ML081270683
| 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) | |
Text
{{#Wiki_filter:* Survey Unit Release Record Design # EP-PPH 108 I Revision # I Original Page 1 of 3 Survey Unit #(s) PPH 108
- 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 Description residual radioactivity at concentrations well below the release criteria.
- 4) Surveys in EP PPH 108 were performed using a scintillation detector optimized to 60 measure gamma energies representative of C0 . 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)/LVS-002, Work Execution Package (WEP) 05-006. Survey instructions described in this document constitute "Special Methods" and the survey design used in the acquisition of survey measurements.
- 6) 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:
~ DWojtkowiak FSS/Characterization Engineer 04/07/08
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Technical Reviewer (FSS/Characterization Engineer) 4- /1- 08 FSS/Characterization Manager Form CS-09/1 Rev 0
FSS Design # EP PPH 108 I Revision # Original I Page 2 of3 Survey Unit: PPH 108 1.0 HistoryfDescription 1.1 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. 1.2 EP PPH 108 consists of 4, 6 and 8" diameter piping that is approximately 171 feet in length. 2.0 Survey Design Information 2.1 EP PPH 108 was surveyed lAW Procedure #BSlILVS-002. 2.2 100% 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. 2.3 Surface area for the 4" piping is 973 cm2 for each foot of piping, 2 2 corresponding to a total 4" piping surface area of 106,057 cm (10.61 m ) for the entire length of (approximately 109') of 4" piping. 2.4 100% 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. 2.5 Surface area for the 6" piping is 1,459 cm2 for each foot of piping, 2 2 corresponding to a total 6" piping surface area of 21 ,885 cm (2.19 m ) for the entire length of (approximately 15') of 6" piping. 2.6 100% 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. 2.7 Surface area for the 8" piping is 1,946 cm2 for each foot of piping, 2 2 corresponding to a total 8" piping surface area of 91 ,462 cm (9.15 m ) for the entire length of (approximately 15') of8" piping. 3.0 Survey Unit Measurement LocationsfData 3.1 Pipe interior radiological survey forms are provided in Attachment 2 of this release record. 4.0 Survey Unit InvestigationslResults 4.1 None 5.0 Data Assessment Results 5.1 Data assessment results are provided in the EPlBuried Pipe (BP) Survey Report provided in Attachment 1. 5.2 This survey unit was assessed as a building re-use scenario with all activity derived dose as a 100% C060 nuclide distribution. This is the most conservative DCGL for the facility (11,000 dpm/l OOcm\
FSS Design # EP PPH 108 I Revision # Original I Page 3 of3 Survey Unit: PPH 108 5.3 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. 5A 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. 5.5 No area factors were used for this survey unit. 5.6 Background was not subtracted from the survey measurements. 5.7 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 6.0 Documentation of evaluations pertaining to compliance with the unrestricted use limit of 25 mrem/yr and dose contributions from Embedded Pipe and radionuclides contributing 10% in aggregate of the total dose for both structural scenarios and soils. 6.1 A review of the survey results has shown that the dose contribution for 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. 7.0 Attachments Attachment 1 - BSI EP/BP Survey Report Attachment 2 - Pipe Interior Radiological Survey Form Attachment 3 - Soil Sample Analysis Attachment 4 - DQA Worksheet Attachment 5 - EP PPH 108 Spreadsheet Disc
SECTION 7 ATTACHMENT 1 7 PAGES
BSI EP/BP SURVEY EPORT Pipe 10 PPH 108 Survey Location PPH Rms 1, 3, 4, 5, 6 & 8 811~. 315108, 3I6Ill8 2350-1 # 189094 1203438 Survey Date 312oW8. 3125/1l6, J/31/!J8 Nal detector 44-159 Oetector-Sled # Survey Time See Survey Sheets LVS-1 #238369 Pipe Size 4",6"& 8" Detector Efficiency 000039 000031 0.00029 0.0002
,.,. ~ ~alodbY Oelador ElIIchoncy (In DCGL (",","D0cm21 110E+04 em:Q 973 1459 1946 973 Pfpe An. ~orporat"dby s..v""O.Ulm'l 21.9 Field BKG Ccpml 3.4 3.4 3.5 127 Routine Survey X Field MDCR ''' 9 9 9 15.3 QASurvey NominaJ MOC '",","lIIIanll 2,372 1.990 1595 7,862 I' Survey Measurement Results I
Total Number of Survey Measurements 95 15 47 14 Number of Measurements >MDC 91 1 1 7 Number of Measurements Above 50% DCGL 25 1 1 7 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 1 TBD 06-004 Piping Group 1 SR-13 Radionuclide Distribution Sample EP 3-7 Measured Nuclide Co-60 Area Factor/EMC Used No PasslFail FSS Pass MREMIYR Contribution <25 COMMENTS: ACTIVITY VALUES NOT BACKGROUND CORRECTED. RP Engineer I Date
~ O. Wojtkowiak - 4/912008
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-, ' I 1 8 8 20,513 2,108 0.192 2 12 12 30,769 3,162 0.287 3 14 14 35,897 3,689 0.335 4 7 7 17,949 1,845 0.168 ."
