ML081270683

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Survey Unit Release Record EP-PPH 108
ML081270683
Person / Time
Site: Plum Brook
Issue date: 05/01/2008
From:
US National Aeronautics & Space Admin (NASA), John H. Glenn Research Ctr at Lewis Field
To:
NRC/RGN-III/DNMS/DB
References
EP-PPH 108
Download: ML081270683 (49)
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  • Survey Unit Release Record Design # EP-PPH 108 I Revision # I Original Page 1 of 3 Survey Unit #(s) PPH 108 Description
1) Portions of Embedded Pipe (EP) Survey Unit PPH 108 that remain embedded in the building foundation walls meet the defmition of embedded pipe for Plum Brook Reactor Facility (PBRF). The portion of piping which transits in soil under and between the buildings does not meet the criteria for embedded piping. Upon demonstration of compliance with the release criteria, the complete piping system will be grouted, including the portions embedded in the building structure that will remain embedded for any future reuse and those portions in the ground that can be released for unrestricted use. 2) EP PPH 108 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) A core bore was performed to remove a section of this pipe system to facilitate access for remediation and survey. Underlying soils were exposed by this activity.

Isotopic analysis of soil samples taken after the completion of these activities indicate residual radioactivity at concentrations well below the release criteria.

4) Surveys in EP PPH 108 were performed using a scintillation detector optimized to measure gamma energies representative of C0 60. Sample#EP 3-7 from Survey Request (SR)-13 was referenced for this decision.
5) Survey Instructions for this survey unit are incorporated into and performed in accordance with (IA W) the Babcock Services Incorporated (BSI)/L VS-002, Work Execution Package (WEP) 05-006. Survey instructions described in this document constitute "Special Methods" and the survey design used in the acquisition of survey measurements.
6) 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.

Approval Signatures Date: Form CS-09/1 Rev 0 FSS/Characterization Engineer Technical Reviewer (FSS/Characterization Engineer) DWojtkowiak 04/07/08-L/ /> 4-/1-08 FSS/Characterization Manager -FSS Design # EP PPH 108 I Revision # Page 2 of3 I Survey Unit: PPH 108 HistoryfDescription The subject pipe is a 4, 6 and 8" vent line from PPH Room 1, PPH Room 3, PPH Room 4, PPH Room 5 and PPH Room 6 to the sump located in PPHRoom 8. EP PPH 108 consists of 4, 6 and 8" diameter piping that is approximately 1 71 feet in length. Survey Design Information EP PPH 108 was surveyed lAW Procedure

  1. BSlIL VS-002. 100% of the 4" pipe was accessible for survey. The accessible 4" pipe was surveyed by static measurement at one foot increments, for a total of 109 survey measurements. Surface area for the 4" piping is 973 cm 2 for each foot of piping, corresponding to a total 4" piping surface area of 106,057 cm 2 (10.61 m 2) for the entire length of (approximately 109') of 4" piping. 100% of the 6" pipe was accessible for survey. The accessible 6" pipe was surveyed by static measurement at one foot increments, for a total of 15 survey measurements. Surface area for the 6" piping is 1,459 cm 2 for each foot of piping, corresponding to a total 6" piping surface area of 21 ,885 cm 2 (2.19 m 2) for the entire length of (approximately 15') of 6" piping. 100% of the 8" pipe was accessible for survey. The accessible 8" pipe was surveyed by static measurement at one foot increments, for a total of 47 survey measurements. Surface area for the 8" piping is 1,946 cm 2 for each foot of piping, corresponding to a total 8" piping surface area of 91 ,462 cm 2 (9.15 m 2) for the entire length of (approximately 15') of8" piping. Survey Unit Measurement LocationsfData Pipe interior radiological survey forms are provided in Attachment 2 of this release record. Survey Unit InvestigationslResults None Data Assessment Results Data assessment results are provided in the EPlBuried Pipe (BP) Survey Report provided in Attachment
1. This survey unit was assessed as a building re-use scenario with all activity derived dose as a 100% C0 60 nuclide distribution.

This is the most conservative DCGL for the facility (11,000 dpm/l OOcm\ FSS Design # EP PPH 108 I Revision # Page 3 of3 I Survey Unit: PPH 108 No individual measurement observed in EP PPH 108 exceeded the Unity Rule as provided in Section 3.6.3 of the FSSP. No Elevated Measurement Comparisons (EMC) was required or perfonned. The survey unit that is constituted by EP PPH 108 passes FSS. Mean unity for this survey unit was 0.369 of unity. 5 DCGL's for the building reuse scenario are used to demonstrate compliance with the release criterion for this release record. The DCGL's for embedded pipe are not applied. No area factors were used for this survey unit. Background was not subtracted from the survey measurements. Statistical Summary Table Statistical Parameter 4" Pipe 6" Pipe 8" Pipe Total Number of Survey Measurements 109 15 47 Number of Measurements >MDC 98 1 1 Number of Measurements Above 50% of DCGL 32 1 1 Number of Measurements Above DCGL 0 0 0 Mean 00424 0.314 00460 Median 00407 0.281 00491 Standard Deviation 0.133 0.110 0.131 Maximum 0.791 0.563 0.607 Minimum 0.140 0.161 0.140 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. A review of the survey results has shown that the dose contribution for EP PPH 108 to be less than 25 mrem/yr. The dose contribution is estimated to be 9.24 mrem/yr based on the average of the actual gross counts measured. Attachments Attachment 1 -BSI EP/BP Survey Attachment 2 -Pipe Interior Radiological Survey Attachment 3 -Soil Sample -DQA -EP PPH 108 Spreadsheet

