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: 3) Embedded Pipe surveys in EP ROLB-105 were performed using a scintillation detector optimized to measure beta energies 285 keV (IS0 7503 - 1 Table3, Tc99). This energy is lower than the beta energy for C060 (96 keV, IS0 7503-1 Table 3), assuring the nuclide of concern for DCGL is assessed during data acquisition.
: 3) Embedded Pipe surveys in EP ROLB-105 were performed using a scintillation detector optimized to measure beta energies 285 keV (IS0 7503 - 1 Table3, Tc99). This energy is lower than the beta energy for C060 (96 keV, IS0 7503-1 Table 3), assuring the nuclide of concern for DCGL is assessed during data acquisition.
Revision # Original Page 1 of 4 FSS Design # EP ROLB-105 Revisi on # Original Page 2 of 4 Survey Unit: ROLB-105 1.0 History/Description 1.1 The subject pipe is the source we ll in the ROLB -15 level.
Revision # Original Page 1 of 4 FSS Design # EP ROLB-105 Revisi on # Original Page 2 of 4 Survey Unit: ROLB-105 1.0 History/Description 1.1 The subject pipe is the source we ll in the ROLB -15 level.
1.2 EP ROLB-105 consists of 18.75" diameter piping that is approximately 44 feet in length.
1.2 EP ROLB-105 consists of 18.75" diameter piping that is approximately 44 feet in length.
2.0 Survey Design Information 2.1 EP ROLB-105 was surveyed IAW Procedure #BSI/LVS-003.
 
===2.0 Survey===
Design Information 2.1 EP ROLB-105 was surveyed IAW Procedure #BSI/LVS-003.
2.2 41 feet of the 18.75" pipe was accessible for direct survey by pipecrawler technology. The inaccessible piping includes a ~1.9 ft 2 (~0.17m 2 ) section of an end cap at one end of the well and the three feet of piping between the -18' elevation and the -15' elevation in the ROLB. The end cap and upper 3 feet of the source well are inaccessible to the pipecrawler.
2.2 41 feet of the 18.75" pipe was accessible for direct survey by pipecrawler technology. The inaccessible piping includes a ~1.9 ft 2 (~0.17m 2 ) section of an end cap at one end of the well and the three feet of piping between the -18' elevation and the -15' elevation in the ROLB. The end cap and upper 3 feet of the source well are inaccessible to the pipecrawler.
2.3 100% of the accessible piping was scanned.
2.3 100% of the accessible piping was scanned.  
2.4 Eight survey locations were selected by a random number generator for static measurements. At each accessible location four static measurements were acquired IAW BSI/LVS-003 for a total of 32 static measurements (Att. 1A).
 
