 31, 2008, PBRF Laboratory personnel performed 4190 gamma spectroscopy sample analyses of 3006 samples. PBRF performed a total of 1547 quality assurance analyses.
INTRA-LABORATORY COMPARISON (REPLICATE) RESULTS c          C    SDR Replicate                                                                                0          (1)
They include:
Gamma Log            Sample ID                                                                                                              Original  :p E  Number Acquisition          Sample  Analysis                                        Original  Replicate                    ::I
* 29 blank analyses on 29 samples
                                                                                                                                                                .2 Number              Number                                                        Nuclide          Units                                2 Sigma      "'0 0  Ratio  (1) SDR-SDR Date            Type  Performed                                          Result    Result                    til        !!?
* 615 Quality Control (QC) checks
(Original)         (Replicate)                                                                                                           Uncertainty    (1)        0)    08 08-By                                                                                  0:::        <t:    ###
* 615 Background checks
PBOB-001500        PBOB-001501    5/14/2008            Puck    PBRF                  K-40        pCi/g    9.10E+00    B.30E+00        2.40E+00    B.O  1.10  YES    N/A PBOB-001500        PBOB-001501    5/14/200B 14/200B          Puck    PBRF               Cs-137          pCi/g    5.B3E+01    5.61 E+01      2.60E+00  45.1.04  YES    N/A PBOB-001500 PB08-oo1520 PBOB-001520 B-001520 PBOB-001540 PBOB-001501 PBOB-001521 PBOB-001521 PBOB-001541 511412008 5I141200B 5/141200B 5/1412008 51141200B 5/15/200B OOB ffiRF Puck Puck Puck Water
* 15 Cross-check Program sample analyses on 3 samples
                                                                  ,y.",
* 24 inter-laboratory comparison (replicate) analyses on 12 samples
PBRF PBRF PBRF PBRF Co-60 K-40 Cs-137 K-40 pCi/g pCi/g pCi/g pCi/g 1.20E+00 1.10E+01 E+01 3.80E+00 E+OO 6.30E-01 OE-01 1.50E+00 9.70E+00 3.BOE+00 6.50E-01 1.9BE-01 3.00E+00 5.00E+00 2.50E-01 12.0 7.0 1.5 5.0 O.BO 1.13 1.00 0.97 YES YES YES YES N/A N/A N/A N/A
* 249 intra-laboratory comparison (replicate) analyses on 132 samples 1.1.2 Of all the QA samples that were analyzed on the PBRF Gamma Spectroscopy Systems, there were 4 discrepancies that required documentation of a Sample Deviation Report (SDR). 1.2 Liquid Scintillation Analyzer 1.2.1 PBRF laboratory personnel performed 523 tritium sample analyses during this report period. PBRF performed a total of 1789 analyses of quality assurance (QA) samples. They include:
                                                                            ~ "
* 612 analyses on 3 reference standards
PBOB-001540 BOB-001540        PB08-001541 PBOB-001541    5/15/200B 5/15/2008            Water    PBRF               Cs-137          pCi/g      1.60E-01    1.70E-01      3.40E-02    9.0  0.94  YES    N/A PBOB-001540        PBOB-OO1541 PBOB-OO  1541  5/15/2008            Water    PBRF                      H3      pCi/ml    3.6BE+01    3.50E+01        2.67E+00  2B.0  1.05  YES    N/A PBOB-001560        PB08-001561 PBOB-001561    5115/200B              125    PBRF                  K-40        pCi/g    4.20E+00    4.90E+00        1.50E+00    6.0  0.B6  YES    N/A PBOB-0015BO 8-0015BO      PB08-0015B1 PBOB-0015B1    5/191200B 5/1912008            Water    PBRF                  K-40        pCi/g    1.03E+00    B.60E-01 8.60E-01        1.97E-01  10.0  1.20  YES    N/A PB08-oo15BO
* 227 analyses on 227 blank samples
              -0015BO      PBOB-0015B1    5/191200B            Water    PBRF              Cs-137          pCi/g      1.70E-01    1.BOE-01      2.60E-02  13.0  0.94  YES    N/A PBOB-001600        PBOB-001601    5/19/200B            Water    PBRF                   K-40        pCi/g    7.80E-01 7.BOE-01    6.00E-01        3.00E-01    5.0  1.30  YES    N/A f~~
* 454 analyses on 2 background samples
PBOB-001600        PBOB-001601    5/191200B 5/19120              Water    PBRF                     H3      pCi/ml        <MDA      <MDA            N/A    N/A    N/A  YES    N/A f~            -----------
* 454 analyses on 2 QC Check samples
PBOB-001620        PBOB-001621    5/13/200B 5/13/2008            Water    PBRF                   K-40        pCi/g    B.40E-01    5.40E-01      2.50E-01  7.0    1.56  YES    N/A E
* 8 Cross-check Program sample analyses on 2 samples
                                        -----------                                                              ~~~~~~~
* 20 inter-laboratory comparison (replicate) on 20 samples
                                                                                                                                      ~.
* 14 intra-laboratory comparison (replicate) on 14 samples 1.2.2 Of all the QA samples that were analyzed on the PBRF Liquid Scintillation Analyzer, there were no discrepancies that required documentation of a Sample Deviation Report . 1 I 1.3 Four Sample Deviation Reports were completed as a result of deficiencies found I during this report period. Two were associated with MAPEP Series 18 Co-60 failures.
PBOB-001620        PBOB-001621    5/13/2008            Water    PBRF                    H3      pCi/ml        <MDA      <MDA            N/A    NfA N/A    N/A  Y YES    N/A
Two were failures to attain agreement between intra-laboratory replicate analyses of K-40. These failures were investigated by the Laboratory Manager and I corrective actions were documented.
~ ~ ~    -------------
Refer to Section 10.0 of this report. 2.0 INrRODUCTION I I 2.1 This report has been prepared by the PBRF Radiological Laboratory Manager in accordance with PBRF procedure RP-060, PBRF Radiological Laboratory Quality Assurance/Quality Control Program. It provides a summary and interpretation of PBRF Laboratory QA Program for the period of January 1, 2008 to December 31, 2008. I 3.0 DISCUSSION I 3.1 A QA program is an essential part of any radiological monitoring program. It I provides reasonable assurance that the results of radiation measurements are valid. To be effective, elements of QA must be evident in all phases of the monitoring program. These include, but are not limited to, sample collection, I preservation and shipment, receipt of samples by the laboratory, preparation and analysis of samples and data review and reporting.
PBOB-001640        PBOB-001641    5/161200B              125    PBRF                  K-40       pCi/g    5.00E+00    5.40E+00        1.30E+00 E+OO  8.0 B.O    0.93  YES    N/A PB08-001640 PBOB-001640        PBOB-001641    5/16/200B              125    PBRF               Cs-137          pCi/g    3.50E-01    3.20E-01        B.90E-02  B.O    1.09  YES    N/A PBOB-001660        PB08-001661 PBOB-001661    5/221200B 5/2212008            Puck    PBRF                  K-40        pCi/g    1.16E+01    B.OOE+OO        3.00E+00  8.0 B.O    1.45  YES    N/A PBOB-0016BO        PBOB-001681 PBOB-0016B1    5/211200B 5/2112008            Puck    PBRF                  K-40        pCi/g    1.04E+01    7.60E+00        2.90E+00  7.0    1.37  YES    N/A 10
An effective QA program will allow for the identification of deficiencies in all monitoring processes so that appropriate investigative and corrective actions can be implemented.
I 3.2 The United States Nuclear Regulatory Commission (USNRC) published Regulatory I Guide 4.15, "Quality Assurance for Radiological Monitoring Programs (Normal Operations)
-EfHuent Streams and the Environment", which defines an acceptable QA program. The guidance contained in Regulatory Guide 4.15 and NRC I 10CFR50, Appendix B, "Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants" has been adopted by the PBRF Facility.
Procedures have been written and implemented to meet the objectives of these position documents.
I 3.3 Samples are typically analyzed only once because of workload constraints.
Therefore, laboratory personnel must be confident in the analytical results which are reported.
One means of achieving confidence in the results is through the analysis I of QA samples. This report provides the analytical results of various QA samples processed by the PBRF laboratory during this period. I 3.4 Quality Control checks are performed on at least 5% of all samples analyzed on the I PBRF Gamma Spectroscopy Systems and/or Liquid Scintillation Analyzer.
For the purpose of comparing results, these samples may be analyzed in duplicate by an independent laboratory (inter-laboratory comparison) or by PBRF (intra-laboratory comparison) in their entirety or split to perform multiple analyses.
The original analytical results are then compared with the replicate analysis results for I agreement.
I I I I I I I I I I I I I I I I I I 1.3 Four Sample Deviation Reports were completed as a result of deficiencies found during this report period. Two were associated with MAPEP Series 18 Co-60 failures.
Two were failures to attain agreement between intra-laboratory replicate analyses of K-40. These failures were investigated by the Laboratory Manager and corrective actions were documented.
Refer to Section 10.0 of this report. 2.0 INrRODUCTION 2.1 This report has been prepared by the PBRF Radiological Laboratory Manager in accordance with PBRF procedure RP-060, PBRF Radiological Laboratory Quality Assurance/Quality Control Program. It provides a summary and interpretation of PBRF Laboratory QA Program for the period of January 1, 2008 to December 31, 2008. 3.0 DISCUSSION 3.1 A QA program is an essential part of any radiological monitoring program. It provides reasonable assurance that the results of radiation measurements are valid. To be effective, elements of QA must be evident in all phases of the monitoring program. These include, but are not limited to, sample collection, preservation and shipment, receipt of samples by the laboratory, preparation and analysis of samples and data review and reporting.
An effective QA program will allow for the identification of deficiencies in all monitoring processes so that appropriate investigative and corrective actions can be implemented.
3.2 The United States Nuclear Regulatory Commission (USNRC) published Regulatory Guide 4.15, "Quality Assurance for Radiological Monitoring Programs (Normal Operations)
-EfHuent Streams and the Environment", which defines an acceptable QA program. The guidance contained in Regulatory Guide 4.15 and NRC 10CFR50, Appendix B, "Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants" has been adopted by the PBRF Facility.
Procedures have been written and implemented to meet the objectives of these position documents.  


===3.3 Samples===
-------------------                                                                                                TABLE 1 (Continued)
are typically analyzed only once because of workload constraints.
INTRA-LABORATORY COMPARISON (REPLICATE) RESULTS c:        "E      SDR Replicate                                                          0          Q.l Gamma Log                            Sample ID                                                                                                        Original                          Number Number                            Number Acquisition                Sample      Analysis Nuclide Units Original Replicate 2 Sigma 5    Ratio E
Therefore, laboratory personnel must be confident in the analytical results which are reported.
Q.l    SDR-Date                  Type      Performed                      Result    Result                  '0 (Original)                        (Replicate)                                                                                                    Uncertainty fI)
One means of achieving confidence in the results is through the analysis of QA samples. This report provides the analytical results of various QA samples processed by the PBRF laboratory during this period. 3.4 Quality Control checks are performed on at least 5% of all samples analyzed on the PBRF Gamma Spectroscopy Systems and/or Liquid Scintillation Analyzer.
Q.l OB OB-By                                                            Q.l        en 0::        <<        ###
For the purpose of comparing results, these samples may be analyzed in duplicate by an independent laboratory (inter-laboratory comparison) or by PBRF (intra-laboratory comparison) in their entirety or split to perform multiple analyses.
PBOB-001720                          PB08-001721          I    6/4/200B                  Water      PBRF         K40    pCi/g 5.70E-01  6. 1OE-01  1.60E-01  I  7.0  0.93  YES        N/A t**          ---------                                                      ----------
The original analytical results are then compared with the replicate analysis results for agreement.
PBOB-001720                          PB08-001721                6/4/2008                  Water      PBRF           H3    pCi/g  <MDA      <MDA        N/A      N/A    N/A  YES        N/A PBOB-001740                          PBOB-001741              6/161200B                Puck (T)     PBRF          K40    pCilg  7.BOE+00  1.03E+01  1.60E+00    10.0~
2 I I I I I I I I I I I I I I I I I I The PBRF laboratory participates in the United States Department of Energy Mixed Analyte Performance Evaluation Program (MAPEP) and the Eckert & Zeigler Analytics cross check programs.
10.0  0.76  YES        N/A r-....
Blind spike samples are sent to the PBRF Laboratory for gamma spectroscopy and tritium analysis approximately twice a year. Results are submitted via the Internet and evaluated for agreement. Blank samples are analytical control samples, usually distilled water or verified clean (non-radiological) sand or soil, used to demonstrate that reported analytical results are not the result of Laboratory and/or Sample Processing Facility contamination.
PB08-001740                          PB08-001741              6/16/200B                Puck (T)     PBRF        Cs-137  pCilg  7.60E-01  7.00E-01  1.60E-01    10.0  1.09  YES        N/A
They are used to evaluate the entire analytical procedure (sample preparation and analysis) and are prepared at the PBRF Facility for analysis in conjunction with batches or groups of regular samples. This report is divided into the following sections:
                          ...-  cc..***
* Section 4.0 -Laboratory Program
PB08-001740                          PBOB-001741              6/161200B                Puck (B)     PBRF          K40    pCi/g 9.00E+00  1.12E+01  1.BOE+00    10.0  O.BO  YES        N/A r ....           ---------
* Section 5.0 -Inter-laboratory and Intra-laboratory Comparison Analysis
PB08-001740                        PBOB-001741              6/1612008                Puck (B)     PBRF         Cs-137  pCi/g 5.80E-01  4.60E-01  1.40E-01      B.O  1.26  YES        N/A PBOB-001760                          PBOB-001761              6/17/200B                Puck (T)    PBRF          K40    pCi/g  1.00E+01  5.20E+00  2.B4E+00      7.0   1.92  YES        N/A PB08-001760                        PBOB-001761              6/17/2008                Puck (T)    PBRF        Cs-137  pCilg  1.94E+00  2.10E+00  3.30E-01    12.0  0.92  YES        N/A PB08-001760                        PB08-001761              6/171200B                Puck (B)    PBRF          K40    pCi/g  1.ooE+01  1.11E+01  2.70E+00    7.0   0.90  YES        N/A PBOB-001760                        PB08-001761              6/17/2008                Puck (B)    PBRF        Cs-137  pCilg  1.70E+00  1.60E+00  2.90E-01    12.0   1.06  YES        N/A PB08-OO1780                        PB08-0017B1              6/191200B                  Air        PBRF          K40    uCi/ml 2.30E-09  1.70E-09  6.ooE-10    8.0   1.35  YES        N/A PB08-001BOO                        PBOB-001B01 6/23/2008                Puck (T)    PBRF          K40    pCi/g  7.97E+00  9.20E+00  2.23E+00    7.0    0.B7  YES    I  N/A PB08-oo1Boo                        PB08-001B01              6/231200B                Puck (T)    PBRF        Cs-137  pCi/g  6.30E-01  5.30E-01  1.BOE-01    7.0   1.19  YES        N/A PB08-001BOO                        PB08-001B01              6/23/2008                Puck (B)    PBRF          K40    pCi/g  9.05E+00  9.40E+00  2.40E+00    B.O    0.96  YES      N/A PB08-OO1800                        PBOB-001B01              6/23/200B                Puck (B)    PBRF        Cs-137  pCi/g  5.00E-01  6.10E-01  1.90E-01    5.0    0.B2  YES      N/A PBOB-001B20                        PBOB-001B21              6/25/200B                  Water      PBRF          K40    pCilg  7.10E-01  B.BOE-01  1.90E-01    7.0   0.B1  YES      N/A PBOB-001B20                        PBOB-001B21              6/251200B                  Water  I  PBRF           H3    pCilg    <MDA      <MDA        N/A      N/A    N/A  YES      N/A PB08-001B40                        PBOB-001B41              6/27/2008                Puck (T)     PBRF          K40    pCilg  7.BOE+00  7.30E+00  1.30E+oo    12.0  1.07  YES      N/A 11 J
* Section 6.0 -Quality Control Checks
* Section 7.0 -Background Determinations
* Section 8.0 -Blank Sample Analysis
* Section 9.0 -Cross-check Program
* Section 10.0 -Laboratory/Sample Deviation Reports
* Section 11.0 -Attachments Brief discussions and summaries as well as applicable acceptance criteria are included for each section. Analytical results, which did not meet the specified acceptance criteria, are noted and discussed. LABORATORY PROGRAM The PBRF Radiological Laboratory is designed to support the analytical requirements of decommissioning work activities, environmental program, and Final Status Survey. The laboratory consists of three high resolution gamma spectroscopy units, one liquid scintillation counter, and three gas flow proportional alphalbeta counters.
The laboratory is operated by qualified personnel with documented training on all of the laboratory equipment.
Sample processing is performed in accordance with site procedures and chain of custody is maintained for all samples. There were no significant laboratory program changes during this period.
I I I I I I I I I I I I I I I I I I 4.0 3.5 The PBRF laboratory participates in the United States Department of Energy Mixed Analyte Performance Evaluation Program (MAPEP) and the Eckert & Zeigler Analytics cross check programs.
Blind spike samples are sent to the PBRF Laboratory for gamma spectroscopy and tritium analysis approximately twice a year. Results are submitted via the Internet and evaluated for agreement.  


===3.6 Blank===
samples are analytical control samples, usually distilled water or verified clean (non-radiological) sand or soil, used to demonstrate that reported analytical results are not the result of Laboratory and/or Sample Processing Facility contamination.
They are used to evaluate the entire analytical procedure (sample preparation and analysis) and are prepared at the PBRF Facility for analysis in conjunction with batches or groups of regular samples. 3.7 This report is divided into the following sections:
* Section 4.0 -Laboratory Program
* Section 5.0 -Inter-laboratory and Intra-laboratory Comparison Analysis
* Section 6.0 -Quality Control Checks
* Section 7.0 -Background Determinations
* Section 8.0 -Blank Sample Analysis
* Section 9.0 -Cross-check Program
* Section 10.0 -Laboratory/Sample Deviation Reports
* Section 11.0 -Attachments Brief discussions and summaries as well as applicable acceptance criteria are included for each section. Analytical results, which did not meet the specified acceptance criteria, are noted and discussed.
LABORATORY PROGRAM 4.1 The PBRF Radiological Laboratory is designed to support the analytical requirements of decommissioning work activities, environmental program, and Final Status Survey. The laboratory consists of three high resolution gamma spectroscopy units, one liquid scintillation counter, and three gas flow proportional alphalbeta counters.
The laboratory is operated by qualified personnel with documented training on all of the laboratory equipment.
Sample processing is performed in accordance with site procedures and chain of custody is maintained for all samples. There were no significant laboratory program changes during this period. 3 I 5.0 INTER-LABORATORY
& IN"rRA-LABORATORY COMPARISON ANALYSIS 5.1 For this report period, 24 gamma spectroscopy comparison analyses were I performed on 12 inter-laboratory samples and 249 gamma spectroscopy comparison analyses were performed on 132 intra-laboratory samples. This equates to approximately 6.5% of the total gamma spectroscopy sample analysis I performed during the report period. Two intra-laboratory comparison results were not in agreement and a Sample Deviation Report was completed for each. All of the remaining comparison analyses performed in this period were in agreement.
I 5.2 Air filter and smear samples are not typically sent to an off site laboratory for gross activity comparison analysis.
In addition, the PBRF laboratory does not perform I gross activity analysis on water or soil samples. Therefore, no inter-laboratory or intra-laboratory gross alpha/beta comparative analyses were performed during this period.I 5.3 For this report period, 14 intra-laboratory tritium comparative analyses were performed on 14 samples and 20 inter-laboratory tritium comparative analyses I were performed on 20 samples. This is approximately 6.5% of the total tritium sample analysis performed during the report period. All of the comparative analyses performed in this period were in agreement.
I I I I I I I I I I I I I I I I I I I I I I I I I I I I 5.0 INTER-LABORATORY
& IN"rRA-LABORATORY COMPARISON ANALYSIS 5.1 For this report period, 24 gamma spectroscopy comparison analyses were performed on 12 inter-laboratory samples and 249 gamma spectroscopy comparison analyses were performed on 132 intra-laboratory samples. This equates to approximately 6.5% of the total gamma spectroscopy sample analysis performed during the report period. Two intra-laboratory comparison results were not in agreement and a Sample Deviation Report was completed for each. All of the remaining comparison analyses performed in this period were in agreement.
5.2 Air filter and smear samples are not typically sent to an off site laboratory for gross activity comparison analysis.
In addition, the PBRF laboratory does not perform gross activity analysis on water or soil samples. Therefore, no inter-laboratory or intra-laboratory gross alpha/beta comparative analyses were performed during this period. 5.3 For this report period, 14 intra-laboratory tritium comparative analyses were performed on 14 samples and 20 inter-laboratory tritium comparative analyses were performed on 20 samples. This is approximately 6.5% of the total tritium sample analysis performed during the report period. All of the comparative analyses performed in this period were in agreement.
-------------------
TABLE INTRA-LABORATORY COMPARISON (REPLICATE) Gamma Log Number (Original)
Sample ID Number (Replicate)
Acquisition Date Sample Type Replicate Analysis Performed By Nuclide Units Original Result Replicate Result Original 2 Sigma Uncertainty c: .2 S (5 If) (]) 0 c: (]) E (]) Ol <t: SDR Number ### PBOS-00020 PBOS-00021 111012008 Paint Chips PBRF K-40 pCilg 6.7SE+02 9.09E+02 3.20E+02 4.0 0.75 YES N/A PB08-00020 PB08"()0021 PBOS"()0041 1/10/2008 Paint Chips PBRF Co-60 pCilg S.02E+01 S.10E+01 2.44E+01 7.0 0.99 YES N/A PBOB"()0040 PBOS-00040 1/14/200B 1/14/200S Puck PBRF K-40 pCilg 9.40E+00 B.60E+00 2.60E+00 7.0 1.09 YES N/A PBOS-00041 Puck PBRF Co-60 pCilg 1.35E+01 1.32E+01 B.20E"()1 33.0 1.02 YES N/A PBOB-00040 PBOB-00041 1/14/200B Puck PBRF Cs-137 pCi/g 2.30E+00 2.70E+00 3.90E"()1 12.0 0.85 YES N/A PB08-00060 PBOS"()OOBO PBOB-00061 PBOB-000B1 1/15/200B 1/161200S Soil PBRF K-40 pCi/g 1.35E+01 1.19E+01 1.95E+00 14.0 1.13 YES N/A Air PBRF K-40 uCi/ml 1.44E-09 1.60E-09 4.30E-10 7.0 0.90 YES N/A PB08"()0100 PBOS-00100 PB08-00101 PBOB"()0101 1/1712008 1/17/200S Soil PBRF Co-60 pCilg 2.50E+02 2.47E+02 B.30E+00 60.0 1.01 YES N/A Soil Air PBRF Cs-137 pCilg 1.40E+04 1.38E+04 4.50E+02 62.0 1.01 YES N/A PBOS"()0120 PBOS-00121 1/231200S PBRF K-40 uCilml 2.60E"()9 2.20E-09 6.90E-10 8.0 1.18 YES N/A PBOB-00140 PBOS-00141 1/2B1200B Puck PBRF Ag108m pCilg 1.20E+00 1.20E+00 1.50E"()1 16.0 1.00 YES N/A PBOB-00140 PBOS-00160 PBOS-00160 PBOS-00141 1/2S/200B Puck PBRF Cs-137 pCi/g 7.50E-01 9.30E-01 2.30E-01 7.0 0.81 YES N/A PBOS-00161 PBOB"()0161 1/2S/2008 112S12008 Water Water PBRF PBRF K-40 pCi/g S.50E-01 9.70E-01 3.40E-01 5.0 15.0 0.88 YES N/A Cs-137 pCi/g 6.BOE-01 1.40E-01 6.00E-01 9.00E-02 1.13 YES N/A PB08-00160 PBOS-00160 PBOS-00161 112B1200B Water PBRF Co-60 pCi/g 1.20E-01 4.00E-02 7.0 1.17 YES N/A PBOB-00161 1/2S1200B Water PBRF H3 pCilml 9.44E+01 8.96E+01 4.22E+00 45.0 1.05 YES N/A PBOB-00180 PBOB-001BO PBOB-001S1 1/221200B Water PBRF K-40 pCilg 6.40E-01 7.30E-01 2.60E"()1 5.0 0.88 YES N/A PBOB-001B1 1/221200S Water PBRF H3 pCilml 1.00E+00 4.00E-01 1.00E+00 2.0 2.50 YES N/A PBOB-00200 PBOB-00201 1/30/200B Air PBRF K-40 uCi/ml 7.11E-10 7.00E-10 1.BOE-11 79.0 1.02 YES N/A PBOB-00220 PBOB-00220 PBOS-00221 2/512008 Soil PBRF PBRF K-40 pCilg 6.10E+00 3.S0E+00 1.70E+00 7.0 1.61 YES N/A PBOS"()0221 2/512008 Soil Cs-137 pCilg 1.00E+00 1.10E+00 2.70E-01 7.0 0.91 YES N/A -------------------
TABLE 1 INTRA-LABORATORY COMPARISON (REPLICATE)
RESULTS c: c: SDR Gamma Log Sample ID Replicate Original .2 0 (]) Number Number Number Acquisition Sample Analysis Nuclide Units Original Replicate 2 Sigma S E SDR-Date Type Result Result (5 (]) (Original) (Replicate)
Performed By Uncertainty If) 08-(]) Ol <t: ### PBOS-00020 PBOS-00021 111012008 Paint -40 pCilg 6.7SE+02 9.09E+02 3.20E+02 4.0 0.75 YES N/A Chips PB08-00020 PB08"()00 Paint 0-60 pCilg S.02E+01 S.10E+01 2.44E+01 7.0 0.99 YES N/A Chips PBOB"()0040 PBOS"()OO 1/14/200B Puck PBRF K-40 pCilg 9.40E+00 B.60E+00 1.09 YES NI PBOS-00040 PBOS-00041 1/14/200S Puck PBRF Co-60 pCilg 1.35E+01 1.32E+01 B.20E 1.02 YES PBOB-00040 PBOB-00041 1/14/200B Puck PBRF Cs-137 pCi/g 2.30E+00 2.70E+00 3.90E"()1
: 1. 0.85 YES PB08-00060 PBOB-00061 1/15/200B Soil PBRF K-40 pCi/g 1.35E+01 1.19E+01 1.95E+00 14.0 1.13 YES N/A PBOS"()OOBO PBOB-000B1 1/161200S Air PBRF K-40 uCi/ml I 1.44E-09 1.60E-09 4.30E-10 7.0 0.90 YES N/A PB08"()0100 PB08-00101 1/1712008 Soil PBRF Co-60 pCilg 2.50E+02 2.47E+02 B.30E+00 60.0 1.01 YES N/A PBOS-00100 PBOB"()0101 1/17/200S Soil PBRF Cs-137 pCilg 1.40E+04 1.38E+04 4.S0E+02 62.0 1.01 YES N/A PBOS"()0120 PBOS-00121 1/231200S Air PBRF K-40 uCilml 2.60E"()9 2.20E-09 6.90E-10 8.0 1.18 YES N/A PBOB-00140 PBOS-00141 1/2B1200B Puck PBRF Ag108m pCilg E+OO 1.20E+00 1.S0E"()1 16.0 1.00 YES N/A PBOB-00140 PBOS-00141 1/2S/200B Puck PBRF Cs-137 pCi/g 7.S0E-01 9.30E-01 2.30E-01 7.0 0.81 YES N/A ----------------
PBOS-00160 PBOS-00161 1/2S/2008 Water PBRF K-40 pCi/g S.SOE-01 9.70E-01 3.40E-01 S.O 0.88 YES N/A PBOS-00160 PBOB"()0161 112S12008 Water PBRF Cs-137 pCi/g 6.BOE-01 6.00E-01 9.00E-02 1S.0 1.13 YES N/A PB08-00160 PBOS-00161 112B1200B Water PBRF Co-60 pCi/g 1.40E-01 1.20E-01 4.00E-02 7.0 1.17 YES N/A ------------
PBOS-00160 PBOB-00161 1/2S1200B Water PBRF H3 pC' 9.44E+01 8.96E+01 4.22E+00 4S.0 1.0S YES N/A PBOB-00180 PBOB-001S1 1/221200B Water PBRF K-40 pCilg 6.40E-01 7.30E-01 2.60E"()1 5.0 0.88 Y E ------------PBOB-001BO PBOB-001B1 1/221200S Water PBRF H3 pCilml 1.00E+00 4.00E-01 1.00E+00 2.0 2.S0 Y N/A PBOB-00200 PBOB-00201 1/30/200B Air PBRF K-40 uCi/ml 7.11E-10 7.00E-10 1.BOE-11 79.0 1.02 YES N/A PBOB-00220 PBOS-00221 2/S12008 Soil PBRF K-40 pCilg 6.10E+00 3.S0E+00 1.70E+00 7.0 1.61 YES N/A ----------PBOB-00220 PBOS"()0221 2/S12008 Soil PBRF Cs-137 pCilg 1.00E+00 1.10E+00 2.70E-01 7.0 0.91 5 
-------------------
TABLE 1 (Continued)
TABLE 1 (Continued)
INTRA-LABORATORY COMPARISON (REPLICATE) Gamma Log Sample ID Acquisition Number Number Date (Original) (Replicate)
INTRA-LABORATORY COMPARISON (REPLICATE) RESULTS t::        'E  SDR Replicate                                                  .2          Q)
PB08-00240 PB08-00241 2/6/2008 PB08-00260 PB08-00261 2/6/2008 PB08-00280 PB08-00281 2/612008 PB08-00303 PB08-00304 211112008 PB08-00320 PB08-00321 2112/2008
Gamma Log              Sample ID                                                                                        Original                E Number Acquisition          Sample      Analysis                  Original Replicate              'S Number            Number                                                      Nuclide Units                      2 Sigma    "0  Ratio  Q)  SDR-Date            Type      Performed                    Result    Result                (I)        ~
-
(Original)          (Replicate)                                                                                      Uncertainty  Q)              OB-By                                                      cr          Jl    ###
PB08-00340 PB08-00341 2/1312008 PB08-00360 PB08-00361 2113/2008 PB08-00380 PB08-00381 211212008 PB08-00422 PB08-00423 2/2012008 PB08-00422 PB08-00423 2120/2008 PB08-00440 PB08-00441 2/21/2008 PB08-00460 PB08-00461 2121/2008 PB08-00480 PB08-00481 212212008 PB08-00500 PB08-00501 212512008 PB08-00534 PB08-00535 2/27/2008 PB08-00540 PB08-00541 2/2712008 PB08-00560 PB08-00561 2/2712008 PB08-00580 PB08-00581 2/2912008 PB08-00580 PB08-00581 2/29/2008 PB08-00600 PB08-00602 3/3
PBOB-001860            PBOB-001861        6/3012008    08    Puck (T)    PBRF     
: 4. If both sample results are less than Minimum Detectable Activity (MDA), they are in agreement.
: 4. If both sample results are less than Minimum Detectable Activity (MDA), they are in agreement.
When comparing a positive result to a <MDA result, the <MDA result is assumed to be positive activity and used to calculate the ratio. 5. Those sample analyses that do not agree are annotated by a "NO" answer in the "Agreement" column. The corresponding Sample Deviation Report (SDR) number can be located in the "SDR Number" column. TABLE 3: SAMPLE RESOLUTION AND RATIO AGREEMENT CRITERIA RATIO <4 0.4 -2.5 4-7 0.5 -2.0 8-15 0.6 -1.66 16 -50 0.75-1.33 51 -200 0.8 -1.25 >200 0.85 -1.18 6.0 QUALITY CONTROL CHECKS 6.1 A Quality Control Check is performed on the PBRF Gamma Spectroscopy Systems daily before analyzing samples and immediately after changes in electronic components that may affect system operability.
I          When comparing a positive result to a <MDA result, the <MDA result is assumed to be positive activity and used to calculate the ratio.
The results are compared to parameters specified in RP-021, Rev. 0, Operation and Calibration of the ORTEC Gamma Spectroscopy System. Results that are not within the prescribed ranges are investigated prior to placing the system in operation.
: 5. Those sample analyses that do not agree are annotated by a "NO" answer in the "Agreement" I          column. The corresponding Sample Deviation Report (SDR) number can be located in the "SDR Number" column.
A total of 615 Quality Control Checks were performed during this period. No deficiencies were noted. 6.2 A system normalization and calibration using flame-sealed unquenched Carbon-14, Tritium, and background reference standards traceable to the National Institute of Standards (NIST) is performed on the PBRF Liquid Scintillation Analyzer daily before analyzing samples and immediately after changes in electronic components that may affect system operability.
I                  TABLE 3: SAMPLE RESOLUTION AND RATIO AGREEMENT CRITERIA RESOLUTIC~~                  RATIO I                                            <4 4-7 0.4 - 2.5 0.5 - 2.0 I                                          8-15 16 - 50 0.6 -1.66 0.75-1.33 I                                        51 - 200
The results are compared to parameters specified in RP-020, Rev. 0, Packard TriCarb 2900 TR Liquid Scintillation Analyzer.
                                            >200 0.8 -1.25 0.85 -1.18 6.0   QUALITY CONTROL CHECKS I          6.1     A Quality Control Check is performed on the PBRF Gamma Spectroscopy Systems daily before analyzing samples and immediately after changes in electronic components that may affect system operability. The results are I                  compared to parameters specified in RP-021, Rev. 0, Operation and Calibration of the ORTEC Gamma Spectroscopy System. Results that are not within the prescribed ranges are investigated prior to placing the system in operation. A total I                  of 615 Quality Control Checks were performed during this period. No deficiencies were noted.
Results that are not within the prescribed ranges are I 21 I investigated prior to placing the system in operation.
I          6.2     A system normalization and calibration using flame-sealed unquenched Carbon-14, Tritium, and background reference standards traceable to the National Institute of Standards (NIST) is performed on the PBRF Liquid Scintillation Carbon I                  Analyzer daily before analyzing samples and immediately after changes in electronic components that may affect system operability. The results are compared to parameters specified in RP-020, Rev. 0, Packard TriCarb 2900 TR I                  Liquid Scintillation Analyzer. Results that are not within the prescribed ranges are I                                                         21
A total of 204 system normalization and calibrations were performed.
  ~------------------------------~
No deficiencies were noted. I 6.3 Two tritium QC Check samples are analyzed on the Liquid Scintillation Analyzer with each batch of samples. The QC check samples are prepared from a NIST traceable tritium source solution and scintillation cocktail.
 