  • SECTION ATTACHMENT 7

-.. * ----BSI EP/BP SURVEY PPH Pipe Survey Location PPH Rms 1, 3, 4, 5, 6&8 315108, 3I6Ill8 189094 2350-1 #Survey Date 312oW8. 3125/1l6, J/31/!J8 Nal detector Oetector-Sled

  1. See Survey Sheets Survey Time #238369 Pipe Size 4",6"& 8" Detector Efficiency 000031 000039 0.00029 0.0002 ,.,.

bY Oelador ElIIchoncy (In DCGL (",","D0cm21 110E+04 em:Q Pfpe An. by 21.9 Field BKG Ccpml 3.4 3.4 3.5 s..v""O.Ulm'l Routine Survey 15.3 Field MDCR ''' QASurvey NominaJ MOC '",","lIIIanll 2,372 1.990 7,862 Survey Measurement Total Number of Survey Number of Measurements >MDC Number of Measurements Above 50% DCGL Number of Measurements Above DCGL 0 0 0 0 Mean 0.421 0.314 0254 0.460 Median 0.407 0.281 0.242 0.491 Standard Deviation 0133 0110 0094 0.131 MaXimum 0791 0.563 0.532 0607 Minimum 0.168 0.161 0.097 0140 Russell Phelps Survey Technician(s) Survey Unit Classification TBD 06-004 Piping Group SR-13 Radionuclide Distribution Sample EP Measured Co-60 Area Factor/EMC Used No PasslFail FSS Pass MREMIYR Contribution <25 ACTIVITY VALUES NOT BACKGROUND O. Wojtkowiak -4/912008 RP Engineer I Date I'

  • PPH 4, 6 8" TBD 06-004 Group =It:.. l: Q) E Q) gcpm... ::2 111 ftI Q) 1 8 2 12 3 14 47 5 13 6 23 7 14 8 12 99 10 19 11 32 12 12 ncpm -, 8 12 14 7 13 23 14 12 9 19 32 12 Co-50 activity (total dpm) 20,513 30,769 35,897 17,949 33,333 58,974 35,897 30,769 23,077 48,718 82,051 30769 ! I I Co-50 .otMty J (dpm/100cm2) 2,108 3,162 3,689 1,845 3,426 6,061 3,689 3,162 2,372 5,007 8,433 3,162 I Unity I 0.192 0.287 0.335 0.168 0.311 0.551 0.335 0.287 0.216 0.455 0.767 0.287 ." ." ::I: ::0 I 1 of 6
  • PPH 4,6 8" TBD 06-004 Group I t: ClI E activity Co-GO activity gcpm ncpm Unity (total dpm) (dpm/100cm2)
J III III ClI :::E I 13 18 18 46,154 4,743 0.431 14 26 26 66,667 6,852 0.623 15 33 33 84,615 8,696 0.791 16 20 20 51,282 5,271 0.479 17 29 29 74,359 7,642 0.695 18 15 15 38,462 3,953 0.359 19 27 27 69,231 7,115 0.647 20 13 13 33,333 3,426 0.311 21 25 25 64,103 6,588 0.599 22 21 21 53,846 5,534 0.503 23 21 21 53,846 5,534 0.503 24 14 14 35,897 3,689 0.335 25 18 18 46,154 4,743 0.431 26 29 29 74,359 7,642 0.695 27 10 10 25,641 2,635 0.240 "tJ 28 17 17 43,590 4,480 0.407 "tJ 29 20 20 51,282 5,271 0.479 30 25 25 64,103 6,588 <31 13 13 33,333 3,426 0.311 :;0 32 14 14 35,897 3,689 0.335 33 19 19 48,718 5,007 0.455 N 34 14 14 35,897 3,689 0.335 W 35 26 26 66,667 6,852 36 24 24 61,538 6,325 37 19 19 48,718 5,007 38 17 17 43,590 4,480 39 19 19 48,718 5,007 40 17 17 43,590 4,480 41 23 23 58,974 6,061 42 20 20 51,282 5,271 43 22 22 56,410 5,798 44 22 22 56,410 5,798 45 20 20 51,282 5,271 46 20 20 51,282 5,271 47 21 21 53,846 5,534 48 12 12 30,769 3,162 49 29 29 74,359 7,642 50 22 22 56,410 5,798 51 11 11 28,205 2,899 0.264 PPH-VR1 Drop 52 18 18 46,154 4,743 0.431 2of6
  • PPH 4,68 11 TBD 06*004 Group :rt c: -Q) E Q) gcpm... ::::s ::!: Q) I 53 54 55 56 57 58 59 60 61 62 63 64 65 66 67 68 69 70 71 72 73 74 75 76 77 78 79 80 81 82 83 84 85 86 87 88 89 90 91 92 93 94 95 j co-<o .cd.", ncpm (total dpm) 11 28,205 2,899 0.264 7 17,949 1,845 0.168 16 41,026 4,216 0.383 17 43,590 4,480 0.407 13 33,333 3,426 0.311 16 41,026 4,216 0.383 15 38,462 3,953 0.359 "tJ 15 38,462 3,953 0.359 "tJ 20 51,282 5,271 0.479 ::I: 13 33,333 3,426 17 43,590 4,480 0.407 ::0 11 28,205 2,899 0.264 en 13 33,333 3,426 16 41,026 4,216 13 33,333 3,426 13 33,333 3,426 18 46,154 4,743 28 71,795 7,379 13 33,333 3,426 17 43,590 4,480 16 41,026 4,216 18 46,154 4,743 14 35,897 3,689 20 51,282 5,271 13 33,333 3,426 19 48,718 5,007 16 41,026 4,216 12 30,769 3,162 15 38,462 3,953 0.359 14 35,897 3,689 0.335 ::I: 23 58,974 6,061 25 64,103 6,588 < 14 35,897 3,689 0.335 ::0 17 43,590 4,480 0.407 10 25,641 2,635 22 56,410 5,798 21 53,846 5,534 16 41,026 4,216 16 41,026 4,216 23 58,974 6,061, 15 38,462 3,953 11 28,205 2,899 12 30,769 3,162 Co-60 activity Unity (dpm/100cm2)

