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{{#Wiki_filter:Survey Unit Release Record 1 2) EP Rx 138-1 is a Class 1, Group 1 survey unit as per the PBRF Final Status Survey Plan (FSSP) and Technical Basis Document (TBD)-06-004.
{{#Wiki_filter:Survey Unit Release Record 1
Design # Survey Unit  
: 2) EP Rx 138-1 is a Class 1, Group 1 survey unit as per the PBRF Final Status Survey Plan (FSSP) and Technical Basis Document (TBD)-06-004.
#(s) 3) Surveys in EP Rx 138-1 were performed using a scintillation detector optimized to measure gamma energies representative of Cod0. Sample #EP 3- 9 from Survey Request (SR)-13 was referenced for this decision.
Design #
EP-Rx 138-1 / 5) Instrument efficiency determinations are developed in accordance with the 1 Description BSILVS-002, WEP 05-006, these determinations  
Survey Unit #(s)
&e appropriate for the types of radiation involved and the media being surveyed.
: 3) Surveys in EP Rx 138-1 were performed using a scintillation detector optimized to measure gamma energies representative of Cod0. Sample #EP 3-9 from Survey Request (SR)-13 was referenced for this decision.
Rx 138-1 1) Embedded Pipe (EP) Survey Unit Rx 138-1 meets the definition of embedded pipe for Plum Brook Reactor Facility (PBRF). Revision # 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 document constitute "Special Methods" and the survey design used in the acquisition of survey measurements.
EP-Rx 138-1  
/ 5) Instrument efficiency determinations are developed in accordance with the 1
Description BSILVS-002, WEP 05-006, these determinations &e appropriate for the types of radiation involved and the media being surveyed.
Rx 138-1
: 1) Embedded Pipe (EP) Survey Unit Rx 138-1 meets the definition of embedded pipe for Plum Brook Reactor Facility (PBRF).
Revision #
: 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 document constitute "Special Methods" and the survey design used in the acquisition of survey measurements.
: 6) Only the eight feet of the approximate overall length of twenty two feet of this pipe was accessible for final survey. However, it is concluded that the final survey of the accessible portion of this pipe system is appropriate to demonstrate the radiological condition of the entire pipe and the suitability of the pipe for unrestricted release.
: 6) Only the eight feet of the approximate overall length of twenty two feet of this pipe was accessible for final survey. However, it is concluded that the final survey of the accessible portion of this pipe system is appropriate to demonstrate the radiological condition of the entire pipe and the suitability of the pipe for unrestricted release.
Original Technical Reviewer FSSICharacterization Manager Page 1 of 4 Approval Signatures Date: FSSICharacterization Engineer A /(- 2 8- 0'7 FSS Design # EP Rx 138-1 Revisi on # Original Page 2 of 4 Survey Unit: Rx 138-1 1.0 History/Description 1.1 The subject pipe system is a 1" sy stem line. The ends of the piping section are accessible from the Sub Pile Room and Quad "D" on the -25' elevation of the Reactor Building.
Original Technical Reviewer FSSICharacterization Manager Page 1 of 4 Approval Signatures Date:
1.2 EP Rx 138-1 is approximately 22 feet in length. The middle portion of the pipe run could not be accessed for survey due to a series of mitered, 90 o elbows that prevent the travel of ra diological detectors past the access points. Consequently, only eight of the approximate 22 feet of total length for this pipe was accessible for survey.
FSSICharacterization Engineer A  
/(- 2 8- 0'7  
 
