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{{#Wiki_filter:Description Survey Unit Release Record Design # Survey Unit #(s) document constitute "Special Methods" and the survey design used in the acquisition of survey measurements.  
{{#Wiki_filter:Survey Unit Release Record Design #               EP-S 1          Revision #          Original      Page 1 of 3 Survey Unit #(s)                                             S1
: 1) Embedded Pipe (EP) Survey Unit S1 meets the definition of embedded pipe for Plum Brook Reactor Facility (PBRF).
: 2) EP S1 is a Class 1, Group 1 survey unit as per the PBRF Final Status Survey Plan (FSSP) and Technical Basis Document (TBD)-06-004.
: 3) Surveys in EP S1 were performed using a scintillation detector optimized to measure gamma energies representative of Co-60. Sample #EP 3-9 from Survey Request (SR)-13 was referenced for this decision.
: 4) Survey Instructions for this survey unit are incorporated into and performed in accordance with (IAW) the Babcock Services Incorporated (BSI)/LVS-002, Work Execution Package (WEP) 05-006. Survey instructions described in this Description document constitute "Special Methods" and the survey design used in the acquisition of survey measurements.
: 5) Instrument efficiency determinations are developed in accordance with the BSYLVS-002, WEP 05-006, these determinations are appropriate for the types of radiation involved and the media being surveyed.
: 5) Instrument efficiency determinations are developed in accordance with the BSYLVS-002, WEP 05-006, these determinations are appropriate for the types of radiation involved and the media being surveyed.
FSSICharacterization Engineer FSSICharacterization Manager EP-S 1 S 1 1) Embedded Pipe (EP) Survey Unit S1 meets the definition of embedded pipe for Plum Brook Reactor Facility (PBRF). 2) EP S1 is a Class 1, Group 1 survey unit as per the PBRF Final Status Survey Plan (FSSP) and Technical Basis Document (TBD)-06-004.
FSSICharacterization Engineer FSSICharacterization Manager
: 3) Surveys in EP S1 were performed using a scintillation detector optimized to measure gamma energies representative of Co-60. Sample #EP 3-9 from Survey Request (SR)-13 was referenced for this decision.
: 4) Survey Instructions for this survey unit are incorporated into and performed in accordance with (IAW) the Babcock Services Incorporated (BSI)/LVS-002, Work Execution Package (WEP) 05-006. Survey instructions described in this Revision # Original Page 1 of 3 FSS Design # EP S1 Revision # Original Page 2 of 3 Survey Unit: S1 1.0 History/Description 1.1 The subject pipe system is a 2" service conduit adjacent to the 1.51 drain system access box in the annulus on the -25' elevation of the Reactor Building.
1.2 EP S1 is approximately 16 feet in length.
1.3 Any contamination of this service conduit is expected to be cross contamination from the remediation e fforts of RX1.51 which is adjacent to this service conduit in a valve box on the RB -25' annulus. Service conduit S1 was open to cross contamination during those remediation efforts.
2.0 Survey Design Information 2.1 EP S1 was surveyed IAW Procedure #BSI/LVS-002.
2.2 100% of the 2" ID pipe was accessible for survey. The accessible 2" ID pipe was surveyed by static measurement at one foot increments, for a total of 16 survey measurements.
2.3 Surface area for the 2" ID piping is 486 cm 2 for each foot of piping, corresponding to a total 2" ID piping surface area of 7776 cm 2 (0.8 m 2) for the entire accessible length of (16') of 2" piping.
3.0 Survey Unit Measurement Locations/Data 3.1 Pipe interior radiological survey forms are provided in Attachment 2 of this release record.
4.0 Survey Unit Investigations/Results 4.1 None 5.0 Data Assessment Results 5.1 Data assessment results are provided in the EP/Buried Pipe (BP) Survey Report provided in Attachment 1.
5.2 All measurement results are less than the Derived Concentration Guideline Level (DCGL) for radionuclide specif ic EP that corresponds to the 1 mrem/yr dose goal established in Table 3-3 of the FSSP.
5.3 When implementing the Unity Rule, provided in Section 3.6.3 of the FSSP, and applying the Nuclide Frac tion (NF), provided in TBD-06-004, the survey unit that is constituted by EP S1 passes FSS.
5.4 Background was not subtracted from the survey measurements and the Elevated Measurement Comparison (EMC) was not employed for the accessible portion of this survey unit.


