ML072850766

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Nasa Plum Brook Reactor, Embedded Pipe Survey Records
ML072850766
Person / Time
Site: Plum Brook
Issue date: 08/09/2007
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: ML072850766 (365)
v • d • e


Text

National Aeronautics and Space Admini st rat ion John H. Glenn Research Center Lewis Field Plum Brook Station Sandusky, OH 44870 Reply IO Attn of QD U.S. NRC Region I11 Mr. William G. Snell, RIII/DNMS/DB 2443 Warrenville Road Suite 2 10 Lisle, IL 60532-4352 August 9,2007

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- 1.13 Survey Unit Release Record EP-1.14 Survey Unit Release Record EP-1.4 1 Survey Unit Release Record EP- 1.43 Survey Unit Release Record EP- 1.93 Survey Unit Release Record EP- HPT 102 Survey Unit Release Record EP-Rx 139 Survey Unit Release Record EP-Rx 15 1 Survey Unit Release Record EP-Rx 162 Survey Unit Release Record EP-Rx 163 Survey Unit Release Record EP- I .37 Survey Unit Release Record EP- 1.8 1 Survey Unit Release Record EP-Rx 127 Survey Unit Release Record EP-Rx 148 Survey Unit Release Record EP-Rx 152 Survey Unit Release Record EP-Rx 157 Survey Unit Release Record EP-1.3 1 Survey Unit Release Record EP- 1.33 Survey Unit Release Record EP 1.82 Survey Unit Release Record EP-Rx 150 Survey Unit Release Record EP-Rx 160 Survey Unit Release Record EP-Rx 204 Survey Unit Release Record EP-Rx 207 Survey Unit Release Record EP-Rx 208 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 0 2001, 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, 61 00 Columbus Avenue, Sandusky, OH 44870, at (419) 621- 3357. Sincerely, Keith M. Peecook Decommissioning Program Manager Design ## Survey Unit #(s) Description Survey Unit Release Record EP-1.13 1 Revision ## 1 Original 1 Page 1 of 3 1.13 1) Embedded Pipe (EP)

Survey Unit 1.13 meets the definition of embedded pipe for Plum Brook Reactor Facility (PBRF).

2) EP 1.13 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 1.13 were performed using a scintillation detector optimized to measure gamma energies representative of CO-60. Sample
  1. 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 FSS Design # EP 1.13 I Revision # Original I Survey Unit:

1.13 I 1 .o 2.0 3.0 4.0 5.0 History/Description 1.1 The subject pipe is the 2" drain line for the 24" Rx Coolant return loop piping. The function of this piping was to convey water from the coolant loop to the sump in the sub pile room corridor on the -47. EP 1.13 consists of 2" diameter piping that is approximately 39 feet in length and has three elbows from 45' to 90". 1.2 Survey Design Information 2.1 2.2 EP 1.13 was surveyed IAW Procedure #BSI/LVS-002.

100% of the 2" ID pipe was accessible for survey. The accessible 2" ID pipe was surveyed by static measurement at one foot increments, for a total of 39 survey measurements.

Surface area for the 2" ID piping is 486 cm2 for each foot of piping, corresponding to a total 2" ID piping surface area of 18,971 cm2 (1.9 m2) for the entire length of (approximately 39')

of 2" piping. 2.3 Survey Unit Measurement Locations/Data 3.1 Pipe intenor 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 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 Level (DCGL) for radionuclide specific EP that corresponds to the 1 mrern/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 (NF), provided in TBD-06-004, the survey unit that is constituted by EP 1.13 passes FSS. Background was not subtracted from the survey measurements and the Elevated Measurement Comparison (EMC) was not employed for this survey unit.

I 1 FSS Design # EP 1.13 Revision # Ori@ Page 3 of 3 I 5.5 Statistical Summary Table Number of Measurements

>MDC Number of Measurements Above 50% of DCGL Number of Measurements Above DCGL 2" Pipe Statistical Parameter 5 0 0 6.0 7.0 Standard Deviation Maximum I Total Number of Survey Measurements I 39 I 0.01 35 ' 0.0797 I Mean 10.0224 I I Median I 0.0184 1 Minimum I 0.0065 I 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 1.13 to be less than 1 mredyr. The dose contribution is estimated to be 0.0224 mredyr based on the average of the actual gross counts measured.

Attachments Attachment 1 - BSI EPBP Survey Report Attachment 2 - Pipe Interior Radioiogical Survey Form Attachment 3 - DQA Worksheet Attachment 4 - EP 1.13 SURR & Spreadsheet Disc SECTION 7 ATTACHMENT 1 3 PAGE(S)

BSI EP/BP SURVEY REPORT 159#238367/nosled RP Engineer I Date COMMENTS:

ACTIVIlY VALUES NOT BACKGROUND CORRECTED.

I 8) 7-13-97 711 312007 C060 activity (total dpm) EP 1.13 2" Pipe TBD 06-004 Group I Co60 activity Cs-I 37 activity (dpmllOOern2) (dpmllOOcrn2) I I Eu-I 52 activlty Eu-164 activity Nb-84 activity (dpmllWcrn2) (dpm1100cm2) (dpm1100cm2)

Ag108m actlviiy (dptn/IOOm2) 39 25 25 25 - 25 21 39 32 21 18 47 39 21 18 18 29 93 15 1s le 2E 5: a 30 3 4% l! 2: 3( I! l! l! .__ I 1 of2 0.021 0.021 0.028 0.018 0.01 5 EP 1.13 2" Pipe TBD 06-004 Group I Eu-154 advlty Nb-94 activity (dpm1100cm2) 1 (dpm1100cm2)

I I Cos0 actlvlty C060 actlvlty gcpm ncpm (totaldpm) (dpm1100cm2)

Ag-108m activlty (dpml100cm2) 1,623 3 - 3 7,895 4 4 10,526 2,164 1,623 3 3 - 7,895 - 2 2 __ 5,263 1,082 3 3 7,895 1,623 4 4 10,526 2,164 10 26,316 - 5,410 _-_ 10.. _-__ __ - _- 546j 63 409 47 273 32 409 47 546 63 1 58 I I I I 1,364 __ Cs-137 actlvlty Eu-162 actlvfty (dpmllOOcm2) (dpm1100cm2) 15 11 8 11 15 38 MEAN MEDIAN ____ 2.053 I ! I 1.026 STD DEV MAX MIN __- 5,132 I I 409 1 47 I 11 - Unity - 0.01( 0.01: 0.01( 0.ON O.Ol( 0.01: 0.03; - 0.02: 0.011 0.01: 0.081 0.oa - 2of2 SECTION 7 ATTACHMENT 2 6 PAGE(S)

I Position Feet into Pipe Count Time # from Opening (min)

BSILVSPipeCrawler-002 Re\.ision 4 Net dprd100cm' 1 Gross Coullts Gross cpm cprn Pipe Interior Radiological Survey Form 1 \ 2 7 3 3 4 "i 5 6 (a 7 8 0 9 9 10 I IO Date: 2-rZ -a G Time: /os 27 / ./J Pipe ID#: Pipe Diameter:

,'< Building:

c,c Elevation: - Yr Gross Co60 J cs "wPp/t' Lop *,d Type of Survey Investigation Characterization Final Survey A Other Zi?,70/ 1 1 t/ 1 Detector ID# / Sled ID# V'f-62 Detector Cal Date: //-f7-ug Detector Cal Due Date: I/-/ 7 - (3 G Instrument:

23 J-4 I Instrument ID #: ur2z3 Instrument Cal Date: //-[ 7 -0 J- Instrument Cal Due Date: 114 7-d L I // r, r- ala !a 3 7 3 .F I z 3t.r I 7 1 t .> ? 7 ,31 5- I z b 3 z It s* 3 I 7 el y l z (Q I I 2 2 4- J d - From the Daily Pipe Survey Detector Control Form for the Selected Detector Background Value Lf( 4 cpm MDCRS,,, i&b cpm Efficiency Factor for Pipe Diameter MDCSWlC bb3b dPd \DD cm2 Is the MDCrahC acceptable?

@ No (if no, zd~ust saiile comlt time and recalculate IvIDCb,,)

0 t WZ, 2 (from detector efficiency determination)

I .. . I\ u LY Technician Signature Pipe Interior Radiological Survey s> Package Page 1 of - 3 REFERENCE COPY - Attac'ment 3, Page 1 BSb'LVSPipeCrawler-002 Revision 4 Pipe Interior Radiological Survey Form (Continuation Form) Building:

n .fl Elevation:

REFERENCE COPY 0 Package Page 2 of 2 Attachment 3, Page 2 7"' I REFERENCE COPY m BSILVSPipeCrawler-002 Revision 5 Pipe Interior Radiological Survey Form Date: 6 6') Time: \I9 5 Pipe ID#: \ . \3 Pipe Diameter:

'XI' Gross Co60 d cs Access Point Area: 5& QL k QUddwL- J System: 4 Building:

C ad Elevation:

Type of Survey Investigation Characterization Final Survey

% Other Detector ID# / Sled ID# 4 q-15 9 /x3s3L7 / & SLA Instrument:

Instrument ID #: \E;? o?"! Detector Cal Date: (n-al- 0 b Detector Cal Due Date: 6 - &\- 07 \ - \\ - d 8 Instrument Cal Date: 1- It- o] Instrument Cal Due Date: From the Daily Pipe Survey Detector Control Form for the Selected Detector Background Value 1 cpm MDCRSMiiC 7 A CPm Efficiency Factor for Pipe Diameter ok 0 0 038 @om detector efficiency determination) (ifno, adjust sanple count tine and recalculate bDCLhi) Technician Signature Q->L a, Pipe Interior Radiological Survey Package Page 1 of3 REFERENCECOPY Attachment 3, Page 1 B S I/LVSPipeCrawler-002 Revision 5 Pipe Interior Radiological Survey Form (Continuation Form) Date: xT - 03 Pipe ID#: \ ,13 Pipe Diameter:

xt' Access Point Area:

sb!! fi\u Building:

c Md Elevation:

43.' System: Package Page 2 of% REFERENCE COPY Attachment 3, Page 2

SECTION 7 ATTACHMENT 3 PAGE(S)

Design # EP 1.13 Revision # Original I. 2. 3. Have surveys been performed in accordance with survey instructions in the Survey Design? Is the instrumentation MDC for strudure 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 embeddedlburied piping static measurements below the DCGLw ? Survey Unit # 4. 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 ? EP 1.13 cz Yes Answers to the following questions should be fully documented in the Survey Unit Release Record

6. Were the MDCs and assumptions used to develop them appropriate for the instruments and techniques used to perfon the survey?

No NIA XI I ~~ 8. 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?

7. Were the survey methods used to collect data proper for the types of radiation involved and for the media beina SUNeved? X X XI ~ ~~ ~ ~ 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 1. Has a posting plot been created?

I I lx 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. If elevated areas have been identified by scans andlor sampling, is the average activity in each elevated area < DCGLEM~ (Class I), 4. Is the result of the Elevated Measurements Test

< 1 .O? 5. Is the result of the statistical test (S+ for Sign Test or W, for WRS Test) 2 the critiil value? DCGLw (Class 21, or ~0.5 DCGLW (Class 3)? X X X X X Data Analysis Form CS-09/2 Rev 0 e Page 1 of 1 i SECTION 7 ATTACHMENT 4 1 DISC

! Survey Unit Release Record Design # Survey Unit #(s) Description EP-1.14 1 Revision#

1 Original 1 Page 1 of 3 1.14 1) Embedded Pipe (EP) Survey Unit 1.14 meets the definition of embedded pipe for Plum Brook Reactor Facility (PBRF).

2) EP 1.14 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 I. 14 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 (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.
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 1.14 Revision # Original 1 .o 2.0 3.0 4.0 5.0 Page 2 of 3 History/Description 1.1 The subject pipe is the 2" drain line for the 24" Rx Coolant return loop piping. The fimction of this piping was to convey water from the coolant loop to the sump in the sub pile room corridor on the -47 foot elevation. . EP 1.14 consists of 2" diameter piping that is approximately 35 feet in length and has three elbows from 45" to 90". 1.2 Survey Design Information 2.1 2.2 EP I. 14 was surveyed IAW Procedure

  1. BSL/LVS-002.

1W/o of the 2" ID pipe was accessible for survey. The accessible 2" ID pipe was surveyed by static measurement at one foot increments, for a total of 35 survey measurements.

Surface area for the 2" ID piping is 486 cm2 for each foot of piping, corresponding to a total 2" ID piping surface area of 1 7,025 cm2 (1.7 m2) for the entire length of (approximately 35') of 2" 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 InvestigationslRedts 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 Report provided in Attachment

1. All measurement results are less than the Derived Concentration Guideline Level @CGL) 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 1.14 passes FSS. Background was not subtracted from the survey measurements and the Elevated Measurement Comparison (EMC) was not employed for this survey unit.

FSS Design ## EP 1.14 I Revision ## Original Survey Unit: 1.14 Page 3 of 3 5.5 Statistical Summary Table ~ ~~ Total Number of Survey Measurements Number of Measurements

>MDC 2" Pipe Statistical Parameter 35 12 Number of Measurements Above 50% of DCGL Number of Measurements Above DCGL 0 0 I Mean 10.0391 I ~ I-- Median I 0.0307 1 I Standard Deviation I 0.0519 I 10.0032 I Minimum 6.0 7.0 ~ 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 1.14 to be less than 1 mredyr. The dose contribution is estimated to be 0.0391 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 - EP 1.14 SURR & Spreadsheet Disc I SECTION 7 ATTACHMENT 1 3 PAGE(S)

BSI EP/BP SURVEY REPORT Pipe ID 1.14 Survey Location I Primary Coolant Drain 42 ~ 2350-1 # 2/22/2006, 612612 007 Survey Date 2 1222311 89094 44-62#2127011121 44- 159#238367/nosled Sunrey Time DetectorSled

  1. I/ 0851,1600 Pipe Size DCGL mmmamzi pf~ *rr Inmrponm Routine Survev 1 2 Detector Efficiency 0.000U0.00038 1.7 Field BKG ~cpm~ 4.411.3 X Field MDCR 10.616.9 2.41 E95 Plp -Inml=-d w- orurrvm CmZ) 486 survey I Nominal YDC IdPnnmCmt) 11 I 0.0307 Median Standard Deviation 0.0519 66361531 4 I 0.3227 Maximum Minimum 0. W32 DEBRAUX, FOWLER Survey Technician(s)

~~ Number of Measurements

>MDC 1 :OMMENTS:

12 CTlVlTY VALUES NOT BACKGROUND CORRECTED.

I Number of Measurements Above 50% DCGL /7- /pa7 RP Engineer I Date 0 Number of Measurements Above DCGL 0 Mean 0.0391 EP 1.14 2" Pi pe TBD 06-004 Group 1 4,875 2,925 4,875 2,925 3.413 ___- ___- 3,413 1,296 907 778 778 907 - 1,296 .- 6,825 3,592 -_ 7,698 5,645 3,079 -- 7,185 ___- 51,318 4,105 8.21 1 _- ,- 1,814 955 2,046 1,501 81 9 1,910 13,642 -__. 1,091 2.183 ~- 6,158 3,079 5.132 1,637 81 9 1 .a - Unity - 0.031 0.021 0.0lE 0.031 O.Olf 0.021 0.01 E 0.012 0.04E 0.037 0.034 0.037 0.02f 0.031 0.02f 0.04: 0.02: 0.04* 0.03: 0.01 E 0.04: 0.32: 0.02* 0.05; 0.02: 0.032 0.03s 0.01I 0.03; 0.01: 0.08i 0.01 I -__ -- __ - -- --~ -_ - .~ -- -__ _- - Co-60 activity (total dpm) C0-60 activity (dpm1100cm2)

Cs-137 activity (dpmllOOcm2)

Nb-94 activity (dpm1100crn2)

Ag-108111 activity (dpmll OOcm2) ncpm 25,000 17,500 15,000 25,000 15,006 17,500 15,000 10,000 37,500 30,000 27,500 30,000 22.500- ~~ ___-~ _____-- -. ____ ~~- ~__~ -- -___-- 150 5,139 3,598 3,084 5,139 3,084 3,598 3,084 2,056 7,709 6,167 5,653 6,167 4,625 - ____._~ ____.- __ - __-____ __--- ~ ___ _____ _- - ___- _c_- _____ 105 90 _~.- -___ 36 21 25 21 14 150 90 105 3 3 2 7.5 6 5.5 6 5 4.5 3.5 -- __~ .~ -. - .- 4.5 __- 122 81 ____~ -Lgw 1.950 518 90 60 225 165 180 135 1 80 -___~ 306 244 - 54 43 1,555 1,426 1,555 4.388 1.166 __ 224 244 _- i a3 39 43 32 36 32 - 25,000 22.500 -____-- . -- -,--- 4,875 1,296 4.388 1.166 150 135 5,139 __ 4.625 351000 18.421 -~___ _c- --___ __ 7: 195 3,787 8,115 5,951 3,246 7,574 - 54,099 4,328 8,656 - 3,787 .. 5,410 _ 6,492 - 3,246 5,410 3.246 _____~ --~_- -__- ___ _- _- -- __ - - -~ 50 26 285 . 150 210 111 -~-__ 39,474 28.947 - ---- - 322 236 129 300 2,144 172 343 214 257 -____-~ -.-____ -. - 1 50 -~ -~__ 57 41 -~--- 151789 36,842 263,158 21,053 42,105 18,421 26,318 31,579 15,789 26,316 15.789 __~___ -___ ____- -- __ ___---~ __~-.- _____..~_