5 13 13 33,333 3,426 0.311 ::I: 6 23 23 58,974 6,061 0.551 7 14 14 35,897 3,689 0.335 <
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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 ::I: 30 25 25 64,103 6,588 0.599 31 13 13 33,333 3,426 0.311 <
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- PPH 108 11 4,68 Pipe TBD 06*004 Group 1
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- 0 64 11 11 28,205 2,899 0.264 I 65 13 13 33,333 3,426 0.311 en 66 16 16 41,026 4,216 0.383 67 13 13 33,333 3,426 0.311 68 13 13 33,333 3,426 0.311 69 18 18 46,154 4,743 0.431 70 28 28 71,795 7,379 0.671 71 13 13 33,333 3,426 0.311 72 17 17 43,590 4,480 0.407 73 16 16 41,026 4,216 0.383 74 18 18 46,154 4,743 0.431 75 14 14 35,897 3,689 0.335 76 20 20 51,282 5,271 0.479 77 13 13 33,333 3,426 0.311 78 19 19 48,718 5,007 0.455 79 16 16 41,026 4,216 0.383 80 12 12 30,769 3,162 0.287 81 15 15 38,462 3,953 0.359 "tJ 82 14 14 35,897 3,689 0.335 "tJ 83 23 23 58,974 6,061 0.551 ::I:
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- PPH 108 4, 6 8" Pipe TSD 06-004 Group 1
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QI E Co-60 activity Co-50 activity QI gcpm ncpm (total dpm) (dpmI100cm2) Unity ell III QI
- e 96 7 7 35,000 3,597 0.327 97 3 3 15,000 1,542 0.140 98 8 8 40,000 4,111 0.374 99 8 8 40,000 4,111 0.374 100 9 9 45,000 4,625 0.420 101 13 13 65,000 6,680 0.607 102 10 10 50,000 5,139 0.467 103 11 11 55,000 5,653 0.514 104 13 13 65,000 6,680 0.607 105 11 11 55,000 5,653 0.514 106 13 13 65,000 6,680 0.607 107 9 9 45,000 4,625 0.420 108 12 12 60,000 6,166 0.561 109 11 11 55,000 5,653 0.514 110 14 14 45,161 3,095 0.281 111 12 12 38,710 2,653 0.241 112 8 8 25,806 1,769 0.161 113 12 12 38,710 2,653 0.241 114 20 20 64,516 4,422 0.402 "'0 115 14 14 45,161 3,095 0.281 "'0 116 22 22 70,968 4,864 0.442
- c 117 118 17 20 17 20 54,839 64,516 3,759 4,422 0.342 0.402
- 0 I
119 9 9 29,032 1,990 0.181 00 I 120 28 28 90,323 6,191 0.563 ~ 121 20 20 64,516 4,422 0.402 122 12 12 38,710 2,653 0.241 123 14 14 45,161 3,095 0.281 124 12 12 38,710 2,653 0.241 4of6
- PPH 108 4, 6 8" Pipe TSD 06-004 Group 1
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- 2 gcpm ncpm (total dpm) (dpm/100cm2)
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- e 125 17 17 58,621 3,012 0.274 "tJ 126 13 13 44,828 2,304 0.209 "tJ 127 10 10 34,483 1,772 0.161 :1:
128 129 18 10 18 10 62,069 34,483 3,190 1,772 0.290 0.161
- u I 130 24 24 82,759 4,253 0.387 ~
I 131 12 12 41,379 2,126 0.193 N 132 6 6 20,690 1,063 0.097 133 15 15 51,724 2,658 0.242 134 26 26 89,655 4,607 0.419 135 29 29 100,000 5,139 0.467 136 18 18 62,069 3,190 0.290 137 24 24 82,759 4,253 0.387 138 27 27 93,103 4,784 0.435 139 14 14 48,27-5 2,481 0.226 140 12 12 41,379 2,126 0.193 141 20 20 68,966 3,544 0.322 142 10 10 34,483 1,772 0.161 143 17 17 58,621 3,012 0.274 "tJ 144 12 12 41,379 2,126 0.193 "lJ 145 9 9 31,034 1,595 0.145 ~ 146 33 33 113,793 5,848 0.532 147 12 12 41,379 2,126 0.193 <
;0 148 19 19 65,517 3,367 0.306 149 20 20 68,966 3,544 0.322
~I 150 11 11 37,931 1,949 0.177 N 151 18 18 62,069 3,190 0.290 152 13 13 44,828 2,304 0.209 153 19 19 65,517 3,367 0.306 154 13 13 44,828 2,304 0.209 155 13 13 44,828 2,304 0.209 156 12 12 41,379 2,126 0.193 157 16 16 55,172 2,835 0.258 158 20 20 68,966 3,544 0.322 159 16 16 55,172 2,835 0.258 160 15 15 51,724 2,658 0.242 161 14 14 48,276 2,481 0.226 5 af6
- PPH 108 4, 6 8" Pipe TBD 06-004 Group 1
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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 6of6
I: I SECTION 7 ATTACHMENT 2 27 PAGES
- Pipe Interior Radiological Survey Form