FSS Design # EP S1 Revision # Original Page 3 of 3 Survey Unit: S1 Statistical Summary Table Statistical Parameter 2" Pipe Total Number of Survey Measurements 16 Number of Measurements >MDC 9 Number of Measurements Above 50% of DCGL 0 Number of Measurements Above DCGL 0 Mean  0.023 Median  0.024 Standard Deviation 0.008 Maximum  0.036 Minimum  0.012  6.0 Documentation of evaluations pertaining to compliance with the unrestricted use limit of 25 mrem/yr and dose contributions from Embedded Pipe and  
FSS Design # EP S1                 Revision # Original                   Page 2 of 3 Survey Unit: S1 1.0    History/Description 1.1    The subject pipe system is a 2 service conduit adjacent to the 1.51 drain system access box in the annulus on the -25 elevation of the Reactor Building.
1.2    EP S1 is approximately 16 feet in length.
1.3    Any contamination of this service conduit is expected to be cross contamination from the remediation efforts of RX1.51 which is adjacent to this service conduit in a valve box on the RB -25 annulus. Service conduit S1 was open to cross contamination during those remediation efforts.
2.0    Survey Design Information 2.1    EP S1 was surveyed IAW Procedure #BSI/LVS-002.
2.2    100% of the 2 ID pipe was accessible for survey. The accessible 2 ID pipe was surveyed by static measurement at one foot increments, for a total of 16 survey measurements.
2.3    Surface area for the 2 ID piping is 486 cm2 for each foot of piping, corresponding to a total 2 ID piping surface area of 7776 cm2 (0.8 m2) for the entire accessible length of (16) of 2 piping.
3.0   Survey Unit Measurement Locations/Data 3.1    Pipe interior radiological survey forms are provided in Attachment 2 of this release record.
4.0   Survey Unit Investigations/Results 4.1    None 5.0   Data Assessment Results 5.1    Data assessment results are provided in the EP/Buried Pipe (BP) Survey Report provided in Attachment 1.
5.2    All measurement results are less than the Derived Concentration Guideline Level (DCGL) for radionuclide specific EP that corresponds to the 1 mrem/yr dose goal established in Table 3-3 of the FSSP.
5.3    When implementing the Unity Rule, provided in Section 3.6.3 of the FSSP, and applying the Nuclide Fraction (NF), provided in TBD-06-004, the survey unit that is constituted by EP S1 passes FSS.
5.4    Background was not subtracted from the survey measurements and the Elevated Measurement Comparison (EMC) was not employed for the accessible portion of this survey unit.


radionuclides contributing 10% in aggregat e of the total dose for both structural scenarios and soils.
FSS Design # EP S1                    Revision # Original                  Page 3 of 3 Survey Unit: S1 Statistical Summary Table Statistical Parameter                2 Pipe Total Number of Survey Measurements                16 Number of Measurements >MDC                      9 Number of Measurements Above 50% of DCGL                0 Number of Measurements Above DCGL                  0 Mean                          0.023 Median                        0.024 Standard Deviation                    0.008 Maximum                        0.036 Minimum                        0.012 6.0    Documentation of evaluations pertaining to compliance with the unrestricted use limit of 25 mrem/yr and dose contributions from Embedded Pipe and radionuclides contributing 10% in aggregate of the total dose for both structural scenarios and soils.
6.1 A review of the survey results has sh own that the dose contribution for the accessible portion of EP S1 to be less than 1 mrem/yr. The dose contribution is estimated to be 0.023 mrem/yr based on the average of the  
6.1     A review of the survey results has shown that the dose contribution for the accessible portion of EP S1 to be less than 1 mrem/yr. The dose contribution is estimated to be 0.023 mrem/yr based on the average of the actual gross counts.
7.0    Attachments Attachment 1 - BSI EP/BP Survey Report Attachment 2 -Pipe Interior Radiological Survey Form Attachment 3 - DQA Worksheet Attachment 4 -Disc containing RR for EP S1 & Spreadsheet


actual gross counts.
SECTION 7 ATTACHMENT 1 2 PAGES
7.0 Attachments Attachment 1 - BSI EP/BP Survey Report Attachment 2 -Pipe Interior Radiological Survey Form  Attachment 3 - DQA Worksheet Attachment 4 -Disc containing RR for EP S1 & Spreadsheet