One QC Check sample I is placed before the sample set and one is placed after the sample set. Tritium QC check samples were analyzed in 227 sample batches during this report period. No deficiencies were noted. I  
I~------------------------------~
I          investigated prior to placing the system in operation. A total of 204 system normalization and calibrations were performed. No deficiencies were noted.
I     6.3 Two tritium QC Check samples are analyzed on the Liquid Scintillation Analyzer with each batch of samples. The QC check samples are prepared from a NIST traceable tritium source solution and scintillation cocktail. One QC Check sample I         is placed before the sample set and one is placed after the sample set. Tritium QC check samples were analyzed in 227 sample batches during this report period.
No deficiencies were noted.
I


==7.0 BACKGROUND==
==7.0 BACKGROUND==
DETERMINATIONS I      7.1 A background check is performed on the Gamma Spectroscopy Systems at least daily as required by procedure PBRF-RP-021, Rev. 2, Operation and Calibration of the ORTEC Gamma Spectroscopy System. Background determinations are I          used to ensure that the counting environment is free of contamination.
Background results are plotted daily to observe trends and unusual results. A total of 615 background checks were performed on the PBRF Gamma Spectroscopy I          Systems during this report period. All background checks were performed satisfactorily. No deficiencies were noted.
I      7.2 A background reference sample is analyzed daily prior to sample counting to calculate the figure of merit (FOIVI) quench indicating parameter (QIP) of E2/B.
This value is used to determine counting efficiency.
I      7.3 Two background samples are analyzed on the Liquid Scintillation Analyzer with each batch of samples. The background samples are prepared with de-ionized I          water and scintillation cocktail. One background sample is placed before the sample set and one is placed after the sample set. Results are used to subtract a background count from the sample count and calculate an MDA. Background I          samples were analyzed in 227 sample batches during this report period. No deficiencies were noted.
I  8.0 BLANK SAMPLE ANALYSIS 8.1 Sample Processing Facility and Laboratory Technicians prepare blank samples I          during the processing of regular samples in accordance with RP-060. The analysis of blank samples ensures that measurement error is not the result of contamination of sampling equipment or processing techniques. The acceptance I          criteria for blank sample results are no detectable PBRF related activity above the target Minimum Detectable Activity (MDA).
I          8.1.1 A total of 29 Gamma Spectroscopy Analyses were performed on 29 blank samples during this report period. No PBRF related gamma activity was detected in any blank sample above the analysis MDA.
I          8.1.2 A total of 227 tritium analyses were performed on 227 blank samples during this report period. No tritium activity was observed in any blank I                  sample above the analysis MDA.
I                                            22


DETERMINATIONS I 7.1 A background check is performed on the Gamma Spectroscopy Systems at least I daily as required by procedure PBRF-RP-021, Rev. 2, Operation and Calibration of the ORTEC Gamma Spectroscopy System. Background determinations are used to ensure that the counting environment is free of contamination.
I~------------------------------~
Background results are plotted daily to observe trends and unusual results. A total of 615 background checks were performed on the PBRF Gamma Spectroscopy I Systems during this report period. All background checks were performed satisfactorily.
I  9.0  CROSS-CHECK PROGRAM 9.1 PBRF participates in the United States Department of Energy (DOE) Mixed I             Analyte Performance Evaluation Program (MAPEP). MAPEP Series 18 was issued in January 2008 and resulted in a Co-60 failure on the MaS (soil) sample and a Co-60 failure on the RdF (filter) sample. Co-60 was incorrectly identified in I            the MaS sample, when in fact it was not present above the analysis sensitivity.
No deficiencies were noted. I 7.2 A background reference sample is analyzed daily prior to sample counting to calculate the figure of merit (FOIVI) quench indicating parameter (QIP) of E 2/B. This value is used to determine counting efficiency.
Co-60 was reported outside the acceptance range (> 30%) of the reference value and Cs-137 was> 20% for the RdF sample. A replicate analysis performed on I            these results was in agreement with the reference values. The remaining results were within the acceptance range for each sample matrix. Series 19 was issued in August 2008. All reported results were within the acceptance range for each I            sample matrix. MAPEP Series results are shown in Attachment B.
I I 7.3 Two background samples are analyzed on the Liquid Scintillation Analyzer with each batch of samples. The background samples are prepared with de-ionized water and scintillation cocktail.
9.2  Tritium cross-check samples obtained from Eckert & Ziegler Analytics were I             analyzed in January and July. Each sample was analyzed multiple times to reduce the counting uncertainty. The average of these analysis and uncertainties are then reported to Eckert & Ziegler Analytics. The cross-check sample results I            were within the acceptable range of the standard for both series. Cross-check results are shown in Attachment B.
One background sample is placed before the I sample set and one is placed after the sample set. Results are used to subtract a background count from the sample count and calculate an MDA. Background samples were analyzed in 227 sample batches during this report period. No deficiencies were noted. I 8.0 BLANK SAMPLE ANALYSIS I 8.1 Sample Processing Facility and Laboratory Technicians prepare blank samples during the processing of regular samples in accordance with RP-060. The I analysis of blank samples ensures that measurement error is not the result of contamination of sampling equipment or processing techniques.
I   10.0 LABORATORY/SAMPLE DEVIATION REPORTS 10.1 A Laboratory/Sample Deviation Report (SDR) provides a method to document I            sampling or sample analysis conditions that are adverse to quality. The identification of the condition adverse to quality, the cause of the condition, and the corrective action taken are documented and reported to the appropriate levels I            of management.
The acceptance criteria for blank sample results are no detectable PBRF related activity above the target Minimum Detectable Activity (MDA). I 8.1.1 A total of 29 Gamma Spectroscopy Analyses were performed on 29 blank samples during this report period. No PBRF related gamma activity was detected in any blank sample above the analysis MDA. I I 8.1.2 A total of 227 tritium analyses were performed on 227 blank samples during this report period. No tritium activity was observed in any blank sample above the analysis MDA.
10.2 Each SDR is completed in accordance with procedure RP-060, PBRF I             Radiological Laboratory Quality Assurance/Quality Control Program.
I I I I I I I I I I I I I I I I I I investigated prior to placing the system in operation.
10.3 A total of 4 SDRs were completed during this report period. Each incident was I            investigated by the Laboratory Manager and corrective actions were addressed and all SDRs were closed. A copy of each SDR is provided in Attachment A. The SDRs consisted of the following:
A total of 204 system normalization and calibrations were performed.
I
No deficiencies were noted. 6.3 Two tritium QC Check samples are analyzed on the Liquid Scintillation Analyzer with each batch of samples. The QC check samples are prepared from a NIST traceable tritium source solution and scintillation cocktail.
* SDR-08-001 - MAPEP MaS-18 Co-60 failure
One QC Check sample is placed before the sample set and one is placed after the sample set. Tritium QC check samples were analyzed in 227 sample batches during this report period. No deficiencies were noted.
* SDR-08-002 - MAPEP RdF-18 Co-60 failure and Cs-137 waming I
* SDR-08-003 - K-40 replicate not in agreement I   11.0 ATTACHMENTS SDR-08-004 - K-40 replicate not in agreement I       A.
B.
Sample Deviation Reports Cross-Check Reports I
I                                              23
  ~----------------------------~


==7.0 BACKGROUND==
I I
I I
I I
I      Attachment A I Sample Deviation Reports I
I I
I I
I I
I I
I I            24
 
I~------------------------------~
I                                                          EXHIBIT 2 I                                              SAMPLE DEVIATION REPORT I  SAMPLE LOCATION/DESCRIPTION MAPEP MaS-18 Co-GO failure REPORT NUMBER SDR-08-001 I  INSTRUMENT (Check One)
Gross Alpha/Beta D        Liq. Scinto D      Gamma Spec.      r8:I      Serial #  Detector #1 #2 #3 I  SAMPLE TYPE (Check One)
I  Soil r8:I    Water/Liquid D        PlanchetD          Concrete Debris D        Other D SAMPLE START DATEITIME                                                SAMPLE STOP DATEITIME I
I 2/4/08 111 :05                              I N/A I  ANALYTICAL PROBLEM MAPEP MaS-18 Soil sample results were in excess of the Co-GO reference value. The reported value was 14.3 Bq/kg and the reference value was 2.9 Bq/kg. As this was a sensitivity test for Co-GO, no acceptance range is given.
I I
I  CORRECTIVE ACTIONS AND/OR COMMENTS A review of the gamma spectroscopy analysis for this sample revealed that the Co-50 1332 peak was not present I  in the spectrum. Since the Gamma Vision library recognized the 1173 peak, it associated the region counts with Co-GO and reported an incorrect activity. This is not the library that is normally used to analyze PBRF soil samples,
* but was used for MAPEP since the results are reported in Becquerels. The library was corrected to require both
* peaks to be present to identify Co-GO in a sample.
I
* I  Submitted By: (Print/Sign) R. Case                                                                DATE 8/13/08 I  Radiological Laboratory Manager (Print/Sign) R. Case                                              DATE 8/13/08 DATE 8/13/08 NASA Project RSO (PrintlSign) W. Stoner I
I 25 I
 
I~------------------------------~                            EXHIBIT 2 I
I  SAMPLE LOCATION/DESCRIPTION SAMPLE DEVIA DEVIAnON nON REPORT I REPORT NUMBER I                      MAPEP RdF-18 Co-60 failure and Cs-137 warning I
SDR-08-002 INSTRUMENT (Check One)
I  Gross Alpha/Beta D        Liq. Scinto D      Gamma Spec. [8]          Serial #    Detector #1 #2 #3 I . SAMPLE TYPE (Check One)
SoUD        Water/Liquid D        PlanchetD        Concrete Debris D        Other [8] Air Filter I  SAMPLE START DA*rE/TIME                                          SAMPLE STOP DATEITIME I  ANALYTICAL PROBLEM 2/4/08/14:27                                                    N/A I  MAPEP RdF-18 Air filter Co-60 sample result was> 30% (48.9%) of the reference value and Cs-137 was >20%
(28.9%) of the reference value. The reported value for Co-60 was 1.95 +/-0.33 8q/sample and the reference value was 1.318q/sample. The reported value for Cs-137 was 3.48 +/-0.5 8q1sample and the reference value was 2.70 8q/sample.
I I
CORRECTIVE ACTIONS ANDIOR COMMENTS I  The reported values are the numerical average for each nuclide of 5 trials. The standard deviation in the trial set is 0.6 8q for Co-60 and 0.7 8q for Cs-137. A replicate analysis was performed on these results. 80th the Co-60 and Cs-137 results were in agreement with the MAPEP reference values. The sample analYSis process for this I  geometry was observed by the Laboratory Manager and no discrepancies were found. The samples were analyzed for 1000 seconds which is typical for this sample type. However, a significantly longer count time will improve the uncertainty and should result in a smaller variance between sample trials. Subsequent MAPEP filter samples will I  be given a 43,200 second count time.
Submitted By: (Print/Sign) R. Case                                                                DATE 8/13/08 I  Radiological Laboratory Manager (Print/Sign) R. Case                                              DATE 8/13/08 I  NASA Project RSO (Print/Sign) W. Stoner                                                          DATE 8/13/08 I
I I                                                            26
 
I EXHIBIT 2 I                                                  SAMPLE DEVIATION REPORT I i SAMPLE LOCATION/DESCRIPTION                                                                        REPORT NUMBER I    INSTRUMENT (Check One)
PB08-02340 K-40 not in agreement SDR-08-003 I    Gross Alpha/Beta D          Liq. Scinto D        Gamma Spec. [ZJ          Serial #    Detector #3 & #1 SAMPLE TYPE (Check One)
I    Soil D        Water/Liquid D        PlanchetD        Concrete Debris D          Other [ZJ Concrete Core I    SAMPLE START DATEITIME SAMPLE STOP DATEITIME 8/21/08/10:48                                                        N/A I    ANALYTICAL PROBLEM I
PB08-02340 K-40 (12.6+/-3 pCi/g) replicate analysis not in agreement with PB08-02343 recount (6.5+/-2 pCi/g) on I    Detector #1.
I I    CORRECTIVE ACTIONS AND/OR COMMENTS Sample was recounted on Detectors #1 & #2 (PB08-02500 & PB08-02501). The K-40 results (pCi/g) were in I    agreement on both counts with the original result and with each other.
Detector        Original        Replicate      2 Sigma            Resolution    Ratio    Agreement Original        1.26E+01          6.50E+OO      3.00E+OO              8.0        1.94          No I            Det#1 &#2 Oet#1 &#3 Oet#1 & Oet#1 8.40E+OO 8.40E+00 8.40E+00 9.40E+OO 1.26E+01 6.50E+OO 2.20E+00 2.20E+OO 2.20E+00 8.0 8.0 8.0 0.89 0.67 1.29 Yes Yes Yes Det#2 & Oet#1      1.2SE+01          9.40E+OO      3.00E+00              8.0      I 1.34        Yes I    The differences in the results are not statistically significant within the variability of the time of measurement uncertainty. No further action is required.
I    Submitted By: (Print/Sign)          R. Case                                                        DATE 9/9/08 I  : Radiological Laboratory Manager (Print/Sign)            R. Case                                      DATE 9/9/08 NASA Project RSO (Print/Sign)        W. Stoner                                                      DATE 9/9/08 I
I 27 I
 
I~----------------------------~                        EXHIBIT 2 I
SAMPLE DEVIATION REPORT I  SAMPLE LOCATION/DESCRIPTION REPORT NUMBER I                              PBOS"()2960 K-40 not in agreement                                      SDR-OS-004 INSTRUMENT (Check One)
I  Gross Alpha/Beta  0      Liq. Scinto      Gamma Spec. [gI          Serial #    Detector #2 & #1 I  SAMPLE TYPE (Check One)
Soil [gI    WaterlLiquid          Planchet 0      Concrete Debris  0      Other  0  Concrete Core I  SAMPLE START DATErrlME                                            SAMPLE STOP DATEfTlME 12/11/0S/12:54                                                    NIA I i ANALYTICAL PROBLEM PB08"()2960 K-40 (1.7+/-0.72 pCi/g) replicate analysis count on Detector #2 not in agreement with PBOS"()2961 I  recount (10.0+/-2 pCilg) on Detector #1.
I I  CORRECTIVE ACTIONS ANDIOR COMMENTS The sample was re-analyzed on Detectors 1,2, and 3 with the following K-40 results:
I                            Detector 1            Detector 2            Detector 3 I                            10.1+/-1.7              10.1+/-1.9              9.99+/-1.8 I
Agreement was obtained between all three detectors. No further action is required.
I I  Submitted By: (Print/Sign)        R. Case                                                      DATE: 117/09 DATE: 117/09 I  Radiological Laboratory Manager (Print/Sign)
NASA Project RSO (Print/Sign) W. Stoner R. Case DATE: 117109 I
I I                                                            28
 
