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| issue date = 08/16/2007
| issue date = 08/16/2007
| title = Nasa Plum Brook Reactor, Embedded Pipe Survey Records
| title = Nasa Plum Brook Reactor, Embedded Pipe Survey Records
| author name = Peecook K M
| author name = Peecook K
| author affiliation = US National Aeronautics & Space Admin (NASA), John H. Glenn Research Ctr at Lewis Field
| author affiliation = US National Aeronautics & Space Admin (NASA), John H. Glenn Research Ctr at Lewis Field
| addressee name = Snell W G
| addressee name = Snell W
| addressee affiliation = NRC/RGN-III/DNMS/DB
| addressee affiliation = NRC/RGN-III/DNMS/DB
| docket = 05000030, 05000185
| docket = 05000030, 05000185
Line 15: Line 15:


=Text=
=Text=
{{#Wiki_filter:National Aeronautics and Space Administration John H. Glenn Research Center Lewis Field Plum Brook Station Sandusky, OH 44870 Reply to Attn of: QD August 16,2007 U.S. NRC Region I11 Mr. William G. Snell, RIII/DNMS/DB 2443 Warrenville Road Suite 210 Lisle. IL 60532-4352
{{#Wiki_filter:}}
___
 
==Subject:==
Submittal of Embedded Pipe Survey Unit Release Records, Plum Brook Reactor Facility, License No. TR-3, Docket No. 50-30, and License No. R-93, Docket No, 50- 185
 
==Dear Mr. Snell:==
 
Enclosed for your review and assessment are copies of the following completed embedded pipe survey unit release records: Survey Unit Release Record EP-Rx 130 Survey Unit Release Record EP-1.38 Survey Unit Release Record EP- 1.4 1A-4 Survey Unit Release Record EP-Rx 155 Survey Unit Release Record EP- 1.64 1 -8 Survey Unit Release Record EP-Rx 150D Survey Unit Release Record EP-Rx 161 Survey Unit Release Record EP- 1.44 Survey Unit Release Record EP-Rx 148D Survey Unit Release Record EP-Rx 149 Survey Unit Release Record EP-Rx 13 1 Survey Unit Release Record EP- 1.4 1 A-6 Survey Unit Release Record EP- 1.42A-4 Survey Unit Release Record EP-Rx 1 13D Survey Unit Release Record EP- 1.64 1-4 Survey Unit Release Record EP-HL- 1 1 1 Survey Unit Release Record EP-Rx 137 Survey Unit Release Record EP-Rx 084 Survey Unit Release Record EP- 152D As discussed during your on site inspection on June 25 through June 27, 2007, we will periodically submit the completed survey unit release records for your inspection. Further, as discussed at the exit meeting, it is our intention to begin grouting of the embedded piping that has been shown by the Final Status Survey to meet the dose criteria of Subpart E, Section 20.1402, 10 CFR Part 20. -. RECEIVED AUG 1 7 2007 2 If you have no issues with the records under this submittal, we will begin the grouting process on August 20,2007. Should you have any questions or need additional information, please contact Mr.
William Stoner of my staff, NASA Plum Brook Station, 6100 Columbus Avenue, Sandusky, OH 44870, at (4 19) 62 1 - 3349, or Mr. John Thomas of my staff, NASA Plum Brook Station, 6 100 Columbus Avenue, Sandusky, OH 44870, at (419) 621- 3357.
Sincerely, Keith M. Peecook Decommissioning Program Manager Survey Unit Release Record
~- Design # Survey Unit #(s) Description EP-Rx-084 1 Revision#
I Original 1 Page 1 of 3 Rx-084 1) Embedded Pipe (EP) Survey Unit Rx-084 meets the definition of embedded pipe for Plum Brook Reactor Facility (PBRF). 2) EP Rx-084 is a Class 1, Group 3.1 survey unit as per the PBRF Final Status Survey Plan (FSSP) and Technical Basis Document (7'BD)-06-004.
: 3) Surveys in EP Rx-084 were performed using a scintillation detector optimized to measure gamma energies representative of Cs-137. Sample #EP 3-8 fiom 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 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 BSVLVS-002, WEP 05-006, these determinations are appropriate for the types of radiation involved and the media being surveyed.
Date: Approval Signatures FSS/Characterization Engineer I n/ 0 COPY cs-o9/1 FSS Design # EP Rx-084 Revision # Original 1.0 2.0 3.0 4.0 5.0 Page 2 of 3 HistoryDescription 1.1 1.2 Survey Design Information 2.1 2.2 The subject pipe system is the 4" floor drain line from the Room 22 trench, which drains to the sump. EP Rx-084 consists of 4" diameter piping that is approximately 6 feet in length. EP Rx-084 was surveyed IAW Procedure
#BSL/LVS-002.
1 W! of the 4" ID pipe was accessible for survey. The accessible 4" ID pipe was surveyed by static measurement at one foot increments, for a total of 6 survey measurements.
Surface area for the 4" ID piping is 973 cm2 for each foot of pi ing, corresponding to a total 4" ID piping surface area of 5,837 cm (0.6 m2) for the entire length of (approximately 6') of 4" piping.. 2.3 P Survey Unit Measurement hations/Data 3.1 Pipe interior radiological survey forms are provided in Attachment 2 of this release record.
Survey Unit Investigations/Results 4.1 None Data Assessment Results 5.1 5.2 Data assessment results are provided in the EP/Buried Pipe (BP)
Survey Report provided in Attachment
: 1. All measurement results are less than the Derived Concentration Guideline Level (DCGL) for radionuclide specific EP that corresponds to the 1 mredyr dose goal established in Table 3-3 of the FSSP. When implementing the Unity Rule, provided in Section 3.6.3 of the FSSP, and applying the Nuclide Fraction (NF), provided in Tl3D-06-004, the survey unit that is constituted by EP Rx-084 passes FSS. Background was not subtracted fi-om the survey measurements and the Elevated Measurement Comparison (EMC) was not employed for this survey unit. 5.3 5.4 I I Number of Measurements
>MDC I FSS Design # EP Rx-084 I Revision # Original 1 ~age3of3 1 6 Survey Unit:
Rx-084 - ~ Number of Measurements Above 50% of DCGL Number of Measurements Above DCGL 6.0 7.0 0 0 5.5 Mean Median Standard Deviation Maximum Statistical Summary Table 0.0052 0.0051 0.0009 0.0065 4" Pipe Statistical Parameter L Total Number of Survey Measurements 1 6 Minimum 10.0037 Documentation of evaluations pertaining to compliance with the unrestricted use limit of 25 mredyr and dose contributions fiom 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 EP Rx-084 to be less than 1 mredyr. The dose contribution is estimated to be 0.005 rnredyr based on the average of the actual gross counts measured.
Attachments Attachment 1 - BSI EPBP Survey Report Attachment 2 - Pipe Interior Radiological Survey Form Attachment 3 - DQA Worksheet SECTION 7 ATTACHMENT 1 z PAGE(S) 
-- I BSI EPIBP SURVEY REPORT Pipe ID RxQW Survey Location Rm-22 trench Survey Date 19-Apr-07 23!500-1#
2 1223 Detector-Sled
# 44-1 591247696101 Median 0.0051 Standard Deviation 0.0009 Maximum 0.0065 Minimum 0.0037 STOCK Sunrey Technician(s)
ACTIVITY VALUES NOT BACKGROUND CORRECTED RP Engineer I Date BJ & wo-07 71'1012007 EP Rx-084 4" Pipe TBD 06404 Group 3.1 1of1 I SECTION 7 ATTACHMENT 2 2 PAGE(S)
BSULVSPipeCrawler-002 Revision 4 Pipe Interior Radiological Survey Form Date: 4//9'/0 7 Time: 081 7 - Pipe ID#: 5?4 Pipe Diameter:
-4 ' , Access Point Area: k,&- mw,+ Building:
@ Elevation:
 
===7.7 System===
&j- /lv g SUP4 3( Other / Type of Survey Investigation Characterization Final Survey Gross Ab C06O cs / Detector ID# / Sled ID# 49- yq -2 $76 4G I lo 1 Detector Cal Date: 11 /I >-/&I 6 Detector Cal Due.Date:
I I 1 5/07 Instrument:
3,3 1-0 -1 Instrument ID #: Zfrtz3 Instrument Cal Date: 1 5+(& Instrument Cal Due Date: I(/[ +q I From the Daily Pipe Survey Detector Control Form for the Selected Detector BackgroundValue GI 7 cpm MDCR,,fic I it 2 CPm Efficiency Factor for Pipe Diameter 0 00 0 Zb (from detector efficiency determination)
Is the MDC,,,,, acceptable?
@ No (if no, adjust sample count time and recalculate h4DC%,,,,)
Comments:
I 7-t- Is;?& v ~rrirPuvE Technician Signature Pipe Interior Radiological Survey REFERENCE COPY 0 Package Page 1 of & Attachment 3, Page 1 
'I # I J ,tcg- i- b Qr, - Y' . -3 &---OD- ! .' r'. I- -2 !I $ t SECTION 7 ATTACHMXNT 3 I PAGE(S) 
~~ ~ DQA Check Sheet - Design # EP Rx-084 Revision # Original Survey Unit
# EP Rx-084 Preliminary Data Review' Answers to the following questions should be fully documented in the Survey Unit Release Record Have surveys been performed in accordance with survey instructions in the Survey Design? Yes No NIA 1, X X 2. Is the inxmektion 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 embeddedburied piping static measurements below the DCGLw ? X 4. Was the instrumentation MDC for structure scan measurements, soil scan measurements, and static measurements or soil samples addressed in the survey design? embeddedhuried piping scan measurements below the DCGLW, or, if not, was the need for additional
: 5. Was the instrumentation MDC for volumetric measurements and smear analysis .z 10% DCGLw ? X X Ix/ 5, 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?
: 3. 3. Is the data set comprised of qualified measurement results collected in accordance with the survey design, which accurately reflects the radiological status of the facility?
Were 'Special Methods" for data collection property applied for the survey unit under review?
X X Graphical Data Review 1. Has a posting plot been created?
I I lx 2. 3. Has a histogram (or other frequency plot) been created? Have other graphical data tools been created to assist in analyzing the data?
X X Data Analysis I. Are all sample measurements below the DCGLw (Class 1 & 2), or 0.5 DCGLw (Class 3)? 1x1 I ~~ 2. Is the mean of the sample data DCGLw? X X X 3. If elevated areas have been identified by scans andlor sampling, is the average activity in each elevated area
: 4. Is the result of the Elevated Measurements Test
< 1 .O? DCGLEMC (Class l), < DCGLW (Class 2), or ~0.5 DCGLW (Class 311 5. :mments: Is the result of the statistical test (S+ for Sign Test or W, for WRS Test) the critical value? X I' Page 1 of 1 pZ-l CS-0912 I Rev0 1 Design # EP-Rx 148D Survey Unit #(s) Revision ## Original Page 1 of 3 Description Rx 148D 1) Embedded Pipe (EP) Survey Unit Rx 148D meets the definition of embedded pipe for Plum Brook Reactor Facility (PBRF). 2) EP Rx 148D is a Class 1, Group 2 survey unit as per the PBRF Find Status Survey Plan (FSSP) and Technical Basis Document (TBD)-06-004.
: 3) Surveys in EP Rx 148D were performed using a scintillation detector optimized to measure gamma energies representative of CO-60. Sample #EP 2- 1 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 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 BSVLVS-002, WEP 05-006, these determinations are appropriate for the types of radiation involved and the media being surveyed.
FSS Design # EP Rx 148D Revision # Original 1 .o 2.0 3.0 4.0 5.0 Page 2 of 3 HistoryDescription 1.1 1.2 Survey Design Information 2.1 2.2 The subject pipe system is the 0.75" Quad "B" system line.
EP Rx 148D is approximately 16 feet in length. EP Rx 148D was surveyed IAW Procedure #BSI/LVS-002.
100% of the 0.75" ID pipe was accessible for survey. The accessible 0.75" ID pipe was surveyed by static measurement at one foot increments, for a total of 16 survey measurements. Surface area for the 0.75" ID piping is 182 cm2 for each foot of pi ing, corresponding to a total 0.75" ID piping surface area of 3,101 cm (0.3 m2) for the entire length of (16) of 0.75" piping.. 2.3 4 Survey Unit Measurement Locations/Data 3.1 Pipe interior radiological survey forms are provided in Attachment 2 of this release record. Survey Unit InvestigationslResults 4.1 None Data Assessment Results 5.1 5.2 Data assessment results are provided in the EP/Buried Pipe (BP) Survey Report provided in Attachment
: 1. All measurement results are less than the Derived Concentration Guideline Level (DCGL) for radionuclide specific EP that corresponds to the 1 mredyr dose goal established in Table 3-3 of the FSSP. 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 148D passes FSS. Background was not subtracted
&om the survey measurements and the Elevated Measurement Comparison (EMC) was not employed for this survey unit.
5.3 5.4 FSS Design ## EP Rx 148D 5.5 Revision # Original Page 3 of 3 Statistical Summary Table Total Number of Survey Measurements Number of Measurements
>MDC Number of Measurements Above 50% of DCGL Number of Measurements Above DCGL I I 0.75" 16 12 0 0 Statistical Parameter Mean Median Standard Deviation Maximum 0.0441 ' 0.0423 0.0147 0.0725 I Minimum 0.0161 6.0 Documentation of evaluations pertaining to compliance with the unrestricted use limit of 25 mredyr 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 EP Rx 148D to be less than I mredyr. The dose contribution is estimated to be 0.044 mredyr based on the average of the actual gross counts. 7.0 Attachments Attachment 1 - BSI EPBP Survey Report Attachment 2 - Pipe Interior Radiological Survey Form Attachment 3 - DQA Worksheet Attachment 4 -Disc containing RR for EP Rx 1.48D & Spreadsheet s -- SECTION 7 ATTACHMENT 1 2 PAGE(S) clii BSI EPJBP SURVEY REPORT Survey Location 2350-1 # DetectorSled
# Pipe ID --I- Survey Date 02-Aug-06
-27 Trench Loop Drain 189094 0047-no sled survey Time Pipe Size 0.75" DCGL 2.41 E45 Routine Survey 1 O:% Field BKG 1-1 18.3 Field MDCRmm) 17.8 Nominal MDC wpnnooantl 7,631 > Survey Measurement Results Total Number of Survey Measurements Number of Measurements Above 50% DCGL Number of Measurements Above DCGL 16 Number of Measurements MDC 12 0 0 Mean 0.0611 Median 0.0423 Standard Deviation 0.0147 Maximum 0.0725 Minimum 0.0161 STOCK Survey Technician@)
Measured Nuclide C0-60 Pass/Fail FSS Pass Area FactorlEMC Used NO MREM/YR Contribution
<l OMMENTS: CTlVlTY VALUES NOT BACKGROUND CORRECTED RP Engineer I Date 7117RM17 EP Rx 1480 0.75" Pipe TBD 06-004 Group 2 4 14 E 1; ~- ncpm 10 11 ._ ~~ 15 7 __ - __-- C0-80 activity (total dpm) 16.949 ___ ~___ 161949 20,339 30,508 23,729 6,780 11,864 - 25,424 15,254 25,424 11,864 __ 23,729 15,254 207339 .__ - ____ __. ___ -- - __ ___-. Cos0 activity Cs-137 activity (dpmll OOcm2) (dpmll OOcm2) 9,292 4,818
__ 5,300 7,433 3,855 9.292 4.818 __ ._ _- ._ - - -~ __ ___ 11,150 5,782 - 16,725 8,673 __ 13,009 __ 6,745 3,717 1,927 3,373 6,504 7,227 -- __ 13,938 8,363 4,336 3,373 6,504 6,745 _~- 13,009 4,336 8,363 ~- 11~150 __ - 5,782 __ .____ _ ~~ -~ - - 13,938- - 7,227 __ - -- __ - - __- ___ ____ ~-_____- Eu-162 activity Eu-154 activity Nb-94 activity AglOBm activity (dpmll OOcm2) (dpmll OOcm2) (dpmll OOcm2) (dpmll OOcm2) ___ .- - 62 ~ 44 4 .- 214 267 77 54 5 92 65 5 32 1 .- ~ ______ _- 48 1 139 98 8 108 76 6 374 31 22 2 107 54 38 3 187 401 69- 49 4 24 1 82 7 401 116 187 54 38 3 374 1 08 76 6 - 69 49 4 24 1 92 65 5 32 1 -_ - __ __ ~____ ____- . 82 7 116 .. .__ -. ___- ____ ~____ - ._-_______________
__--- ___ - Unity - 0.04( 0.04~ 0.03; 0.04( 0.04I 0.07; 0.0% 0.01t 0.021 0.06( 0.03t 0.06( 0.021 0.03 0.03t 0.041 - -_ - ___ - .- ~- __ __ ~- ~- - - 0.04 0.04: 0.01! 0.07: 0.0m .~ - - lofl SECTION 7 ATTACHMENT 2 3 PAGE(S)
I BSI/L,VG~~~C~~I~~-OO~
Revision 4 Pipe Interior Radiologid Survey 
-- I BSYLVSPipeCrawler-002 Revision 4 Pipe Interior Radiological Survey Form (Continuation Form) Ic!z Access Point Area: - 27 ' wd System: kDP Drnrt/ I v 75 - '* Pipe Diameter:
Date: Pipe ID#: Building:
(!& Elevation:
Package Page 2 of 3 I REFERENCE COPY I Attachment 3, Page 2 
 