23 53 377 30 60 --____ ____--___

22 1 1,579 1 26 253 14 1 00 8 16 7 lo 111 1 58 26 38 -~___ 5.132 1.364 45 -. 189 95 158 95 426 ~__ _. ~ ~- 129 214 129 86 ____ -. 579 23 38 23 102 15 6 27 _._____ - 141607 2,164 13.856 2,053 I 546 63 4 1 of2

.- Co-60 activity ncpm (total dpm) ____- 10.526 --t- EP 1.14 2" Pipe TBD 06-004 Group 1 C0-60 acuvity (dpmllOOcm2)

Cs-137 activity (dpm1100cm2) 21 429 86 _- Eu-162 activity (dpmll OOcm2) 51 3 10,264 2.053 --__.___ Eu-164 actlvity (dpm1100cm2)

Nb-94 actMty (dpmll00cm2) 16 316 63 Ag-1 O8m acff vity (dpmll OOcm2) 4 75 15 -~-~ MEAN MEDIAN 3TD DEV MAX MlN - Un-Hy - 0.002 0.065 0.01 3 - 0.035 0.031 0.052 0.329 0.00: - 2of2 SECTION 7 ATTACHMENT 2 6 PAGE(S)

' !' Position Feet into Pipe # from Opening 1 1 2 2 4 4 3 5 s 6 7 7 8 9 9 10 /E c B S VLVSPipeCrawler-002 Revision 4 dpm/100cm2 I (min) cpm cpm I Count Time Gross counts Gross Net 7 tO - r //3 7, 7 3 t>- h 1 z (0 3 2. 10 I I 2 h 2 31s 2, c 2 y 7s 2 z I z /A cl, .I/ I d Pipe Interior Radiological Survey Form Tpe of Survey Investigation Characterization Final Survey

?( Other 1 Gross Co60 J cs Detector Ib# / Sled ID# 97 *u77 o/ f ILf Detector Cal Date: //-I 7-c9C Detector Cd Due Date: //-/7-0 6 Instrument:

?a So4 Instrument ID #: i%LZZJ Instrument Cal Date: 4 (-17 -d J- Instrument Cal Due Date: //7 7-0 c From the Daily Pipe Survey Detector Co~trol Form for the Selected Detector Background Value 4!* 4 cpm MDCRS,,, 10% C cpm Efficiency Factor for Pipe Diameter mcstatlc bb36 dpd LVD Cm2 dl moa (from detector efficiency determination)

Is the h4DCSbbc acceptable?

No (ifno, adjust sample count time mil recalculate MI-,) / Technician Signature Pipe Interior Radiological Survey Package Page 1 of 2 REFERENCE COPY Attachment 3, Page 1 I Pipe Interior Radiological Survey Form (Continuation Form) Position Feet into Pipe Count Time Gross Counts Gross f! fi-om Opening (min) cpm Pi // 3 // A5 fa 12- 2 /. P (0 13 /? 9- 9 45 /d /4 a ,b C /c 1- c a ? 44 I& /G 2 I, I./ .7 ,- f Date: Pipe ID#: Building:

dpm/100cm2 1 Net cpm B. la, Y1@ I I 4, d Pipe Diameter:

Elevation:

Y BSb'LVSPipeCrawler-002 Revision 3 \I I Access Point Area:

System: n Package Page 2 of 2 I I REFERENCE COPY . Attachment 3, Page 2 I b . QL .- f 7 REFERENCECOPY I-1

'I BSI/LVSPipeCrawler-O02 Revision 5 Pipe Interior Radiological Survey Form Date: c-m -b> Time: \\ \9 PipeD#: I . I Pipe Diameter:

Access Point Area: SH~ e,\+ &, Building:

GU Elevation:

-4 a' System: Type of Survey Investigation Characterization Final Survey ,?(- Other J Gross Co60 \f N nn cs - Detector ID# / Sled ID# 44 / 2283 d7 / d 5 Detector Cal Date: c- I\- 0 6 Detector Cal Due Date: c a-l-97 Instrument:

4 Instnunent ID #: I8elOS-l Instrument Cal Date: I- I 0 c) Instrument Cal Due Date: I 41 -0 6, From the Daily Pipe Sumey Detector Control Form for the Selected Detector BackgroundValue

\. b cpm MDCRskh, Y,.t CPm Efficiency Factor for Pipe Diameter 0 0 'D 00 3 8 MDcstatic 5314 IO73 cm2 Is the MDCsutic acceptable? (fiom detector efficiency determination)

No (if no, adjust sample count time and recalculate MDCR,,,,)

Comments:

34 ~,bon F8-3-9 \007! L+&-, c4\ L 14 LJ t4L:n \~m,llttk 6s md ne,tdI,wfi, - \ Technician Signature Pipe Interior Radiological Survey REFERENCE COPY 0 Package Page 1 of3 Attachment 3, Page 1 I i BS VLVSPipeCrawler-002 Revision 5 Pipe Interior Radiological Survey Form (Continuation Form) Access Point Area:

Date: c-27 07 Pipe ID#: 'Lj\ Building:

Pipeexa;::

System: Attachment 3, Page 2

SECTION 7 ATTACHMENT 3 I PAGE(S)

Design # Survey Unit# I EP 1.14 EP 1.14 Revision # 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?

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? I Yes No N/A X lx 3. 4. 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? Is the instrumentation MDC for embeddedhuried piping static measurements below the DCGLw ? X X 1 5. Was the instrumentation MDC for volumetric measurements and smear analysis z 10% DCGLw ? I 1 I X ~ ~~ ~ 8. 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?
6. Were the MDCs and assumptions used to develop them appropriate for the instruments and techniques used to Derform the survev?

I X X jxj 7. Were the survey methods used to collect data proper for the types of radiation involved and for the media beina surveved? ~~ ~ ~ ~~ ~ ~ ~ 2. Has a histogram (or other frequency plot) been created?

X 1. Has a posting plot been created?

I I lx 1. 2. 3. 4. Are all sample measurements below the DCGLw (Class 1 & Z), or 0.5 DCGLW (Class 3)? Is the mean of the sample data < DCGLw? If elevated areas have been identified by scans and/or sampling, is the average activity in each elevated area

< DCGLEMC (Class 1). .C DCGLw (Class 2), or ~0.5 DCGLW (Class 3)? Is the result of the Elevated Measurements Test < 1 .O? X X X X 3. Have other graphical data tools been created to assist in analyzing the data? I I Ix 5, Is the result of the statistical test (S+ for Sign Test or W, for WRS Test) 2 the critical value? Data Analysis X FSSCharadedzation Engineer (prinUsign)

Date FSS/ Characterization Meneger (printlsign)

Date 7-1747 7hfl/07 Page 1 of 1 SECTION 7 ATTACHMENT 4 1 DISC Design # Survey Unit #(s) Description Survey Unit Release Record EP-1.41 1 Revision#

1 Original 1 Page 1 of 3 1.41 1) Embedded Pipe (EP) Survey Unit 1.4 1 meets the definition of embedded pipe for Plum Brook Reactor Facility (PBRF). 2) EP 1.41 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 1.41 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 BSILVS-002, WEP 05-006, these determinations are appropriate for the types of radiation involved and the media being surveyed.

Date: Approval Signatures FSS/Characterization Manager CS-09/1 0 COPY

- FSS Design # EP 1.41 Revision # Original 1.0 2.0 3.0 4.0 5.0 Page 2 of 3 HistoxyDescription 1.1 1.2 Survey Design Information 2.1 2.2 The subject pipe system is the 6 inch header from the hot drain system service ring to the drain trench on the Rx building -25 foot elevation. The pipe section has one 90 degree along its 45 foot length.

EP 1.41 was surveyed IAW Procedure

  1. BSYLVS-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 45 survey measurements.

Surfixe 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 65,655 cm2 (6.6 m2) for the entire length of (approximately 45') 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 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 1.41 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 FSS Design # EP 1.41 Revision # Original 5.5 Statistical Summary Table Page 3 of 3 Statistical Parameter Total Number of Survey Measurements Number of Measurements

>MOC Number of Measurements Above 50% of DCGL 45 44 0 Number of Measurements Above DCGL lol Standard Deviation Maximum I Mean Io.0192 I 0.0126 0.0876 I Median 10.0172 1 6.0 7.0 Documentation of evaluations pertaining io compliance with the unrestricted use limit of 25 mrdyr 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 1.41 to be less than 1 mredyr. The dose contribution is estimated to be 0.01 9 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 - EP 1.41 SURR & Spreadsheet Disc SECTION 7 ATTACHlMENT 1 3 PAGEIS)

Pipe ID 1.44 Survey Location Survey Date 02-Apr-07 2350-1 # Survey Time 13:27 Detector-Sled

  1. I I Quad B Trench Drain 189094 lMG1 LVS-11107 rpipesh. I Number of Measurements

>MDC Number of Measurements Above 50% DCGL Number of Measurements Above DCGL Mean 6" II 44 0 0 0.01 92 Detector Efficiency Median 1 0.00038 0.01 72 DCGL (dpnn-1 2.41 E95 1459 Field BKG-) 3.6 Maximum I Routinesurvey I 0.0876 X II Minimum I 9.5 0.0086 I I NOT BACKGROUND CORRECTED D& 7d3-07 RP Engineer I Date EP 1.41 6" Pipe TBD 06-004 Group 2 114 145 114 104 125 109 135 73 73 109 114 88 83 140 -- gcpm ncpm 3 0.01 1 0.01 1 0.016 0.017 0.013 0.01 3 0.021 0.018 0.016 0.016 0.009 0.009 0.023 0.013 0.015 0.016 - --- C0-60 activlty C0-60 activity (total dpm) (dpml100cm2)

Cs-137 activity (dpmlIOOcm2) 1,496 2,245 1,683 1,309 2,151 2,058 2,899 2,245 1,871 2,058 2,619 2,058 - 1,871 2,245 1,964 2,434 1,305 1,305 1 ,w 2,052 1,59( 1,4% 2,52! 2,15' _- _- ~__~ _- -_ _- ____~ _- Eu-152 acUvity (dpmlIOOcm2) 24 36 27 21 34 33 46 36 30 33 42 33 30 36 31 39 21 21 -~ 3 3 25 24 4c 34 31 3( 1* I It ~~ Eu-I 54 activity (dpd100cm2) 17 25 19 15 24 __ 23 33 25 21 - _- 23 30 23 21 25 22 27 - - _- ~~ _- 15 15 - 22 23 ia 17 25 24 I 1: Nb-94 aetivity (dpmll OOcm2) 1 2 2 1 2 2 3 2 2 2 2 2 2 2 2 2 1 _____- 1 2 2 ~ 1 1 4 4 ~~ c 1 L Ag-108111 activity (dpmll OOcm2) 83 125 93 73 119 _- 114 161 125 104 3 156 1 83 45 3; 24 1; I - 28 20 1 2 99 30 21 1 2 104 1 0.01 3 1 of2 SECTION 7 ATTACHMENT 2 3 PAGE(S)

BSVLVSPipeCrawler-002 Revision 4 Pipe Interior Radiological Survey Form Date: 4/2/07 Time: 1327 Access Point Area: 7pElUCt-l QUM /&- !h System: Pipe ID#: 114 I Pipe Diameter:

6 Building:

a Elevation:

-27' Finalsurvey x Other / cs Type of Survey Investigation Gross Co60 Detector ID# I Sled ID# (flG / LVS- / 11 Detector Cal Date: ,/ti /07 Detector Cal Due Date: t/rr/o8 z3~0-f Instrument ID #: / s90 ?+ Instrument Cal Date: lfi, /07 Instrument Cal Due Date: h/O& I Instrument:

From the Daily Pipe Survey Detector Control Form for the Selected Detector Background Value 3.6 cpm MDCRStiltiC 485 cpm Efficiency Factor for Pipe Diameter

~fDC,tatlc ZDbb dpd cm' Is the IbCstahc acceptable?

a No (ifno, adjust sample count time and recalculate MDCR,) 0, 0 0 03 % (from detector efficiency determination)

Technician Signature Pipe Interior Radiological Survey 3 Package Page 1 of- Attachment 3, Page 1 REFERENCE COPY BSI/LVSPipeCrawler-O02 Revision 4 Pipe Interior Radiological Survey Form (Continuation Form) Pipe lbneter: 6 ' , Access Point Area: 7'flEIVc-d QUAD R &-o w Elevation:

-27 System: Pipe ID#: Building:

Date: Pipe ID#: Building:

'? I- REFERENCE COPY a Package Page - 2 of 2 Attachment 3, Page 2

I I SECTION 7 ATTACHMENT 3 PAGE(S)

DQA Check Sheet Design # I EP 1.41 I Revision # I Original I Survey Unit # 1 EP 1.41 - ~ ~ ~~~ -~ ~ Preliminary Data Review' Answers to the following questions should be fully documented in the Survey Unit Release Record 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. Was the instrumentation MDC for structure Scan measurements, soil Scan measurements, and static measurements or soil samples addressed in the survey design?

Yes No N,A 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 Was the instrumentation MDC for volumetric measurements and smear analysis < 10% DCGLW ? X X X 5. 3. 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?

3. X X Were "Special Methods" for data collection properly applied for the survey unit under review? ~ ~ X 3. Is the data set comprised of qualified measurement resub dMed in accordance with the survey design, which accurately reflects the radiological status of the facillty3 Graphical Data Review 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?

X X Data Analysls 1. Are all sample measurements below the DCGLW (Class 1 8 2), or 0.5 DCGLw (Class 3)? 2. Is the mean of the sample data

< DCGLw? X 3. If elevated areas have been identified by scans andor sampling, is the average activity in each elevated area 4. Is the result of the Elevated Measurements Test 1 .O? X X X DCGLEMC (Class l), < DCGLW (Class 2), or e0.5 DCGLW (Class 3)? 5. 2omments:

Is the result of the statistical test (S+ for Sign Test or W, for WRS Test) 2 the critical value? I ~ X Form Rev 0 CS-091'2 Page 1 of I SECTION 7 ATTACHMENT 4 1 DISC Survey Unit Release Record EP-1.43 Design # Survey Unit #(s) Revision # Original Page 1 of 3 Description I 1) Embedded Pipe (EP) Survey Unit 1.43 meets the definition of embedded pipe for Plum Brook Reactor Facility (PBRF). 2) EP 1.43 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 1.43 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 BSVLVS-002, WEP 05-006, these determinations are appropriate for the types of radiation involved and the media being surveyed.

Approval Signatures I Date: 1 FSS/CharacteMonEngineer I ,q, / I 74-07 FSS/Charactdzation Manager cs-o9/1 0 COPY

- FSS Design # EP 1.43 Survey Unit: 1.43 Revision # Original Page 2 of 3 1.0 2.0 3.0 4.0 5.0 Hi story/Description 1.1 1.2 Survey Design Information 2.1 2.2 The subject pipe system is the 6 inch return header from the cooling water service ring to the drain trench on the Rx building -25 foot elevation.