SECTION 7 ATTACHMENT 1 2 PAGES BSI EPlBP SURVEY REPORT EP S1 2" Pipe TBD 06-004 Group 1 Measurement #gcpmncpm Co-60 activity  (total dpm)
BSI EPlBP SURVEY REPORT EP S1 2" Pipe TBD 06-004 Group 1 Measurement #
Co-60 activity (dpm/100cm2)
Co-60 activity  Co-60 activity  Cs-137 activity    Eu-152 activity  Eu-154 activity  Nb-94 activity  Ag-108m activity gcpm  ncpm    (total dpm)     (dpm/100cm2)     (dpm/100cm2)       (dpm/100cm2)     (dpm/100cm2)     (dpm/100cm2)     (dpm/100cm2)
Cs-137 activity (dpm/100cm2)
Unity 1                12    12        29,268             6,017               238               5,708           1,517               176                 42   0.036 2                9    9          21,951             4,513               179               4,281           1,138               132                 31   0.027 3                8    8          19,512             4,011               159               3,805           1,012               117                 28   0.024 4                11    11        26,829             5,515               219               5,232           1,391               161                 38   0.033 5                6    6          14,634             3,008               119               2,854             759                88                 21   0.018 6                7    7          17,073             3,510               139               3,329             885               102                 24   0.021 7                10    10        24,390             5,014               199               4,756           1,264               146                 35   0.030 8                9    9          21,951             4,513               179               4,281           1,138               132                 31   0.027 9                8    8          19,512             4,011               159               3,805           1,012               117                 28   0.024 10                5    5          12,195             2,507               99               2,378             632                73                 17   0.015 11                4    4          9,756             2,006               79               1,903             506                59                 14   0.012 12                6    6          14,634             3,008               119               2,854             759                88                 21   0.018 13                4    4          9,756             2,006               79               1,903             506                59                 14   0.012 14                8    8          19,512             4,011               159               3,805           1,012               117                 28   0.024 15                4    4          9,756             2,006               79               1,903             506                59                 14   0.012 16              11    11        26,829             5,515               219               5,232           1,391               161                 38   0.033 MEAN           0.023 MEDIAN         0.024 STD DEV         0.008 MAX           0.036 MIN         0.012 1 of 1
Eu-152 activity (dpm/100cm2)
 
Eu-154 activity (dpm/100cm2)
SECTION 7 ATTACHMENT 2 2 PAGES
Nb-94 activity (dpm/100cm2)
 