I I
I I
I I
I    Attachment B Cross-Check Reports I
I I
I I
I I
I I
I I
29 I


DETERMINATIONS 7.1 A background check is performed on the Gamma Spectroscopy Systems at least daily as required by procedure PBRF-RP-021, Rev. 2, Operation and Calibration of the ORTEC Gamma Spectroscopy System. Background determinations are used to ensure that the counting environment is free of contamination.
o o
Background results are plotted daily to observe trends and unusual results. A total of 615 background checks were performed on the PBRF Gamma Spectroscopy Systems during this report period. All background checks were performed satisfactorily.
o                          PEP                  Analyte Mixed Analy1e Performance Evaluat on ProtJraIT1  Pro~ram o Laborotory Rssult.! For MAPEP Series 18 LaboroJory NASA P"um  P um Brook Reactor Faciliiy 6100 Columbus Cohmbus Ave Facility Lab (PBRF01) o Sandusl:y, OH 44870 Sandusl]',
No deficiencies were noted. 7.2 A background reference sample is analyzed daily prior to sample counting to calculate the figure of merit (FOIVI) quench indicating parameter (QIP) of E 2/B. This value is used to determine counting efficiency.
  ~L\PEP-3i
7.3 Two background samples are analyzed on the Liquid Scintillation Analyzer with each batch of samples. The background samples are prepared with de-ionized water and scintillation cocktail.
  ~L\PIP-Oi - ~hS18:
One background sample is placed before the sample set and one is placed after the sample set. Results are used to subtract a background count from the sample count and calculate an MDA. Background samples were analyzed in 227 sample batches during this report period. No deficiencies were noted. 8.0 BLANK SAMPLE ANALYSIS 8.1 Sample Processing Facility and Laboratory Technicians prepare blank samples during the processing of regular samples in accordance with RP-060. The analysis of blank samples ensures that measurement error is not the result of contamination of sampling equipment or processing techniques.
Inom;mic Inon!4Illc
The acceptance criteria for blank sample results are no detectable PBRF related activity above the target Minimum Detectable Activity (MDA). 8.1.1 A total of 29 Gamma Spectroscopy Analyses were performed on 29 blank samples during this report period. No PBRF related gamma activity was detected in any blank sample above the analysis MDA. 8.1.2 A total of 227 tritium analyses were performed on 227 blank samples during this report period. No tritium activity was observed in any blank sample above the analysis MDA. 22 I I I I I I I I I I I I I I I I I I CROSS-CHECK PROGRAM PBRF participates in the United States Department of Energy (DOE) Mixed Analyte Performance Evaluation Program (MAPEP). MAPEP Series 18 was issued in January 2008 and resulted in a Co-60 failure on the MaS (soil) sample and a Co-60 failure on the RdF (filter) sample. Co-60 was incorrectly identified in the MaS sample, when in fact it was not present above the analysis sensitivity.
                    ~laS18: &idio\ogic:ll,
Co-60 was reported outside the acceptance range (> 30%) of the reference value and Cs-137 was> 20% for the RdF sample. A replicate analysis performed on these results was in agreement with the reference values. The remaining results were within the acceptance range for each sample matrix. Series 19 was issued in August 2008. All reported results were within the acceptance range for each sample matrix. MAPEP Series results are shown in Attachment B. Tritium cross-check samples obtained from Eckert & Ziegler Analytics were analyzed in January and July. Each sample was analyzed multiple times to reduce the counting uncertainty.
                            &!d:iologica~  inorganic ;llld  semi-,*oi:ltile ol'ganics combined soil and Semi-yol:ltile                                  standard 5 0il sTandard units:
The average of these analysis and uncertainties are then reported to Eckert & Ziegler Analytics.
Units: (mgikg)
The cross-check sample results were within the acceptable range of the standard for both series. Cross-check results are shown in Attachment B. LABORATORY/SAMPLE DEVIATION REPORTS A Laboratory/Sample Deviation Report (SDR) provides a method to document sampling or sample analysis conditions that are adverse to quality. The identification of the condition adverse to quality, the cause of the condition, and the corrective action taken are documented and reported to the appropriate levels of management. Each SDR is completed in accordance with procedure RP-060, PBRF Radiological Laboratory Quality Assurance/Quality Control Program. A total of 4 SDRs were completed during this report period. Each incident was investigated by the Laboratory Manager and corrective actions were addressed and all SDRs were closed. A copy of each SDR is provided in Attachment A. The SDRs consisted of the following: SDR-08-001
(mg kg) o  Analyre Analyte Antimony AnIimooy Resul NR Ref Vahre Flag li:abJe 23.a 23_~
-MAPEP MaS-18 Co-60 failure SDR-08-002
Rag Nores        Bils Bill Ac:aptance Aa:eptmce Range BaDge 166.5-30'_6 5 -30.6 Unc L'nc Yalm:
-MAPEP RdF-18 Co-60 failure and Cs-137 waming SDR-08-003
                                                                                                                  ~ame Ell" line Eagc o Arser5c Barium Beryllium Berylium Cadmium NR NR NR NR 20 2 202 244 13_B 13.B 9.49' Q.4G 14.1 14_1 -20.
-K-40 replicate not in agreement SDR-08-004
171
-K-40 replicate not in agreement ATTACHMENTS Sample Deviation Reports Cross-Check Reports 23 I 9.0 CROSS-CHECK PROGRAM I I I I I I I I I I I I I I I I 9.1 PBRF participates in the United States Department of Energy (DOE) Mixed Analyte Performance Evaluation Program (MAPEP). MAPEP Series 18 was issued in January 2008 and resulted in a Co-60 failure on the MaS (soil) sample and a Co-60 failure on the RdF (filter) sample. Co-60 was incorrectly identified in the MaS sample, when in fact it was not present above the analysis sensitivity.
                                                                                                    -26.3
Co-60 was reported outside the acceptance range (> 30%) of the reference value and Cs-137 was> 20% for the RdF sample. A replicate analysis performed on these results was in agreement with the reference values. The remaining results were within the acceptance range for each sample matrix. Series 19 was issued in August 2008. All reported results were within the acceptance range for each sample matrix. MAPEP Series results are shown in Attachment B. 9.2 Tritium cross-check samples obtained from Eckert & Ziegler Analytics were analyzed in January and July. Each sample was analyzed multiple times to reduce the counting uncertainty.
                                                                                                    -317 171-317 9] -17.9 9]-lHI 6.64-12,34 6.64-12.34 3
The average of these analysis and uncertainties are then reported to Eckert & Ziegler Analytics.
o Chromum CobII Cobalt Copper l ead lead NR NR NR NR 70_7 70.7 4 1.5 4U:
The cross-check sample results were within the acceptable range of the standard for both series. Cross-check results are shown in Attachment B. 10.0 LABORATORY/SAMPLE DEVIATION REPORTS 10.1 A Laboratory/Sample Deviation Report (SDR) provides a method to document sampling or sample analysis conditions that are adverse to quality. The identification of the condition adverse to quality, the cause of the condition, and the corrective action taken are documented and reported to the appropriate levels of management.
B7_0 87.0 79 49 2{j
10.2 Each SDR is completed in accordance with procedure RP-060, PBRF Radiological Laboratory Quality Assurance/Quality Control Program. 10.3 A total of 4 SDRs were completed during this report period. Each incident was investigated by the Laboratory Manager and corrective actions were addressed and all SDRs were closed. A copy of each SDR is provided in Attachment A. The SDRs consisted of the following:
                                                                                                .5- 91 .9 4~L5-zg 11-54.
* SDR-08-001
                                                                                                    -54.0
-MAPEP MaS-18 Co-60 failure
                                                                                                        .9 0
* SDR-08-002
_Q - 1l3.1 eo .9-55-103 55 1 3_1
-MAPEP RdF-18 Co-60 failure and Cs-137 waming
                                                                                                    -103 o Merot.y Merou.ry ickel Selenium Sillierr S
* SDR-08-003
NR NR NR NR
-K-40 replicate not in agreement
                                                        <  .04
* SDR-08-004
                                                        <0.04 145 4.44
-K-40 replicate not in agreement 11.0 ATTACHMENTS A. B. Sample Deviation Reports Cross-Check Reports I 23
                                                          ~A 1r.!.4 1 02 -1 Bg 102-1    ~
3.1111 -5.77 3.
64
                                                                                                    -5_77
                                                                                                .7 -1 20.1 64.7-1Zn.l o Thanium Thallium Van.-fum Vanadium Zin<:
Zill<:
raniu m-T~  ocaI NR NR NR NR
                                                          << 1.0'
                                                          < 1.0 16 1611 319 12.0 12.0' 113-2[}g 113-209 223-4 15 8 .4 -15.6 o
ranium-lJfwI* m-238 Ufwlillm-238                                NR        11 .9 11.9                                8_3-15.5 8.3-1    5.5 ranillm-235                                NR      (l.O75 Q.075                              0.0'53 - O.OQB 0.053-0.mlB o    Ormnc Oreamc Analyre                                Resul Result NR Ref Vaws:
VIIWf        Fblg Flag Notes        z-Ac    epta:nce Acceptance
:B..Iwgs:
:B.allge 25_6-195_7 25.0 -1 Q5.7 Units (ugl:g)
(Ul,l:g)
Unc Unc Vawe Flag VaWf o
de!til~H C defta~HC                                              11  0 .6 110.6 beta-8HC                                    NR      18.33                                1.83  -43.94
                                                                                              .83-43.B4 gamma-BHC (Undane) gamrna-SHC                                  NR      lB.OO                                1.80-40.
1.80'-46.56  56 4.4'-ODT 4.-I'-DDT                                    NR      10  1.7 101.7                                25.3 -178 .1 25.3-178.
NR                                            3.59 - 72.57 3.59-    7257 o
Diadrin Dieklrin                                              35.86 Heptachlor HeptachlCf"                                  NR        7.5 1                              0.75-115.83 0.75-     5.83 Nilphthalene NaphthalenE                                  NR        3524                              1010-6008 1010'-6038 Acenap      thene AoItnaphlhene                                NR        231 9 2319                                724 -3914 724-3914 NR o
Anthracene                                            2270 2270'                                664-3877 Benzo(a:l3f1wKene Benzo(a:tM1lhracene                          NR          707 7  7                              177  -1237 177-1237 Benzo(k )IluolillnfMne Benzo(k)IIuorarnh4!ne                        NR        3330 3330'                              1150    -55 11 1150'-5511 2-O\Ioronaphthaiene 2 -011oronapnthalene                        NR        27ge 2795                                815-4n4 81 5 -4n4 o Issued 4123:
4/23: _008                                  Pa;e 1 of4                                              PriD!ed PriJIred 4mI2OO3 4mI2OO&
o o
o                                                                    30


Attachment Sample Deviation I I I I I I I Attachment A I Sample Deviation Reports I I I
o o      R.;I!liolol:ical Aual;.,e Analyte                                R"~lIh RIMtlr R~r
I I I I I I I I 24 I I I I I I I I I I I I I I I I I I EXHIBIT SAMPLE DEVIATION SAMPLE LOCATION/DESCRIPTION MAPEP MaS-18 Co-GO failure INSTRUMENT (Check Gross Alpha/Beta D Liq. Scinto D Gamma Spec. r8:I Serial SAMPLE TYPE (Check One) REPORT NUMBER SDR-08-001 Detector #1 #2 #3 Soil r8:I Water/Liquid D PlanchetD Concrete Debris D Other D SAMPLE START DATEITIME I SAMPLE STOP DATEITIME 2/4/08 111 :05 I N/A ANALYTICAL PROBLEM MAPEP MaS-18 Soil sample results were in excess of the Co-GO reference value. The reported value was 14.3 Bq/kg and the reference value was 2.9 Bq/kg. As this was a sensitivity test for Co-GO, no acceptance range is given. CORRECTIVE ACTIONS AND/OR COMMENTS A review of the gamma spectroscopy analysis for this sample revealed that the Co-50 1332 peak was not present in the spectrum.
                                                        \\ *i!.lm~
Since the Gamma Vision library recognized the 1173 peak, it associated the region counts with Co-GO and reported an incorrect activity.
                                                          'a1ne      Flag :t\otel.
This is not the library that is normally used to analyze PBRF soil samples,
Flag. Note!>      Bias Bi3S Acceptance Ballg~
* but was used for MAPEP since the results are reported in Becquerels.
Rallll!:
The library was corrected to require both
[!I1J I~
* peaks to be present to identify Co-GO in a sample.
Uue Uuc (Rcr l:>J.l Uue
* Submitted By: (Print/Sign)
:l'alni: fl3~
R. Case Radiological Laboratory Manager (Print/Sign)
:l'allli:   E1311 o
R. Case NASA Project RSO (PrintlSign)
Americium-241                                  124          127.2     A                 -2.5    89.0 - 165.4                  7.7 Cesium-l34 Ce5ium-l34                                    NR              854                                598-1110 598  - 1110 Cesium-137                                    548            545    A                  0.6    382 - 709                  13.4      L Cobalt*57                                      426            421    A                  1.2     295-547 295  - 547                  82      L o
W. Stoner 25 DATE 8/13/08 DATE 8/13/08 DATE 8/13/08 I I I I I I I I I I I I I I I I I I EXHIBIT 2 SAMPLE DEVIATION REPORT SAMPLE LOCATION/DESCRIPTION REPORT NUMBER MAPEP MaS-18 Co-GO failure SDR-08-001 INSTRUMENT (Check One) Gross Alpha/Beta D Liq. Scinto D Gamma Spec. r8:I Serial # Detector #1 #2 #3 SAMPLE TYPE (Check One) Soil r8:I Water/Liquid D PlanchetD Concrete Debris D Other D SAMPLE START DATEITIME I SAMPLE STOP DATEITIME 2/4/08 111 :05 I N/A ANALYTICAL PROBLEM MAPEP MaS-18 Soil sample results were in excess of the Co-GO reference value. The reported value was 14.3 Bq/kg and the reference value was 2.9 Bq/kg. As this was a sensitivity test for Co-GO, no acceptance range is given. CORRECTIVE ACTIONS AND/OR COMMENTS A review of the gamma spectroscopy analysis for this sample revealed that the Co-50 1332 peak was not present in the spectrum.
Cobalt-60 Coball-60                                     14.3              2.9           (4 )                                           2.78 Iron*55                                        NR              390                                273*507 Manganese-54                                  NR              570                                399* 741 Nickel-63 Nickel*63                                      NR              640                                448-832 Plutonium-238                                  NR            728                                51.0-94.6 o Plutonium*2391240 Plutonium-2391240 Potassium-40 Strontium*90 Strontium* 90 Technetium-99 NR NR NR NR 90.1 571 493 273 63.1*117.1 400- 742 400-742 345-641 191-355 o Uranium-234i233 Uranium-2341233 Uranium-238 Zinc-65 NR NR NR 142 148 99-185 104-192 o  .\ J.\I'U'-1I7-\b\\      J{atliulul:iull, inuI!!ani, l\I'U'-1I7- \b\\ Ill : l{adiulul!ic:I[,  iour!!"nic    U)mlJill~tI ,,,,t~I' o>mlJill~t.I  "alcl'  ,1:lIlllanl
Since the Gamma Vision library recognized the 1173 peak, it associated the region counts with Co-GO and reported an incorrect activity.
                                                                                    ,(miliant o      11loru~ll1c luolumne Rd Ref                                    Acceptance Acceptauce Ulli,, : (1I1jl.
This is not the library that is normally used to analyze PBRF soil samples,
Unih Une Uue (l11)!.' LI Ulle Une Li o  An.,lyte Analyte Amertcium-241 Americium-241 Cesium-l34 Cesium* l34 Cesium*137 Ce5ium*137 R~lth Result NR NR NR
* but was used for MAPEP since the results are reported in Becquerels.
:l'~I!l~
The library was corrected to require both
                                                        ~-aht~
* peaks to be present to identify Co-GO in a sample.
1.23 Flail :t\ot~
* Submitted By: (Print/Sign)
RW NQt~
R. Case DATE 8/13/08 Radiological Laboratory Manager (Print/Sign)
(11)
R. Case DATE 8/13/08 NASA Project RSO (PrintlSign)
Bi:tS      Rall~
W. Stoner DATE 8/13/08 25 I I I I I I I I I I I I I I I I I I EXHIBIT SAMPLE DEVIA nON REPORT SAMPLE LOCATION/DESCRIPTION I REPORT NUMBER MAPEP RdF-18 Co-60 failure and Cs-137 warning INSTRUMENT (Check One) I SDR-08-002 Gross Alpha/Beta D Liq. Scinto D Gamma Spec. [8] Serial # Detector #1 #2 #3 . SAMPLE TYPE (Check One) SoUD Water/Liquid D PlanchetD Concrete Debris D Other [8] Air Filter SAMPLE START DA*rE/TIME SAMPLE STOP DATEITIME 2/4/08/14:27 N/A ANALYTICAL PROBLEM MAPEP RdF-18 Air filter Co-60 sample result was> 30% (48.9%) of the reference value and Cs-137 was
Rru.J~
>20% (28.9%) of the reference value. The reported value for Co-60 was 1.95 +/-0.33 8q/sample and the reference value was 1.318q/sample.
0.86*1.60 0.86*1     .60 rallll:;
The reported value for Cs-137 was 3.48 +/-0.5 8q1sample and the reference value was 2.70 8q/sample.
                                                                                                                          )'1I11l!:  Elaa flllil o Coball-57 Cobalt-57 Cobalt-60 Hydrogen-3 Iron-55 24 8.9 NR NR 22.8 8.40 472 36.5 A
CORRECTIVE ACTIONS ANDIOR COMMENTS The reported values are the numerical average for each nuclide of 5 trials. The standard deviation in the trial set is 0.6 8q for Co-60 and 0.7 8q for Cs-137. A replicate analysis was performed on these results. 80th the Co-60 and Cs-137 results were in agreement with the MAPEP reference values. The sample analYSis process for this geometry was observed by the Laboratory Manager and no discrepancies were found. The samples were analyzed for 1000 seconds which is typical for this sample type. However, a significantly longer count time will improve the uncertainty and should result in a smaller variance between sample trials. Subsequent MAPEP filter samples will be given a 43,200 second count time. Submitted By: (Print/Sign)
A 5.3 6.0 16.0-29.6 5.88*10.92 330-614 25.6-47.5 0.97 0.74 o
R. Case DATE 8/13/08 Radiological Laboratory Manager (Print/Sign)
Manganese-54                                  NR            12.1                                8.5-15.7 Nickel*63                                      NR            30.7                              21.5*39.9 Plutonium-238                                  NR            073                                0.51 --0.95 0.95 Plutonium-239J240                              NR          0.0141 Strontium-go Strontium-SO                                  NR            11 .40 11.40                              7.98 -14.82
R. Case DATE 8/13/08 NASA Project RSO (Print/Sign)
                                                                                                          -14 .82 o T echnetium-99 Technetlum-99 Uranium*2341233 lkanium*234J233 Uranium*238 Zinc-65 NR NR NR NR 11.2 3.63 3.74 16.3 7.8-14.6 2.54-4 2.54 2.62-4.86 2.62-4.88 11.4-21.2
W. Stoner DATE 8/13/08 26 I I I I I I I I I I I I I I I I I I EXHIBIT 2 SAMPLE DEVIA nON REPORT SAMPLE LOCATION/DESCRIPTION I REPORT NUMBER MAPEP RdF-18 Co-60 failure and Cs-137 warning I SDR-08-002 INSTRUMENT (Check One) Gross Alpha/Beta D Liq. Scinto D Gamma Spec. [8] Serial # Detector #1 #2 #3 . SAMPLE TYPE (Check One) SoUD Water/Liquid D PlanchetD Concrete Debris D Other [8] Air Filter SAMPLE START DA*rE/TIME SAMPLE STOP DATEITIME 2/4/08/14:27 N/A ANALYTICAL PROBLEM MAPEP RdF-18 Air filter Co-60 sample result was> 30% (48.9%) of the reference value and Cs-137 was
                                                                                                              .72
>20% (28.9%) of the reference value. The reported value for Co-60 was 1.95 +/-0.33 8q/sample and the reference value was 1.318q/sample.
                                                                                                          - 4.72 11.4 - 21.2 o
The reported value for Cs-137 was 3.48 +/-0.5 8q1sample and the reference value was 2.70 8q/sample.
o    \IAPEP-07-Rdnll : l{:lCtiolul!ical
CORRECTIVE ACTIONS ANDIOR COMMENTS The reported values are the numerical average for each nuclide of 5 trials. The standard deviation in the trial set is 0.6 8q for Co-60 and 0.7 8q for Cs-137. A replicate analysis was performed on these results. 80th the Co-60 and Cs-137 results were in agreement with the MAPEP reference values. The sample analYSis process for this geometry was observed by the Laboratory Manager and no discrepancies were found. The samples were analyzed for 1000 seconds which is typical for this sample type. However, a significantly longer count time will improve the uncertainty and should result in a smaller variance between sample trials. Subsequent MAPEP filter samples will be given a 43,200 second count time. Submitted By: (Print/Sign)
      \IAPEP-07-Rtln8 RaurololllcaJ Raurolo lesl It:uliolul:ical "ir air lilll'r Ref                                  Acceptance Acce)1t~lIce IBq sallt l""1 UlIIls 18'15:UIII'I.,)
R. Case DATE 8/13/08 Radiological Laboratory Manager (Print/Sign)
UUlts Uue Uue o    Annlyte Americium*241 Cesium* 134 Cesium-137 Re!,u Re;,t tllll NR NR 3.48
R. Case DATE 8/13/08 NASA Project RSO (Print/Sign)
                                                            \'llll.l~
W. Stoner DATE 8/13/08 26 I I I I I I I I I I I I I I I I I I I EXHIBIT 2 SAMPLE DEVIATION REPORT i SAMPLE LOCATION/DESCRIPTION REPORT NUMBER PB08-02340 K-40 not in agreement SDR-08-003
Vall.li:
..INSTRUMENT (Check Gross Alpha/Beta D Liq. Scinto D Gamma Spec. [ZJ Serial # Detector #3 &SAMPLE TYPE (Check Soil D Water/Liquid D PlanchetD Concrete Debris D Other [ZJ Concrete SAMPLE START DATEITIME
0.158 2.52 2.70 Flag Flag.
: SAMPLE STOP DATEITIME 8/21/08/10:48 N/A I ANALYTICAL PROBLEM PB08-02340 K-40 (12.6+/-3 pCi/g) replicate analysis not in agreement with PB08-02343 recount (6.5+/-2 pCi/g) on Detector #1. CORRECTIVE ACTIONS AND/OR COMMENTS Sample was recounted on Detectors
W
#1 & #2 (PB08-02500
                                                                                'ates ates      Bin.,
& PB08-02501).
BiA!'
The K-40 results (pCi/g) were in agreement on both counts with the original result and with each other. Detector Original Replicate 2 Sigma Resolution Ratio Agreement Original 1.26E+01 6.50E+OO 3.00E+OO 8.0 1.94 No Det#1 &#2 8.40E+OO 9.40E+OO 2.20E+00 8.0 0.89 Yes Oet#1 &#3 8.40E+00 1.26E+01 2.20E+OO 8.0 0.67 Yes Oet#1 & Oet#1 8.40E+00 6.50E+OO 2.20E+00 8.0 1.29 Yes Det#2 & Oet#1 1.2SE+01 9.40E+OO 3.00E+00 8.0 I 1.34 Yes The differences in the results are not statistically significant within the variability of the time of measurement uncertainty.
28.9
No further action is required.
                                                                                                        &1Ll!l~
DATE 9/9/08 Submitted By: (Print/Sign)
R.11l1!~
R. Case DATE 9/9/08: Radiological Laboratory Manager (Print/Sign)
0.111-0.205 1.76*3.28 1.89*3.51 1.89
R. Case DATE 9/9/08 NASA Project RSO (Print/Sign)
* 3.51
W. Stoner I I I I I I I I I I I I I I I I I I I i EXHIBIT 2 SAMPLE DEVIATION REPORT SAMPLE LOCATION/DESCRIPTION REPORT NUMBER PB08-02340 K-40 not in agreement SDR-08-003
::;alm: flag
.. --------INSTRUMENT (Check One) Gross Alpha/Beta D Liq. Scinto D Gamma Spec. [ZJ Serial # Detector #3 & #1 SAMPLE TYPE (Check One) Soil D Water/Liquid D PlanchetD Concrete Debris D Other [ZJ Concrete Core : SAMPLE START DATEITIME SAMPLE STOP DATEITIME 8/21/08/10:48 I N/A ANALYTICAL PROBLEM PB08-02340 K-40 (12.6+/-3 pCi/g) replicate analysis not in agreement with PB08-02343 recount (6.5+/-2 pCi/g) on Detector #1. CORRECTIVE ACTIONS AND/OR COMMENTS Sample was recounted on Detectors
:l-alm:
#1 & #2 (PB08-02500
0.50 flail o    Cobalt-57 CobaIt-60 Coball-60 Manganese.54 Manganese*54 Plutonium-238 3.76 1.95 NR NR NR 3.55 1.31 0.1053 A                  5.9 48.9 2.49 *4*4.62 0.92*1.70
& PB08-02501).
                                                                                                                .62 0.0737 - 0.1369 0.0799*0.1483 0.34 0.33 o
The K-40 results (pCi/g) were in agreement on both counts with the original result and with each other. Detector Original Replicate 2 Sigma Resolution Ratio Agreement Original 1.26E+01 6.50E+OO 3.00E+OO 8.0 1.94 No Det#1 &#2 8.40E+OO 9.40E+OO 2.20E+00 8.0 0.89 Yes Oet#1 &#3 8.40E+00 1.26E+01 2.20E+OO 8.0 0.67 Yes Oet#1 & Oet#1 8.40E+00 6.50E+OO 2.20E+00 8.0 1.29 Yes Det#2 & Oet#1 1.2SE+01 9.40E+OO 3.00E+00 8.0 I 1.34 Yes The differences in the results are not statistically significant within the variability of the time of measurement uncertainty.
Plutonium-239i240 Plutonium-239J240                              NR        0.1141 Strontium-go Strontium-SO                                  NR          1.548                              1.084-2.012 Uranium-234/233                                NR          0.218                              0.153*0.283 Uranium-238                                    NR          0.225                              0.158-0.293 Zinc-65                                        NR            2.04                                1.43-2.65 o
No further action is required.
o                                                                                          31
Submitted By: (Print/Sign)
R. Case DATE 9/9/08 : Radiological Laboratory Manager (Print/Sign)
R. Case DATE 9/9/08 NASA Project RSO (Print/Sign)
W. Stoner DATE 9/9/08 27 I I I I I I I i I I I I I I I I I I I EXHIBIT 2 SAMPLE DEVIATION REPORT : SAMPLE LOCATION/DESCRIPTION REPORT NUMBER PBOS"()2960 K-40 not in agreement INSTRUMENT (Check One) Gross Alpha/Beta 0 Liq. Scinto Gamma Spec. [gI Serial # SDR-OS-004 Detector #2 & #1 SAMPLE TYPE (Check One) Soil [gI WaterlLiquid Planchet 0 Concrete Debris 0 Other 0 Concrete Core SAMPLE START DATErrlME SAMPLE STOP DATEfTlME 12/11/0S/12:54 NIA ANALYTICAL PROBLEM PB08"()2960 K-40 (1.7+/-0.72 pCi/g) replicate analysis count on Detector #2 not in agreement with PBOS"()2961 recount (10.0+/-2 pCilg) on Detector #1. CORRECTIVE ACTIONS ANDIOR COMMENTS The sample was re-analyzed on Detectors 1,2, and 3 with the following K-40 results: ! Detector 1 Detector 2 Detector 3 10.1+/-1.7 10.1+/-1.9 9.99+/-1.8 I Agreement was obtained between all three detectors.
No further action is required.
DATE: 117/09 Submitted By: (Print/Sign)
R. Case DATE: 117/09 Radiological Laboratory Manager (Print/Sign)
R. Case DATE: 117109 NASA Project RSO (Print/Sign)
W. Stoner I I I I I I I I I I I I I I I I I I i EXHIBIT 2 SAMPLE DEVIATION REPORT SAMPLE LOCATION/DESCRIPTION
: REPORT NUMBER PBOS"()2960 K-40 not in agreement SDR-OS-004 INSTRUMENT (Check One) Gross Alpha/Beta 0 Liq. Scinto Gamma Spec. [gI Serial # Detector #2 & #1 SAMPLE TYPE (Check One) Soil [gI WaterlLiquid Planchet 0 Concrete Debris 0 Other 0 Concrete Core SAMPLE START DATErrlME SAMPLE STOP DATEfTlME 12/11/0S/12:54 NIA ANALYTICAL PROBLEM PB08"()2960 K-40 (1.7+/-0.72 pCi/g) replicate analysis count on Detector #2 not in agreement with PBOS"()2961 recount (10.0+/-2 pCilg) on Detector #1. CORRECTIVE ACTIONS ANDIOR COMMENTS The sample was re-analyzed on Detectors 1,2, and 3 with the following K-40 results: ! Detector 1 Detector 2 Detector 3 10.1+/-1.7 10.1+/-1.9 9.99+/-1.8 I Agreement was obtained between all three detectors.
No further action is required.
Submitted By: (Print/Sign)
R. Case DATE: 117/09 Radiological Laboratory Manager (Print/Sign)
R. Case DATE: 117/09 NASA Project RSO (Print/Sign)
W. Stoner DATE: 117109 28 Attachment Cross-Check I I I I I I I Attachment B I Cross-Check Reports I I I I I I I I I I I 29 


