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{{#Wiki_filter:OAK RIDGE INSTITUTE FOR SCIENCE AND EDUCATION Distribution approval and concurrence
{{#Wiki_filter:OAK RIDGE INSTITUTE FOR SCIENCE AND EDUCATION hlarch 31, 2008 hlr. WiUlam Snell U.S. Nuclear Regulatory Commission Regon I11 2443 Warrenvdle Road Lisle, IL 60532-4351
: Technical hlanagement Team Member Quality Manager hlarch 31, 2008 Initials A -r hlr. W'iUlam Snell U.S. Nuclear Regulatory Commission Regon I11 2443 Warrenvdle Road Lisle, IL 60532-4351  


==SUBJECT:==
==SUBJECT:==
LETTER REPORT FOR 23 WATER SAMPLES FROM THE VICINITY OF THE BRAIDWOOD NUCLEAR GENERATING STATION, BRAIDWOOD, ILLINOIS
LETTER REPORT FOR 23 WATER SAMPLES FROM T H E VICINITY OF T H E BRAIDWOOD NUCLEAR GENERATING STATION, BRAIDWOOD, ILLINOIS
[INSPECTION REPORT NO. 050-00456/2007-0061 (RFTA NO. 07-005) DCN: 1766-LR-01-0  
[INSPECTION REPORT NO. 050-00456/2007-0061 (RFTA NO. 07-005)
DCN: 1766-LR-01-0


==Dear Mr. Snell:==
==Dear Mr. Snell:==


The Oak hdge Institute for Science and Education (ORISE) received 23 water samples associated with the Braidwood Nuclear Generating Station on December 28,2007.
The Oak h d g e Institute for Science and Education (ORISE) received 23 water samples associated with the Braidwood Nuclear Generating Station on December 28,2007. The sample analysis was delayed until authorization was received from the Office of Nuclear Reactor Regulation on February 29, 2008.
The sample analysis was delayed until authorization was received from the Office of Nuclear Reactor Regulation on February 29, 2008. The samples were analyzed for tritium to an averaged minimum detectable concentration of 180 pCi/L using a liquid scindation analyzer.
The samples were analyzed for tritium to an averaged minimum detectable concentration of 180 pCi/L using a liquid scindation analyzer. The sample identifications and collection data are presented in Table 1. The tritium data are presented in Table 2. The pertinent procedure references are provided in the specific tables.
The sample identifications and collection data are presented in Table 1. The tritium data are presented in Table 2. The pertinent procedure references are provided in the specific tables.
ORISEs Quality Control (QC) requirements were met for these analyses. The QC files are available for your review upon request.
ORISE's Quality Control (QC) requirements were met for these analyses.
hly contact information is listed below. You may also contact Wade Ivey at 865.576.9184 with any questions or comments.
The QC files are available for your review upon request. hly contact information is listed below. You may also contact Wade Ivey at 865.576.9184 with any questions or comments.
Sincerely, Dale Condra, Manager Laboratory RDC:\WI:km Enclosures C:       T. Carter, NRC/FSME/DWMEP T-8F5                           E. Abelquist, ORISE E. & o x - D a h , NRC/NMSS/TWFN 8A23                     S. Roberts, ORISE File 1766 Distribution approval and concurrence :      Initials  A Technical hlanagement Team Member Quality Manager                                    -r Voice: 865.241.3242                   Fax: 865.41.3248               E-mail: Dale.Condra@orau.org RECEIVED APR 0 3 2008
Sincerely, Dale Condra, Manager Laboratory RDC:\WI:km Enclosures C: T. Carter, NRC/FSME/DWMEP T-8F5 E. &ox-Dah, NRC/NMSS/TWFN 8A23 File 1766 E. Abelquist, ORISE S. Roberts, ORISE Voice: 865.241.3242 Fax: 865.41.3248 E-mail: Dale.Condra@orau.org RECEIVED APR 0 3 2008 TABLE 1 SAMPLE IDENTIFICATIONS AND COLLECTION DATA BRAIDWOOD NUCLEAR GENERATING STATION BRAIDWOOD, ILLINOIS Collection Date Braldmood Nuclear Generaung Station 1766-1.R-01-0 TABLE 2 ORISE Sample ID TRITIUM CONCENTRATIONS IN WATER SAMPLES BY LIQUID SCINTILLATION ANALYSIS AP2, REVISION 16 AND CP4, REVISION 3 BRAIDWOOD NUCLEAR GENERATING STATION BRAIDWOOD, ILLINOIS NRC Region I11 Tritium Concentrations Sample ID (PCi/L) 1766WOOOl 1766W0002 BD-07-6-01 17,130 f 8309 , 180b BD-07-6-02 10 +_ 110 , 180 1766W0003 I BD-07-6-03 I 170 t 110 , 180 1766W0004 1766W0005 BD-07-6-04 90 f 110 , 180 BD-07-6-05 110 f 110 , 180 1766W0006 I BD-07-6-06 I 40 t 110 , 180 1766W0007 1766W0008 1766W0009 BD-07-6-07 80 f 110 , 180 BD-07-6-08 130 f 110 , 180 BD-07-6-09 440 f 120 , 180 1766W0010 I BD-07-6-10 I 3,670 +_ 250 , 180 1766W0011 1766W0012
 