Ag-108m activity (dpm/100cm2)
                                                                              -.     BSIiLVSPipeCrawler-002 Revision 5 Pipe Interior Radiological Survey Form Date:     l-)b-V 8               Time:         1 34D Pipe JD#:     ~ $
Unity1121229,268         6,017             238               5,708             1,517             176               42                     0.03629921,951         4,513             179               4,281             1,138             132               31                     0.02738819,512         4,011             159               3,805             1,012             117               28                     0.0244111126,829         5,515             219               5,232             1,391             161               38                     0.03356614,634         3,008             119               2,854             759                88                 21                     0.01867717,073         3,510             139               3,329             885               102               24                     0.0217101024,390         5,014             199               4,756             1,264             146               35                     0.03089921,951         4,513             179               4,281             1,138             132               31                     0.02798819,512         4,011             159               3,805             1,012             117               28                     0.024105512,195         2,507             99                 2,378             632                73                 17                     0.01511449,756           2,006             79                 1,903             506                59                 14                     0.012126614,634         3,008             119               2,854             759                88                 21                     0.01813449,756           2,006             79                 1,903             506                59                 14                     0.012148819,512         4,011             159               3,805             1,012             117               28                     0.02415449,756           2,006             79                 1,903             506                59                 14                     0.01216111126,829         5,515             219               5,232             1,391             161               38                     0.033 MEAN 0.023 MEDIAN 0.024 STD DEV 0.008 MAX 0.036 MIN 0.012 1 of 1 SECTION 7 ATTACHMENT 2 2 PAGES
Q               Pipe Diameter:         z'(-             Access Point Area: R 6 Pnldd~lrs Building:                         Elevation:       <-ar                         System:           &,bZ,J/
-. BSIiLVSPipeCrawler-002 Revision 5 Pipe Interior Radiological Survey Form Date: l-)b-V 8 Time: 13 4D Pipe JD#: ~ $Q Pipe Diameter:
Type of Survey     Investigation         Characterization           Final Survey     X       Other   X Gross                           C06O   X                                 Cs Detector ID# I Sled ID#         2 4 7 / ~ 9 7 l /t/a 5 4 2 Detector Cal Date:         /o-/b - 07             Detector Cal Due Date: - / - 1 h -
z'(- Access Point Area: R6 Pnldd~lrs Building:
Instrument:           -G%~o     - 1               Instrument ID #:                 ~93#3L?
Elevation:  
Instrument Cal Date:         10-Ib-07             Instrument Cal Due Date:             1D - / L o - 0 2 From the Daily Pipe Survey Detector Control Form for the Selected Detector Background Value         / w 8 cpm MDCRstam             -         CPm Efficiency Factor for Plpe Diameter 6.0004 (               (from detector efficiency detemnation)
<-ar System: &,bZ,J/ 7 Type of Survey Investigation Characterization Final Survey X Other X Gross C06O X Cs Detector ID# I Sled ID# 247/~97 l /t/a 542 Detector Cal Date:  
M"c,tat.       39&             dpm/       1 VZ,       cmZ Is the MDCStamacceptable?                 No         (dno, adjust sample count tune and recalculate MDCLw)
/o-/b - 07 Detector Cal Due Date: - / - 1 h - Instrument: -G%~o - 1 Instrument ID #: ~93#3L? Instrument Cal Date: 10-Ib-07 Instrument Cal Due Date: 1D -/Lo -02 From the Daily Pipe Survey Detector Control Form for the Selected Detector Background Value  
Comments:         D       YYI&     w*c l & l ~
/ w 8 cpm MDCRstam - CPm Efficiency Factor for Plpe Diameter 6. 0004 ( (from detector efficiency detemnation)
    ~ p epun 5      &+       "1.d1 (w-           o:& nr? R Q - u )o -SfP I
M"c,tat. 39& dpm/ 1 VZ, cmZ Is the MDCStam acceptable?
WP~=,     IprrdIh~
No (d no, adjust sample count tune and recalculate MDCLw) Comments:
Technician Signature Pipe Interior Radiological Survey Package Page 1 of 0 REFERENCE COPY Attachment 3, Page 1
D YYI& w* 5 cl&l~ ~pe pun &+ "1.d1 (w- o:& nr? RQ-u )o -SfP WP~=, IprrdIh~ I Technician Signature Pipe Interior Radiological Survey REFERENCE COPY 0 Package Page 1 of Attachment 3, Page 1 BSYLVSPipeCrawler-002 Revision 5 Pipe Interior Radiological Survey Form (Continuation Form) Date: I-lb-0%, Pipe Diameter: " Access Point Area:  
 
