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Text

Survey Unit Release Record EP Pph 115, Revision - Original
	ML081330339
Person / Time
Site:	Plum Brook
Issue date:	04/09/2008
From:	Case R, Wojtkowiak D, Wood G; US National Aeronautics & Space Admin (NASA), John H. Glenn Research Ctr at Lewis Field
To:	; NRC/RGN-III
References
	EP-PPH 115
	Download: ML081330339 (29)
	v • d • e

{{#Wiki_filter:* Survey Unit Release Record

Design # EP-PPH 115 Revision # Original Page 1 of 3 Survey Unit #(s) PPH 115

1) Portions of Embedded Pipe (EP) Survey Unit PPH 115 that remain embedded in the building foundation walls meet the definition of embedded pipe for Plum Brook Reactor Facility (PBRF). The portion of piping which transits in soil under 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 115 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) Two core bores were performed to remove sections 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 Description release criteria.

4) Surveys in EP PPH 115 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)/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 BSVLVS-002, WEP 05-006, these determinations are appropriate for the types of radiation involved and the media being surveyed.

Approval Signatures Date:

                                          ~                    D Wojtkowiak FSS/Characterization Engineer                   . C-J ;:.....                            04/09/08 Technical Reviewer 1J~- /7- D ~

(FSS/Characterization Engineer) FS S/Characterization Manager Form CS-09/1

FSS Design # EP PPH 115 Revision # Original Page 2 of3 Survey Unit: PPH 115 1.0 HistorylDescription 1.1 The subject pipe system consists of two cleanouts and floor drain piping from PPH Room 5 and PPH Room 6. 1.2 EP PPH 115 consists of three sections of 4" diameter piping that is approximately 13 feet in total length. 2.0 Survey Design Information 2.1 EP PPH 115 was surveyed lAW Procedure #BSI/LVS-002. 2.2 100% of the 4" pipe sections were accessible for survey. The accessible 4" pipe was surveyed by static measurement at one foot increments, for a total of 13 survey measurements. 2.3 Surface area for the 4" piping is 973 cm2 for each foot of piping, corresponding to a total 4" piping surface area of 12,649 cm2 (1.27 m2) for the entire length of (approximately 13') of 4" piping. 3.0 Survey Unit Measurement LocationslData 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 I. 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\ 5.3 No individual measurement observed in EP PPH 115 exceeded the Unity Rule as provided in Section 3.6.3 of the FSSP. No Elevated Measurement Comparisons (EMC) was required or performed. The survey unit that is constituted by EP PPH 115 passes FSS. Mean unity for this survey unit was 0.391 of unity. 5.4 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.

FSS Design # EP PPH 115 ] Revision # Original Page 3 of 3 I Survey Unit: PPH 115 5.7 Statistical Surrunary Table Statistical Parameter 4" Pipe Total Number of Survey Measurements 13 Nwnber of Measurements >MDC 10 Number of Measurements Above 50% ofDCGL 2 Nwnber of Measurements Above DCGL o Mean 0.391 Median 0.383 Standard Deviation 0.157 Maximum 0.791 Minimwn 0.168 6.0 Docwnentation 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 115 to be less than 25 mrem/yr. The dose contribution is estimated to be 9.78 mrem/yr based on the average of the actual gross counts measured. 7.0 Attachments Attachment 1 - BSI EPIBP Survey Report Attachment 2 - Pipe Interior Radiological Survey Form Attachment 3 - Soil Sample Analysis Attachment 4 - DQA Worksheet Attachment 5 - EP PPH 115 Spreadsheet Disc

SECTION?

ATTACHMENT 1 2 PAGES

IkJm BSI EP/BP SURVEY REPORT Pipe ID PPH 115 Survey Location PPH Rms 5 & 6, 0' ft. el.