===2.4 Eight===
survey locations were selected by a random number generator for static measurements. At each accessible location four static measurements were acquired IAW BSI/LVS-003 for a total of 32 static measurements (Att. 1A).
2.5 The pipe's upper 7" was survey ed and bounded under SR-99. Further direct surveys into the pipe well by personnel was not warranted based on piping history, pipecrawler survey resu lts, difficulty for personnel access, and confined space concerns.
2.5 The pipe's upper 7" was survey ed and bounded under SR-99. Further direct surveys into the pipe well by personnel was not warranted based on piping history, pipecrawler survey resu lts, difficulty for personnel access, and confined space concerns.
2.6 The surface area for the 18.75" piping is 4560 cm 2 for each foot of piping, corresponding to a piping surface area of 202340 cm 2 (20.23 m 2) for the 44 feet of embedded pipe 18.75" piping and end cap.
2.6 The surface area for the 18.75" piping is 4560 cm 2 for each foot of piping, corresponding to a piping surface area of 202340 cm 2 (20.23 m 2) for the 44 feet of embedded pipe 18.75" piping and end cap.  
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 1A & 1B.
===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 1A & 1B.
5.2 This survey unit was assessed for compliance with the release criterion attributing all activity derived dose as a 100% Co60 nuclide distribution. This is the most conservative DCGL for the facility.
5.2 This survey unit was assessed for compliance with the release criterion attributing all activity derived dose as a 100% Co60 nuclide distribution. This is the most conservative DCGL for the facility.
5.3 All scan measurement results are le ss than the Derived Concentration Guideline Level (DCGL) for radionuc lide specific EP th at corresponds to the 1 mrem/yr dose goal established in Table 3-3 of the FSSP.
5.3 All scan measurement results are le ss than the Derived Concentration Guideline Level (DCGL) for radionuc lide specific EP th at corresponds to the 1 mrem/yr dose goal established in Table 3-3 of the FSSP.
FSS Design # EP ROLB-105 Revisi on # Original Page 3 of 4 Survey Unit: ROLB-105 5.4 Scan measurements are acquired at 0.7 inches/sec for each section of accessible 18.75"piping. The documented gross cpm measurement for each scan is the highest, instantaneous, cpm count rate observed during the scan. The derived activity from these scan measurements is the most conservative quantity for that s ection of assessed piping. This conservatism is replicated when determining compliance with the DCGL release criterion. (BSI/LVS 003, WEP 05-000-6).
FSS Design # EP ROLB-105 Revisi on # Original Page 3 of 4 Survey Unit: ROLB-105 5.4 Scan measurements are acquired at 0.7 inches/sec for each section of accessible 18.75"piping. The documented gross cpm measurement for each scan is the highest, instantaneous, cpm count rate observed during the scan. The derived activity from these scan measurements is the most conservative quantity for that s ection of assessed piping. This conservatism is replicated when determining compliance with the DCGL release criterion. (BSI/LVS 003, WEP 05-000-6).
5.5 All static measurement results are less than the Derived Concentration Guideline Level (DCGL) for radionuc lide specific EP th at corresponds to the 1 mrem/yr dose goal established in Table 3-3 of the FSSP.
5.5 All static measurement results are less than the Derived Concentration Guideline Level (DCGL) for radionuc lide specific EP th at corresponds to the 1 mrem/yr dose goal established in Table 3-3 of the FSSP.  
5.6 Direct measurements of the upper bound of the source well were acquired by  FSS/Characterization personnel (Att. 2B) .The direct measurements of the upper bound of the source well indi cate no total surface activity levels >145dpm/100cm 2 (<0.001 Unity).
 
5.7 When implementing the Unity Rule, provided in Section 3.6.3 of the FSSP, the survey unit that is constituted by EP ROLB-105 passes FSS.
===5.6 Direct===
5.8 Background was not subtracted from the survey measurements and the Elevated Measurement Comparison (EMC) was not employed for this  
measurements of the upper bound of the source well were acquired by  FSS/Characterization personnel (Att. 2B) .The direct measurements of the upper bound of the source well indi cate no total surface activity levels >145dpm/100cm 2 (<0.001 Unity).
5.7 When implementing the Unity Rule, provided in Section 3.6.3 of the FSSP, the survey unit that is constituted by EP ROLB-105 passes FSS.
 
===5.8 Background===
was not subtracted from the survey measurements and the Elevated Measurement Comparison (EMC) was not employed for this  
 
survey unit.


survey unit.
===5.9 Based===
5.9 Based upon the results of the final survey measurements and the direct survey of the upper source well boundary, it is reasonable to conclude that the final survey of the accessible porti on of this pipe system is appropriate to demonstrate the radiological condition of the entire pipe. Survey Unit EP ROLB-105 demonstrates complia nce with the DCGL values, as presented in Sections 3.3, 7.5 and Attachment C of the PBRF FSSP.   
upon the results of the final survey measurements and the direct survey of the upper source well boundary, it is reasonable to conclude that the final survey of the accessible porti on of this pipe system is appropriate to demonstrate the radiological condition of the entire pipe. Survey Unit EP ROLB-105 demonstrates complia nce with the DCGL values, as presented in Sections 3.3, 7.5 and Attachment C of the PBRF FSSP.   