SECTION 7 ATTACHMENT 3 I PAGE(S)
DQA Check Sheet Survey Unit # ~~ Design # I EP Rx 148D I Revision # I Original I ~ EP Rx 148D Yes X X X X Preliminary Data Review' No NIA X X X Answers to the following questions should be fully documented in the Survey Unit
: 1. Has a posting plot been created? Release Record Have surveys been performed in accordance with survey instructions in the Survey Design? 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? 1. 2. X - ~~ 3. 4. Is the instrumentation MDC for embeddedlburied piping static measurements below the DCGLw ? Was the instrumentation MDC for structure scan measurements, soil scan measurements, and ernbeddedhuried piping scan measurements below the DCGLw, or, if not, was the need for additional static measurements or soil samples addressed in the survey design? 5. Was the instrumentation MDC for volumetric measurements and smear analysis < 10% DCGLW ? 6. Were the MDCs and assumptions used to develop them appropriate for the instruments and techniques used to perform the survey?
~~ 2. Has a histogram (or other frequency plot) been created? 3. Have other graphical data tools been created to assist in analyzing the data?
: 7. Were the survey methods used to collect data proper for the types of radiation involved and for the media being surveyed?
X X 6. 9. Were "Special Methods' for data collection properly applied for the survey unit under review? Is the data set comprised of qualified measurement results collected in accordance with the survey design, which accurately reflects the radiological status of the facility? Graphical Data Review XI I Data Analysis 1. Are all sample measurements below the DCGLw (Class 1 81 2), or 0.5 DCGLW (Class 3)? 1x1 I 2. Is the mean of the sample data DCGLW? X x 3. 4. Is the result of the Elevated Measurements Test 1 .O? X If elevated areas have been identified by scans andlor sampling, is the average activity in each elevated area .C DCGLEMC (Class l), < DCGLW (Class 2), or <0.5 DCGLw (Class 3)? ~ 5. Comments:
Is the result of the statistical test (S+ for Sign Test or W, for WRS Test) 1: the critical value? X cs-0912 1 :: 1 Page 1 of 1 SECTION 7 ATTACHMENT 4 1 DISC Survey Unit Release Record EP-Rx 137 Design # Revision # Original Page 1 of 3 Survey Unit #(s) Description
: 2) EP Rx 137 is a Class 1, Group 2 survey unit as per the PBRF Final Status Survey Plan (FSSP) and Technical Basis Document (TBD)-06-004.
: 3) Surveys in EP Rx 137 were performed using a scintillation detector optimized to measure gamma energies representative of CO-60. Sample #EP 2-1 hm 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 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 BSI/LVS-002, WEP 05-006, these determinations are appropriate for the types of radiation involved and the media being surveyed.
Date: Approval Signatures 1 FSS/Characterization Manager I ,////'/fl cs-o9/1 1 1 Y FSS Design # EP Rx 137 1 .o 2.0 3.0 4.0 5.0 Revision # Original Page 2 of 3 History Description 1.1 1.2 Survey Design Information 2.1 2.2 The subject pipe system is the 1.5 inch line The pipe is approximately 9 feet in length. EP Rx 137 was surveyed IAW Procedure #BSI/LVS-002.
100% of the 1.5" ID pipe was accessible for survey.
The accessible 1.5" ID pipe was surveyed by static measurement at one foot increments, for a total of 9 survey measurements.
Surface area for the 1.5" ID piping is 365 cm2 for each foot of pi ing, corresponding to a total 1.5" ID piping surface area of 3,283 cm (0.3 m2) for the entire length of (approximately 9') of 1.5" piping.. 2.3 4 Survey Unit Measurement LocationsData 3.1 Pipe interior radiological survey forms are provided in Attachment 2 of this release record. Survey Unit InvestigationsResults 4.1 None Data Assessment Results 5.1 5.2 Data assessment results are provided in the EPBuried Pipe (BP) Survey Report provided in Attachment
: 1. 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. When implementing the Unity Rule, provided in Section 3.6.3 of the FSSP, and applying the Nuclide Fraction 0, provided in TBD-06-004, 5.3 __ _~_~~ - passemr Kri37 ~~ __~ - the survey untt that is co&tuted b Y Background was not subtracted from the survey measurements and the Elevated Measurement Comparison (EMC) was not employed for this survey unit. 5.4 FSS Design ## EP Rx 137 Revision # Ori@ 5.5 Statistical Summary Table Page 3 of 3 6.0 ~- ~ 7.0 Number of Measurements
>MDC Number of Measurements Above 50% of DCGL Number of Measurements Above DCGL Mean Median Statistical Parameter 4 0 0 0.0097 0.0085 1.5" Pipe I Total Number of Survey Measurements 19 I Standard Deviation 10.0034 I Maximum 10.0149 Minimum 10.0042 Documentation of evaluations pertaining to compliance with the unrestricted use limit of 25 mrem4r and dose contributions hm 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 EP Rx 137 to be less than 1 mredyr. The dose contribution is estimated to be 0.010 mrendyr based on the average of the actual gross counts measured.
___ __ ___ _____.____---
Attachments Attachment I - BSI EPBP Survey Report Attachment 2 - Pipe Interior Radiological Survey Form Attachment 3 - DQA Worksheet Attachment 4 - SURR EP RX 137 8z Spreadsheet Disc SECTION 7 ATTACHMENT 1 z PAGE(S)
BSI EPIBP SURVEY REPORT I Pi- ID Survey Date Survey Time L Pipe Size I Rx 137 22-Few 10:50 1.5 2.41 EW 0.3 X Survey Location 23500-1 # DetectorSkd
# Detector Efficiency Nominal MDC 1dpn-4 jurvey Measurement Results Drain Line 44.2 212223 4442 # 212701l121 0.00028 365 4.9 10.6 9,688 Total Number of Survey Measurements Number of Measurements Above 50% DCGL Number of Measurements Above DCGL 9 Number of Measuments
>MDC 4 0 0 Mean 0.0097 Median 0.0085 Standard Deviation 0.0034 Maximum 0.0149 Minimum I 0.0042 DEBRAUX Survey Technician(s)
Survey Unit Classification I 1 TBD OR004 Piaina G~UD 7 I SR-13 Radionudide Distribution Sample I EP 2-1 Measured Nudide Am Factor/EMC Used No MREMlYR Contribution
<l Pass/Fail FSS Pass COMMENTS:
ACTMTY VALUES NOT BACKGROUND CORRECTED 7 07 RP Engineer I Date 1 7 07 RP Engineer I Date TJ-7 2.2 Cs-137 actlvity (dpm/100cm2)
-+= Eu-IS2 activity (dpm1100cm2)
I-- 1,777 1,015 76 1 508 1,015 1,015 1,523 1,523 1,269 -+- 28 16 12 8 16 16 24 24 20 __ 1.5 ~- 5,357 1 3,571 2 7.143 21 7.143 2.5 8.929 ---+-- EP Rx 1.37 1.5" Pipe TBD 06-004 Group 2 1 I I Cogg activity (dpm1100cm2) 3,426 1,958 1,468 979 1,958 1,958 2,937 2,937 2.447 I lofl i 11 --I-+ 14 Nb-94 aetlvity (dpmll OOcm2) 2 1 1 0 1 99 56 42 28 56 1 1 56 85 1 1 85 70 MEAN MEDIAN 5TD DEV w MAIN - Unity - 0.01 f O.OOE 0.OM O.O@ O.OOE 0.001 0.01 I 0.01: 0.01 1 0.01( 0.001 0.00: 0.01! 0.001 - -
SECTION 7 ATTACHMENT 2 z PAGE@)
I BSVLVSPipeCrawler-002 Revision 4 Pipe Interior Radiological Survey Form Date: 2-tZ-06 Time: 1 om 5 m?, Pipe ID#: kp 37 Pipe Diameter:
f .a- AccessPointArea:
c Building:
e* Elevation: - System: Type of Survey Investigation Characterization FinalSurvey7( 0th Gross Co60 J cs DetectorID#/SledID#
YY-62 @Z# 270f / /z/ Detector Cal Date: //-/ 7- - Detector Cal Due Date: d //I 7-3 & Instrument:
23- -t Instnunent ID #: UILLL3 Instrument Cal Date: //-r 7 ~4- Instrument Cal Due Date: // 77-06 From the Daily Pipe Survey Detector Control Form for the Selected Detector BackgroundValue qcr) cpm Efficiency Factor for Pipe Diameter 0. 0 0 02 8 Is the MDCsuc acceptable?
@ No (if no, adjust sample count time and recalculate MDCL) MDcRstaac pb cpm cm2 MDCStati, 468s- dpm/ too --- @om detector efficiency determination) tW / __ - Technician Signature C. 0 Pipe Interior Radiological Survey REFERENCECOPY 0 Package Page 1 of 2 Attachment 3, Page 1 i / REFERENCE COPY 0 I I SECTION 7 ATTACHMENT 3 PAGE(S) I I Design # EP Rx 137 Revision # Survey Unit# [ EP Rx 137 Original Answers to the following questions should be fully documented in the Survey Unit Release Record Have surveys been performed in accordance with survey instructions in the Survey Design? Yes X 1. I I lx 2. Is the instrumentation MDC for structure static measurements below the DCGLw for Class 1 and 2 survey units, or Mow 0.5 DCGLw for Class 3 sunrey units? No 3. 4. Was the instrumentation MDC for structure scan measurements, soil scan measurements, and static measurements or soil samples addressed in the survey design? Is the instrumentation MDC for embeddedlburied piping static measurements below the DCGLw ? embeddedlburied piping scan measurements below the DCGLW, or, if not, was the need for additional X X 3. Is the data set comprised of qualified measurement results collected in accordance with the survey design, which accurately reflects the radiolosicat status of the facilii 5. 5. 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 colled data proper for the types of radiation involved and for the media being surveyed?
: 3. Was the instrumentation MDC for volumetric measurements and smear analysis 10% DCGLw ? Were 'Special Methods" for data collection properly applied for the survey unit under review? X X X 1. Has a posting plot been created?
Ix 2. 3. Has a histogram (or other frequency plot) been created? Have other graphical data tools been created to assist in analyzing the data? Y Page 1 of 1 X X cs-0912 Kl 2. 3. If elevated areas have been identified by scans and/or sampling, is the average activity in each elevated area < DCGLEMC (Class l), < DCGLW (Class 2), or (0.5 DCGLw (Class 3)? 4. Is the result of the Elevated Measurements Test < I .O? Is the mean of the sample data < WGLw? X X X I 5. Is the result of the statistical test (S+ for Sign Test or Wr for WRS Test) 2 the critical value? X I SECTION 7 ATTACHMENT 4 1 DISC Design ## Survey Unit #(s) Description Survey Unit Release Record EP-1.44 I Revision ## 1 Original 1 Page 1 of 3 1.44 1) Embedded Pipe (EP) Survey Unit 1.44 meets the definition of embedded pipe for Plum Brook Reactor Facility (PBRF). 2) EP 1.44 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 1.44 were performed using a scintillation detector optimized to measure gamma energies representative of Co-60. Sample #EP 3-9 ffom Survey Request (SR)-13 was referenced for this decision.
: 4) Survey Instructions for this survey unit are incorporated into and performed in accordance with (LAW) 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.
: 5) Instrument efficiency determinations are developed in accordance with the BSILVS-002, WEP 05-006, these determinations are appropriate for the types of radiation involved and the media being surveyed.
COPY 1 Approval Signatures Date: FSS/Characterkation Engineer aractenzahon cs-o9/ 1 I I FSS Design ## EP 1.44 Revision # Original - Page 2 of 3 1 .O 2.0 3.0 4.0 5.0 History/Description 1.1 The subject pipe system is the 2" and 2.5" suction header from the Sub Pile Room sump to the drain trench on the Rx Building -25 foot elevation.
The function of this pipe was to convey water from the top of the Sub Pile Room sump to the drain trench on the Rx building -25ft., where the pipe is currently breached.
EP 1.44 consists of 2" and 2.5" diameter piping that is approximately 54 feet. 1.2 Survey Design Information 2.1 2.2 EP 1.44 was surveyed MW Procedure
#BSVLVS-O02.
100% of the 2" and 2.5" ID pipe was accessible for survey. The pipe was surveyed by static measurement at one foot increments, for a total of 54 survey measurements.
Surface area for the 50' run of 2" ID piping is 486 cm2 for each foot of piping and the 4' run of 2.5" ID piping is 603 cmz for each foot of piping corresponding to a total piping surface area of 26,756 cm2 (2.7 m2) for the entire length (approximately 54') of piping. 2.3 Survey Unit Measurement LocationsData 3.1 Pipe interior radiological survey forms are provided in Attachment 2 of this release record.
Survey Unit InvestigatiordResults 4.1 None Data Assessment Results 5.1 5.2 5.3 5.4 Data assessment results are provided in the EPBuried Pipe (SP) Survey All measurement results are less than the Derived Concentration Guideline Level (DCGL) for radionuclide specific EP that corresponds to the 1 mdyr dose goal established in Table 3-3 of the FSSP. 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 1.44 passes FSS. Background was not subtracted fiom the survey measurements and the Elevated Measurement Comparison (EMC) was not employed for this survey unit. __ Report provided in Attachment
: 1. ~ -~
FSS Design # EP 1.44 5.5 Statistical Summary Table Revision # Original Page 3 of 3 2"12.5" Pipe Statistical Parameter Total Number of Survey Measurements Number of Measurements
>MDC Number of Measurements Above 5Ooh of DCGL 54 54 0 Number of Measurements Above DCGL Mean 0 0.21 12 I Maximum Median Standard Deviation I 0.4079 I 0.1898 0.0697 I Minimum [ 0.1085 I Documentation of evaluations perbining to compliance with the unrestricted use limit of 25 dyr and dose contributions fiom 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 EP 1.44 to be less than 1 mredyr. The dose contribution is estimated to be 0.21 1 mredyr based on the average of the actual gross counts measured.
~ - --- Attachment 1 - BSI EPBP Survey Report Attachment 2 - Pipe Interior Radiological Survey Form Attachment 3 - DQA Worksheet Attachment 4 - SURR EP 1.44 & Spreadsheet 1 SECTION 7 ATTACHMENT 1 .3 PAGE(S) 1 .u Survey Location Pip ID 1-19-06,1-20-06 8 2350-1 # survey Date 2-22-06 Sunmy Time 1400 I0810 / 0846 Detector-Sled It Pipe size 2- Detector Efficiency Subpile suctions -27 212223 204402-121, 212701- 121 0.00026 / 0.0002 Measured Nudide Area FactorEMC Used Pdail FSS MREMNR Contribution 7HM007 c0-60 No Pass el - I COMMENTS:
ACTlvlTY VALUES NOT WCKGROUND CORRECTED fld 7-10-07 RP Engineer I Date EP 1.44 Iwl I 25 39.5 39.5 1511923 j 31 1232 26 31.5 31.5 121,154 1 24,906 27 40 40 153,846 ~ 31,627 28 49 49 188,462 1 38,743 29 37.5 37.5 144,231 I 29,65(3 30 32 32 123,077 I 25,302 31 43.5 43.5 167,308 34,394 40.5 40.5 155,769 1 32,022 12 421 331208 13 321 321 123.077 1 1 25,302 1,238 987 1,254 ~- 1,536 _- - 1,175 1,003 1,363 1,269 29,627 7,876 91 1-- 21a 220 28,126 7,477 865 207 30,377 8,075 934 ~- 223 23,626 6,281 727 1 74 30,002 7,976 923 36,752 9,770 1,131 27c) 24,001 6,380 738 178 32,627 - 8,673 1,004 240 __ ___- Cs-137 activity Eu-162 activity Eu-164 activity Nb-94 actlvlty Ag-1OSm activity (dpm11ooCm2) (dpm1100cm2) (dpm1100cm2) (dpmn00cm2) (dpm1100em2) 1.222 I 29.251 I 7.776 I 900 I 215 ~~ 924 22,126 5,882 68 1 163 212 1,207 28,876 7,677 888 174 987 23,626 6,281 727 204 854 229 __ 1,301 31,127 8,275 958 __ - _- -_____ 1,159 27,751 7,377 - 1.536 36.752 9.770 1.131 270 -- 1 0.179 - 1 of2 
- to 1'0 IOP'O ILO'O 161'0 ' 12'0 z2.0 '1E'O '1E.O 18E.O .PZO .Z*'O IOP'O :OP'O X.0 )CE'O ILZ'O tPZ'0 )ZZ'O e61.0 181'0 11z-0 DZ'O 1LL.O . 1 1'0 :61'0 EZ'O I81'0 .I_ __.- - ___ - Qun - - w* EZS'L 8S 1'* 1 P9c Ei-3'1 8S1'EL rn 898'1 8S0'91 C8Z LLC'C 691'01 9LE 69S' 1 6SS'E 1 LLP 966'1 LPZ'L 1 _- 1 LP EL6' 1 8tQ'L 1 1w 9t%' 1 1S6'Sl __- 69* 9S'1 6SE'E 1 szc C9*'1 P9L'CL 68Z CLZ'1 8W'O 1 WZ LOL'1 lLS'6 __ EZZ E6 SL0'8 ozz EZ6 9L6'L SPZ I LZO'1 1 6L8'8 - EZ I 186 ] VLP'8 - ZS2'8E ~ 1 86s' 1 PZE'OP v91'961 I 19 1s 10s 800'19 I lE1'Z 99L'ES 8E9'19Z 189 89 16P - ZSL'OE (382' 1 8 1P'ZE Z69'LS 1 1P 1P sc - LL8'LE *89' 1 626'68 1EZ'PGC s-09 S'OS PE ZOS'1E 91*'1 80Z'EE 8ES'L91 IP ZP E* I 'I 1 If SECTION 7 ATTACHMENT 2 7 PAGE(S)
Pipe Interior Radiological Survey Form Date: /4'P L Time: l$m -2.7 p~~k4 Elevation: - 25 Access Point Area:
1 , Building:
';7 & fh I+ System: sifd /';d GL<+ Pipe Diameter: Pipe ID # 1. f14/ Type of Survey Investigation Characterization Sled Size a"v,;.-/~
ZQ&?$Z, inch Cal Due Date: //- /7-4 Detector:
LJY-I 7 Cal Date: I/- 17-0b Instrument:
33S-l-4 Instrument ID #: ai aaa3 Cal Date: I I '17 -0)- Cal Due Date: / / 9 VL 6a-a Other f do yJ0 a
* s'i.4 /a/ Detector ID #: - From the Daily Pipe Survey Detector Control Form for the Selected Detector Background Value $9 cpm Efficiency Factor for Pipe Diameter 0 I 0 0 03 MDCSCltlC 783b dpm/100cm2 MDCRStatX
/if f cpm (taken fiom detector - ,+ -., Is the MDC,,, acceptable?
@ No (if no, adjust sample count time and recalculate MDCbQC) - Comiients:
A/' 71 i4c Pipe Interior Radiological Survey Radiological Survey Commenced: Date:
/# / F
* LJ L Time: / yd3 REFERENCECOPY 0 Package Page 1 of 2 Attachment 3, Page 1 
 
Pipe Interior Radiological Survey Form Date: /-LO -0 1& Time: OB/ 0 Building:
y Elevation: - 2 7 Access Point Area: 7-7Z-d L, t( System: qqGp 1 CG 5 uc7f 8 Pipe Diameter:
ir Pipe ID # 1, YL( Type of Survey Investigation Characterization
@-yo Other / 5& Sled Size 3"dI NyC hlLbe 6/21 inch Detector:
9Yf-L72 Detector ID #: LO Y"1Z - p-/ Cal Date: //-/ 7-0 6 Cal Due Date: /k/7-049 Instrument:
am-, Instrument ID #: ZMZ23 Cal Date: / /L/ 7-QT Cal Due Date: //-I73 6 From the Daily Pipe Survey Detector Control Form for the Selected Detector Background Value
-541 cpm MDcRstatlc
/O47 cpm Efficiency Factor for Pipe Diameter 0, OoOa (taken from detector MDcstatlc 5305 dpm/100cm2 Comments:
CLW~~/UL~QT~O~
/V~/VI~ - 51d&~3 126 P(f'@- Is the MDCsUhc acceptable?
@ No (if no, adjust sample count time and recalculate MDCb,) ClAvS? fk/m - Pipe Interior Radiological Survey z- Package Page 1 of - c REFERENCE COPY u Attachment 3, Page 1 I z Package Page
&of - REFERENCE COPY Attachment 3, Page 2 
 
1 B WLVSPipeCrawler-002 Revision 4 Pipe Interior Radiological Survey Form L'UD\yL 6.~471 L : */ R-e?d#- S.1 Date: I-22-0 b Time: Pipe ID#: 1, qc( Pipe Diameter:
f&S Access Point Area: ,I p Building:
% Elevation:
* - YS System: /t;/mpu CliL L/&S Type of Survey Investigation Characterization Final Survey ->( Other Gross Co60 J cs Detector ID# 1 Sled ID# ry-6 2 a770r I f 21 J Detector Cal Date:
I /-I 7- 0 Detector Cal Due Date: I/-/ 7-0 b Instrument:
7 3 m -( Instrument ID #: a27 v Instrument Cal Date: //77-0c Instrument Cal Due Date: /l-f 7-0 6 From the Daily Pipe Survey Detector Control Form for the Selected Detector Background Value yc cpm MDCRstatic 13.b cpm Efficiency Factor for Pipe Diameter MDCStatK 5305 dPd \vQ cm2 Is the MDCSbtic acceptable?
Comments:
fN1JtG -3clfLJW 01 ooaz (from detector efficiency determination)
@ No (if no, adjust sampTe count time and recalculate MDCR,& Technician Signature r ,ot& Pipe Interior Radiological Survey -- 9 10 3 Package Page 1 of REFERENCE COPY Attachment 3, Page 1 
 
SECTION 7 ATTACHMENT 3 .I PAGE(S)
Design # EP 1.44 Revision # Original Survey Unit # EP 1.44 5. Were theMDCs and assumptions used to develop them appropriate for the instruments and techniques - used to perform the survey?
Answers to the following questions should be fully documented in the Survey Unit Release Record Yes No NIA 1. 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 sunrey units? 3. Is the instrumentation MDC for embeddedhuried piping static measurements below the DCGLw ? Have surveys been performed in accordance with survey instructions in the Survey Design? X X X X 3. If elevated areas have been identified by scans andlor sampling, is the average activity in each elevated area < DCGLEMC (Class l), DCGLW (Class 2), or ~0.5 DCGLw (Class 3)? I 4. was theinstrumentation MDC for structure scan measurements, soil scan measurements, and embedded/buried piping scan measurements below the DCGLw, or, if not, was the need for additional static measurements or soil samples addressed in the survey design? Was the instrumentation MDC for volumetric measurements and smear analysis 10% DCGLw ? 5. X X Comments:
: 7. Were the survey methods used to collect data proper for the types of radiation involved and for the media being surveyed?
: 5. 9. Is the data set comprised of qualied measurement results collected in accordance with the survey design, which accurately reflects the radiological status of the facility?
Were "Special Methods" for data collection properly applied for the survey unit under review? a4 FSS/Charaderization Engineer (prlnt/$ign)
FSS/ Characterization Manager (prinffsign)
X X X Page 1 of 1 1. 2. Has a posting plot been created? Has a histoaram (or other freauency plot) been created?
X X 3. Have other graphical data tools been created to assist in analyzing the data?
X 1. 2. Is the mean of the sample data DCGLw? Are all sample measurements below the DCGLw (Class 1 8 2), or 0.5 DCGLW (Class 3)? X X 4. 5. Is the result of the Elevated Measurements Test 1 .O? Is the result of the statistical test (S+ for Sign Test or W, for WRS Test) 2 the critical value? X X SECTION 7 ATTACHMENT 4 1 DISC Survey Unit Release Record EP-Rx 152D Design # Survey Unit #(s) Revision # Original Page 1 of 3 Description
: 2) EP Rx 152D is a Class I, Group 2 survey unit as per the PBRF Final Status Survey Plan (FSSP) and Technical Basis Document (TBD)-06-004.
: 3) Surveys in EP Rx 152D were performed using a scintillation detector optimized to measure gamma energies representative of CO-60.
Sample #EP 2- 1 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 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.
Date: Approval Signatures I I FSS/Characterization Engineer I 9" / 7-/? -07 Technical Reviewer (FSS/Characterization Engineer) FSS/Characterization Manager Y 7-23-07 //' El CS-0911 0 COPY FSS Design # EP Rx 152D Revision # Original 1 .o 2.0 3.0 4.0 5.0 Page 2 of 3 HistoryDescription 1.1 1.2 Survey Design Information 2.1 The subject pipe system is the 0.75" Quad "B" system line. EP Rx 152D is approximately 15 feet in length. EP Rx 152D was surveyed IAW Procedure #BSI/LVS-002.
2.2 100% of the 0.75" ID pipe was accessible for survey. The accesslulc 75" ID pipe was surveyed by static measurement at one foot increments, for a total of 15 survey measurements.
Surface area for the 0.75" ID piping is 182 cm2 for each foot of pi ing, corresponding to a total 0.75" ID piping surface area of 2,736 cm (0.3 m2) for the entire length of (1 5') of 0.75" piping.. 2.3 4 Survey Unit Measurement Locations/Data 3.1 Pipe interior radiological survey forms are provided in Attachment 2 of this release record. Survey Unit InvestigationsResults 4.1 None Data Assessment Results 5.1 5.2 Data assessment results are provided in the EPBuried Pipe (BP) Survey Report provided in Attachment
: 1. All measurement results are less than the Derived Concentration Guideline Level (DCGL) for radionuclide specific EP that corresponds to the 1 mredyr dose goal established in Table 3-3 of the FSSP. 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 152D passes FSS. Background was not subtracted from the survey measurements and the Elevated Measurement Comparison (EMC) was not employed for this survey unit. 5.3 5.4 FSS Design # EP Rx 152D Survey Unit:
Rx 152D Revision # Original Page 3 of 3 J 5.5 Statistical Summary Table Number of Measurements
>MDC Number of Measurements Above 50% of DCGL 0.75" Pipe Statistical Parameter 12 0 I Total Number of Survey Measurements I 15 I Number of Measurements Above DCGL 0 I Mean 0.051 3 I Median 10.0524 I Maximum Minimum I Standard Oeviation 0.1047 0.0201 10.0216 1 6.0 Documentation of evaluations pertaining to compliance with the unrestricted use limit of 25 mredyr and dose contributions fiom 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 EP Rx 152D to be less than 1 mredyr. The dose contribution is estimated to be 0.05 1 mredyr based on the average of the actual gross counts. 7.0 Attachments Attachment 1 - BSI EPBP Survey Report Attachment 2 - Pipe Interior Radiological Survey Form Attachment 3 - DQA Worksheet Attachment 4 -Disc containing RR for EP Rx 1.52D & Spreadsheet SECTION 7 ATTACHMENT 1 z PAGE(S)
Fl!r . .. ,I BSI EP/BP SURVEY REPORT I I Survey Location ~~ ~ Survey Time SurveyDate 1 02-Aug-06 I I 2350-1 # 13:08 I 1 -27' Trench Loop Drain DCGL idpnn-ml) 189094 2.41E95 plph b=wmd b~ - BMns), Iln -4 1 82 0.3 Field BKGmt 18.3 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 DetectorSled
# 15 12 0 0 0.0513 0.0524 0.0216 0.1047 004740 sled II Pipe Size I 0.75" Detector Efficiency 0.00059 Routine Survey I X II Field MDCR (spn) I 17.8 I 0.0201 Minimum STOCK Survey Technician(s)
:OMMENTS:
CTIVITY VALUES NOT BACKGROUND CORRECTED BdM/ 747-07 RP Engineer I Date 7/17/2007 EP Rx 152D 0.75" Pipe TBD 06-004 Group 2 - Unity - 0.03 0.06( 0.03t 0.061 0.04f 0.07; 0.02( 0.W 0.05: 0.10! 0.03: 0.03( 0.05: 0.05 0.024 0.05 0.05: 0.10! 0.021 ___ __ -~ ___ __. -- _- ___ - 0.02: . -- - Cs-137 activity (dpm/l OOcm2) Nb-94 activity (dpmll OOcrn2) Ag-108rn activity (dpmll00cm2)
Cod0 activity (dpm1100cm2)
Eu-lS2 activlty Eu-164 activity (dpd100cm2) (dpmllOOcrn2) 374 6,745 7,227 - 4,336 8,191 5,782 9,154 2,409 5,300 6,264 12,527 3,855 4,336 6,264 - 6,745 2.891 -__ ___ _- __ - __ __ __~__ -- -__ _____ __ __ _- - 13,009 13,938 8,363 15,796 11,150 17,654 4,646 10,221 ~ __ 12,079 24,159 7,433 8,363 12,079 __ 13,009 5,575 -- -__-- - __ __ -~ -- -- -__ - - ___-_ .___ ____ __ -_ _____- ____ ___ 23,729 25,424 15,254 28,814 20,339 32,203 8,475 18,644 22,034 44,068 13,559 15,254 23,729 10,169 _ - ___ _- __ ___~ ___- ____- ~~ - _~ _____ ____- 22,034 - ___. ___ ____ 40 1 24 1 455 - ~. 69 49 8 5 92 131 92 65 103 146 27 39 85 60 100 71 141 200 69 49 71 76 46 33 _- _I ~- _- ~- - 62 44 __- - 100 108 - 32 1 508 ~- 9 2 5 134 294 695 214 24 1 374 -__. 348 ._ - Ma i 60 - f --5! 11 11 6 12 4 4 - 6 6 3 - MEAN V~EDIAN SD DN MAX -. _- MIN 1 of 1 I I SECTION 7 ATTACHMENT 2 3 PAGE(S)
BSL'LVSPipeCrawler-002 Revision 4 dpd 1 OOcm' Gross Net fiom Opening (min) cpm cpm Positioc Feet hto Pipe Count Time Gross counts # Pipe Interior Radiological Survey Form 1 f le- /e fl //=L 2 2 ! I$ fE 3 3 - 4 4 9 17 17 1% a 6 6 Fj 'I 9 5 Date: Pipe ID#: Building:
fl \a 1 l i Time: /,'3u8' Access Point Area: -2 7 mt+ I System: Lbpp r>&H KJq Pipe Diameter:
a 75 c. vp Elevation:
7 + 17 Y 9 13 8 I I 10 i /D 26 11 9 I ~ I 1 S li 13 I 26 I 4 /.I REFERENCECOPY Package Page 1 of 3 Attachment 3, Page 1 BSYLVSPipeCrawler-002 Revision 4 I Pipe Interior Radiological Survey Form (Continuation Form) Date: g[z/O6 Pipe ID#: iYL Pipe Diameter:
875 Access Point Area:
Building:
kg Elevation: - 27 System: d / I / REFERENCE COPY 0 Attachment 3, Page 2 
 