A vertical 90 degree elbow is 34 feet into the pipe section. The pipe is approximately 47 feet in length. EP 1.43 was surveyed IAW Procedure

  1. 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 47 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 68,573 cm2 (6.9 m2) for the entire length of (approximately 47') of 6" 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 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 inredyr 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 1.43 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 1.43 Revision # Original 5.5 Statistical Summary Table Page 3 of 3 I Statistical P ammeter - Total Number of Survey Measurements 47 Number of Measurements

>MDC 47 1 Pipe Number of Measurements Above 50% of DCGL Number of Measurements Above DCGL Mean 0 0 0.0177 Median Standard Deviation Maximum Minimum 0.0172 0.0041 0.0258 0.0094 6.0 7.0 Documentation of evaluations pertaining to compliance with the unrestricted use limit of 25 llzfemjyT 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 1.43 to be less than 1 mredyr. The dose contribution is estimated to be 0.01 8 mredyr based on the average of the actual 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 1.43 & Spreadsheet Disc

_- I SECTION 7 ATTACHMENT 1 3 PAGE@)

i Survey Date ai&@ -_ - BSI EPIBP SURVEY REPORT 02-Apr-07 I 1 Pipe ID I .43 Survey Location I Trench Service Ring I II I I I1 I II L I 2350-1 # Total Number of Survey Measurements Number of Measurements

  • MDC Number of Measurements Above 50% DCGL Number of Measurements Above DCGL Mean Median Standard Deviation 189094 47 47 0 0 0.0177 0.01 72 0.0041 Detector-skd
  1. 1MGl LVS-VI07 PipeSke I I 6 II Debector Efficiency O.OOO38 ~~ 1 0.0258 Maximum Minimum 0.0094 Stodc Survey Technician(8)

ZOMMENTS:

9CTMTY VALUES NOT BACKGROUND CORRECTED RP Engineer I Date 1 BCpu ?-/Po7 EP 1.43 6" Pipe TBD 06-004 Group 2 gcpm ncpm 28 28 20 20 27 2a 26 2e 27 20 25 25 20 2c ____ -_ __- Lo- 15 15 1E 17 17 19 1: 18 1E 23 2: 1E 19 22 22 22 22 29 2s 31 31 18 1E 12 1; 3: 33 25 2: 22 2: 30 3( 24 2r 27 2; 2! 29 21 2' 17 1; -- __ - ~. . ___ ____ ~__ - ~~ 71 1053 52,632 65,789 52,632 68,421 52,632 39,474 39,474 44,737 50,000 47,368 60,526 50,066 57,895 57,895 76,316 81,579 47,368 31,579 86,842 65,789 57,895 78,947 63,158 71,053 76,316 55,263 44,737 65,789 60.526 COM) activity Cs-137 activity (dpmll OOcm2) (dpmll OOcm2) 5,050 2,619 - 3,607 1,871 - 4,870 - 2,525 1,871 3,607 - 4,509 2 , 338 3,607 1,871 4,690 - 2,432 3.607 1.871 _____ _-___ - 3.427 1.777 2,151 1.777 .- - 3,968 2,058 - 3,968 2,058 - 5@!-. 2,712 - 5,591 2,899 3,247 1,683 1,122 2,164 - - 5952 3,086 - 4,509 2,338 3,968 2,058 2,806 4,329 - 2,245 - 4,870 2,525 5,231 2,712 3,066 1,590 - 4,509 2,338 4,148 2,151 ___ - 5,411 - - - 3,788 1,964 Eu-1 I2 activity Eu-I 64 activity (dpm1100cm2) (dpm1100cm2) 42 I 30 - 21 30 40 29 30 21 - __ 37 26 21 30 39 27 21 30 22 16 22 16 - - 25 18 27 19 -. 28 26 -. - 34 24 20 28 33 23 23 33 31 43 33 46 27 19 13 18 35 49 37 26 33 23 45 32 - __ __ __ ~- - - -. 36 25 40 29 43 31 NbQ4 activity Ag-1 O8m activity (dpm1100cm2) (dpml100crn2) 2 145 2 104 2 135 2 104 1 78 , 1 78 1 88 2 99 2 93 2 119 2 99 2 114 2 114 3 151 3 161 2 93 1 62 3 171 2 130 2 114 2 125 2 140 3 151 2 106 1 8E 3- 156 unw - 0.02; 0.01C 0.02' 0.OlC 0.02( O.Olf 0.02( O.Olf 0.01:

0.01: 0.01: O.Ol! O.OlA 0.011 O.Ot! 0.01; 0.01: 0.02: 0.024 0.014 O.OO! 0.02( 0.021 0.01' 0.02: O.Ol! 0.02 0.02: 0.011 0.01 0.021 0.011 - 1 of2 EP 1.43 6" Pipe TBD 06-004 Group 2

  • E e! z z E 3 00 33 34 - 35 36 -37 I QcPm 14 14 23 23 29 25 22 22 22 22 _~ ___ ncpm CdK) activlty (dpm1100cm2)

Cs-137 activity (dpm1100cm2) 2; 1 2 3 2 2 2 3 2 2 1 3 2 2 2 1 36,842 _- 60,526 - 76,316 57,895 57,895 50,000 76,316 50,000 71,053 36,842 84,211 73,684 63,158 57,895 42,105 73 119 151 114 99 151 99 140 73 166 145 125 114 83 114 4.148 ~ ____-. 5,231 3,968 _____ 2,712 2,058 ___- +--- 3,968 3,427 3,427 4,870 2,525 ____- ____- 5,231 -___- I---+- 2,058 1,777 2,712 1,777 2,525 1,309 ____ .~ __--- Eu-I 52 actlvlty 5,772 5,050 _____ 4,329 3,968 2,886 - .. 2,993 2,619 2,245 2,058 1,496 ____ - __ 21 34 43 33 33 28 43 28 40 48 42 36 33 24 Eu-164 activity (dpm1100cm2) 15 24 31 23 23 20 31 20 29 15 - 34 30 25 23 17 (dpm1100cm2) (dpn1100crnZ)

Nb-gq- I AQ-108m- MEAN MEDIAN STD DEV MAX IMIN - Unity 7 0.01' 0.01I 0.02: 0.01; 0.01; 0.01! 0.02: 0.01! 0.02' 0.01' 0.02! 0.02: 0.01! 0.01' 0.01: 0.01 I 0.01' 0.00 0.021 0.00 __- - 20f2 SECTION 7 ATTACHMENT 2 4 PAGE(S)

I) 1 BSVLVSPipeCrawler-002 Revision 4 Pipe Interior Radiological Survey Form U 4(2/07 Time: a0 I443 Pipe Diameter: Access Point Area:

Elevation:

-27' System: Date: Pipe ID#: Building:

Type of Survey Investigation Characterization Final Survey A, Other v Gross C06O V cs Detector ID# / Sled ID# /w,/ l-vs c 1 I io7 Detector Cal Date: L&,167 Detector Cal Due Date:

Ill1 lo6 Instrument Cal Date:

1/11 103 Instrument Cal Due Date: I If ok Instrument:

23m-/ Instrument ID #: /gq 69 4- I 1 From the Daily Pipe Survey Detector Control Form for the Selected Detector Background Value 3a 6 cpm Efficiency Factor for Pipe Diameter MD C% tahc 9s cpm 0 I 0 0038 (from detector efficiency determination) mcstatic 7% CP dpd \ cm2 Is the MDCSahc acceptable? ,a No (if no, adjust sample count time and recalculate MDC%,,J Comments:

Pipe Interior Radiological Survey REFERENCE COPY 0 Package Page 1 of& Attachment 3, Page 1 I Pipe Interior Radiological Survey Form (Continuation Form) I BWLVSPipeCrawler-002 Revision 4 Package Page z of - Ll REFERENCE COPY Attachment 3, Page 2 BSYLVSPipeCrawler-002 Revision 4 Pipe Interior Radiological Survey Form (Continuation Form) Date: +/z/a7 Pipe ID#: I t43 Pipe Diameter:

6 " Access Point Area:

e Y REFERENCECOPY U Package Page 3 - of$ Attachment 3, Page 2

I SECTION 7 ATTACHMENT 3 I PAGE(S)

Design # EP 1.43 Preliminary Data Revlew' Revision # Original Survey Unit # EP 1.43 4. Was the instrumentation MDC for structure scan measurements, soil scan measurements, and embeddediburied 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 ? Answers to the following questions should be fully documented in the Survey Unlt Release Record Yes No -~ 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 beina surveved?

X N/A 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. Is the instrumentation MDC for embeddediburied piping static measurements below the DCGLw 7 Have surveys been performed in accordance with survey instructions in the Survey Design?

x X X ~~ ~ 8. 9. Were 'Special Methods" for data collection properfy 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 X Page 1 of 1 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 ~~ 1. 2. 3. if elevated areas have been identified by sans andlor sampling, is the average activity in each elevated area 4. Is the result of the Elevated Measurements Test 1 .O? Are all sample measurements below the DCGLw (Class 1 81 2), or 0.5 DCGLW (Class 3)? Is the mean of the sample data < DCGLw? DCGLutc (Class l), DCGLW (Class 2), or ~0.5 DCGLw (Class 317 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? X SECTION 7 ATTACHMENT 4 1 DISC I I Survey Unit Release Record Design # Survey Unit #(s) Description EP 1.93 1 Revision#

I Original I Page 1 of 3 1.93 1) Embedded Pipe (EP) Survey Unit 1.93 meets the definition of embedded pipe for Plum Brook Reactor Facility (PBRF). 2) EP 1.93 is a Class 1, Group 3.2 survey unit as per the PBRF Final Status Survey Plan (FSSP) and Technical Basis Document (TBD)-06-004.

3) Surveys in EP 1.93 were performed using a scintillation detector optimized to measure gamma energies representative of Cs-137. Sample
  1. EP 3-1 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. Approval Signatures I nata. - I -e.-. -- Form cs-o9/1 Rev 0 0 COPY FSS Design # EP 1.93 Revision # Original I Survey Unit: 1.93 I Page 2 of 3 1.0 2.0 3.0 4.0 5.0 HistoryLDescription 1.1 The subject pipe is a drain system overflow pipe servicing the Hot Dry Storage (HDS) pit in the Hot Lab. The header runs fiom the northwest side of the HDS pit to the valve pit on the -25 ft elevation of the Hot Lab.

EP 1.93 consists of 3" diameter piping that is approximately 24 feet in length. 1.2 Survey Design Information 2.1 2.2 EP 1.93 was surveyed IAW Procedure #BSYLVS-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 24 survey measurements. Surface area for the 3" ID piping is 486 cm2 for each foot of piping, corresponding to a total 3" ID piping surface area of 1 7,5 12 cm2 ( 1.8 m2) for the entire length of (approximately 24') 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 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 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 1.93 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 1.93 Revision # Original 6.0 7.0 Page 3 of 3 5.5 Statistical Summary Table Number of Measurements

>MDC Number of Measurements Above 50% of DCGL 3 Pipe Statistical Parameter 12 0 I Total Number of Survey Measurements I 24 Mean Median Standard Deviation Maximum 0.0020 0.0019 0.0007 0.0034 1 Number of Measurements Above DCGL lo1 I Io.0009 Minimum Documentation of evaluations pertaining to compliance with the unrestricted use limit of 25 mdyr 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 1.93 to be less than 1 mredyr. The dose contribution is estimated to be 0.002 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 - EP 1.93 SURR & Spreadsheet Disc SECTION 7 ATTACHMENT 1 7 PAGE(S)

I- Pipe ID EP 1.93 Survey Location Survey Date 16-W-06 23!500-1#

BSI EP/BP SURVEY REPORT HDS riser -25' 203488 L Median 0.0019 Standard Deviation 0.0007 Maximum 0.0034 Minimum o.Ooo9 STOCK Survey Technician(s)

Survey Time I - Measured Nuclide CS-1 37 Area FactorEMC Used No MREWR Contribution el PasslFaii FSS Pass COMMENTS:

ACTIVITY VALUES NOT BACKGROUND CORRECTED.

DetectorSkd

  1. 44-159 #238369/101 I r Survey Unit Classifcation 1 TBD 06-004 Piping Group 3.2 SR-I3 Radionudie Distribution Sample EP 3-1 1 o&' 7-13-07 RP Engineer I Date EP 1.93 3" Pipe TBD 06-004 Group 3.2 Nb-94 activity (dpmll OOcm2) Ag-lO&n activity (dpmllOOcm2)

CAO activity (dpml100cm2)

Cb137 activity (dpml100cm2)

Eu-164 activity ld~m/lOOcm2)

Unity - 0.00; 0.001 0.001 0.00; 0.00: 0.00: 0.00' 0.00: 0.00: 0.00: 0.00' 0.00' 0.00: 0.00: 0.00' 0.00: 0.00: 0.00: 0.00' 0.00: 0.00: 0.00: 0.00: 0.00: -~ ~. .. 273 214 1 56 __ - 17 14 2,492 1,958 .__ 1,424 2,136 2.136 ._.____ 10 15 15 21 ____-~ 234 234 12 331 214 292 ______ 3,026 1,958 2,670 2,670 2,314 1,958 1,602 3,382 3,560 1,246 4.272 .__ ____--- __ 22,078 14.286 14 19 19 -~ - 15 19:481 15 19,481 13 16,883 11 14,286 9 - 1 1,688 19 24,675 20 25,974 7 9,091 24 31,169 25,974 12 15,584 lo 12,987 15 19,481 19 24,675 18 23,377 26 33,766 23 29,870 ___ ~- ___- _- 20 2 2 214 175 -__- -_ 16 14 11 24 25 9 30 25 15 12 19 24 22 32 29 __ - - 370 390 13 46 390 _______ __ 3,560 2.136 234 195 292 - __ ____-__ 1,780 2,670 3,382 3,204 4,628 4.094 ~__- 370 351 - 507 448 MEAN MEDIAN - STD DEV MAX MIN _- __ -- 1of1 SECTION 7 ATTACHMENT 2 -3 PAGE(S)

BSYLVSPipeCrawler-002 Revision 4 Date: Pipe ID#: Building:

Pipe Interior Radiological Survey Form ~O/I c/, 6 Time: 0344 - Access Point Area:

/&,r 13~ 9 . 5m@e Pipe Diameter:

7 I1 RI s wbf- c. k: ;,q+~ Elevation:

.. 1 System: Type of Survey Investigation Characterization Final Survey Gross C060 cs 1/ 69 1 fDf ' 23 83 7 Detector ID## / Sled ID# 44 /W - Detector Cal Date: 9/5!&7 L Detector Cal Due Date:

9/s/4 7 Instrument:

Z3m-/ Instrument ID #: &?+W Instrument Cal Date: 7Id06 Instrument Cal Due Date:

7/ s/o 7 From the Daily Pipe Survey Detector Control Form for the Selected Detector Backgroundvalue Ge4 cpm MDCRstatic I/. 7 cpm Efficiency Factor for Pipe Diameter MDCtatIC 'z-lo b 0 \aD cm2 Comments:

rys- I/ 0 ,mO? 7 (from detector efficiency determination)

T .-i I -7 1 .I ,. -Lstahc d- bM (u count time ana recdcuiate MUCG,) Technician Signature Pipe Interior Radiological Survey REFERENCECOPY 0 Package Page 1 om - Attachment 3, Page 1 BSVLVSPipeCrawler-002 Revision 4 Pipe Interior Radiological Survey Form (Continuation Form) Date: 4 3 Access Point Area:

& r Dpq cmmg System: El s 6R Pipe ID#: to// t /a 6 Pipe Diameter:

3l Building:

A )4l,n Elevation:

-2 5' Package Page 3f 3 REFERENCECOPY 0 Attachment 3, Page 2

I SECTION 7 ATTACHMENT 3

Design # EP 1.93 Revision # Yes Answers to the following questions should be fully documented in the Survey Unit Release Record Original Survey Unit # 4. 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 ? EP 1.93 6. Were the MDCs and assumptions used to develop them appropriate for the instruments and techniques used to perform the survey? I 1. 2. 3. 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? Is the instrumentation MDC for embeddedlburied piping static measurements below the DCGLw ? lx 7. Were the survey methods used to collect data proper for the types of radiation involved and for the media beinn surveyed?

X X ~ 8. 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 facilrty?

I X X I ~~~~ ~ ~ ~ ~~ ~ 2. 3. Has a histogram (or other frequency plot) been created? Have other graphical data tools been created to assist in analyzing the data?

1. Has a posting plot been created?

I I lx X X 1. Are all sample measurements below the DCGLW (Class 1 8 2), or 0.5 DCGLw (Class 3)? 2. Is the mean of the sample data DCGLw? - Data Analysis X X 3. If elevated areas have been identified by scans andlor sampling, is the average activity in each 4. Is the result of the Elevated Measurements Test < 1 .O? 5. Is the result of the statistical test (S+ for Sign Test or W, for WRS Test) 2 the critical value? X X X --- FSS/ Characterization Manager (prinUsign)

I I Date 17/zJ-f& I Page 1 of 1 Form cs-0912 Rev 0 SECTION 7 ATTACHMENT 4 1 DISC Survey Unit Release Record ~~~~~ EP HPT-I 02 Design # ~ ~ ~ ~ ~ ~~

Revision # Original Page 1 of 3 Survey Unit #(s) Description

2) EP HPT-102 is a Class 1, Group 3.2 survey unit as per the PBRF Final Status Survey Plan (FSSP) and Technical Basis Document (TBD)-06-004.
3) Surveys in EP HPT- 102 were performed using a scintillation detector optimized to measure gamma energies representative of Cs-137. Sample #EP 3-1 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 BSVLVS-002, WEP 05-006, these determinations are appropriate for the types of radiation involved and the media being surveyed.

0 COPY FSS Design # EP HPT-I 02 1 .o 2.0 3.0 4.0 5.0 Revision # Original Page 2 of 3 HistoryDescription 1.1 The subject pipe is part of the the 2" drain line for the 24" Rx Coolant return loop piping. The function of this piping was to convey water from the coolant loop to the sump in the sub pile mom corridor on the -47. EP HPT-102 consists of 4" diameter piping that is approximately 23 feet in length. 1.2 Survey Design Information 2.1 2.2 EP HPT-102 was surveyed IAW Procedure

  1. 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 23 survey measurements. Surface area for the 4" ID piping is 486 cm2 for each foot of piping, corresponding to a total 4" ID piping surface area of 18,971 cm2 (1.9 m2) for the entire length of (approximately 23') of 4" 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 Investigations/Results 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 Level (DCGL) for radionuclide specific EP that corresponds to the 1 mrem/yr 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 HPT-102 passes FSS. Background was not subtracted from the survey measurements and the Elevated Measurement Comparison (EMC) was not employed for this survey unit.