@A~/&VLV-S Building:
BSYLVSPipeCrawler-002 Revision 5 Pipe Interior Radiological Survey Form (Continuation Form)
Elevation:  
Date:     I-lb-0%,                               "
-24' System: &hm #I-i- REFERENCE COPY Package Page 5 of? Attachment 3, Page 2 SECTION 7 ATTACHMENT 3 1 PAGE 1 Survey Unit # I EP S1 I DQA Check Sheet Preliminary Data Review' Answers to the following questions should be fully documented in the Survey Unit Release Record Design # 1. Have surveys been performed in accordance with survey instructions in the Survey Design? 2. Is the instrumentation MDC for structure static measurements below the DCGLw for Class 1 and 2 survey units, or below 0.5 DCGLw for Class 3 survey units? 3. Is the instrumentation MDC for ernbeddedlburied piping static measurements below the DCGLW? 4. Was the instrumentation MDC for structure scan measurements, soil scan measurements, and ernbeddedlburied piping scan measurements below the DCGLw or, if not, was the need for additional static measurements or soil samoles addressed in the survev desian? - Yes EP S1 1 5. Was the instrumentation MDC for volumetric measurements and smear analysis c 10% DCGLW ? 1 I 1x1 Revision # 1 8. Were "Soecial Methods" for data collection roo ell^
Pipe Diameter:               Access Point Area: @A~/&VLV-S Building:                       Elevation:     -24'           System:         &hm   #I-i-Package Page 5 of?
a~olied for the survev unit under review? 1x1 I 1 Original 6. Were the MDCs and assumptions used to develop them appropriate for the instruments and techniques used to perform the survey? 7. Were the survey methods used to collect data proper for the types of radiation involved and for the media being surveyed?
REFERENCE COPY Attachment 3, Page 2
9 Is the data set comprised of qualified measurement results collected in accoroance wlth the survey I deslran, whlch accuratelv reflects the raololotl~cal status of the fac,l tv? X I I X 1 Graphical Data Review 1 I 1. Has a posting plot been created? 1 I 1x1 1 2. Has a histogram (or other frequency plot) been created? I 1 1x1 1 3. Have other graphical data tools been created to assist in analyzing the data? I I 1x1 I Data Analysis I I 1. Are all samole measurements below the DCGLw (Class 1 & 2). or 0.5 DCGLw (Class 3)? / X / 1 I 1 5. Is the result of the statistical test (S+ for Sign Test or W, for WRS Test) 2 the critical value? I 1 1x1 2. Is the mean of the sample data c DCGLw? 3. If elevated areas have been identified by scans andior sampling, is the average activity in each elevated area c DCGLEM~ (Class 1). c DCGLw (Class 2), or ~0.5 DCGLw (Class 3)?  
 
: 4. Is the result of the Elevated Measurements Test c 1.0? I Comments:
SECTION 7 ATTACHMENT 3 1 PAGE
FSSICharacterization Engineer (prinusign)
 
FSSl Characterization Manager (printlsign)
DQA Check Sheet Design #                EP S1            Revision #        Original 1   Survey Unit #     I                                                       EP S1                                 I Preliminary Data Review' Answers to the following questions should be fully documented in the Survey Unit Release Record                                         Yes
X Date X X Date Page 1 of 1 SECTION 7 ATTACHMENT 4 1 DISC}}
: 1. Have surveys been performed in accordance with survey instructions in the Survey Design?
: 2. Is the instrumentation MDC for structure static measurements below the DCGLw for Class 1 and 2 survey units, or below 0.5 DCGLw for Class 3 survey units?
: 3. Is the instrumentation MDC for ernbeddedlburied piping static measurements below the DCGLW?
: 4. Was the instrumentation MDC for structure scan measurements, soil scan measurements, and ernbeddedlburied piping scan measurements below the DCGLw or, if not, was the need for additional static measurements or soil samoles addressed in the survev desian?
1 5. Was the instrumentation MDC for volumetric measurements and smear analysis c 10% DCGLW?           1     I 1 x 1
: 6. Were the MDCs and assumptions used to develop them appropriate for the instruments and techniques used to perform the survey?
: 7. Were the survey methods used to collect data proper for the types of radiation involved and for the   X media being surveyed?
1 8. Were "Soecial Methods" for data collection roo ell^ a~oliedfor the survev unit under review?      1 x 1    I  1 I 9   Is the data set comprised of qualified measurement results collected in accoroance wlth the survey deslran, whlch accuratelv reflects the raololotl~calstatus of the fac,l tv?
X     I I 1                                                         Graphical Data Review                                     1 I 1. Has a posting plot been created?                                                                   1     I 1 x 1 1 2. Has a histogram (or other frequency plot) been created?                                           I     1 1 x 1 1 3. Have other graphical data tools been created to assist in analyzing the data?                     I     I 1 x 1 I                                                               Data Analysis                                       I I 1. Are all samole measurements below the DCGLw (Class 1 & 2). or 0.5 DCGLw (Class 3)?                 / X   / 1   I
: 2. Is the mean of the sample data c DCGLw?                                                               X
: 3. If elevated areas have been identified by scans andior sampling, is the average activity in each X
elevated area c DCGLEM~       (Class 1). c DCGLw (Class 2),or ~ 0 . 5DCGLw (Class 3)?
: 4. Is the result of the Elevated Measurements Test c 1.0?                                                       X 1 5. Is the result of the statistical test (S+ for Sign Test or W, for WRS Test) 2 the critical value?  I      1 1 x 1 I
Comments:
FSSICharacterization Engineer (prinusign)                                                             Date FSSl Characterization Manager (printlsign)                                                             Date Page 1 of 1
 