FSS Design # EP ROLB-105 Revisi on # Original Page 4 of 4 Survey Unit: ROLB-105 5.10 Statistical Summary Table Statistical Parameter 18.75" Pipe Total Number of Static Survey Measurements 32 Number of Measurements >MDC 32 Number of Measurements Above 50% of DCGL 0 Number of Measurements Above DCGL 0 Mean  0.009 Median  0.010 Standard Deviation 0.001 Maximum  0.012 Minimum  0.007  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 aggregat e of the total dose for both structural scenarios and soils.
FSS Design # EP ROLB-105 Revisi on # Original Page 4 of 4 Survey Unit: ROLB-105 5.10 Statistical Summary Table Statistical Parameter 18.75" Pipe Total Number of Static Survey Measurements 32 Number of Measurements >MDC 32 Number of Measurements Above 50% of DCGL 0 Number of Measurements Above DCGL 0 Mean  0.009 Median  0.010 Standard Deviation 0.001 Maximum  0.012 Minimum  0.007  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 aggregat e 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 EP ROLB-105 to be less than 1 mrem/yr. The dose contribution is estimated to be 0.009 mrem/yr based on the av erage of the actual gross counts measured.
6.1 A review of the survey results has shown that the dose contribution for EP ROLB-105 to be less than 1 mrem/yr. The dose contribution is estimated to be 0.009 mrem/yr based on the av erage of the actual gross counts measured.  
7.0 Attachments Attachment 1A - BSI EP/BP Survey Report Static & Random Number Generated Static Locations Attachment 1B - BSI EP/BP Survey Report Scan Attachment 2A - Pipe Interi or Radiological Survey Form Attachment 2B - FSS/Characterization Survey Form Attachment 3 - DQA Worksheet Attachment 4 - EP ROLB-105 SURR & Spreadsheet Disc SECTION 7 ATTACHMENT 1A 3 PAGES   
 
===7.0 Attachments===
Attachment 1A - BSI EP/BP Survey Report Static & Random Number Generated Static Locations Attachment 1B - BSI EP/BP Survey Report Scan Attachment 2A - Pipe Interi or Radiological Survey Form Attachment 2B - FSS/Characterization Survey Form Attachment 3 - DQA Worksheet Attachment 4 - EP ROLB-105 SURR & Spreadsheet Disc SECTION 7 ATTACHMENT 1A 3 PAGES   
-- --. @@& BSl EPlBP SURVEY REPORT (STATIC) Pipe ID Survey Date Survey Time Pipe Size DCGL (dpm1100cm2) 50% DCGL (~P~IIOOC~~)
-- --. @@& BSl EPlBP SURVEY REPORT (STATIC) Pipe ID Survey Date Survey Time Pipe Size DCGL (dpm1100cm2) 50% DCGL (~P~IIOOC~~)
Routine Survey QA Survey ROLB 105 03-Apr-06 1245 18.75" 240800 120400 X Survey Measurement Results Survey Location 2350-1 # Detector-Sled  
Routine Survey QA Survey ROLB 105 03-Apr-06 1245 18.75" 240800 120400 X Survey Measurement Results Survey Location 2350-1 # Detector-Sled  

Revision as of 21:32, 14 October 2018

Plum Brook Reactor Facility (Pbrf Survey Unit Release Record EP ROLB-105
ML080590183
Person / Time
Site: Plum Brook
Issue date: 02/21/2008
From: Case R, Wood G
- No Known Affiliation
To:
NRC/RGN-III
References
EP ROLB-105
Download: ML080590183 (31)
v • d • e


Text

Description Survey Unit Release Record Design # Survey Unit #(s) 4) Survey Instructions for this survey unit are incorporated into and performed in accordance with (IAW) the Babcock Services Incorporated (BSI)/LVS-003, 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 meashements.

5) Instrument efficiency determinations are developed in accordance with the BSIILVS-003, WEP 05-006, these determinations are appropriate for the types of radiation involved and the media being surveyed.

FSSICharacterization Engineer CS-0911 EP ROLB-105 ROLB- 105 1) Embedded Pipe (EP) Survey Unit ROLB-105 meets the definition of embedded pipe for Plum Brook Reactor Facility (PBRF). 2) EP ROLB-105 is a Class 1, Group 1 survey unit as per the PBRF Final Status Survey Plan (FSSP) and Technical Basis Document (TBD)-06-004.