Survey Date 2121108,31612008,3128/08 2350-1 # 189094 / 203438 Survey Time See Survey Sheets Detector-Sled # LVS-1, 101 & no sled Pipe Size 4" Detector Efficiency 0.00039 DCG L (dpm/10OCm2) 1.10E+04 Pipe Area Incorporated by Detector Efficiency (in cm21 973 Pipe Area Incorporated by Survev Data 1m" 1.3 Field BKG (cpm) 3.2 to 3.6 Routine Survey X Field MDCR (cpm) 3.5 to 10 QA Survey Nominal MDC (dpm/100cm2) 2,366 Survey Measurement Results Total Number of Survey Measurements 13 Number of Measurements >MDC 10 Number of Measurements Above 50% DCGL 2 Number of Measurements Above DCGL 0 Mean 0.391 Median 0.383 Standard Deviation 0.157 Maximum 0.791 Minimum 0.168 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 Pass/Fail FSS Pass MREMNR Contribution <25 COMMENTS: ACTIVITY VALUES NOT BACKGROUND CORRECTED RP Engineer I Date

                                                             ~                                                       D. Wojtkowiak - 4/9/2008 5/6/2008

EP PPH-115
4" Pipe

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1 33 33 84,615 8,696 1 17 17 43,590 4,480 2 15 15 38,462 3,953 3 7 7 17,949 1,845 4 13 13 33,333 3,426 5 16 16 41,026 4,216 6 15 15 38,462 3,953 7 14 14 35,897 3,689 8 17 17 43,590 4,480 9 7 7 17,949 1,845 10 19 19 48,718 5,007 11 17 17 43,590 4,480 1 22 22 56,410 5,798 MEAN MEDIAN STANDARD DEVEIATION MAXIMUM MINIMUM 1 of 1

SECTION 7 ATTACHMENT 2 7 PAGES
Pipe Interior Radiological Survey Form
BSL/LVSPipeCrawler-002 Revision 5 Date: ~*J(*()t Time: Ij-J 6

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C06 a~ fOb b (I Pipe ID#: Pipe Diameter: Access Point Area: Building: Pry I<-flo. b Elevation: Q System: f!J Type of Survey Investigation Characterization Final Survey t- Oth...Le-'-r-~----- Gross Co60 / Cs - - - Detector ID# / Sled ID# . 13 ('CfO~ 16f+1! I 1--1/ S~ I / (l 0 '5(~ A Detector Cal Date: l' d- 5"0 ~ Detector Cal Due Date: _.L-'_."",J-,-,,[O-'._0----'-7 _ Instrument: 'J...3 SV - ( Instrument ID #: _l"--""---1-"--o--::.9_y-'------ _ Instrument Cal Date: t* ). )" '() g Instrument Cal Due Date: I' J- 'J- 'd

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SECTION?

ATTACHMENT 3 11 PAGES

Attachment 3 Comments.

The graphic map in this attaclunent portrays the extent of core bores and excavations to support remediation of PH 115. Also included are the physical survey locations for the soil samples acquired to verify soil activity levels were less than DCGL at the conclusion of remediation activities in the various excavations. The appropriate soil sample 1D numbers can be discerned in the hexagon symbols on the map. The soil sample results are included in this attaclunent.

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ORTEC g v - 1 (1087) npp32 G53w3.05 26-MAR-2008 16:49:38 page 1 PBRF Spectrum name: PB08-01085.An1 sample description PB08-01085; SR99-17; PPH-RM5; FD-5; 3/26/08 spectrum Filename: Z:\Lab\SAMPLE 08\PB08-01085.An1 Acquisition information Start time: 26-Mar-2008 16:42:58 Live time: 300 Real time: 302 Dead time: 0.50 %

Detector 1D: 1 Detector system

      #1 DETECTOR (#129)

Calibration Filename: [] COpy 250ml #73678-773 (MC129) Jan08 Energy Calibration created: 09-Jan-2008 08:36:01 Zero offset: -0.051 kev Gain: 0.250 kev/channel Quadrat;-c: -8.299E-09 kev/channel A2 Efficiency Calibration created: 09-Jan-200809:15:56 Type: Pol ynomi al uncertainty: 1. 663 % coefficients: -0.338084 -4.099654 0.610757