FSS Design # EP Rx 138-1 Revision # Original Page 2 of 4 Survey Unit: Rx 138-1 1.0 History/Description 1.1 The subject pipe system is a 1 system line. The ends of the piping section are accessible from the Sub Pile Room and Quad D on the -25 elevation of the Reactor Building.
1.2 EP Rx 138-1 is approximately 22 feet in length. The middle portion of the pipe run could not be accessed for survey due to a series of mitered, 90o elbows that prevent the travel of radiological detectors past the access points. Consequently, only eight of the approximate 22 feet of total length for this pipe was accessible for survey.
2.0 Survey Design Information 2.1 EP Rx 138-1 was surveyed IAW Procedure #BSI/LVS-002.
2.0 Survey Design Information 2.1 EP Rx 138-1 was surveyed IAW Procedure #BSI/LVS-002.
2.2 The accessible portion of the 1" ID pipe was surveyed by static measurement at one foot increments, for a total of 8 survey measurements.
2.2 The accessible portion of the 1 ID pipe was surveyed by static measurement at one foot increments, for a total of 8 survey measurements.
2.3 Surface area for the 1" ID piping is 243 cm 2 for each foot of piping, corresponding to a total 1" ID piping surface area of 1,946 cm 2 (0.2 m 2) for the entire accessible length of (8') of 1" piping.
2.3 Surface area for the 1 ID piping is 243 cm2 for each foot of piping, corresponding to a total 1 ID piping surface area of 1,946 cm2 (0.2 m2) for the entire accessible length of (8) of 1 piping.
3.0 Survey Unit Measurement Locations/Data 3.1 Pipe interior radiological survey forms are provided in Attachment 2 of this release record.
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.
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.
Line 33: Line 43:
5.3 All measurement results from the eight feet of accessible pipe 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 All measurement results from the eight feet of accessible pipe 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.
5.4 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.
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.
5.5 In addition to the eight final survey measurements taken in the accessible portion of this pipe, additional radiological surveys were performed to the extent possible as allowed by the conf iguration of this piping. These surveys were performed to provide additional assurance that the FSS Design # EP Rx 138-1 Revisi on # Original Page 3 of 4 Survey Unit: Rx 138-1 radiological conditions represented by the eight interior survey measurements are representative of the entire length of pipe.
5.5 In addition to the eight final survey measurements taken in the accessible portion of this pipe, additional radiological surveys were performed to the extent possible as allowed by the configuration of this piping. These surveys were performed to provide additional assurance that the  
5.6 Scan surveys were performed for pre and post remediation purposes, using a beta-gamma GM detector on the exterior of the access point for this pipe system. The surveys are documented as survey nos. NASA-07-3204 and NASA-07-3221, performed in support of RWP PB-07-100. Both pre and post surveys showed negligible levels of activity. The scan survey results indicated activity <1,000 dpm per dir ect frisk. In addi tion, smear rag was pulled through the length of the pi ping section. No loose radiological contamination greater than 1,000 dpm/100cm 2 was detected.
5.7 Based upon the results of the final survey measurements combined with the results of the operational survey, it is reasonable to conclude that the final survey of the accessible portion of this pipe system is appropriate to demonstrate the radiological condition of the entire pipe. Survey Unit    EP Rx 138-1 demonstrates complia nce with the DC GL values, as presented in Sections 3.3, 7.5 and Attachment C of the PBRF FSSP.
5.8 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 Rx 138-1 passes FSS.


Statistical Summary Table Statistical Parameter 1" Pipe Total Number of Survey Measurements 8 Number of Measurements >MDC 8 Number of Measurements Above 50% of DCGL 1 Number of Measurements Above DCGL 0 Mean 0.2107 Median 0.1174 Standard Deviation 0.1633 Maximum 0.5146 Minimum 0.0967 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 Rx 138-1 Revision # Original Page 3 of 4 Survey Unit: Rx 138-1 radiological conditions represented by the eight interior survey measurements are representative of the entire length of pipe.
5.6 Scan surveys were performed for pre and post remediation purposes, using a beta-gamma GM detector on the exterior of the access point for this pipe system. The surveys are documented as survey nos. NASA-07-3204 and NASA-07-3221, performed in support of RWP PB-07-100. Both pre and post surveys showed negligible levels of activity. The scan survey results indicated activity <1,000 dpm per direct frisk. In addition, smear rag was pulled through the length of the piping section. No loose radiological contamination greater than 1,000 dpm/100cm2 was detected.
5.7 Based upon the results of the final survey measurements combined with the results of the operational survey, it is reasonable to conclude that the final survey of the accessible portion of this pipe system is appropriate to demonstrate the radiological condition of the entire pipe. Survey Unit EP Rx 138-1 demonstrates compliance with the DCGL values, as presented in Sections 3.3, 7.5 and Attachment C of the PBRF FSSP.
5.8 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 Rx 138-1 passes FSS.
Statistical Summary Table Statistical Parameter 1 Pipe Total Number of Survey Measurements 8
Number of Measurements >MDC 8
Number of Measurements Above 50% of DCGL 1
Number of Measurements Above DCGL 0
Mean 0.2107 Median 0.1174 Standard Deviation 0.1633 Maximum 0.5146 Minimum 0.0967 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.