SECTION 7 ATTACHMENT 3 / PAGE(S)
DQA Check Sheet Design # 1 EP Rx 152D I Revision # I Original I ~~ - ~- Survey Unit # EP Rx 152D Preliminary Data Review' Yes No N/A Answers to the following questions should be fully documented in the Survey Unit Release Record Have surveys been performed in accordance with survey instructions in the Survey Design? I. X ~ I 2. Is the instrumentation MDC for structure static measurements below the DCGLw for Class 1 and 2 survev units, or below 0.5 DCGLW for Class 3 survev units? ~ ~~ ~ ~~ 3. t, Is the instrumentation MDC for embeddedlburied piping static measurements below the DCGLw ? X Was the instrumentation MDC for structure scan measurements, soil scan measurements, and embeddedhried piping scan measurements below the DCGLw, or, if not, was the need for additional static measurements or soil samples addressed in the survey desian? I - X ~ ~~~ ~ ~ ___ ~ ~~ __ 5. Was the instrumentation MDC for volumetric measurements and smear analysis 10% DCGLw ? 5. Were the MDCs and assumptions used to develop them appropriate for the instruments and techniques used to perform the survey?
I Tx IxI 7. Were the survey methods used to collect data proper for the types of radiation involved and for the media being Surveyed?
: 3. 3. Were "Special Methods" for data collection properly applied for the survey unit under review? X X Is the data set comprised of qualified measurement results collected in accordance with the survey design, which accurately reflects the radiological status of the facility? Graphical Data Review I. Has a posting plot been created?
I I Ix ?. Has a histogram (or other frequency plot) been created?
: 3. Have other graphical data tools been created to assist in analyzing the data? X X Data Analysis I. Are all sample measurements below the DCGLw (Class 1 8 2), or 0.5 DCGLw (Class 3)? 1x1 I ?. X 3. t. Is the result of the Elevated Measurements Test 1 .O? X Is the mean of the sample data c DCGLW? X If elevated areas have been identified by scans and/or sampling, is the average activity in each elevated area c DCGLEMC (Class I), < DCGLw (Class 2), or <0.5 DCGLW (Class 3)? 5. hrnments:
Is the result of the statistical test (S+ for Sign Test or W, for WRS Test) 2 the critical value? X -- Page 1 of 1 Kl CS-09/2 SECTION 7 ATTACHMENT 4 1 DISC I EP-Rx 149 Revision # Original Design # Page 1 of 3 Survey Unit #(s) Description
: 2) EP Rx 149 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 Rx 149 were performed using a scintillation detector optimized to measure gamma energies representative of CO-60. Sample #EP 3-9 from Survey Request (SR)- 1 3 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 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 BSULVS-002, WEP 05-006, these determinations are appropriate for the types of radiation involved and the media being surveyed.
0 COPY cs-0911 1 :: 1 Survey Unit: Rx 149 1 .o 2.0 3.0 4.0 5.0 History Description 1.1 1.2 Survey Design Information 2.1 2.2 The subject pipe is the drain line from the dry annulus inside the CV to the drain trench on the Rx Building -25 foot elevation.
EP Rx 149 consists of 3" diameter piping that is approximately 20 feet in length. EP Rx 149 was surveyed LAW Procedure
#BSI/LVS-002.
100% of the 3" ID pipe was accessible for survey. The accessible 3" ID pipe was surveyed by static measurement at one foot increments, for a total of 20 survey measurements. Surface area for the 3" ID piping is 730 cm2 for each foot of piping, corresponding to a total 3" ID piping surface area of 14,593 cm2 (1.5 m2) for the entire length of (approximately 20') of 3" piping.. 2.3 Survey Unit Measurement Locations,Data 3.1 Pipe interior radiological survey forms are provided in Attachment 2 of this release record. Survey Unit Investigations/Results 4.1 None Data Assessment Results 5.1 5.2 Data assessment results are provided in the EPBuried Pipe @P) Survey Report provided in Attachment
: 1. All measurement results are less than the Derived Concentration Guideline Level (DCGL) for radionuclide specific EP that corresponds to the 1 rnredyr dose god established in Table 3-3 of the FSSP. 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 149 passes FSS. Background was not subtracted from the survey measurements and the Elevated Measurement Comparison (EMC) was not employed for this survey unit. 5.3 5.4 FSS Design
# EP Rx 149 Survey Unit: Rx 149 Revision # Origrnal 5.5 Statistical Summary Table ~~ ~~ Total Number of Survey Measurements 20 Number of Measurements
>MDC 1 0 0 Number of Measurements Above 50% of DCGL Number of Measurements Above DCGL Mean 0.0106 I Statistical Parameter Standard Deviation Maximum Minimum 0.0038 0.01 88 0.0025 I Median I0.0100 I 6.0 7.0 Documenbtion 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 EP Rx 149 to be less than 1 mredyr. The dose contribution is estimated to be 0.01 mdyr based on the average of the actual gross counts measured.
Attachments Attachment 1 - BSI EP5P Survey Report Attachment 2 - Pipe Interior Radiological Survey Form Attachment 3 - DQA Worksheet Attachment 4 - SURR EP RX 149 & Spreadsheet Disc
_- I SECTION 7 ATTACHMENT 1 2 PAGE(S)
__ . . BSI EP/BP SURVEY REPORT Survey Date 20-Feb-06 Survey Tim 07:55 Pipe ID I Rx 149 I! Survey Location I CV -38el. 2350-1 # 212223 Detector-Sled W 44-62/21 2701
-1 21 Pipe Sb 3 1.5 Routine Survey X DCGL imooau) 2.41E95 PlPAm-m QA survey r: ?' < , &*., . i *... '' - 'ij l. ' ' ' Detector Efficiency 0.00013 g.*trit=pm~-em-wman2) 730 Field BKG 1cpm1 4.7 Field WDCRrpl) 10.4 Nominal MDC 2,779 --- :OMMENTS:
CTNITY VALUES NOT BACKGROUND CORRECTED Total Number of Survey Measurements Number of Measurements
>MDC Number of Measurements Above 50% DCGL Number of Measurements Above DCGL Mean Median Maximum Minimum Standard Deviation RP Engineer I Date 20 1 0 0 0.0106 0.01 00 0.0188 0.0025 0.0038 7/12/2007 EP Rx 149 3" Pipe TBD 06-004 Group 1
* C Q) E Cos0 actlvtty C0-60 acthrlty Cs-137 activity 3 gcpm ncpm (totaldpm) (dpm1100cm2) (dpm1100cm2) - Eu-152 activity (dpmllOOcm2)
Eu454actlvlty , Nb-Wactivity (dpm1100cm2) (dpm1100crn2) . 11 10 17 11 17 12 16 14 10 10 12 16 22 6 3 17 11 ___-- ___. 40 346 1 346 40 518 I 60 397 ~ 46 5s- - 40 __ __ -- 0.00s O.Ol? 0.00s Om 0.011 0.01: 0.01; 0.oot 0.oot 0.01* 0.01: O.OO! 0.00: O.Ol! -0:OOE ___ om 0.03 622 397 ~__ 72 46 Ag-106m-l (dpmll OOcm2) L!!iIyf ~~ ~- 622 449 570 518 346 346 449 570 795 225 104 622 397 _______ .____ ---- 72 52 66 60 40 40 52 66 92 26 12 72 46 . __ 0.01 MEDIAN STD DEV 0.00: 1of1 SECTION 7 ATTACEIMENT 2 3 PAGE(S)
BSyLVSPipeCrawler-002 Revision 4 Pipe Interior Radiological Survey Form Date: 2-2 &)& Time: 02.rr Pipe ID#: I YCj Pipe Diameter:
Access Point Area: spa ccwkf Q~\I Building:
RX Elevation:
System: I Type of Survey Investigation Characterization Final Survey Other / Gross (2060 J cs Detector Cal Date: /j-[7-&+ T Detector Cal Due Date:
I/-/ 7- Ob Detector ID# / Sled ID# 4Y42 'Z/27@/ i /a/ Instrument:
7 m?- ( Instrument ID #: 2i27 23 Instrument Cal Date: Instrument Cal Due Date: / I-/ 7 c 0 From the Daily Pipe Survey Detector Control Form for the Selected Detector BackgroundValue q.7 cpm Efficiency Factor for Pipe Diameter MDCstatx 277G dpd !Do cmz Is the MDCSbuC acceptable?
a No (if no, adjwt saqle count time and recalculate MDCL,,) hDC%lZtIC
/PI 9 CPm 0 0 00 17 (from detector efficiencpdeterrnination)
F.l.-mfil fill c I NII\ 2-Lt b r( L/N(B e. sz, / rmP /e 775 Technician Signature Pipe Interior Radiological Survey Packagepage 1 of2 REFERENCE COPY Attachment 3, Page 1 I BSVLVSPipeCrawler-002 Revision 4 Pipe Interior Radiological Survey Form (Continuation Form) Date: 2'7 0- G3 Access Point Area: 5 P/L c wi21 f3 T) f PipeD#: Rx iyC) Pipe Diameter:
It Building:
j2-x Elevation:
System: Package Page AofJ Attachment 3, Page 2 
 
i SECTION 7 ATTACHMENT 3 I PAGE@) 
~ ~ DQA Check Sheet Design # EP Rx 149 Revision # Original Survey Unit # EP 149 Preliminary Data Review' Answers to the following questions should be fully documented in the Survey Unit Release Record Yes No NIA 1. 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. 4. Have surveys been performed in accordance with survey instructions in the Survey Design?
X X Is the instrumentation MDC for embeddedlburied piping static measurements below the DCGLw ? embeddedlburied piping scan measurements below the DCGLw, or, if not, was the need for additional X Was the instrumentation MDC for structure scan measurements, soil scan measurements, and static measurements or soil samples addressed in the survey design? X 5. Was the instrumentation MDC for volumetric measurements and smear analysis 10% DCGLW ? I I 1 X -~ 6. Were the MDCs and assumptions used to develop them appropriate for the instruments and techniques used to nerform the survey? ~~ ~ X X 7. Were the survey methods used to collect data proper for the types of radiation involved and for the media being surveyed?
: 8. 9. Is the data set comprised of qualified measurement results collected in accordance with the survey design, which accurately refleds the radiological status of the facility?
Were 'Special Methods" for data collection properly applied for the survey unit under review? X Graphical Data Review ~~~~ ~ 1. Has a posting plot been created? X 2. Has a histogram (or other frequency plot) been created?
X 3. Have other graphical data tools been mated to assist in analyzing the data?
: 1. Are all sample measurements below the DCGLw (Class 1 8 2), or 0.5 DCGLw (Class 3)? X Data Analysis 1x1 2. Is the mean of the sample data DCGLw? X X 3. If elevated areas have been 'Mentitied by scans and/or sampling, is the average activity in each elevated area < DCGLEW (Class l), < DCGLW (Class 2), or <0.5 DCGLW (Class 3)? 4. 5. Is the result of the Elevated Measurements Test < 1 .O? Is the result of the statistical test (S+ for Sign Test or Wr for WRS Test) 2 the critical value? X X Comments:
FSS/Charaderization Engineer (prinVsign)
Date 7-12 47 FSSl Characterization Manager (print/sign)
Date &D7 I- Page 1 of 1 SECTION 7 ATTACIXMENT 4 1 DISC I a COPY Design ## Survey Unit #Is) Description Survey Unit Release Record ~~ ~ EP-Rx 130 1 Revision#
I Original 1 Page 1 of 3 Rx 130 1) Embedded Pipe (EP) Survey Unit Rx 130 meets the definition of embedded pipe for Plum Brook Reactor Facility (PBRF). 2) EP Rx 130 is a Class 1, Group 2 survey unit as per the PBRF Final Status Survey Plan (FSSP) and Technical Basis Document (TBD)-06-004.
: 3) Surveys in EP Rx 130 were performed using a scintillation detector optimized to measure gamma energies representative of CO-60. Sample #EP 2- 2 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 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.
FSS Design # EP Rx 130 Revision # Original I Survey Unit: Rx 130 I Page 2 of 3 1.0 2.0 3.0 4.0 5.0 HistoryDescription 1.1 1.2 Survey Design Wormation 2.1 2.2 The subject pipe system is the 3" Quad "A" spare system line. EP Rx 130 consists of approximately 2 1 feet in length from the Reactor Building -25' elevation, Quad "A" to the Sub Pile Room. EP Rx 130 was surveyed LAW Procedure
#BSI/LVS-002.
100% of the 3" ID pipe was accessible for survey.
The accessible 3" ID pipe was surveyed by static measurement at one foot increments, for a total of 21 survey measurements.
Surface area for the 3" ID piping is 730 cm2 for each foot of piping, corresponding to a total 3" ID piping surface area of 15,323 cm2 (1.5 m2) for the entire length of (21 ') of 3" piping. 2.3 Survey Unit Measurement LocationsData 3.1 Pipe interior radiological survey forms are provided in Attachment 2 of this release record. Survey Unit InvestigationslResults 4.1 None Data Assessment Results 5.1 5.2 Data assessment results are provided in the EPBuried Pipe (BP) Survey Report provided in Attachment
: 1. All measurement results are less than the Derived Concentration Guideline Level (DCGL) for radionuclide specific EP that corresponds to the 1 mredyr dose goal established in Table 3-3 of the FSSP.
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 130 passes FSS. Background was not subtracted from the survey measurements and the Elevated Measurement Comparison (EMC) was not employed for this survey unit. 5.3 5.4 FSS Design # EP Rx 130 Survey Unit:
Rx 130 I Revision # Original Page 3 of 3 5.5 Statistical Summary Table i Statistical Parameter 3" Pipe 6.0 7.0 Total Number of Survey Measurements Number of Measurements
>MDC Number of Measurements Above 50% of DCGL Number of Measurements Above DCGL Mean Median Standard Deviation Maximum Minimum Documentation of evaluations pertaining to compliance with the unrestricted use limit of 25 mredyr 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 EP Rx 130 to be less than 1 dyr. The dose contribution is estimated to be 0.036 mredyr based on the average of the actual gross counts. Attachments Attachment 1 - BSI EPBP Survey Report Attachment 2 - Pipe Interior Radiological Survey Form Attachment 3 - DQA Worksheet Attachment 4 -Disc containing RR for EP Rx 130 & Spreadsheet 21 17 0 0 0.0358 0.0183 0.0481 0.2070 0.01 05 I SECTION 7 ATTACHMENT 1 z PAGE(S)
BSI EP/BP SURVEY REPORT Survey Location 2350-1 # DetectorSled
# Pipe ID Survey Date 12-Jan-06
-25 el. Quad A 203488 44-62 2127011121
~~ Survey Time I 1 08:33 pipesire I ~ Detector Efficiency PIP- hmmmd LY - Emdmwlln -21 Fild BKGmm) Field MDCRlm) Nominal MDC ~dpnnmsnq 3" 0.00013 730 22 385 2,779 DCGL #pyrmsmli Routine Survey 2.41 E95 1.5 X Total Number of Survey Measurements Number of Measurements
>MDC Number of Measurements Above 50% DCGL Number of Measurements Above DCGL 3Zev-Measurement Results 21 17 0 0 SR-13 Radionuclide Distribution Sample EP 2-2 Measured Nuclide CO-60 Pass/Fail FSS Pass Area FaaorEMC Used No MREWR Conbibution
<l :OMMENTS:
CTIVITY VALUES NOT BACKGROUND CORRECTED 8-12 47 RP Engineer I Date 8/13/2007 EP Rx 130 3" Pipe TBD 06-004 Group 2 3t C E Cod0 activity COS0 activity Cs-137 activity Eu-152 activity Eu-154 activity e! gcpm ncpm (total dpm) (dpmllOOcm2) (dpm1100cm2) (dpm11Wcm2) (dpm1100cm2) a (1D u , NM4 activity Ag-108m activity (dpn\rlOOcm2) (dpmllOOcm2) 14 837 3 161 91 2 91 2 3 152 3. 152 2 91 1 70 2 109 3 152 1 79 2 100 __- ~___ ___ ___. 1 79 23 1,374 1 79 2 140 1 00 2 5 303 9 555 ~- .- __. - Unity - 0.121 0.02' 0.01, 0.01 0.02 0.02 0.01 0.01 0.01 0.02 0.01 0.01 0.01 0.02 0.01 __ __~ -- ~. lofl SECTION 7 ATTACHMENT 2 3 PAGE(S)
Pipe Interior Radiological Survey Form Date: /-/t-oG, Time: 0 *5.3 3 --* *- Building: Elevation - L> - Access Point qVAO 4 5WpT PipeID kg /a@ System : .. -G SPR Type of Survey Investigation Characterization (F;;als i urve r> # Other /- Detector:
y+ht Detector ID #: 7 fZ7@//- Cal Date: 1/77 Cal Due Date: AI-/7-u 6 Instrument:
lri3 -/ Instrument ID #: z/rz23 Cal Date: //-7 7-7.J- Cal Due Date: //-/ 7- c7 6 Pipe Diameter:
3 If Area: Sled Size inch From the Daily Pipe Survey Detector Control Form for the Selected Detector Background Value 3.2 CPm PVIIDCRStatiC 3 RJ- CPm Efficiency Factor for Pipe
: 0. 0 00 [3 (taken from . Pipe Interior Radiological Survey Radiological Survey Commenced:
Date: I 7t-0 @ ' Time: 33 Package Page 1 of& Attachment 3, Page 1 REFERENCE COPY Pipe Interior Radiological Survey Form (Continuation Form) .. I I I I I REFERENCECOPY Package Page &of 2 Attachment 3, Page 2 
 