                                    -0.082467     0.004895 -0.000109 Library Files Main analysis library:       plumbrk 01.1ib Library Match width:         0.500 Peak stripping:              Library based Analysis parameters Analysis engine:             npp32     G53w3.05 Start channel:             155 (     38.73kev)

Stop channel: 8144 ( 2037.21kev) Peak rejection level: 25.000% Peak search sensitivity: 3 sample Size: 4.4520E+02 Activity scaling factor: 1.0000E+06/( 1.0000E+00* 4.4520E+02) 2.2462E+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

ORTEC g v - i (1087) npp32

PB08-01085
G53w3.05 26-MAR-2008 16:49:38 Page 2 PBRF spectrum name: PB08-01085.An1 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 18-Mar-2008 15:47:00 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: 0.1637 SUM MAR Y 0 F PEA K S I N RAN G E *****

peak Area Uncert FWHM Corrctn Nuclide Brnch. Act. NUC Energy Factor Energy Ratio pCi/g 77.10 50. 23.70 0.71 8.389E-02 238.47 57. 14.89 1. 20 6.441E-02 238.63 43.300 4.160E-01 PB212 351. 52 74. 13.88 1.10 4.765E-02 351. 93 37.600 8.358E-01 PB214 609.17 38. 17.90 0.51 3.006E-02 609.31 46.100 5.500E-01 BI214 661. 29 18. 23.57 0.50 2.809E-02 661.66 85.100 1. 524E-01 cs137 1460.90 91. 10.48 1. 78 1.481E-02 1460.83 11.000 1.130E+01 K40

************ U N IDE N T I FIE D                                                    PEA K

SUMMARY

Peak centroid Background Net Area Intensity Uncert FWHM suspected channel Energy Counts Counts Cts/sec 2 sigma % keY Nuclide 308.33 77 .10 33. 50. 0.166 47.40 0.707 PB-214 M 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 26-MAR-2008 16:49:38 page 3 PBRF spectrum name: PB08-01085.An1

* '1,~ 1.. ,'. ,'r .': '1: -.'.. -J.. r: * * * '1: I D E NT I F I E 0          P EAK        S U M M A R Y * "!( 1.. '1: '1: 7. 1: *

1.. "1: '1, .t;-:..

Nuclide Peak centroid Background Net Area Intensity Uncert FWHM Channe 1 Energy Counts Counts ets/Sec 2 sigma % keY AM-241 0.00 59.54 O. O. 0.000 0.00 0.000 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 page 2

u-235 0.00

143.76 O.

PB08-01085 O. 0.000

0.00 0.000 u-235 0.00 185.71 O. O. 0.000 0.00 0.000 RA-226 0.00 186.21 O. O. 0.000 0.00 0.000 PB-212 953.27 238.47 5. 57. 0.191 29.78 1.199s EU-152 0.00 344.28 O. O. 0.000 0.00 0.000 PB-214 1405.09 351.52 7. 74. 0.247 27.76 1.101s Ag-108m 0.00 *433.94 O. O. 0.000 0.00 0.000 BI-214 2434.92 609.17 2. 38. 0.126 35.79 0.508s Ag-108m 0.00 614.28 O. O. 0.000 0.00 0.000 CS-137 2643.23 661.29 O. 18. 0.060 47.14 0.500 Ag-108m 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 BI-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 0.00 1173.24 O. O. 0.000 0.00 0.000 EU-154 0.00 1274.44 O. O. 0.000 0.00 0.000 co-60 0.00 1332.50 O. O. 0.000 0.00 0.000 EU-152 0.00 1408.01 O. O. 0.000 0.00 0.000 K-40 5839.75 1460.90 O. 91. 0.303 20.97 1.776 s - Peak fails shape tests.