~ ~~ ~~~ BD-07-6-11 8,110 440 , 180 BD-07-6-12 3,630 2 250 , 180 1766W0013 1 BD-07-6-13 I 10 & 110 , 180 1766W0014 1766W0015 1766W0016 BD-07-6-14 260 f 110 , 180 BD-07-6-15 70 f 110 , 180 BD-07-6-16 4,780 f 290 , 180 1766W0017 I BD-07-6-17 I 250 f 110 , 170 1766W0018 1766W0019 1766W0020 BD-07-6-18 1,260 f 150 , 170 BD-07-6-19 560 f 120 , 170 BD-07-6-20 100 f 100 , 170 1766W0021 I BD-07-6-21 1 120 +_ 100 , 170 1766W0022 1766W0023
TABLE 1 SAMPLE IDENTIFICATIONS AND COLLECTION DATA BRAIDWOOD NUCLEAR GENERATING STATION BRAIDWOOD, ILLINOIS Collection Date Braldmood Nuclear Generaung Station                             1766-1.R-01-0
~ ~~ ~ BD-07-6-22 350 f 110 , 170 BD-07-6-23 530 120 , 170 dUncertaintics represent the 95% confidence level, based on total propagated uncertainties.
 
bXI1lCs arc prcsentcd after the comma. Urdu-ood Nuclear Gencrating Stanon}}
TABLE 2 TRITIUM CONCENTRATIONS IN WATER SAMPLES BY LIQUID SCINTILLATION ANALYSIS AP2, REVISION 16 AND CP4, REVISION 3 BRAIDWOOD NUCLEAR GENERATING STATION BRAIDWOOD, ILLINOIS ORISE                  NRC Region I11             Tritium Concentrations Sample ID                       Sample ID                        (PCi/L) 1766WOOOl                       BD-07-6-01             17,130 f 8309 , 180b 1766W0002                      BD-07-6-02                   10 +_ 110 , 180 1766W0003             I       BD-07-6-03       I         170   t   110 , 180 1766W0004                       BD-07-6-04                 90 f 110 , 180 1766W0005                      BD-07-6-05                 110 f 110 , 180 1766W0006             I       BD-07-6-06       I         40   t   110 , 180 1766W0007                       BD-07-6-07                 80 f 110 , 180 1766W0008                      BD-07-6-08                 130 f 110 , 180 1766W0009                      BD-07-6-09                 440 f 120 , 180 1766W0010             I       BD-07-6-10
                                                                            ~
I ~~
3,670 +_ 250 , 180
                                                                                          ~~~
1766W0011                      BD-07-6-11             8,110         440 , 180 1766W0012                      BD-07-6-12             3,630 2 250 , 180 1766W0013             1       BD-07-6-13       I         10 &       110 , 180 1766W0014                       BD-07-6-14                 260 f 110 , 180 1766W0015                      BD-07-6-15                 70 f 110 , 180 1766W0016                      BD-07-6-16             4,780 f 290 , 180 1766W0017               I       BD-07-6-17       I         250 f 110 , 170 1766W0018                       BD-07-6-18               1,260 f 150 , 170 1766W0019                      BD-07-6-19                 560 f 120 , 170 1766W0020                      BD-07-6-20                 100 f 100 , 170 1766W0021               I       BD-07-6-21       1         120 +_     100 , 170
                                                                                                      ~       ~~ ~
1766W0022                      BD-07-6-22                 350 f 110 , 170 1766W0023                      BD-07-6-23                 530         120 , 170 dUncertaintics represent the 95% confidence level, based on total propagated uncertainties.
b X I 1 l C s arc prcsentcd after the comma.
U r d u - o o d Nuclear Gencrating Stanon}}