This survey unit was not a system pipe. The piping of this survey unit was utilized as a source well. Group 1 is the most conservative piping group for dose assessment referenced in TBD-06-004.

3) Embedded Pipe surveys in EP ROLB-105 were performed using a scintillation detector optimized to measure beta energies 285 keV (IS0 7503 - 1 Table3, Tc99). This energy is lower than the beta energy for C060 (96 keV, IS0 7503-1 Table 3), assuring the nuclide of concern for DCGL is assessed during data acquisition.

Revision # Original Page 1 of 4 FSS Design # EP ROLB-105 Revisi on # Original Page 2 of 4 Survey Unit: ROLB-105 1.0 History/Description 1.1 The subject pipe is the source we ll in the ROLB -15 level.

1.2 EP ROLB-105 consists of 18.75" diameter piping that is approximately 44 feet in length.

2.0 Survey

Design Information 2.1 EP ROLB-105 was surveyed IAW Procedure #BSI/LVS-003.

2.2 41 feet of the 18.75" pipe was accessible for direct survey by pipecrawler technology. The inaccessible piping includes a ~1.9 ft 2 (~0.17m 2 ) section of an end cap at one end of the well and the three feet of piping between the -18' elevation and the -15' elevation in the ROLB. The end cap and upper 3 feet of the source well are inaccessible to the pipecrawler.

2.3 100% of the accessible piping was scanned.

2.4 Eight

survey locations were selected by a random number generator for static measurements. At each accessible location four static measurements were acquired IAW BSI/LVS-003 for a total of 32 static measurements (Att. 1A).

2.5 The pipe's upper 7" was survey ed and bounded under SR-99. Further direct surveys into the pipe well by personnel was not warranted based on piping history, pipecrawler survey resu lts, difficulty for personnel access, and confined space concerns.

2.6 The surface area for the 18.75" piping is 4560 cm 2 for each foot of piping, corresponding to a piping surface area of 202340 cm 2 (20.23 m 2) for the 44 feet of embedded pipe 18.75" piping and end cap.

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 1A & 1B.

5.2 This survey unit was assessed for compliance with the release criterion attributing all activity derived dose as a 100% Co60 nuclide distribution. This is the most conservative DCGL for the facility.

5.3 All scan measurement results are le ss than the Derived Concentration Guideline Level (DCGL) for radionuc lide specific EP th at corresponds to the 1 mrem/yr dose goal established in Table 3-3 of the FSSP.

FSS Design # EP ROLB-105 Revisi on # Original Page 3 of 4 Survey Unit: ROLB-105 5.4 Scan measurements are acquired at 0.7 inches/sec for each section of accessible 18.75"piping. The documented gross cpm measurement for each scan is the highest, instantaneous, cpm count rate observed during the scan. The derived activity from these scan measurements is the most conservative quantity for that s ection of assessed piping. This conservatism is replicated when determining compliance with the DCGL release criterion. (BSI/LVS 003, WEP 05-000-6).

5.5 All static measurement results are less than the Derived Concentration Guideline Level (DCGL) for radionuc lide specific EP th at corresponds to the 1 mrem/yr dose goal established in Table 3-3 of the FSSP.

5.6 Direct

measurements of the upper bound of the source well were acquired by FSS/Characterization personnel (Att. 2B) .The direct measurements of the upper bound of the source well indi cate no total surface activity levels >145dpm/100cm 2 (<0.001 Unity).

5.7 When implementing the Unity Rule, provided in Section 3.6.3 of the FSSP, the survey unit that is constituted by EP ROLB-105 passes FSS.

5.8 Background

was not subtracted from the survey measurements and the Elevated Measurement Comparison (EMC) was not employed for this

survey unit.

5.9 Based

upon the results of the final survey measurements and the direct survey of the upper source well boundary, it is reasonable to conclude that the final survey of the accessible porti on of this pipe system is appropriate to demonstrate the radiological condition of the entire pipe. Survey Unit EP ROLB-105 demonstrates complia nce with the DCGL values, as presented in Sections 3.3, 7.5 and Attachment C of the PBRF FSSP.