D - Peak area deconvoluted. A Derived peak area. hh~~~ SUM MAR Y o F LIB R A R Y PEA K USA G E ***** - Nuclide - Ave~age ------------- Peak ------------- Name Code ActlVlty Energy Activity Code MDA value pci/g kev pci/g pCi/g COMMENTS K-40 N 1. 1305E+01 1460.83 1.130E+01 ?( 9.156E-01 10.48 G K cs-137 I 1. 5245E-01 661.66 1. 524E-01C 6.242E-02 23.57 G K PB-212 N 4.1599E-01 238.63 4.160E-01 ( 9.270E-02 14.89 G K 0 ORTEe 9 v - i (1087) npp32 G53w3.05 26-MAR-2008 16:49:38 page 4 PBRF Spectrum name: PB08-01085.An1 Nuclide Ave activity Energy Activity Code peak MDA Comments PB-214 N 8.3577E-01 351.93 8.358E-01 *( 1.699E-01 13.88 G K BI-214 N 5.5004E-01 609.31 5.500E-01?( 1.435E-01 17.90 G K 1764.49 O.OOOE+OO & 7.698E-01 31. 62 G 1120.29 O.OOOE+OO % 5.894E-01 169.97 G ( - This peak used in the nuclide activity average .. h 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.

page 3

PB08-0l085

               + - Peak actlvlty 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 - Fission Product P - Positron Decay N Naturally occurring Isotope S - single-Escape P - Photon Reaction D Double-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

    ~I * .,) * .J. J. J..

SUM MAR Y o F N U C L I DES I N SAM P L E 1: '1: 1; '1:

Time of Count Time Corrected uncertainty 2 Sigma Nuclide Activity Activity counting Total MDA pci/g pCi/g pCi/g pCi/g K-40 & 1.1305E+Ol 1.1305E+Ol 2.3701E+00 2.3978E+00 9.l56E-Ol co-60 B< 9.3322E-02 9.3593E-02 A9-108m;; 4.l474E-02 4.1475E-02 JL _.CS-137Vt EU-152 B<

1. 5237E-Ol 1.l597E-Ol

1. 5245E-Ol 1.l6l0E-Ol 7.l865E-02 7.2032E-02 6.239E-02 EU-154 B< 1. 0466E-Ol 1.0485E-Ol 0

ORTEC g v - i (1087) npp32 G53W3.05 26-MAR-2008 16:49:38 Page 5 PBRF Spectrum name: PB08-01085.Anl PB-2l2 >. 4.l599E-Ol 4.l599E-Ol 1. 2389E-Ol 1. 2435E-Ol 9.270E-02 PB-214 & 8.3576E-Ol 8.3577E-Ol 2.3201E-Ol 2.3357E-Ol 1.699E-Ol BI-212 B< 1. 0329E+00 1. 0329E+00 BI-214 & 5.5003E-Ol 5.5004E-Ol 1. 9688E-Ol 1.9789E-Ol 1. 43 5E-Ol RA-226 B< 2.l287E+00 2.l287E+00 TH-234 B< 1. 5306E+00 1. 5306E+00 U-235 8< 4.8550E-Ol 4.8550E-Ol AM-24l B< 1. 8481E-Ol 1. 8481E-0l

               # - 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.

A - Activity printed, but actlvlty < MDA. B - Activity < MDA and failed test. C - Area < Critical level. F - Failed fraction or key line test. H - Halflife limit exceeded _____________________________ SUM MAR Y --------------------------- Total Activity ( 38.7 to 2037.2 keV) 1.5237l33E-Ol pCi/g Total Decayed Activity ( 38.7 to 2037.2 kev) 1.5244865E-Ol pCi/g Analyzed by: fi~ ning project page 4

                     *
                    ~8-01085

Reviewed by:

S~Vi sor MAR 2 6 2008 R. Case Laboratory: PBRF page 5

PB08-01215
ORTEC g v - i (1087) npp32 G53w3.05 07-APR-2008 17:14:25 page 1 PBRF spectrum name: PB08-01215.An1 sample description PB08-01215; SR99-33; PpH RM 6; FD-6; 4/7/08 spectrum Filename: z:\Lab\SAMPLE 08\PB08-01215.An1 Acquisition information Start time: 07-Apr-2008 17:08:41 Live time: 300 Real time: 301 Dead time: 0.21 %