I I 30f6 I

  • PPH 4, 6 8" TSD 06-004 Group ,.., ....c: QI E QI... :;, :e QI

gcpm ncpm Co-60 activity (total dpm) 35,000 15,000 40,000 40,000 45,000 65,000 50,000 55,000 65,000 55,000 65,000 45,000 60,000 55,000 45,161 38,710 25,806 38,710 64,516 45,161 70,968 54,839 64,516 29,032 90,323 64,516 38,710 45,161 38,710 Co-50 activity (dpmI100cm2) 3,597 1,542 4,111 4,111 4,625 6,680 5,139 5,653 6,680 5,653 6,680 4,625 6,166 5,653 3,095 2,653 1,769 2,653 4,422 3,095 4,864 3,759 4,422 1,990 6,191 4,422 2,653 3,095 2,653 Unity 0.327 0.140 0.374 0.374 0.420 0.607 0.467 0.514 0.607 0.514 0.607 0.420 0.561 0.514 0.281 0.241 0.161 0.241 0.402 0.281 0.442 0.342 0.402 0.181 0.563 0.402 0.241 0.281 0.241 "'0 "'0 :c <:::0 00 4of6

  • PPH 4, 6 8" TSD 06-004 Group ... c Q) E Co-50 activity Co-GO activity Q) gcpm ncpm Unity... (total dpm) (dpm/100cm2):e Q)125 17 17 58,621 3,012 "tJ 126 13 13 44,828 2,304 0.209 127 10 10 34,483 1,772 0.161 128 18 18 62,069 3,190 <129 10 10 34,483 1,772 0.161 130 24 24 82,759 4,253 0.387 131 12 12 41,379 2,126 0.193 132 6 6 20,690 1,063 133 15 15 51,724 2,658 134 26 26 89,655 4,607 135 29 29 100,000 5,139 136 18 18 62,069 3,190 137 24 24 82,759 4,253 138 27 27 93,103 4,784 139 14 14 48,27-5 2,481 140 12 12 41,379 2,126 141 20 20 68,966 3,544 142 10 10 34,483 1,772 143 17 17 58,621 3,012 "tJ 144 12 12 41,379 2,126 "lJ 145 9 9 31,034 1,595 146 33 33 113,793 5,848 147 12 12 41,379 2,126 0.193 ;0148 19 19 65,517 3,367 149 20 20 68,966 3,544 0.322 150 11 11 37,931 1,949 151 18 18 62,069 3,190 152 13 13 44,828 2,304 153 19 19 65,517 3,367 154 13 13 44,828 2,304 155 13 13 44,828 2,304 156 12 12 41,379 2,126 157 16 16 55,172 2,835 158 20 20 68,966 3,544 159 16 16 55,172 2,835 160 15 15 51,724 2,658 161 14 14 48,276 2,481 5 af6
  • * --PPH 4, 6 8" TBD 06-004 Group :u:... I E Co-60 activity Co-50 activity G> gcpm ncpm... (total dpm) (dpm/100cm2)
I G> L.. 162 15 15 51,724 2,658 163 17 17 58,621 3,012 164 8 8 27,586 1,418 "lJ 165 11 11 37,931 1,949 0.177 J: 166 16 16 55,172 2,835 0.258 167 18 18 62,069 3,190 0290 < 168 9 9 31,034 1,595 0.145 .a=. 169 22 22 75,862 3,898 0_354 I N 170 8 8 27,586 1,418 0_129 171 11 11 37,931 1,949 0.177 Unity 0.242 0274 0_129 "lJ 6of6
  • I I: SECTION 7 ATTACHMENT 2 27 PAGES

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  • BSIIL VSPipeCrawler-002 Revision 5 Pipe Interior Radiological Survey Form .Building:

Date: 3';lJ1'of Time: Pipe ID#: PPH V R/ Pipe Diameter: E evation: Type of Survey Gross Co60 / Detector ID# I Sled ID# __ --,-,--(__1__ _ Detector Cal Date: /. d '):0 f Detector Cal Due Instniment: j{Y-L s-() I Instrument ID Instrument Cal Date: (0 .':Pr. 0 7 Instrument Cal Due 16 --'--"---------- From the Daily Pipe Survey Detector Control Form for the Selected Detector Background Value 3.t.j cpm MDCR static cr cpm Efficiency Factor for Pipe Diameter' O.ooooq_ (from detector efficiency determination) G 2:MDCstatic 1 Z, dprn/ I 00 cm Is the MDCstatic acceptable? No (if no, adjust sample count time and recalculate MDCRstalic) Comments: Technician Signature Pipe Interior Radiological Survey Position Feet into Pipe Count Time Gross Counts Gross Net dprn/100cm 2 # from Opening (min) cpm cpm 1 / I g 8 / 2 ::z / /) / 3 3 I 1t1 It( / 4 Jj / 7 7 / 5 s /3 I r< AI /}, 6 6 .)..> V"/ / J . 7 7 \ 1£.1 ) v, / 8 r \ 1.1.. / 9 1 \ q 9 / 10 ( () v )q Ie{ / Package Page 1 REFERENCE COpy Attachment 3, Page 1 BSIILVSPipeCrawler-002 Revision 5 '. Pipe Interior Radiological Survey Form (Continuation Form) Date: Pipe ID#: Building: Pipe Diameter: __.1_1_1 ' Access Point Area: fPH R f'1'1. 1{ Elevation: 0 System: l[g * .... % Position # Feet into Pipe from Opening Count Time (min) Gross Counts Gross cpm* Net cpm dpm/lOOcm 2 I ( ]( I .3J. / ,ef-. I Id... II /// / / / /// //// // ,;11 / vfr / / / /1/// // / ///// / / / Package Page d-. of::::J Attaclunent 3, Page 2 i ,:'; '. ..... ...* .", . __***_*k*" .' CO\J'T'>JU""l"otJ s .. 

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  • BSIIL VSPipeCrawler-002 Revision 5 Pipe Interior Radiological Survey Form Date: .:s .,£)-OX' Time: ( I Pipe ID#: ee HI,) (( I-j -

Diameter: __Jl-,--" Access Point Area: ffJlf RM 3 Building: ee H . Elevation: 0 System: Other V 101 Detector Cal Date: . {. J 5" -0 t' Detector Cal Due Instniment: a 3> 5-0 -( Instrument ill Instrument Cal Date: (. <h S'. 0 r Instrument Cal Due From the Daily Pipe Survey Detector Control Form for the Selected Detector Background Value 3 ,v( cpm M.-DCRstatic try cpm EfficiencyFactorfor Pipe Diameter . O. f) 00<31 (from detector efficiency determination) MDCstatic 'Z.3 . I {jC) crtl Is the MDCstatic acceptable? 0es..) No (If no, adjust sample count tIme and recalculate MDCR,tatic) Comments; s+q riel SGt. rue-r ct.! v I( -3 we VL1--C{ U f" ( Wet 7 10 (/f?, J r;v1.cz r) Lf I, I Technician Signature Pipe Interior Radiological Survey Position Feet into Pipe Count Time Gross Counts Gross Net dpm/lOOcm 2 # from Opening (min) cpm cpm 1 I , 18 lR / 2 / / 3 3 I ") 33 / 4 L-f / ;)..C'J -'--0 / 5 ,20 ;V 6 6 \ I / 7 7 '\ <17 ..)l / 8 X' /3 I 3 / 9 q J..!) / 10 10 J-I .2/ V Package Page 1 of 3 REFERENCE COpy Attachment 3, Page 1 1JltJcoc/( INc.:.

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  • BSIIL VSPipeCrawler-002 Revision 5 Pipe Interior Radiological Survey Fonh (Continuation Form) Date: Pipe ID#: Building: I .. 5 AS I Do PH V{( /-2* Pipe Diameter:

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  • BSIILVSPipeCrawler-002 Revision 5 . Pipe Interior Radiological Survey Form* Date: 3 .(, -()g Tillie: -----<-/J{-,,--=--I q=---__ Pipe ID#: 11 g LD..L.>tc2'-Ff--Pipe Diameter:

__ Access Point Area: fM-::e_. __ Building: ef fI Elevation: V System: Type of Survey Investigation Characterization Final Survey 2{ Other /' Gross Co60 Cs* __----..:........:0..-.-'---,-Detector ID# / Sled ID# L / 101 Detector Cal Date: ( J ').0 g Instnunent: d,5,5"(l ( Instrument Cal Date: I* olS' 0 f From the Daily Pipe Survey Detector Control Form for the Selected Detector Background Value :3. 6 cpm MDCRstatic q cpm Efficiency Factor for Pipe Diameter ()

  • 0 00 :3 q (from detector efficienCY determination) 2 MDCstatic "2 ?;t-z..-dpm/ / f:J"O *cm Is the MDCstauc acceptable? No (if no, adjust sample count time and recalculate MDCRstatic)

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  • BSIILVSPipeCrawler-002 Revision 6 Pipe Interior Radiological Survey Form Date: 3* S /-or Time: /33l.. .1-J If Pipe ID#: PfH Pipe Diameter:

__----'-____ Access Point Area: Pf II gfYl b Building: £P if Elevation: f) System: Ve"l t <<,'seR.. Type of Survey Investigation Characterization Final Survey ;<) Other ,/ Gross Co60 ./ Cs Detector ID# I Sled ID# J VS [ I ----'---1-,---, _ Detector Cal Date: I .d..')' 0 g' Detector Cal Due Date: (' J ), CJ '1 Instrument: -.5 -() -f Instrument ID #: a () 3)-/ 3 g-Instrument Cal Date: .L-1-",-O_*-'.-1-=-6_' (=--'7--'----- _ Instrument Cal Due Date: -.L-1-'<-O_-_I--=6_'---'O=------=--! _ From the Daily Pipe Survey Detector Control Form for the Selected Detector Background Value 3, J.. cpm MDCR static C/ cpm Efficiency Factor for Pipe Diameter D . DOD 39 (from detector efficiency determination) 2 MDCstatic -z. 3 7 Z-dprn/ / [)c;> Is the MDCstatic acceptable? (if no, adjust sample count time and recalculate 6J No Comments: Oe c 1f. II "==::: Technician Signature A-f 4!pA Pipe Interior Radiological Survey Position Feet into Pipe Count Time Gross Counts Gross Net dprn/l00cm 2 # from Opening (min) cpm. cpm 1 , I[ ,I / 2 1. I 7 1 / 3 3 ( I b I h / 4 ).} \ /1 17 / 5 S 13 13 At 6 b } I b I b / 7 ....., / 8 { 15 1/ 9 ( ,)0 / 10 10 13 / Package Page 1 of REFERENCE COpy Attachment 3, Page 1