radionuclides contributing 10% in aggregat e of the total dose for both structural scenarios and soils.
FSS Design # EP Rx 138-1 Revision # Original Page 4 of 4 Survey Unit: Rx 138-1 6.1 A review of the survey results has shown that the dose contribution for the accessible portion of EP Rx 138-1 to be less than 1 mrem/yr. The dose contribution is estimated to be 0.211 mrem/yr based on the average of the actual gross counts.
FSS Design # EP Rx 138-1 Revisi on # Original Page 4 of 4 Survey Unit: Rx 138-1 6.1 A review of the survey results has sh own that the dose contribution for the accessible portion of EP Rx 138-1 to be less than 1 mrem/yr. The dose contribution is estimated to be 0.211 mrem/yr based on the average of the  
7.0 Attachments - BSI EP/BP Survey Report -Pipe Interior Radiological Survey Form & Radiation Protection Survey Forms - DQA Worksheet -Disc containing RR for EP Rx 138-1 & Spreadsheet


actual gross counts.
SECTION 7 ATTACHMENT 1 z PAGE(S)
7.0 Attachments Attachment 1 - BSI EP/BP Survey Report Attachment 2 -Pipe Interior Radiological Survey Form & Radiation Protection Survey Forms Attachment 3 - DQA Worksheet Attachment 4 -Disc containing RR for EP Rx 138-1 & Spreadsheet


SECTION 7 ATTACHMENT 1 z PAGE(S)
BSI EPIBP SURVEY REPORT Suwey Locatlon Detector-Sled #
BSI EPIBP SURVEY REPORT Suwey Locatlon Detector-Sled  
Detector Efficiency Survey Unit Classification TBD 06-004 Piping Group SR-13 Radionuclide Distribution Sample Measured Nuclide Area FactorIEMC Used PassiFail FSS MREMNR Contribution 1
# Detector Efficiency Survey Unit Classification TBD 06-004 Piping Group SR-13 Radionuclide Distribution Sample Measured Nuclide Area FactorIEMC Used PassiFail FSS MREMNR Contribution 1 1 EP 3-9 Co-60 No Pass <I COMMENTS:
1 EP 3-9 Co-60 No Pass  
ACTIVITYVALUES NOT BACKGROUND CORRECTED RP Engineer 1 Date EP Rx 138-1 1" Pipe TBD 06-004 Group 1 Measurement #gcpmncpm Co-60 activity   (total dpm)
<I COMMENTS:
ACTIVITYVALUES NOT BACKGROUND CORRECTED RP Engineer 1 Date  
 
EP Rx 138-1 1" Pipe TBD 06-004 Group 1 Measurement #
gcpm ncpm Co-60 activity (total dpm)
Co-60 activity (dpm/100cm2)
Co-60 activity (dpm/100cm2)
Cs-137 activity (dpm/100cm2)
Cs-137 activity (dpm/100cm2)
Line 56: Line 74:
Nb-94 activity (dpm/100cm2)
Nb-94 activity (dpm/100cm2)
Ag-108m activity (dpm/100cm2)
Ag-108m activity (dpm/100cm2)
Unity1323245,070         18,531           734               17,578           4,673             541               129                   0.1112282839,437         16,214           643               15,381           4,089             473               113                   0.0973353549,296         20,268           803               19,226           5,111             591               141                   0.1214333346,479         19,110           757               18,128           4,819             558               133                   0.1145292940,845         16,793           666               15,930           4,235             490               117                   0.1006149149209,859       86,284           3,420             81,849           21,759           2,518             601                   0.5157120120169,014       69,490           2,754             65,919           17,524           2,028             484                   0.4148626287,324         35,903           1,423             34,058           9,054             1,048             250                   0.214 MEAN0.211MEDIAN0.117 STD DEV0.163 MAX0.515MIN0.097 1 of 1 SECTION 7 ATTACHMENT 2 5 PAGE(S)
Unity 1
- IBSYE~peC~awler-ti02 Revision 5 Pipe Interior Radiplogical Survey Form ate, i!:J7 : ti7 Tke: 134.5' I' J, pipe ICM 8% (38 *( Pipe Diamefer:
32 32 45,070 18,531 734 17,578 4,673 541 129 0.111 2
I Access Point Area-. QUAD 0 SutIding:
28 28 39,437 16,214 643 15,381 4,089 473 113 0.097 3
RX Ebvatim: - System: Typeofsurvey hv&- Charactdzation . oross coso J DetecrOf D# I sled ID# MY GI i.5~-X).WT Detector ~al Date: 7 I 4 - 07 ~ete~tof ca ~~e~ate: 9 -!Y -o$ ~nsram~nt:
35 35 49,296 20,268 803 19,226 5,111 591 141 0.121 4
a350 - I li~stmmd ID #: av34bB InstmmntCatDate:  
33 33 46,479 19,110 757 18,128 4,819 558 133 0.114 5
29 29 40,845 16,793 666 15,930 4,235 490 117 0.100 6
149 149 209,859 86,284 3,420 81,849 21,759 2,518 601 0.515 7
120 120 169,014 69,490 2,754 65,919 17,524 2,028 484 0.414 8
62 62 87,324 35,903 1,423 34,058 9,054 1,048 250 0.214 MEAN 0.211 MEDIAN 0.117 STD DEV 0.163 MAX 0.515 MIN 0.097 1 of 1
 