Latest revision as of 19:08, 14 November 2019

Oak Ridge Institute for Science and Education - Braidwood
ML080940398
Person / Time
Site: Braidwood Constellation icon.png
Issue date: 03/31/2008
From: Condra D
Oak Ridge Institute for Science & Education
To: Snell W
NRC/RGN-III
References
DCN 1766-LR-01-0, FOIA/PA-2010-0209, IR-07-006, RFTA 07-005
Download: ML080940398 (4)
v • d • e


Text

OAK RIDGE INSTITUTE FOR SCIENCE AND EDUCATION hlarch 31, 2008 hlr. WiUlam Snell U.S. Nuclear Regulatory Commission Regon I11 2443 Warrenvdle Road Lisle, IL 60532-4351

SUBJECT:

LETTER REPORT FOR 23 WATER SAMPLES FROM T H E VICINITY OF T H E BRAIDWOOD NUCLEAR GENERATING STATION, BRAIDWOOD, ILLINOIS

[INSPECTION REPORT NO. 050-00456/2007-0061 (RFTA NO.07-005)

DCN: 1766-LR-01-0

Dear Mr. Snell:

The Oak h d g e Institute for Science and Education (ORISE) received 23 water samples associated with the Braidwood Nuclear Generating Station on December 28,2007. The sample analysis was delayed until authorization was received from the Office of Nuclear Reactor Regulation on February 29, 2008.

The samples were analyzed for tritium to an averaged minimum detectable concentration of 180 pCi/L using a liquid scindation analyzer. The sample identifications and collection data are presented in Table 1. The tritium data are presented in Table 2. The pertinent procedure references are provided in the specific tables.

ORISEs Quality Control (QC) requirements were met for these analyses. The QC files are available for your review upon request.

hly contact information is listed below. You may also contact Wade Ivey at 865.576.9184 with any questions or comments.

Sincerely, Dale Condra, Manager Laboratory RDC:\WI:km Enclosures C: T. Carter, NRC/FSME/DWMEP T-8F5 E. Abelquist, ORISE E. & o x - D a h , NRC/NMSS/TWFN 8A23 S. Roberts, ORISE File 1766 Distribution approval and concurrence : Initials A Technical hlanagement Team Member Quality Manager -r Voice: 865.241.3242 Fax: 865.41.3248 E-mail: Dale.Condra@orau.org RECEIVED APR 0 3 2008

TABLE 1 SAMPLE IDENTIFICATIONS AND COLLECTION DATA BRAIDWOOD NUCLEAR GENERATING STATION BRAIDWOOD, ILLINOIS Collection Date Braldmood Nuclear Generaung Station 1766-1.R-01-0

TABLE 2 TRITIUM CONCENTRATIONS IN WATER SAMPLES BY LIQUID SCINTILLATION ANALYSIS AP2, REVISION 16 AND CP4, REVISION 3 BRAIDWOOD NUCLEAR GENERATING STATION BRAIDWOOD, ILLINOIS ORISE NRC Region I11 Tritium Concentrations Sample ID Sample ID (PCi/L) 1766WOOOl BD-07-6-01 17,130 f 8309 , 180b 1766W0002 BD-07-6-02 10 +_ 110 , 180 1766W0003 I BD-07-6-03 I 170 t 110 , 180 1766W0004 BD-07-6-04 90 f 110 , 180 1766W0005 BD-07-6-05 110 f 110 , 180 1766W0006 I BD-07-6-06 I 40 t 110 , 180 1766W0007 BD-07-6-07 80 f 110 , 180 1766W0008 BD-07-6-08 130 f 110 , 180 1766W0009 BD-07-6-09 440 f 120 , 180 1766W0010 I BD-07-6-10

~

I ~~

3,670 +_ 250 , 180

~~~

1766W0011 BD-07-6-11 8,110 440 , 180 1766W0012 BD-07-6-12 3,630 2 250 , 180 1766W0013 1 BD-07-6-13 I 10 & 110 , 180 1766W0014 BD-07-6-14 260 f 110 , 180 1766W0015 BD-07-6-15 70 f 110 , 180 1766W0016 BD-07-6-16 4,780 f 290 , 180 1766W0017 I BD-07-6-17 I 250 f 110 , 170 1766W0018 BD-07-6-18 1,260 f 150 , 170 1766W0019 BD-07-6-19 560 f 120 , 170 1766W0020 BD-07-6-20 100 f 100 , 170 1766W0021 I BD-07-6-21 1 120 +_ 100 , 170

~ ~~ ~

1766W0022 BD-07-6-22 350 f 110 , 170 1766W0023 BD-07-6-23 530 120 , 170 dUncertaintics represent the 95% confidence level, based on total propagated uncertainties.

b X I 1 l C s arc prcsentcd after the comma.

U r d u - o o d Nuclear Gencrating Stanon

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