FSS Design # EP ROLB-105 Revisi on # Original Page 4 of 4 Survey Unit: ROLB-105 5.10 Statistical Summary Table Statistical Parameter 18.75" Pipe Total Number of Static Survey Measurements 32 Number of Measurements >MDC 32 Number of Measurements Above 50% of DCGL 0 Number of Measurements Above DCGL 0 Mean 0.009 Median 0.010 Standard Deviation 0.001 Maximum 0.012 Minimum 0.007 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 aggregat e 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 EP ROLB-105 to be less than 1 mrem/yr. The dose contribution is estimated to be 0.009 mrem/yr based on the av erage of the actual gross counts measured.

7.0 Attachments

Attachment 1A - BSI EP/BP Survey Report Static & Random Number Generated Static Locations Attachment 1B - BSI EP/BP Survey Report Scan Attachment 2A - Pipe Interi or Radiological Survey Form Attachment 2B - FSS/Characterization Survey Form Attachment 3 - DQA Worksheet Attachment 4 - EP ROLB-105 SURR & Spreadsheet Disc SECTION 7 ATTACHMENT 1A 3 PAGES

-- --. @@& BSl EPlBP SURVEY REPORT (STATIC) Pipe ID Survey Date Survey Time Pipe Size DCGL (dpm1100cm2) 50% DCGL (~P~IIOOC~~)

Routine Survey QA Survey ROLB 105 03-Apr-06 1245 18.75" 240800 120400 X Survey Measurement Results Survey Location 2350-1 # Detector-Sled

  1. Detector Efficiency Pipe Area Incorporated by Detector Efficiency (in cm2) Field BKG (CP~) Field MDCR (CP~) Nominal MDC (dpm/lOOcm2)

Total Number of Survey Measurements Number of Measurements

>MDC Number of Measurements Above 50% DCGL Number of Measurements Above DCGL Mean Median Standard Deviation Maximum Minimum -15 ROLB 203440 22321 0-LVS CRLR20 0.06 13 100 235.6 55.9 1,017 32 32 0 0 0.009 0.01 0 0.001 0.012 0.007 Survey Technician(s)

ROSENHAGEN Survey Unit Classification Area FactorIEMC Used PassIFail FSS MREMNR Contribution 1 No Pass < 1 COMMENTS:

ACTIVITY VALUES NOT BACKGROUND CORRECTED.

RP Engineer I Date m& /z- %Idag / r EP ROLB 105 18.75" PipeMeasurement ID #gcpmnet cpm Co-60 activity (total dpm)

Co-60 activity (dpm/100cm2)

Unity11521522,480 2,480 0.01021751752,855 2,855 0.01231651652,692 2,692 0.01141471472,398 2,398 0.01051511512,463 2,463 0.01061521522,480 2,480 0.01071471472,398 2,398 0.01081571572,561 2,561 0.01191431432,333 2,333 0.010101541542,512 2,512 0.010111611612,626 2,626 0.011121401402,284 2,284 0.009131631632,659 2,659 0.011141591592,594 2,594 0.011151361362,219 2,219 0.009161521522,480 2,480 0.010171151151,876 1,876 0.008181521522,480 2,480 0.010191261262,055 2,055 0.009201201201,958 1,958 0.008211271272,072 2,072 0.009221151151,876 1,876 0.008231421422,316 2,316 0.010241341342,186 2,186 0.009251011011,648 1,648 0.007261371372,235 2,235 0.009271091091,778 1,778 0.007281151151,876 1,876 0.008291271272,072 2,072 0.009301241242,023 2,023 0.008311161161,892 1,892 0.008321171171,909 1,909 0.008MEAN0.009MEDIAN0.010STD DEV0.001MAX0.012MIN0.007 1 OF 1 EXCEL RNG ADD-IN FOR ROLB 105 5 13 16 20 24 31 32 39 SECTION 7 ATTACHMENT 1B 3 PAGES

-r .: - w. < h&& BSI EPlBP SURVEY REPORT (SCAN) Pipe ID ROLB 105 Survey Location -15 ROLB Survey Date 331 -06 1 43-06 2350-1 # 203440 SurveyTime 1115/0800 Detector-Sled

  1. 22321 0-LVS CRLR20 Pipe Size 18.75" Detector Efficiency 0.0499 DCGL (dpm/IOOcm2) 240800 Efficiency (In cm2) 100 Pipe Area Incorporated by Detector 50% DCGL (dpm1100cm2) 120400 Field BKG (CP~) 290 / 235.6 Survey Technician(s)

ACTIVITY VALUES NOT BACKGROUND CORRECTED.