SECTION 7 ATTACHMENT 2 5
PAGE(S)  
 
IBSYE~peC~awler-ti02 Revision 5 Pipe Interior Radiplogical Survey Form ate, i!:J7 : ti7 Tke:
134.5' I'
J, pipe ICM 8% (38 *(
Pipe Diamefer:
I Access Point Area-. QUAD 0 SutIding: RX Ebvatim:
System:
Typeofsurvey hv&-
Charactdzation oross coso J DetecrOf D# I sled ID# MY GI i.5~-X).WT Detector ~ a l Date:
7 I 4 - 07  
~ete~tof ca ~ ~ e ~ a t e :
9 -!Y -o$  
~nsram~nt: a350 - I li~stmmd ID #:
av34bB InstmmntCatDate:  
'?-/'4-07 h&mmentWDueDate:
'?-/'4-07 h&mmentWDueDate:
g-)'-f-& Fm the Daily Pipe Survey Detector C~nbroIBom far the Selected Detector BackgronndValue 78 Cpm MD~ tab la cpm Efficiency Pactor for Pipe Diameter 0,'13007/ (firam detecmr efficiency determintion)
g-)'-f-&
F m the Daily Pipe Survey Detector C~nbroIBom far the Selected Detector BackgronndValue 78 Cpm M
D
~
tab la cpm Efficiency Pactor for Pipe Diameter 0,'13007/
(firam detecmr efficiency determintion)
Is the MDCrtati, acceptable?
Is the MDCrtati, acceptable?
[if no, ad@t sample tart time and recalculate bDCl&dJ GO " D". b5.k \ (8'-lb - -- -. Technician Signature Pipe Interior Radiological Survey \J REFERENCE COPY package Page I of3 Attachment 3, Page 1
[if no, ad@t sample tart time and recalculate bDCl&dJ GO " D". b 5. k  
\\
(8'-lb Technician Signature Pipe Interior Radiological Survey  
\\J REFERENCE COPY package Page I o f 3, Page 1  
 
REFERENCECOPY
 
RADIATION PRO'I'ECZTON SURVEY FORB4 3 ? a g e L o f L
 
RADXA3XON PROmGTZON SURTEY FORM I
Page 1 of )
RP-005 / 1 Rev. 0
 
SECTION 7 ATTACHMENT 3 I
PAGE(S)


REFERENCECOPY RADIATION PRO'I'ECZTON SURVEY FORB4 3?ageLofL RADXA3XON PROmGTZON SURTEY FORM I Page 1 of ) RP-005 / 1 Rev. 0 SECTION 7 ATTACHMENT 3 I PAGE(S)
FSSlCharaderization Engineer (prinffsign)
FSSlCharaderization Engineer (prinffsign)
CS-0912 Page 1 of 1 SECTION 7 ATTACHMENT 4 1 DISC}}
CS-0912 Page 1 of 1  
 
SECTION 7 ATTACHMENT 4 1 DISC}}

Latest revision as of 19:39, 14 January 2025

EP-RX-138-1, Nasa, Survey Unit Release Record
ML073400106
Person / Time
Site: Plum Brook  File:National Aeronautics and Space Administration icon.png
Issue date: 11/29/2007
From:
US National Aeronautics & Space Admin (NASA)
To:
NRC/RGN-III/DNMS/DB
References
EP-RX-138-1
Download: ML073400106 (16)


Text

Survey Unit Release Record 1

2) EP Rx 138-1 is a Class 1, Group 1 survey unit as per the PBRF Final Status Survey Plan (FSSP) and Technical Basis Document (TBD)-06-004.