  • BSVLVSPipeCrawler-002 Revision 6 Pipe Interior Radiological Survey Form (Continuation Form) Date: .3 -3 I 0 f JJ II Pipe ID#: PfH VB. -6 Pipe Diameter:

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  • BSI/L VSPipeCrawler-002 Revision 5 Pipe Interior Radiological Survey Form Date: 3, d J--f. Q8 Time: i 0 '3 7 Pipe ID#: ppll \f R-g' Pipe Diameter:

__ __ Access Point Area: fPI1 R f M _, .. System: lIe"+ oD:.: Type of Survey Investigation Characterization __ Final Survey ;<) Other " Gross Co60 / CsDetector ID# / Sled ID# L 1/ 5-(/ 1-)OlL.-.L/_----'--Detector Cal Date: ....!-I--,* _ Detector Cal Due Instrument: d 3 5"0 -(Instrument ID Instrument Cal Date: f D-Ih -() 7 Instrument Cal Due Date: /0-If'of , From the Daily Pipe Survey Detector Control Form for the Selected Detector Background Value . 1-( cpm MDCRstatic q cpm Efficiency Factor for Pipe Diameter' (). 0 00 a9 (from detector efficiency determination) MDCstatic -z,37Z / t:::5D cm 2 Is the MDC static acceptable? No (lfno, adjust sample count hme and recalculate Comments: SiC1 fie d s (;,,," u e y' 1\.5 £fQ VI1 50-t1t1, ,() ; Technician Signature MA. f4 A Pipe Interior Radiological Survey Position Feet into Pipe Count Time Gross Counts Gross Net dprn/100cm 2 # from Opening (min) cpm cpm 1 ! Ir / 2 ( I b I fo / 3 3 / 18 fC{ / 4 J1 Iii J / 5 S ctD dO )} /A 6 b \ I 3 / 7 I \ {q } '1 / 8 2 \ I 6 I 0 / 9 1 I / 10 10 W' /S 15' '// Package Page 1 ofREFERENCE COpy Attachment 3, Page 1 fiicocJ(:ERVICES INC.

  • BSIJL Revision 5 Pipe Interior Radiological Survey Form (Continuation Form) Date: If Pipe ID#:

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  • BSIIL VSPipeCrawler-002 Revision 4 Pipe Interior Radiological Survey Form Date: <g/I+-/OG Time: Pipe ID#:

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  • BSI/L VSPipeCrawler-002 Revision 4 Pipe Interior Radiological Survey Form (Continuation Form) Date: '8/U /.0 5 " Pipe ID#:

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  • *--BSIJL VSPipeCrawler-002 Revision 5 Pipe Interior Radiological Survey Form Date::3 . (), 0 8 Titne:I,{£O 0 r Dp' / f . 5( j Pipe ID#: -L ./I VR &- Pipe Diameter:

Access Point Area: . r. 5; e o£l(M ( Building: ffff Elevation: 1 System: V(At Type of Survey Investigation Characterization Final Survey Other ./' Gross Co60 / Cs' Detector ID# I Sled ID# J-LJ,5' I I { 0( Detector Cal Date: I .J. s* a B: Detector Cal Due Date: J .).. r* 0 f Instrument: Instrument ID #: a 03 if37 Instrument Cal Date: .....:./...::.{)_*_t..><.G_* O:-...L2 Instrument Cal Due Date: I (). 1&' 0 ? From the Daily Pipe Survey Detector Control Form for the Selected Detector Background Value 3* If cpm :NIDCRstatic 1 cpm Efficiency Factor for Pipe Diameter 0.00031 (from detector efficiency determination) MDCstatic I tt 0 dprn/ l f1C) cm 2 Is the MDCstatic acceptable? No (ifno, adjust sample count time and recalculate NIDCR;t.tic) S ("q" [JeL/ (rOw. QCA-f slie (}f /(fY] Cl ' I Technician Signature Pipe Interior Radiological Survey Position Feet into Pipe Count Time Gross Counts Gross Net dprn/l00cm 2 # from Opening (min) cpm cnm 1 I j. p.( Ilf / 2 J. I I). / 3 j / I( / 4 .'-{ Id. IJ.. / 5 S dO II VA 6 b \ ( J-j /1 1/ rr 7 7 \ d..d / 8 /7 f I / 9 \// dO ;lO / 10 (0 '\/ q 4 V Package Page 1 of 3 II A NCE COpy Attachment 3, Page 1

  • *BSI/L VSPipeCrawler-OO2 Revision 5 Pipe Interior Radiological Survey (Continuation Form) Date: 3'dO'G? / If . ()Ct.f.s;Je Pipe ID#: pp It vRB-\* . Pipe Diameter:

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  • BSVL VSPipeCrawler-002 Revision 5 Pipe Interior Radiological Survey Form Date: 3*cl v ( 07 Time: Pipe ID#: V R t-(-.2 Pipe DIameter:

8 (' Access Point Area: fJ P If J'I1 Building: .pel-{ Elevation: 0 System: _ Type of Survey Investigation Characterization __ Final Survey Other Gross Co60 Cs Detector ID# / Sled ID# J-_U-'--S_---'--(__ / __ _ Detector Cal Date: ( 'J-S' '0 f Detector.Cal Due Date: I .J... 5" () 'i' Instrument: . d-:5 S Q-r Instrument ill #: :J 0 3 '13 r Instrument Cal Date: --,-1-=D_'_I_b_' _0_1____ Instrument Cal Due Date: -----'-I_o_*---'-I_{_,_o---'y<-- _ From the Daily Pipe Survey Detector Control Form for the Selected Background Value if MDCRstatic 9 Efficiency Factor for Pipe Diameter . o,ooo;;;q (from detector efficiency determination) 16 . dpml tJ79 Is the MDCstatic acceptable? No (ifno, adjust sample count time and recalculate Comments: VOlA -f.,. (\ vi.. FrOM U f< t+ J... 0 (rJtf) SO /q§ Ala r i6 {ta""! 0<' ;"5 AJ. 3 I 6 {' F/pe h) l( t-( I ,5 £f'(I Pipe Interior Radiological Survey Position # Feet into Pipe from Opening Count Time (min) Gross Counts Gross cpm Net cpm dpmllOOcm 2 1 I I 17 17 /// 2 .2. I r.3 I S 3 3 I 10 1O 4 vi { (:1 I\{ /5 S ) f.O ,0 jI./6 6 I ;)11 / 7 7 I (-) }J / 8 / 9 / 10 V REFERENCE COpy Package Page 1 of Attachment 3, Page 1 S&RVJCES INC.

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  • BSIJLVSPipeCrawler-002 Revision 5 Pipe Interior Radiological Survey Form Gross Co60 / Detector ID# / Sled ID# J-V 5 -I /Detector Cal Date: I.J" S' Detector Cal Due Instrument:
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  • BSVLVSPipeCrawler-002 Revision 5 Pipe Interior Radiological Survey Form (Continuation Form) Date: 3* 6-0 (f.f Pipe ID#: _VL.-'.L-lB.......4c---=<6-'-__

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Pipe Diameter: ---:5::.3 Access Point Area: f RfV1'(L-Building: PPH . Elevation: O_.__ lIB.. Type of Survey Investigation Characterization Final Survey Other Gross Co60 /'. Cs Detector ID# / Sled ID# ,L U5-/ / 10 I--_............... Detector Cal Date: /. ). 5' '6 r Detector Cal Due Date: O=-.-q _ Instniment: '3 5' c2 I Instrument ID #: dO:) C{ .s % Instrument Cal Date: J ()-((. 0 7 Instrument Cal Due Date: I 0. I {. 0 r From the Daily Pipe Survey Detector Control Form for the Selected Detector Background Value I V. I cpm 11DCR stat ic 2-2.1. . cpm Efficiency Factor for Pipe Diameter (j. Ooo?-'1 (from detector efficiency determination) 2 11DC stat ic /6'1,5 dprn/ __ Is the MDC static acceptable? c:Y;) No (if no, adjust sample count time and recalculate Comments: Co 01 ;¥ItA Fr 0 VVl h 0 (' '--fI a fe.5 Teclmician Signature Pipe Interior Radiological Survey Position # Feet into Pipe from Opening Count Time (min) Gross Counts Gross cpm Net cpm dprn/lOOcm 2 I I I /5 15 // // 2 / /7 J7 3 3 / )( g I { 4 '1 / I 5 5 I Ib I (, Al va 6 b \ l Y' )t /' / 7 7 \ G //8 ;s \ 21 J). 9 q L 0 /V 10 (0 r I I I REFERENCE COpy Package Page 1 of .=2-. Attachment 3, Page 1 SeRVICES iNC. ... 

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  • SECTION ATTACHMENT 6
  • 1 PB08-01217 ORTEC g v -i (1087) npp32 G53w3.05 07-APR-2008 17:21:00 page PBRF spectrum name: PB08-01217.An1 sample description PB08-01217; SR99-36; PPH RM 4; VR4-2; 4/7/08 Spectrum Filename:

Z:\Lab\SAMPLE 08\PB08-01217.An1 Acquisition information Start time: Live time: Real time: Dead time: Detector ID: Detector system#3 DETECTOR (#131) Calibration Filename: 07-Apr-2008 17:15:16 300 301 ro 250ml #73678-773 (MC131) Sept07 Energy calibration Created: zero offset: Gain: Quadrati c: Efficiency Calibration Created: Type: uncertainty: coefficients: Library Main analysis Library Match peak Analysis parameters Analysis Start Stop Peak rejection peak search sample Activity scaling Detection limit Random systematic Fraction Background o 05-Sep-2007 16:56:38 0.565 kev 0.247 kev/channel 5.022E-08 kev/channel A 2 05-Sep-2007 17:17:39 polynomial 1.204 % -0.304311 -4.249899 -0.094002 0.005803 pl umbrk 01.1 i b Library npp32 155 ( 38.83kev 8144 ( 2014.22kev) 25.000% 3 4. 3150E+02 1.0000E+06/( 1.0000E+00* 4.3150E+02) 2.3175E+03 Nureg 4.16 1.0000000E+00 1.0000000E+00 '0.000% best method (based on spectrum). Page 1