I 1 I Total Number of Survey Measurements Number of Measurements NDC 1 FSS Design # EP HPT-102 I Revision # Ori@ I Page3of3 I 23 14 Survey Unit:

HPT- 102 -~ Number of Measurements Above DCGL 0 Mean 0.0017 5.5 Statistical Summary Table Statistical Parameter 1 Pipe 1 Number of Measurements Above 50% of DCGL 1 0 I Median 1 0.0017 I Standard Deviation 10.0007 I Maximum 10.0037 I Minimum I 0.0006 6.0 7.0 Documentation of evaluations pertaining io compliance with the unrestricted use limit of 25 mrdyr 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 HPT-102 to be less than 1 mredyr. The dose contribution is estimated to be 0.002 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 - EP HPT 102 SURR & Spreadsheet Disc SECTION 7 ATTACHMENT 1 2 PAGE(S)

I Total Number of Survey Measurements Number of Measurements

>MDC Number of Measurements Above 50% DCGL Number of Measurements Above DCGL Mean Median Standard Deviation Maximum Minimum .- .. - BSI EP/BP SURVEY REPORT 23 14 0 0 0.0017 0.0017 0.0007 0.0037 O.OOO6 I PipeID I HPTIO2 I I TBD 06-004 Piping Group SR-13 Radionudie Distribution Sample Measured Nuclide Area FactarEMC Used Survey Loution 3.2 EP 3-1 1 cs-137 Nn I Valve Pit fkmr drains ~~ PasdFail FSS Pass MREWR Contribution

<l I I 2350-1 I 203488 Survey Time I DetectorSkd

  1. 44-1 59 #238369/101 0.00071 Pipe Size 4 Detector EfRckncy WGL iwooant) 3.79E+06 9.--4--(kCnll) 973 m4 2.2 Fkld BKG (qn) 5 -*rrLrOrpm(.dw Routine Survev X Field MDCRccai 10.7 I COMMENTS:

ACTIVITY VALUES NOT BACKGROUND CORRECTED. RP Engineer I Date "A HPT 102 4" Pipe TBD 06-004 Group 3.2 Eu-I52 activity (dpm1100cm2) - UnW - 0.002 0.001 0.002 0.002 0.001 0.001 0.002 0.002 0.002 0.002 0.002 0.001 0.001 0.001 0.002 0.001 0.002 0.001 0.001 0.001 0.002 0.004 0.00: -. ELI-I54 activity Nb-94 activity Ag-108m activity (dpm1100cm2) (dpm/100cm2) (dpm1100cm2) at UI s I Co60actlvity 1 Co-60activity 1 Cs-137activity (total dpm) (dpmllOOcm2) (dpm1100cmZ) ncpm 238 1 15 15 21,127 2,172 - 2 13 - 13 18,310 1,882 206 - 3 16 16~- 2233L-.- ____ 2,316 - 254 4 20 20 28.169 2.895 31 7 ___ ~- 5 11 11 15:493 6 6 6 8,451 7 16 16 22,535 9 18 18 25,352 2,606

-___ 285 - ~_ ~ 8 -~ 17 17 23,944 2,461 - 10 _~___ -16 16 22,535 2,316 11 15 15 21,127 2,172 12 11 11 15,493 16 16 22,535 254 -I -I - -I 15 I -I 222 2.606 285 ._______ 25.352 __ - __ 18 8 8 1 1,268 - 19 14 14 19,718 20 11 11 15,493 1,592 21 19 19 26,761 22 35 35 49,296 555 23 31 31 43.662 4.488 492 ~- -I 11 I -I -I -I - 0.00; 0.00; 0.001 0.004 0.001 - 1 of 1 L SECTION 7 ATTACHMENT 2 3 PAGE(S)

I I BSIILVSPipeCrawler-002 Revision 4 Pipe Interior Radiological Survey Form Date: Time: /$y% *I )spr 1 Access Point Area:

y# LVE i?j - I System: Pipe ID#: 0 2 Pipe Diameter:

Building:

'.& L&E Elevation:

-25 Type of Survey Investigation Characterization FinalSurvey x Other 4 GrOSS C060 cs 2L-d.- Detector ID# / Sled ID# - /s9 Z% &369 I 10 1 7 Detector Cal Date: 9/S/OG Detector Cal Due Date: ?/ 5.h 7 Instrument:

7-3 TO -1 Instrument ID #: 34Er Instrument Cal Date: t/Sh b Instrument Cal Due Date: 7[r /a 7 From the Daily Pipe Survey Detector Control Form for the Selected Detector Background Value ,q P cpm Efficiency Factor for Pipe Diameter 0.0 00 7 I mcsta,c 'Z\ G 5 dpd 100 cm2 MDCLtic /O I 7 CP~ (from detector efficiency determination)

Technician Signature Pipe Interior Radiological Survey REFERENCE COPY 0 Package Page 1 oa Attachment 3, Page 1 I I BSYLVSPipeCrawler-002 Revision 4 Pipe Interior Radiological Survey Form (Continuation Form) Access Point Area:

V*VE Pl r Building: Elevation:

  • zr System: PLF oe.u I CF- I' Date: !$/ 8/46 Pipe ID#: ~d Pipe Diameter:

S*iX/ICEY th'C. REFERENCE COPY a Package Page 7 of 5 Attachment 3, Page 2

SECTION 7 ATTACHMENT 3 I PAGE(S)

DQA Check Sheet Design # HPT 102 Revision # Original Survey Unit # HPT 102 Preliminary Data Review' Yes No NIA Answers to the following questions should be fully documented in the Survey Unit Release Record 1. 2. 3. Have surveys been performed in accordance with survey instructions in the Survey Design? X X 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 embeddedlburied 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? embeddedlburied 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. 1x1 I 6 Were the MDCs and assumptions used to develop them appropriate for the instruments and techniques used to wrform the survev?

7. Were the survey methods used to collect data proper for the types of radiation involved and for the media beina surveyed?

~~ 8. B. 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 facillty3 Graphical Data Review 1. Has a posting plot been created? I I 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? X X Data Analysis ~~ 1. Are all sample measurements below the DCGLw (Class 1 8 2), or 0.5 DCGLw (Class 3)? X 2. Is the mean of the sample data DCGLW?

X X X 3. 4. If elevated areas have been identified by sans and/or sampling, is the average activity in each elevated area c DCGL- (Class l), Is the result of the Elevated Measurements Test c 1 .O? DCGLw (Class 2), or <0.5 DCGLw (Class 3)? ~~ ~ 5. Comments:

Is the result of the statistical test (S+ for Sign Test or Wr for WRS Test) 2 the critical value? X Date 7434'7 FSSl Characterization Manager (printlsign)

R. Case Date 7/23~0-7 F SS/Characterization Engineer (printlsign)

I I Page 1 of 1 SECTION 7 ATTACHMENT 4 1 DISC Design # EP-RX 139 Survey Unit #(s) Revision # Original Page 1 of 3 Description FSS/Characterization Engineer hddt/7/1 Rx 139 1) Embedded Pipe (EP) Survey Unit Rx 139 meets the definition of embedded pipe for Plum Brook Reactor Facility (PBRF). FSS/Characterization Manager

2) EP Rx 139 is a Class 1, Group 1 survey unit as per the PBRF Final Status Survey Plan (FSSP) and Technical Basis Document (TBD)-06-004. ,J .case 7LJd97 3) Surveys in EP Rx 139 were performed using a scintillation detector opthized 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) Instnunent 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 I //rY / V-7/fAdA/r - I /b-D7 Technical Reviewer (FSS/Characterization Engineer) - v- 0 COPY cs-o9/ 1 El FSS Design # EP Rx 139 Revision # Original 1.0 2.0 3.0 4.0 5.0 Page 2 of 3 HistoryiDescription 1.1 The subject pipe is the drain line from the Rx tank penetration on the Rx Building -8 foot elevation. . EP Rx 139 consists of 1" diameter piping that is approximately 4 feet in length. 1.2 Survey Design Information 2.1 2.2 EP Rx 139 was surveyed IAW Procedure

  1. BSI/LVS-002.

100% of the 1" ID pipe was accessible for survey. The accessible 1" ID pipe was surveyed by static measurement at one foot increments, for a total of 4 survey measurements.

Surface area for the 1" ID piping is 243 cm2 for each foot of iping, corresponding to a total 1" ID piping surface area of 973 cm (0.1 m2) for the entire length of (approximately 4') of 1" 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 5.3 5.4 Data assessment results are provided in the EPBuried Pipe (BP) Swey 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 medyr 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 139 passes FSS. Background was not subtracted from the survey measurements and the Elevated Measurement Comparison (EMC) was not employed for this survey unit.

I FSS Design ## EP Rx 139 I Revision ## Original 1 Page3 of3 1 Number of Measurements

>MDC Number of Measurements Above 50% of DCGL 1 Survey Unit: Rx 139 I 4 0 6.0 7.0 Number of Measurements Above DCGL Mean Median Standard Deviation Maximum Minimum 5.5 Statistical Summary Table 0 0.1247 0.1 165 0.0335 0.1717 0.0940 1" Pipe Statistical Parameter I Total Number of Survey Measurements I41 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 139 to be less than 1 mredyr. The dose contribution is estimated to be 0.125 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 - SURR EP RX 139 & Spreadsheet Disc SECTION 7 ATTACHMENT 1 Z PAGE(S)

I c Number of Measurements Above DCGL 0 Mean 0.1247 Median 0.1165 Standard Deviation 0.0335 I 1 I I 0.0940 Minimum I STOCK Survey Technician(s)

BSI EP/BP SURVEY REPORT .- I SR-13 Radionudi Distribution Sample EP 3-1 Measured Nudi CO-60 PasdFail FSS Pass Area FadorlEMC Used No MREMNR Contriin 4 1-- ~- Maximum I 0.1717 I I COMMENTS:

ACTMTY VALUES NOT BACKGROUND CORRECTED 7-13 -U RP Engineer I Date 711 32007

- 60'0 !P !Z :Z )E wdau :L1'0 *0'0 II C'O ZP P LZ E EZ 2 OE C H 0 i! urd38 3

  • ZC'O :LC'O IC C'O 60'0 :zc*o - - 4wn - 102 62 1 01 C EEL 929 9 18 18L'8Z 209'81 19L'SC 8ss'oz 000'OL OOO'SP **E '8E 000'09 I SECTION 7 ATTACHMENT 2 I PAGE(S)

BSILVSPipeCrawler-002 Revision 4 Pipe Interior Radiological Survey Form 1230 Date: 2fZZ ,/07 Time: c Rc IfWK Pipe Diameter:

1 bo " Access Point Area: I System: Pipe ID#: Rc ,139 Building:

LV Elevation: - "; Type of Survey Investigation Characterization Final Survey Gross C06O t/ cs No 5LED &- Detector ID# I Sled ID# FO//. YL -% 0047 I Detector Cal Date: 1/11 117 Detector Cal Due Date: 1 /I//o Y IC 18409+ Instrument Cal Date: 07 bZZ:Ee:ate:

I /I I /.u Instrument

From the Daily Pipe Survey Detector Control Form for the Selected Detector BackgroundValue 7.7 cpm MDcRstatlc Iz, 5 CPm Efficiency Factor for Pipe Diameter MDcstatlc b/OW dPd /OD cm2 0, 0 030 6 (from detector efficiency determination) m I:,btatIc YO sample c Ount me and recalculate MDCK, ) ntu Technician Signature I Pipe Interior Radiological Survey Package Page 1 of1 Attachment 3, Page 1 I SECTION 7 ATTACHMENT 3 I PAGE(S)

I Yes X X X X X X I No NIA X X X DQA Check Sheet

1. Has a posting plot been created?

I - Design# I EP Rx 139 I Revision#

I Original I X EP Rx 139 ___~ 3. Have other graphical data tools been created to assist in analyzing the data? 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? X ~ 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? 1. Are all sample measurements below the DCGLw (Class 1 & 2), or 0.5 DCGLw (Class 3)? ~ 3. Is the instrumentation MDC for embeddedlburied piping statk measurements below the DCGLw ? 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 statii measurements or soil samples addressed in the sunrey design? 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 invoked and for the medii being surveyed?
8. 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 design. which accurately reflects the radidoaical status of the facilitv?
2. Has a histogram (or other frequency plot) been created?

I I Ix 2. Is the mean of the sample data c DCGLW? 3. If elevated areas have been identified by scans and/or sampling, is the average activity in each elevated area DCGLEMC (Class l), 4. Is the result of the Elevated Measurements Test

< 1 .O? DCGLw (Class 2), or ~0.5 DCGLw (Class 3)? j-' I I Ix 5. Is the result of the statistical test (S+ for Sign Test or W for WRS Test) 2 the critical value? Comments:

Page 1 of 1 CS-0912 El I SECTION 7 ATTACHMENT 4 1 DISC Survey Unit Release Record Design # Survey Unit #(s) Description EP-Rx 151 I Revision # I Original I Page 1 of 3 Rx 151 1) Embedded Pipe (EP) Survey Unit Rx 15 1 meets the definition of embedded pipe for Plum Brook Reactor Facility (PBRF). 2) EP Rx 15 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 15 1 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.

0 COPY CS-0911 1 1 FSS Design # EP Rx 151 1.0 2.0 3.0 4.0 5.0 Revision ## Original Page 2 of 3 HistoryDescription 1.1 1.2 Survey Design Information 2.1 2.2 The subject pipe system is the 3" Quad "B" spare DI water system line. EP Rx 15 1 consists of approximately 2 1 feet in length from the Reactor Building -25' elevation to Quad "B'. EP Rx 15 1 was surveyed IAW Procedure

  1. 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 729.7 cm2 for each foot of piping, corresponding to a total 3" ID piping surface area of 15,330 cm2 (1.5 m2) for the entire length of (21') of 3" piping.. 2.3 Survey Unit Measurement LOcationslData 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 mredy 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 15 1 passes FSS. Background was not subtracted f?om the survey measurements and the Elevated Measurement Comparison (EMC) was not employed for this survey unit.

5.3 5.4 t I 1 FSS Design # EP Rx 151 Survey Unit: Rx 151 Revision # Original Page 3 of 3 I - - Total Number of Survey Measurements Number of Measurements

>MDC 5.5 Statistical Summary Table 21 7 3" Pipe Statistical Parameter Median Standard Deviation 0.0098 0.0048 1 Number of Measurements Above 50% of DCGL I 0 Maximum Minimum I Number of Measurements Above DCGL Io 0.0199 0.0042 I Mean I0.0105 6.0 7.0 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 Rx 151 to be less than 1 rnredyr. The dose contribution is estimated to be 0.01 1 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 - EP RX 15 1 SURR & Spreadsheet Disc SECTION 7 ATTACHMENT 1 z PAGE(S) clai - ._ BSI EP/BP SURVEY REPORT DCGL ~spnnmau) 2.41 EM5 *- Routine Survey Survey Location Quad B Spare line 1 PipeID 1 Rx151 11 1 212223 Survey Date 13-De005 2350-1 # Pb.ClllncorpmdwD.Maemdnq(lnsllq 730 Field BKG (cpl) 5.2 Field MDCR (opn) 10.8 I Mean Median Standard Deviation I Survey Time I 08:24 /I 0.01 05 0.0098 0.0048 Detector-Sled

  1. I SR-13 Radionudie Distribution Sample EP 2-1 Measured Nudi C0-60 Pass/Feil FSS PaSS Area FactorlEMC Used No MREhWR Contribution 4 COMMENTS:

ACTIVITY VALUES NOT BACKGROUND CORRECTED I 44-62204402/101

!' I Pipesize 13" II Detector Efficiency 0.00014 I 0.0199 Maximum Minimum 0.0042 ROSENHAGEN Survey Technician(s) 7-/c/-D 7 RP Engineer 1 Date EP Rx 151 3" Pi pe TBD 06-004 Group 2 Unity 7 0.001 0.001 0.00 0.01 0.011 0.01 I 0.011 0.001 -~ ._ 1of1 SECTION 7 ATTACHMENT 2 3 PAGE(S)

Date: Building:

System: Pipe Interior Radiological Survey Form /2-i 3 Time: 0.232 Y a)< &w- Elevation: - 2)- Access Point Area: &d Pipe Diameter:

3 rf Pipe ID # ~~ Type of Survey Investigation Characterization c-2 Other rx Sled Size 3" inch Detector:

Yc/-crr- Detector ID #: ZUYO'2, Cal Date: //-I 7 - e.J- Cal Due Date:

,/ ag fnstrument:

7-3--- ( Instrument ID #: 3/zzZ3 .. - -* . . ~. -- .. -- - . -. , 0- ., .. -*._...... . c.-- - Cal Date: f/+f 7 - Lstr Cal Due Date:

0 d3= From the Daily Pipe Survey Detector Control Form for the Selected Detector BackgrouTld Value J-62 cpm MDCRtatlC

0. Cpm Efficiency Factor fo: Pipe Diameter 0- OV 0 14 (taken from MDCStatlC z IT42 dpdl OOcm2 Is the MDCStabc acceptable?