SECTION 7 ATTACHMENT 4 1 DISC}}

Latest revision as of 06:06, 13 March 2020

Plum Brook Reactor Facility, Survey Unit Release Record Embedded Pipe (EP) S1
ML080670266
Person / Time
Site: Plum Brook
Issue date: 03/04/2008
From: Wood G
US National Aeronautics & Space Admin (NASA), John H. Glenn Research Ctr at Lewis Field
To:
NRC/RGN-III
References
EP-S1
Download: ML080670266 (12)


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Survey Unit Release Record Design # EP-S 1 Revision # Original Page 1 of 3 Survey Unit #(s) S1

1) Embedded Pipe (EP) Survey Unit S1 meets the definition of embedded pipe for Plum Brook Reactor Facility (PBRF).
2) EP S1 is a Class 1, Group 1 survey unit as per the PBRF Final Status Survey Plan (FSSP) and Technical Basis Document (TBD)-06-004.
3) Surveys in EP S1 were performed using a scintillation detector optimized to measure gamma energies representative of Co-60. Sample #EP 3-9 from Survey Request (SR)-13 was referenced for this decision.
4) Survey Instructions for this survey unit are incorporated into and performed in accordance with (IAW) the Babcock Services Incorporated (BSI)/LVS-002, Work Execution Package (WEP)05-006. Survey instructions described in this Description document constitute "Special Methods" and the survey design used in the acquisition of survey measurements.
5) Instrument efficiency determinations are developed in accordance with the BSYLVS-002, WEP 05-006, these determinations are appropriate for the types of radiation involved and the media being surveyed.

FSSICharacterization Engineer FSSICharacterization Manager

FSS Design # EP S1 Revision # Original Page 2 of 3 Survey Unit: S1 1.0 History/Description 1.1 The subject pipe system is a 2 service conduit adjacent to the 1.51 drain system access box in the annulus on the -25 elevation of the Reactor Building.

1.2 EP S1 is approximately 16 feet in length.

1.3 Any contamination of this service conduit is expected to be cross contamination from the remediation efforts of RX1.51 which is adjacent to this service conduit in a valve box on the RB -25 annulus. Service conduit S1 was open to cross contamination during those remediation efforts.

2.0 Survey Design Information 2.1 EP S1 was surveyed IAW Procedure #BSI/LVS-002.

2.2 100% of the 2 ID pipe was accessible for survey. The accessible 2 ID pipe was surveyed by static measurement at one foot increments, for a total of 16 survey measurements.

2.3 Surface area for the 2 ID piping is 486 cm2 for each foot of piping, corresponding to a total 2 ID piping surface area of 7776 cm2 (0.8 m2) for the entire accessible length of (16) of 2 piping.

3.0 Survey Unit Measurement Locations/Data 3.1 Pipe interior radiological survey forms are provided in Attachment 2 of this release record.