  • PB08-01217 PBRF ORTEC g v -i (1087) npp32 G53w3.05 07-APR-2008 17:21:00 Page spectrum name: PB08-01217.An1 2 Half lives decay limit: Activity range factor: Min. step backg. energy 12.000 2.000 0.000 Corrections Status Comments Decay correct to date: YES 02-Apr-2008 13:39:00 Decay during acquisition:

NO Decay during collection: NO True coincidence correction: NO Peaked background correction: NO Absorption (Internal): NO Geometry correction: NO Random summing: NO Energy Normalized diff: of:*"!r******* SU MMARY 0 F PEAKS I N RAN GE Peak Area Uncert FWHM Corrctn Nuclide Brnch. Act. Nuc Energy Factor Energy Ratio pci/g 186.39 46. 23.06 1. 94 7.184E-02 185.71 57.200 PBC<MDA u235 186.21 3.590 3.684E+00 RAn6 238.67 68. 15.63 0.48 6.195E-02 238.63 43.300 5.253E-01 PB212 295.46 42. 20.20 0.69 5.271E-02 352.08 50. 15.24 0.97 4.553E-02 351. 93 37.600 6.156E-01 PB214 609.16 45. 16.04 1.02 2.830E-02 609.31 46.100 7.175E-01 BI214 661.86 25. 24.33 0.77 2.639E-02 661.66 85.100 2.325E-01 cs137 1173.14 20. n.36 0.36 1. 656E-02 1173.24 99.974 2.527E-01 c060 1332.24 23. 20.85 0.46 1. 494E-02 1332.50 99.986 3. nOE-01 c060 1460.74 101. 9.95 0.99 1. 387E-02 1460.83 11.000 1.383E+01 K40 ****-1:******* UN IDE NTI FIE D PEA K SUM MARY of: "1:* of: * '1:* ,'( *"1."1.

  • peak centroid Background Net Area Intensity Uncert FWHM Channel Energy counts Counts cts/sec 2 sigma % kev NUC ide 1194.33 295.46 10. 42. 0.140 40.41 0.692 sM s -Peak fails shape D -peak area L -Peak written from unknown C -Area < critical M -Peak is close to a library This section based on library: plumbrk 01.lib o ORTEC g v -i (1087) npp32 G53W3.05 07-APR-2008 17:21:00 page PBRF spectrum name:

IDE N T I FIE D PEA K SUM MAR Y ************** Nuclide Peak centroid Background Net Area Intensity Uncert FWHM channel Energy counts counts cts/sec 2 sigma % kev AM-241 0.00 59.54 O. O. 0.000 0.00 0.000 page 2

  • PB08-01217 TH-234 0.00 63.29 O. O. 0.000 0.00 0.000 TH-234 0.00 92.59 O. O. 0.000 0.00 0.000 EU-152 0.00 121. 78 O. O. 0.000 0.00 0.000 EU-154 0.00 123.07 O. O. 0.000 0.00 0.000 u-235 0.00 143.76 O. O. 0.000 0.00 0.000 u-235 0.00 185.71 O. O. 0.000 0.00 0.000 RA-226 752.68 186.39 12. 46. 0.152 46.12 1.9365 PB-212 964.41 238.67 12. 68. 0.225 31. 25 0.4815 EU-152 0.00 344.28 O. O. 0.000 0.00 0.000 PB-214 1423.59 352.08 2. 50. 0.168 30.48 0.967 Ag-I08m 0.00 433.94 O. O. 0.000 0.00 0.000 B1-214 2464.22 609.16 2. 45. 0.149 32.07 1.0195 Ag-I08m 0.00 614.28 O. O. 0.000 0.00 0.000 cs-137 2677.50 661. 86 3. 25. 0.083 48.66 Ag-I08m 0.00 722.91 O. O. 0.000 0.00 0.000 EU-154 0.00 723.30 O. O. 0.000 0.00 0.000 B1-212 0.00 727.33 O. O. 0.000 0.00 0.000 EU-154 0.00 1004.72 O. O. 0.000 0.00 0.000 co-60 4745.60 1173.14 O. 20. 0.067 44.72 EU-154 0.00 1274.44 O. O. 0.000 0.00 0.000 co-60 5388.83 1332.24 O. 23. 0.077 41. 70 EU-152 0.00 1408.01 O. O. 0.000 0.00 0.000 K-40 5908.18 1460.74 O. 101. 0.337 19.90 0.9905 5 -peak fails shape tests. D -Peak area deconvoluted.

A Derived peak area. ***** SUM MAR Y o F LIB RAR Y PEA K USA GE ***** -Nuclide -Average Peak Name Code Activlty Energy Activity Code MDA value pci/g kev pci/g pCi/g COMMENTS K-40 N 1. 3825E+Ol 1460.83 1.383E+Ol ?( 1.009E+00 9.95 G K co-60 F 2.8736E-Ol 1332.50 3.220E-O@

1. 032E-Ol 20.85 G K 1173.24 2.527E-0 ? 9.314E-02 22.36 G K cs-137 I 2.3247E-Ol 661.66
1. 003E-Ol 24.33 G K 0 ORTEC 9 v -i (l087) npp32 G53w3.05 07-APR-2008 17:21:00 Page 4 PBRF spectrum name: PB08-01217.Anl Nuclide Ave activity Energy Activity code peak MDA Comments PB-212 N 5.2530E-Ol 238.63 5.253E-Ol ( 1. 493E-Ol 15.63 G K PB-214 N 6.1562E-Ol 351. 93 6.156E-Ol ( 1. 229E-Ol 15.24 G K B1-214 N 7.1752E-Ol 609.31 7.175E-Ol