EP ROLB-105 18.75" PipeMeasurement ID #gcpmnet cpm Co-60 activity (total dpm)

Co-60 activity (dpm/100cm2)

Unity12052054,108 4,108 0.01722612615,230 5,230 0.02231761763,527 3,527 0.01541611613,226 3,226 0.01351531533,066 3,066 0.01361291292,585 2,585 0.01171501503,006 3,006 0.01281561563,126 3,126 0.01391391392,786 2,786 0.012101761763,527 3,527 0.015111541543,086 3,086 0.013121721723,447 3,447 0.014131591593,186 3,186 0.013141411412,826 2,826 0.012151871873,747 3,747 0.016161721723,447 3,447 0.014171611613,226 3,226 0.013181621623,246 3,246 0.013191781783,567 3,567 0.015201341342,685 2,685 0.011211621623,246 3,246 0.013221471472,946 2,946 0.012231641643,287 3,287 0.014241521523,046 3,046 0.013251561563,126 3,126 0.013261621623,246 3,246 0.013271691693,387 3,387 0.014281951953,908 3,908 0.016291741743,487 3,487 0.014301661663,327 3,327 0.01411941943,888 3,888 0.01621881883,768 3,768 0.01631921923,848 3,848 0.01641911913,828 3,828 0.01651761763,527 3,527 0.01561751753,507 3,507 0.01571681683,367 3,367 0.01481801803,607 3,607 0.01591711713,427 3,427 0.014101821823,647 3,647 0.015111721723,447 3,447 0.014121641643,287 3,287 0.014131641643,287 3,287 0.014142042044,088 4,088 0.017151721723,447 3,447 0.014161531533,066 3,066 0.013171631633,267 3,267 0.014 1 OF 2 EP ROLB-105 18.75" PipeMeasurement ID #gcpmnet cpm Co-60 activity (total dpm)

Co-60 activity (dpm/100cm2)

Unity181891893,788 3,788 0.016191811813,627 3,627 0.015201891893,788 3,788 0.016212232234,469 4,469 0.019222122124,248 4,248 0.018231671673,347 3,347 0.014242042044,088 4,088 0.017251841843,687 3,687 0.015261941943,888 3,888 0.016271901903,808 3,808 0.016282302304,609 4,609 0.019292342344,689 4,689 0.019302182184,369 4,369 0.018311861863,727 3,727 0.015322352354,709 4,709 0.020331901903,808 3,808 0.016341961963,928 3,928 0.016351841843,687 3,687 0.015362072074,148 4,148 0.017371961963,928 3,928 0.016382222224,449 4,449 0.018391901903,808 3,808 0.016401941943,888 3,888 0.016412102104,208 4,208 0.017421841843,687 3,687 0.015431761763,527 3,527 0.015442052054,108 4,108 0.017452132134,269 4,269 0.018461751753,507 3,507 0.015471981983,968 3,968 0.016481871873,747 3,747 0.016492072074,148 4,148 0.017502262264,529 4,529 0.019512012014,028 4,028 0.017521761763,527 3,527 0.015531921923,848 3,848 0.016MEAN0.015MEDIAN0.015STD DEV0.002MAX0.022MIN0.011 2 OF 2 SECTION 7 ATTACHMENT 2A 11 PAGES

-- - BSVLVSPipeCrawler-003 Original Pipe Interior Radiological Survey Form Date: 3 .3 /- 0 b Time: /I/ r Pipe ID#: DL &!A-fi- /cpipe Diameter:

/a %' Access Point Area: 2-115 Building:

70 Lt.3 Elevation: - IS- System: kkb 5'k& &~/ds Type of Survey Investigation - Characterization - Final Survey Other r/' Gross V' Cs137 Detector ID# / Sled ID# c:l-t/h,~23$lo/