4.0 Survey Unit Investigations/Results 4.1 None 5.0 Data Assessment Results 5.1 Data assessment results are provided in the EP/Buried Pipe (BP) Survey Report provided in Attachment 1.

5.2 All measurement results are less than the Derived Concentration Guideline Level (DCGL) for radionuclide specific EP that corresponds to the 1 mrem/yr dose goal established in Table 3-3 of the FSSP.

5.3 When implementing the Unity Rule, provided in Section 3.6.3 of the FSSP, and applying the Nuclide Fraction (NF), provided in TBD-06-004, the survey unit that is constituted by EP S1 passes FSS.

5.4 Background was not subtracted from the survey measurements and the Elevated Measurement Comparison (EMC) was not employed for the accessible portion of this survey unit.

FSS Design # EP S1 Revision # Original Page 3 of 3 Survey Unit: S1 Statistical Summary Table Statistical Parameter 2 Pipe Total Number of Survey Measurements 16 Number of Measurements >MDC 9 Number of Measurements Above 50% of DCGL 0 Number of Measurements Above DCGL 0 Mean 0.023 Median 0.024 Standard Deviation 0.008 Maximum 0.036 Minimum 0.012 6.0 Documentation of evaluations pertaining to compliance with the unrestricted use limit of 25 mrem/yr and dose contributions from Embedded Pipe and radionuclides contributing 10% in aggregate of the total dose for both structural scenarios and soils.

6.1 A review of the survey results has shown that the dose contribution for the accessible portion of EP S1 to be less than 1 mrem/yr. The dose contribution is estimated to be 0.023 mrem/yr based on the average of the actual gross counts.

7.0 Attachments Attachment 1 - BSI EP/BP Survey Report Attachment 2 -Pipe Interior Radiological Survey Form Attachment 3 - DQA Worksheet Attachment 4 -Disc containing RR for EP S1 & Spreadsheet

SECTION 7 ATTACHMENT 1 2 PAGES

BSI EPlBP SURVEY REPORT EP S1 2" Pipe TBD 06-004 Group 1 Measurement #

Co-60 activity Co-60 activity Cs-137 activity Eu-152 activity Eu-154 activity Nb-94 activity Ag-108m activity gcpm ncpm (total dpm) (dpm/100cm2) (dpm/100cm2) (dpm/100cm2) (dpm/100cm2) (dpm/100cm2) (dpm/100cm2)

Unity 1 12 12 29,268 6,017 238 5,708 1,517 176 42 0.036 2 9 9 21,951 4,513 179 4,281 1,138 132 31 0.027 3 8 8 19,512 4,011 159 3,805 1,012 117 28 0.024 4 11 11 26,829 5,515 219 5,232 1,391 161 38 0.033 5 6 6 14,634 3,008 119 2,854 759 88 21 0.018 6 7 7 17,073 3,510 139 3,329 885 102 24 0.021 7 10 10 24,390 5,014 199 4,756 1,264 146 35 0.030 8 9 9 21,951 4,513 179 4,281 1,138 132 31 0.027 9 8 8 19,512 4,011 159 3,805 1,012 117 28 0.024 10 5 5 12,195 2,507 99 2,378 632 73 17 0.015 11 4 4 9,756 2,006 79 1,903 506 59 14 0.012 12 6 6 14,634 3,008 119 2,854 759 88 21 0.018 13 4 4 9,756 2,006 79 1,903 506 59 14 0.012 14 8 8 19,512 4,011 159 3,805 1,012 117 28 0.024 15 4 4 9,756 2,006 79 1,903 506 59 14 0.012 16 11 11 26,829 5,515 219 5,232 1,391 161 38 0.033 MEAN 0.023 MEDIAN 0.024 STD DEV 0.008 MAX 0.036 MIN 0.012 1 of 1

SECTION 7 ATTACHMENT 2 2 PAGES

-. BSIiLVSPipeCrawler-002 Revision 5 Pipe Interior Radiological Survey Form Date: l-)b-V 8 Time: 1 34D Pipe JD#: ~ $

Q Pipe Diameter: z'(- Access Point Area: R 6 Pnldd~lrs Building: Elevation: <-ar System: &,bZ,7 J/

Type of Survey Investigation Characterization Final Survey X Other X Gross C06O X Cs Detector ID# I Sled ID# 2 4 7 / ~ 9 7 l /t/a 5 4 2 Detector Cal Date: /o-/b - 07 Detector Cal Due Date: - / - 1 h -

Instrument: -G%~o - 1 Instrument ID #: ~93#3L?