Detector 1D: 3 Detector system

       #3 DETECTOR (#131) calibration
        . Fi 1ename:

250ml #73678-773 (MC131) Sept07 ro COl Energy Calibration created: 05-Sep-200716:56:38 zero offset: 0.565 keY . Gain: 0.247 keY/channel Quadratic: 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:       plumbrk 01.lib 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: 4.6390E+02 Activity scaling factor: 1.0000E+06/( 1.0000E+00* 4.6390E+02) 2.1556E+03 Detection limit method: Nureg 4.16 Random error: 1.0000000E+00 systematic error: 1.0000000E+00 Hacti on Li mi t : *0.000% Background width: best method (based on spectrum). o page 1

"

PB08-01215

."

ORTEC g v - i (1087) npp32 G53w3.05 07-APR-2008 17:14:25 Page 2 PBRF Spectrum name: PB08-01215.An1 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 31-Mar-2008 13:40:00 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: 0.1417

  *1..-***                 S U MMA R Y 0 F               P EAKS         I N RAN G E *****

Peak Area Uncert FWHM Corrctn Nuclide Brnch. Act. Nuc Energy Factor Energy Ratio pci/g 77.32 69. 18.21 0.58 8.258E-02 238.44 62. 18.61 0.93 6.196E-02 238.63 43.300 4.512E-01 PB212 351. 97 70. 12.94 1.13 4.555E-02 351. 93 37.600 7.937E-01 PB214 609.00 52. 15.38 0.85 2.830E-02 609.31 46.100 7.741E-01 BI214 1460.49 104. 9.81 1. 85 1. 387E-02 1460.83 11.000 1. 324E+01 K40

  "!: r.of( +: 1; .J,:.-** * * *

U N IDE N T I F I E D PEA K S U M M A R Y ,,/(-/.***** * ***-1.

peak centroid Background Net Area Intensity uncert FWHM suspected channel Energy Counts Counts Cts/sec 2 sigma % kev Nuclide 310.92 77.32 31. 69. 0.229 36.42 0.575 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 17:14:25 Page 3 PBRF spectrum name: PB08-01215.An1

  ***-I;'f.********-Ir I D E N T I F I E D P E A K                             S U M MAR Y **************

Nuclide peak centroid Background Net Area Intensi ty 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 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 page 2

U-235 0.00 185.71

O.

PB08-01215 O. 0.000

0.00 0.000 PB-212 963.47 238.44 17. 62. 0.208 37.22 0.927 EU-152 0.00 344.28 O. O. 0.000 0.00 0.000 PB-214 1423.16 351.97 3. 70. 0.233 25.87 1.128 Ag-108m 0.00 433.94 O. O. 0.000 0.00 0.000 B1-214 2463.60 609.00 3. 52. 0.173 30.77 0.851s Ag-108m 0.00 614.28 O. O. 0.000 0.00 0.000 cs-137 0.00 661. 66 O. O. 0.000 0.00 0.000 Ag-108m 0.00 722.91 O. O. 0.000 0.00 0.000 EU-154 0.00 723.30 O. O. 0.060 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 (0-60 0.00 1173.24* O. O. 0.000 0.00 0.000 EU-154 0.00 1274.44 O. O. 0.000 0.00 0.000 (0-60 0.00 1332.50 O. O. 0.000 0.00 0.000 EU-152 0.00 1408.01 O. O. 0.000 0.00 0.000 K-40 5907.17 1460.49 O. 104. 0.347 19.61 1.850 s - Peak fails shape tests.

D - Peak area deconvoluted. A Derived peak area .