Design #

Survey Unit #(s)

3) Surveys in EP Rx 138-1 were performed using a scintillation detector optimized to measure gamma energies representative of Cod0. Sample #EP 3-9 from Survey Request (SR)-13 was referenced for this decision.

EP-Rx 138-1

/ 5) Instrument efficiency determinations are developed in accordance with the 1

Description BSILVS-002, WEP 05-006, these determinations &e appropriate for the types of radiation involved and the media being surveyed.

Rx 138-1

1) Embedded Pipe (EP) Survey Unit Rx 138-1 meets the definition of embedded pipe for Plum Brook Reactor Facility (PBRF).

Revision #

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 document constitute "Special Methods" and the survey design used in the acquisition of survey measurements.
6) Only the eight feet of the approximate overall length of twenty two feet of this pipe was accessible for final survey. However, it is concluded that the final survey of the accessible portion of this pipe system is appropriate to demonstrate the radiological condition of the entire pipe and the suitability of the pipe for unrestricted release.

Original Technical Reviewer FSSICharacterization Manager Page 1 of 4 Approval Signatures Date:

FSSICharacterization Engineer A

/(- 2 8- 0'7

FSS Design # EP Rx 138-1 Revision # Original Page 2 of 4 Survey Unit: Rx 138-1 1.0 History/Description 1.1 The subject pipe system is a 1 system line. The ends of the piping section are accessible from the Sub Pile Room and Quad D on the -25 elevation of the Reactor Building.

1.2 EP Rx 138-1 is approximately 22 feet in length. The middle portion of the pipe run could not be accessed for survey due to a series of mitered, 90o elbows that prevent the travel of radiological detectors past the access points. Consequently, only eight of the approximate 22 feet of total length for this pipe was accessible for survey.

2.0 Survey Design Information 2.1 EP Rx 138-1 was surveyed IAW Procedure #BSI/LVS-002.

2.2 The accessible portion of the 1 ID pipe was surveyed by static measurement at one foot increments, for a total of 8 survey measurements.

2.3 Surface area for the 1 ID piping is 243 cm2 for each foot of piping, corresponding to a total 1 ID piping surface area of 1,946 cm2 (0.2 m2) for the entire accessible length of (8) of 1 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 Only the eight feet of the approximate overall length of 22 feet of this pipe was accessible for final survey.

5.3 All measurement results from the eight feet of accessible pipe 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.

5.4 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.

5.5 In addition to the eight final survey measurements taken in the accessible portion of this pipe, additional radiological surveys were performed to the extent possible as allowed by the configuration of this piping. These surveys were performed to provide additional assurance that the

FSS Design # EP Rx 138-1 Revision # Original Page 3 of 4 Survey Unit: Rx 138-1 radiological conditions represented by the eight interior survey measurements are representative of the entire length of pipe.

5.6 Scan surveys were performed for pre and post remediation purposes, using a beta-gamma GM detector on the exterior of the access point for this pipe system. The surveys are documented as survey nos. NASA-07-3204 and NASA-07-3221, performed in support of RWP PB-07-100. Both pre and post surveys showed negligible levels of activity. The scan survey results indicated activity <1,000 dpm per direct frisk. In addition, smear rag was pulled through the length of the piping section. No loose radiological contamination greater than 1,000 dpm/100cm2 was detected.

5.7 Based upon the results of the final survey measurements combined with the results of the operational survey, it is reasonable to conclude that the final survey of the accessible portion of this pipe system is appropriate to demonstrate the radiological condition of the entire pipe. Survey Unit EP Rx 138-1 demonstrates compliance with the DCGL values, as presented in Sections 3.3, 7.5 and Attachment C of the PBRF FSSP.

5.8 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 Rx 138-1 passes FSS.

Statistical Summary Table Statistical Parameter 1 Pipe Total Number of Survey Measurements 8

Number of Measurements >MDC 8

Number of Measurements Above 50% of DCGL 1

Number of Measurements Above DCGL 0

Mean 0.2107 Median 0.1174 Standard Deviation 0.1633 Maximum 0.5146 Minimum 0.0967 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.