o o o o o o o o o o PEP Mixed Analyte Performance Evaluat on Laboroto ry Rssult.! For MAPEP Series 1 8 NASA P um Brook Reactor Facili t y La b (PBRF01) 6100 Co hm bus Ave Sandusl:y, OH 44870 inorganic and semi-,*oi:ltile ol'ganic s combined 5 0il s Tandard Inon!4Illc units: (mgikg) Ref Ac:aptance Unc L'nc Analyre Resul Rag Nores Bill li:abJe BaDge Yalm: Eag AnIimoo y Arse r5c B arium Be ryl liu m Cadm iu m Ch ro mum CobII Coppe r l ead Merou.ry ick el Selenium S r Thaniu m V anadiu m Zi ll<: lJfwI* m-238 ran ill m-235 Oreamc Analyre beta-8 HC gamma-BHC (Unda ne) 4.4'-ODT Di adrin Heptach l Cf" Na ph thale nE Acena p thene Anth racene Benzo(a:tM1 lhracene Benzo (k)IIuo rarnh4!ne 2-011o rona pnt halene Issued 4/23: _008 NR 23.a 1 6 5 -30.6 NR 20 2 14.1-2 0. 3 NR 244 1 71 -317 NR 1 3.B 9]-lHI N R 9.49' 6.64-12 , 34 N R 7 0.7 49.5-91 .9 NR 4 1.5 2{j 1-54.0 NR 87.0 eo.9-1l 3.1 N R 79 5 5 -10 3 N R <0.04 N R 145 NR 4.44 3. 11 -5.77 N R 1r.!.4 64.7-1 20.1 N R <1.0 N R 16 1 113-2[}g NR 319 223-4 1 5 N R 12.0 8.4 -15.6 N R 11 .9 8.3-1 5.5 N R (l.O7 5 0.0'53 -O.O QB Units (Ul,l:g) Ref Acceptance Unc Unc Result VIIWf Fblg Notes z-:B.allge VaWf Flag N R 11 0.6 25.0 -1 Q5.7 N R 1 8.33 1.8 3 -43.94 N R lB.OO 1.80-4 0. 56 N R 1 0 1.7 2 5.3 -17 8 .1 NR 3 5.8 6 3.5 9 -7 257 N R 7.5 1 0.75-1 5.83 N R 3524 1010-6008 N R 231 9 72 4 -3914 NR 227 0 664-3 8 77 NR 7 0 7 177-1237 NR 33 30 1 15 0 -5 5 1 1 N R 2795 81 5 -4n4 Pa;e 1 of4 PriD!ed 4mI2OO3 o o o o o o o o o o o o o o o o o o o PEP Mixed Analy1e Performa n ce Evaluat on ProtJraIT1 LaboroJory Rssult.! For MAPEP Series 1 8 NASA P"um Brook Reactor Facili i y La b (PBRF01) 6100 Columbus Ave Sandusl]', OH 44870
Dq.or1l1UlOlI ot DelAlllm01l      of Elle'!lY PEP Euef!1Y RE. lL - 19<<
&idio\ogic:ll, inorganic
Mixed Analyle 19<~ F"'"101l1 Fremonl A,,,-
;llld Semi-yol:ltile ol'ganic s combined s oil standard Inom;mic Units: (mg kg) Ref Aa:eptmce Unc line Analyte Resul Vahre Flag Nores Bils Range Ell" c Antimony NR 6.5-30'_6 Arser5c NR 202 14_1-26.3 Barium NR 244 171-317 Be rylium NR 1 3_B 9] -17.9 Cadm iu m NR Q.4G 6.64-12.34 Chro mum N R 70_7 Cobalt NR 4U: zg 1-54.0 Copper NR B7_0 eo_Q-1 3_1 lead NR 79 55-103 Merot.y NR < .04 ick el NR 145 102-1 Bg Selenium NR 4.44 3.1 1-5_77 S illier NR 64.7-1Zn.l Thalliu m NR <<1.0' Van.-f u m NR 161 113-2 09 Zin<: NR 319 223-4 1 5 ran iu m-ocaI NR 12.0' 8.4-15.6 Ufwlill m-238 NR 11.9 8_3-15.5 ranill m-235 NR Q.075 0.053-0.mlB Ormnc Units (ugl:g) Ref Ac epta:nce Unc Unc Analyre Resul Vaws: Flag Notes z-:B..Iwgs:
A\ e.
Vawe Flag N R 110.6 25_6-195_7 beta-8HC NR 18.33 .83-43.B4 gamrna-SHC (Undane) NR lB.OO 1.80'-46.56 4.-I'-DDT NR 101.7 25.3-178.
Analyte Performance Evaluation Program
Di eklrin NR 35.86 3.59-72.57 Heptach lor NR 7.5 0.75-15.83 Nil phthalene NR 3524 1010'-6038 AoItnaphlhene NR 2319 724-3914 Anthracene NR 2270' 664-3877 Benzo(a:l3f1wKene NR 7 7 177-1237 Benzo (k )Iluo lillnfMne NR 3330' 1150'-5511 2-O\Ioronaphthaiene NR 27ge 815-4n4 Issued 4123: _008 Pa;e 1 of4 PriJIred 4mI2OO& 30 o Acceptance Uuc Uue Analyte RIMtlr Flag. Note!> Bias\ 'a1ne
                                                                ~[S 11 J9 -. lu.wu
:l'alni:
                                                                ~!S-llJ'I      hJ.lltu fFall aU..... ID ~.q S3~ I; Ij LabomlOlT LabomrolT RI'.     R<,.w
Americium-241 124 127.2 A -2.5 89.0 -165.4 7.7 o Ce5ium-l34 NR 854 598-1110 Cesium-137 548 545 A 0.6 382 -709 13.4 L Cobalt*57 426 421 A 1.2 295-547 82 L Cobalt-60 14.3 2.9 (4) 2.78 o Iron*55 NR 390 273*507 Manganese-54 NR 570 399* 741 Nick e l*63 NR 640 448-832 Plutonium-238 NR 728 51.0-94.6 o Plutoni u m*2391240 NR 90.1 63.1*117.1 Potassium-40 NR 571 400-742 Strontium*90 NR 493 345-641 Technetium-99 NR 273 191-355 Uranium-234 i 233 NR 142 99-185 o Uranium-238 NR 148 104-192 Zinc-65 NR o .\J.\I'U'-1I7-\b\\ Ill: J{atliulul:iull, iour!!"nic ,1:lIlllanl o
                          \JITr5 l r5 Fo/'  '\L~PEP Serif's For .\L-IPEP      Series 19 (PBRFOl) NASA PhWl Brook Reactor Fncility Lab (PBRF01) 6100 CO      hWll>us Ave COhWll>us SaudniJ..-y.
Unih: (1I1jl. LI Ref Acceptauce Uue Une Analyte Result Flail Bi:tS rallll:; Elaa o Americium-241 NR 1.23 0.86*1.60 Cesium-l34 NR Ce5ium*137 NR RW (11) Cobalt-57 24 22.8 A 5.3 16.0-29.6 0.97 o Cobalt-60 8.9 8.40 A 6.0 5.88*10.92 0.74 Hydrogen-3 NR 472 330-614 Iron-55 NR 36.5 25.6-47.5 Manganese-54 NR 12.1 8.5-15.7 o Nicke l*63 NR 30.7 21.5*39.9 Plutonium-238 NR 073 0.51 -0.95 Pluton ium-239 J 240 NR 0.0141 Strontium-go NR 11 .40 7.98 -14.82 o T echn eti um-99 NR 11.2 7.8-14.6 Uranium*234 1 233 NR 3.63 2.54-4.72 Uranium*238 NR 3.74 2.62-4.86 Zinc-65 NR 16.3 11.4-21.2 o o \IAPEP-07-Rdnll
Salldn>l..-y. OH --1--1870 44SiO
: It:uliolul:ical air lilll'r Raurolo lesl UlIIls IBq sallt l""1 Ref Uue Uue Re;,t tll Flag. ates BiA!'Annlyte
:'IL\PEI'*
::;alm: flail o Americium*241 NR 0.158 0.111-0.205 Cesium* 134 NR 2.52 1.76*3.28 Cesium-137 3.48 2.70 W 28.9 1.89*3.51 0.50 Cobalt-57 3.76 3.55 A 5.9 2.4 9 *4.62 0.34 o Coba It-60 1.95 1.31 48.9 0.92*1.70 0.33 Ma nganese*54 NR Plutonium-238 NR 0.1053 0.0737 -0.1369 Plutonium-239i240 NR 0.1141 0.0799*0.1483 o Strontium-go NR 1.548 1.084-2.012 Uran i um-234/233 NR 0.218 0.153*0.283 Uranium-238 NR 0.225 0.158-0.293 Zinc-65 NR 2.04 1.43-2.65 o o 31 o o R.;I!liolol:ical
:\1.\PEI'*HH  IIH-:\laSJ.,:      [{udiuloeic~l, inoreanic
[!I1J (Rcr l:>J.l Acceptance Uue Uue Aual;.,e Flag :t\otel. Bi3S Rallll!: :l'allli: E1311 o Americium-241 124 127.2 A -2.5 89.0 -165.4 7.7 Cesium-l34 NR 854 598-1110 Cesium-137 548 545 A 0.6 382 -709 13.4 L Cobalt*57 426 421 A 1.2 295-547 82 L o Coball-60 14.3 2.9 (4) 2.78 Iron*55 NR 390 273*507 Manganese-54 NR 570 399* 741 Nick e l-63 NR 640 448-832 Plutonium-238 NR 728 51.0-94.6 o Plutoni u m-2391240 NR 90.1 63.1*117.1 Potassium-40 NR 571 400-742 Strontium*90 NR 493 345-641 Technetium-99 NR 273 191-355 o Uranium-2341233 NR 142 99-185 Uranium-238 NR 148 104-192 Zinc-65 NR o .\l\I'U'-1I 7-\b\\ Ill: l{adiulul!ic:I[, inuI!!ani, "alcl' ,(miliant o luolumne Ulli,,: (l11)!.'Li Rd Acceptance Une Ulle o An.,lyte Flail B i:tS
                        \laSI'1 : Rudillioeicul,       jno~l:anic and "mi*              \ulalile organic, "mi-\IlI.llile        Ilr!:"oi"  comlJin~11       ,,,il ,landanl
)'1I11l!:
                                                                                                                                      ,,,;1   ,I:mdanl IlllHl!amc IuoTl!awc                                                                                                                                    !;llIb'    (Ulit lau 1:1I11~ : {UIll. kV.1 R?dlOlol!lcal                                                                                                                                L'IIII~ (B, kgl Ref                                                  AcceptaJlce Acceptauce                      Vueue      Uue
flllil Amertcium-241 NR 1.23 0.86*1.60 Cesi u m*l34 NR Cesium*137 NR RW (11) o Coball-57 24 22.8 A 5.3 16.0-29.6 0.97 Cobalt-60 8.9 8.40 A 6.0 5.88*10.92 0.74 Hydrogen-3 NR 472 330-614 Iron-55 NR 36.5 25.6-47.5 o Manganese-54 NR 12.1 8.5-15.7 Nicke l*63 NR 30.7 21.5*39.9 Plutonium-238 NR 073 0.51 -0.95 Pluton ium-239 J 240 NR 0.0141 Strontium-SO NR 11.40 7.98 -14.82 o Techne tl um-99 NR 11.2 7.8-14.6 lkanium*234J233 NR 3.63 2.54-4.72 Uranium*238 NR 3.74 2.62-4.88 Zinc-65 NR 16.3 11.4 -21.2 o o \IAPEP-07-Rtln8: l{: lCtiolul!ical "ir lilll'r RaurololllcaJ UUlts 18'15:UIII'I.,)
  *Anal)-1!!
Ref Acceptance Uue Uue o Annlyte Re!,u ll Vall.li: Flag 'ates Bin.,
    ..Iuutlyte                                        Resu.
:l-alm: flag Americium*241 NR 0.158 0.111-0.205 Cesium* 134 NR 2.52 1.76*3.28 Cesium-137 3.48 2.70 W 28.9 1.89*3.51 0.50 o Cobalt-57 3.76 3.55 A 5.9 2.49*4.62 0.34 Coba ll-60 1.95 1.31 48.9 0.92*1.70 0.33 M a nganese.54 NR Plutonium-238 NR 0.1053 0.0737 -0.1369 o Pluton i um-239J240 NR 0.1141 0.0799*0.1483 Strontium-SO NR 1.548 1.084-2.012 Ura n i um-234/233 NR 0.218 0.153*0.283 Uranium-238 NR 0.225 0.158-0.293 Zinc-65 NR 2.04 1.43-2.65 o o 31 PEP Mixed Analyte Performance Eva l uation Program Dq.or1l1UlOlI of Euef!1Y RE. l -
Resulth      ,,>:'alll!:    Flag ~(\tc flag      Notess        Bins BIllS IJ~
Fremonl A\ e. 11 J 9 . lu.wu f aU .. ID I; LabomlOlT R<,.\JITr5 For Serif's 19 (PBRFOl) NASA PhWl Brook Reactor Fncility Lab 6100 COhWll>us Ave Salldn>l..-y.
Iljle                \'    IleJ.la8..
OH 44SiO :\1.\PEI'*HH \laSI'1: Rudillioeicul ,
V,~ hle...&#xa3;lag..
and "mi-\IlI.llile
Americium-241                                            72.0            69.1      A                      4.2          48.4-89.8                        1.35      L Antimony-125 Anlimony-125                                              NR             22.8 22 .8                                            16.0-29.6 Cesium-l34                                                NR              581                                            407 -755 Cesium-137                                                3.67              2.8     A                                                                      0.54 Cobalt-57                                                  NR               333                                              233-433 Cobalt-60                                                148.0              145      A                      2.1 2.1           102-189                        242 2.42      L Iron*55 Iron-55                                                    NR               676                                            473-879 Manganese-54                                              NR               415                                              291  540 291-540 Nickel-63                                                  NR               760                                              532*
: organic,
532- 988 Plutonium-238                                              NR Plulonium-2391240 Plutonium-2391240                                          NR             55.6                                            38.9* 72.3 38.9-72.3 Polassium-40 Potassium-40                                              NR               570                                              399-741 Strontium-90                                              NR Technetium-99                                              NR              335                                              235-436 Uranium-2341 Uranium-234 f233    233                                    NR               292                                              204-380 Uranium-238                                                NR              303                                              212-394 Zinc-65                                                    NR                        RW        (1 1i)
,,,il ,I:mdanl IlllHl!amc {UIll. kV.1 R?dlOlol!lcal (B, kgl Ref AcceptaJlce Vue Uue *..Iuutlyte Resu.h ,,>:'alll!:
(11 Rm/i";I'gu',)/ R4",.,?II(/' ['Ilfo" R(/d;""'glC'll/IIt?[i-"*i?llrt*  [\111,,* A  Ugll.l I J.
flag N o te s BIll S Iljle V, hle...&#xa3;lag..
AI/glill    I, :f/O~
Americium-241 72.0 69.1 A 4.2 48.4-89.8 1.3 5 L Antimony-125 NR 22.8 16.0-29.6 Cesium-l34 NR 581 407 -755 Cesium-137 3.67 2.8 A 0.54 Cob al t-57 NR 333 233-433 Cobalt-60 148.0 145 A 2.1 102-189 242 L Iron*55 NR 676 473-879 Manganese-54 NR 415 291 540 Nicke l-63 NR 760 532* 9 88 Plutonium-238 NR Plulon i um-2391240 NR 55.6 38.9* 72.3 Polassium-40 NR 570 399-741 Strontium-90 NR Technetium-99 N R 335 235-436 Uranium-234 1 233 NR 292 204-380 Uranium-238 NR 303 212-394 Zinc-65 NR RW (1 1 ) Rm/i";I'gu',)/
:f}() ~
R4",.,?II(/' [\111,,* A Ugll.l I I ,
:\I.\I'EI'-1l8*
:\I.\I'I , I'-UH -\I:J\\ ''1: l{adlUlo g l<:II , lRorg: mlC cl>nt!Jlm'd luOHlatJ1C l !Ilil s' (H.!!. I.) R,,,hnlu'l.Icnl UUli.;;. rB'I'l_l Ref Uuc line AIm lyre Resu lt :-"ah!5: Flo!! ores Bias Americium-241 NR Cesium-l34 NR 19.5 13.7 -25.4 Cesium-137 24.1 23.6 A 2.1 16.5 -30.7 0.46 L Cobal.I-57 NR RW (11 ) 1 1.2 11 .6 A -3.4 8.1-15.1 0.23 L Hydrogen-3 NR 341 239-443 Iron-55 NR 46.2 32.3-60.1 Manganese-54 NR 13.7 9.6-17.8 Nicke l-63 NR Plulonium-238 NR 0.5 Q.4 -0.7 Plu1onium-2391240 NR S tr on tium-90 NR 645 4.5 2-8.39 T echnelium-99 NR 3.76 2.63-4.89 Uranium-234 1 233 NR 3.44 2.41-4.47 Uranium-238 NR 3.55 2.49-4.62 Zinc-65 NR 17.1 12.0-22.2 /(JI./W/I)gll "I R.*{t,,,,"1<
:\I.\I'I,                    J., : IbdiulogK:JI,
I' Of//(' .l lIgml I.
:'II:.I\\ ''1:
32 o o o o o o o o o o o o PEP M i xed Analyle Performance Evaluatio n Program DelAlllm01l ot Elle'!lY RE. L -19<< F"'"101l1 A,,,-hJ.lltu Fall ... ID I j LabomrolT R I'.w l r5 Fo/' .\L-IPEP S e ri e s 19 (PBRF01) NASA PhWl Brook Reactor Fncility Lab 6100 C O hWll>us A v e SaudniJ..-y.
I'-UH -\I:J\\                             lRorg:mlC wmlJim'd l{adlUlogl<:II, IRore:tnlC          cl>nt!Jlm'd        ""I~r 'I~ndanl
OH --1--1870
                                                                                                  ''''I~r illol aatne luOHlatJ1C                                                                                                                                    llIlIltS:  (H.!!. 1.)
:'IL\PEI'*IIH-:\laSJ.,:
                                                                                                                                                          !Ilils' (Ill!!. I.)
inoreanic and "mi*\ulalile Ilr!:"oi"
Radwlo'lICnl R,,,hnlu'l.Icnl                                                                                                                                L'uJls.
,,,;1 ,landanl IuoTl!awc
UUli.;;. rB'I'l_l (Bq    1_1 R<'f Ref                                                Acc~ptnllct' Acccpronce                      Uue Uuc        line AIm lyre
!;llIb' (Ulit lau Ref Acceptauce ue Uue Anal)-1!!
      .-\JJnlyTe                                        Result Resu lt      :-"ah!5:
Result Flag Bin s \' I le J.la8.. Americium-241 72.0 69.1 A 4.2 48.4-89.8 1.3 5 L Anlimony-125 NR 22.8 16.0-29.6 Cesium-l34 NR 581 407 -755 Cesium-137 3.67 2.8 A 0.54 Cob a l t-57 NR 333 233-433 Cobalt-60 148.0 145 A 2.1 102-189 2.42 L Iron-55 NR 676 473-879 Manganese-54 NR 415 291-540 Nicke l-63 NR 760 532-9 88 P l utonium-238 NR Pluton i um-239 1 240 NR 55.6 38.9-72.3 Potassium-40 NR 570 399-741 Strontium-90 NR Technet i um-99 N R 335 235-436 Uranium-234 f 233 NR 292 204-380 Uranium-238 NR 303 212-394 Zinc-65 NR RW (11 i R(/d;""'glC'll/IIt?[i-"*i?llrt*
:l'al!!!;        Flo!! NOI!!s ores      Bia, Bias              B.all~
['Ilfo" AI/glill J. :f}() :\I.\I'EI'-1l8*:'II:.I\\
RaD~                                  Ela~
J.,: Ibdiulo g K:JI , IRore: tnlC wmlJim'd illol aatne lIlIlt S: (Ill!!. 1.) Radwlo'lICnl L'uJls. (Bq 1_1 R<'f Acc cp ronc e Uue line .-\JJnlyTe Result :l'a l!!!; Flo!! NOI!!s Bia,
:'-.-ollJ~ Elall
:l:'ollll!
:l:'ollll!
Elall Americium-241 NR Cesium-l34 NR 19.5 13.7 -25.4 CHi u m-137 24.1 23.6 A 2.1 16.5 -30.7 0.46 L Cobalt-57 NR RW (11 ) Col).lt-60 1 1.2 11.6 A -3.4 8.1-15.1 0.23 L Hydrogen-3 NR 341 239-443 Iron*55 NR 46.2 32.3-60.1 Manganese-54 NR 13.7 9.6-17.8 Nicke l-63 NR Plut.onium-238 NR 0.5 0.4 -0.7 Plutonium-239
Americium-241                                             NR Cesium-l34                                               NR               19.5                                           13.7 - 25.4 Cesium-137 CHium-137                                              24.1               23.6       A                     2.1           16.5 - 30.7                     0.46       L Cobal.I-57 Cobalt-57                                                 NR                       RW         (11 )
/240 NR S tr on t ium-90 NR 645 4.5 2-8.39 T echnetium-99 NR 3.76 2.63-4.89 Uranium-234 f 233 NR 3.44 2.41-4.47 Uranium-238 NR 3.55 2.49-4.62 Zinc-65 NR 17.1 12.0-22.2 RlidlO/iJgli
    ~t-60 Col).lt-60                                               11.2               11 .6 A                         -3.4             8.1-15.1 8.1-15.1                       0.23       L Hydrogen-3                                               NR               341                                             239-443 o
.,1 R .. (t'I'I*"(,('
Iron-55 Iron*55                                                   NR               46.2                                           32.3- 60.1 Manganese-54                                             NR               13.7                                             9.6-17.8 Nickel-63                                                 NR Plulonium-238 Plut.onium-238                                           NR                 0.5                                             Q.4 - 0.7 0.4 Plu1onium-2391240 Plutonium-239/240                                         NR o    Strontium-90 Technelium-99 echnetium-99 Uranium-2341 Uranium-234f233 Uranium-238 233 NR NR NR NR 645 3.76 3.44 3.55 4.52- 8.39 2.63-4.89 2.41-4.47 2.49-4.62 o    Zinc-65                                                   NR               17.1
lJ,,/('
                                                                                                                        .,1
I.
                                                                                                          /(JI./W/I)gll "I R RlidlO/iJgli 12.0- 22.222 .2
32 
                                                                                                                              ..(t'I'I*"(,('I' Of//('
R.*{t,,,,"1<              .~ lIgll.'l I. ~(I()~
lJ,,/(' .llIgml          ~(J(J.~
o o
o                                                                                                          32
 
I~----------------------------~
        ;  Eckert&Ziegler I            Analytics 1380 Suboird InduslNIIIM:I.
Atlanta. GeoIgia 30318' U.s.A.
I            Tel Fax 404>352-8677 404' 35:1-2137 404'35:1-2137 I                                                  RESULTS OF ENVIRONMENTAL I                                                      CROSS CHECK PROGRAM I                                                                        NASA I                                                      Plum Brook Reactor Facility I                                                            Fourth Quarter 2007 (Ref. Date 12/06/2007)
I                                                              {f() ~                l-iJ..at Daniel M. Mon omery, QA Manager I
I I
SAMPLE                    ANALYSIS I                                                       NASAPBRF VALUE UNCERTAINTY (I Sigma)
ANALYTICS VALVE UNCERTAINTY (I Sigma)
RATIO NASAPBRF:
ANALYTICS I 1554,.792 H-3 H*3                8.85Efil3 pCiIL      1.63Efil3        9.02Efil3 prilL      1.51Efil2          0.98 Water
                                                                                                ,.,*****                            **********,.,t*
I I      Analysis performed 1/9/2008 I
I I                                                                          33


Eckert&Ziegler Analytics 1380 Suboird InduslNIIIM:I.
I I   *-    Eckert & Ziegler Analyll(s 1110 ~_a      lnCII.,t*.- _
Atlanta. GeoIgia 30318' U.s.A. Tel Fax 404'35:1-RESULTS OF CROSS CHECK Plum Brook Reactor Fourth Quarter (Ref. Date
I         ~~
{f() l-iJ..at Daniel M. Mon omery, QA Manager SAMPLE ANALYSIS NASAPBRF UNCERTAINTY ANALYTICS UNCERTAINTY RATIO VALUE (I Sigma) VALVE (I Sigma) NASAPBRF:
r"
ANALYTICS
          ~..
******** , ** ,",." ******".,',.".,',*****,.,*** , **** ,,**,."."" ***,."""""",*** * ******** *******.*,************* ,. 1554,.792 H*3 8.85Efil3 pCiIL 1.63Efil3 9.02Efil3 prilL 1.51Efil2 0.98 Water , ****** "."." ** , ******** *.**,*.........* **** ",.,***** " **** , ***********
(J<<Io1Jloi JOll.* U ~ "
,.,***** , *** , ************** " *************Analysis performed 1/9/2008 I I I I I I I I I
              ~. }~]*""n
I I I I I I I I I ; Eckert&Ziegler Analytics 1380 Suboird InduslNIIIM:I.
              ~'lSl'l')1 I                                              RESULTS OF ENVIRONMENTAt I                                                CROSS CHECK PROGRAM I                                                                  NASA I                                                Plum Brook Reactor Facility I                                                        Second Quarter 2008 (Ref. Date 06-19-2008)
Atlanta. GeoIgia 30318' U.s.A. Tel 404>352-8677 Fax 404' 35:1-2137 SAMPLE ANALYSIS RESULTS OF ENVIRONMENTAL CROSS CHECK PROGRAM NASA Plum Brook Reactor Facility Fourth Quarter 2007 (Ref. Date 12/06/2007)
I I
{f() l-iJ..at Daniel M. Mon omery, QA Manager NASAPBRF VALUE UNCERTAINTY (I Sigma) ANALYTICS VALVE UNCERTAINTY (I Sigma) RATIO NASAPBRF:
I I        SAMPLE                     A."\ALYSIS     NASAPBR..
ANALYTICS
NASAPBR..
******** , ** ,",." ****** ".,',.".,', ***** ,., *** , **** ,, ** ,."."" *** ,."""""", *** * ******** **** ** *.*,* **** ****** ** ,. 1554,.792 H-3 Water H*3 8.85Efil3 pCiIL 1.63Efil3 9.02Efil3 prilL 1.51Efil2 0.98 , ****** "."." ** , ******** *.**,* .........
VALUE UNCERTAINTY (2 Sigma)
* **** ",., ***** " **** , ***********
ANALYTlCS VALUE llNCERTAINTY (1 Siama)
,., ***** , *** , ************** " ** * **********
RATIO NASA POlf:
,.,t* Analysis performed 1/9/2008 33 I I I I I I I I I I I I I I I I I I I *-Eckert & Ziegler Analyll(s 1110  lnCII.,t * .-(J<<Io1Jloi JOll.* U r" RESULTS OF ENVIRONMENT At CROSS CHECK PROGRAM NASA Plum Brook Reactor Facility Second Quarter 2008 (Ref. Date 06-19-2008)
ANALYTlCS I    E6056-192                         8*3       t J8E+04 pCiIL     t.78E~3        1.30[+04 pCiIL       2.17E~2            1.06 8-3 I    Waler
SAMPLE A."\ALYSIS NASAPBR.. UNCERTAINTY ANALYTlCS llNCERTAINTY RATIO VALUE (2 Sigma) VALUE (1 Siama) NASA POlf: ANALYTlCS E6056-192 8*3 t J8E+04 pCiIL 1.30[+04 pCiIL 1.06 8-3 Waler*********.,****w ****************
      ******** *., *** *w **************** *********.**************.*** **
* ******* *.**************.***
I                                                                                                                                      I I Analysis performed 7/1812008 I
*******.***.***.*.*.***.***  
I I                                                                 34}}
******* ************************
* Analysis performed 7/1812008 34 I I I I I I I I I I I I I I I I I I I I -* Eckert & Ziegler Analyll(s 1110 lnCII.,t * .-_ (J<<Io1Jloi JOll.* U " r" SAMPLE A."\ALYSIS E6056-192 8-3 Waler 8*3 RESULTS OF ENVIRONMENT At CROSS CHECK PROGRAM NASA Plum Brook Reactor Facility Second Quarter 2008 (Ref. Date 06-19-2008)
NASAPBR .. VALUE t J8E+04 pCiIL UNCERTAINTY (2 Sigma)
ANALYTlCS VALUE 1.30[+04 pCiIL llNCERTAINTY (1 Siama)
RATIO NASA POlf: ANALYTlCS 1.06 ******** *., *** *w ****************
* ******* *.**************.***
** *****.***.***.*.*.***.***
***** ** ************************
* Analysis performed 7/1812008 34 I}}

Latest revision as of 21:59, 11 March 2020

Pbrf Laboratory Quality Assurance Report 2008
ML102030054
Person / Time
Site: Plum Brook
Issue date: 03/30/2009
From: Case R, Stoner W
US National Aeronautics & Space Admin (NASA)
To:
NRC/FSME
Shared Package
ML102030017 List:
References
Download: ML102030054 (36)


Text

~~------------------------------~

~ ,P PBRF BRF LABORATORY QUALITY

~ ASSU,RANCE REPORT

~J January to December 2008

[~1

~

[~)

~

[I

~

I~

I ------~

I FIFTH EDITION III March 30, 2009 RODERICK C. CASE PBRF LABORATORY MANAGER I

WILLIAM STONER I NASA PROJECT RADIATION SAFETY OFFICER I NASA Plum Brook Reactor Facility 6100 Columbus Avenue Sandusky, Ohio 44870 I

II ~~~~-

_~~-~

It .- .