 *****    5 U M MAR Y        .0 F    LIB R A R Y P E A-K             USA G E *****

- Nuclide - Ave~age ------------- Peak ------------- Name code ActlVlty Energy Activity Code MDA value pcijg kev pcijg pcijg COMMENTS K-40 N 1. 32'42E+01 1460.83 1. 324E+01 ( 9.384E-01 9.81 G K PB-212 N 4.5121E-Ol 238.63 4.512E-01 ( 1. 573E-Ol 18.61 G K PB-214 N 7.9374E-01 351.93 7.937E-01 ( 1. 223E-01 12.94 G K 0 ORTEC g v - i (l087) npp32 G53w3.05 07-APR-2008 i7:14:25 Page 4 PBRF Spectrum name: PB08-01215.An1 Nuclide Ave activity Energy Activity Code peak MDA Comments B1-214 N 7.7410E-01 609.31 7.741E-01 ( 1.605E-Ol 15.38 G K 1764.49 O.OOOE+OO % 7.852E-Ol 25.82 G 1120.29 O.OOOE+OO % 5.517E-Ol 25.82 G ( - This peak used in the nuclide activity average.

   ~    peak is too wide, but only one peak in library.
      - peak is part of a multiplet and this area went negative during deconvolution.

7 - 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 counfinguncertainty range.

peak activity lower than counting uncertainty range.

      - peak outside analysis energy range.
   & - calculated peak centr~id is not.c!ose.enough,to ~he library energy centrold for posltlve ldentlflcatlon.

page 3

P - peakbackground subtraction PB08-01215

                                                                     *
   }     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 Fission Product P positron Decay N Naturally occurring Isotope S single-Escape P Photon Reaction D Double-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

 *****       5 U M 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 K-40     ..      1. 3242E+01     1.3242E+01      2. 5969E+00    2.6258E+00 9.384E-01 co-60 B<         9.5789E-02      9.6035E-02 Ag-108mB<        4.5977E-02      4.5978E-02 C5-137 B<        6.3726E-02      6.3754E-02 EU-152 B<        1. 2226E-01     1. 2238E-01 EU-154 B<        1. 1362E-01     1. 1380E-01 PB-212

4.5121E-01 4.5121E-01 1. 6793E-01 1.6834E-01 1.573E-01 PB-214 ~

7.9373E-01 7.9374E-01 2.0536E-01 2.0667E-01 1.223E-01 BI-212 B< 1. 6349E+00 1. 6349E+00 0 ORTEC 9 v - i (l087) npp32 G53w3.05 07-APR-2008 17:14:25 Page 5 PBRF spectrum name: PB08-01215.An1 BI-214 ~ 7.7409E-01 7.7410E-01 2.3818E-01 2.3961E-01 1. 605E-01 RA-226 B< 2.1736E+00 2.1736E+00 TH-234 B< 1. 6827E+00 1. 6827E+00 u-235 B< 2.9555E-01 2.9555E-01 AM-241 B< 2.1750E-01 2.1751E-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.

A - Activity printed, but actlvlty < MDA. B - Activity < MDA and failed test. C - Area < Critical level. F - Failed fraction or key line test. H Halflife limit exceeded SUM MAR Y --------------------------- Total Activity ( 38.8 to kev) O.OOOOOOOE+OO pCi/g Total Decayed Activity 2014.2 kev) O.OOOOOOOE+OO pCi/g Analyzed by: Project APR 0 8*200B Reviewed by: R.Case Laboratory: PBRF Page 4

SECTION?

ATTACHMENT 4 1 PAGE

DQA Check Sheet Design # EPPPH-115 I Revision # I Original I . Survey Unit # EP PPH-115 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 MOC for embedded/buried piping static measurements below the DCGLw ? X

4. Was the instrumentation MOC 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 MOCs 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 I I X design, which accurately reflects the radiological status of the facility? J 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:

FSS/Characterization Engineer (prinUsign) D Wojtkowiak

                                                                              ~                           Date    04/09/08 FSS/ Characterization Manager (prinUsign)

R~tr~ v Date ~/vj;;8 Form CS-09/2 Rev 0 Page 1 of 1

SECTION 7 ATTACHMENT 5 1 DISC}}

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