No (ifno, adjxSt sample count time and recalculate hDCR,,,) _- - Comments: Pipe Interior Radiological Survey Radiological Survey Commenced:

Date: / 2-1 3 The: a&. Y REFERENCE COPY 0 Package Page 1 of2 Attachment 3, Page 1 I /2-f 3 I I \ I i I REFERENCE COPY 0 Attachment 3, Page 2

SECTION 7 ATTACHMENT 3 I PAGE(S)

~ ~ DQA Check Sheet

-~ Design # EP Rx 151 ~~ -~ ~~ ~ Revision # Original Survey Unit # EP Rx 151 Yes Answers to the following questions should be fully documented In the Survey Unit Release Record 5. Were the MDCs and assumptions used to develop them appropriate for the instruments and techniques used to perform the survey?

No NIA 7. Were the survey methods used to collect data proper for the types of radiation involved and for the media being surveyed?

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. Is the instrumentation MDC for embeddedburied piping static measurements below the DCGLw ? Have surveys been performed in accordance with survey instructions in the Survey Design? X X X I. Has a posting plot been created?

I I Ix 0. 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? 5. Was the instrumentation MDC for volumetric measurements and smear analysis < 10% DCGLw ? X X Data Analysis 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 facility3 Were "Special Methods" for data collection properly applied for the survey unit under review? 1. Are all sample measurements below the DCGLw (Class 1 8 2), or 0.5 DCGLw (Class 3)? 1x1 I X 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? X X Y Page 1 of 1 ~ ~ ~ ~ ~~ ~~ ~~ ~ ~ 2. 3. 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 c 1 .O? Is the mean of the sample data < DCGLW? X DCGLEMC (Class l), c DCGLw (Class 2), or c0.5 DCGLw (Class 3)? El CS-0912 X X 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 .

Design # Survey Unit #(s) Description Survey Unit Release Record EP-Rx 162 I Revision#

I Original I Page 1 of 3 Rx 162 1) Embedded Pipe (EP) Survey Unit Rx 162 meets the definition of embedded pipe for Plum Brook Reactor Facility (PBRF).

2) EP Rx 162 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 162 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 acmrdance 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.

ipproval Signatures 0 COPY FSS Design # EP Rx 162 1.0 2.0 3.0 4.0 5.0 Revision # Original Page 2 of 3 I History#escription 1.1 1.2 Survey Design Information 2.1 2.2 The subject pipe is the drain line fiom the dry annulus inside the CV to the drain trench on the Rx Building -25 foot elevation.

EP Rx 162 consists of 2" diameter piping that is approximately 27 feet in length. EP Rx 162 was surveyed JAW Procedure

  1. BSVLVS-002.

100% of the 2" ID pipe was accessible for survey. The accessible 2" ID pipe was surveyed by static measurement at one foot increments, for a total of 27 survey measurements. Surface area for the 2" ID piping is 486 cm2 for each foot of piping, corresponding to a total 2" ID piping surface area of 13,134 cm2 (1.3 m2) for the entire length of (approximately 27') of 2" 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 162 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 5.4 Survey Unit:

Rx 162 +

FSS Design # EP Rx 162 Revision # 0rigma.I 1 Survey Unit: Rx 162 I Page 3 of 3 5.5 Statistical Summary Table Number of Measurements

>MDC Number of Measurements Above 50% of DCGL Statistical Pammeter 0 0 I Total Number of Survey Measurements I 27 I Mean Median 0.01 16 0.0094 I Number of Measurements Above DCGL lot Standard Deviation Maximum 0.0055 0.0259 r- ~~ Minimum 10.0024 1 6.0 7.0 Documentation of evaluations pertahhg to compliance with the unrestricted Use limit of 25 mrexdyr 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 162 to be less than 1 mredyr. The dose contribution is estimated to be 0.012 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 - EP RX 162 SURR & Spreadsheet Disc I SECTION 7 ATTACHMENT 1 3 PAGE(S)

BSI EPtBP SURVEY REPORT Pipe ID Rx 162 Survey Location 2350-1 # 1/26/06,1130/06, 26/06 i3 2/09/06 cv -2531. 212223,203488 0805,1250,1324 8 Detector-Sled

  1. 1 44-62/204402-121 ~~ ~ I 0.0259 Maximum Minimum 0.0024 ROSENHAGEN Survey Technician@)

-~ ~ ~ COMMENTS:

ACTIVITY VALUES NOT BACKGROUND CORRECTED r 7115Roo7

- 00'0 '10'0 00'0 'LOX 100'0 Ll ;OO'O Cl i 10'0 16 LZ 1 IZO'O : 10'0 :10-0 i00'0 i00'0 -- __ 89 89 11 9P 11 9P i00'0 11 9P 9P i00'0 .OO'O i00'0 110-0 CC 11 a S* 9P 26 ____. zz iOO'0 11 9P .OO'O :10.0 :oo*o i00'0 a PC 3 9 i 10'0 zz Z6 18 21 18 .lO'O :oo*o I10.0 i 10'0 - bun - 61 E 6L zz 26 I N O cv Y-I SECTION 7 ATTACHMENT 2 7 PAGE(S)

I1 Pipe Interior Radiological Survey Form Date: 1-26-06 Time: 080r Building:

(%!& Elevation: -L3- Access Point Area: AN M CClxx System: Pipe Diameter:

zfl Pipe ID # R--x / (o 2 Type of Survey Investigation Characterization Other 1/ Sled Size z/'v,u y~ &&&L 7 LI inch Cal Date: I /-I 7-0 F Cal Due Date: //-f 7 -0 6 Detector:

b-WL Detector ID #: p.7 ClCfr & -7d /2/ Instrument

23m-( Instrument ID #: 7-/22ZJ Cal Date: It-f 7 Cal Due Date: /f-f 7-0 G From the Daily Pipe Survey Detector Control Form for the Selected Detector Background Value $4 cpm MDCRStatlC

/I/ 7 cpm Efficiency Factor for Pipe Diameter OImo2b (taken from detector MDcstatlc 7&3b dpdl 00cm2 ANU@ CL- Pipe Interior Radiological Survey Radiological Survey Commenced:

Date: / - Lb-06 Time: o&c Package Page 1 of 1 Attachment 3, Page I Pipe Interior Radiological Survey Form Date: /- <3 0 -0 c. Time: / tm Building:

\<x Elevation Access Point TRdL L-- IR m' : I+ t RX IGL System: SC~+..~~\~~ ,d Pipe Diameter:

2 " Area: Pipe ID Type of Survey Investigation Characterization Ozu- # Other Sled Size ziidy~h~tca~/L/

inch - fl T- Detector:

YY-62 Detector ID #: @V+a- -I Instrument:

2.3 $3 4 Cal Date: //-/7 -0 5 Cal Due Date: / /-/ 7 - 0 6 - Instrument ID #: z/r p 23 Cal Due Date: //-/ 7-d b I Cal Date: //-/ 7 -0 5 From the Daily Pipe Survey Detector Control Form for the Selected Detector Background Value 5.7 CPm &m!nAW ?+ MDCRstahc.

//. 3 CPm eGd-y Efficiency Factor for Pipe C?L WoZb (taken from detector meter StahC 7 8-3 b dpm/100cm2 (if no, adjust sample count tune and recalculate MDCbt,,) -__ _- - -@*& 7/c,r-] "/ 7-??/&-$ fy LW Is the MDCStabc G4-a .L&- 7Vz fdft4f -- c&3iaZzF?

--/vi 7,nJLtaYrd PA M PLG-e- - Pipe Interior Radiological Survey Radiological Survey Commenced:

Date: /-26)- 0 6 Time: /2 3 a REFERENCE COPY 0 4 Package Page 1 of Attachment 3, Page 1 I d I Package Page 2 of 3 REFERENCECOPY Attachment 3, Page 2 I r I I .. . . REFERENCECOPY 0

Pipe Interior Radiological Survey Form Date: 8- f$ co c Time: 13e Building:

ZX, Elevation:

2. Access Point Area:

A-uvu~J System: Type of Survey Investigation Charzcterization Other Sled Size Detector:

4+i$ P Detector ID #: Jaw.> Cal Date:

// -/7-3r Cal Due Date:

lf 'I 7-047 Instrument:

235.6 -I Instrument ID #: 2--3 Cal Date: // 0 1 7 0-c, Cal Due Date: /{P/?* 0 c L/ k/A Pipe Diameter:

2 " PipeIDfC z' /LJ' rL' inch elmt j-J-4*2 I.$\ l/ CL25AC 121 From the Daily Pipe Survey Detector Control Form for the Selected Detector Background Value .sr CPm MDCRStatiC 164 7 cpm ~Cstaoc --?- &3 i5 .. (if no, adiust smle - count time and recalc- ,I __- Efficiency Factor for Pipe Diameter De am& (taken from detector - ~ -- Coanents:

Pipe Interior Radiological Survey Radiological Survey Commenced:

Date: d ' k- 0 b Time: /3PL/ REFERENCE COPY 0 Package Page 1 of 9 Attachment 3, Page 1

't Position Feet into Pipe Count Time # from Opening (min) 1 t d. 2 A 2 3 3 2 4 - - BSL'LVSPipeCrawler-002 Revision 4 dpm/lOOcm*

1 cpm cpm I 1 Gross counts Gross Net /. r n ILL n Iu I c/ 3 \ I 3 1-I- 4 ?( Pipe Interior Radiological Survey Form 5 6 7 1 8 9 10 Date: J* 7-0 c Time: /e 50 Pipe ID#: zlx [d 2 yrb& Pipe Diameter:

% Access Point Area: c 4 AJ I-)' L: LL~ 5 Elevation:

c LA-- System: Building:

'75 E AL ~-i Type of Survey Investigation Characterization Final Survey Other J Gross Co60 cs Detector Cal Due Date: DetectorID#/SledID# .tLf- 6.b 3SJdfL I p/ Detector Cal Date: t 7 - 9' J - b /7 ep'o LJ -0 G Instrument:

2333 - I Instrument ID #: $lo3 qrdo Instrument Cal Date: /7- /d)d - c7 5- Instrument Cal Due Date: /? -@dU --d co I I I From the Daily Pipe'Survey Detector Control Form for the Selected Detector BackgroundValue J7 cpm MDCRS~Lc /e- 7 cpm MDC,ta,C 7 83 L? Efficiency Factor for Pipe Diameter 0- S&oa (from detector efficiency determination) 2 no, adjust sarnple couot tinx md recalcu!a?e MDCR,,,,) - - .- _. __- -- a+(T Is the MDC,,,, acceptable?

J~l:&y&--e~, c A 2 --.q+A&t+

1 - 8 Technician Signature Pipe Interior Radiological Survey REFERENCE COPY 0 Package Page 1 of 2 Attachment 3, Page 1

I SECTION 7 ATTACHMENT 3 I PAGE@)

SECTION 7 ATTACHMENT 1 PAGE( S)

DQA Check Sheet Design # EP Rx 162 Revision # Original Survey Unit # EP 162 Prelimlnary Data Review' Yes No NfA Answers to the following questions should be fully documented in the Survey Unit Release Record 1 1. 2. 3. Have surveys been performed in accordance with survey instructions in the Survey Design? X X Is the instrumentation MDC for strudure 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 ? 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 Was the instrumentation MDC for volumetric measurements and smear analysis c 10% DCGLw ? X X 5. ~~ IxI I 6. Were the MDCs and assumptions used to develop them appropriate for the instruments and techniques used to mrfom the survev? 1x1 I 7. Were the survey methods used to collect data proper for the types of radiation involved and for the media beina sunreved?

~ 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 faallty3 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. 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 -~ - ~- - 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 X X 3. 4. If elevated areas have been identified by scans and/or sampling, is the avemge activity in each elevated area e DCGLEMC (Class l), Is the result of the Elevated Measurements Test e 1 .O? 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) 2 the critical value? X Form cs-0912 Rev 0 Page 1 of 1 SECTION 7 ATTACHMENT 4 1 DISC Survey Unit Release Record _- ~ Design # -~ Survey Unit qs) - Description EP-Rx 163 1 Revision#

1 Original I Page 1 of 3 Rx 163 1) Embedded Pipe (EP) Survey Unit Rx 163 meets the definition of embedded pipe for Plum Brook Reactor Facility (PBRF).

2) EP Rx 163 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 163 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 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 163 Revision # Ori@ 1.0 2.0 3.0 4.0 5.0 Page 2 of 3 History Description 1.1 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 163 consists of 2" diameter piping that is approximately 23 feet in length. 1.2 Survey Design Information 2.1 2.2 EP Rx 163 was surveyed IAW Procedure

  1. BSI/LVS-002.

100% of the 2" ID pipe was accessible for survey. The accessible 2" ID pipe was surveyed by static measurement at one foot increments, for a total of 23 survey measurements.

Surface area for the 2" ID piping is 486 cm2 for each foot of pi ing, corresponding to a total 2" ID piping surface area of 7,783 cm (0.8 mz) for the entire length of (approximately 23') of 2" 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 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 I, 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 163 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 I I FSS Design # EP Rx 163 Revision # Origrnal 1 Page 3 of 3 5.5 Statistical Summary Table 2" ' Pipe Statistical Parameter Number of Measurements

>MDC Number of Measurements Above 50% of DCGL I Total Number of Survey Measurements I 26 I 0 0 ~~ ~ Mean Median 1 Number of Measurements Above DCGL 101 0.0129 0.0130 J Maximum 0.0234 Minimum r 6.0 Documenbtion 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 163 to be less than 1 mredyr. The dose contribution is estimated to be 0.013 mredyr 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 - DQA Worksheet Attachment 4 - EP RX 163 SURR & Spreadsheet Disc I SECTION 7 ATTACHMENT 1 3 PAGE(S)

BSI EP/BP SURVEY REPORT Pipe ID Rx 163 Survey Location 2350-1 I 1126106,1130106, 2/6/06 Survey Date Survey Time 0815,1350,1250 Detectorsled w Annulus -291. 212223 44-62/204402-121,44-62/204402-no sled Number of Measurements

>MDC Number of Measurements Above 50% DCGL Number of Measurements Above DCGL Mean Median Standard Deviation Maximum Minimum 0 0 0 0.0129 0.0130 0.0051 0.0234 0.0047 Survey Unit Classification TED O6-004 Piping Group SR-13 Radionudide Distribution Sample Measured Nuclide Area FactorlEMC Used PasGail FSS MREWR Contribution 1 1 EP 3-9 Cb60 No Pass el I RP Engineer I Date EP Rx 163 2" Pipe TBD 06-004 Group 1 Co-80 activity (dpm1100cm2) 1,581 1,977 791 1,581 1,581 1,977 - 3,163 1,581 2,767 1,581- Irl Cs-137 activity Eu-162 activity Eu-164 activity Nb94 activity (dpm1100cm2) (dpm/l OOcm2) (dpm1100cm2) (dpm1100cm2) 46 58 78 1,875 498 110 - 2,625 698 81 31 750 199 23 63 1,500 399 46 63 1,500 399 46 - 63 1,500 399 46 78 1,875 498 58 92 63 1,500 399 46 141 3,375 897 104 __ 63 1,500 399 - - - -_ - - - - 125 3,000 798 - 7,692 7,692 7.692 8 -~ 2.5 2.5 9,615 4 4 15,385 9 10 2 2 7,692 11 4.5 4.5 17,308 12 3.5 - 3.5 13,462 : 13 3 3 11,538 14 1.5 1.5 - 5,769 15 - 2 2 7,692 16 2 2 7,692 17 3 3 11,538 18 1 1 3,846 19 1 1 3,846 20 3 3 11,538 21 4 4 15,385 22 3.5 3.5 13,462 23 4 4 19,048 24 2.5 2.5 11,905 25 3 3 14,286 26 3 3 14,286 ___.______.