~ -'" .! !--"! !I ! !~

~~-----------

! ! ! ! ~.- ~--------------------~ ...

TABLE OF CONTENTS SECTION PAGE I 1.0

SUMMARY

.......................................................................................................................... 1 I

2.0 INTRODUCTION

................................................................................................................2 I 3.0 DiSCUSSiON ......................................................................................................................2 I 4.0 .. .............................................................................................. 3 LABORATORY PROGRAM ................................................................................................

I 5.0 INTER-LABORATORY & INTRA-LABORATORY COMPARISON ANALYSIS .................. 4 TABLE 1 -INTRA-LABORATORY COMPARISON (REPLICATE) RESULTS ................................................. 5 I TABLE 2 -INTER-LABORATORY COMPARISON (REPLICATE) RESULTS .............................................. 17 TABLE 3 - SAMPLE RESOLUTION AND RATIO AGREEMENT CRITERIA. ............................................... 21 I

6.0 QUALITY CONTROL CHECKS ........................................................................................21 I

7.0 BACKGROUND

DETERMINATIONS ...............................................................................22 I 8.0 BLANK SAMPLE ANALySiS ............................................................................................22 I 9.0 CROSS-CHECK PROGRAM ............................................................................................23 I 10.0 LABORATORY/SAMPLE DEVIATION REPORTS ........................................................... 23 I 11.0 ATIACHMENTS ...............................................................................................................23 I

I I

I

1.0

SUMMARY

I 1 1.1

.1 Gamma Spectroscopy Systems I 1.1.1 During the report period of January 1, 2008 and December 31, 2008, PBRF Laboratory personnel performed 4190 gamma spectroscopy sample analyses of 3006 samples. PBRF performed a total of 1547 quality I assurance analyses. They include:

  • 29 blank analyses on 29 samples I
  • 615 Quality Control (QC) checks I
  • 615 Background checks 15 Cross-check Program sample analyses on 3 samples I
  • 24 inter-laboratory comparison (replicate) analyses on 12 samples
  • 249 intra-laboratory comparison (replicate) analyses on 132 samples I 1.1.2 Of all the QA samples that were analyzed on the PBRF Gamma Spectroscopy Systems, there were 4 discrepancies that required I documentation of a Sample Deviation Report (SDR).

1.2 Liquid Scintillation Analyzer I 1.2.1 PBRF laboratory personnel performed 523 tritium sample analyses during this report period. PBRF performed a total of 1789 analyses of quality I assurance (QA) samples. They include:

  • 612 analyses on 3 reference standards I
  • 227 analyses on 227 blank samples I
  • 454 analyses on 2 background samples
  • 454 analyses on 2 QC Check samples I
  • 8 Cross-check Program sample analyses on 2 samples I
  • 20 inter-laboratory comparison (replicate) on 20 samples
  • 14 intra-laboratory comparison (replicate) on 14 samples I 1.2.2 Of all the QA samples that were analyzed on the PBRF Liquid Scintillation Analyzer, there were no discrepancies that required documentation of a I Sample Deviation Report .
  • 1

I~------------------------------~

I 1.3 Four Sample Deviation Reports were completed as a result of deficiencies found I during this report period. Two were associated with MAPEP Series 18 Co-60 failures. Two were failures to attain agreement between intra-laboratory replicate analyses of K-40. These failures were investigated by the Laboratory Manager and I corrective actions were documented. Refer to Section 10.0 of this report.

2.0 INrRODUCTION I 2.1 This report has been prepared by the PBRF Radiological Laboratory Manager in accordance with PBRF procedure RP-060, PBRF Radiological Laboratory Quality I Assurance/Quality Control Program. It provides a summary and interpretation of PBRF Laboratory QA Program for the period of January 1, 2008 to December 31, 2008.

I 3.0 DISCUSSION I 3.1 A QA program is an essential part of any radiological monitoring program. It provides reasonable assurance that the results of radiation measurements are valid. To be effective, elements of QA must be evident in all phases of the I monitoring program. These include, but are not limited to, sample collection, preservation and shipment, receipt of samples by the laboratory, preparation and analysis of samples and data review and reporting. An effective QA program will I allow for the identification of deficiencies in all monitoring processes so that appropriate investigative and corrective actions can be implemented.

I 3.2 The United States Nuclear Regulatory Commission (USNRC) published Regulatory Guide 4.15, "Quality Assurance for Radiological Monitoring Programs (Normal Operations) - EfHuent Streams and the Environment", which defines an acceptable I QA program. The guidance contained in Regulatory Guide 4.15 and NRC 10CFR50, Appendix B, "Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants" has been adopted by the PBRF Facility. Procedures I have been written and implemented to meet the objectives of these position documents.

I 3.3 Samples are typically analyzed only once because of workload constraints.

Therefore, laboratory personnel must be confident in the analytical results which are reported. One means of achieving confidence in the results is through the analysis I of QA samples. This report provides the analytical results of various QA samples processed by the PBRF laboratory during this period.

I 3.4 Quality Control checks are performed on at least 5% of all samples analyzed on the PBRF Gamma Spectroscopy Systems and/or Liquid Scintillation Analyzer. For the purpose of comparing results, these samples may be analyzed in duplicate by an I independent laboratory (inter-laboratory comparison) or by PBRF (intra-laboratory comparison) in their entirety or split to perform multiple analyses. The original analytical results are then compared with the replicate analysis results for I agreement.

I 2

I~------------------------------~

I 3.5 The PBRF laboratory participates in the United States Department of Energy Mixed Analyte Performance Evaluation Program (MAPEP) and the Eckert & Zeigler Analytics cross check programs. Blind spike samples are sent to the PBRF I Laboratory for gamma spectroscopy and tritium analysis approximately twice a year. Results are submitted via the Internet and evaluated for agreement.

I 3.6 Blank samples are analytical control samples, usually distilled water or verified clean (non-radiological) sand or soil, used to demonstrate that reported analytical results are not the result of Laboratory and/or Sample Processing Facility I contamination. They are used to evaluate the entire analytical procedure (sample preparation and analysis) and are prepared at the PBRF Facility for analysis in conjunction with batches or groups of regular samples.

I 3.7 This report is divided into the following sections:

I

  • Section 4.0 - Laboratory Program
  • Section 5.0 - Inter-laboratory and Intra-laboratory Comparison Analysis I
  • Section 6.0 - Quality Control Checks I
  • Section 7.0 - Background Determinations
  • Section 8.0 - Blank Sample Analysis I
  • Section 9.0 - Cross-check Program I
  • Section 10.0 - Laboratory/Sample Deviation Reports
  • Section 11.0 - Attachments I Brief discussions and summaries as well as applicable acceptance criteria are included for each section. Analytical results, which did not meet the specified I 4.0 acceptance criteria, are noted and discussed.

LABORATORY PROGRAM I 4.1 The PBRF Radiological Laboratory is designed to support the analytical requirements of decommissioning work activities, environmental program, and Final Status Survey. The laboratory consists of three high resolution gamma I spectroscopy units, one liquid scintillation counter, and three gas flow proportional alphalbeta counters. The laboratory is operated by qualified personnel with I documented training on all of the laboratory equipment. Sample processing is performed in accordance with site procedures and chain of custody is maintained for all samples. There were no significant laboratory program changes during this I period.

I I 3

I~------------------------------~

I 5.0 INTER-LABORATORY & IN"rRA-LABORATORY COMPARISON ANALYSIS 5.1 For this report period, 24 gamma spectroscopy comparison analyses were I performed on 12 inter-laboratory samples and 249 gamma spectroscopy comparison analyses were performed on 132 intra-laboratory samples. This equates to approximately 6.5% of the total gamma spectroscopy sample analysis I performed during the report period. Two intra-laboratory comparison results were not in agreement and a Sample Deviation Report was completed for each. All of the remaining comparison analyses performed in this period were in agreement.

I 5.2 Air filter and smear samples are not typically sent to an off site laboratory for gross activity comparison analysis. In addition, the PBRF laboratory does not perform I gross activity analysis on water or soil samples. Therefore, no inter-laboratory or intra-laboratory gross alpha/beta comparative analyses were performed during this period.

I 5.3 For this report period, 14 intra-laboratory tritium comparative analyses were performed on 14 samples and 20 inter-laboratory tritium comparative analyses I were performed on 20 samples. This is approximately 6.5% of the total tritium sample analysis performed during the report period. All of the comparative analyses performed in this period were in agreement.

I I

I I

I I

I I

I I

I 4


TABLE 1 INTRA-LABORATORY COMPARISON (REPLICATE) RESULTS c:

.2 c: SDR Gamma Log Sample ID Replicate Original 0

(])

Number Acquisition Sample Original Replicate S E Number Number Date Type Analysis Nuclide Units 2 Sigma (5 ~ (]) SDR SDR-Result Result If) ~ ~

(Original) (Replicate) Performed By Uncertainty (])

Ol 08 08-

~ <t: ###

Paint PBOS-00020 PBOS-00021 111012008 PBRF K-40

-40 pCilg 6.7SE+02 9.09E+02 3.20E+02 4.0 0.75 YES N/A Chips Paint PB08-00020 PB08"()0021 PB08"()00 1/10/2008 PBRF Co-60 0-60 pCilg S.02E+01 S.10E+01 2.44E+01 7.0 0.99 YES N/A Chips I~~~~

PBOB"()0040 PBOS"()0041 PBOS"()OO 1/14/200B Puck PBRF K-40 pCilg 9.40E+00 B.60E+00 200E~

2.60E+00 7.0 1.09 1.09 YES N/A NI PBOS-00040 PBOS-00041 1/14/200S Puck PBRF Co-60 pCilg 1.35E+01 1.32E+01 B.20E"()1 B.20E 33.0 1.02 YES N/A PBOB-00040 PBOB-00041 1/14/200B Puck PBRF Cs-137 pCi/g 2.30E+00 2.70E+00 3.90E"()1 1.

12.0 0.85 YES N/A PB08-00060 PBOB-00061 1/15/200B Soil PBRF K-40 pCi/g 1.35E+01 1.19E+01 1.95E+00 14.0 1.13 YES N/A I~~ ~~~~~~~~~~~- !~~~~

PBOS"()OOBO PBOB-000B1 1/161200S Air PBRF K-40 uCi/ml I 1.44E-09 1.60E-09 4.30E-10 7.0 0.90 YES N/A PB08"()0100 PB08-00101 1/1712008 Soil PBRF Co-60 pCilg 2.50E+02 2.47E+02 B.30E+00 60.0 1.01 YES N/A

~~~~~~~- ~~

PBOS-00100 PBOB"()0101 1/17/200S Soil PBRF Cs-137 pCilg 1.40E+04 1.38E+04 4.50E+02 4.S0E+02 62.0 1.01 YES N/A PBOS"()0120 PBOS-00121 1/231200S Air PBRF K-40 uCilml 2.60E"()9 2.20E-09 6.90E-10 8.0 1.18 YES N/A PBOB-00140 PBOS-00141 1/2B1200B Puck PBRF Ag108m pCilg 1.20E+00 E+OO 1.20E+00 1.50E"()1 1.S0E"()1 16.0 1.00 YES N/A PBOB-00140 PBOS-00141 1/2S/200B Puck PBRF Cs-137 pCi/g 7.50E-01 7.S0E-01 9.30E-01 2.30E-01 7.0 0.81 YES N/A PBOS-00160 PBOS-00161 1/2S/2008 Water PBRF K-40 pCi/g S.50E-01 S.SOE-01 9.70E-01 3.40E-01 5.0 S.O 0.88 YES N/A

~~~~~~---

PBOS-00160 PBOB"()0161 112S12008 Water PBRF Cs-137 pCi/g 6.BOE-01 6.00E-01 9.00E-02 15.0 1S.0 1.13 YES N/A PB08-00160 PBOS-00161 112B1200B Water PBRF Co-60 pCi/g 1.40E-01 1.20E-01 4.00E-02 7.0 1.17 YES N/A


~~~~~~~- ~~~~----

~~~~----

PBOS-00160 PBOB-00161 1/2S1200B Water PBRF H3 pC' pCilml 9.44E+01 8.96E+01 4.22E+00 45.0 4S.0 1.05 1.0S YES N/A N/A E

PBOB-00180 PBOB-001S1 1/221200B Water PBRF K-40 pCilg 6.40E-01 7.30E-01 2.60E"()1 5.0 0.88 YES Y


~~------

PBOB-001BO PBOB-001B1 1/221200S Water PBRF H3 pCilml 1.00E+00 4.00E-01 1.00E+00 2.0 2.50 2.S0 Y YES N/A PBOB-00200 PBOB-00201 1/30/200B Air PBRF K-40 uCi/ml 7.11E-10 7.00E-10 1.BOE-11 79.0 1.02 YES N/A PBOB-00220 PBOS-00221 2/512008 2/S12008 Soil PBRF K-40 pCilg 6.10E+00 3.S0E+00 1.70E+00 7.0 1.61 YES N/A

~

PBOB-00220 PBOS"()0221 2/512008 2/S12008 Soil PBRF Cs-137 pCilg 1.00E+00 1.10E+00 2.70E-01 7.0 0.91 YES N/A 5


TABLE 1 (Continued)

INTRA-LABORATORY COMPARISON (REPLICATE) RESULTS c: 'E SDR 0 Q)

Gamma Log Sample ID Replicate Original :p 0 Number Acquisition Sample Original Replicate  :::I E Number Number Type Analysis Nuclide Units 2 Sigma (5 ~ Q) SDR SDR-Date Result Result fI) n::: ~

(Original) (Replicate) Performed By Uncertainty Q) Cl 08 08-n::: ci ###

PB08-00240 PB08-00241 2/6/2008 Air PBRF K-40 uCilml 7.44E-10 8.10E-10 2.00E-10 7.0 0.92 YES NIA PB08-00260 PB08-00261 2/6/2008 Soil PBRF K-40 pCilg 2.31E+01 2.10E+01 4.10E+00 11.0 1.10 YES N/A Y~

PB08-00280 PB08-00281 2/612008 Soil PBRF K-40 pCi/g 1.35E+01 1.79E+01 2.90E+00 9.0 0.75 YES N/A PB08-00303 PB08-00304 211112008 Soil PBRF K-40 pCilg 1.88E+01 1.73E+01 3.20E+00 12.0 1.09 YES N/A PB08-00320 PB08-00321 2112/2008 Soil PBRF K-40 pCi/g I 1.84E+01 2.05E+01 3.20E+00 12.0 0.90 YES YE N/A PB08-00340 PB08-00341 2/1312008 Soil PBRF K-40 pCi/g 2.23E+01 1.60E+01 3.60E+00 12.0 1.39 YES N/A PB08-00360 PB08-00361 2113/2008 Soil PBRF K-40 pCi/g pCilg 1.62E+01 1.96E+01 3.10E+00 10.0 0.83 YES NIA PB08-00380 PB08-00381 211212008 Air PBRF K-40 uCilml 2.20E-11 2.90E-11 6.20E-12 7.0 0.76 YES NIA N/A pc~

PB08-00422 PB08-00423 2/2012008 Water PBRF K-40 pCilg 1.02E+00 7.10E-01 3.30E-01 6.0 1.44

1. YES N/A PB08-00422 PB08-00423 2120/2008 0/2008 Water PBRF H3 pCi/g 2.00E-01 E-01 2.00E-01 1.17E+00 0.3 1.00 YES N/A PB08-00440 PB08-00441 2/21/2008 2121/2008 Soil PBRF K-40 pCilg pC 1.66E+01

.66E+01 1.73E+01 3. 1 1OE+OO OE+OO 11.0 0.96 YES N/A NIA PB08-00460 PB08-00461 2121/2008 Soil PBRF K-40 pCilg 1.56E+01 1A2E+01 3.00E+00 10.0 1.10 YES N/A NIA PB08-00480 08-00480 PB08-00481 212212008 Air PBRF K-40 uCi/ml 5.90E-10 6.50E-10 1.50E+10 0.0 0.91 YES N/A NIA PB08-00500 PB08-00501 PB08-0050 212512008 Soil PBRF K-40 pCilg 1.61E+01 1.50E+01 2.90E+00 11.0 1.07 YES N/A PB08-00534 PB08-00535 PB08-005 2/27/2008 Soil PBRF K-40 pCilg P 1.71E+01 1.59E+01 3.10E+00 11.0 1.08 YES N/A 08-00540 PB08-00540 PB08-00541 2/2712008 Soil PBRF K-40 pCilg 4.40E+00 5.00E+00 1AOE+OO 1 AOE+OO 6.0 0.88 YES N/A 11.0~

~------

PB08-00560 PB08-00561 2/2712008 Soil PBRF K-40 pCilg 1.39E+01 1.57E+01 157E+lli 5OE +OO 2.50E+00 11.0 0.89 YES NIA N/A PB08-00580 PB08-00581 2/2912008 212912008 Water PBRF K-40 pCilg 7.80E-01 7.50E-01 7.50E-0 1.70E-01 1 .70E-01 9.0 1.04 YES N/A r-------

r--------

PB08-00580 PB08-00581 2/29/2008 212912008 Water PBRF H3 pCilg pCi/g 4.00E-01 1.00E+00 7.00E-01 1.1 0040 YES N/A NIA I PB08-00600 PB08-00602 3/3/2008 Puck PBRF K-40 pCilg pCi/g 7.90E+00 7.70E+00 2 AOE+OO 7.0 1.03 YES N/A NIA 6


TABLE 1 (Continued)

INTRA-LABORATORY COMPARISON (REPLICATE) RESULTS Gamma Log Number Sample 10 Number Acquisition Sample Replicate Analysis Nuclide Units Original Replicate Original 2 Sigma

.2 t:

"5 Ratio t:

Q)

E Q)

SDR Number SDR SDR-Date Type Performed Result Result "0 (Original) (Replicate) Uncertainty I/)

Q)

~ 08 08-C)

By 0:: << ###

PB08-00620 PB08-00621 313/2008 Soil PBRF K-40 pCilg pCiI 1.60E+01 1.97E+01 2.95E+00 E+OO 11.0 0.81 YES N/A PB08-00640 PB08-00641 3/412008 Soil PBRF K-40 pCilg 1.27E+01 1.17E+01 2.60E+00 10.0 1.09 YES N/A PB08-00660 PB08-00661 3/4/2008 Soil PBRF K-40 pCilg 1.72E+01 1.64E+01 2.90E+00 12.0 1.05 YES N/A PB08-00683 PB08-006B4 3/5/2008 Air PBRF K-40 uCi/ml 5.50E-10 4.20E-10 1.50E-10 7.0 1.31 YES N/A

-~~~~~~~

PB08-00683 PB08-00684 3/512008 Air PBRF Cs-137 uCilml 2.10E-11 1.10E-11 7.80E-12 5.0 1.91 YES N/A PB08-00700 PB08-00701 3/612008 Air PBRF K-40 uCilml 6.60E-10 6.50E-10 1.90E-10 7.0 1.02 2 YES N/A c-~~~~ ----------

PB08-00720 PB08-00721 3/10/2008 Soil PBRF K-40 pCilg 1.59E+01 1.B4E+01 2.90E+00 11.0 0.86 YES N/A PB08-00740 PB08-00741 3/1012008 Soil PBRF K-40 pCi/g 1.86E+01 2.13E+01 3.30E+00 11.0 0 0.87 YES N/A r~~~~ ~~~~~~~~-~~~-

PB08-00764 PB08-00765 3/1212008 Soil PBRF K-40 pCilg 1.38E+01 1.35E+01 2.70E+00 10.0 1.02 YES N/A PB08-00764 PB08-00765 3/1212008 Soil PBRF Cs-137 pCilg 2.70E-01 1.60E-01 9.40E-02 6.0 1.69 YES N/A PB08-00780 PB08-00781 3112/2008 Soil PBRF K-40 pCi/g 1.49E+01 1.30E+01 2.70E+00 11.0 1.15 YES N/A PB08-00800 PB08-00801 3/13/2008 Soil PBRF K-40 pCilg 1.05E+01 1.0SE+01 1.52E+01 2.60E+00 8.0 0.69 YES N/A PB08-00800 PB08-00801 3/1312008 Soil PBRF Cs-137 pCi/g 2.40E+00 2.10E+00 5.40E-01 9.0 1.14 YES YES N/A

-~~ ---------

PB08-00820 PB08-00821 3/1412008 Soil PBRF K-40 pCi/g 1.64E+01 1.98E+01 2.98E+00 11.0 0.83 YES N/A