SECTION 7 ATTACHMENT 3 I PAGE(S)
DQA Check Sheet Design # I EP Rx 130 1 Revision # 1 Original 1 Survey Unit# I EP Rx 130 ~~~ Preliminary Data Review' Answers to the following questions should be fully documented in the Survey Unit Release Record Have surveys been performed in accordance with survey instructions in the Survey Design? Yes No N,A 1, X I I Ix 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 embeddedhuried piping static measurements below the DCGLW ? I X I 1 I 4. Was the instrumentation iDC for structure scan measurements, soil scan measurements, and embeddedhuned piping scan measurements below the DCGLW. or, if not, was the need for additional static measurements or soil samples addressed in the survey design? Ix I 5. 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?
: 8. Was the instrumentation MDC for volumetric measurements and smear analysis < 10% DCGLW ? i lx X X Were "Special Methods" for data collection properly applied for the survey unit under review? 9. Is the data set comprised of qualified measurement results collected in accordance with the survey desinn, which accurately reflects the radiological status of the facility?
Graphical Data Review 1. Has a posting plot been created? X 2. Has a histogram (or other frequency plot) been created? X 3. Have other graphical data tools been created to assist in analyzing the data? 1. Are all sample measurements below the DCGLw (Class 1 8 2), or 0.5 DCGLW (Class 311 X Data Anaiysls 1x1 2. Is the mean of the sample data DCGLw? X 3. If elevated areas have been identified by scans and/or sampling, is the average activity in each elevated area c DCGLEM (Class l), < DCGLW (Class 2), or <0.5 DCGLw (Class 3)? 4. Is the resuli of the Elevated Measurements Test c 1 .O? 5. Is the result of the statistical test (S+ for Sign Test or W, for WRS Test) 1. the critical value? X X X Comments:
Form Rev 0 CS-0912 Page 1 of 1 SECTION 7 ATTACHMENT 4 1 DISC 0 COPY EP-Rx 13 1 Design # Revision # Original Page 1 of 3 Survey Unit kys) Description
: 2) EP Rx 13 1 is a Class 1, Group 2 survey unit as per the PBRF Final Status Survey Plan (FSSP) and Technical Basis Document (TBD)-06-004.
: 3) Surveys in EP Rx 13 1 were performed using a scintillation detector optimized to measure gamma energies representative of CO-60. Sample #EP 2 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 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 BSILVS-002, WEP 05-006, these determinations are appropriate for the types of radiation involved and the media being surveyed.
I Date: Approval Signatures FSS Design # EP Rx 131 Revision # Original 1 .o 2.0 3.0 4.0 5.0 Page 2 of 3 HistoryDescription 1.1 1.2 The subject pipe system is the 3" Quad "B" spare system line. EP Rx 13 1 consists of approximately 25 feet in length from the Reactor Building -25' elevation, Quad "B" to the Sub Pile Room. The line has one 90 degree elbow along its length. Survey Design Information 2.1 2.2 EP Rx 131 was surveyed IAW Procedure
#BSI/LVS-002.
100% of the 3" ID pipe was accessible for survey. The accessible 3" ID pipe was surveyed by static measurement at one foot increments, for a total of 25 survey measurements.
Surface area for the 3" ID piping is 730 cm2 for each foot of piping, corresponding to a total 3" ID piping surface area of 18,241 cm2 (1.8 m2) for the entire length of (25') of 3" piping. 2.3 Survey Unit Measurement LocationsData 3.1 Pipe interior radiological survey forms are provided in Attachment 2 of this release record. Survey Unit InvestigationsResults 4.1 None Data Assessment Results 5.1 5.2 Data assessment results are provided in the EPBuried Pipe (BP) Survey Report provided in Attachment
: 1. All measurement results are less than the Derived Concentration Guideline Level (DCGL) for radionuclide specific EP that corresponds to the 1 mrexdyr dose goal established in Table 3-3 of the FSSP. 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 13 1 passes FSS. Background was not subtracted fiom the survey measurements and the Elevated Measurement Comparison (EMC) was not employed for this survey unit. 5.3 5.4 I FSS Design ## EP Rx 131 I Revision ## Original I ~age3of3 I Number of Measurements
>MDC Number of Measurements Above 50% of DCGL Number of Measurements Above DCGL Survey Unit: Rx 13 1 18 0 0 5.5 Statistical Summary Table Mean 0.0286 Median 0.0171 6.0 7.0 I Standard Deviation I Statistical Parameter 0.0256 I I 1 25 I Total Number of Survey Measurements I Maximum 10.1107 I ~ ~ Minimum 10.0054 Documentation of evaluations pertaining to compliance with the unrestricted use limit of 25 mredyr 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 EP Rx 13 1 to be less than 1 mredyr. The dose contribution is estimated to be 0.029 mredyr based on the average of the actual gross counts. Attachments Attachment 1 - BSI EPBP Survey Report Attachment 2 - Pipe Interior Radiological Survey Form Attachment 3 - DQA Worksheet Attachment 4 -Disc containing RR for EP Rx 13 1 & Spreadsheet SECTION 7 ATTACHMENT 1 2 PAGE(S)
I@k& BSI EPIBP SURVEY REPORT Survey Location Pipe ID Survey Date -25 el. Quad B Survey Time 13:38 2350-1 f 203488 DetectorSled
# 44-1 59 2383691101 I Detector Efficiency O.OOO66 Field YDCR ~cpn) iurvev Measurement Results Total Number of Survey Measurements Number of Measurements Above 50% DCGL Number of Measurements Above DCGL 25 Number of Measurements
>MDC 18 0 0 Mean 0.0286 Median I 0.01 71 Standard Deviation 0.0256 Maximum I 0.1107 Minimum 0.0054 I STOCK Survey Technician@)
MKtMlYK COntnbutlOn I :OMMENTS:
CTIVITY VALUES NOT BACKGROUND CORRECTED nr cnginwr 1 uaw 8/13/2007 EP Rx 131 3" Pipe TBD 06-004 Group 2 - Unity - 0.025 - 0.032 0.024 0.03E 0.05E 0.05C 0.064 0.01E 0.02i 0.07( 0.0s 0.1 11 0.04E 0.01; 0.00: 0.01; 0.01; 0.OQ 0.01( 0.00: 0.oa 0.01( O.OO! 0.01r 0.01; -- ___ __ __- ___ __-
* C c E 3 e! a (I) m I I Eu-lU activity (dpmll OOcm2) Nb-94 activity (dpmll OOcm2) AglOBm activity (dpm1100cm2)
Cs-137 activity Eu-162 activity (dpm/lOOcm2) (dpdl OOcm2) 48 3,015 3,769 60 2.907 46 __-__ _.____ ._ -- Cog0 activity Cog0 activity ncpm (total dpm) (dpmllOOcm2) 167 3 34 5,814 28 42,424 7,268 5,607 27 40,909 8,306 40 60,606 - 12,667 11,421 55 83,333 14,743 71 107,576 3,738 ~ 27,273 -- -- 30 45,455 6,230 - 78 118182 16,19f 38 57.576 7.891 _-__ __~-. 35 53,030 ______. - . --__ 61 92,424 __ ~ __ -- -~ _- 209 161 239 ___._ ___ - 69 6.568 105 4 -~ ~ 365 329 6 6 ! __ -_ 1 I ___- - 5,922 95 ._ 7,645 122 31 1,938 52 3,230 __ 8399 _- 134 4,092 65 - 13,244 212 5.814 93 -___ ____ 424 108 179 466 7 2 3 8- - 86 22 36 - 95 46 1 50 66 16 227 735 323 70 36 78 78 __-_ _____.~ 4 12 - 186,364 25,541 54 81.818 11.213 _____ -_ 5 1 - _______ 13~ _____._ 191697 2,699 1,246 13 19,697 2,699 2,699 13 - 19,697 1,454 7 10,606 11 16,667 2,284 10 15,152 2,077 7 ~- 10,SW- 1,454 2,284 11 16,667 ~ 10 15,152 2,077 16 24,242 - 3,322 3,945 19- 28,780 __ __ -~ ~- ___ 9,091 ___ 6 __ ___ - -. ~_____- _____-__ ~- - - _________- - - ___. 1,400 1.400 22 __ -.__ ._ 7 1 1 -~ - 1,400 22 754 12 19 1,184 1,077 .. 17 19 1,184 1,077 - 17 1,723 28 2,046 33 ___ ___ 754 12 ~ _~ ____ - __-__ - ______ 1 1 1 ~- 42 66 60 42 1 1 12 9 - 13 12 ___- 66 1 1 60 96 __ .~ 19 23 - . -- 2 2 114 - 0.02! 0.01; 0.021 0.11' O.OO! --__ ___- MEAN MEDIAN STD DN MAX Mii lofl SECTION 7 ATTACHMENT 2 3 PAGE(S)
BSVLVSPipeCrawler-002 Revision 4 Pipe Interior Radiological Survey Form Time: 3 3%- 3 " -2s' System: 5phpE- TD 5PR Access Point Area:
0 mt5 Pipe Date: ID#: PipeDiameter:
Building:
LV Elevation: - Type of Survey Investigation Characterization Final Survey
->( Other Gross Co60 cs I/ 9 Detector ID# / Sled ID# #4 - / 7 Detector Cal Date: 9/r/o G Detector Cal Due Date: I, , Instrument:
Z%O-/ Instrument ID #: 7 /5/ - Instrument Cal Date:
Ob Instrument Cal Due Date: 3 /a7 From the Daily Pipe Survey Detector Control Form for the Selected Detector BackgromdValue 2 cpm I/ MDcRsmc LJ ,$ cpm Efficiency Factor for Pipe Diameter MDCSWI, Zb48 dpml iC.0 cm' Is the MDC,,,, acceptable?
@ No (ifno, adjust sample count tune and recalculate MDCK,,,) 0.00 o bb (from detector efficiency determination)
Comments: ( LA- %3zqs WRU' /0O0~ -z5/ Technician Signature Pipe Interior Radiological Survey - - - .. - , Package Page 1 of3 Attachment 3, Page 1 BSULVSPipeCrawler-002 Revision 4 Pipe Interior Radiological Survey Form (Continuation Form) Package Page of3 REFERENCECOPY Attachment 3, Page 2 
 
SECTION 7 ATTACHMENT 3 PAGE(S)
DQA Check Sheet Answers to the following questions should be fully documented in the Survey Unit Release Record 1. Have surveys been performed in accordance with survey instructions in the Survey Design? Design # I EP Rx 131 1 Revision # I Original I Yes No NIA X Survey Unit# I EP Rx 131 3. 4. Was the instrumentation MDC for structure scan measurements, soil scan measurements, and static measurements or soil samples addressed in the survey design? Is the instrumentation MDC for embeddedhuried piping static measurements below the DCGLw ? embeddedlburied piping scan measurements below the DCGLW, or, if not, was the need for additional Preliminary Data Review' X X 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?
: 8. X X Were "Special Methods" for data collection properly applied for the survey unit under review? I I lx 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? 1. Has a posting plot been created?
Ix 3. Have other graphical data tools been created to assist in analyzing the data? 9. is the data set comprised of qualified measurement results collected in amdance with the survey design, which accurately reflects the radiological status of the facility?
X 1. Are all sample measurements below the DCGLw (Class 1 & 2), or 0.5 DCGLw (Class 3)? 2. Is the mean of the sample data DCGLW? 3. 4. If elevated areas have been identified by scans and/or sampling, is the average activity in each elevated area c DCGLEMC (Class l), Is the result of the Elevated Measurements Test
< 1 .O? DCGLw (Class 2), or ~0.5 DCGLw (Class 3)? 2. Has a histogram (or other frequency plot) been created? I I lx X X X X 5. Is the result of the statistical test (S+ for Sign Test or W, for WRS Test) 2 the critical value? I I Ix Comments:
Page 1 of I SECTION 7 ATTACHMENT 4 1 DISC 0 COPY EP 1.38 Design # Revision # Original Page 1 of 3 Survey Unit #(s) Description I Survey Unit Release Record FSS/Characterization Engineer FSS Design # EP 1.38 1 .o 2.0 3.0 4.0 5.0 Revision # Original Page 2 of3 1 History/Description 1.1 1.2 EP 1-38 was the Quad "B" Drain. The subject pipe is the drain from Quad "B' in the Containment Building to the -25 ft of the Rx Building in mUnp Room #22. The function of this pipe was to convey water fiom Quad "B" in the Containment Building to the HD sump in Pump Room #22 on the Rx Building -25 ft, where the pipe is currently breached.
EP 1.38 consists of approximately 37 linear feet of piping, consisting of 6" and 10" diameter pipes, running from the breach point in Pump Room #22 to the two strainer grates adjacent to the wall in Quad "B", involving two bends of approximately 30" each and a tee to a secondary inlet at the Quad "B" end A diagram of the piping is included in Section 7, Attachment
: 2. Survey Design Information 1.3 2.1 EP 1.38  ti^ SU~VV~ IAW froced~re
#BSEILVS-OOZ.
2.2 100% of the 10'' and 6" ID pipe was accessible for survey. The accessible 10" and 6" ID pipe was surveyed by static measurement at one foot increments, for a total of 37 survey measurements.
Surface area for the 10" ID piping is 2,432 cm2 for each foot of piping, corresponding to a total 10" ID piping surface area of 80,256 cm2 (8.0 m2) for the entire length of (33') of 10" piping. Surface area for the 6" ID piping is 1,459 cm2 for each foot of iping, corresponding to a total 6" ID piping surface area of 5,836 cm (0.6 m') for the entire length (4') of 6" piping. Total surface area for both the 10" and 6" piping that constitutes EP 1.38 is 8.6 m2. 2.3 2.4 ;P 2.5 Survey Unit Measurement Loca.tio~ata 3.1 Pipe interior radiological survey forms are provided in Attachment 2 of this release record.
Survey Unit InvedgatiomRmdb 4.1 None Data Assessment Results 5.1 5.2 Data assessment results are provided in the EP/Buried Pipe (BP) Survey Report provided in Attachment
: 1. All measurement results are less than the Derived Concentration Guideline Level (DCGL) for radionuclide specific EP that corresponds to the 1 mdyr dose goal established in Table 3-3 of the FSSP.
I I I Total Number of Survey Measurements I FSS Design # EP 1.38 1 Revision # Original / Page3of3 1 33 4 I Survey Unit:
1.38 1 Number of Measurements
>MDC Number of Measurements Above 50% of DCGL Number of Measurements Above DCGL 5.3 When implementing the Unity Rule, provided in Section 3.6.3 of the FSSP, and applying the Cesium-l37/Cobalt-60 ratios, provided in TBD- 06-004, the survey unit that is constituted by EP 1.38 passes FSS. Background was not subtracted fiom the survey measurements and the Elevated Measurement Comparison (EMC) was not employed for this survey unit. 5.4 0 4 0 0 0 0 5.5 Statistical Summary Table ~ Mean Median Standard z)eviation Maximum Minimum 1 IO" Pipe I 6" Pipe I 0.015 0.002 0.015 0.002 0.003 0.001 0.021 0.003 0.010 0,001 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 re- has shown tbt the dose contribution for EP 1.38 to be less than 1 mredyr. The dose contribution is estimated to be <0.015 mredyr based on the actual gross counts measured.
 
===7.0 Attachments===
 
Attachment 1 - BSI EPBP Swey Report Attachment 2 - Pipe Interior Radiological Survey Form Attachment 3 - DQA Worksheet Attachment 4 -Disc containing RR for EP 1.38 & Spreadsheet SECTION 7 ATTACHMENT 1 J PAGE(S)
BSI EPlBP SURVEY REPORT Median Standard Deviation Maximum Minimum 0.015 0.002 0.003 0.001 0.021 0.003 0.019 0.001 I Survey Technician@)
Survey Unit Classification TBD Of3404 Piping Group SR-13 Radionuclide Distribution Sample Measured Nudide Area FactwEMC Used PaMail FSS MREMNR ConbibutJon I t 1 2 EP 2-1 COG0 No Pass 4 @A /7.3,=07 RP Engineer I Date EP 1.38 IO" Pipe TBD 06-004 Group 2 gcpm - 30E 2% 33E 32: 31 ( 30: 31 i 31t 35! 314 31! 28 281 32: 21! 19: 19 17 20 17 18 19 19 __ ncpm 30t _~ 2% 33c 32: 31 E 30: -- 31 i 31f 35! 31~ 31! 28' 28( 32; 21! 1 9: 19 17! 20: 171 18, 19 19 - ___ 1-75 102,667 78,667 108,333 - 103,333 101,000 105,667 105,333 118.333 110,000 ____- ~___- 93I667 93,333 107,333 73,000 64,000 64,667 58,333 67,333 61,667 63,667 64,667 - 76.667 56,667 _____ .__- 78,335 r- 73.661 70,00[ c 4,221 3,235 4,523 4,454 4,249 4,153 4,345 4.331 --- 4,866 4,304 4,317 3,851 3,838 4,413 3,002 2,632 2,659 2,399 __ 2,769 2,33C 2,53* 2,61* 2,655 3,152 3,221 2,87* I 3.02s ~~ --__ ~__ - _-___ ____ \ Cs-137 acUvlty p52 activity (dpm1100cm2) dpdlOOcm2) 1' J 35 2,191 - 1,679 27 38 2,347 __ 37 2,312 __ 35 2,205 - 2,155 34 - 2,255 36 36 2,525 40 2.234 36 -_.- 2,248 - __ _.__ 22 1,245 1,437 1,209 __ ___ . 22 1.636 2E -_ ____ - Eu-154 a&ty Nb-94 activity Ag-lO8m activity (dpm1100cm2) (dpmllOOcm2) (dpm11Okm2) 1 of2 Cos0 actMty Co-60 activity Cs-I 37 aaty Eu-152 activity Eu-164 activity ncp (total dpm) (dpm1100cmZ) (dpm/lWcmZ) (dpm1100cm2) (dpm1100cm2) 235 78,333 3,221 1,672 27 19 __ - - - _- - _____- __ ~._____ - - ~. --___ __ ___ _. ~ ~__ ~ __ -. _____ -~ ~ __ ___ __ - ---____-_
_- - ~__ 0.015 0.015 0.003 0.010 Nb-94 activity Ag-108m activity (dpdl00cmZ) (dpmll OOun2) 93 - - 2 MEAN MEDIAN - STDDEV MAX MIN ~ ~. -- - - __ - __ - . 2of2 EP 1.38 6" Pipe TBD 06-004 Group 2 +, E E e! 8 3 3 Cog0 cs-137 Eu-152 Eu-I54 Nb-94 Ag-108m 'Os' activity activity activity activity activity acUvity gcpm ncpm activity (dpm/lM)cm (dpm1100cm (dpm1100cm (dpmllWcm (dpm/lM)cm (dpm/lOOcn 2) 2) 2) 2) 2) 2) (total dpm) 1 3 4 -~ . 2 __ Unity lo 10 5,000 343 3 2 0 10 178 ____ __________
10 10 10 5,000 178 3 2 343 12 12 6,000 41 1 213 3 2 0 12 19 19 9,500 65 1 338 5 4 0 19 .___--- __ _ __ - -~ - ______ .- ~___ - ___ -- - ___ __ __ .___ - 0.001 0.001 0.00; 0.00: ____ - -. - - 0.00; 0.00; 0.00: 0.00' --__ -- _- __ 0.00' ~ ~-__ 1 of 1 SECTION 7 ATTACHMENT 2 PAGE(S)
Pipe Interior Radiologid Survey Form Date: /L-2 -OJ/ Type of Survey Investigation Sled size 10 I Pipe Interfor Radiologleal Survey Package Page I of& Attachment 3, Page 1 I i Pipe Interior Radiological Survey Form (Continuation Form) I I I - .. I __ - . __ -- Package Page & of= Attachment 3, Page 2 
 
Pipe Interior Radiological Survey Form Date: 1-,7-06 Time: /ox- Building:
(2-x Elevation -ZJ" Access Point System: Plra J PipeDiameter:
6 '' Area: PipeD /,3g /a-tn Type of Survey Investigation Characterization
-9 ## Other J Sled Size 6 '' inch /3,~~.?+7
//K&r s/ ,J Detector:
Lu'5 it+ L'.--G Detector ID #: [e- Ld f +/c7 fl 1494 Cal Date: [ L-ZO -c3 >- Cal Due Date: /t-ZO -0G Instrument:
2-3JT9-I Instrument ID #: /3P7JS Cal Date: IZ-LO -or Cal Due Date: / 2 -Ld Q From the Daily Pipe Survey Detector Control Form for the Selected Detector Background Value Jb. 3 cpm Efficiency Factor for Pipe 0.00 7 (taken from detector Meter statlc 3.33 dpm/100cm2 MDCRstatic
/g0s cpm Is the MDC,,,, No (if no, adjust sample count time and recalculate MDW,,) C&%ERB"? r ~')lV7/nld&lT~
0 4l 3 edcy - /nrp pCpl42 r*L /,3GA pa5*3*'( Wrr /.sa4 fc >rn fl [~TK - Pipe Interior Radiological Survey Radiological Survey Commenced:
Date: ( -/ Time: OL?~ I I Package Page 1 ofI Attachment 3, Page 1 
 