__ -- Ag-108m activity (dpm1lOOcmZ) 11 14 19 6 .~ 11 11 11 14 22 11 25 19 17 - 8 11 11 17 6 6 17 22 19 27 17 2c 2c - UnitV - 0.00s 0.01: 0.01 i O.OOf ___.. 0.00s 0.001 0.00: 0.01: 0.01( O.OO! 0.02' 0.01; 0.01r 0.00: O.OO! O.OO! 0.034 0.001 O.OO! 0.014 0.01! 0.01' 0.02: ___ O.Ol! 0.011 0.01; - 1 of2 EP Rx 163 2" Pipe TBD 06-004 Group 1 Unity Cs-137 activity Eu-152 activity Eu-154 actlvky Nb-B4 actlvlty AglOlm activity (dpm1100cm2) (dpm1100cm2) (dpm1100cm2) (dpm1100cm2) (dpmll OOcm2) MEAN 0.01 -+- MEDIAN 0.01 ------k----t----IlsT~

DEV I 0.00 I I I ... 2of2 I SECTION 7 ATTACHMENT 2 7 PAGE(S)

Pipe Interior Radiological Survey Form Date: /-ZG-Ob Time: ox/ i- Building:

prp Elevation: -L Access Point Area: A-p 'Nu LCLiJ 2 System: Pipe Diameter:

2- Pipe ID # Type of Survey Investigation Characterization c&Gy> Other Sled Size 2 dIIJy( BLUOZ- 7 LC inch Detector: "py- 8L Detector ID #: aW-- f2-l S/!!U /I-/ 7 - 0 lQ Instrument

2357?--r Instrument ID #: ZL? 2 2 3 Cal Date: rf-f 7 - 0 5 Cal Due Date: tpf 7 -Lqb Cal Date: 1 /-(7 Cal Due Date: c From the Daily Pipe Survey Detector Control Form for-the Selected Detector BackgroundValue
b. f cpm MDCRstatic lfp7 cpm Efficiency Factor for Pipe Diameter 0 0002b (taken from detector MDcstatlc 7 83 b n dpdl 00cm2 (ifno, adjust sample count time and recalculate MDC&,'I - Is the MDCd, acceptable?

No ' . Pipe Interior Radiological Survey Package Page 1 of J'- REFERENCE COPY n Attachment 3, Page 1 Pipe Interior Radiological Survey Form Date: /I 30- ad Time: 135-0 I Building:

qw 7d-A Elevation d Access Point Dud &'*--F--+

System: J"D*MW'+' Pipe Diameter:

d I' Area: Pipe ID x /L 3 Detector:

cl+- 6 a Detector ID #: &2oyye Z' /3( Cal Date: /[-'/7rO~

Cal Due Date: 11. /7-d Instrument:

2353- I Instrument ID #: gt 223 3 < =4 .FF Type of Survey Investigation Characterization

&->' Other Sled Size // J ~;,,I\V+\\C~

c inch [(- 17 -8 c-1 Cal Date:

//*r7-5 Cal Due Date: From the Daily Pipe Survey Detector Control Form for the Selected Detector Background Value 67 CP* MDCRstatic

/f* 3 CP* Efficiency Factor for Pip e 0 tODb2.b (taken from detector meter statlc 783L - dpdl 00cm2 Pipe Interior Radiological Survey Package Page 1 of& Attachment 3, Page 1

"( / I I ZX /CJ Pipe Interior Radiological Survey Form (Continuatihn Form) 1. 30*@6 Package Page Lofgf Attachment 3, Page 2 r I

Pipe Interior Radiological Survey Form Date: Building:

System: GF Elevation:

/*-f Access Point Area:

g-c TO)-^) Pipe Diameter:

2 Pipe ID # EmLL 7P.y J -D"h;->iL Type of Survey Investigation Characterization Survey) Other Sled Size ccu inch Detector:

q4 -LT Detector ID #: 26 c/s/" 2- /P 17-8 L h Cal Date: // 1740 > Cal Due Date: Instnunent:

260 Instrument ID #: aGv a ? Cal Date:

//* // -d-?g Cal Due Date:

//-/7d 6 From the Daily Pipe Survey Detector Control Form for the Selected Detector BackgroundValue s4- 1 cpm MDCRS,,, /0/7 cpm Efficiency Factor for Pipe Diameter 89 Oms\ (taken from detector dpdl OOcm2 n MDCSWX 970 1 Is the MDCSt,ti, acceptable?

[xes > No (if no, adjust sample count time and recalculate MD-1 Comments : fo~*-Ju&-, ~&./ Pipe Interior Radiological Survey Radiological Survey Commenced:

Date: 0L ' 6 Time: /a bP REFERENCE COPY 0 Package Page 1 of 2 Attachment 3, Page 1 aj I' Pipe Interior Radiological Survey Form Date: a4 4 Time: 13 17 Building:

EA , Elevation: 5 System: - 7; I, < \ Pipe Diameter:

2 " Pipe ID # % /b3 3 pcur e Type of Survey Investigation Characterization Other

/ Sled Size r/. 54a inch Access Point Area:

~*L,CLS Pfi+d-+ &X% C&+*-I Detector:

rf?4 3- Detector ID #: PWO 3. Cal Date: //T7 r-0 > Cal Due Date:

//'/7.0 G Instrument:

23 3 I Instrument ID #: d@aa3 Cal Date: (Pf7'd 5; Cal Due Date:

l(flf7 - From the Daily Pipe Survey Detector Control Form for the Selected Detector Background Value $-I cpm MDCRstatic 10.7 cpm Efficiency Factor for Pipe Diameter MDCStatiC 9 70 1 Am/100cm*

00 0 00 a\ (taken from detector Is the h/lDCsta6c acceptable?

Yes 1 No (if no, adjust sample count time and recalculate MDCR,,ti,)

Comments:

pBF+mzLL3,d s~~A~~ f3z4c/p krt: 4 Pipe Interior Radiological Survey Radiological Survey Commenced:

Date: (;2 *k' 0 b Time. /97 REFERENCECOPY 0 Package Page 1 of 2 Attachment 3, Page 1

.L SECTION 7 ATTACHMENT 3 I PAGE( S)

DQA Check Sheet Design # EP Rx 163 Revision # Original Survey Unit # EP Rx 163 Preliminary Data Review' Answers to the following questions should be fully documented in the Survey Unit Release Record Yes No 1. 2. 3. 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 survey units, or below 0.5 DCGLw for Class 3 survey units? Is the instrumentation MDC for embeddedlburied piping static measurements below the DCGLw ? X 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 5. 10% DCGLw ? IxI 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. 9. Were 'Special Methods" for data collection property 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 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 1, 2. Are all sample measurements below the DCGLW (Class 1 & 2), or 0.5 DCGLw (Class 3)? Is the mean of the sample data < DCGLW? 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 I), < DCGLw (Class 2), or e0.5 DCGLw (Class 3)? 4. Is the result of the Elevated Measurements Test < 1 .O? ~ 5. Comments:

Is the result of the statistical test (S+ for Sign Test or W for WRS Test) 2 the critical value? X r Page 1 of 1 CS-0912 El SECTION 7 ATTACHMENT 4 1 DISC Design # Survey Unit #(s) EP-1.37 Description Revision # Original Page 1 of 3 Survey Unit Release Record 2) EP 1.37 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 1.37 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.

Approval Signatures I Date: CS-09/1 F! 0 COPY FSS Design # EP 1.37 Revision # Original 1.0 2.0 3.0 4.0 5.0 Page 2 of 3 History/Description 1.1 The subject pipe system is the 3" purge line for Canal "E". The function of this pipe was to convey water from the one 3 inch riser in Canal "E" to the HD sump in Pump Room #22 on the Rx Building -25 ft, where the pipe is currently breached.

EP 1.37 consists of approximately 32 feet in length from the pump room to the riser in Canal "E". The pipe section has an approximately three mitd elbows ranging from 45" to 90". 1.2 Survey Design Information 2.1 2.2 EP 1.37 was surveyed IAW Procedure

  1. 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 36 survey measurements.

Surface area for the 3" ID piping is 729.7 cm2 for each foot of piping, corresponding to a total 3" ID piping surface area of 26,280.6 cm2 (2.6 m2) for the entire length of (36') 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 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 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 1.37 passes FSS. Background was not subtracted from the survey measurements and the Elevated Measurement Comparison (EMC) was not employed for this survey unit.

r i- I FSS Design # EP 1.37 Revision # Original Page 3 of 3 5.5 Statistical Summary Table Total Number of Survey Measurements Number of Measurements

>MDC Statistical Parameter 36 31 3" Pipe Number of Measurements Above 50% of DCGL Number of Measurements Above DCGL I I 0 0 Median Standard Deviation 1 0.020 0.007 Mean Maximum Minimum I 0.018 1 0.034 0.004 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 1.37 to be less than 1 mredyr. The dose contribution is estimated to be 0.018 mredyr 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 - DQA Worksheet Attachment 4 -Disc containing RR for EP 1.37 & Spreadsheet SECTION 7 ATTACHMENT 1

BSI EPIBP SURVEY REPORT Total Number of Survey Measurements Number of Measurements

>MDC Number of Measurements Above 50% DCGL Number of Measurements Above DCGL Mean Median Standard Deviation Maximum Minimum 36 31 0 0 0.01 8 0.020 0.007 0.034 0.004 1- I .- SR-13 Radionudie Distribution Sample Measured Nuclide Area FactorlEMC Used PasdFail FSS MREMPlR Contribution c Survey Unit Classification I 1 TBD 06404 Pimna Grow 2 I EP 2-1 c060 No P&SS <l COMMENTS:

ACTIVITY VALUES NOT BACKGROUND CORRECTED EP 1.37 3" Pipe TBD 06-004 Group 2 C&O acthrky Co-Bo activity Cs-137 activity Eu-152 activity gcpm ncpm (total dpm) (dpm1100cm2) (dpm1100cm2) (dpm1100cm2)

Eu-154 activity Nb-Q4 activHty (dpmllOOcm2) (dpm1100crn2)

I ---171 1 Ag-1OBm activity (dpmlqOOcm2) 94 ___-- 122 131 . _. - - __ ~ - 1 02 28 19s 114 -__ - Jnity - 0.001 0.01- 0.014 0.011 0.021 0.014 0.011 0.01 0.02: 0.02 0.01 0.01 0.01 0.00 0.02 0.01 0.01 0.02 0.02 0.02 0.02 0.03 0.02 0.02 0.02 0.02 0.02 0.03 0.01 0.02 0.02 ~ __ - __ __ ~ ~ ._ - - __ ~ __- ___ ~ - __ __ - -- - __ ~- ~ __ __ __ _- ~ 1 of2 P 3 0 N 0 (v c I SECTION 7 ATTACHMENT 2 PAGE(S)

Pipe Interior Radiological Survey Form Date: E- 1 3 -0 5- Time: /l3 a- Building:

&$ &Lo@ Elevation: - 3 3- Access Point Area:

C L Lf System: Pr.4EiS-6 llm/h3 PipeDiameter:

3 ~ -->Pipe rh:r / I3 r,. Type of Survey Investigation Characterization Final Survey Sled Size 3 r( inch Detector:

Yy-4 Detector ID #: zd YYi? ;I- 101 Cal Date: //-/7-0 Cal Due Date: t 1-/ 7 -0 @ Instrulnent:

ZJ JT -I Instrument ID #: 2/2523 Cal Date: I/-/ 7-c;tj I Cal Due Date: - /7-0& Backgroundvalue 5 2 CPm From the Daily Pipe Survey Detector Control Form for the Selected Detector MDCRStatIC

/O-f cpm Adc*'cy A&,,:nrXI Efficiency Factor for Pipe Diameter MDCSbtiC 2 xdpm/l 00cm2 Comments:

I u \TL P; L- Su ,wJ - 0 0 0 4 (taken from detector-Is the MDCSb,, acceptable?

a No (if no: adjust sample count me and recalculate MD%b,) / \ Pipe Interior Radiological Survey Radiological Survey Commenced:

Date: 1z-13 Time: f 3 0 3 Package Page 1 of - Attachment 3, Page 1 Pipe Interior Radiological Survey Form (Continuation Form I I I I I I I Package Page - 73 of - REFERENCE COPY Attachment 3, Page 2

.. . . . 1 ._ \- Drawing PF-00376 - . arious drains. i Pipe Interior Radiological Survey Form Date: /Z/ /JVG Time: //m Elevation:

-32 Access Point Area: /d*cd ipeD# /* 3 7 Type of Survey Investigation Other I/ Detector:

W-GG Detector ID #: ;1../c/ 2-1 D( Cal Date: // - / 6- Cal Due Date:

//- f 7.0 Q Instrument:

J,3 50 - I Instrument ID #: A32623 Cal Date: //. 17

  • 6.5 Cal Due Date:

/I- (?,-bL Sled Size 3 inch From the Daily Pipe Survey Detector Control Form for the Selected Detector Background Value 5~ f cpm 4 MDCRstatic D.3 Efficiency Factor for Pipe Diameter mcstatx 2 Nzdpm/l OOcrn' Is the hMDC,tahc acceptable?

NO (if no, adjust sample count the and recalculate MDCR,,,,)

Comments:

parr, Ub477dR) JaIzb'6cs/

p8. DC&-ZC4 Pipe Interior Radiological Survey Radiological Survey Commenced: Date:

18 '/I* 0 Time: /Y- REFERENCE COPY m 3 Package Page 1 of - Attachment 3, Page 1 Pipe Interior Radiological Survey Form (Continuation Form) I Package Page - 73 of - REFERENCE COPY Attachment 3, Page 2

--. REFERENCECOPY SECTION 7 ATTACRRlENT 3 1 PAGE(S)

DQA Check Sheet Design # I EP 1.37 1 Revision # 1 Original 1 Survey Unit# I EP 1.37 Preliminary Data Review' Answers to the following questions should be fully documented in the Survey Unit Release Record yes No 1. Have surveys been performed in accordance with survey instructions in the Survey Design? 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. 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 ? embedded/buried piping Scan measurements below the DCGLw, or, if not, was the need for additional X X 5. Was the instrumentation MDC for volumetric measurements and smear analysis 10% DCGLw ? I 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 being surveyed?

B. 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 design, which accurately reflects the radiological status of the faciliW Graphical Data Review 1. Has a posting plot been created? lx 2. Has a histogram (or other frequency plot) been created? I I Ix 3. Have other graphical data tools been created to assist in 8nalyzing the data? Are all sample measurements below the DCGLW (Class I 8 2), or 0.5 DCGLw (Class 3)? x Data Analysis 1, X 2. Is the mean of the sample data DCGLw? X X X 3. 6. If elevated areas have been identified by scans andlor sampling, is the average activity in each elevated area Is the result of the Elevated Measurements Test < 1 .O? DCGLEMC (Class I), < DCGLW (Class 21, or ~0.5 DCGLW (Class 3)? 5. Is the result of the statistical test (S+ for Sign Test or W, for WS Test) 2 the critical value? I I Ix FSS/Chamcterizatiofl Engineer (prinffsign)

Date 6--/2-07 FSS/ Characterization Manager (printlsign)

Date 7//g/u-7 /Y Page 1 of 1 El cs-0912 SECTION 7 ATTACEIMENT 4 1 DISC

  • I EP-1.81 Revision # Original Design # Survey Unit #(s) Page 1 of 3 Description 1.81 1) Embedded Pipe (EP) Survey Unit 1.81 meets the definition of embedded pipe for Plum Brook Reactor Facility (PBRF). 2) EP 1.8 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 1.81 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).ILVS-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: I I I C""Y Revision # Original FSS Design

  1. EP 1.8 1 1 .o 2.0 3.0 4.0 5.0 Page 2 of 3 HistorylDescription 1.1 The subject pipe is the floor drain line from Canals "J" & "K" to the -25 A of the Rx Building in Pump Room #22.

The function of this pipe was to convey water from floor drains located in Canals "J" & "K" to the HD sump in Pump Room #22 on the Rx Building -25 ft, where the pipe is currently breached.

EP 1.81 consists of approximately 30 feet in length from the valve pit in the Hot Laboratory Building to the Pump Room #22. The pipe section has at least 5 mitered elbows ranging between 300 and 500. 1.2 Survey Design Information 2.1 2.2 EP 1.81 was surveyed IAW Procedure

  1. BSILVS-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 20 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 29,180 cm2 (2.9 m2) for the entire length of (20') of 6" 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 InvestigatiodResults 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 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 ofthe FSSP, and applying the Cesium-1 37Kobalt-60 ratios, provided in TBD- 06-004, the survey Unit that is constituted by EP 1.81 passes FSS. Background was not subtracted fkom the survey measurements and the Elevated Measurement Comparison (EMC) was not employed for this survey unit.

FSS Design # EP 1.81 5.5 Statistical Summary Table Revision ## Original Page 3 of 3 Statistical Parameter Total Number of Survey Measurements Number of Measurements

>MDC 6" I Pipe I 20 19 Number of Measurements Above 50% of DCGL Number of Measurements Above DCGL 0 0 Mean Median Standard Deviation 0.005 0.003 0.004 6.0 7.0 Maximum Minimum Documentation of evaluations pertaining to compliance with the unrestricted use limit of 25 rnredyr and dose contributions fiom Embedded Pipe and radionuclides contributing 1oo/o 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 1.81 to be Iess than 1 mredyr. The dose contribution is estimated to be 0.005 mredyr based on the average of the actual gross counts measured.