-~~~~

PB08-oo840 PB08-00841 3/1712008 Puck PBRF K-40 pCilg 1.50E+01 1.61 E+01 2.90E+00 10.0 0.93 I YES N/A PB08-00860 PB08-00861 3118/2008 Puck PBRF K-40 pCi/g 1.46E+01 1.70E+01 3.20E+00 9.0 0.86 YES N/A PB08-00877 PB08-00878 3/19/2008 Soil PBRF K-40 pCi/g 1.11E+01 1.53E+01 1.S3E+01 2.40E+00 9.0 0.73 YES N/A

~~~~~~~~

PB08-00900 PB08-00901 3/19/2008 Soil PBRF K-40 pCi/g 1.26E+01 1.35E+01 2.S0E+00 2.50E+00 10.0 0.93 YES N/A PB08-00920 PB08-00921 3/1912008 Soil PBRF K-40 PCVg~+oo pCi/g 4.70E+00 2.90E+00 1.50E+00 6.0 1.62 YES N/A PB08-00940 PB08-00941 312012008 Water PBRF K-40 pCi/g 7.30E-01 6.60E-01 2.BOE-01 5.0 S.O 1.11 YES N/A 7


TABLE 1 (Continued)

INTRA-LABORATORY COMPARISON (REPLICATE) RESULTS c: 'E SDR Replicate .2 (I)

Gamma Log Sample 10 Original Number Acquisition Sample Analysis Original Replicate "5 E Number Number Nuclide Units 2 Sigma (5 Ratio (I) SDR-SDR Date Type Performed Result Result r/) ~

(Original) (Replicate) Uncertainty (I) OB OB-By a::: :f ###

PBOB-00960 PBOB-00961 3/20/200B Soil PBRF K-40 pCi/g 1.65E+01 1.60E+01 3.00E+OO 11.0 1.03 YES N/A PBOB-009BO PBOB-009B1 3124/200B Soil PBRF K-40

~+O1 pCi/g 1.22E+01 1.2BE+01 2.50E+00 10.0 0.95 YES N/A PBOB-01000 B-01000 PBOB-01020 PBOB-01001 PBOB-01021

~

3/24/200B 3/25/200B Soil Puck PBRF PBRF K-40 K-40 PpCi/g pCi/g 1.32E+01 9.60E+00 1.55E+01 7.50E+OO 7.50E+00 2.50E+00 3.40E+00 11.0 6.0 0.B5 1.2B YES YES N/A N/A PBOB-01020 PBOB-01042 PBOB-01021 PBOB-01043 3/25/200B 3/25/200B Puck Puck PBRF PBRF Cs-137 K-40 pCi/g pCi/g 1.B9E+01 1.02E+01 1.73E+01 9.10E+00 1.40E+OO 4.20E+OO 27.0 5.0 1.09 1.12 YES YES

~I N/A N/A

~~k PBOB-01042 PBOB-01043 3125/200B Puck PBRF Cs-137 pCi/g 1.25E+02 1.22E+02 5.BOE+OO 43.0 1.02 YES N/A PB08-01060 PBOB-01061 3/261200B Puck PBRF K-40 pCi/g 7.70E+00 B.60E+00 3.00E+00 5.0 0.90 YES N/A PBOB-01060 PBOB-01061 3/26/200B ....

Puck PBRF Cs-137 pCi/g 3.24E+02 3.14E+02 1.25E+01 52.0 1.03 YES N/A

~

PBOB-010BO PB08-01081 PBOB-010B1 3/26/200B 3/26/2008 Soil PBRF K-40 pCi/g 1.35E+01 1.45E+01 2.BOE+OO 10.0 0.93 YES N/A PBOB-01080 PBOB-010B1 3/26/2008 3/26/200B Soil PBRF Cs-137 pCi/g 9.50E-01 1.20E+00 2.10E-01 9.0 0.79 YES N/A PB08-010BO PBOB-010B1 3/26/200B Soil PBRF Co-60 pCi/g 3.10E+00 3.70E+00 3.20E-01 19.0 0.84 YES N/A PBOB-01103 PBOB-01104 4/1/200B 4/1/2008 Air PBRF K-40 uCi/ml 3.20E-10 3.00E-10 9.00E-11 7.0 1.07 YES N/A PBOB-01120 PBOB-01121 4/1/2008 4/1/200B Puck PBRF K-40 pCi/g 6. BOE+OO 9.30E+00 2.10E+00 6.0 0.73 YES N/A PBOB-01143 PBOB-01144 4/2/200B 4/2/2008 Air PBRF K-40 uCi/ml 7.60E-10 7.20E-10 2.50E-10 6.0 1.06 YES N/A PBOB-01143 PBOB-01144 4/2/200B Air PBRF Cs-137 uCi/ml 3.50E-11 2.30E-11 1.70E-11 4.0 1.52 YES N/A PBOB-01160 PBOB-01161 4131200B Puck PBRF K-40 pCi/g 1.23E+01 B.30E+00 B.30E+OO 2.20E+00 11.0 1.4B YES N/A PBOB-01160 PBOB-01161 4/3/200B Puck PBRF Cs-137 pCi/g 1.90E-01 1.00E-01 9.00E-02 4.0 1.90 YES N/A PBOB-011BO PBOB-011B1 4/3/200B Soil PBRF K-40 pCi/g 1.73E+01 1.9BE+01 3.00E+00 12.0 0.B7 YES N/A PBOB-011BO PBOB-011B1 4131200B Soil PBRF Cs-137 pCi/g 4.00E-01 3.40E-01 1.40E-01 6.0 1.1B YES N/A PBOB-01200 PBOB-01201 4/7/200B Puck PBRF K-40 pCi/g 9.90E+OO 9.60E+00 2.60E+00 B.O 8.0 1.03 1.03= YES N/A 8


TABLE 1 (Continued)

INTRA-LABORATORY COMPARISON (REPLICATE) RESULTS Gamma Log Number Sample 10 Number Acquisition Sample Replicate Analysis Nuclide Units Original Replicate Original 2 Sigma c

0

s(5 Ratio c:

c:

Q.)

E Q.)

SOR Number SOR SOR-Date Type Performed Result Result VI ~

(Original) (Replicate) Uncertainty Q.) C> OB OB-By a:: << ###

PBOB-0122B PBOB-01229 4/B/200B Soil PBRF K-40 pCi/g 1.27E+01 1.26E+01 2.70E+00 OE+OO 9.0 1.01 YES N/A PBOB-0122B PBOB-01228 PBOB-01229 4/B/200B Soil PBRF Cs-137 pCilg 3..10E-01 1OE-01 3.30E-01 1.20E-01 5.0 0.94 YES N/A PB08-01250 PBOB-01251 4191200B 125 PBRF K-40 pCi/g 4.50E+00 5.70E+00 1.60E+00 6.0 0.79 YES N/A PBOB-012BO PBOB-01281 PBOB-012B1 4115/200B Soil PBRF K-40 pCi/g 1.36E+01 1.45E+01 2.70E+00 10.0 0.94 YES N/A PBOB-01307 PBOB-01310 4/171200B Air PBRF K-40 uCilml 3.30E-10 2.15E-10 7.9BE-11 B.O 1.53 YES N/A PBOB-01320 PBOB-01321 41171200B Soil PBRF K-40 pCilg 6.00E+00 9.90E+00 2.60E+00 5.0 0.61 YES N/A PBOB-01320 PB08-01321 PBOB-01321 4/17/200B Soil PBRF Cs-137 pCilg 4. 1 1OE-01 OE-01 4.90E-01 1.20E-01 7.0 0.B4 YES N/A PBOB-01340 PBOB-01341 4/22/200B Air PBRF K-40 uCilml uC 4.70E-10 B.10E-10 1.50E-10 6.0 0.5B YES N/A PBOB-01360 PBOB-01361 4/24/200B Air PBRF K-40 uCi/ml 7.60E-10 5.70E-10 1.70E-10 9.0 1.33 YES N/A PBOB-013BO PBOB-013B1 4128/2008 Water PBRF K-40 pCi/g 5.60E-01 5.50E-01 1.70E-01 7.0 1.02 YES N/A PBOB-013S0 PBOB-013BO PBOS-013S1 PBOB-013B1 412S1200S 412B1200S Water PBRF H3 pCilml <MOA <MOA N/A N/A N/A YES ...

N/A PB08-001400 PBOS-001400 PBOB-001420 PBOB-001440 PB08-001401 PBOS-001401 PBOS-001421 PBOB-001421 PBOB-001441 51112008 5/6/200B 5/B/200B Air Air Air PBRF BRF PBRF PBRF K-40 K-40 K-40 uCilml uCilml uCi/ml 4.30E-10 4.BOE-10 9.90E-10 5.30E-10 6.B5E-10 9.12E-10 9.30E-11 1.40E-10 2.50E-10 9iE' 9.0 7.0 B.O 0.S1 0.70

.70 1.09 YES YES YES N/A N/A N/A PBOB-001460 PBOB-001461 5/13/200B Puck PBRF K-40 pCi/g 9.40E+00 9.70E+00 2.40E+00 B.O 0.97 YES N/A PBOB-001480 PB08-0014B1 PB08-001481 5/131200S 5/131200B Puck PBRF K-40 pCilg 1.17E+01 9.40E+00 2.B5E+00 2.S5E+00 B.O 1.24 YES N/A C~'~


~

PBOB-001480 PB08-0014S0 PBOB-0014B1 PBOB-001481 5/131200B 5/1312008 Puck PBRF Cs-137 pCilg 2.10E+03 2.10E+03 7.30E+01 5B.0 1.00 YES N/A PBOB-0014BO PBOB-001481 511312008 Puck PBRF Co-6 Co-60 Ci/g pCi/g 2.40E+00 2.10E+00 3.10E-01 15.0 1.14 YES N/A 9


TABLE 1 (Continued)

INTRA-LABORATORY COMPARISON (REPLICATE) RESULTS c C SDR Replicate 0 (1)

Gamma Log Sample ID Original :p E Number Acquisition Sample Analysis Original Replicate  ::I

.2 Number Number Nuclide Units 2 Sigma "'0 0 Ratio (1) SDR-SDR Date Type Performed Result Result til  !!?

(Original) (Replicate) Uncertainty (1) 0) 08 08-By 0::: <t: ###

PBOB-001500 PBOB-001501 5/14/2008 Puck PBRF K-40 pCi/g 9.10E+00 B.30E+00 2.40E+00 B.O 1.10 YES N/A PBOB-001500 PBOB-001501 5/14/200B 14/200B Puck PBRF Cs-137 pCi/g 5.B3E+01 5.61 E+01 2.60E+00 45.0 1.04 YES N/A PBOB-001500 PB08-oo1520 PBOB-001520 B-001520 PBOB-001540 PBOB-001501 PBOB-001521 PBOB-001521 PBOB-001541 511412008 5I141200B 5/141200B 5/1412008 51141200B 5/15/200B OOB ffiRF Puck Puck Puck Water

,y.",

PBRF PBRF PBRF PBRF Co-60 K-40 Cs-137 K-40 pCi/g pCi/g pCi/g pCi/g 1.20E+00 1.10E+01 E+01 3.80E+00 E+OO 6.30E-01 OE-01 1.50E+00 9.70E+00 3.BOE+00 6.50E-01 1.9BE-01 3.00E+00 5.00E+00 2.50E-01 12.0 7.0 1.5 5.0 O.BO 1.13 1.00 0.97 YES YES YES YES N/A N/A N/A N/A

~ "

PBOB-001540 BOB-001540 PB08-001541 PBOB-001541 5/15/200B 5/15/2008 Water PBRF Cs-137 pCi/g 1.60E-01 1.70E-01 3.40E-02 9.0 0.94 YES N/A PBOB-001540 PBOB-OO1541 PBOB-OO 1541 5/15/2008 Water PBRF H3 pCi/ml 3.6BE+01 3.50E+01 2.67E+00 2B.0 1.05 YES N/A PBOB-001560 PB08-001561 PBOB-001561 5115/200B 125 PBRF K-40 pCi/g 4.20E+00 4.90E+00 1.50E+00 6.0 0.B6 YES N/A PBOB-0015BO 8-0015BO PB08-0015B1 PBOB-0015B1 5/191200B 5/1912008 Water PBRF K-40 pCi/g 1.03E+00 B.60E-01 8.60E-01 1.97E-01 10.0 1.20 YES N/A PB08-oo15BO

-0015BO PBOB-0015B1 5/191200B Water PBRF Cs-137 pCi/g 1.70E-01 1.BOE-01 2.60E-02 13.0 0.94 YES N/A PBOB-001600 PBOB-001601 5/19/200B Water PBRF K-40 pCi/g 7.80E-01 7.BOE-01 6.00E-01 3.00E-01 5.0 1.30 YES N/A f~~

PBOB-001600 PBOB-001601 5/191200B 5/19120 Water PBRF H3 pCi/ml <MDA <MDA N/A N/A N/A YES N/A f~ -----------

PBOB-001620 PBOB-001621 5/13/200B 5/13/2008 Water PBRF K-40 pCi/g B.40E-01 5.40E-01 2.50E-01 7.0 1.56 YES N/A E


~~~~~~~

~.

PBOB-001620 PBOB-001621 5/13/2008 Water PBRF H3 pCi/ml <MDA <MDA N/A NfA N/A N/A Y YES N/A

~ ~ ~ -------------

PBOB-001640 PBOB-001641 5/161200B 125 PBRF K-40 pCi/g 5.00E+00 5.40E+00 1.30E+00 E+OO 8.0 B.O 0.93 YES N/A PB08-001640 PBOB-001640 PBOB-001641 5/16/200B 125 PBRF Cs-137 pCi/g 3.50E-01 3.20E-01 B.90E-02 B.O 1.09 YES N/A PBOB-001660 PB08-001661 PBOB-001661 5/221200B 5/2212008 Puck PBRF K-40 pCi/g 1.16E+01 B.OOE+OO 3.00E+00 8.0 B.O 1.45 YES N/A PBOB-0016BO PBOB-001681 PBOB-0016B1 5/211200B 5/2112008 Puck PBRF K-40 pCi/g 1.04E+01 7.60E+00 2.90E+00 7.0 1.37 YES N/A 10


TABLE 1 (Continued)

INTRA-LABORATORY COMPARISON (REPLICATE) RESULTS c: "E SDR Replicate 0 Q.l Gamma Log Sample ID Original Number Number Number Acquisition Sample Analysis Nuclide Units Original Replicate 2 Sigma 5 Ratio E

Q.l SDR-Date Type Performed Result Result '0 (Original) (Replicate) Uncertainty fI)

Q.l OB OB-By Q.l en 0:: << ###

PBOB-001720 PB08-001721 I 6/4/200B Water PBRF K40 pCi/g 5.70E-01 6. 1OE-01 1.60E-01 I 7.0 0.93 YES N/A t** --------- ----------

PBOB-001720 PB08-001721 6/4/2008 Water PBRF H3 pCi/g <MDA <MDA N/A N/A N/A YES N/A PBOB-001740 PBOB-001741 6/161200B Puck (T) PBRF K40 pCilg 7.BOE+00 1.03E+01 1.60E+00 10.0~

10.0 0.76 YES N/A r-....

PB08-001740 PB08-001741 6/16/200B Puck (T) PBRF Cs-137 pCilg 7.60E-01 7.00E-01 1.60E-01 10.0 1.09 YES N/A

...- cc..***

PB08-001740 PBOB-001741 6/161200B Puck (B) PBRF K40 pCi/g 9.00E+00 1.12E+01 1.BOE+00 10.0 O.BO YES N/A r .... ---------

PB08-001740 PBOB-001741 6/1612008 Puck (B) PBRF Cs-137 pCi/g 5.80E-01 4.60E-01 1.40E-01 B.O 1.26 YES N/A PBOB-001760 PBOB-001761 6/17/200B Puck (T) PBRF K40 pCi/g 1.00E+01 5.20E+00 2.B4E+00 7.0 1.92 YES N/A PB08-001760 PBOB-001761 6/17/2008 Puck (T) PBRF Cs-137 pCilg 1.94E+00 2.10E+00 3.30E-01 12.0 0.92 YES N/A PB08-001760 PB08-001761 6/171200B Puck (B) PBRF K40 pCi/g 1.ooE+01 1.11E+01 2.70E+00 7.0 0.90 YES N/A PBOB-001760 PB08-001761 6/17/2008 Puck (B) PBRF Cs-137 pCilg 1.70E+00 1.60E+00 2.90E-01 12.0 1.06 YES N/A PB08-OO1780 PB08-0017B1 6/191200B Air PBRF K40 uCi/ml 2.30E-09 1.70E-09 6.ooE-10 8.0 1.35 YES N/A PB08-001BOO PBOB-001B01 6/23/2008 Puck (T) PBRF K40 pCi/g 7.97E+00 9.20E+00 2.23E+00 7.0 0.B7 YES I N/A PB08-oo1Boo PB08-001B01 6/231200B Puck (T) PBRF Cs-137 pCi/g 6.30E-01 5.30E-01 1.BOE-01 7.0 1.19 YES N/A PB08-001BOO PB08-001B01 6/23/2008 Puck (B) PBRF K40 pCi/g 9.05E+00 9.40E+00 2.40E+00 B.O 0.96 YES N/A PB08-OO1800 PBOB-001B01 6/23/200B Puck (B) PBRF Cs-137 pCi/g 5.00E-01 6.10E-01 1.90E-01 5.0 0.B2 YES N/A PBOB-001B20 PBOB-001B21 6/25/200B Water PBRF K40 pCilg 7.10E-01 B.BOE-01 1.90E-01 7.0 0.B1 YES N/A PBOB-001B20 PBOB-001B21 6/251200B Water I PBRF H3 pCilg <MDA <MDA N/A N/A N/A YES N/A PB08-001B40 PBOB-001B41 6/27/2008 Puck (T) PBRF K40 pCilg 7.BOE+00 7.30E+00 1.30E+oo 12.0 1.07 YES N/A 11 J

TABLE 1 (Continued)

INTRA-LABORATORY COMPARISON (REPLICATE) RESULTS t:: 'E SDR Replicate .2 Q)

Gamma Log Sample ID Original E Number Acquisition Sample Analysis Original Replicate 'S Number Number Nuclide Units 2 Sigma "0 Ratio Q) SDR-Date Type Performed Result Result (I) ~

(Original) (Replicate) Uncertainty Q) OB-By cr Jl ###

PBOB-001860 PBOB-001861 6/3012008 08 Puck (T) PBRF K-40 pCilg pCi/g 1.22E+01 B.10E+OO 3.35E+00 3.3 7.0 0 1.51 YES YE N/A PBOB-001860 PB08-001B61 6/30/2008 Puck (B) PBRF K-40 pCi/g 1.16E+01 9.70E+OO 2.32E+00 10.0 1.20 YES YE N/A PB08-001860 PB08-001B61 6/301200B Puck (B) PBRF Cs-137 pCi/g 3.70E-01 3.70E-01 1.60E-01 5.0 1.00 1.0 YES N/A PB08-001860 PB08-001861 6/30/2008 Puck (T) PBRF Cs-137 pCi/g 3.40E-01 1.71E-01 1.10E-01 6.0 1.99 YES N/A PB08-001880 PB08-001881 I 7/2/2008 Air PBRF K-40 uCilml uCi/ml 9.30E-10 B.20E-10 1.96E-10 9.0 1.13 YES N/A PB08-001900 8-001900 PB08-001901 712/2008 008 Puck PBRF K-40 pCi/g 9.00E+00 7.50E+OO 2.20E+00 B.O 1.20 YES N/A PBOB-001900 B-001900 PB08-001901 2008 7/2/2008 Puck PBRF K-40 pCi/g 6.90E+00 9.BOE+00 1.90E+00 7.0 0.70 YES N/A I

PBOB-001920 BOB-001920 PBOB-001921 7/8/2008 125 _ PBRF K-40 pCi/g 4.60E+00 4.80E+00 1.30E+00 7.0 0.96 YES N/A PB08-001920 B08-001920 PBOB-001921 7/8/200B 125 PBRF Co-60 pCi/g 1.50E-01 1.00E-01 5.00E-02 6.0 1.50 YES N/A PBOB-001920 PB08-001921 7/8/2008 125 PBRF Cs-137 pCilg pCi/g 5.BOE-01 6.30E-01 1.30E-01 9.0 0.92 YES N/A c~~~~~~~~~

~~~~~~~ ~ ~ ~ ~ ~

~ ~

PBOB-001940 PB08-001941 7/9/2008 Puck PBRF K-40 pCi/g 4.40E+00 4.60E+00 1.20E+00 E+OO 7.0 0.96 YES N/A f~~~~~~~~