--- I SECTION 7 ATTACHMXNT 3 I PAGE( S) 
~~ DQA Check Sheet Design #- 1 EP 1.38 I Revision # I Original 1 ~~ ~ ~ ~ Survey Unit # EP 1.38 Preliminary Data Review' Yes No NIA Answers to the following questions should be fully documented in the Survey Unit Release Record 1. Have surveys been performed in accordance with survey instructions in the Survey Design?
X I 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?
lx 3. 4. Is the instrumentation MDC for embeddedhuried piping static measurements below the DCGLw ? embeddedhuried piping scan measurements below the DCGLw, or, if not, was the need for additional X Was the instrumentation MDC for structure scan measurements, soil scan measurements, and static measurements or soil samples addressed in the survey design? X 5. Was the instrumentation MDC for volumetric measurements and smear analysis 10% DCGLW ? 1 X 5. 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 beina surveved?
X ~~~~~ ~ ~~ ~ 3. Were "Special Methods" for data collection properly applied for the survey unit under review? 1x1 I X 3. Is the data set comprised of qualified measurement results collected in accordance with the survey design, which accurately reflects the radiological status of the facility?
GraDhical Data Review 1. Has a posting plot been created? X 2. Has a histogram (or other frequency plot) been created? X 3. Have other graphical data tools been created to assist in analyzing the data? I I Ix Data Analysis 1. 2. 3. 4. Are all sample measurements below the DCGLw (Class 1 & 2). or 0.5 DCGLw (Class 3)? Is the mean of the sample data
< DCGLw? If elevated areas have teen identified by scans and/or sampling, is the average activity in each elevated area < DCGLam: (Class f), c DCGLw (Class 2), or ~0.5 DCGLW (Class 3)? Is the result of the Elevated Measurements Test c 1 .O? X X X X 5. hnments: Is the result of the statistical test (S+ for Sign Test or W, for WRS Test) ? the critical value? X FSSICharacteriration Engineer
@tintisign)
Date L-L-07 FSSl Characterization Manager (prinvsign)
Form CS-Q9/2 Rev 0 Page 1 of 1 SECTION 7 ATTACHMENT 4 1 DISC t 1 EP- 1.4 1 A-4 0 COPY Revision # Original Page 1 of 3 Design # Survey Unit #(s) Description
: 2) EP 1.41A-4 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 1.41A-4 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 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 BSVLVS-002, WEP 05-006, these determinations are appropriate for the types of radiation involved and the media being surveyed.
I I I FSS Design # EP 1.41A-4 Revision # Original Page 2 of 3 1.0 HistorylDescription 1.1 1.2 The subject pipe system is a 4" Quad "C" system line. EP 1.41A-4 consists of approximately 48 feet in length fkom the Reactor Building -25' elevation to Quad "C". 2.0 Survey Design Information 2.1 2.2 EP 1.41A-4 was surveyed IAW Procedure
#BSL/LVS-002.
100% of the 4" ID pipe was accessible for survey. The accessible 4" ID pipe was surveyed by static measurement at one foot increments, for a total of 48 survey measurements.
Surface area for the 4" ID piping is 973 cm2 for each foot of piping, corresponding to a total 4" ID piping surface area of 46,698 cm2 (4.7 m2) for the entire length of (48') of 4" piping.. 2.3 3.0 Survey Unit Measurement Locations/Data Pipe interior radiological survey forms are provided in Attachment 2 of this release record.
3.1 I 4.0 Survey Unit InvestigationdResults 4.1 None 5.0 Data Assessment Results 5.1 5.2 Data assessment results are provided in the EP/Buried Pipe (BP) Survey Report provided in Attachment
: 1. All measurement results are less than the Derived Concentration Guideline Level (DCGL) for radionuclide specific EP that corresponds to the 1 mredyr dose goal established in Table 3-3 of the FSSP. FSSP, and applying the Nuclide Fraction (NF), provided in TBD-06-004, the survey unit that is constituted by EP 1.41A-4 passes FSS. Background was not subtracted fkom the survey measurements and the Elevated Measurement Comparison (EMC) was not employed for this survey unit. 5.3 When implementing the Unii thp- 5.4 
- FSS Design # EP 1.41A-4 Survey Unit:
1.4 1 A-4 Revision # Original Page 3 of 3 5.5 Statistical Summary Table ~ Statistical Parameter Total Number of Survey Measurements Number of Measurements
>MDC Number of Measurements Above 50% of DCGL Number of Measurements Above DCGL 4" Pipe 48 48 0 0 Mean Median 0.0891 0.0784 Minimum 10.0212 Standard Deviation Maximum Documentation of evaluations pertaining to compliance with the unrestricted use limit of 25 mredyr 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 EP 1.41A-4 to be less than 1 mdyr. The dose contribution is estimated to be 0.089 mredy-r based on the average of the actual gross counts. - mments 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 1.41A-4 & Spreadsheet 0.0532 0.3065 SECTION 7 ATTACHMENT 1 3 PAGE(S) I i lliiki@ -L- _L .- BSI EP/BP SURVEY REPORT Pipe ID Survey Location I I -27 Trench 't I Survey Date 01-Mar-06 1 I 2350-1 P I 203488 I I I SunreyTime I 10:15 I I DetectorSled P I lMG1 LVS-lI101 I I Pipesize 4" II Detector Efficiency 1 0.00052 DCGL mmaq 2.41 EM5 RphIncopon.dbY-Lmdrryh=Ul 973 Routine Survey Field MDCR4m) 19 Field BKG IWI 21.7 Maximum 0.3065 Minimum 0.0212 I ROSENHAGEN Survey Technician@)
__ LUES NOT BACKGROUND CORRECTED 8-2-07 RP Engineer I Date ZP 1 1EZ 8EP SEE 116 619 E8S :m'O 160'0 190'0 190.0 K)1-0 ilC'0 i60'0 :LO'O MOO 180'0 .60'0 rLO'O 360'0 301'0 181'0 )P1'0 )Z 1'0 !OE'O iLO'O 3Zl.O 361'0 .E1'0 $11'0 !9 1'0 ;6 C '0 ,CC'O 20.0 iLO.0 $80'0 UO.0 :so-o :90.0 - Qun - P66'1 1 88L'E 168'2 Z69'Z 98P'P 980'9 99 so 1 08 6LP 619 E88 989 889 005' 1 988 PL PZ 1 6E 1 91 1 98 LEL'P 98P'P LZ9'L ZE6'9 WO'S 096'1 1 OW'* vs EO 1 901 P11 PZ 1 112 L8- 696 OP9 P9C 1Pl 8SE PLE'8 EES'9 Z6 LPl 182 *9 1 E89 06L 6E 1 68 1 LZZ 6Z 1 98 88 SEO'S I 618'9 ~ EO 1 16 Z96 ZW 8% 6% EEP 18E 091 921'8 989'P 160% 06C'E 6EL'E I 06Z'E/ EPZ'Z 1 PPP *98 I OW'* I 90E lzm'z 1 I ~ 004'L 1SZ'P 1 9L8'0 1 921'01 9L8'91 866'8 1 CSL'91 - 919' 1 1 ElE'L - ESO'PL 8EP'P 1 - *18'11 - ES'S 1 9L8'9 1 689'81 - 911'61 - ZGL'8P ES'Z 1 m'oz ZOS'lE P18'0Z 866'8 1 - 689'92 -_ 686'OE 919'L 1 919' 1 1 E90'P 1 9LE'Zl 8*P'8 866'6 PlB'ZZ - ______ 100'1 1 - vsv 99p'cc EZP PL9'0 1 90E 60L'L 88s 9Z8'P 1 *09 OZZ'4 1 p6P ESP'Z 1 099 WP'9 1 SOL 06L'L 1 661'1 EPZ'OE 166 1 EZS'EZ 66L 1 191'02 LEO'Z t6*'19 SZS PPZ'E 1 8E8 CSl'lZ 9CE'l 80Z'EE OL8 1P6'1z l6L 996'6 1 *LO' 1 180'LZ E6Z' 1 I Sl9'ZE 9EL I 18S'81 - _- . _- . 98P 94z'z 1 104 1S9'Z 1 SZ8'Pl 968'8 S 19 9LP'O 1 CEZ'p6 1 1*Z'6 L L 000'9L 68 SL CEZ'W1 LLO'8Pl LL vsc'czc *9 S19'691 *8 LLO'ELC lEZ'p6Z ESl 9P8'8ZZ 611 s1'961 10 1 000'009 091 9p8'8Z1 L9 69L'SOZ LO1 LLO'EZE 891 Z9p'ElZ 111 ~ --__ lEZ'P61 80E'L 16 869'98 *16' 10 1 __- urd3u 82 LO1 LZ 91 59 91 ?E PZ urd36 EP 1.41A-4 4" Pipe TBD 06-004 Group I 73 36 26 18 27 38 40 27 42 32 47 51 77 43 ___ -~ ___ 28 ~- 155,769 140,385 69,231 34,615 27 51,923 38 73.077 90,385 98,077 43 82,692 ___-- t C0-60 acUvity (dpm/l Wcm2) 16,011 .. 14,430 7,116 5,139 3.558 5,337 7,511 7,907 5,337 5,535 8,302 6,325 9,290 10,081 15,220 8.500 Cs-137 activity (dpm/l OOcm2) 635 572 282 204 141 212 ______ 298 31 3 212 21 9 329 251 368 400 603 _. ___ 337 Eu-152 activity (dpmll OOcm2) 15,188 13,688 - 6,750 4,875 3,375 5,063 - 7,125 7.500 - 5,063 5.250 7,875 - 6,000 - 8,813 9,563 14,438 8,063 I I 1 4,038 1 3,639 1 1,795 Nb-B4 acUvity Ag-108m activity (dpmllWcm2) (dpm1100cm2) 208 150 . 36 104 25 156 37 219 52 231 55 156 37 162 39 242 58 185 44 271 65 294 70 444 106 248 59 _____ MEDIAN STD DEV - Unrty - 0.09: 0.08E 0.04; 0.03* 0.021 0.03; 0.04: 0.04; 0.03; 0.03: 0.05( 0.03E 0.05: 0.06( 0.09' 0.05' 0.08s 0.07t 0.05: 0.30; 0.02; -_ - __ ~- - 2of2 T I SECTION 7 ATTACHMENT 2 4 PAGE(S)
I BSYLVSPipeCrawler-002 Revision 4 Pipe Interior Radiological Survey Form L+&-J c Date: 3 -- /.+ c c Time: /d/< Pipe ID#: // W 4 Pipe Diameter:
4 'I Access Point Area:
dp Jczz& Type of Survey Investigation Characterization Final Survey K Other u~ ~%-b Building:
Z6 Elevation:
'ZZ &)fiD p, System: & wn Gross Co60 o/ cs 140 Detector ID# I Sled ID# d/k+?oN /hf e 1 I /& 1 Detector Cal Date: zt' - PEc YL' Detector Cal Due Date: P - 9Ec 0 t Instrument:
2363 -t Instrument ID #: 2d3 ~VJ' Instrument Cal Date: / 7 - r;~ .J - aii- Instrument Cal Due Date: i7- do/ -o& From the Daily Pipe Survey Detector Control Form for the Selected Detector Background Value 18 ? cpm MDCRStat,, cpm Efficiency Factor for Pipe Diameter MDcstatlc 155 7 dPd lrr0 cm2 Is the MDCstatIc acceptable?
@ No (if no, adjust sample count time and recalculate MDCR,,,) 0. 0 0 052 (from detector efficiency determination)
Comments:
/<4 ti, &-L Techcian Signature
// Pipe Interior Radiological Survey J Package Page 1 off REFERENCE COPY Attachment 3, Page 1 I BSI/LVSPipeCrawler-O02 Revision 4 Pipe Interior Radiological Survey Form (Continuation Form) QM~ e Date: 7 ob {ESJeL Pipe ID#: /e 49 Pipe Diameter:
+'I Access Point Area:
/J=+ c/p Lurj.cL Building:
;;3 g Elevation: -dah- QW3 & System: 7/n &5A :>.E /;r REFERENCECOPY Package Page of 3 Attachment 3, Page 2 I BSYLVSPipeCrawler-002 Revision 4 Pipe Interior Radiological Survey Form (Continuation Form) Cya4-3 r d.cJ SfL dC Access Point Area:
5- up Date: /ed6 Pipe ID#: t4 t// Pipe Diameter:
Building:
P-+- K Elevation:
-23 qrA*D c System: 7Zt6n% Ctir~3~,R REFERENCE COPY 0 Package Page 2 of $ Attachment 3, Page 2 REFERENCE COPY 2.
SECTION 7 ATTACHMENT 3 1 PAGE(S)
I I Design # EP 1.41A-4 Revision # Original Survey Unit # 3. 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?
X EP 1.41A-4 Answers to the following questions should be fully documented in the Survey Unit Release Record
: 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 embedded/buried piping static measurements below the DCGLW ? Yes No X X X 3. Have other graphical data tools been created to assist in analyzing the data? I I Ix 1. Was the instrumentation MDC for structure Scan measurements, soil scan measurements, and embeddedlburied piping scan measurements below the DCGLw, or, if not, was the need for additional static measurements or soil samples addressed in the survey design? Was the instrumentation MDC for volumetric measurements and smear analysis 10% DCGLw ? 5. Data Analyds X X ~ ~~ 3. 3. Were "Special Methods" for data collection properly applied for the survey unit under review? Is the data set comprised of qualified measurement results collected in accordance with the survey design, which accurately reflects the radiological status of the facility?
X 3. If elevated areas have been identified by scans andor sampling, is the average activity in each elevated area < DCGLEMC (Class l), DCGLw (Class 2), or ~0.5 DCGLw (Class 3)? X X ~ I. !. Has a posting plot been created? Has a histogram (or other frequency plot) been created? hmments: - X X /I cs-0912 I. !. Is the mean of the sample data DCGLW? Are all sample measurements below the DCGLW (Class 1 8 2), or 0.5 DCGLw (Class 3)? Page 1 of 1 X X 1. i. Is the result of the Elevated Measurements Test e 1 .O? Is the result of the statistical test (S+ for Sign Test or W, for WRS Test) 2 the critical value? X X 
, SECTION 7 ATTACHMENT 4 1 DISC i EP- 1.41A-6 Revision # Design ## Original Page 1 of 3 Survey Unit #(s) Description
: 2) EP 1.41 A-6 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 1.41A-6 were performed using a scintillation detector optimized to measure gamma energies representative of CO-60. Sample #EP 3- 9 fiom 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 document constitute "Special Methods" and the survey design used in the acquisition of survey measurements.
: 5) Instrument eficiency determinations are developed in accordance with the BSI/LVS-002, WEP 05-006, these determinations are appropriate for the types of radiation involved and the media being surveyed. 
.- I J 1 FSS Design # EP 1.41A-6 1 Revision # Original I ~age2of3 I Survey Unit: 1.41A-6 I 1 .o 2.0 3.0 4.0 5.0 History/Description 1.1 1.2 Survey Design Information 2.1 2.2 The subject pipe system is a 6" Quad "C" system line. EP 1.41 A-6 consists of approximately 16 feet in length from the Reactor Building -25' elevation to Quad "C". EP 1.41A-6 was surveyed IAW Procedure #BSI/LVS-002.
100% of the 6" ID pipe was accessible for survey. The accessible 6" ID pipe was surveyed by static measurement at one foot increments, for a total of 16 survey measurements.
Surface area for the 6" ID piping is 1,459 cm2 for each foot of piping, corresponding to a total 6" ID piping surface area of 23,344 cm2 (2.3 m2) for the entire length of (1 6') of 6" piping.. 2.3 Survey Unit Measurement LocationdData 3.1 Pipe interior radiological survey forms are provided in Attachment 2 of this release record.
Survey Unit InvestigationslResults 4.1 None Data Assessment Results 5.1 5.2 Data assessment results are provided in the EP/Buried Pipe (BP) Survey Report provided in Attachment
: 1. All measurement results are less than the Derived Concentration Guideline Level (DCGL) for radionuclide specific EP that corresponds to the 1 mredyr dose goal established in Table 3-3 of the FSSP. 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 1.41A-6 passes FSS. Background was not subtracted from the survey measurements and the Elevated Measurement Comparison (EMC) was not employed for this survey unit. 5.3 -- 5.4 I J FSS Design # EP 1.41A-6 Revision # Original Page 3 of 3 5.5 Statistical Summary Table Total Number of Survey Measurements Number of Measurements
>MDC 6" Pipe Statistical Parameter 16 16 Number of Measurements Above DCGL Mean I Number of Measurements Above 50% of DCGL I 0 I 0 0.0857 I Median 10.0644 I I Standard Deviation 10.0737 I r 10.3495 I I Minimum 10.0429 1 6.0 73- Documentation of evaluations pertaining to compliance with the unrestricted use limit of 25 mredyr 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 EP 1.41A-6 to be less than 1 mredyr. The dose contribution is estimated to be 0.086 mredyr based on the average of the actual gross counts. ~ --- Attachment 1 - BSI EPBP Survey Report Attachment 2 - Pipe Interior Radiological Survey Form Attachment 3 - DQA Worksheet Attachment 4 -Disc containing RR for EP 1.4 1 A-6 & Spreadsheet SECTION 7 ATTACHMENT 1 PAGE(S)
B%I EP/BP SURVEY REPORT I PipeID I EPlAlA-6 sunmy Date 1 WuI-07 SU~Y nm 6" DCGL 2.41 E95 4 ne 41 L.a I I RoutineSurvey
] X Survey Location -27 Trench 2350-1 # 189094 DebctorSled P 1MGl LVS-lI101 Detector Efficiency 0.0002 10 I J Nominal MDC (dpnnLmw 3,143 Survey Measurement Results ACTMTY VALUES NOT BACKGROUND CORRECTED RP Engineer I Date 81MDo7 EP 1.41A-6 6" Pipe TBD 06-004 Group 1 I 1
* C E Cos0 activity C060 activity Cs-137 activity Eu-152 activity EMS4 activity Nb-94 actiVyr Ag-108m activity U gcpm ncpm (total dpm) (dpm1100cm2) (dpmllWcm2) (dpmllOOcm2) (dpm1100cm2) (dpm1100cm2) (dpm11OOcm2) unw 8 3 1 31 31 155,000 10,624 42 1 10,078 2,679 31 0 74 0.063 230 30 150,000 10,281 407 9,753 2,593 300 72 0.061 81 0.069 4 26 26 130,000 8,910 353 8,452 2,247 260 62 0.053 5 35 35 175,000 1 1,995 475 11,378 3,025 350 - &I 0.072 134 0.114 8 171 171 855,000 58,602 2,323 55,590 14,778 1,710 408 - 0.350 936 36 180,000 12,337 489 11,703 3,111 360 86 0.074 10 53 53 265,000 18,163 720 17,230 4,580 530 127 0.108 11 49 49 245,000 16,792 666 15,929 4,235 490 117 0.100 13 21 21 105,000 7,197 285 6,827 1,815 210 - 50 0.043 14 23 23 115,000 7,882 312 7,477 1,988 - 230 55 0.047 15 32 32 160,000 10,966 435 10,403 2,765 320 76 0.065 16 23 23 115,000 7,882 31 2 7,477 1,988 230 55 0.047 MEAN 0.086 MEDIAN MAX 334 34 170,000 11,652 462 11,053 2,938 340 6 27 27 135,000 9,253 367 8,777 2,333 270 64 0.055 756 56 280,000 19,191 76 1 18,205 - 4,840 560 -__ 12 24 24 120,000 8,225 326 7,802 2,074 240 57 0.049 __ 0.064 1 STD DEV 0.074 I -_ 0.350 ~ - I 1 MIN 0.043 1 of 1 SECTION 7 ATTACHMENT 2 z PAGE(S)
I BSYLVSPipeCrawler-002 Revision 5 Pipe Interior Radiological Survey Form Date: 7 -1 I - b> Time: lL30 Pipe ID#: I .q ) A Pipe Diameter: Access Point Area: &A\Zk*>S$*&
'I Building:
C\/ Elevation:
-27' System: Type of Survey Investigation Characterization Finalsurvey x- Other \/ Gross Co60 J cs Detector ID# / Sled ID# \ mG\ / UJ 5 - 1 f 101 Detector Cal Date: \ - \ 1 - 03 Detector Cal Due Date:
\ -\b ok lnstrumen t : %>So- \ Instrument ID #: N?\B1q Instrument Cal Date:
1 - 1 1 07 Instrument Cal Due Date: \ -\I -'uG From the Daily Pipe Survey Detector Control Form for the Selected Detector Backgroundvalue 3.3 cpm MDCRStatiC
\D CPm Efficiency Factor for Pipe Diameter mcstatic 31U dpd cm2 Is the MDCsuQc acceptable?
@ No (if no, adjust sample count time and recalculate h4Dmmec) 0.0 0 02 @om detector efficiency determination)
Comments: -JXA;~\ KP 3- 7 \b'dVkh.LI$/C 0 \.\)O% CI) Technician Signature Pipe Interior Radiological Survey Package Page 1 of - 7 REFERENCE COPY a Attachment 3, Page 1 BSb'LVSPipeCrawler-002 Revision 3 Pipe Interior Radiological Survey Form (Continuation Form) Date: Pipe ID#: Pipe Diameter:
6'' Access Point Area: b& -35' Building : Elevation:
J System: Attachment 3, Page 2 SECTION 7 ATTACHMENT 3 I PAGE(S)
I I 1. Are all sample measurements below the DCGLW (Class 1 & 2), or 0.5 DCGLw (Class 3)? 2. Is the mean of the sample data DCGLW? DQA Check Sheet Design # EP 1.41A-6 Revision # Original Survey Unit # EP 1.41A-6 X X Preliminary Data Review' Answers to the following questions should be fully documented In the Survey Unit Release Record 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. Yes No N,A X X Is the instrumentation MDC for embeddedlburied piping static measurements below the DCGLw ? X 4. 5. Is the result of the Elevated Measurements Test < 1 .O? Is the result of the statistical test (S+ for Sign Test or W, for WRS Test) 2 the critical value? 4. Was the instrumentation MDC for structure scan measurements, soil scan measurements, and static measurements or soil samples addressed in the survey design? embedded/buried piping scan measurements below the DCGLW, or, if not, was the need for additional Was the instrumentation MDC for volumetric measurements and smear analysis < 10% DCGLw ? X X 5. X X 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 medii being surveyed?
: 8. 9. Is the data set comprised of qualified measurement results collected in accordance with the survey design, which accurately reflects the radiological status of the facility?
Were 'Special Methods' for data collection properly applied for the survey unit under review?
X X Graphical Data Review 1. Has a posting plot been created?
X 2. Has a histogram (or other frequency plot) been created?
X 3. Have other graphical data tools been created to assist in analyzing the data? I I 1x X 3. If elevated areas have been identitied by scans and/or sampling, is the average activity in each elevated area DCGLEK (Class I), < DCGLW (Class 2), or ~0.5 DCGLw (Class 3)? FSS/Characterization Engineer (printlsign)
FSS Characterization Manager (printlsign)
*- Page 1 of 1 CS-09J2 FI SECTION 7 ATTACHMENT 4 1 DISC Survey Unit Release Record - Design # Survey Unit #(s) Description EP-1.42A-4 1 Revision # 1 Original 1 Page 1 of 3 1.42A-4 1) Embedded Pipe (EP) Survey Unit 1.42A-4 meets the definition of embedded pipe for Plum Brook Reactor Facility (PBRF). 2) EP 1.42A-4 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 1.42A-4 were perf'urmed using a scintillation detector optimized to measure gamma energies representative of (20-60. 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 document constitute "Special Methods" and the survey design used in the aquisition 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.
1 Page 2 of 3 FSS Design ## EP 1.42A-4 Survey Unit: 1.42A-4 Revision # Original 1 .o 2.0 3.0 4.0 5.0 History/Description 1.1 1.2 Survey Design Information 2.1 2.2 The subject pipe system is a 4" Quad "C" system line. The piping designated EP 1.42A-4 is approximately 48 feet in length from the Reactor Building -25 ' elevation to Quad "(2". EP 1.42A-4 was surveyed IAW Procedure #BSI/LVS-002.
100% of the 4" ID pipe was accessible for survey. The accessible 4" ID pipe was surveyed by static measurement at one foot increments, for a total of 48 survey measurements.
Surface area for the 4" ID piping is 973 cm2 for each foot of piping, corresponding to a total 4" ID piping surface area of 46,698 cm2 (4.7 m2) for the entire length of (48') of 4" piping.. 2.3 Survey Unit Measurement LocationdData 3.1 Pipe interior radiological survey forms are provided in Attachment 2 of this release record.
Survey Unit Investigations/Results 4.1 None Data Assessment Results 5.1 5.2 Data assessment results are provided in the EPBuried Pipe (BP)
Survey Report provided in Attachment
: 1. All measurement results are less than the Derived Concentration Guideline LeveI (DCGL) for radionuclide specific EP that corresponds to the 1 mredyr 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 appIying the Nuclide Fraction 0, provided in TBD-06-004, the survey unit that is constituted by EP 1.42A-4 passes FSS. Background was not subtracted fiom the survey measurements and the Elevated Measurement Comparison (EMC) was not employed for this survey unit. ~ - - ~ 5.4 I t ~~ ~ FSS Design ## EP 1.42A-4 Revision # Original Page 3 of 3 I Survey Urd: 1.42A-4 I ! 5.5 Statistical Summary Table Total Number of Survey Measurements Number of Measurements
>MDC Statistical Parameter 48 47 4" Pipe ~~ ~~ ~ Number of Measurements Above DCGL Mean 0 0.0374 I Number of Measurements Above 50% of DCGL I 0 Median 10.0330 Standard Deviation I 0.0209 Maximum 10.0931 Minimum 10.0083 Documentation of evaluations pertaining to compliance with the unrestricted use limit of 25 mredyr 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 EP 1.42A-4 to be less than 1 mredyr. The dose contribution is estimated to be 0.037 mredyr based on the average of the actual gross counts. A-p--- -~ Attachment 1 - BSI EPBP Survey Report Attachment 2 - Pipe Interior Radiological Survey Form Attachment 3 - DQA Worksheet Attachment 4 -Disc containing RR for EP 1.42A-4 & Spreadsheet SECTION 7 ATTACHMENT 1 3 PAGE(S) liiw iLI .- BSI EP/BP SURVEY REPORT Pipe ID EP 4.4-4 Suwey Date I 1 Pipe Size DCGL 2.41 EM5 un5 4.7 ' #p.*rrksffpaMbY I ~outinesurvey I X Survey Locatlon 2350-1 # Quad C I-27 Trench 203488 Detector-Skd Y 1MGl LVS-lI101 Detector Efficiency 0.00052 I 973 P(P- kcorpon*d bY - Ef===Y m-1 Field BKG 1-1 21.7 Field MDCR-I 19 Nominal MDC (dpnmnu) 1,557 I irvey Measurement Results Total Number of Survey Measurements Number of Measurements Above 50% DCGL Number of Measurements Above DCGL 48 Number of Measurements NDC 47 0 0 Mean 0.0374 Median 0.0330 Standard Deviation 0.0209 Maximum 0.0931 I 0.0083 Minimum ROSENHAGEN Survey Technician(s)
TBD O6-004 Piping Group 1 SR-13 Radionuclide Distribution Sample EP 3-9 Measured Nudi Ca-60 Area Factor/EMC Used No MREMNR Contribution
<l Pasflail FSS Pass COMMENTS:
ACTIVITY VALUES NOT BACKGROUND CORRECTED P -B-07 RP Engineer I Date EP 1.42A-4 4" Pipe TBD 06-004 Group 1 28 30 - gcpm - ia 14 32 27 2e 25 2e 32 24 2* 3c I* 21 3; 7E 7( 45 6* 5E 4: 4t 4i 4: l! li 41 5; 9 41 4! 21 _-__ _- __ -- __-- ___ ___- ___ - 53,846 57.692 '1" 61,538 51,923 - 28 53,846 29 55.769 ~ -- - - 32 79 70 49 66 56 43 ~- 63.462 61,538 151,923 134,615 94,231 126,923 107,692 82.692 -zJ--2m 40.385 92,308 90,385 82,692 28.846 48 92.308 94,231 53,846 c660 actlvity (dpm1100cm2) 1,977 2,767 6,325 5,337 5,535 5,732 5,139 6,523 4.744 _____ 5,535 5.930 3,558 4,151 6,325 15,616 13,837 9,686 13,046 1 1,069 8,500 9,488 9,290 8,500 2,965 3,360 9,488 11,267 10,674 9,488 9,686 5,535 ___I_ ___-__ Cs-I 37 activity (dpmll OOcm2) 78 .- 110 251 212 219 227 204 259 188 219 235 141 165 251 61 9 548 ___~ 384 517 439 337 __ 376 368 337 118 133 376 447 ______ 423 376 384 21 9 ~I__ Eu-IS2 advlty (dpm1100cm2) - 1,875 2,625 6,000 5,250 5,438 - 4,875 - 6,188 4,500 5,250 5,625 3,375 3,938 6 , 000 14,813 13,126 9,188 12,376 10,501 8,063 9.000 - 5,063 - ____- 8,813 - 8,063 2,813 3,188 - 9,000 _- 10,688 10,126 9,000 - 9,188 5.250 a -+GE j 1,346 1 1.396 2,443 ~ 2,343 i 2,143 i 748 i 847 i 2,393 2,393 Nb-Q4 activity 58 81 185 156 162 167 1 50 190 138 162 173 104 121 185 456 404 283 38 1 323 248 277 271 248 ~. 87 98 277 329 31 1 277 283 - 162 Ag-108m activity (dpmll OOcm2) 14 19 44 37 39 40 - 36 45 33 39 41 25 29 44 109 96 67 91 77 59 66 65 59 21 23 66 79 74 6* 67 - Unity - 0.01L 0.01 i 0.031 0.03; 0.03: 0.03 0.03' 0.031 0.02I 0.03: 0.03f 0.02' 0.02! 0.03(
0.09: 0.08: 0.051 0.07l 0.oa 0.05' 0.05; 0.05! 0.05' 0.011 0.02( 0.05 0.06' 0.W 0.05' 0.051 0.03: __-- - 1 of2 EP 1.42A-4 4" Pipe TBD 06-004 Group 1 23,077 30,769 32,692 17,308 28,846 30,769 48,077 67,308 53,846 88,462 94,231 51.923 7 Unity - 0.01s 0.01 E 0.01: 2,372 3,163 1,779 2,965 3,163 4,942 6,918 9,093 9,686 5.337 3,360 _____ 5,535 42 43 44 45 16 1* 25 2f 28 2f 35 3i 46 46 47 49 48 27 4* 42 2i *I I E"-& activity (dpnirl OOem2) Eu-162 activity (dpm1100cm2)
Nb-91 activity (dpm1100cm2)
Ag-1 O8m activity (dpm1100cm2)
Cs-137 activity (dpmll OOcrn2) 22 125 92 75 75 - 3,000 18 102 2,438 ______ 18 102 2,438 10 O.OOE 0.012 0.014 0.015 0.02c 0.01 1 0.01E 0.015 0.022 0.041 0.03: 0.09 0.05t 0.03; __- 40 58 69 92 98 1,313 1,875 - 2,250 3,000 - 3,188 - 1,688- 2,813 3,000 4,688 6,563 5,250 8,625 9,188 5,063 ___-___ 55 78 7 1c 14 17 22 23 12 -37)-; 38 16 94 125 133 71 118 52 87 92 144 202 162 , 265 21 22 41 15 1f 125 196 274 219 360 384 ____- 34 48 I 1,745 , 2,293 i 2,443 i 1,346 I I 39 63 67 37 283 156 212 - 0.03i 0.03: 0.02' 0.09: 0.00l ~. - A- MEAN MEDIAN STD DEV s!= --+--- MAX -_ MIN 2of2 SECTION 7 ATTACHMENT 2 4 PAGE(S)
I I BSVLVSPipeCrawler-002 Revision 4 Pipe Interior Radiological Survey Form c' Date: 3' /'ob Time: 08-27 5- Pipe ID#: /. Yd-4 PipeDiameter:
L/ Access Point Area:
/5fr rp Js5s~c uJAs7-5 ,+; Type of Survey Investigation Characterization Final Survey Other
/ pn~r EJ; Gross C060 I/ Building:
R X Elevation:
z-5 1;3utb c System: x';'~ ,+,+mL C/*i cs - Detector ID# / Sled ID# &?/@P/ /fib/ LJP 1 I /of Detector Cal Date: zl9- lSE.5 - o Detector Cal Due Date:
u- D*t- --oi Instrument Cal Date: /7 - dd d- 0 Instrument Cal Due Date: /7 dov- ob Instrument ID #: 2-35/n7 Instrument:
A39 I From the Daily Pipe Survey Detector Control Form for the Selected Detector Background Value 3/# ? cpm MDCRStatlC 14 cpm Efficiency Factor for Pipe Diameter 8 . b 0 0 5 MDC,,,, 1557 dPd 100 cm2 Is the MDCstabc acceptable?
@ No (ifno, adjust sample count time and recalculate MDCR,,,,) (from detector efficiency determination)
Technician Signature Pipe Interior Radiological Survey Package Page 1 of 2 REFERENCECOPY Attachment 3, Page 1 BSI/LVSPipeCrawler-O02 Revision 4 Pipe Interior Radiological Survey Form (Continuation Form) qJwdd c Access Point Area:
/SW Lip v~p~E.c /( Date: 3+ bb Pipe ID#: 1 ./ 3 Pipe Diameter:
&& Building:
2K Elevation:
-25 ?l/ptD c S ys tern: 7?r># d 2-23 b IC. Attachment 3, Page 2 BSE'LVSPipeCrawler-002 Revision 4 Pipe Interior Radiological Survey Form (Continuation Form) Building : Elevation: - 25 ,?UP%& c S ys tern : Package Page 2:f \ REFERENCE COPY Attachmen{;, Page 2 
 