7% ,/& Detector Cal Date: /Ir;.N&/ti'\*0 G Detector Cal Due Date: - Q7 hstrument:

235- t ~nstrument ID #: S'Q~YVO Instrument Cal Date: I 5- /rZW - 9 & Instrument Cal Due Date: /bR. AAf - 0 7 From the Daily Pipe Survey Detector Control Form for the Selected Detector Background Value 2 96' cpm MDC~,,, N7 Jf-f-qprn Efficiency Factor for Pipe Diameter 01 D 'f49 (from detector efficiency determination)

MDCSsbc 35bv dpmt im cm2 Is the MDC,,,,, acceptable?

No (if no, adjust sample count time and recalculate IvfDCLJ Comments: - , %RJC+ - Technician Signature f' 52- LZ+$&. f/ - Pipe Interior Radiological Survey v Package Page I of 3 REFERENCE COPY' Attachment 3, Page 1

- Pipe Interior Radiological Survey Form (Continuation Form)

-. BSI/LVSPipeCrawler-003 Original Date: 3- 3/*0L Pipe ID#: SrlAf,- Pipe Diameter:

18 % I' Access Point Area: ;?d d Building:

  • L& Elevation: - )s System: C& 5- I I I I I I I I b 3 Package Page - of - Attachment 3, Page 2
g. V!T . .. . . - - - ---- ---f- .. k, -- : A,. ! i ii : ,, b ,. 1;- . r ,. , . : I.. _ , . PADlATt0d i-; : ~~srfunstJr 1' . kEF'AsE Q'M 3 , Cee3.cncNr) i : L.. --+ 5 -rur uen~ 06 1.r 4 wlt~i.* rrenxe .. . , z>LIMG OF*. QIL~C~ COUKONC; eocn Ce~s~ncw) - ..y..

- BSVLVSPipeCrawler-003 Original Pipe Interior Radiological Survey Form Date: q..- 3 , C 6 Time: ofla C) Pipe 1D#: && ~&f& Pipe Diameter:

18% " Access Point Area: '/X Building:

flo.-~j Elevation:

-/S System: a&. S~& Type of Survey Investigation J' Characterization - Final Survey /C Other X Gross C06O Cs137 Detector ID# / Sled tD# ~q~/l b /d23 1 7'~ d#-,/& Detector Cal Date: 1 $.in&& - o b Detector Cal Due Date: /I-. r*rA-A -a 7 Instrument:

23%- Instrument ID #: dd3YY b Instrument Cal Date: /s' fl &L - ab Instrument Cal Due Date: / S. fvlWe-- C -7 From the Daily Pipe Survey Detector Con.trol Form for the Selected Detector Background Value a 3 $- & cpm MDCRs-1, SF(4 ,, Efficiency Factor for Pipe Dlameter 0.0499 (from detector efficiency determination)

MDCstatIc 3Zl b - dpm/ i cm2 Is the MDC,,,, acceptable?

a NO (if no, adjust sample count tune and recalculate MDC%& comments: " fkp/~/7~ h4&T7 ; 3 cr*.,& C?J *A' . FLU? YC--/ - I h#/e~f Technician Signature

// Pipe Interior Radiological Survey Package Page 1 of REFERENCE COPY Attachment 3, Page 1

-- BSI/LVSPipeCrawler-003 Original Pipe Interior Radiological Suwey Form (Continuation Form) Date: 4.3-0 d Pipe ID#: p,Schp?F //OT Pipe Diameter:

/S 3~" Access Point Area: ,/5- & 4 Building:

70~0 Elevation:

-1 ,c System: &d-k +&A REFERENCECOPY Package page 2 of Attachment 3, Page 2 BSIILVSPipeCrawler-002 Revision 4 Pipe Interior Radiological Survey Form (Continuation Form) Date: &?,o b '( Pipe ID#: &,&-S+&+ I b_T Pipe Diameter:

/ 8 '14 Access Point Area:

di16'@ . Building:

723.d Elevation: System: d4 L S ?5+d~L REFERENCE COPY J Package Page 3 of - Attachment 3, Page 2 /-