?( 1. 531E-Ol 16.04 G K 1764.49 O.OOOE+OO % 1. 504E+00 195.79 G 1120.29 O.OOOE+OO % 5.931E-Ol 88.71 G RA-226 N 3.6836E+00 Page 3

  • PB08-01217 186.21 3.684E+00
  • ( 1.553E+00 23.06 G K ( -This peak used in the nuclide activity average. peak is too wide, but only one peak in

-Peak is part of a multiplet and this area negative during ? -Peak is too @ -peak is too wide at FW25M, but ok at % -Peak fails sensitivity $-Peak identified, but first peak of this failed one or more qualification + -Peak activity higher than counting uncertainty Peak activity lower than counting uncertainty -Peak outside analysis energy &-calculated peak centroid is not close enough to library energy centroid for positive P -peakbackground } Peak is too close to another for the to be found directly. Nuclide Codes: peak T -Thermal Neutron Activation G -Gamma F -Fast Neutron Activation X -I -Fi ssi on product P -Positron N -Naturally occurring Isotope S - P -photon Reaction D -Dou C -charged particle Reaction K -Key M -NO MDA calculation A -Not in R -coincidence Corrected C -coincidence H -Halflife limit o ORTEC g V -i (1087) npp32 G53W3.05 07-APR-2008 17:21:00 Page 5 PBRF Spectrum name: PB08-01217.An1

          • SUM MAR Y oF NUCLI DES IN SAMPLE Time of Count Time corrected uncertainty 2 sigma Nuclide Activity Activity counting Total MDA pci/g pci/g pci/g pci/g 1. 3825E+01 1. 3825E+01 2.7513E+00 2.7811E+00 1.009E+00

&:.-____ Co-60 2.8683E-01 2.8736E-01 8.7859E-02 8.8263E-02

1. 030E-01 Ag-10 . 6.1569E-02 6.1571E-02 cs-13 # 2.3240E-01 2.3247E-01
1. 1313E-01 1.1333E-01
1. 002E-01 EU-15 < 1. 8301E-01 1. 8314E-01 EU-154 B< 1. 5437E-01 1. 5454E-01 PB-212
  • 5.2530E-01 5.2530E-01
1. 6417E-01 1.6473E-01
1. 493E-01 J.PB-214 6.1562E-01 6.1562E-01 1.8767E-01 1. 8854E-01 1. 229E-01 BI-212 B< 9.7371E-01 9.7371E-01 BI-214 & 7.1752E-01 7.1752E-01 2.3014E-01 2.3140E-01
1. 531E-01 RA-226 & 3.6836E+00 3.6836E+00
1. 6988E+00 1. 7435E+00 1. 553E+00 TH-234 B< 1. 6951E+00 1.6951E+00 u-235 B< 2.2506E-01 2.2506E-01 AM-241 B< 2.3853E-01 2.3854E-01 # -All peaks for activity calculation had bad Activity omitted from &-Activity omitted from total and all peaks had bad shape. < -MDA value printed. page 4
  • A-printed, but activity < B -Actlvlty < MDA and failed C -Area < critical F -Failed fraction or key line H -Halflife limit

5 U M MAR Y Total Activity ( 38.8 to 2014.2 kev) 5.1922846E-01 pci/g Total Decayed Activity ( 38.8 to 2014.2 kev) 5.1983637E-01 pCi/g Analyzed Reviewed project Laboratory: PBRF R.case page 5

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  • SECTION ATTACHMENT 1 OOA Check Sheet Design # EP PPH-108 I Revision # Original ISurvey Unit EP Preliminary Data Answers to the following questions should be fully documented in the Survey Yes No N/A Release Record Have surveys been performed in accordance with survey instructions in the Survey Design? X Is the instrumentation MDC for structure static measurements below the DCGLw for Class 1 and 2 X survey units, or below 0.5 DCGLw for Class 3 survey units? Is the instrumentation MDC for embedded/buried piping static measurements below the DCGLw ? X Was the instrumentation MDC for structure scan measurements, soil scan measurements, and embedded/buried piping scan measurements below the DCGL w , or, if not, was the need for additional X static measurements or soil samples addressed in the survey design? XWas the instrumentation MDC for volumetric measurements and smear analysis < 10% DCGLw ? Were the MDCs and assumptions used to develop them appropriate for the instruments and techniques X used to perform the survey? Were the survey methods used to collect data proper for the types of radiation involved and for the X media being surveyed?

XWere "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 X design, which accurately reflects the radiological status of the facility? Graphical Data Review XHas a posting plot been created? XHas a histogram (or other frequency plot) been created? XHave other graphical data tools been created to assist in analyzing the data? Data Analysis XAre all sample measurements below the DCGLw (Class 1 & 2), or 0.5 DCGLw (Class 3)? XIs the mean of the sample data < DCGLw? If elevated areas have been identified by scans and/or sampling, is the average activity in each X elevated area < DCGLEMc (Class 1), < DCGLw (Class 2), or <0.5 DCGLw (Class 3)? XIs the result of the Elevated Measurements Test < 1.0? X Comments: See Section 5 of this Survey Unit Release Record Is the result of the statistical test (5+ for Sign Test or W, for WRS Test) .::: the critical value? Date 04/07/08 FSS/Characterization Engineer (print/sign) o Wojtkowiak RCas9 :J/;h o Date FSS/ Characterization Manager (print/sign) Form CS-09/2 Rev 0 Page 1 of 1

  • SECTION ATTACHMENT 1}}
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