SECTION 7 ATTACHMENT 3 I PAGE(S)
DQA Check Sheet Answers to the following questions should be fully documented in the Survey Unit Release Record Design # I EP 1.42A-4 I Revision#
I Original I Yes No N,A ~ ~~ 2. 3. 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? Is the instrumentation MDC for embeddedhuried piping static measurements below the DCGLw ? I. Have surveys been performed in accordance with survey instructions in the Survey Design?
1x1 I X X 0. Was the instrumentation MDC for structure scan measurements, soil scan measurements, and embeddedhuried piping scan measurements below the DCGLW, or, if not, was the need for additional static measurements or soil samples addressed in the survey design? 5. Was the instrumentation MDC for volumetric measurements and smear analysis 10% DCGLw ? X X 3. Were the MDCs and assumptions used to develop them appropriate for the instruments and techniques used to perform the survey? 2. Has a histogram (or other frequency plot) been created? 7. Wem the survey methods used to colled data proper for the types of radiation involved and for the media being surveyed?
~ ~~ ?. Is the mean of the sample data DCGLW?
X 3. If elevated areas have been identified by scans and/or sampling, is the average activity in each elevated area 1. Is the result of the Elevated Measurements Test 1 .O? DCGLEMC (Class l), < DCGLW (Class 2), or <0.5 DCGLw (Class 3)? 3. Were "Special Methods" for data collection properly applied for the survey unit under review?
1x1 I ~ ~~ X X X 3. Is the data set comprised of qualified measurement results collected in accordancewith thervey design, which accurately reflects the radiological status of the facility?
Graphical Data Review ~ 5. Is the result of the statistical test (S+ for Sign Test or W, for WRS Test) 1. the critical value? 1. Has a posting plot been created?
I I Ix ~ X FSSCharaderization Engineer (printlsign)
FSSl Characterization Manager (print/sign)
: 3. Have other graphical data tools been created to assist in analyzing the data? I I Ix *p Data Analysls I. Are all sample measurements below the DCGLW (Class 1 8 2), or 0.5 DCGLw (Class 3)? Form cs-0912 Rev 0 Page 1 of 1 SECTION 7 ATTACHMENT 4 1 DISC Survey Unit Release Record Design # Survey Unit
#(s) Description EP-Rx155 1 Revision#
1 Original I Page 1 of 3 Rx155 1) Embedded Pipe (EP) Survey Unit Rxl55 meets the definition of embedded pipe for Plum Brook Reactor Facility (PBRF). 2) EP RX155 is a Class 1, Group 2 swey unit as per the PBRF Final Status Survey Plan (FSSP) and Technical Basis Document (TBD)-06-004.
: 3) Surveys in EP Rx155 were performed using a scintillation detector optimized to measure gamma energies representative of CO-60. Sample #EP 2- 1 from Survey Request (SR)-l3 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 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 BSIZVS-002, WEP 05-006, these determinations are appropriate for the types of radiation involved and the media being surveyed.
_- I FSS Design # EP Rx155 1.0 2.0 3.0 4.0 5.0 Revision # Original Page 2 of 3 Hi st oryiDescripti on 1 .I EP Rxl55 is a sump trench vent that is located in the pump room on the - 25 foot of the Reactor Building.
The purpose of the system is to ventilate the sump trench. This system involves approximately 7 liner feet of drain system piping.
EP Rx155 consists of 7 linear feet
(') of 10 inch (") Inside Diameter (ID) piping starting in the -25 foot elevation trench and running to Quad B. The total piping for EP Rx155 is 7'. I .2 Survey Design Information 2.1 2.2 EP Rx155 was surveyed IAW Procedure
#BSULVS-002.
IOP? of the 10" ID pipe was accessible for survey. The accessible 10" ID pipe was surveyed by static measurement at one foot increments, for a total of 7 survey measurements.
Surface area for the 10" ID piping is 2,432 cm2 for each foot of piping, corresponding to a total 10" ID piping surface area of 17,024 cm2 (1.7 m2) for the entire length of (7') of IO" piping.. 2.3 Survey Unit Measurement LocationsData 3.1 Pipe interior radiological survey forms are provided in Attachment 2 of this release record. Survey Unit Investigationshtesults 4.1 None Data Assessment Results 5.1 5.2 5.3 5.4 Data assessment results are provided in the EPBuried Pipe (BP) Survey Report provided in Attachment
: 1. Level (DCGL) for radionuclide specific EP that corresponds to the 1 mredyr dose goal established in Table 3-3 of the FSSP. When implementing the Unity Rule, provided in Section 3.6.3 of the FSSP, and applying the Cesium-137/Cobalt-60 ratios, provided in TBD- 06-004, the survey unit that is constituted by EP Rx155 passes FSS. Background was not subtracted from the survey measurements and the Elevated Measurement Comparison (EMC) was not employed for this survey unit. 43ukkh&
FSS Design # EP Rx155 6.0 Revision # Original Page 3 of 3 7.0 Total Number of Survey Measurements
 