~~~~~~~~~~ ~

PB08-001940 PBOB-001941 7/9/2008 Puck PBRF K-40 pCi/g 3.70E+00 4.00E+00 1.10E+00 7.0 0.93 YES N/A 1~~OB-001960

~~~~~~ ~

PBOB-001960 PBOB-001961 7/101200B Puck PBRF K-40 pCi/g 7.BOE+00 7.40E+00 2.20E+00

.20E+00 7.0 1.05 YES N/A

~ ~ ~ ~ ~

1~~OB-001960 PBOB-001960 PB08-001961 7/10/2008 Puck PBRF K-40 pCilg pCi/g 6.90E+00 7.50E+00 2.00E+00 7.0 0.92 YES N/A 1.~N/A PB08-001980 PB08-001981 7/1412008 Puck PBRF K-40 pCi/g 7.40E+00 7.00E+00 2.00E+00 7.0 1.06 YES N/A 12


TABLE 1 (Continued)

INTRA-LABORATORY COMPARISON (REPLICATE) RESULTS c: 'E SDR Replicate .2 Gamma Log Sample ID Original Q.)

E Number Acquisition Sample Analysis Original Replicate "5 Number Number Nuclide Units 2 Sigma (5 Ratio Q.) SDR-SDR Date Type Performed Result Result th ~

(Original) (Replicate) Uncertainty Q.) Cl OB-By IY ~ ##If.

PBOS-0019S0 PBOS-OO 19S1 7/141200S Puck PBRF Cs-137 pCi/g 2.40E+01 2.44E+01 1.20E+00 40.0 0.9S YES N/A PBOS-0019S0 PBOS-0019S1 7/141200S Puck PBRF K-40 pCi/g 7.30E+00 7.ooE+00 1.90E+00 S.O 1.04 YES N/A PBOS-0019S0 PBOS-0019S1 7/14/200S Puck PBRF Cs-137 pCi/g 2.44E+01 2.40E+01 1.30E+00 3S.0 1.02 YES N/A PBOS-002000 PBOS-002001 7/16/200S Puck PBRF K-40 pCi/g 7.70E+00 S.10E+00 1OE+OO

2. 1OE+OO 7.0 0.95 YES N/A PBOS-002000 PBOB-002001 7/16/200B Puck PBRF RF K-40 pCi/g 7.10E+00 6.S0E+00 2.ooE+00 7.0 1.04 YES N/A PBOS-002020 PBOS-002021 7/21/200B Puck PBRF BRF K-40 pCi/g 5.BOE+00 5.10E+00 1.40E+00 S.O 1.14 YES N/A

_p~~:=~ml~

PBOS-002020 PBOS-002021 71211200S Puck PBRF K-40 pCi/g 5.10E+00 5.10E+00 1.30E+00 S.O 1.00 YES N/A 08-002040 PBOO-002040 PBOS-002041 71221200S Puck PBRF K-40 pCi/g 9.50E+00 7.10E+00 7.10E "'

2.40E+00 B.O 1.34 YES YE N/A fA OS-002040 PBOS-002040 PBOS-002041 71221200B Puck PUCk_ PBRF Cs-137 pCi/g 2.25E+00 2.40E+00 3.22E-01 14.0 0.94 YES N/A NfA B

PBOS-002060 S-002060 PBOS-002061

  • 7/23/200S Puck PBRF K-40 pCi/g 9. 1 1OE+OO OE+OO 9.40E+00 2.20E+00 8.0 0.97 Y YES N/A

_ ...... ------- r---

PBOS-002060 PBOS-002061 7/23/200S 3/200S Puck PBRF Cs-137 pCi/g 1.26E+01 1.1SE+01 S.30E-01 30.0 1.07 YES N/A PBOS-002060 BOS-002060 PBOB-002061 7/23/200S Puck PBRF Co-60 pCi/g 9.50E-01 7.50E-01 2.30E-01 B.O 1.27 YES N/A PBOS-0020S0 PBOS-002081 7/24/200S Air PBRF K-40 uCi/ml 1.90E-09 1.60E-09 5.00E-10 B.O 1.19 YES N/A I........

PBOS-002100 PBOB-002101 7/24/200B Puck PBRF K-40 pCi/g 9.30E+00 9.20E+OO 2.95E+00 6.0 1.01 YES N/A PBOS-0021oo PBOS-002101 7/2412008 Puck PBRF Cs-137 pCi/g i 1.45E+01 1.57E+0 1.57E+01 10E+00 1.10E+00 26.0 0.9 0.92 YES N/A f

~~OS.002120 PBOS*002120 PBOB*002121 7/2912008 Puck PBRF K-40 pCi/g 9.50E+00 9.50E+OO 2.50E+00

.50E+00 8.0 1.00

1. YES N/A S-002120 PBOS-002120 PBOS-002121 7/29/2008 Puck PBRF Cs-137 pCi/g 4.32E+02 4.2SE+02 1.57E+01 55.0 1.01 YES N/A PBOS-002136 PBOS-002141 7/31/200S Puck PBRF K-40 pCi/g P B.50E+00 6.60E+00 2.14E+00 8.0 1.29 YES N/A c

PB08-002136 PBOO-002136 ~141 PBOS-002141 7/31/200S Puck PBRF Cs-137 pCi/g S.90E-01 9.60E-01 1.90E-01 9.0 0.93 YES N/A 13


TABLE 1 (Continued)

INTRA-LABORATORY COMPARISON (REPLICATE) RESULTS c: "E SDR Replicate 0 Q)

Gamma Log Sample ID Original Number Acquisition Sample Analysis Original Replicate ~ E Number Number Nuclide Units 2 Sigma (5 Ratio Q) SDR SDR-Date Type Performed Result Result <n ~

(Original) (Replicate) Uncertainty Q) C) OB-By c::: << ###

PBOB-02160 PBOB-02161 B/4/200B Puck PBRF K-40 pCi/g 3.70E+00 2.24E+00 9.20E-01 B.O 1.65 YES N/A PBOB-021BO PBOB-021B1 B/5/200B Water PBRF K-40 pCi/g 7.90E-01 9.70E-01 1.BOE-01 9.0 0.B1 YES N/A PBOB-021BO PBOB-021B1 B/5/200B Water PBRF H3 pCi/ml <MDA <MDA N/A N/A N/A YES N/A PBOB-02200 PBOB-02201 BI6/200B Puck PBRF K-40 pCi/g 3.20E+00 2.90E+00 1.20E+00 5.0 1.10 YES N/A PBOB-02200 PBOB-02201 BI6/200B Puck PBRF Co-60 pCi/g 3.30E-01 4.20E-01 B.50E-02 B.O 0.79 YES N/A PBOB-02220 PBOB-02221 BI6/200B Puck PBRF K-40 pCi/g 1.40E+01 1.14E+01 3.70E+00 B.O 1.23 YES N/A PBOB-02220 PBOB-02221 BI6/200B Puck PBRF Co-60 pCi/g 2.20E+00 2.00E+00 3.40E-01 13.0 1.10 YES N/A PBOB-02220 PBOB-02221 BI6/200B Puck PBRF Cs-137 pCi/g 4.70E+00 5.14E+00 5.90E-01 16.0 0.91 YES N/A PBOB-02240 PBOB-02241 B171200B Puck PBRF K-40 pCi/g B.20E+00 B.BOE+OO 2.30E+00 7.0 0.93 YES N/A PBOB-02240 PBOB-02241 B171200B Puck PBRF Co-60 pCi/g 4.50E-01 4.10E-01 1.20E-01 B.O 1.10 YES N/A PBOB-02240 PBOB-02241 BI7I200B Puck PBRF Cs-137 pCi/g 6.30E+00 6.40E+00 5.BOE-01 22.0 0.9B YES N/A I

PBOB-02260 PBOB-02261 B/11/200B Puck PBRF K-40 pCi/g B.OOE+OO B.BOE+OO 1.BOE+00 9.0 0.91 YES N/A PBOB-022BO PBOB-022B1 B/12/00B Puck PBRF K-40 pCi/g 7.50E+00 7.10E+00 2.30E+00 7.0 1.06 YES N/A PBOB-02300 PBOB-02301 B/13/200B Puck PBRF K-40 pCi/g 7.70E+00 5.20E+00 1.BOE+00 9.0 1.4B YES N/A PBOB-02300 PBOB-02301 B/13/200B Puck PBRF Cs-137 pCi/g 9.00E-01 9.90E-01 1.60E-01 11.0 0.91 YES N/A PBOB-02320 PBOB-02321 B/19/200B Air PBRF K-40 uCi/ml 6.60E-10 B.30E-10 2.30E-10 6.0 O.BO YES N/A PBOB-02340 PBOB-02343 BI21/200B Puck PBRF K-40 pCi/g 1.26E+01 6.50E+00 3.00E+00 B.O 1.94 NO 003 PBOB-02360 PBOB-02361 BI21/200B Puck PBRF K-40 pCi/g 9.90E+00 1.12E+01 2.70E+00 7.0 O.BB YES N/A PBOB-02360 PBOB-02361 BI21/200B Puck PBRF Cs-137 pCi/g B.40E-01 1.20E+00 2.20E-01 B.O 0.70 YES N/A 14


TABLE 1 (Continued)

INTRA-LABORATORY COMPARISON (REPLICATE) RESULTS Gamma Log Sample ID Acquisition Sample Replicate Analysis Original Replicate Original I::

0

0:;
J I ::

E SDR Number Number Number Nuclide Units 2 Sigma "0 Ratio SDR-SDR Date Type Performed Result Result tI) ~

(Original) (Replicate) Uncertainty C) OB-08 By 0::: << ###

PB08-02380 PB08-02381 8/2612008 B/261200B Puck PBRF K-40 pCilg 7.70E+00 9.00E+00 2.12E+00 7.0 0.B6 0.86 YES N/A PB08-02400 PBOB-02400-R PB08-02400-R 8/2712008 B/271200B Puck PBRF K-40 pCi/g 7.BOE+00 7.23E+00 2.20E+00 7.0 1.0B 1.08 YES N/A


j-----j---

PBOB-02420 PB08-02422 B/2B1200B Puck PBRF K-40 pCi/g 1.19E+01 1.09E+01 2.90E+00 B.O 1.09 YES N/A 11---------------- + - - - - - - - - + - - - - - - + - - - - - I - - - - - + - - - - f - - - - j -------------------1------1 --------------- j-----j----t-PBOB-02340 PBOB-02500 PB08-02500 9/B/200B 9/B/2008 Puck PBRF K-40 pCi/g 8.40E+00 B.40E+00 6.50E+00 2.20E+00 B.O 1.29 YES 003 PB08-02340 PB08-02500 9/BI2008 9/B/200B Puck PBRF K-40 pCilg p B.40E+00 1.26E+01 2.20E+00 B.O 8.0 0.67 YES 003


j----------t-----+-------t----------j-PB08-02440 PBOB-02441 9/2/2008 9/2/200B Puck PBRF K-40 p pCi/g 1.16E+01 9.50E+00 2.BOE+00 B.O 8.0 1.22 YES N/A


- - - - - t - - - - - - - - - - - - j - - - - + - - - - - - - - - - j - - - - t - -

PBOB-02460 PBOB-02461 9/3/200B Puck PBRF K-40 pCi/g 7.50E+00 6.60E+00 2.20E+00 7.0 1.14 YES N/A PB08-02460 PBOB-02461 PB08-02461 9/312008 Puck PBRF Cs-137 pCilg 4.60E-01 6.50E-01 1.60E-01 6.0 0.71 YES N/A PBOB-02480 PB08-024BO PBOB-024B1 PB08-024B1 9/4/200B 9/4/2008 Puck PBRF K-40 pCilg 5.70E+00 4.30E+00 1.70E+00 7.0 1.33 YES N/A PBOB-024BO PB08*02480 PBOB-024B1 PB08-02481 9/4/2008 Puck PBRF Cs-137 pCi/g 1.BOE+01 1.83E+01 E+01 1.10E+00 33.0 0.98 YES N/A PBOB-02500 PBOB*02500 PBOB-02501 PB08-02501 9/8/2008 9/B/2008 Puck PBRF K-40 pCi/g B.40E+00 8.40E+00 9.40E+00 2.20E+00 8.0 0.89 YES N/A PB08-02500 PBOB-02501 PB08-02501 9/812008 9/81200B Puck PBRF Cs-137 pCi/g 2.70E-01 3.70 E-O E-O11 1.00E-01 5.0 0.73 YES N/A 11--------+----------------

PBOB-02520 PB08-02520 PBOB-02521 PB08-02521 9/9/2008 9/9/200B Puck PBRF K-40 pCi/g 8.40E+00 1.27E+01 2.30E+00 7.0 0.66 YES N/A 11--------+-------------

PBOB-02520 PBOB-02521 9/9/2008 9/9/200B Puck PBRF Cs-137 pCilg 4.60E-01 3.10E-01 1.70E-01 5.0 1.4B 1.48 YES N/A PB08-02540 PBOB-02540 PBOB-02541 PB08-02541 9/9/2008 9/9/200B Water PBRF K-40 pCi/g 7.40E-01 6.60E-01 1.98E-01 1.9BE-01 7.0 1.12 YES N/A PB08-02560 PBOB-02560 PB08-02561 PBOB-02561 9/15/2008 Puck PBRF K-40 pCi/g 1.23E+01 7.42E+00 2.BOE+00 2.80E+00 9.0 1.66 YES N/A r~""'"

PBOB-02580 PB08-025BO PBOB-02581 PB08-02581 9/1712008 Puck PBRF K-40 pCi/g 9.30E+00 1.05E+01 2.10E+00 I !iW 9.0 I 0.89 0.B9 YES N/A I...... -----f---------------

PB08-02580 PBOB-02581 PB08-02581 9/1712008 Puck PBRF Cs-137 pCi/g 2.90E-01 2.10E-01 1.20E-01 5.0 1.38 YES N/A PBOB-02600 PB08-02600 PBOB-02601 PB08-02601 9/2212008 Puck PBRF K K-40 pCi/g 1.54E+01 1.01E+01 1.01 E+01 3.60E+00 9.0 1.52 YES N/A 15


TABLE 1 (Continued)

INTRA-LABORATORY COMPARISON (REPLICATE) RESULTS c: "E SDR Replicate 0 Q)

Gamma Log Sample ID Original  :;::

E Number Acquisition Sample Analysis Original Replicate  ::J Number Number Nuclide Units 2 Sigma (5 Ratio Q) SDR SDR-Date Type Performed Result Result t/) ~

(Original) (Replicate) Uncertainty Q) 08 08-By ex:: <<Cl ###

PB08-02600 PB08-02601 9/22/2008 Puck I PBRF Cs-137 pCi/g 6.60E-01 4.50E-01 2.20E-01 6.0 1.47 YES N/A r~~~

PB08-02620 PB08-02621 9123/2008 Puck PBRF K-40 pCi/g 8.60E+00 8.50E+00 2.40E+00 7.0 1.01 YES N/A

~ ~~~~~

PB08-02620 PB08*02621 9/2312008 Puck PBRF Co-60 pCi/g 5.30E-01 5.30E-01 1.60E-01 7.0 1.00 YES N/A

~ ~~~~~~~

PB08-02620 PB08-02621 9/2312008 Puck PBRF Cs-137 pCi/g 4.00E-01 4.10E-01 1.20E-01 7.0 0.98 YES N/A N~I PB08-02640 PB08-02641 9125/2008 Puck PBRF K-40 pCi/g 1.31E+01 9.30E+00 3.22E+00 8.0 1.41

.41 YES N/A

~-O1 PB08-02640 PB08-02641 9/2512008 Puck PBRF Co-60 pCilg pC,g 4.00E-01 3.30E-01 1.80E-01 4.0 1.21

.21 YES N/A PB08-02640 PB08-02641 9/25/2008 Puck PBRF Cs-137 pCilg 5.90E-01 E-01 3.00E-01 2.20E-01 5.0 1.97 YES N/A Nt PB08-02660 PB08-02661 9/29/2008 Water PBRF K-40 pCi/g 8.00E-01 8.80E-01 1.70E-01 9.0 0.91 YES N/A PB08-02660 PB08-02661 9/2912008 Water PBRF Cs-137 pCi/g 2.30E-02 4.30E-02 9.00E-03 5.0 0.53 YES N/A PB08-02820 PB08-02821 11/512008 Water PBRF K-40 pCi/g 5.80E-01 7.60E-01 1.20E-01 10.0 0.76 YES N/A PB08-02820 PB08-02821 11/512008 Water PBRF Cs-137 Cs-1 pCi/g 2.00E-02 1.00E-02 8.00E-03 5.0 2.00 YES N/A PB08-02840 PB08-02841 11/121200B Soil PBRF K-40 pCi/g 1.63E+01 1.63E+01 3.BOE+00 9.0 1.00 YES N/A PBOB-02B40 PBOB-02841 11/121200B Soil PBRF Cs-137 pCi/g 4.20E-01 3.40E-01 1.60E-01 5.0 1.24 YES N/A PBOB-02B60 PBOB-02B61 11/17/200B Soil PBRF K-40 pCi/g 9.30E+00 1.16E+01 2.40E+00 B.O O.BO YES N/A PBOB-02860 PB08*02B61 PB08-02B61 11/17/200B Soil PBRF Cs-137 pCi/g 2.60E-01 1.60E-01 7.20E-02 7.0 1.63 YES N/A PB08-02BBO PBOB-028B1 11/24/200B Puck PBRF K-40 pCi/g 9.60E+00 9.30E+00 2.40E+00 B.O 1.03 YES N/A PB08*02BBO PBOB*02BB1 111241200B Puck PBRF Cs-137 pCi/g 3.60E+00 3.40E+00 4.30E+00 1.7 1.06 YES N/A PBOB-02900 PBOB-02901 11124/200B ' Puck PBRF K-40 pCi/g ilg 1.11E+01 B.10E+00 2.50E+00 9.0 1.37 YES N/A r---~~~

PBOB-02920 PBOB-02921 12/2/200B Water PBRF K-40 pCi/g i/g 7.00E-01 7.20E-01 2.60E-01 5.0 0.97 YES N/A 16


TABLE 1 (Continued)

INTRA-LABORATORY COMPARISON (REPLICATE) RESULTS c: 'E SDR Replicate 0 (!)

Gamma Log Sample ID Original +=l Number Acquisition Sample Analysis Original Replicate  ::J E Number Number Nuclide Units 2 Sigma (5 Ratio (!) SDR SDR-Date Type Performed Result Result III ~

(Original) (Replicate) Uncertainty (!) 08 08-By 0::: <<Ol ###

PB08-02920 PB08-02921 1212/2008 Water PBRF H3 pCilml <MDA <MDA N/A N/A N/A YES N/A PB08-02940 PB08-02941 1212/2008 Water PBRF K-40 pCi/g <MDA <MDA N/A N/A N/A YES N/A PB08-02940 PB08-02941 12/2/2008 Water PBRF H3 pCilml <MDA <MDA N/A N/A N/A YES N/A PB08-02960 PB08-02961 12110/2008 Soil PBRF K-40 pCi/g 1.70E+00 1.06E+01 7.20E-01 5.0 0.16 NO 004 PB08-02960 PB08-02961 1/6/2009 Soil PBRF K-40 pCi/g 1.00E+01 1.01E+01 1.

1.80E+00 11.0 0.99 YES N/A PB08-02980 PB08*02981 1211712008 Puck PBRF K-40 pCi/g 5.76E+00 6.34E+00 1.54E+00 1 7.0 0.91 YES N/A PC~01 PB08-02980 PB08-02981 12117/2008 Puck PBRF Cs-137 pCilg 4.97E+01 3.90E+01 2.10E+00 47.0 1.27 YES N/A PB08*03000 PB08-03001 12/23/2008 Puck PBRF K-40 pCi/g 6.15E+00 4.60E+00 1.40E+00 9.0 1.34 YES N/A TABLE 2 INTER-LABORATORY COMPARISON (REPLICATE) RESULTS c: 'E SDR Replicate 0 (!)

Gamma Log Sample ID Original +=l Number Acquisition Sample Analysis Original Replicate  ::J E Number Number Nuclide Units 2 Sigma (5 Ratio (!) SDR SDR-Date Type Performed Result Result III ~

(Original) (Replicate) Uncertainty (!) 08 08-By 0::: :if ###

PB08-00071 F8A 170276-001 1/1512008 Water TAISTL Cs-137 uCilml 8.30E-OS 6.00E-08 1.70E-08 10.0 1.38 YES N/A PB08-00071 F8A170276-001 1/151200S Water TAISTL H3 uCilml 2.02E-05 2.16E-05 3.40E-09 3.40 11882.0 0.94 YES N/A PB08-00072 F8A170276-002 1/1512008 Water TAISTL Cs-137 .'"',,_.

uCi/ml 1.52E-06 1.60E-06 1.10E-07 28.0 0.95 YES N/A PB08-OOO72 PB08-00088 F8A170276-002 F8A180273*001 1/1512008 111612008 Water er Water TAISTL TAISTL H3 H3 Cs-137

~uCi/ml uCi/ml 2.78E-04 5.60E-08 2.92E-04 8.00E-08 1.80E-05 1.30E-08 1.30E-OB 31.0 9.0 0.95 0.70 YES YES N/A N/A 17


TABLE 2 (Continued)

INTER-LABORATORY COMPARISON (REPLICATE) RESULTS Gamma Log Sample ID Acquisition Sample Replicate Analysis Original Replicate Original c

.2 "S

-c Cl)

E SDR Number Number Number Nuclide Units 2 Sigma (5 Ratio Cl) SDR SDR-Date Type Performed Result Result II)  !!:!

(Original) (Replicate) Uncertainty Cl) OB OB-By c:::

C)

<C #11#

PBOB-OOOBB FBA1 FBA 1B0273-001 1/16/200B Water TAiSTL H3 uCi/ml 1.55E-05 1.54E-05 1.10E-06 2B.0 1.01 YES N/A PBOB-00089 FBA1B0273-oo1 1/161200B Water TAiSTL Cs-137 uCilml 5.5BE-07 S.5BE-07 6.00E-07 5.20E-OB 21.0 0.93 YES N/A PBOB-OOOB9 FBA1 FBA 1B0273-oo1 1I1612ooB Water TAiSTL H3 uCilml 2. 79E-04 2.95E-04 2.9SE-04 1.BOE-05 1.BOE-OS 31.0 0.95 0.9S YES N/A

~

PB08-OO52B FBB2B0209-oo3 2I27/2ooB Water TAiSTL Cs-137 uCilml 4.20E-OB 5.00E-OB S.OOE-OB 1.30E-OB 6.0 0.B4 YES N/A PBOB-0052B FBB2B0209-oo3 21271200B Water TAiSTL H3 uCilml 7.03E-04 7.31E-04 31E-04 4.40E-05 4.40E-OS 32.0 0.96 YES N/A PBOB-00526 FBB2B0209-oo1 2/271200B Water TAiSTL Cs-137 uCilml 1.5BE-06 1.90E-06

.90E-06 2.ooE-07

~

16.0 0.B3 YES N/A PBOB-00526 FBB2B0209-oo1 2/27/200B Water TAiSTL H3 uCi/ml 2.96E-04 E-04 3. 1 1OE-04 OE-04 1.90E-05 1.90E-OS 31.0 0.95 YES N/A PBOB-00527 PBOB-00S27 FBB2B0209-002 2/271200B Water TAiSTL Cs-137 uCi/ml 6.50E-OB 7.00E-OB 1.50E-OB 9.0 0.93 YES N/A PBOB-00527 FBB2B0209-002 2/27/200B Water TAiSTL H3 uCi/ml 5.05E-05 5.14E-05 3.20E-06 32.0 0.9B YES N/A PBOB-01019 FBC260229-OO1 3/25/2008 3/2S/2008 Water TAiSTL Cs-137 uCi/ml uC"ml I 6.50E-07

.50E-07 S.90E-07 5.90E-07 7.00E-OB 19.0 1.10 YES N/A PBOB-Ol019 PBOB-01019 FBC260229-oo1 3J2512~AlSTL 3/25/200B Water TAiSTL H3 uCi/ml u 1.57E-04 1.S7E-04 1.91E-04 5.34E-06 S.34E-06 59.0 0.B2 YES N/A PBOB-Ol463 L35200-1 5/131200B Puck uck TBE K-40 pCilg 1.07E+Ol 1.07E+01 1.03E+01 3.10E+00 7.0 1.04 YES N/A


~

PBOB-01463 L352oo-1 5/131200B Puck TBE Cs-137 pCilg 3.50E-01 3.ooE-01 1.40E-01 5.0 1.17 YES N/A PBOB-01505 L35264-1 5/1412008 Water TBE K-40 pCi/g I 2.BOE-01 3.ooE-01 1.50E-01

1. 3.7 0.93 YES N/A PBOB-01505 L35264-1 5/14/200B Water ater TBE Cs-137 pCi/g 3.BOE+00 3.BOE+00 2.ooE-Ol 2.ooE-01 3B.0 1.00 YES N/A PBOB-01505 L35264-1 5/14/200B Water TBE H3 pCi/g 5.B2E+Ol 5.77E+Ol S.77E+Ol 3.30E+00 35.0 1.01 YES N/A PBOB-01506 PBOB-01S06 L35264-3 5/14/200B S/14/200B Water TBE K-40 pCilg 9.BOE-Ol 9.BOE-01 9.40E-Ol 9.40E-01 3.20E-01 6.0 1.04 YES N/A PBOB-01506 L35264-3 5/1412008 Water TBE Cs-137 pCilg 2.50E-Ol 2.50E-01 1.BOE-01 5.00E-02 10.0 1.39 YES N/A 18

TABLE 2 (Continued)

INTER-LABORATORY COMPARISON (REPLICATE) RESULTS r::: "E SDR Replicate Gamma Log Sample ID Acquisition Sample Analysis Original Replicate Original 0-;0 Q)

E Number Number Number Nuclide Units 2 Sigma "0 Ratio Q) SDR-Date Type Performed Result Result If) ~

(Original) (Replicate) Uncertainty Q)

Cl OB-By c::: << ###

PBOB-01506 L35264-3 5/14/200B Water TBE H3 pCi/g 1.4BE+01 1.4BE+01 1.BOE+00 16.0 1.00 YES N/A PBOB-01507 L35264-2 5/14/200B Water TBE K-40 pCi/g 7.30E-01 1.10E+00 2.BOE-01 5.0 0.66 YES N/A PBOB-01507 L35264-2 5/14/200B Water TBE Cs-137 pCi/g 1.30E-01 1.10E-01 3.00E-02 9.0 1.1B YES N/A PBOB-01507 L35264-2 5/14/200B Water TBE H3 pCi/g 5.20E+00 5.BOE+00 1.30E+00 B.O 0.90 YES N/A PBOB-01539 L35266-1 5/15/200B Water TBE K-40 pCi/g 9.70E-01 1.20E+00 3.00E-01 6.0 0.B1 YES N/A PBOB-01539 L35266-1 5/15/200B Water TBE Cs-137 pCi/g 7.40E-01 7.10E-01 B.00E-02 19.0 1.04 YES N/A PBOB-01539 L35266-1 5/15/200B Water TBE H3 pCi/g 1.96E+01 1.93E+01 2.10E+00 19.0 1.02 YES N/A PBOB-01540 L35266-2 5/15/200B Water TBE K-40 pCi/g 6.30E-01 1.10E+00 2.50E-01 5.0 0.57 YES N/A PBOB-01540 L35266-2 5/15/200B Water TBE Cs-137 pCi/g 1.70E-01 1.10E-01 3.00E-02 11.0 1.55 YES N/A PBOB-01540 L35266-2 5/15/200B Water TBE H3 pCi/g 3.42E+01 3.4BE+01 2.60E+00 26.0 0.9B YES N/A PBOB-01997 L35B20 7/16/200B Water TBE Cs-137 pCi/g 1.90E-01 1.60E-01 2.30E-02 17.0 1.19 YES N/A PBOB-01997 L35B20 7/16/200B Water TBE H3 pCi/ml B.06E+01 B.26E+01 3.B4E+00 42.0 0.9B YES N/A PBOB-0199B L35B20 7/16/200B Water TBE Cs-137 pCi/g 3.70E-01 3.B1E-01 3.00E-02 25.0 0.97 YES N/A PBOB-0199B L35B20 7/16/200B Water TBE H3 pCi/ml 3.67E+02 3.94E+02 B.04E+OO 91.0 0.93 YES N/A PBOB-021B4 L36026-1 B/5/200B Water TBE Cs-137 pCi/g 2.60E-01 2.21 E-01 3.60E-02 14.0 1.1B YES N/A I

PBOB-021B4 L36026-1 B/5/200B Water TBE H3 pCilml 2.B6E+01 2.BOE+01 2.B5E+00 20.0 1.02 YES N/A PBOB-021B3 L36026-2 B/5/200B Water TBE Cs-137 pCi/g 2.40E-01 2.31E-01 3.30E-02 15.0 1.04 YES N/A 19


TABLE 2 (Continued)

INTER*LABORATORY COMPARISON (REPLICATE) RESULTS c 'E SDR Replicate 0 Q)

Gamma Log Sample ID Original Number Acquisition Sample Analysis Original Replicate  ::J E Number Number Nuclide Units 2 Sigma (5 Ratio Q) SDR-Date Type Performed Result Result (J) ~

(Original) (Replicate) Uncertainty Q) Cl OB-By 0::: << ###

PBOB-021B3 L36026-2 B/5/200B Water TBE H3 pCilml 1.70E+01 1.BOE+01 1.S6E+00 1S.0 0.94 YES N/A NIA PB08-02291 L360B2-1 B/13/200S Water TBE Cs-137 pCi/g 2.00E-01 2.30E-01 3.20E-02 13.0 0.B7 YES N/A PBOB-02291 L360B2-1 B/13/2008 Water TBE H3 pCilml 2.00E+00 1.60E+00 9.90E-01 4.0 1.25 YES N/A PBOB-02292 L360B2-2 8/13/2008 Water TBE Cs-137 pCilg 1.00E-01 S.BOE-02 2.30E-02 9.0 1.14 YES N/A PBOB-02292 L360B2-2 8/13/200S B/13/200S Water TBE H3 pCi/ml 2.10E+01 1.S4E+01 2.07E+00 20.0 1.14 YES N/A PBOB-02317 L36161-2 8/19/2008 B/19/200B Water TBE Cs-137 pCi/g 1.00E+00 1.06E+00 7. 1 1OE-02 OE-02 2S.0 0.94 YES N/A NIA PBOB-02317 L36161-2 B/19/200S Water TBE H3 pCi/ml 9.36E+01 9.07E+01 4.13E+00 45.0 1.03 YES N/A PBOB-0231S L36161-1 B/19/200S Water TBE Cs-137 pCi/g 2.10E-01 1.90E-01 3.00E-02 14.0 1.11 YES N/A PBOB-0231B L36161-1 S/19/2008 Water TBE H3 pCi/ml 2.S6E+01 2.99E+01 2.37E+00 24.0 0.96 YES N/A PBOB-02451 L36292-1 9/3/200B Water TBE Cs-137 pCilg 1.05E-01 7.00E-02 3.50E-02 6.0 1.50 YES N/A PBOB-02451 BT10 9/31200B Water TBE H3 pCi/ml 3.60E+00 3.30E+00 1.17E+00 6.0 1.09 YES N/A PBOB-02452 L36292-2 9/3/200B Water ter TBE Cs-137 pCilg 3.90E-01 3.10E-01 6.00E-02 13.0 1.26 YES N/A PBOB-02452 L36292-2 9/3/200B 9/3/200S Water TBE H3 pCilml 1.26E+01 1.64E+01 1.73E+00 15.0 0.77 YES N/A PBOB-02B23 L370B3 L370S3 11/61200B Water TBE Cs-137 pCi/g 1.44E+00 1.46E+00 B.70E-02 33.0 0.99 YES N/A PBOB-02B23 L370B3 L370S3 11/6/200B Water TBE H3 pCi/ml 4.03E+02 4.6BE+02 3.S7E+01 21.0 0.B6 YES N/A PBOB-02B24 L370S3 11/61200S Water TBE Cs-137 pCi/g 7.17E-01 7.50E-01 6.00E-02 24.0 0.96 YES N/A PBOS-02B24 PBOB-02B24 L370S3 L370B3 11/6/200B Water TBE H3 pCi/ml 1.27E+03 1.45E+03 1.22E+02 21.0 O.BS O.SS YES N/A Note: TAlSTL - Test America/Sevem-Trent Laboratory TBE - Teledyne Brown Engineering 20

I~------------------------------~

I TABLES 1&2 - NOTES To determine agreement:

I 1. The original result is divided by its associated one sigma uncertainty to obtain the resolution.

2. The original result is then divided by the corresponding replicate result to obtain the ratio.

I 3. The measurement is in agreement if the value of the ratio falls within the limits shown in Table 3 for the corresponding resolution. The criteria are similar to those listed in USNRC Inspection I Procedure 84750 "Radioactive Waste Treatment, and Effluent and Environmental Monitoring" with minor adjustments to account for activity concentrations with large uncertainties.

4. If both sample results are less than Minimum Detectable Activity (MDA), they are in agreement.

I When comparing a positive result to a <MDA result, the <MDA result is assumed to be positive activity and used to calculate the ratio.

5. Those sample analyses that do not agree are annotated by a "NO" answer in the "Agreement" I column. The corresponding Sample Deviation Report (SDR) number can be located in the "SDR Number" column.

I TABLE 3: SAMPLE RESOLUTION AND RATIO AGREEMENT CRITERIA RESOLUTIC~~ RATIO I <4 4-7 0.4 - 2.5 0.5 - 2.0 I 8-15 16 - 50 0.6 -1.66 0.75-1.33 I 51 - 200

>200 0.8 -1.25 0.85 -1.18 I 6.0 QUALITY CONTROL CHECKS I 6.1 A Quality Control Check is performed on the PBRF Gamma Spectroscopy Systems daily before analyzing samples and immediately after changes in electronic components that may affect system operability. The results are I compared to parameters specified in RP-021, Rev. 0, Operation and Calibration of the ORTEC Gamma Spectroscopy System. Results that are not within the prescribed ranges are investigated prior to placing the system in operation. A total I of 615 Quality Control Checks were performed during this period. No deficiencies were noted.