- BSIILVSPipeCrawler-002 Revision 5 Date: 3';lJ1'of Time:
Pipe ID#: PPH V R~/- / Pipe Diameter:
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.Building: E evation: Type of Survey Gross - - - Co60 / Detector ID# I Sled ID# _ _,"",-L~{/_5- ,-,- (_ _ 1 _ _~I(}:........L/~, _ Detector Cal Date: /. d '):0 f Detector Cal Due Date: Instniment: j{Y- L ~ s-() ~ I Instrument ID #: Instrument Cal Date: (0 .':Pr. 0 7 Instrument Cal Due Date: 16 From the Daily Pipe Survey Detector Control Form for the Selected Detector Background Value 3 . t.j cpm MDCRstatic cr cpm Efficiency Factor for Pipe Diameter' O.ooooq_ (from detector efficiency determination)
- MDCstatic ~~ 1 Z, dprn/ I 00 cm 2
Is the MDCstatic acceptable? Comments: G No (if no, adjust sample count time and recalculate MDCRstalic) Technician Signature Pipe Interior Radiological Survey Position Feet into Pipe Count Time Gross Net Gross Counts dprn/100cm 2
# from Opening (min) cpm cpm 1 / I g 8 /
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Pipe Interior Radiological Survey Form (Continuation Form)
- BSIILVSPipeCrawler-002 Revision 5 Date:
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- Pipe Interior Radiological Survey Form
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_ _Jl-,--" 0 Access Point Area: System: ffJlf RM 3 Other V 101 Detector Cal Date: . {. J 5" -0 t' Detector Cal Due Date: Instniment: a 3> 5-0 -( Instrument ill #: Instrument Cal Date: ( . <h S'. 0 r Instrument Cal Due Date: 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 7"2 .~ I {jC) crtl Is the MDCstatic acceptable? 0es..) No (If no, adjust sample count tIme and recalculate MDCR,tatic) Comments; r;v1.cz r) s+q riel Lf I, SGt. rue- r ct.! v I( - 3 we VL1-- C{ Uf" ( Wet 7 I 10 (/ f?, J Technician Signature Pipe Interior Radiological Survey Position Feet into Pipe Count Time Gross Net Gross Counts dpm/lOOcm 2 1 I from Opening (min) 18 cpm lR cpm
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- PB08-01217 ORTEC g v - i (1087) npp32 G53w3.05 07-APR-2008 17:21:00 page 1 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: 07-Apr-2008 17:15:16 Live time: 300 Real time: 301 Dead time: 0.23 %
Detector ID: 3 Detector system
#3 DETECTOR (#131)
Calibration Filename: 250ml #73678-773 (MC131) Sept07 ro COpy Energy calibration Created: 05-Sep-2007 16:56:38 zero offset: 0.565 kev Gain: 0.247 kev/channel Quadrati c: 5.022E-08 kev/channel A2 Efficiency Calibration Created: 05-Sep-2007 17:17:39 Type: polynomial uncertainty: 1. 204 % coefficients: -0.304311 -4.249899 0.669559
-0.094002 0.005803 -0.000133 Library Files Main analysis library: pl umbrk 01.1 i b Library Match width: 0.500 peak stripping: Library based Analysis parameters Analysis engine: npp32 G53w3.05 Start channel: 155 ( 38.83kev )
Stop channel: 8144 ( 2014.22kev) Peak rejection level: 25.000% peak search sensitivity: 3 sample Size: 4. 3150E+02 Activity scaling factor: 1.0000E+06/( 1.0000E+00* 4.3150E+02) 2.3175E+03 Detection limit method: Nureg 4.16 Random error: 1.0000000E+00 systematic error: 1.0000000E+00 Fraction Limit: '0.000% Background width: best method (based on spectrum). o Page 1
PBRF ORTEC g v - i (1087) npp32 PB08-01217 G53w3.05 07-APR-2008 17:21:00 Page spectrum name: PB08-01217.An1 2 Half lives decay limit: 12.000 Activity range factor: 2.000 Min. step backg. energy 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 Calibration Normalized diff: 0.0764
***** S U MMA R Y 0 F P EAKS I N RAN G E of:*"!r**
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:******* U N IDE N T I FIE D PEA K SUM M A R Y of: "1:* of: * '1:* ,'( *"1."1.