- BSILVSPipeCrawler-003 Original Pipe Interior Radiological Survey Form Date: .5' 0~6 Time: /24s Pipe ID#: g&i 5#&/0.,' Pipe Diameter:

/D Yq " Access Point Area: '/gfi6G Building:

C~ZULB Elevation: -I 5 System: &A ~n(ss~7 Type of Survey Investigation Characterizat~on Final Survey l(i Other )9 Gross J C06O Cs137 Detector ID# 1 Sled ID# f%-//C- / $9 3 0 I ?C y4-//lu Detector Cal Date:

/s /l'?kl ' 0 6 Detector Cal Due Date: /S-- @/fwd 0 7 Instrument:

$352- Instrument ID #: #35% Instrument Cal Date: S -&f& '0 L. Instrument Cal Due Date:

,5- Pi'W .L)7 From the Daily Pipe Survey Detector Control Form for the Selected Detector Background Value 6735.6 cpm MDCRstatic 3-j, 9 CPm Efficiency Factor for Pipe Diameter 0. 0 & 13 (from detector efficiency determination)

MDCstatic 1017 d~ml 100 cm2 Is the hlDCs,ti, acceptable?

NO (if no, adjust sample count time and recalculate MDCR,~) Comments:

4 ZA-40, ;JbS I@ Technician Signature Pipe Interior Radiological Survey f Package Page 1 of JSf Attachment 3, Page I

- BSb'LVSPipeCrawler-003 Original Pipe Interior Radiological Survey Form (Continuation Form) Date: 4 2, (u Pipe ID#: &&. j fls Pipe Diameter:

/83Lfrf Access Point Area: - I>- R 0 i-& Building:

Elevation: - IA- System: /& Sd4-Fr REFERENCE COPY 1 4" Package Page 2 of $f Attachment 3, Page 2 BSIILVSPipeCrawler-003 Original REFERENCECOPY n

EXCEL RNG ADD-IN FOR ROLB 105 REFERENCE COPY SECTION 7 ATTACHMENT 2B 3 PAGES

~adiolo~i61 Instrument Data FSSICHARACTERIZATION SURVEY FORM Fnstrument

~ype 1 2350-1 1 Instrument Type 1 NIA ( Instrument Type I NIA I Serial Number / 193707 / Serial Number 1 NIA I Serial Number I NIA Survey Unit No. 1 GI. ~ue ate I 911 0108 I Cal. Due Date I NIA I Cal. Due Date I NIA NIA I probe TYP~ 1 44-1 16 I Probe Type I NIA I probe ~ype I NIA NIA I Serial Number I 223210 / Serial Number 1 NIA I Serial Number I NIA ClassificaUon Survey Number Survey Location I Cal. Due date 1 911 0108 I Cal. Due date I NIA 1 Cal. Due date I NIA CHSS23 ROLE Basement - Source Pit Survey Request (SR) # I Efficiency I 42.7% I Efficiency I NIA I ERciency I NIA 99 Reason1 Type 1 ABCR (CW) I 265 1 ABCR (CW) 1 NIA I Background (cpm) 1 NIA CharaterizationlScans

& Statics Technician rpdrm.los

.. . I I I I .. . - .. . Survey Summary - Technician Field Notes The purpose of this survey was to perform scan and statics of the source pit in the ROLB Basement.

Date of Survey MDC Scan (dpm~00cm~

Source Checks Sat IXI Unsat Supervisor Review I ~-o&c/ p z/pC &. / / Date of Review 2 - 2 /- 3 8 R. Fowler1 R R 2/21/08 1630 Miscellaneous Suwev Data Source Checks Technician ,prrm3*l., Time of suwey NIA MDC Scan (dpm~ 0Ocm2) Sat 0922 NIA Unsat MDC Scan (dpm1100cm')

Source Checks NIA Sat Unsat ERlZATlON SURVEY FO BCR # = Background Count Rate

- - FSSICHARACTERIZATION SURVEY FORM (continuation Sheet) Page 3 of&

SECTION 7 ATTACHMENT 3 1 PAGE Page 1 of 1 SECTION 7 ATTACHMENT 4 1 DISC

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