Instrument Cal Date: 10-Ib-07 Instrument Cal Due Date: 1D - / L o - 0 2 From the Daily Pipe Survey Detector Control Form for the Selected Detector Background Value / w 8 cpm MDCRstam - CPm Efficiency Factor for Plpe Diameter 6.0004 ( (from detector efficiency detemnation)

M"c,tat. 39& dpm/ 1 VZ, cmZ Is the MDCStamacceptable? No (dno, adjust sample count tune and recalculate MDCLw)

Comments: D YYI& w*c l & l ~

~ p epun 5 &+ "1.d1 (w- o:& nr? R Q - u )o -SfP I

WP~=, IprrdIh~

Technician Signature Pipe Interior Radiological Survey Package Page 1 of 0 REFERENCE COPY Attachment 3, Page 1

BSYLVSPipeCrawler-002 Revision 5 Pipe Interior Radiological Survey Form (Continuation Form)

Date: I-lb-0%, "

Pipe Diameter: Access Point Area: @A~/&VLV-S Building: Elevation: -24' System: &hm #I-i-Package Page 5 of?

REFERENCE COPY Attachment 3, Page 2

SECTION 7 ATTACHMENT 3 1 PAGE

DQA Check Sheet Design # EP S1 Revision # Original 1 Survey Unit # I EP S1 I Preliminary Data Review' Answers to the following questions should be fully documented in the Survey Unit Release Record Yes

1. Have surveys been performed in accordance with survey instructions in the Survey Design?
2. Is the instrumentation MDC for structure static measurements below the DCGLw for Class 1 and 2 survey units, or below 0.5 DCGLw for Class 3 survey units?
3. Is the instrumentation MDC for ernbeddedlburied piping static measurements below the DCGLW?
4. Was the instrumentation MDC for structure scan measurements, soil scan measurements, and ernbeddedlburied piping scan measurements below the DCGLw or, if not, was the need for additional static measurements or soil samoles addressed in the survev desian?

1 5. Was the instrumentation MDC for volumetric measurements and smear analysis c 10% DCGLW? 1 I 1 x 1

6. Were the MDCs and assumptions used to develop them appropriate for the instruments and techniques used to perform the survey?
7. Were the survey methods used to collect data proper for the types of radiation involved and for the X media being surveyed?

1 8. Were "Soecial Methods" for data collection roo ell^ a~oliedfor the survev unit under review? 1 x 1 I 1 I 9 Is the data set comprised of qualified measurement results collected in accoroance wlth the survey deslran, whlch accuratelv reflects the raololotl~calstatus of the fac,l tv?

X I I 1 Graphical Data Review 1 I 1. Has a posting plot been created? 1 I 1 x 1 1 2. Has a histogram (or other frequency plot) been created? I 1 1 x 1 1 3. Have other graphical data tools been created to assist in analyzing the data? I I 1 x 1 I Data Analysis I I 1. Are all samole measurements below the DCGLw (Class 1 & 2). or 0.5 DCGLw (Class 3)? / X / 1 I

2. Is the mean of the sample data c DCGLw? X
3. If elevated areas have been identified by scans andior sampling, is the average activity in each X

elevated area c DCGLEM~ (Class 1). c DCGLw (Class 2),or ~ 0 . 5DCGLw (Class 3)?

4. Is the result of the Elevated Measurements Test c 1.0? X 1 5. Is the result of the statistical test (S+ for Sign Test or W, for WRS Test) 2 the critical value? I 1 1 x 1 I

Comments:

FSSICharacterization Engineer (prinusign) Date FSSl Characterization Manager (printlsign) Date Page 1 of 1

SECTION 7 ATTACHMENT 4 1 DISC