===5.5 Statistical===
 
Summary Table 7 Statistical Parameter Number of Measurements
>MDC Number of Measurements Above 50% of DCGL I 10" I 0 0 Number of Measurements Above DCGL Mean Median Standard Deviation Maximum Minimum 0 0.012 0.012 0.002 0.015 0.01 0 Documentation of evaluations pertaining to compliance with the unrestricted use limit of 25 mredyr 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 EP Rx155 to be less than 1 mredyr. The dose contribution is estimated to be less than 0.012 mrerdyr based on the average of the actual gross counts measured.
____ ~. _____ Attachments Attachment 1 - BSI EPBP Survey Report Attachment 2 - Pipe Interior Radiological Survey Form Attachment 3 - DQA Worksheet Attachment 4 -Disc containing RR for EP Rxl55 & Spreadsheet I SECTION 7 ATTACHMENT 1 2 PAGE(S)
I I Pipe ID Rx155 Survey Location Survey Date 10-Jan-06 2350-1 # Survey Time 1030 Detector-Sled
# Pipe Size 1 0" Detector Efficiency Plpe Area Incorporabed by Detsctor EWtciency (in cm2) 8SI EP/BP SURVEY REPORT -25 RX B566A-108 B I CRON/G3 0.003 2432 ~~ ~ DCGL (dpmM0OcrnZ) 240,800 Routine Survev X I I ~~ Field BKG(crm) 369.7 Field MDCR 1-1 I 69.3 Number of Measurements
>MDC Number of Measurements Above 50% DCGL Number of Measurements Above DCGL QA Survey I Norninal~~~(dW-2) 1 11,223 I I Survey Measurement Results 0 0 0 Total Number of Survey Measurements I 7 ~~ ~- ~ Median Standard Deviation 0.012 0.002 Mean I 0.012 ~~ ~ Minimum 0.010 Maximum I 0.015 RP Engineer I Date L 07 Activity values are not background corrected.
2OMMENTS:
6/6/2007 EP Rx155 TBD 06-004 Group 2
* C c. f s 2 a Q) (P 1 2 3 4 5 6 7 - gcpm 247 231 188 182 174 206 196 --t--- Cs-137 activity (dpmllWcm2)
Co-60 activity (total dpm) Eu-152 actlvity (dpm1100cm2)
Eu-154 actMty (dpn\nOOcm2) i Nb-S4 activity (dpm/lOOcm2)
I 247 231 188 1 82 1 74 206 196 I i _~__ 82,333 77,000 62,667 60,667 58,000 68,667 65,333 ~ 3,385 i 3166 ___+A I 2,577 -. ' 2,495 2,385 2,823 i I 17t_: 16 L _Ti- I Unity Agl08m activity (dpmfl00cmZ)
__ 98 0.015 92- 0.0% 72 0.011 69 0.01C 82 0.01; 78 0.01; 75 00% ~ ___ 1of1 SECTION 7 ATTACHMENT 2 2 PAGE(S)
I Pipe Interior Radiological Survey Form Date: /. /P-Ub Time: /636 Building : ?!rkT* Elevation
/ 2s' Access Point - 32 A; S++ System: bT-c+?MPipe Diameter:
&/Area: Pipe ID Zf - />-A ' Type of Survey Investigation Characterization Final Survey
# Other ,/ Sled Size L' inch Detector:
Bfk#d/ cp 3 17 - rood 'dei- jq- h)Dd Cal Date: Instrument:
33s -- I Cal Date: From the Daily Pipe Survey Detector Control Form Background Value 2k 7 7 cpm MDCRstatic b 7-3 CPm Efficiency Factor for Pipe (3c on3 meter statlc /) 223 dpm/100cm2 Detector ID #: 35b(dk-/bd Cal Due Date: /'7 -Nod -0 (&. Instrument ID #: 2Q3~mY Cal Due Date: /'7-+JtI: - u c for the Selected Detector (taken from detector IS the MDCSQtic (ifno, adjust sample count time and recalculate MDCR,,,ic) c&%&?fitli!e?
REFERENCECOPY 0 Attachment 3, Page 1 REFERENCECOPY I-I SECTION 7 ATTACHMENT 3 I PAGE(S)
I I Design # EP Rx155 Revision # Original I ~~ 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? Survey Unit # Ix EP Rx155 Answers to the following questions should be fully documented in the Survey Unit Release Record Have surveys been performed in accordance with survey instructions in the Survey Design? 1. 5. Was the instrumentation MDC for volumetric measurements and smear analysis < 10% DCGLW ? I I I X Yes No NIA X ~~ 3. 4. Is the instrumentation MDC for embeddedlburied piping static measurements below the DCGLw ? Was the instrumentation MDC for structure scan measurements, soil scan measurements, and embeddedlburied piping scan measurements below the DCGLw, or, if not, was the need for additional static measurements or soil samples addressed in the survey design?
X 9. Is the data set comprised of qualified measurement results collected in accordance with the survey design, which accurately reflects the radiological status of the facility?
GraDhical Data Review X ~~~ ~~ ~ 6. Were the MDCs and assumptions used to develop them appropriate for the instruments and techniques used to perform the survey3 7. Were the survey methods used to collect data proper for the types of radiation involved and for the media being surveyed?
: 8. Were 'Special Methods" for data collection properly applied for the survey unit under review?
~- ~ Data Analysis X X ___ ~- - ___ - X ~- - 1. Are all sample measurements below the DCGLw (Class 1 & 2). or 0.5 DCGLw (Class 3)? ~~ 1. 2. 3. Has a posting plot been created?
Has a histogram (or other frequency plot) been created? Have other graphical data tools been created to assist in analyzing the data? X X X 2. Is the mean of the sample data DCGLw? 3. 4. If elevated areas have been identified by scans andlor sampling, is the average activity in each elevated area < DCGLEMC (Class l), < DCGLw (Class Z), or <0.5 DCGLw (Class 3)? Is the result of the Elevated Measurements Test 1 .O? Form Rev 0 CS-09D X X X Page 1 of 1 ~~~~~ ~ 5. Is the result of the statistical test (S+ for Sign Test or W, for WRS Test) 2 the critical value? X SECTION 7 ATTACHMENT 4 1 DISC 43 COPY EP-Rx 113D Revision ## Design ## Original Page 1 of 3 Survey Unit #(s) Description
: 2) EP Rx 113D is a Class 1, Group 2 survey unit as per the PBRF Final Status Survey Plan (FSSP) and Technical Basis Document (TBD)-06-004.
: 3) Surveys in EP Rx I 13D were performed using a scintillation detector optimized to measure gamma energies representative of Co-60.
Sample #EP 2- 1 fiom 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 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 BSVLVS-002, WEP 05-006, these determinations are appropriate for the types of radiation involved and the media being surveyed.
FSS Design ## EP Rx 1 13D Revision # Original 1 .o 2.0 3.0 4.0 5.0 Page 2 of 3 History Description 1.1 1.2 Survey Design Information 2.1 2.2 The subject pipe system is the 0.75" Quad "B" system line. EP Rx 1 13D is approximately 17 feet in length.
EP Rx 113D was surveyed IAW Procedure #BSI/LVS-002.
100% of the 0.75" ID pipe was accessible for survey.
The accessible 0.75" ID pipe was surveyed by static measurement at one foot increments, for a total of 17 survey measurements.
Surface area for the 0.75" ID piping is 182 cm2 for each foot of pi ing, corresponding to a total 0.75" ID piping surface area of 3,101 cm (0.3 m2) for the entire length of (17) of 0.75" piping..
2.3 P Survey Unit Measurement Locations/Data 3.1 Pipe interior radiological survey forms are provided in Attachment 2 of this release record. Survey Unit InvestigationsResults 4.1 None Data Assessment Results 5.1 5.2 Data assessment results are provided in the EP/Buried Pipe (BP) Survey Report provided in Attachment
: 1. All measurement results are less than the Derived Concentration Guideline Level (DCGL) for radionuclide specific EP that corresponds to the 1 &yr dose goal established in Table 3-3 of the FSSP. When implementing the Unity Rule, provided in Section 3.6.3 of the 5.3 FSSP, and applying the Nuclide Fraction (NF), provided in TBD-06-004, the survey unit that is constituted by EP Rx 113D passes FSS. 5.4 Background was not subtracted from the survey measurements and the Elevated Measurement Comparison (EMC) was not employed for this survey unit.
I I FSS Design # EP Rx 113D Revision # Original Page 3 of 3 5.5 Statistical Summary Table Total Number of Survey Measurements Number of Measurements
>MDC I 0.75" 17 12 Statistical Parameter Number of Measurements Above 50% of DCGL Number of Measurements Above DCGL 1 Pipe 0 0 Standard Deviation Maximum 0.01 38 0.0685 Mean Minimum Io.0464 0.0242 Median 10.0483 Documentation of evaluations pertaining to compliance with the unrestricted use limit of 25 medyr and dose contributions fiom 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 EP Rx 113D to be less than 1 mredyr. The dose contribution is estimated to be 0.046 rnredyr based on the average of the actual gross counts. ______ - - __ ---- Attachment 1 - BSI EPBP Survey Report Attachment 2 - Pipe Interior Radiological Survey Form Attachment 3 - DQA Worksheet Attachment 4 -Disc containing RR for EP Rx 1.13D & Spreadsheet SECTION 7 ATTACRNIENT 1 Z PAGE(S)
BSI EPlBP SURVEY REPORT Pipe ID Rx 113D Survey Location
-27' Trench Loop Drair SurveyDate 1 02;;; , 1 1 2350-I# Survey Time DetectorSled
# I 0.00059 189094 0047-no sled Pipe Size 0.75" 1 1 Detector Efficiency 2.41 E+05 P(p-kapon(.d w- Emancr DCGL 14mno~a2)
Fkld BKG iSp.1 182 18.3 Routine Survey I X Total Number of Survey Measurements Number of Measurements
>MDC Number of Measurements Above 50% DCGL Number of Measurements Above DCGL Mean Median Standard Deviation 17.8 I II Field MDCR 1-1 17 12 0 0 0.0464 0.0483 0.0138 Area FactodEMC Used PasslFail FSS MREWR Contribution Maximum I 0.0685 Minimum 0.0242 STOCK Survey Technician(s)
No Pass <f Survey Unit Classification 1 1 TED 06-004 Piping Group 2 SR-13 Radionuclide Distribution Sample EP 2-1 Measured Nudie I cm COMMENTS:
ACTIMTY VALUES NOT BACKGROUND CORRECTED
&e 7-/7-07 RP Engineer I Date EP Rx 113D 0.75" Pipe TBD 06-004 Group 2 - Unity - 0.03; 0.03; 0.06 0.021 0.021 0.05; 0.05; 0.06( 0.041 0.041 0.041 0.06( 0.W 0.04I 0.061 0.024 0.05; 0.04t 0.04 O.Olr 0.061 0.024 ~. - - ._ - Co60 activity (total dpm) Ag-lO8m activity (dpmll OOcm2) COS0 actlvity Cs-137 activlty (dpm1100cm2) (dpm1lOOcm2) ncpm 13,559 13,559 -. - 27,119 _- - ~- 11.864 4 62 44 62 44 4 123 i 87 7 54 38 3 46 33 3 100 71 6 .__ 100 71 6 116 I 82 7 92 65 5 92 65 5 ~- ____ -_ ___ __ -_ 92 I 65 5 214 214 - ._ ~- - ___ 7,709 14,867 ._ 3,373 6,504 5,575 2,891
__ 12,079 6,264 12,079 6,264
.~ 13,938 7,227 11,150 5,782 - 11,150 5,782 -- -- 11.150 5.782 428 187 160 348 348 401 32 1 32 1 32 1 401 294 32 1 455 160 348 -. . - -. - __ - -. 10;169 22.034 13 13 - 15 12 12 12 15 12 17 6 - - -~ 11 _-___ ~- ,- 13,938 7,227 10.221 5.300 25,424 18,644 20,339 28,814 10,169 22.034 - -___ _____ 92 I 65 5 -- 131 I I 92 8 5,782 - 8,191 12,079 6,264 5,575 ____- 46 I ! 33 1 3 100 I 6 12 dEAN lllEDlAN 3D DEV dAx dlN T 1of1 SECTION 7 ATTACHMENT 2 3 PAGE(S) 
-- I I BSYLVSPipeCrawler-002 Revision 4 Pipe Interior Radiological Survey Form I Date: T/Z,/OG Time: 1025 Pipe Diameter:
.7d' -27 Access Point Area: - 2 7 ~rz E~JC /+ System: LW? OR#/n/ I Pipe IDX: & It9 Building: Elevation:
Type of Survey Investigation Characterization Final Survey )( Other f Gross Co60 4 cs Detector ID# / Sled ID# e// A- % ym47 I No SLED Detector Cal Date: 2[2d/Og I I Detector Cal Due Date:
2/za/,7 # Instrument:
23 co- 1 Instrument ID #: gqD 9 Instrument Cal Date: 31) >'/a t Instrument Cal Due Date: 3/r r&7 # t From the Daily Pipe Survey Detector Control Form for the Selected Detector Background Value r.3 cpm MDCRstatlc 17, 8 CPm Efficiency Factor for Pipe Diameter mcstahc 763 I dpm' 100 cm2 Is-the-MDCskhc acceptable?
@ No (if nq adj.st-.saqk aunt tmeand.redadattC 0.0 006 (from detector efficiency determination)
Ccments: L~JI n- 5Q.T UI?+ Efz- / LLWPL-1~~ - Technician Signature
#
I I BSULVSPipeCrawler-002 Revision 4 Pipe Interior Radiological Survey Form (Continuation Form) Pipe Diameter:
8 7s" Access Point Area: S ys tern: Elevation:
-21 Pipe ID#: Building:
Package Page 3 of 3 n REFERENCECOPY Attachment 3, Page 2 I 1 1 I L I SECTION 7 ATTACHMENT 3 I PAGE(S) 
~~ - DQA Check Sheet Survey Unit # Design # T EP Rx 113D 1 Revision # 1 Original 1 __~ EP Rx 113D Answers to the following questions should be fully documented in the Survey Unit Release Record 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? Yes No 1. 2. Have surveys been performed in accordance with survey instructions in the Survey Design?
X NIA X 6. Were the MDCs and assumptions used to develop them appropriate for the instruments and techniques used to perform the survey3 7. Were the survey methods used to collect data proper for the types of radiation involved and for the media being surveyed?
X ~~ 3. 4. Was the instrumentation MDC for structure scan measurements, soil scan measurements, and embeddedlburied piping scan measurements below the DCGLw, or, if not, was the need for additional static measurements or soil samples addressed in the survey design?
Was the instrumentation MDC for volumetric measurements and smear analysis .z 10% DCGLw ? Is the instrumentation MDC for embeddedlburied piping static measurements below the DCGLw ? 5. X 1. Has a posting plot been created? I I lx 8. 9. Is the data set comprised of qualified measurement results collected in accordance with the survey design, which accurately reflects the radiological status of the facility?
Were "Special Methods" for data collection property applied for the survey unit under review?
X X 3. Have other graphical data tools been created to assist in analyzing the data? I I Ix ~__ ~~ ~ 2. Has a histogram (or other frequency plot) been created? X 1. 2. 3. 4. Are all sample measurements below the DCGLw (Class 1 & 2), or 0.5 DCGLW (Class 3)? Is the mean of the sample data c DCGLw? If elevated areas have been identified by scans and/or sampling, is the average activity in each elevated area Is the result of the Elevated Measurements Test < 1 .O? DCGLEMC (Class I), < DCGLw (Class 2), or ~0.5 DCGLw (Class 3)? Form cs-0912 Rev 0 X X X X Page 1 of 1 ~~ 5. Is the resuli of the statistical test (S+ for Sign Test or Wr for WRS Test) 2 the critical value? X SECTION 7 ATTACHMENT 4 1 DISC I EP- 1.64 1-8 Revision ## '0 copy Original Page 1 of 3 Design # Survey Unit #(s) Description 1.64 1-8 1) Embedded Pipe (EP) Survey Unit 1.641-8 meets the definition of embedded pipe for Plum Brook Reactor Facility (PBRF).
: 2) EP 1.641-8 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 1.641 -8 were performed using a scintillation detector optimized to measure gamma energies representative of CO-60. Sample #EP 3-8 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 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 BSVLVS-002, WEP 05-006, these determinations are appropriate for the types of radiation involved and the media being surveyed.
r I FSS Design # EP 1.64 1-8 1 .o 2.0 3.0 4.0 5.0 Revision # Original Page 2 of 3 HistoryDescription 1.1 The subject pipe system is the header fiom the 4 inch overflow to Canals H & G to the -25A of Rx Building in Pump Room #22. The hction of this pipe was to convey water fiom the 4 inch overflow piping leading to canals "H' and "G to the HD sump in Pump Room #22, where the pipe is currently breached. Survey Unit 1.64 1-8 represents all the 8"diameter piping associated with pipe ID 1 541. EP 1.641 -8 consists of 8" diameter piping that is approximately 5 1 feet in length. 1.2 Survey Design Information 2.1 2.2 EP 1.641-8 was surveyed IAW Procedure #BSVLVS-002.
100% of the 8" ID pipe was accessible for survey. The accessible 8" ID pipe was surveyed by static measurement at one foot increments, for a total of 5 1 survey measurements.
Surface area for the 8" ID piping is 1,946 cm2 for each foot of piping, corresponding to a total 8" ID piping surface area of 99,234 cm2 (9.9 m2) for the entire length of (approximately 5 1 ') of 8" piping.. 2.3 Survey Unit Measurement Locations/Data 3.1 Pipe interior radiological survey forms are provided in Attachment 2 of this release record. Survey Unit InvestigationsResults 4.1 None Data Assessment Results 5.1 5.2 5.3 5.4 Data assessment results are provided in the EP/Buried Pipe (BP) Survey All measurement results are less than the Derived Concentration Guideline Level (DCGL) for radionuclide specific EP that corresponds to the 1 mdyr dose goal established in Table 3-3 of the FSSP. 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 1.641-8 passes FSS. Background was not subtracted from the survey measurements and the Elevated Measurement Comparison (EMC) was not employed for this survey unit. Report provided in Attachment
: 1. ____.__ ~ __
FSS Design # EP 1.641 -8 5.5 Statistical Summary Table Revision I# Original Page 3 of 3 I Statistical Parameter - Survey Unit: 1.641 -8 Total Number of Survey Measurements Number of Measurements
>MDC Number of Measurements Above 50% of DCGL Number of Measurements Above DCGL Mean Median Standard Deviation Maximum Minimum Documentation of evaluations pertaining to compliance with the unrestricted use limit of 25 mdyr 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 EP 1.641-8 to be less than 1 mrdyr. The dose contribution is estimated to be 0.01 7 rnredyr based on the average of the acW gross counts measured.
-~-~ - Attachments Attachment 1 - BSI EP/BP Survey Report Attachment 2 - Pipe Interior Radiological Survey Form Attachment 3 - DQA Worksheet Attachment 4 - SURR EP 1.641 -8 & Spreadsbeet Disc 51 25 0 0 0.0171 0.0161 0.0085 0.0628 0.0058 SECTION 7 ATTACHMENT 1 3 PAGE(S)
BSI EPlBP SURVEY REPORT Survey Date - Pipe ID 1.641 -8 Survey Location 1 Canal GBH overflow ! 11 I 18-Jul-07 2350-1 # 189094 .- SR-13 Radionudide Distribution Sample Measured Nuclide Area Fador/EMC Used PasslFail FSS MREMNR Contribution
___- - I SuweyTime 1 13:s 11 EP 3-8 No Pass 4 ~- I 1MGI LVS-Ill07 Survey Technidan(s)
Survey Unit Classifmtion I 1 TBD O6-004 Piping Group 1 I 8Ll u 7-2E-07 RP Engineer I Date 7/25/2007 l- EP 1.641-8 8" Pipe TBD 06-004 Group 1 Cs-137 activity Eu-152 activrty (dpmll OOcmZ) (dpmll OOcmZ) 1 36 3.250 __- 97 __ 27322 126 3,018 165 3,947 184 4,411 107 2,554 145 3,482 155 3,714 136 3,250 126 3,018 116 2,786 78 1,857 78 1.857 ~- 68 I 1,625 97 I 2.322 555 1864 1 617 I 802 1,173 926 -/987 1864 864 432 =p 555 Nb-94 activity (dpml100cmZ) 64 100 71 93 121 136 79 107 114 100 93 86 57 57 88 1 oa 5c 71 71 64 107 -- 1 of2 11 32 1 1 4. 1 .- 1' 1 ___- ~~ ncpm 7 7 1c 14 1: IC E f 1; l! -- 14 1: 4: l! L 1' 33,333 47,619 57,143 47,619 61,905 38,095 23,810 33,333 23,810 57,143 90,476 66,667 80,952 204,762 71,425 66,667 61,905 57,142 52,381 EP 1.641-8 8" Pipe TBD 06-004 Group 1 co80 activity Cs-137 activity (dpmll00cm2) (dpmllOOcm2) t----t- Eu-152 activity Eu-1 activity Nb-94 activity AglOBm activity (dpm1100cm2) 00cm2) (dpm1100cmZ) (dpm1100cm2)
MEAN MEDIAN 1 1 STD DEV MIN _- MAX .___ __ Unity - O.Ol( 0.011 0.011 0.01! 0.01! 0.01: 0.00 0.01' 0.00 0.01 0.02 0.02 0.01 0.01 0.01 2of2 SECTION 7 ATTACHMENT 2 4 PAGE(S)
Date: I BSYLVSPipeCrawler-002 Revision 5 Pipe Interior Radiological Survey Form 7-19-0'7 Time: 139.4 Pipe ID#: \ b'4 \ Pipe Diameter:
s It Access Point Area: -dl & h% a\&- 4 System: k\ 6aH W%& Building:
Elevation:
U Type of Survey Investigation Characterization Finalsurvey
>( Other d Gross Co60 \I cs Detector ID# / Sled ID# Inhi /kWI 1 107 Detector CalDate: ' - 0 7 Detector Cal Due Date: 1 d 'jj Instrument Cal Date: 1 - f) - 0 7 Instrument Cal Due Date: \@ \\ - 0 5 Instrument:
13Sd - I Instnunent ID #: my d1u From the Daily Pipe Survey Detector Control Form for the Selected Detector Background Value 3 L cpm MDCRStiLtiC 9, 5 cpm Efficiency Factor for Pipe Diameter PvlDCstatic 2 dpd LOP cm2 Is the MDCstabc acceptable?
01 0 Dz 1 (from detector efficiency determination)
No (if no, adjust sample count time and recalculate MDatic) Comments:
Q. 4 sV\lmf*d Em-% 1 I h34 c,*LL / u Technician Signature 3A Pipe Interior Radiological Survey Package Page 1 of 2 REFERENCECOPY Attachment 3, Page 1 I BSVLVSPipeCrawler-002 Revision 5 Pipe Interior Radiological Survey Form (Continuation Form) Access Point Area: TMQ~ Building: Elevation: System:
L\ GCNO~LU Pi;eaz#: $2 *' Pipe Diameter:
REFERENCECOPY Package Page z of* Attachment 3, Page 2 I BSULVSPipeCrawler-002 Revision 5 Position Feet into Pipe Count Time # fiom Opening (min) 4b uc I 47 97 4Y 4% -47 uq SO S-) s\ 4\ \ Pipe Interior Radiological Survey Form (Continuation Form) I dpm/100cm2 1 Gross Counts Gross Net cpm cpm 97 y 3 n I& J1 1s 15 I (4 lq \? \3 \z la. 11 I\ lv I I REFERENCE COPY Package Page 5 of & Attachment 3, Page 2 REFERENCE COPY 0 SECTION 7 ATTACHMENT 3 1 PAGE(S)
_- I SECTION 7 ATTACHMENT 4 1 DISC Design # Survey Unit #(s) Description Survey Unit Release Record EP-1.641-4 1 Revision # I Original I Page 1 of 3 1.641-4 1) Embedded Pipe (EP) Survey Unit 1.6414 meets the definition of embedded pipe for Plum Brook Reactor Facility (PBRF). 2) EP 1.641-4 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 1.641 -4 were performed using a scintillation detector optimized to measure gamma energies representative of CO-60. Sample #EP 3-8 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 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 BSVLVS-002, WEP 05-006, these determinations are appropriate for the types of radiation involved and the media being surveyed.
FSS Design # EP 1.641-4 Revision ## Original 1.0 2.0 3.0 4.0 5.0 Page 2 of 3 Historyfiscription 1,1 The subject pipe section is the 4 inch overflow header to Canals F, G & H. The function of this pipe was to convey water fiom the 4 inch risers in each of the canals to the 8 inch header leading to the HD sump in Pump Room #22 on the Rx -25ft, where the pipe is currently breached. Survey Unit 1.641 -4 represents all the 4"diameter piping associated with pipe ID 1.641. EP 1,641 -4 consists of 4" diameter piping that is approximately 34 feet in length. 1.2 Survey Design Information 2.1 2.2 EP 1.641-4 was surveyed IAW Procedure
#BSVLVS-002.
100% of the 4" ID pipe was accessible for survey.
The accessible 4" ID pipe was surveyed by static measurement at one foot increments, for a total of 34 survey measurements.
Surface area for the 4" ID piping is 973 cm2 for each foot of piping, corresponding to a total 4" ID piping surface area of 33,078 cm2 (3.3 rn') for the entire length of (approximately 34') of 4" piping.. 2.3 Survey Unit Measurement Locations/Data 3.1 Pipe interior radiological survey forms are provided in Attachment 2 of this release record. Survey Unit InvestigationsAXesults 4.1 None Data Assessment Results 5.1 5.2 5.3 5.4 Data assessment results are provided in the EP/Buried Pipe (BP) Survey All measurement results are less than the Derived Concentration Guideline Level (DCGL) for radionuclide specific EP that corresponds to the 1 mredyr dose goal established in Table 3-3 of the FSSP. 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 1.641 -4 passes FSS. Background was not subtracted from the survey measurements and the Elevated Measurement Comparison (EMC) was not employed for this survey unit.
Report provided in Attachment
: 1. -~__-
FSS Design # EP 1.641 -4 Revision # 0rigm.d 5.5 Statistical Summary Table Page 3 of 3 6.0 Total Number of Survey Measurements Number of Measurements
>MDC Number of Measurements Above 50% of DCGL Number of Measurements Above DCGL Mean Median Standard Deviation Maximum Minimum 7.0 34 21 0 0 0.0194 0.0187 0.0053 0.0324 0.0085 Statistical Parameter Documentation of evalrtations periaining to compliance with the unrestricted use limit of 25 mdyr 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 EP 1.641 -4 to be less than 1 mrerdyr. The dose contribution is estimated to be 0.019 mredyr based on the average of the actual gross counts measured. ~ ~ ~ Attachments Attachment I - BSI EP/BP Survey Report Attachment 2 - Pipe Interior Radiological Survey Form Attachment 3 - DQA Worksheet Attachment 4 - SURR EP 1.641 -4 & Spreadsheet SECTION 7 ATTACHMlENT 1 3 PAGE(S)
BSI EPIBP SURVEY REPORT Survey Date I ! !! Pipe ID 1.641 4 Survey Location I Canal G8H overflow I 19Jul-07 2350-1 t 189094 Pipe Size Survey Time I 4" Detector Efficiency I O.OOO36 I1 I Detector-SM
# TBD O6-004 Piping Group SR-I3 Radionuclide Distribution Sample Measured Nuclide Area FactorlEMC Used PasslFail FSS MREMlYR Contribution lMGl LVS-IIlOl I 1 EP 3-8 co-60 ~ No Pass <l RP Engineer I Date - I Maximum I 0.0324 Minimum 0.0085 I Survey Technician(s)
FOWLER COMMENTS:
ACTIVITY VALUES NOT BACKGROUND CORRECTED.
EP 1.6414 4" Pipe TBD 06-004 Group 1 I I I I I Ag-108m activlty (dpmllOOcm2) 18 20 16 10 14 .~ 28 24 - 22 _- 24 Jnity - 0.01! 0.01' 0.01~ O.OO! 0.01: 0.01 0.01 0.01 0.01 0.02 0.02 0.02 0.01 0.02 0.01 0.02 0.02 - - - - - ___ - __ - __ - __ __ - __ __ 1 of2 ncpm s EP 1.641-4 4" Pipe TBD 06-004 Group 1 activity Cs-137 activity (dpm1100cm2) 4,283 Eu-152 activity Eu-164 activity Nb-94 activity Ag-108m activity (dpm1100crnZ) (dpm1100crn2) (dpml100cm2) (dpm1100crn2) 4,334 1,152 133 32 0.02; 4,063 1,080 125 30 0.02( I MEAN 0.01! MEDIAN O.Ol! 0.ooi STD DN -~ MAX 0.03: MI N 0.00 _- - - 2of2 SECTION 7 ATTACHMENT 2 3 PAGE(S)
I I BSYLVSPipeCrawler-002 Revision 5 Pipe Interior Radiological Survey Form Date: 7 - I 7 -07 Time: O%S 6 Access Point Area: d- &[ System: G+)i L\m SCJ Pipe ID#: 1 kb2j 1 ~ Pipe Diameter:
Y* / Building: Elevation:
-25' Type of Survey Investigation Characterization FinalSurveyx-Other / Gross Co60 d cs Detector ID# / Sled ID# I mb 1 U f -1 /\ol Detector Cal Date: \- \I- as
* Detector Cal Due Date: 1- l\- bP Instrument:
23so -1.. Instrument ID #: 167 Q?q Instrument Cal Date: 1- \\ - 07 Instrument Cal Due Date: 1 -11 0 9 From the Daily Pipe Survey Detector Control Form for the Selected Detector BackgroundValue 3 \ cpm Efficiency Factor for Pipe Diameter 61000367 (fiom detector efficiency determination)
MDCRStiItlC 9,\ CPm MDCS,tlC 3054 dpd IOa cm2 Is the MDCSQtic acceptable?
@ No (if no, adjust sample count time and recalculate MDCR&
Technician Signature r Pipe Interior Radiological Survey REFERENCECOPY 0 Package Page 1 of3 Attachment 3, Page 1 Pipe Interior Radiological Survey Form (Continuation Form) I BSYLVSPipeCrawler-002 Revision 5 H Date: Pipe ID#: ZJ Pipe Diameter: Access Point Area: , Building:
7 - \ 9 - 07 Elevation: System:
G+ H cor.,*\ Duuclu. 2JJ Y Attachment 3, Page 2 
 
I SECTION 7 ATTACHMENT 3 I PAGE( S)
DQA Check Sheet ~~ Survey Unit # Design # 1 EP 1.6414 I Revision # I Original 1 EP 1.641-4 Yes Answers to the following questions should be fully documented in the Survey Unit Release Record
: 1. Have surveys been performed in accordance with survey instructions in the Survey Design? 1x1 I No N/A 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? I - 3. 4. Was the instrumentation MDC for structure scan measurements, soil scan measurements, and static measurements or soil samples addressed in the survey design? Is the instrumentation MDC for embeddedhuried piping static measurements below the DCGLw ? embedded/buried piping scan measurements below the DCGLw, or, if not, was the need for additional Ix X X ~ ~~ ~ ~ ~ ~~ 5. Was the instrumentation MDC for volumetric measurements and smear analysis < 10% DCGLw ? 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? - X X 8. Were 'Special Methods" for data collection properly applied for the survey unit under review? 1x1 I 1. Has a posting plot been created?
X 2. 3. Has a histogram (or other frequency plot) been created?
Have other graphical data tools been created to assist in analyzing the data?
Data Analysis X X 2. Is the mean of the sample data < DCGLW? 3. If elevated areas have been identified by scans and/or sampling, is the average activity in each elevated area .Z DCGLEMC (Class l), .Z DCGLW (Class 2), or ~0.5 DCGLW (Class 3)? 4. Is the result of the Elevated Measurements Test .Z 1 .O? X X X Page 1 of 1 5. Is the result of the statistical test (S+ for Sign Test or W, for WRS Test) 2 the critical value? X 
-- I SECTION 7 ATTACHMENT 4 1 DISC Design # EP-Rx 150D Revision # Original Survey Unit #(s) Page 1 of 3 Description Rx 150D 1) Embedded Pipe (EP) Survey Unit Rx 150D meets the definition of embedded pipe for Plum Brook Reactor Facility (PBRF). 2) EP Rx 150D is a Class 1, Group 2 survey unit as per the PBRF Final Status Survey Plan (FSSP) and Technical Basis Document (TBD)-06-004.
: 3) Surveys in EP Rx 150D were performed using a scintillation detector optimized to measure gamma energies representative of CO-60. Sample #EP 2- 1 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 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.
FSS Design ## EP Rx 150D Survey Unit: Rx l5OD 1 .o 2.0 3.0 4.0 5.0 HistoryDescription 1.1 1.2 Survey Design Information 2.1 2.2 The subject pipe system is the 0.75" Quad "B" system line. EP Rx 1 SOD is approximately 15 feet in length. EP Rx 1 SOD was surveyed IAW Procedure #BSVLVS-002.
100% of the 0.75" ID pipe was accessible for survey. The accessible 0.75" ID pipe was surveyed by static measurement at one foot increments, for a total of 15 survey measurements.
Surface area for the 0.75" ID piping is 182 cm2 for each foot of pi ing, corresponding to a total 0.75" ID piping surface area of 2,736 cm (0.3 m2) for the entire length of (1 5') of 0.75" piping..
2.3 B Survey Unit Measurement LocationsData 3.1 Pipe interior radiological survey forms are provided in Attachment 2 of this release record.
Survey Unit InvestigationslResults 4.1 None Data Assessment Resuits 5.1 5.2 Data assessment results are provided in the EPBuried Pipe (BP) Survey Report provided in Attachment
: 1. All measurement results are less than the Derived Concentration Guideline Level (DCGL) for radionuclide specific EP that corresponds to the 1 mdyr dose goal established in Table 3-3 of the FSSP.
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 150D passes FSS. Background was not subtracted from the survey measurements and the Elevated Measurement Comparison (EMC) was not employed for this survey unit. 5.3 5.4 FSS Design # EP Rx l5OD Revision # Original 5.5 Statistical Summary Table Page 3 of 3 Statistical Parameter Total Number of Survey Measurements Number of Measurements >MDC Number of Measurements Above 50% of DCGL 0.75" Pipe 15 10 0 Documentation of evaluations pertaining to compliance with the unrestricted use limit of 25 &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 EP Rx 150D to be less than 1 mredyr. The dose contribution is estimated to be 0.038 mredyr based on the average of the actual gross counts. ____..~_______. - Attachment 1 - BSI EPBP Survey Report Attachment 2 - Pipe Interior Radiological Survey Form Attachment 3 - DQA Worksheet Attachment 4 -Disc containing RR for EP Rx 1 SOD & Spreadsheet Number of Measurements Above DCGL Mean Median Standard Deviation Maximum Minimum 0 0.0384 0.0403 0.01 30 0.0564 0.0161 4 SECTION 7 ATTACHMENT 1 2 PAGE(S) 
! I Number of Measurements
>MDC Number of Measurements Above 50% DCGL Number of Measurements Above DCGL Mean BSI EPIBP SURVEY REPORT 10 0 0 0.0384 Pipe ID 2 I 02-Aug-06 Survey Date Survey Time 12:50 Pipe Size 0.75 DCGL wmmcm2) 2.41 E95 nP.Wlnsorpor*pW
 