0.01 8 0.001 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 1.81 & Spreadsheet SECTION 7 ATTACHMENT 1 2 PAGE(S)

BSI EP/BP SURVEY REPORT 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 20 19 0 0 0.005 0.003 0.004 0.018 I Minimum I 0.001 SR-13 Radionuclide Distribution Sample Measured Nuclide Area Factor/EMC Used Pass/Fail FSS MREMNR Contribution ROSENHAGEN Survey Techn ician(s)

EP 2-1 Co60 No Pass <1 I Survey Unit Classification I 1 RP Engineer I Date I TBD 06-004 Piping Group I 2 6-12-07 COMMENTS:

ACTIVITY VALUES NOT BACKGROUND CORRECTED EP 1.81 3" Pipe TBD 06-004 Group 2 Eu-164 acthflty (dpmll OOm2) I I I I I Nb-94 actIW (dpmll OOcm2) II I ncpm cod0 activity (dpm1100cm2)

-437 activity (dpmll OOcm2) Eu-152 actMty (dpm1100cm2) - 1 18 18 9,000 617 320 5 2 19 19 9,500 651 338 5 3 21 21 10,500 - 720 374 6 5 4 17 17 8,500 583 302 5 13 13 6,500 446 231 4 6 28 28 14.000 960 498 8 __ __ -_ __ __ 18 7 62 62 31;OOO 2,125 1,103 8 25 25 12,500 857 445 7 9 15 15 7,500 514 267 4 2 11 13 13 6.500 446 231 4 ____ -_ -- 10 8 8 4,000 274 142 .- 7 62 62 31;OOO 2,125 8 25 25 12,500 857 9 15 15 7.500 514 1,103 18 101 81 8) 4,000 1 274 I 2 111 131 131 6.500 I 4461 231 .- - - 12 20 20 10,000 685 6 1 ----%$ 13 i4 14 7.000 480 4 13 14 45 45 221500 __ 1,542 800 15 62 62 31 ,OOO 2,125 1,103 18 10 16 35 35 17,500 1,199 623 18 32 32 16.000 1.097 569 9 -~ _______-__---- - 17 33 33 16,500 1,131 587 9 ___. - 15 20 123 123 61 SO0 4.215 2.188 35 19 53 53 26150- 943 ____ I I I I _=I ' 1 41 0 Ag-lO8m acthrlty (dpm/l OOcm2) 18 19 21 17 13 -- 13 I 20 - 14 45 - 62 35 33 32 53 122 ~ __- -__ - ~~__ MEAN ~ MAX MIN - JnW 3.003 3.00= m D.004 __ D.001 0.001 -__ D.00C D.OW 0.002 -_ ___ 0.oo.l o.00; o.00: 0.00; 0. OOi 0.001 O.OOf -_ 653 O.ODt -__ O.OOt 0.011 -_ - - -- 0.00: oool 0.011 0.00' - lofl SECTION 7 ATTACHMENT 2 3 PAGE(S)

Pipe Interior Radiological Survey Form Date: /. +dL Time: 03p Building:

RQtzSii 8 d,5 Elevation: - zc-r Access Point Area: -z7 ' /354 c d System: PW M +ttq bn~r r3 Pipe Diameter:

~/---.-.PiPe~*~r Lk/ T/ I Type of Survey Investigation Characterization inal Suve Sled Size 6" inch Detector:

2) cfiu fJ /#6 Detector ID #: 6VS-j - (07 Cal Date: /A 02-0 5- Cal Due Date: /3-2 a-*L Instrument:

9357 - I Instrument ID #: 13Y7d v Cal Date: Cal Due Date: i3 $4 'c Position Feet into Pipe

  1. fiom Opening 1 f* 2 26- 3 4 9k 5 3 .f I 6 && 7 7.t; 8 8f.i 9 %- 10 /6P y- From the Daily Pipe Survey Detector Control Form for the Selected Detector BackgroundValue

/ 8- cpm MD CRstatic 7s CPm Efficiency Factor for Pipe Diameter dpdl 00cm2 Count Time Gross counts Gross Net (&> cpm cpm 1 /r /r nZe r\1A / /$ t? E 1 I at 81 I (7 17 I r3 /3 )

  • 2Y I ha+ / PX r3.S I fY /$ I 8 4 JI V 333 d m/100cm2 a No (if no, adjust sample count time and recalculate MDCR,,,,)

mcstatlc Is the MDCstatic acceptable?

J+/pw- 7 Jq 6 I/ eC/ Comments:

I I Pipe Interior Radiological Survey Radiological Survey Commenced:

Date: /, 9- O The: 0 7 re) REFERENCE COPY U Package Page 1 of 2 Attachment 3,Page-k

_-- __ I Pipe Interior Radiological Survey Form (Continuation Form) REFERENCECOPY

-0 Package Page - 7F of - Attachment 3, Page 2

SECTION 7 ATTACHMENT 3 I PAGE(S)

DQA Check Sheet Survey Unit # ~~ Design # 1 EP 1.81 I Revision # I Original I EP 1.81 Yes X 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 survev units.

or below 0.5 DCGLw for Class 3 survev units? I No N/A Ix ~ 3. 4. Was the instrumentation MDC for stnicture 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 ? embeddedburied piping scan measurements below the DCGLw, or, if not, was the need for additional 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 survep 7. Were the survey methods used to collect data proper for the types of radiation involved and for the medii being surveyed?

8. Were "Special Methods" for data collection properly applied for the survey unit under review?

-~ ~ (XI 9. Is the data set comprised of qualified measurement results collected in accordance with the survey desian. which acwratelv reflects the radiolwical status of the facility?

X X X 1. Has a postinn plot been created? I I Ix 2. Has a histogram (or other frequency plot) been created? Ix ~~ ~ 3, Have other graphical data tools been created to assist in analyzing the data? X 2. Is the mean of the sample data DCGLw? 3. elevated area < DCGLEMC (Class I), If elevated areas have been identified by scans andor sampling, is the average activity in each DCGLW (Class Z), or <0.5 DCGLw (Class 3)? .- Page 1 of 1 X X Form CS-09/2 Rev 0 4. 5. Is the result of the Elevated Measurements Test Is the result of the statistical test (S+ for Sign Test or W, for WRS Test) 2 the ctitical value? 1 .O? X X SECTION 7 ATTACHMENT 4 1 DISC Design # EP-Rx 127 Revision # Original Survey Unit #(s) Page 1 of 3 Description

2) EP Rx 127 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 127 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.

COPY FSS Design ## EP Rx 127 Revision # Original 1 .o 2.0 3.0 4.0 5.0 Page 2 of 3 History/Description 1.1 The subject pipe is the drain line on the Rx Building -25 foot elevation.

The bction of this pipe was to convey waste water from the drain openings to the drain trench on the Rx building -27ft. EP Rx 127 consists of 4" diameter piping that is approximately 2 1 feet in length. 1.2 Survey Design Information 2.1 2.2 EP Rx 127 was surveyed IAW Procedure

  1. 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 21 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 20,430 cm2 (2.0 m2) for the entire length of (approximately 2 1 ') of 4" piping.. 2.3 Survey Unit Measurement LocationslData 3.1 Pipe interior radiological survey forms are provided in Attachment 2 of this reiease record. Survey Unit InvestigationdResults 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 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 127 passes FSS. Background was not subtracted from the survey measurements and the Elevated Measurement Comparison (EMC) was not employed for this survey unit.

FSS Design # EP Rx 127 Revision # Origrnal 5.5 Statistical Summary Table Page 3 of 3 Statistical Parameter

~ Number of Measurements

>MOC Number of Measurements Above 50% of DCGL 4" Pipe 17 0 I Total Number of Survey Measurements I 21 I Number of Measurements Above DCGL Mean Median Standard Deviation Maximum Minimum 0 0.0177 0.0141 0.0184 0.0943 0.0059 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 127 to be less than 1 mredyr. The dose contribution is estimated to be 0.01 8 mredyr based on the average of the actual gross counts measured.

7.0 Attachments Attachment I - BSI EP/BP Survey Report Attachment 2 - Pipe Interior Radiological Survey Form Attachment 3 - DQA Worksheet Attachment 4 - EP RX 127 SURR & Spreadsheet Disc SECTION 7 ATTACHMENT 1 L PAGE(S)

I Pipe ID I Rx 127 BSI EP/BP SURVEY REPORT Survey Location 1 -27 el. RBDL-1 ~-~ ~~ I 0.0943 Maximum Minimum 0.0059 ROSENHAGEN Survey Technician(s) 23%-1 I 203488 08:05 Detector-Skd

  1. LVS-lI101 ~~ ~ ~~~ ~ ~~ ~~ ~~

ACTIVITY VALUES NOT BACKGROUND CORRECTED RP Engineer 1 Date 7/14/2007 EP Rx 127 4" Pipe TBD 06-004 Group 1 - gcpm - 15 11 5 1c 7 e 14 8C 14

  • 14 14 E 1C 14 1E i 1: 11 2E li ____ _- _.__ -~ ___ I Cod0 activity C0-60 activity (total dpm) (dpm1100cm2) ncpm 15 28.846 2.965 2,174 10 19.231 1.977 9,615 _- 7 13,462 1,384 8 15,385 1,581 2,767 80 153,846 15,813 - -- 14 26,923 2,767 ._ ~- 6 11.538 1.186 __ ~- 14 26,923 -- ____ ___ ____ 2,570 21,154 2,174 50,000 5,139 32,692 3,360 Cs-137 activity Eu-152 activity Eu-154 actlvlty Nb-94 activity Ag-1OBm activity (dpml100cm2) (dpmll OOcm2) (dpm1100cm2) (dpm1100Grn2) (dpm1100cm2)

I -~ - STD DEV 0.01 I MAX 0.09 lofl SECTION 7 ATTACHMENT 2 3 PAGE@)

BSI/LVSPipeCrawler-O02 Revision 4 Position I Feet into Pipe ' Count Time # I from Opening (min)

Pipe Interior Radiological Survey Form Net cpm 1 dpd100crn' Gross Gross Counts CPm Date: 2-9-d 6 Time : OBGJ- ID#: ipx m7 Dime ter : Area: TlE-i-il H Pipe (-ZF PMX-L) Pipe Access Point /f rf RpVrnC CfQ Mq(i+ Building: -x Elevation:

-27 System: Type of Survey Investigation Characterization Final Survey -%- Other J Gross Co60 d cs Detector ID# / Sled ID# LV5-1 / /ol Detector Cal Date: //-/7-C F Detector Cal Due Date: 1 I-/ 7- I9 6 Instrument:

23rO-/ Instrument ID #: zo3yf3d 0 Date: i- f 7 - 0 c Date: //.-I74 & Instrument Cal Instrument Cal Due From the Daily Pipe Survey Detector Control Form for the Selected Detector Background Value )4,3 cpm MDCRStatIC

/6/4 cpm Efficiency Factor for Pipe Diameter lVlY L statlc /do / a mi f vu cm Is the PVfDCsUQc acceptable?

&r(ifno, adjust sampie count time and recalculate MDW,) Comments:

0- 0 T> 052 (from detector efficiency determination) f -9 I -- Technician Signature Pipe Interior Radiological Survey BSI/LVSPipeCrawler-002 Revision 4 Pipe Interior Radiological Survey Form (Continuation Form) Date: 2-g-o 6 Pipe ID#: j~7 &@~1- I) Pipe Diameter:

4 I( Access Point Area:

f72c13L.r M Building:

QLx Elevation:

'27 System: 4x2 j- I*T (ho ni k,G REFERENCECOPY Package Page 2 of 3 Attachment 3, Page 2

! I I t SECTION 7 ATTACHMENT 3 1 PAGEIS)

I I i ~ - ~- ~ ~ DQA Check Sheet Design # Rx 127 Revision # Original Survey Unit # Rx 127 Preliminary Data Review' Yes No N/A Answers to the following questions should be fully documented in the Survey Unit Release Record

1. Have surveys been performed in accordance with survey insbuctions 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. 4. X X 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? 5. Was the instrumentation MOC for volumetric measurements and smear analysis < 10% DCGLw ? X X X IxI 6. Were the MDCs and assumptions used to develop them appropriate for the instruments and techniques used to perfom 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. Q. Were 'Speaal 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 7. 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. 2. X 3. 4. Is the result of the Elevated Measurements Test 1 .O? X Are all sample measurements below the DCGLw (Class 1 8 2), or 0.5 DCGLW (Class 3)? Is the mean of the sample data

< DCGLw? X X If elevated areas have been identified by scans and/or sampling, is the average activity in each elevated area < DCGLw (Class l), < DCGLw (Class 2), or ~0.5 DCGLW (Class 3)? 5. Comments:

Is the result of the statistical test (S+ for Sin Test or W, for WRS Test) 2 the critical value? X Form Rev 0 CS-0912 Page 1 of 1 SECTION 7 ATTACHMENT 4 1 DISC I I Design ## Survey Unit #(s) Description Survey Unit Release Record EP-Rx 148 1 Revision#

1 Original I Page 1 of 3 Rx 148 1) Embedded Pipe (EP) Survey Unit Rx 148 meets the definition of embedded pipe for Plum Brook Reactor Facility (PBRF). 2) EP Rx 148 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 148 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.

I Date: ipproval Signatures ewewer - FSS/Characterhation Manager - tG=h Form Rev 0 CS-0911 li_l COPY FSS Design # EP Rx 148 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" Quad "B" system line.

EP Rx 148 consists of approximately 21 feet in length from the Reactor Building -25' elevation to Quad "B". EP Rx 148 was surveyed IAW Procedure

  1. 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 21 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 20,430 cm2 (2.0 m2) for the entire length of (2 1 ') 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 InvestigationsResdts 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 medyr 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 148 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 148 Revision # Original 5.5 Statistical Summary Table Page 3 of 3 Statistical Parameter Survey Unit: Rx 148 1 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 6.0 Documentation of evaluations pextaining to compliance With the unrestricted use limit of 25 mrerdyr 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 148 to be less than 1 mredyr. The dose contribution is estimated to be 0.010 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 - EP RX 148 SURR & Spreadsheet Disc 21 2 0 0 0.0098 0.0094 0.001 9 0.0129 0.0060 SECTION 7 ATTACHMENT 1 2 PAGE(S)

BSI EP/BP SURVEY REPORT Survey Location I Quad B Survey Date Sunrey Time Pipe Size DCGL I- 2.41 EN5 F 11-Jan46 10:55 4" Routine Survey I X DetectorSled I Detector Efficiency PipD&alllmPmmby-*Fcm5)

Field BKG (cpn) Field MDCR1-i Nominal MDC ~dpnn-) 1MGl LVS-11101 0.00052 973 22.2 19.3 1,557 2350-1 # Median Standard Deviation Maximum Minimum I 134738 0.0094 0.001 9 0.0129 0.0060 I I Sumv Measurement f I COMMENTS:

ACTIVITY VALUES NOT BACKGROUND CORRECTED . I I I ieSUltS 21 2 0 0 .. 3098 Total Number of Survey Measurements Number of Measurements

>MDC Number of Measurements Above 50% DCGL Number of Measurements Above DCGL - 1 U.L. Mean Survey Technician@)

711512007 EP Rx 148 4" Pipe TBD 06404 Group 2 CI C E" L a QD J, *I I I I I I I I I Co-60 activity (dpmll OOcm2) 1,977 __.____- Cr-137 activity Eu-152 activity (dpmll OOcm2) (dpmll OOcm2) 1,025 16 _- Eu-IS4 actlvity (dpm1100cm2)

~. 12 13 13 25:OOO 13 9 9 17.308 Nb94 activity Ag-108m activity (dpmlIWcm2) (dpml100cm2)

-. _~___ -- 16 12 12 17 10 10 19.231 ncpm - 18 15 15 281846 19 10 - 10 19,231 20 13 13 25,000 21 . 13 13 25,OOT Cos0 activity (totaidpm) 13 15 16 _____-. ____. 2.174 1 57 63 1 1 80 . 1 74 ____ - -- - __ - 2,174 - 1,127 18 2,767 - 1,435- 23 922 15 - 2,965 1,537 25 20 16 1,537 25 - 1,977 1,025 16 2.570 1.332 21 ___- - -____ - 2,570 . 7,332 21 - 1,384 717 11 ___ ~ 1,977 1,025 - -___- 2,965 _- - 2,570 - 1,332 21 1,779 -_ ___ 2,372 1,230

____ 0.009 0.01 1 =. 0.009 0.012 0.009 1 of 1 SECTION 7 ATTACHMENT 2 3 PAGE(S)

.- I' Pipe Interior Radiological Survey Form Date: t -/f -06 Time: 1 UJ-3' Building:

47% Elevation - 2," Access Point QLw0 L3 Detector:

13Kmd irn6-I Detector ID #: LVS -1 Cal Date: 1 L- Le -Of Cal Due Date: /2-- 20-06 Instrument:

3577 -I Instrument ID #: /3V7JB Cal Date: / L- 2 0 Cal Due Date: /'-U -0 L From the Daily Pipe Survey Detector Control Form for the Selected Detector Background Value 22-R cpm MDCRstatic 17.3 CPm Efficiency Factor for Pipe 0 - 000- (taken from detector Meter statlc 1557 dpdl OOcm' c$jiE.@e ? IZk /%? System: Bdc,t a')~(rp,%cL73 Pipe Diameter:

4 if Area: Pipe JD Type of Survey Invesigation Characterization a inal sun;$ # Other rM Sled Size O&&IUE / 01 inch (if no, adjust sample count tune and recalculate MDCR,,) Is the MDC,,,,, @ No ~ -- _--- Pipe Interior Radiological Survey Radiological Survey Commenced:

Date: REFERENCE COPY -0 Package Page 1 of& -4ttachment 3, Page 1 REFERENCE COPY 0 Package Page &of Attachment 3, Page 2

i SECTION 7 ATTACHMENT 3 I PAGEIS) t I DQA Check Sheet Design # EP Rx 148 Revision # Original Survey Unit # EP Rx 148 Preliminary Data Review' Answers to the following questions should be fully documented in the Survey Unit Release Record Yes No NIA 1. 2. Have surveys been performed in accordance with survey instructions in the Survey Design? X X 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 suwey units? 3. 4. 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 Was the instrumentation MDC for volumetric measurements and smear analysis < 10% DCGLW ? X Was the instrumentation MDC for strudure scan measurements, soil scan measurements, and static measurements or soil samples addressed in the survey design?