- peak centroid Background Net Area Intensity Uncert FWHM sus~ected 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 tests.
D- peak area deconvoluted. L- Peak written from unknown list. C - Area < critical level. M- Peak is close to a library peak. This section based on library: plumbrk 01.lib o ORTEC g v - i (1087) npp32 G53W3.05 07-APR-2008 17:21:00 page 3 PBRF spectrum name: PB08-01217.An1
************** 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
TH-234 TH-234 0.00 0.00 63.29 92.59
- O.
O. PB08-01217 O. O. 0.000
- 0.00 0.000 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 0.775s,.....---
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 0.3615---- 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 0.4645..........- 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 R A R Y PEA K USA G E *****
- 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 2.3247E-Ol 2.325E-0~ cs-137 I 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
( - This peak used in the nuclide activity average.
*23.06 G K peak is too wide, but only one peak in library.
- Peak is part of a multiplet and this area went negative during deconvolution.
? - Peak is too narrow.
@ - peak is too wide at FW25M, but ok at FWHM.
% - Peak fails sensitivity test.
$ - Peak identified, but first peak of this nuclide failed one or more qualification tests.
+ - Peak activity higher than counting uncertainty range.
Peak activity lower than counting uncertainty range.
- Peak outside analysis energy range.
& - calculated peak centroid is not close enough to the library energy centroid for positive identlfication.
P - peakbackground subtraction
} Peak is too close to another for the activity to be found directly.
Nuclide Codes: peak codes: T - Thermal Neutron Activation G - Gamma Ray F - Fast Neutron Activation X - X-Ray I - Fi ssi on product P - Positron Decay N - Naturally occurring Isotope S - single-Escape P - photon Reaction D - Dou le-Escape C - charged particle Reaction K - Key Line M - NO MDA calculation A - Not in Average R - coincidence Corrected C - coincidence Peak H - Halflife limit exceeded 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 o F N U C L I DES I N SAM P L E 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 K-40~
&:.- ____ Ag-10 Co- 60 2.8683E-01 2.8736E-01 8.7859E-02 8.8263E-02 1. 030E-01
. 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 PB-214 J.
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 shape.
~ Activity omitted from total
& - Activity omitted from total and all peaks had bad shape.
< - MDA value printed.
page 4
A B Act~v~ty
- PB08-01217 printed, but activity < MDA.
Actlvlty < MDA and failed test. C - Area < critical level. F - Failed fraction or key line test. H - Halflife limit exceeded
----------------------------- 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 by: project Reviewed by: Laboratory: PBRF R.case page 5
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SECTION 7 ATTACHMENT 4 1 PAGE
OOA Check Sheet Design # EP PPH-108 I Revision # Original I I Survey Unit # EP PPH-108 Preliminary Data Review' Answers to the following questions should be fully documented in the Survey Unit Yes No N/A Release Record
- 1. Have surveys been performed in accordance with survey instructions in the Survey Design? X
- 2. 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?
- 3. Is the instrumentation MDC for embedded/buried piping static measurements below the DCGLw ? X
- 4. Was the instrumentation 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 X static measurements or soil samples addressed in the survey design?
- 5. Was the instrumentation MDC for volumetric measurements and smear analysis < 10% DCGLw ? X
- 6. Were the MDCs and assumptions used to develop them appropriate for the instruments and techniques X
used to perform the survey?
- 7. Were the survey methods used to collect data proper for the types of radiation involved and for the X
media being surveyed?
- 8. Were "Special Methods" for data collection properly applied for the survey unit under review? X
- 9. 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
- 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? X Data Analysis
- 1. Are all sample measurements below the DCGLw (Class 1 & 2), or 0.5 DCGLw (Class 3)? X
- 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 X
elevated area < DCGLEMc (Class 1), < DCGLw (Class 2), or <0.5 DCGLw (Class 3)?
- 4. Is the result of the Elevated Measurements Test < 1.0? X
- 5. Is the result of the statistical test (5+ for Sign Test or W, for WRS Test) .::: the critical value? X Comments: See Section 5 of this Survey Unit Release Record FSS/Characterization Engineer (print/sign) o Wojtkowiak
~ Date 04/07/08 FSS/ Characterization Manager (print/sign) RCas9 K~ Date :J/;ho Form CS-09/2 Rev 0 Page 1 of 1
SECTION 7 ATTACHMENT 5 1 DISC}}