I 6.2 A system normalization and calibration using flame-sealed unquenched Carbon-14, Tritium, and background reference standards traceable to the National Institute of Standards (NIST) is performed on the PBRF Liquid Scintillation Carbon I Analyzer daily before analyzing samples and immediately after changes in electronic components that may affect system operability. The results are compared to parameters specified in RP-020, Rev. 0, Packard TriCarb 2900 TR I Liquid Scintillation Analyzer. Results that are not within the prescribed ranges are I 21

~------------------------------~

I~------------------------------~

I investigated prior to placing the system in operation. A total of 204 system normalization and calibrations were performed. No deficiencies were noted.

I 6.3 Two tritium QC Check samples are analyzed on the Liquid Scintillation Analyzer with each batch of samples. The QC check samples are prepared from a NIST traceable tritium source solution and scintillation cocktail. One QC Check sample I is placed before the sample set and one is placed after the sample set. Tritium QC check samples were analyzed in 227 sample batches during this report period.

No deficiencies were noted.

I

7.0 BACKGROUND

DETERMINATIONS I 7.1 A background check is performed on the Gamma Spectroscopy Systems at least daily as required by procedure PBRF-RP-021, Rev. 2, Operation and Calibration of the ORTEC Gamma Spectroscopy System. Background determinations are I used to ensure that the counting environment is free of contamination.

Background results are plotted daily to observe trends and unusual results. A total of 615 background checks were performed on the PBRF Gamma Spectroscopy I Systems during this report period. All background checks were performed satisfactorily. No deficiencies were noted.

I 7.2 A background reference sample is analyzed daily prior to sample counting to calculate the figure of merit (FOIVI) quench indicating parameter (QIP) of E2/B.

This value is used to determine counting efficiency.

I 7.3 Two background samples are analyzed on the Liquid Scintillation Analyzer with each batch of samples. The background samples are prepared with de-ionized I water and scintillation cocktail. One background sample is placed before the sample set and one is placed after the sample set. Results are used to subtract a background count from the sample count and calculate an MDA. Background I samples were analyzed in 227 sample batches during this report period. No deficiencies were noted.

I 8.0 BLANK SAMPLE ANALYSIS 8.1 Sample Processing Facility and Laboratory Technicians prepare blank samples I during the processing of regular samples in accordance with RP-060. The analysis of blank samples ensures that measurement error is not the result of contamination of sampling equipment or processing techniques. The acceptance I criteria for blank sample results are no detectable PBRF related activity above the target Minimum Detectable Activity (MDA).

I 8.1.1 A total of 29 Gamma Spectroscopy Analyses were performed on 29 blank samples during this report period. No PBRF related gamma activity was detected in any blank sample above the analysis MDA.

I 8.1.2 A total of 227 tritium analyses were performed on 227 blank samples during this report period. No tritium activity was observed in any blank I sample above the analysis MDA.

I 22

I~------------------------------~

I 9.0 CROSS-CHECK PROGRAM 9.1 PBRF participates in the United States Department of Energy (DOE) Mixed I Analyte Performance Evaluation Program (MAPEP). MAPEP Series 18 was issued in January 2008 and resulted in a Co-60 failure on the MaS (soil) sample and a Co-60 failure on the RdF (filter) sample. Co-60 was incorrectly identified in I the MaS sample, when in fact it was not present above the analysis sensitivity.

Co-60 was reported outside the acceptance range (> 30%) of the reference value and Cs-137 was> 20% for the RdF sample. A replicate analysis performed on I these results was in agreement with the reference values. The remaining results were within the acceptance range for each sample matrix. Series 19 was issued in August 2008. All reported results were within the acceptance range for each I sample matrix. MAPEP Series results are shown in Attachment B.

9.2 Tritium cross-check samples obtained from Eckert & Ziegler Analytics were I analyzed in January and July. Each sample was analyzed multiple times to reduce the counting uncertainty. The average of these analysis and uncertainties are then reported to Eckert & Ziegler Analytics. The cross-check sample results I were within the acceptable range of the standard for both series. Cross-check results are shown in Attachment B.

I 10.0 LABORATORY/SAMPLE DEVIATION REPORTS 10.1 A Laboratory/Sample Deviation Report (SDR) provides a method to document I sampling or sample analysis conditions that are adverse to quality. The identification of the condition adverse to quality, the cause of the condition, and the corrective action taken are documented and reported to the appropriate levels I of management.

10.2 Each SDR is completed in accordance with procedure RP-060, PBRF I Radiological Laboratory Quality Assurance/Quality Control Program.

10.3 A total of 4 SDRs were completed during this report period. Each incident was I investigated by the Laboratory Manager and corrective actions were addressed and all SDRs were closed. A copy of each SDR is provided in Attachment A. The SDRs consisted of the following:

I

  • SDR-08-001 - MAPEP MaS-18 Co-60 failure
  • SDR-08-002 - MAPEP RdF-18 Co-60 failure and Cs-137 waming I
  • SDR-08-003 - K-40 replicate not in agreement I 11.0 ATTACHMENTS SDR-08-004 - K-40 replicate not in agreement I A.

B.

Sample Deviation Reports Cross-Check Reports I

I 23

~----------------------------~

I I

I I

I I

I Attachment A I Sample Deviation Reports I

I I

I I

I I

I I

I I 24

I~------------------------------~

I EXHIBIT 2 I SAMPLE DEVIATION REPORT I SAMPLE LOCATION/DESCRIPTION MAPEP MaS-18 Co-GO failure REPORT NUMBER SDR-08-001 I INSTRUMENT (Check One)

Gross Alpha/Beta D Liq. Scinto D Gamma Spec. r8:I Serial # Detector #1 #2 #3 I SAMPLE TYPE (Check One)

I Soil r8:I Water/Liquid D PlanchetD Concrete Debris D Other D SAMPLE START DATEITIME SAMPLE STOP DATEITIME I

I 2/4/08 111 :05 I N/A I ANALYTICAL PROBLEM MAPEP MaS-18 Soil sample results were in excess of the Co-GO reference value. The reported value was 14.3 Bq/kg and the reference value was 2.9 Bq/kg. As this was a sensitivity test for Co-GO, no acceptance range is given.

I I

I CORRECTIVE ACTIONS AND/OR COMMENTS A review of the gamma spectroscopy analysis for this sample revealed that the Co-50 1332 peak was not present I in the spectrum. Since the Gamma Vision library recognized the 1173 peak, it associated the region counts with Co-GO and reported an incorrect activity. This is not the library that is normally used to analyze PBRF soil samples,

  • but was used for MAPEP since the results are reported in Becquerels. The library was corrected to require both
  • peaks to be present to identify Co-GO in a sample.

I

  • I Submitted By: (Print/Sign) R. Case DATE 8/13/08 I Radiological Laboratory Manager (Print/Sign) R. Case DATE 8/13/08 DATE 8/13/08 NASA Project RSO (PrintlSign) W. Stoner I

I 25 I

I~------------------------------~ EXHIBIT 2 I

I SAMPLE LOCATION/DESCRIPTION SAMPLE DEVIA DEVIAnON nON REPORT I REPORT NUMBER I MAPEP RdF-18 Co-60 failure and Cs-137 warning I

SDR-08-002 INSTRUMENT (Check One)

I Gross Alpha/Beta D Liq. Scinto D Gamma Spec. [8] Serial # Detector #1 #2 #3 I . SAMPLE TYPE (Check One)

SoUD Water/Liquid D PlanchetD Concrete Debris D Other [8] Air Filter I SAMPLE START DA*rE/TIME SAMPLE STOP DATEITIME I ANALYTICAL PROBLEM 2/4/08/14:27 N/A I MAPEP RdF-18 Air filter Co-60 sample result was> 30% (48.9%) of the reference value and Cs-137 was >20%

(28.9%) of the reference value. The reported value for Co-60 was 1.95 +/-0.33 8q/sample and the reference value was 1.318q/sample. The reported value for Cs-137 was 3.48 +/-0.5 8q1sample and the reference value was 2.70 8q/sample.

I I

CORRECTIVE ACTIONS ANDIOR COMMENTS I The reported values are the numerical average for each nuclide of 5 trials. The standard deviation in the trial set is 0.6 8q for Co-60 and 0.7 8q for Cs-137. A replicate analysis was performed on these results. 80th the Co-60 and Cs-137 results were in agreement with the MAPEP reference values. The sample analYSis process for this I geometry was observed by the Laboratory Manager and no discrepancies were found. The samples were analyzed for 1000 seconds which is typical for this sample type. However, a significantly longer count time will improve the uncertainty and should result in a smaller variance between sample trials. Subsequent MAPEP filter samples will I be given a 43,200 second count time.

Submitted By: (Print/Sign) R. Case DATE 8/13/08 I Radiological Laboratory Manager (Print/Sign) R. Case DATE 8/13/08 I NASA Project RSO (Print/Sign) W. Stoner DATE 8/13/08 I

I I 26

I EXHIBIT 2 I SAMPLE DEVIATION REPORT I i SAMPLE LOCATION/DESCRIPTION REPORT NUMBER I INSTRUMENT (Check One)

PB08-02340 K-40 not in agreement SDR-08-003 I Gross Alpha/Beta D Liq. Scinto D Gamma Spec. [ZJ Serial # Detector #3 & #1 SAMPLE TYPE (Check One)

I Soil D Water/Liquid D PlanchetD Concrete Debris D Other [ZJ Concrete Core I SAMPLE START DATEITIME SAMPLE STOP DATEITIME 8/21/08/10:48 N/A I ANALYTICAL PROBLEM I

PB08-02340 K-40 (12.6+/-3 pCi/g) replicate analysis not in agreement with PB08-02343 recount (6.5+/-2 pCi/g) on I Detector #1.

I I CORRECTIVE ACTIONS AND/OR COMMENTS Sample was recounted on Detectors #1 & #2 (PB08-02500 & PB08-02501). The K-40 results (pCi/g) were in I agreement on both counts with the original result and with each other.

Detector Original Replicate 2 Sigma Resolution Ratio Agreement Original 1.26E+01 6.50E+OO 3.00E+OO 8.0 1.94 No I Det#1 &#2 Oet#1 &#3 Oet#1 & Oet#1 8.40E+OO 8.40E+00 8.40E+00 9.40E+OO 1.26E+01 6.50E+OO 2.20E+00 2.20E+OO 2.20E+00 8.0 8.0 8.0 0.89 0.67 1.29 Yes Yes Yes Det#2 & Oet#1 1.2SE+01 9.40E+OO 3.00E+00 8.0 I 1.34 Yes I The differences in the results are not statistically significant within the variability of the time of measurement uncertainty. No further action is required.

I Submitted By: (Print/Sign) R. Case DATE 9/9/08 I  : Radiological Laboratory Manager (Print/Sign) R. Case DATE 9/9/08 NASA Project RSO (Print/Sign) W. Stoner DATE 9/9/08 I

I 27 I

I~----------------------------~ EXHIBIT 2 I

SAMPLE DEVIATION REPORT I SAMPLE LOCATION/DESCRIPTION REPORT NUMBER I PBOS"()2960 K-40 not in agreement SDR-OS-004 INSTRUMENT (Check One)

I Gross Alpha/Beta 0 Liq. Scinto Gamma Spec. [gI Serial # Detector #2 & #1 I SAMPLE TYPE (Check One)

Soil [gI WaterlLiquid Planchet 0 Concrete Debris 0 Other 0 Concrete Core I SAMPLE START DATErrlME SAMPLE STOP DATEfTlME 12/11/0S/12:54 NIA I i ANALYTICAL PROBLEM PB08"()2960 K-40 (1.7+/-0.72 pCi/g) replicate analysis count on Detector #2 not in agreement with PBOS"()2961 I recount (10.0+/-2 pCilg) on Detector #1.

I I CORRECTIVE ACTIONS ANDIOR COMMENTS The sample was re-analyzed on Detectors 1,2, and 3 with the following K-40 results:

I Detector 1 Detector 2 Detector 3 I 10.1+/-1.7 10.1+/-1.9 9.99+/-1.8 I

Agreement was obtained between all three detectors. No further action is required.

I I Submitted By: (Print/Sign) R. Case DATE: 117/09 DATE: 117/09 I Radiological Laboratory Manager (Print/Sign)

NASA Project RSO (Print/Sign) W. Stoner R. Case DATE: 117109 I

I I 28

I I

I I

I I

I Attachment B Cross-Check Reports I

I I

I I

I I

I I

I I

29 I

o o

o PEP Analyte Mixed Analy1e Performance Evaluat on ProtJraIT1 Pro~ram o Laborotory Rssult.! For MAPEP Series 18 LaboroJory NASA P"um P um Brook Reactor Faciliiy 6100 Columbus Cohmbus Ave Facility Lab (PBRF01) o Sandusl:y, OH 44870 Sandusl]',

~L\PEP-3i

~L\PIP-Oi - ~hS18:

Inom;mic Inon!4Illc

~laS18: &idio\ogic:ll,

&!d:iologica~ inorganic ;llld semi-,*oi:ltile ol'ganics combined soil and Semi-yol:ltile standard 5 0il sTandard units:

Units: (mgikg)

(mg kg) o Analyre Analyte Antimony AnIimooy Resul NR Ref Vahre Flag li:abJe 23.a 23_~

Rag Nores Bils Bill Ac:aptance Aa:eptmce Range BaDge 166.5-30'_6 5 -30.6 Unc L'nc Yalm:

~ame Ell" line Eagc o Arser5c Barium Beryllium Berylium Cadmium NR NR NR NR 20 2 202 244 13_B 13.B 9.49' Q.4G 14.1 14_1 -20.

171

-26.3

-317 171-317 9] -17.9 9]-lHI 6.64-12,34 6.64-12.34 3

o Chromum CobII Cobalt Copper l ead lead NR NR NR NR 70_7 70.7 4 1.5 4U:

B7_0 87.0 79 49 2{j

.5- 91 .9 4~L5-zg 11-54.

-54.0

.9 0

_Q - 1l3.1 eo .9-55-103 55 1 3_1

-103 o Merot.y Merou.ry ickel Selenium Sillierr S

NR NR NR NR

< .04

<0.04 145 4.44

~A 1r.!.4 1 02 -1 Bg 102-1 ~

3.1111 -5.77 3.

64

-5_77

.7 -1 20.1 64.7-1Zn.l o Thanium Thallium Van.-fum Vanadium Zin<:

Zill<:

raniu m-T~ ocaI NR NR NR NR

<< 1.0'

< 1.0 16 1611 319 12.0 12.0' 113-2[}g 113-209 223-4 15 8 .4 -15.6 o

ranium-lJfwI* m-238 Ufwlillm-238 NR 11 .9 11.9 8_3-15.5 8.3-1 5.5 ranillm-235 NR (l.O75 Q.075 0.0'53 - O.OQB 0.053-0.mlB o Ormnc Oreamc Analyre Resul Result NR Ref Vaws:

VIIWf Fblg Flag Notes z-Ac epta:nce Acceptance

B..Iwgs:
B.allge 25_6-195_7 25.0 -1 Q5.7 Units (ugl:g)

(Ul,l:g)

Unc Unc Vawe Flag VaWf o

de!til~H C defta~HC 11 0 .6 110.6 beta-8HC NR 18.33 1.83 -43.94

.83-43.B4 gamma-BHC (Undane) gamrna-SHC NR lB.OO 1.80-40.

1.80'-46.56 56 4.4'-ODT 4.-I'-DDT NR 10 1.7 101.7 25.3 -178 .1 25.3-178.

NR 3.59 - 72.57 3.59- 7257 o

Diadrin Dieklrin 35.86 Heptachlor HeptachlCf" NR 7.5 1 0.75-115.83 0.75- 5.83 Nilphthalene NaphthalenE NR 3524 1010-6008 1010'-6038 Acenap thene AoItnaphlhene NR 231 9 2319 724 -3914 724-3914 NR o

Anthracene 2270 2270' 664-3877 Benzo(a:l3f1wKene Benzo(a:tM1lhracene NR 707 7 7 177 -1237 177-1237 Benzo(k )IluolillnfMne Benzo(k)IIuorarnh4!ne NR 3330 3330' 1150 -55 11 1150'-5511 2-O\Ioronaphthaiene 2 -011oronapnthalene NR 27ge 2795 815-4n4 81 5 -4n4 o Issued 4123:

4/23: _008 Pa;e 1 of4 PriD!ed PriJIred 4mI2OO3 4mI2OO&

o o

o 30

o o R.;I!liolol:ical Aual;.,e Analyte R"~lIh RIMtlr R~r

\\ *i!.lm~

'a1ne Flag :t\otel.

Flag. Note!> Bias Bi3S Acceptance Ballg~

Rallll!:

[!I1J I~

Uue Uuc (Rcr l:>J.l Uue

l'alni: fl3~
l'allli: E1311 o

Americium-241 124 127.2 A -2.5 89.0 - 165.4 7.7 Cesium-l34 Ce5ium-l34 NR 854 598-1110 598 - 1110 Cesium-137 548 545 A 0.6 382 - 709 13.4 L Cobalt*57 426 421 A 1.2 295-547 295 - 547 82 L o

Cobalt-60 Coball-60 14.3 2.9 (4 ) 2.78 Iron*55 NR 390 273*507 Manganese-54 NR 570 399* 741 Nickel-63 Nickel*63 NR 640 448-832 Plutonium-238 NR 728 51.0-94.6 o Plutonium*2391240 Plutonium-2391240 Potassium-40 Strontium*90 Strontium* 90 Technetium-99 NR NR NR NR 90.1 571 493 273 63.1*117.1 400- 742 400-742 345-641 191-355 o Uranium-234i233 Uranium-2341233 Uranium-238 Zinc-65 NR NR NR 142 148 99-185 104-192 o .\ J.\I'U'-1I7-\b\\ J{atliulul:iull, inuI!!ani, l\I'U'-1I7- \b\\ Ill : l{adiulul!ic:I[, iour!!"nic U)mlJill~tI ,,,,t~I' o>mlJill~t.I "alcl' ,1:lIlllanl

,(miliant o 11loru~ll1c luolumne Rd Ref Acceptance Acceptauce Ulli,, : (1I1jl.

Unih Une Uue (l11)!.' LI Ulle Une Li o An.,lyte Analyte Amertcium-241 Americium-241 Cesium-l34 Cesium* l34 Cesium*137 Ce5ium*137 R~lth Result NR NR NR

l'~I!l~

~-aht~

1.23 Flail :t\ot~

RW NQt~

(11)

Bi:tS Rall~

Rru.J~

0.86*1.60 0.86*1 .60 rallll:;

)'1I11l!: Elaa flllil o Coball-57 Cobalt-57 Cobalt-60 Hydrogen-3 Iron-55 24 8.9 NR NR 22.8 8.40 472 36.5 A

A 5.3 6.0 16.0-29.6 5.88*10.92 330-614 25.6-47.5 0.97 0.74 o

Manganese-54 NR 12.1 8.5-15.7 Nickel*63 NR 30.7 21.5*39.9 Plutonium-238 NR 073 0.51 --0.95 0.95 Plutonium-239J240 NR 0.0141 Strontium-go Strontium-SO NR 11 .40 11.40 7.98 -14.82

-14 .82 o T echnetium-99 Technetlum-99 Uranium*2341233 lkanium*234J233 Uranium*238 Zinc-65 NR NR NR NR 11.2 3.63 3.74 16.3 7.8-14.6 2.54-4 2.54 2.62-4.86 2.62-4.88 11.4-21.2

.72

- 4.72 11.4 - 21.2 o

o \IAPEP-07-Rdnll : l{:lCtiolul!ical

\IAPEP-07-Rtln8 RaurololllcaJ Raurolo lesl It:uliolul:ical "ir air lilll'r Ref Acceptance Acce)1t~lIce IBq sallt l""1 UlIIls 18'15:UIII'I.,)

UUlts Uue Uue o Annlyte Americium*241 Cesium* 134 Cesium-137 Re!,u Re;,t tllll NR NR 3.48

\'llll.l~

Vall.li:

0.158 2.52 2.70 Flag Flag.

W

'ates ates Bin.,

BiA!'

28.9

&1Ll!l~

R.11l1!~

0.111-0.205 1.76*3.28 1.89*3.51 1.89

  • 3.51
alm
flag
l-alm:

0.50 flail o Cobalt-57 CobaIt-60 Coball-60 Manganese.54 Manganese*54 Plutonium-238 3.76 1.95 NR NR NR 3.55 1.31 0.1053 A 5.9 48.9 2.49 *4*4.62 0.92*1.70

.62 0.0737 - 0.1369 0.0799*0.1483 0.34 0.33 o

Plutonium-239i240 Plutonium-239J240 NR 0.1141 Strontium-go Strontium-SO NR 1.548 1.084-2.012 Uranium-234/233 NR 0.218 0.153*0.283 Uranium-238 NR 0.225 0.158-0.293 Zinc-65 NR 2.04 1.43-2.65 o

o 31

Dq.or1l1UlOlI ot DelAlllm01l of Elle'!lY PEP Euef!1Y RE. lL - 19<<

Mixed Analyle 19<~ F"'"101l1 Fremonl A,,,-

A\ e.

Analyte Performance Evaluation Program

~[S 11 J9 -. lu.wu

~!S-llJ'I hJ.lltu fFall aU..... ID ~.q S3~ I; Ij LabomlOlT LabomrolT RI'. R<,.w

\JITr5 l r5 Fo/' '\L~PEP Serif's For .\L-IPEP Series 19 (PBRFOl) NASA PhWl Brook Reactor Fncility Lab (PBRF01) 6100 CO hWll>us Ave COhWll>us SaudniJ..-y.

Salldn>l..-y. OH --1--1870 44SiO

'IL\PEI'*
\1.\PEI'*HH IIH-:\laSJ.,: [{udiuloeic~l, inoreanic

\laSI'1 : Rudillioeicul, jno~l:anic and "mi* \ulalile organic, "mi-\IlI.llile Ilr!:"oi" comlJin~11 ,,,il ,landanl

,,,;1 ,I:mdanl IlllHl!amc IuoTl!awc  !;llIb' (Ulit lau 1:1I11~ : {UIll. kV.1 R?dlOlol!lcal L'IIII~ (B, kgl Ref AcceptaJlce Acceptauce Vueue Uue

  • Anal)-1!!

..Iuutlyte Resu.

Resulth ,,>:'alll!: Flag ~(\tc flag Notess Bins BIllS IJ~

Iljle \' IleJ.la8..

V,~ hle...£lag..

Americium-241 72.0 69.1 A 4.2 48.4-89.8 1.35 L Antimony-125 Anlimony-125 NR 22.8 22 .8 16.0-29.6 Cesium-l34 NR 581 407 -755 Cesium-137 3.67 2.8 A 0.54 Cobalt-57 NR 333 233-433 Cobalt-60 148.0 145 A 2.1 2.1 102-189 242 2.42 L Iron*55 Iron-55 NR 676 473-879 Manganese-54 NR 415 291 540 291-540 Nickel-63 NR 760 532*

532- 988 Plutonium-238 NR Plulonium-2391240 Plutonium-2391240 NR 55.6 38.9* 72.3 38.9-72.3 Polassium-40 Potassium-40 NR 570 399-741 Strontium-90 NR Technetium-99 NR 335 235-436 Uranium-2341 Uranium-234 f233 233 NR 292 204-380 Uranium-238 NR 303 212-394 Zinc-65 NR RW (1 1i)

(11 Rm/i";I'gu',)/ R4",.,?II(/' ['Ilfo" R(/d;""'glC'll/IIt?[i-"*i?llrt* [\111,,* A Ugll.l I J.

AI/glill I, :f/O~

f}() ~
\I.\I'EI'-1l8*
\I.\I'I, J., : IbdiulogK:JI,
'II:.I\\ 1:

I'-UH -\I:J\\ lRorg:mlC wmlJim'd l{adlUlogl<:II, IRore:tnlC cl>nt!Jlm'd ""I~r 'I~ndanl

'I~r illol aatne luOHlatJ1C llIlIltS: (H.!!. 1.)

!Ilils' (Ill!!. I.)

Radwlo'lICnl R,,,hnlu'l.Icnl L'uJls.

UUli.;;. rB'I'l_l (Bq 1_1 R<'f Ref Acc~ptnllct' Acccpronce Uue Uuc line AIm lyre

.-\JJnlyTe Result Resu lt  :-"ah!5:

l'al!!!; Flo!! NOI!!s ores Bia, Bias B.all~

RaD~ Ela~

'-.-ollJ~ Elall
l:'ollll!

Americium-241 NR Cesium-l34 NR 19.5 13.7 - 25.4 Cesium-137 CHium-137 24.1 23.6 A 2.1 16.5 - 30.7 0.46 L Cobal.I-57 Cobalt-57 NR RW (11 )

~t-60 Col).lt-60 11.2 11 .6 A -3.4 8.1-15.1 8.1-15.1 0.23 L Hydrogen-3 NR 341 239-443 o

Iron-55 Iron*55 NR 46.2 32.3- 60.1 Manganese-54 NR 13.7 9.6-17.8 Nickel-63 NR Plulonium-238 Plut.onium-238 NR 0.5 Q.4 - 0.7 0.4 Plu1onium-2391240 Plutonium-239/240 NR o Strontium-90 Technelium-99 echnetium-99 Uranium-2341 Uranium-234f233 Uranium-238 233 NR NR NR NR 645 3.76 3.44 3.55 4.52- 8.39 2.63-4.89 2.41-4.47 2.49-4.62 o Zinc-65 NR 17.1

.,1

/(JI./W/I)gll "I R RlidlO/iJgli 12.0- 22.222 .2

..(t'I'I*"(,('I' Of//('

R.*{t,,,,"1< .~ lIgll.'l I. ~(I()~

lJ,,/(' .llIgml ~(J(J.~

o o

o 32

I~----------------------------~

Eckert&Ziegler I Analytics 1380 Suboird InduslNIIIM
I.

Atlanta. GeoIgia 30318' U.s.A.

I Tel Fax 404>352-8677 404' 35:1-2137 404'35:1-2137 I RESULTS OF ENVIRONMENTAL I CROSS CHECK PROGRAM I NASA I Plum Brook Reactor Facility I Fourth Quarter 2007 (Ref. Date 12/06/2007)

I {f() ~ l-iJ..at Daniel M. Mon omery, QA Manager I

I I

SAMPLE ANALYSIS I NASAPBRF VALUE UNCERTAINTY (I Sigma)

ANALYTICS VALVE UNCERTAINTY (I Sigma)

RATIO NASAPBRF:

ANALYTICS I 1554,.792 H-3 H*3 8.85Efil3 pCiIL 1.63Efil3 9.02Efil3 prilL 1.51Efil2 0.98 Water

,.,***** **********,.,t*

I I Analysis performed 1/9/2008 I

I I 33

I I *- Eckert & Ziegler Analyll(s 1110 ~_a lnCII.,t*.- _

I ~~

r"

~..

(J<<Io1Jloi JOll.* U ~ "

~. }~]*""n

~'lSl'l')1 I RESULTS OF ENVIRONMENTAt I CROSS CHECK PROGRAM I NASA I Plum Brook Reactor Facility I Second Quarter 2008 (Ref. Date 06-19-2008)

I I

I I SAMPLE A."\ALYSIS NASAPBR..

NASAPBR..

VALUE UNCERTAINTY (2 Sigma)

ANALYTlCS VALUE llNCERTAINTY (1 Siama)

RATIO NASA POlf:

ANALYTlCS I E6056-192 8*3 t J8E+04 pCiIL t.78E~3 1.30[+04 pCiIL 2.17E~2 1.06 8-3 I Waler

                • *., *** *w **************** *********.**************.*** **

I I I Analysis performed 7/1812008 I

I I 34