===0.3 Routine===
Survey X D p '1 Total Number oi Survey Location -27' Trench Loop Drair Detector-Sled
# 0047-no sled Detector Etficiency 0.00059 182 Field MDCR (cp) Survey Measurement Results iurvey Measurements 15 aurvey unn uassmtxion 1 I TBD O6-004 PiDitw Group 2 .- 1 SR-13 Radionuclide Distribution Sample EP 2-1 Measured Nudide C0-60 PasdFail FSS Pass Area FactorlEMC Used No MREMNR Contribution el :OMMENTS:
CTNITY VALUES NOT BACKGROUND CORRECTED 7- /7-0 7 EP Rx 150D 0.75" Pipe TBD 06-004 Group 2 11 7 A A I3 C060 activity (totaldpm) ncpm 10 16,949 18,644 11 7 11,864 11 18,644 10 16,949 10 16,949 14 23,729 4 6,78C 9 15,254 4 6,78C 12 20,33E 14 23,72E 8 13,552 6 10,161 ~- ___ - ___ _- 13. __ 22,03 C0-60 acthri (dpmll OOcm2) 9,292 6,504 10,221 9,292 9,292 13,009 3,717 8,363 3,717 - 11,150 13,009 7.433 10,221 ~- .~ 12:079 5.572 Cs-137 activity (dpm1100cm2) 4,818 5,300 3,373 5,300 4,818 4,818 6,745 1,927 4,336 1,927 5,782 6,745 3,855 6,264 __ 2,891 --- ~___-. t--- I _-- EU-152 activity ldomllOOcm2l
.. 77 85 54 85 77 77 - 108 31 69 - 31 92 108 62 1 oa 46 Eu-1 activity Nb-94 activity Ag-lO8m activity (dpml ? OOcm2) (dpmll00cm2) (dpm1100cm2)
I i MEAN 0.038 0.040 MEDIAN __ - STD DEV 0.01 3 MAX 0.056 MIN 0.016 - 1 of 1 I SECTION 7 ATTACHMENT 2 3 PAGE(S)
I Position Feet into Pipe Count Time Gross Counts # fiom Opening (min) 1 I IO 2 3 1 jr 3 3 e IO 4 iA 5 6 L IC) 7 7 I+ 8 Q 4 9 4 7 io 10 w I I BSVLVSPipeCrawler-002 Revision 4 Net 1 dpdl OOcm2 Gross cpm cpm 10 la /a/ /I 10 JO I 4 I 14 j I I 4 I I ! 4 d I I I Pipe Interior Radiological Survey Form Time: IZe Pipe Diameter:
e75 Access Point Area: - 2 7 '7/2tW df Elevation:
-27 System: Loo? D/-w.rlLlf c Type of Survey Investigation Characterization A Final Survey X Other - Gross C06O .rl cs - Detector ID# / Sled ID# ~o//. I; L - x *ob471 &O SLiW3 Detector Cal Date: Z/ZO 10 6 Detector Cal Due Date: 0 7 Instrument:
23 523 -7 Instrument ID #: I69094 II Instrument Cal Date: 3/45/06 Instrument Cal Due Date: 31 I S/O 7 From the Daily Pipe Survey Detector Control Form for the Selected Detector BackgroundValue
/%, 3 cpm MDCRStatl, l7* S CPm Efficiency Factor for Pipe Diameter MDC,tab, 763\ dpd 10- cm2 Is &he MDC,tah, acceptable?
I f 0. 0 0 06 (from detector efficiency determination)
No (ifao, adjust sample count time am? refikulate MI3?3,,) Cclmlents:
En, SURA/\-& Et32 L. I c9.M PLrSN $Pytw)J E)b 576 n Technician Signature Pipe Interior Radiological Survey
~____ ~~ ___~ -~ _____~ REFERENCECOPY Package Page 1 ofa Attachment 3, Page 1 i I BSYLVSPipeCrawler-002 Revision 4 Pipe Interior Radiological Survey Form (Continuation Form) Date: Pipe ID#: Building:
rzw Access Point Area: -.y' m&.wgt 'b Pipe Diameter:
*75 Elevation:
-27' System: L@? D PPInl Package Page & of2 Attachment 3, Page 2 
 
SECTION 7 ATTACHMENT 3 1 PAGE($)
DQA Check Sheet Answers to the following questions should be fully documented in the Survey Unit Release Record 1, Have surveys been performed in accordance with survey instructions in the Survey Design? Design # I EP Rx 1500 I Revision # 1 Original 1 Yes No NIA X EP Rx 150D 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. 4. Was the instrumentation MDC for structure scan measurements, soil scan measurements, and static measurements or soil samples addressed in the survey design? Is the instrumentation MDC for embeddedburied piping static measurements below the DCGLW ? embedd&uried piping scan measurements below the DCGLw, or, if not, was the need for additional X X X -~ ~ 5. 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?
Was the instrumentation MDC for volumetric measurements and smear analysis < 10% DCGLw ? X X 8. Were "Special Methods" for data collection properly applied for the survey unit under review? IXl'l 1. Has a posting plot been created?
I I X 2. 3. Has a histogram (or other frequency plot) been created? Have other graphical data tools been created to assist in analyzing the data? Data Analysls X X 1. Are all sample measurements below the DCGLw (Class 1 i3 2), or 0.5 DCGLw (Class 3)? 1x1 I 2. 3. If elevated areas have been identified by scans andlor sampling, is the average activity in each elevated area c DCGLEM (Class I), < DCGLW (Class 2), or ~0.5 DCGLw (Class 3)? 4. Is the result of the Elevated Measurements Test 1 .O? Is the mean of the sample data c DCGLw? X X X 5. Is the result of the statistical test (S+ for Sign Test or W, for WRS Test) 5 the critical value? X Form Rev 0 CS-0912 FSSlCharacterization Engineer (prinffsign)
FSS/ Characterization Manager (prinffsign)
Page 1 of 1 Date 7-17-07 Date 8)Nh SECTION 7 ATTACHMENT 4 1 DISC 0 COPY HL-111 Revision # Original Design # Survey Unit #(s) Page 1 of 3 Description Approval Signatures Date: 2) HL-111 is a Class 1, Group 2 survey unit as per the PBRF Final Status Survey Plan (FSSP) and Technical Basis Document (TBD)-06-004.
,.VL FSS/Characterization Engineer
: 3) Surveys in HL-111 were performed using a scintillation detector optimized to measure gamma energies representative of CO-60. Sample #EP 2-5 fiom Survey Request (SR)- 13 was referenced for this decision.
7- /a- 07 4) Survey Instructions for this survey unit are incorporated into and performed in accordance with (IAW) the Babcock Services Lncorporated (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.
: 5) Instrument efficiency determinations are developed in accordance with the BSVLVS-002, WEP 05-006, these determinations are appropriate for the types of radiation involved and the media being surveyed.
7-1 8-07 Technical Reviewer (FS S/C haracterization Engineer)
FSWChaacterization Manager I FSS Design # HL-111 I Revision # Original I ~age2of3 I Survey Unit: HL-111 I 1 .o 2.0 3.0 4.0 5.0 HistoryDescription 1.1 The subject pipe system is the 3" vent line for Canal J. The function of this pipe was to convey water f?om the 3"risers in Quad "*3" to the HD sump in Pump Room#22 on the Rx building -25fi., where the pipe is currentIy breached.
HL-111 consists of 3" diameter piping that is approximately 3 feet in length. 1.2 Survey Design Idormation 2.1 2.2 HL-111 was surveyed IAW Procedure
#BSVLVS-002.
100% of the 3" ID pipe was accessible for survey, The accessible 3" ID pipe was surveyed by static measurement at one foot increments, for a total of 3 survey measurements.
Surface area for the 3" ID piping is 730 cm2 for each foot of pi ing, corresponding to a total 3" ID piping surface area of 2,190 cm (0.2 m2) for the entire length of (approximately 3') of 3" piping. 2.3 P Survey Unit Measurement Locations/Data 3.1 Pipe interior radiological survey forms are provided in Attachment 2 of this release record.
Survey Unit InvestigationsResults 4.1 None Data Assessment Results 5.1 5.2 5.3 5.4 Data assessment results are provided in the EPBuried Pipe (BP) Survey Report provided in Attachment 1.
All measurement results are less than the Derived Concentration Guideline mredyr dose goal established in Table 3-3 of the FSSP. When implementing the Unity Rule, provided in Section 3.6.3 of the FSSP, and applying the Nuclide Fraction 0, provided in TBD-06-004, the survey unit that is constituted by HL-111 passes FSS. Background was not subtracted from the survey measurements and the Elevated Measurement Comparison (EMC) was not employed for this survey unit. re--
FSS Design # HL-111 Revision # Original 5.5 Statistical Summary Table Page 3 of 3 6.0 ~~ ~ Total Number of Survey Measurements Number of Measurements MDC Statistical Parameter 3 3 I Pipe ~ Number of Measurements Above 50% of DCGL Number of Measurements Above DCGL 0 0 Mean Median 0.0279 0.0320 ~ ~- Standard Deviation Maximum Minimum 10.0183 0.0083 0.0333 Documentation of evaluations pertaining to compliance with the unrestricted use limit of 25 medyr and dose contributions
&om 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 HL-111 to be less than 1 mredyr. The dose contribution is estimated to be 0.028 mredyr based on the average of the actual gross counts measured.
~- - ~ -- Attachments Attachment 1 - BSI EPBP Survey Report Attachment 2 - Pipe Interior Radiological Survey Form Attachment 3 - DQA Worksheet Attachment 4 -Disc containing RR for HL- 1 1 1 i? Spreadsheet SECTION 7 ATTACHMENT 1 2 PAGE(S) ce ._ BSI EWBP SURVEY REPORT Total Number of Survey Measurements Number of Measurements
>MDC Number of Measurements Above 50% DCGL Pipe ID I HL-I 11 II Survey Location I Canal J Vent 3 3 0 II Survey Date 1 iwan-06 Number of Measurements Above DCGL Mean Median Standard Deviation Maximum Minimum 23500-1 # 1 212223 0 0.0279 0.0320 0.0083 0.0333 0.0183 ___t____ll I 21 2701 -1 21 I DetectorSM
# It I Pipesize I 3 II Detector Efficiency 1 0.00013 DCGL #pnnmnai 2.41 E45 Rp-lnmP-wJw-emw 730 Field BKG 1~1 5.6 ~~ ~ OMMENTS: CTlVlTY VALUES NOT BACKGROUND CORRECTED RP Engineer I Date 7-7-07 9cpm 7 4 7.3 7 ncpm 4 7.3 7 30.769 SI154 ~- 53.846 Co40 activity 4,215 7,692 7.376 ___ ____ HL-I I1 3" Pipe TBD 06-004 Group 2 - I Cs-137 activity (dpm/100cm2) 2,186 3,989 3,825 EulS2 activity (dpm/l OOcm2) 35 64 ______ 61 1 I AglO8m activity ~~1~~ I (dpm1100crn2) 2 121 4 22 1 41 212 - 0.01 t 0.03: 0.03; 0.021 0.03; 0.001 0.03: 0.011 - - 1 of1 SECTION 7 ATTACHMENT 2 I PAGE(S) i Pipe Interior Radiological Survey Form Date: /" /'Ifdt Time: /3 lfJ- C4U4tfL Building : ?*And Elevation
/ 2s Access Point  LA- System: 7 d297 Pipe Diameter:
Area: Pipe ID Type of Survey Investigation Sled Size 3'b44( sm?&l(oeinch L - /If Characterization L>T Final Survey ## Other 4 Detector:
4.4 t Detector ID #: 31r736P- /a/ Cal Date:
flW-04 -0 5 Cal Due Date: 13-Fo\r -ad Instrument:
3 353 { Instrument ID #: aiasP.3 Cal Date: /7 - &)Od Q 5 Cal Due Date: I77faN -0 b From the Daily Pipe Survey Detector Control Form for the Selected Detector Background Value 30 6 cpm MDCRstatic 1/. 1 CPm Efficiency Factor for Pipe ~,OOOI.3 (taken from detector calibration certificate)
Qpjyeter StahC 27 79 dpdl OOcm' IS the MDCStatic
@ No (if no, adjust sample count time and recalculate MDCL6,) C&%&&?!e?
$&7& SdA 4Lf Pipe Interior Radiological Survey Radiological Survey Commenced:
Date: / - / ' 6 b Time: /3 6f- REFERENCE COPY 0 Package Page 1 of1 Attachment 3, Page 1 I I SECTION 7 ATTACHMENT 3 I PAGE(S) 
. I I I Design # HL-Ill Revision # Original Survey Unit # HL-111 Answers to the following questions should be fully documented in the Survey Unit Release Record
: 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 I and 2 survey units, or below 0.5 DCGLw for Class 3 survey units? 3. Is the instrumentation MDC for embedded/buried piping static measurements below the DCGLw ? 4. embedded/buried piping scan measurements below the DCGLW, or, if not, was the need for additional Was the instrumentation MDC for volumetric measurements and smear analysis c 10% DCGLW ? Yes X X Was the instrumentation MDC for structure scan measurements, soil scan measurements, and static measurements or soil samples addressed in the survey design? 5. 6. Were the MDCs and assumptions used to develop them appropriate for the instruments and techniques used to perform the survey3 7. Were the survey methods used to collect data proper for the types of radiation involved and for the media being surveyed?
: 8. Were 'Spedal Methods" for data collection property applied for the survey unit under review?
X X No N/A X X X Page 1 of 1 I, 2. 3. Has a posting plot been created? Has a histogram (or other frequency plot) been created? Have other graphical data tools been created to assist in analyzing the data? X X X 2. 3. If elevated areas have been identified by scans and/or sampling, is the average activity in each elevated area Is the mean of the sample data c DCGLw? DCGLEW (Class I), < DCGLw (Class 2), or 4.5 DCGLW (Class 3)? X X 4. 5. Is the result of the Elevated Measurements Test < 1 .O? Is the result of the statistical test (S+ for Sign Test or W, for WRS Test) 2 the Critical value? X X I SECTION 7 ATTACHMENT 4 1 DISC I I EP-Rx 16 1 Design # Revision # Original Page 1 of 3 Survey Unit #(s) Description Rx161 1) Embedded Pipe (EP) Survey Unit Rx161 meets the definition of embedded pipe for Plum Brook Reactor Facility (PBRF). 2) EP RX161 is a Class 1, Group 2 survey unit as per the PBRF Final Status Survey Plan (FSSP) and Technical Basis Document (TBD)-06-004.
: 3) Surveys in EP Rx161 were performed using a scintillation detector optimized to measure gamma energies representative of CO-60. Sample
#EP 2- 1 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 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 BSILVS-002, WEP 05-006, these determinations are appropriate for the types of radiation involved and the media being surveyed.
COPY Approval Signatures Form Rev 0 CS-09/1 I t FSS Design ## EP Rxl61 Revision # Original Page 2 of 3 1 .o 2.0 3.0 4.0 5.0 History/Description 1.1 EP Rx161 is a Canal E drain that terminates in Quad B. The subject piping described in this report is integral to the drain system for the Reactor Building. The piping that constitutes EP Rx 16 1 addressed in this report service floor and equipment drains on the -25 foot of the Reactor Building.
The purpose of the system is to convey waste water from the Canal E drain openings to Quad B. This system involves approximately 3 liner feet of drain system piping.
EP Rx161 consists of 3 linear feet (') of 6 inch (") bide Diameter (ID) piping starting in the
-25 foot elevation trench and running to Quad B. The total piping for EP Rx161 is 3'. 1.2 Survey Design Information 2.1 2.2 EP Rx161 was surveyed IAW Procedure
#BSI/L,VS-002.
100% of the 6" ID pipe was accessible for survey. The accessible 6" ID pipe was surveyed by static measurement at one foot increments, for a total of 3 survey measurements.
Surface area for the 6" ID piping is 1,459 cm2 for each foot of iping, corresponding to a total 6" ID piping surface area of 4,377 cm (0.4 m2) for the entire length of (3') of 6" piping.. 2.3 4 Survey Unit Measurement LocationsData 3.1 Pipe inkxior radiological survey forms are provided in Attachment 2 of this release record. Survey Unit Investigationshtesults 4.1 None Data Assessment Results ~~ ~- ___ 5.1 5.2 Data assessment results are provided in the EPBuriedPipe (BP) Survey Report provided in Attachment 1.
All measurement results are less than the Derived Concentration Guideline Level (DCGL) for radionuclide specific EP that corresponds to the 1 mrdyr dose goal established in Table 3-3 of the FSSP. When implementing the Unity Rule, provided in Section 3.6.3 of the FSSP, and applying the Cesium-l37/CobaltdO ratios, provided in TBD- 06-004, the survey unit that is constituted by EP Rxl6 1 passes FSS. Background was not subtracted from the survey measurements and the Elevated Measurement Comparison (EMC) was not employed for this survey unit.
5.3 5.4 FSS Design # EP Rx161 Revision # Original 5.5 Statistical Summary Table Page 3 of 3 Statistical Parameter I Total Number of Survey Measurements 3 Number of Measurements
>MDC Number of Measurements Above 50% of DCGL 3 0 Median Number of Measurements Above DCGL Mean I 0.002 I 0 0.002 Standard Deviation Maximum I Minimum I 0.002 0.000 0.002 6.0 7.0 Documentation of evaluations pertaining to compliance with the unrestricted use limit of 25 mredyr and dose contributions fiom 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 EP Rx161 to be less than1 mredyr. The dose contribution is estimated to be 0.002 mredyr, based on the average of the actual gross counts measured.
Attachments Attachment 2 - Pipe Interior Radiological Survey Form Attachment 3 - DQA Worksheet Attachment 4 -Disc containing RR for EP Rx 161 & Spreadsheet
~~
SECTION 7 ATTACHMENT 1 7 PAGE(S)
I Pipe ID I Rxl61 I ~~~ Survey Location 2350-1 # ~ ~ -25 RX 134738 Survey Date Survey Time 13-Jan-06 1335 ~ Detector-Sled
## LVSl -1 07 Detector Efficiency 0.002 1459 Field BKG (cpm) 20.7 Pipe Area Incorporated by Detector Efficiency (in cm2) I Total Number of Survey Measurements I 3 7- Pipe Size DCGL (dpWlOOem2)
Pipe Area Incorporated by survey ~aii tm'l Routine Survey QA Survey 6' 240,800 0.4 X Field MDCR (cpm) 18.6 Nominal MDC (dpnJtoomrZ) 333 I 7 Number of Measurements
>MDC Number of Measurements Above 50% DCGL Number of Measurements Above DCGL Mean Median I 0.002 3 0 0 0.002 Standard Deviation Maximum Minimum 0.000 0.002 0.002 Activity values are not background corrected.
COMMENTS:
Survey Unit Classification TBD 06-004 Piping Group Measured Nuclide Area FactorIEMC Used Pass/Faii FSS MREMNR Contribution
-~ ~ SR-13 Radionuclide Distribution Sample 61612007 1 2 _~__. FP 7-1 _~~__~ - co60 No Pass <1 2 3 ___ 14 15 16 ncpm Co-80 activity (total dpm) 14 15 16 __~ - 7,000 7,500 8,000 EP Rx161 TBD 06-004 Group 2 (d C7*ih lOOcm2) 1 480 3 Cs-137 activity (dpmll00cm2)
Eu-162 actMty (dpm1100an2)
Eu-1 S4 acthrity (dpm110Ocm2)
Nb-04 activity (dpmHOOcm2) 249 267 285 ______ 4 - 3 4 5 _____.. 3 3 - 0 0 0 Ag-l08m activity (dpmll OOcm2) 0.002 MEDIAN- 0.002 0.00: 0.009 - 1of1 SECTION 7 ATTACHMENT 2 2 PAGE(S) 1 Position Feet into Pipe Count Time - 1 1 I 2 3 I 3 .3 1 4 nl& nl a 5 I ~~ # from Opening (min) I 6 7 8 I 9 10 J L Pipe Interior Radiological Survey Form +. Date: i-I3-& Time: 13)- Building:
Q-f Elevation - 2)- Access Point &q@Al-- IG Q-% /I$/ System: ,&iik'.&&W9da& Pipe Diameter:
fn f( Area: Pipe ID Type of Survey Investigation Characterization Final Survey ## Other Sled Size hff p/07 inch Cal Date: fL-/ 7- or Cal Due Date: /L-t 7 Detector:
d/ffZOAl /m&-/ Detector ID #: /- \IS 1 707 Instrument:
7,3J-V-- / Instrument ID #: rW7n3 Cal Date: 12-1 7 Cal Due Date: &-f 7- 0 E. fi &QS %p-p __~~--- woss CPm CPm Counts - dpdl OOcm' I /Y /Y nle, a/@ fG 16 Id- / >- fl kw nb I I I I I I 1 JI 4 From the Daily Pipe Survey Detector Control Form for the Selected Detector Background Value do a 7 cpm MDCRstabc
/QIt cpm Efficiency Factor for Pipe meter statlc c~U dpm/100crn2 r.- . 0 0 oz (taken from detector Is the MDCShhc a No (dno, adjust sample count tune and recalculate MDCL,,) as q c&%Efitble?
&7&(- s I a ssp / C~rMPI-C,--c
/ Pipe Interior Radiological Survey Radiological Survey Commenced:
Date: 1 -I3 ab Time. - /33J--- REFERENCECOPY 0 Package Page 1 of[ Attachment 3, Page 1 
 
SECTION 7 ATTACHMENT 3 PAGE(S)
I I ~~ Survey Unit # DQA Check Sheet ~ ~ EP Rx161 Design # 1 EP Rx161 I Revision # 1 Original I Answers to the following questions should be fully documented in the Survey Unit Release Record
: 1. Have surveys been performed in accordance with survey inshuctions in the Survey Design?
Yes No NIA X I 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. 4. Is the instrumentation MDC for embeddedhuried piping static measurements below the DCGLW ? Was the instrumentation MDC for structure scan measurements, soil scan measurements, and embeddedhuried piping scan measurements below the DCGLW, or, if not, was the need for additional static measurements or soil samples addressed in the survey design? Ix X 5. 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? Was the instrumentation MDC for volumetric measurements and smear analysis
< 10% DCGLW ? 8. Were 'Special Methods" for data collection properly applied for the survey unit under review?
X X X IxI 9. Is the data set comprised of qualified measurement results collected in accordance with the survey design, which accurately reflects the radiological status of the facility? ~~ ~ 1. 2. Has a posting plot been created? Has a histogram (or other frequency plot) been created? Graphical Data Review X X 2. 3. 4. Is the mean of the sample data
< DCGLw? If elevated areas have been identied by scans andlor sampling, is the average activity in each elevated area < DCGk (Class I), c DCGLw (Class Z), or 6.5 DCGLw (Class 3)? Is the result of the Elevated Measurements Test 1 .O? 3. Have other graphical data tools been created to assist in analyzing the data? I I lx X X X Data Analysis - - ____- -. 1. Are all sample measurements below the DCGLw (Class 1 & 2), or 0.5 DCGLw (Class 3)? 1x ~ ____ ~~ ~~ ~~ 5. Is the result of the statistical test (S+ for Sign Test or W, for WRS Test) 2 the critical value? X FSS/Characterization Engineer (prinUsign)
D4/e8w&&$(4&&
XdL4 Date 3. Case Date 6-06-07 5//3107 FSS/ Characterization Manager (printlsign)
I X/IY/Wk I Form CS-09/2 Rev 0 Page 1 of 1 SECTION 7 ATTACHMENT 4 1 DISC}}

Latest revision as of 21:35, 14 January 2025

Nasa Plum Brook Reactor, Embedded Pipe Survey Records
ML072851270
Person / Time
Site: Plum Brook  File:National Aeronautics and Space Administration icon.png
Issue date: 08/16/2007
From: Peecook K
US National Aeronautics & Space Admin (NASA), John H. Glenn Research Ctr at Lewis Field
To: Snell W
NRC/RGN-III/DNMS/DB
References
Download: ML072851270 (256)
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