FSS Design # EP Rx 138-1 Revision # Original Page 4 of 4 Survey Unit: Rx 138-1 6.1 A review of the survey results has shown that the dose contribution for the accessible portion of EP Rx 138-1 to be less than 1 mrem/yr. The dose contribution is estimated to be 0.211 mrem/yr based on the average of the actual gross counts.

7.0 Attachments - BSI EP/BP Survey Report -Pipe Interior Radiological Survey Form & Radiation Protection Survey Forms - DQA Worksheet -Disc containing RR for EP Rx 138-1 & Spreadsheet

SECTION 7 ATTACHMENT 1 z PAGE(S)

BSI EPIBP SURVEY REPORT Suwey Locatlon Detector-Sled #

Detector Efficiency Survey Unit Classification TBD 06-004 Piping Group SR-13 Radionuclide Distribution Sample Measured Nuclide Area FactorIEMC Used PassiFail FSS MREMNR Contribution 1

1 EP 3-9 Co-60 No Pass

<I COMMENTS:

ACTIVITYVALUES NOT BACKGROUND CORRECTED RP Engineer 1 Date

EP Rx 138-1 1" Pipe TBD 06-004 Group 1 Measurement #

gcpm ncpm Co-60 activity (total dpm)

Co-60 activity (dpm/100cm2)

Cs-137 activity (dpm/100cm2)

Eu-152 activity (dpm/100cm2)

Eu-154 activity (dpm/100cm2)

Nb-94 activity (dpm/100cm2)

Ag-108m activity (dpm/100cm2)

Unity 1

32 32 45,070 18,531 734 17,578 4,673 541 129 0.111 2

28 28 39,437 16,214 643 15,381 4,089 473 113 0.097 3

35 35 49,296 20,268 803 19,226 5,111 591 141 0.121 4

33 33 46,479 19,110 757 18,128 4,819 558 133 0.114 5

29 29 40,845 16,793 666 15,930 4,235 490 117 0.100 6

149 149 209,859 86,284 3,420 81,849 21,759 2,518 601 0.515 7

120 120 169,014 69,490 2,754 65,919 17,524 2,028 484 0.414 8

62 62 87,324 35,903 1,423 34,058 9,054 1,048 250 0.214 MEAN 0.211 MEDIAN 0.117 STD DEV 0.163 MAX 0.515 MIN 0.097 1 of 1

SECTION 7 ATTACHMENT 2 5

PAGE(S)

IBSYE~peC~awler-ti02 Revision 5 Pipe Interior Radiplogical Survey Form ate, i!:J7 : ti7 Tke:

134.5' I'

J, pipe ICM 8% (38 *(

Pipe Diamefer:

I Access Point Area-. QUAD 0 SutIding: RX Ebvatim:

System:

Typeofsurvey hv&-

Charactdzation oross coso J DetecrOf D# I sled ID# MY GI i.5~-X).WT Detector ~ a l Date:

7 I 4 - 07

~ete~tof ca ~ ~ e ~ a t e :

9 -!Y -o$

~nsram~nt: a350 - I li~stmmd ID #:

av34bB InstmmntCatDate:

'?-/'4-07 h&mmentWDueDate:

g-)'-f-&

F m the Daily Pipe Survey Detector C~nbroIBom far the Selected Detector BackgronndValue 78 Cpm M

D

~

tab la cpm Efficiency Pactor for Pipe Diameter 0,'13007/

(firam detecmr efficiency determintion)

Is the MDCrtati, acceptable?

[if no, ad@t sample tart time and recalculate bDCl&dJ GO " D". b 5. k

\\

(8'-lb Technician Signature Pipe Interior Radiological Survey

\\J REFERENCE COPY package Page I o f 3, Page 1

REFERENCECOPY

RADIATION PRO'I'ECZTON SURVEY FORB4 3 ? a g e L o f L

RADXA3XON PROmGTZON SURTEY FORM I

Page 1 of )

RP-005 / 1 Rev. 0

SECTION 7 ATTACHMENT 3 I

PAGE(S)

FSSlCharaderization Engineer (prinffsign)

CS-0912 Page 1 of 1

SECTION 7 ATTACHMENT 4 1 DISC