X X 5. 6. Were the MDCs and assumptions used to develop them appropriate for the instruments and techniques used to wrform the survev? -~ ~ 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. Were 'SDecial 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 design, which accurately reflects the radiological status of the facility?

Graphical Data Review 1. Has a posting plot been created? X 2. 3. Has a histogram (or other frequency plot) been cteated? Have other graphical data tools been created to assist in analyzing the data?

X X ~ ~ Data Analysis 1. Are all sample measurements below the DCGLw (Class 1 8 2), or 0.5 DCGLw (Class 3)? X 2. Is the mean of the sample data DCGLW?

X 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 result of the Elevated Measurements Test 1 .O? X 5. Is the mutt of the statistical test (S+ for Sign Test or W, for WRS Test) 2 the critical value? X Comments:

r Page 1 of 1 CS-09/2 El SECTION 7 ATTACHMENT 4 1 DISC Design # Survey Unit #(s) EP-Rx 152 Description Revision # Original Page 1 of 3 2) EP Rx 152 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 152 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 (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 BSI/LVS-002, WEP 05-006, these determinations are appropriate for the types of radiation involved and the media being surveyed.

Date: Approval Signatures FSS/Characterhlion Engineer COPY FSS Design # EP Rx 152 1.0 2.0 3.0 4.0 5.0 Revision # Original Page 2 of 3 HistoryDescription 1.1 1.2 Survey Design Information 2.1 2.2 The subject pipe system is the 3" Quad "B' De-ionized (DI) water line. The function of this pipe was to convey DI.

EP Rx 152 consists of approximately 21 feet in length from the Reactor Building -25' elevation to Quad "B". EP Rx 152 was surveyed IAW Procedure

  1. 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 21 survey measurements.

Surface area for the 3" ID piping is 729.7 cm2 for each foot of piping, corresponding to a total 3" ID piping surface area of 15,330 cm2(1.5 m2) for the entire length of (21 ') of 3" piping.. 2.3 Survey Unit Measurement LocatiodData 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 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 152 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 I I FSS Design # EP Rx 152 Revision # Original Page 3 of 3 5.5 Statistical Summary Table Number of Measurements

>MDC Number of Measurements Above 50% of DCGL Statistical Parameter 8 0 ~~ r Total Number of Survey Measurements I 21 I Number of Measurements Above DCGL Mean 0 0.01 1 I I I Standard Deviation Maximum 0.003 0.018 Median I 0.011 I Minimum I 0.007 I 6.0 Documentation of evaluations pertaining to compliance with the unrestricted use limit of 25 mredy-r 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 152 to be less than 1 mredyr. The dose contribution is estimated to be 0.01 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 152 82 Spreadsheet SECTION 7 ATTACHMENT 1 L- PAGE(S)

~~ Maximum I I I 0.01 a I COMMENTS:

ACTMM VALUES NOT BACKGROUND CORRECTED 6/12/2007

SECTION 7 ATTACHMENT 2 $ PAGE(S)

I .- I Pipe Interior Radiological Survey Form Date: 19- /A bS Time: Building:

a46 Elevation:

Accesspoint Area: ,$%%> &t&:d*%%?fi u' (d Pipe Diameter:

c3f' _=.3 P(pe r~:r j? 15-3 Type of Survey Investigation Characterization Final Surve Lf Detector:

Lcy-4 % Detector ID #: &Jqq 3 7 +fN Cal Date: // , ,/7. 03- Cal Due Date: /)- /7*d Cal Date: f/. /?* 8s- Cal Due Date:

//- /3 4 6 Sled Size 3 /' inch Instrument

235 &I-( Instrument ID #: 3 02 a3 From the Daily Pipe Survey Detector Control Form for the Selected Detector Backg-roundValue fc 2 cpm mcktahc p r Efficiency Factor for Pipe Diameter MDcstatic Comments:

2 W-Z m/100cm2 & No (if no, adjust sample count time and recalculate MDCR*& Is the MDC,,a,, acceptable?

Pipe Interior Radiological Survey Radiological Survey Commenced:

Date: /3

  • 13 ' OrTke:

I Pipe Interior Radiological Survey Form (Continuation Form) I I 1 I I I I Package Page 2 of 2 Attachment 3, Page 2 REFERENCE COPY

\9 c-, . -c P- II i Pipe Interior Radiological Survey Form Date: /L -/3 '0 f Time: /05= Elevation: - z >- Access Point Area:

0 ,ctm n Pipe Diameter:

3 '( 7 Type of Survey Investigation Characterization Other Sled Size 3 '( inch Detector:

yY-& 7 Detector ID #: 2 0 Y vc 2-1 DI Cal Date: //-17-0 5 Cal Due Date: //77 436 Instrument:

23 \m-\ Instrument ID #: 2Jzzz3 Cal Date: //-/7-0>-

Cal Due Date: //-f7-d 6 From the Daily Pipe Survey Detector Control Form for the Selected Detector BackgroundValue

5. L cpm MDCRStatlC 181 B CPm Efficiency Factor fo; Pipe Diameter z 84 3A m/100cm2 & No (if no, adjust sample count time and recalculate MDCK,,,) MDCStahC Is the MDC,,,, acceptable?

Comments:

7/r2Jc( 4 Pfd oc PIP6 5ul) />4d?l4 /L-/z - c4 I Pipe Interior Radiological Survey Radiological Survey Commenced:

Date: / L-f 3 - 6 Time: 1 3 )v Package Page 1 of1 Attachment 3, Page 1

SECTION 7 ATTAC-NT 3 PAGE(S)

Design # Survey Unit # EP hl52 Revision # Original EP Rx152 X - - X Answers to the following questions should be fully documented in the Survey Unit Release Record Yes No NIA - 8. Were "Special Methods" for data collection properly applied for the survey unit under review?

1x1 I 1. 2. 3. 4. 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? Is the instrumentation MDC for embeddedhuried piping static measurements below the DCGLw ? 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 static measurements or soil samples addressed in the survey design? 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 beina surveyed?

Data Analysis X X 1. Are all sample measurements below the DCGLw (Class I & 2), or 0.5 DCGLw (Class 3)? 1. Has a posting plot been created?

1x1 I X 2. Has a histogram (or other frequency plot) been mated? 3. Have other graphical data tools been created to assist in analyzing the data? X X Page 1 of 1 2. Is the mean of the sample data

< DCGLW? 3. If elevated areas have been identified by scans andor sampling, is the average activity in each elevated area < DCGLEMC (Class I), 4. Is the result of the Elevated Measurements Test I .O? DCGLW (Class 2), or e0.5 DCGLw (Class 3)? X X X ~~ 5. Is the result of the statistical test (S+ for Sign Test or W, for WRS Test) 2 the uitical value? X SECTION 7 ATTACHMENT 4 1 DISC I EP-Rx 157 Revision # Original Design # Page 1 of 3 ~ Survey Unit #(s) Description I 2) EP Rx 157 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 157 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 (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 BSVLVS-002, WEP 05-006, these determinations are appropriate for the types of radiation involved and the media being surveyed.

I FSS Design # EP Rx 157 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 is the drain line from the dry annulus inside the CV to the drain trench on the Rx Building -25 foot elevation.

EP Rx 157 consists of 4" diameter piping that is approximately 5 feet in length. EP Rx 157 was surveyed IAW Procedure

  1. 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 5 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 4,864 cm (0.5 m2) for the entire length of (approximately 5') of 4" 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 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 I. 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 157 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 157 Revision # Original 5.5 Statistical Summary Table Page 3 of 3 Statistical Parameter

-~ Total Number of Survey Measurements Number of Measurements

>MDC 5 4 ~ ~ Number of Measurements Above 50% of DCGL Number of Measurements Above DCGL 0 0 Mean 0.0288 Median 0.0307 Standard Deviation Maximum I Minimum I 0.0184 I 0.0064 0.0337 6.0 7.0 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 157 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 measured.

Attachments Attachment I - BSI EPBP Survey Report Attachment 2 - Pipe Interior Radiological Survey Form Attachment 3 - DQA Worksheet Attachment 4 - EP RX 157 SURR & Spreadsheet Disc I I SECTION 7 ATTACHMENT 1 z PAGE(S)

BSI EPIBP SURVEY REPORT Pipe ID Rx 157 Survey Location I cv -25el. Survey Date 2350-1 # 1890% survey rime 13:17 DedectorSJed

  1. 44-159D38369-101 Total Number of Survey Measurements Number of Measurements

>MDC Number of Measurements Above 50% DCGL Number of Measurements Above DCGL Mean Median Standard Deviation 5 4 0 0 0.0288 0.0307 0.0064 Maximum I 0.0337 Minimum 0.0184 STOCK Survey Technician(s)

COMMENTS:

ACTIVITY VALUES NOT BACKGROUND CORRECTED 711512007 EP Rx 157 4" Pipe TBD 06-004 Group 1 iL C Q) E C0-60 activity C0-60 activity Cs-137 activity Eu-152 acUvky Eu-154 acUvity 3 gcpm ncpm (total dpm) (dpm1100cm2) (dpmllO0cm2) (dpm1100cm2) (dpm110Ocm2)

CI 3 8 4,625 183 4,388 1,166 - -. 5,139 204 4,875 1,296 5,653 224 5,363 1,426 224 5,363 1,426 122 2,925 1 9 9 45,000 2 10 10 50,000 3 11 -~ 11 55,000 4 11 11 55w- 5,653 778 __- __- - 5 6 6 30,000 3,084 - - __ - __-. - - ._____~ __- _- Nb94 actlvfty (dpm1100cm2) 135 150 165 165 90 I AglOBm activity (dpmll OOcm2) Unity 0.02! MEDIAN 0.03' STD DEV 0.01 I 1 of1 SECTION 7 ATTACHMENT 2 3 PAGE(S)

P BSILVSPipeCrawler-002 Revision 4 Pipe Interior Radiological Survey Form 7/.t/b 6 1317 1 Time: Pipe Diameter:

Access Point Area:

C 1/ - 2 S* AR/WLG~ I) Date: Pipe ID#: 62 /,s7 Building:

<L/ Elevation: -ZS' System: mr\l LIUF Type of Survey Investigation Characterization Final Survey Other Gross cs i /o I c060 --G Detector ID# / Sled ID# 49 - (2'1 23 T 36 9 Detector Cal Date: 9-/& /o E, Detector Cal Due Date: 3/6/0 7 Instrument:

7 3 saL/ Instrument ID #: f 5#o/m+ Instrument Cal Date: 3// ,/or2 Instrument Cal Due Date: 7// do7 c l From the Daily Pipe Survey Detector Control Form for the Selected Detector Background Value 12 ,3 cpm Efficiency Factor for Pipe Diameter MDCRstaoc 15.1 cpm 6,000 a (from detector efficiency determination)

M-DCStatlC 404q - -- --- - 1s mt stabc ~LL-' e and recalculate MUCR mc) Commciits:

Zdl mypL C3W=,G= Technician Signature Pipe Interior Radiological Survey REFERENCECOPY 0 Package Page 1 of z Attachment 3, Page 1

I ! SECTION 7 ATTACHMENT 3 I PAGE(S)

DQA Check Sheet Design # Survey Unit #l ~ ~~ EP Rx 157 Revision # Original EP 157 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. Yes No NIA X Ixl I 6. Were the MDCs and assumptions used to develop them appropriate for the instruments and techniques used to perform the survey? ~~- ~ ~~ 2. Is the instrumentation MDC for structuk 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 embeddedlburied piping static measurements below the DCGLW ? 7. Were the survey methods used to coflect data proper for the types of radiation involved and for the media beinn surveyed?

X X 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? 5. Was the instrumentation MDC for volumetric measurements and smear analysis c 10% DCGLW ? 1. Has a posting plot been created?

I I lx X X 8. 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?

3. Have other graphical data tools been created to assist in analyzing the data? I I Ix X X DoGl Analysis ~ 2. Has a histogram (or other frequency plot) been created? 1. Are all sample measurements below the DCGLW (Class 1 & 2), or 0.5 DCGLw (Class 3)? 1x1 1 X 2. Is the mean of the sample data DCGLw? 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 c 1 .O? DCGLEMC (Class l), c DCGLw (Class 2), or ~0.5 DCGLw (Class 3)? X X X Form cs-o9/2 Rev 0 5. Is the result of the statistical test (S+ for Sign Test or W, for WRS Test) 2 the critical value? Page 1 of 1 X SECTION 7 ATTACHMENT 4 1 DISC

. Survey Unit Release Record Design # survey Unit kys) Description

~- ~ ~~ EP-1.31 1 Revision # I Original I Page 1 of 3 - 1.31 1) Embedded Pipe (EP) Survey Unit 1.3 1 meets the definition of embedded pipe for Plum Brook Reactor Facility (PBRF). 2) EP 1.3 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 1.3 1 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 BSI/LVS-002, WEP 05-006, these determinations are appropriate for the types of radiation involved and the media being surveyed.

Date: Approval Signatures w CQPY FSS Design # EP 1.3 1 1.0 2.0 3.0 4.0 5.0 Revision # Original Page 2 of 3 HistoryAIescription 1.1 The subject pipe system is the 3" purge line for Quad "D'. The function of this pipe was to convey water from the one 3 inch riser in Quad "D to the HD sump in Pump Room #22 on the Rx Building -25 ft, where the pipe is currently breached.

EP 1.3 1 consists of approximately 150 feet in length fhm the pump room to the riser in Quad "D".

The pipe section has approximately eight elbows ranging from 45" to 90". 1.2 Survey Design Information 2.1 2.2 EP 1.3 1 was surveyed IAW Procedure

  1. 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 14 1 survey measurements.

Surface area for the 3" ID piping is 729.7 cm2 for each foot of pi ing, corresponding to a total 3" ID piping surface area of 102,930 cm (1 0.3 m2) for the entire length of (141') of 3" piping.. 2.3 P Survey Unit Measurement LocationdData 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 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 1.3 1 passes FSS. Background was not subtracted from the survey measurements and the Elevated Measurement Comparison (EMC) was not employed for this survey unit.

FSS Design ## EP 1.3 1 Revision # Original 5.5 Statistical Summary Table Page 3 of 3 3" Pipe Statistical Parameter Number of Measurements

>MDC Number of Measurements Above 50% of DCGL I Total Number of Survey Measurements I 141 0 0 Number of Measurements Above DCGL Mean 0 0.020 Median Standard Deviation Maximum I 0.020 1 0.006 0.038 I Minimum I 0.008 1 6.0 7.0 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 1.3 1 to be less than 1 mredyr. The dose contribution is estimated to be 0.020 mredyr based on the average of the actual gross counts measured.

Attachments 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 1.3 1 & Spreadsheet

  • SECTION 7 ATTAC**MENT 1 (n PAGE(S)

BSI EPIBP SURVEY REPORT SR-13 Radionudde Distribution Sample Measured Nudi Area FadorEMC Used Pass/Fail FSS MREMNR Contribution Survey Measurement Results Total Number of Survey Measurements Number of Measurements Above 50% DCGL Number of Measurements Above DCGL 141 Number of Measurements

>MDC 0 0 0 Mean 0.020 Median 0.020 Standard Deviation 0006 Maximum 0 038 Minimum 0.008 ROSENHAGEN Survey Technician($)

EP 2-1 Co60 No Pass <l ~~ COMMENTS:

ACTIVITY VALUES NOT BACKGROUND CORRECTED RP Engineer I Date 6/11/2007 EP 1.31 3" Pipe TBD 06-004 Group 2 It lr 1' 1' I t C0-60 activity c060 activtty Cs-137 activity ncpm19~ (total dpm) 1 (dpm1100cmZ) 1 (dpm1100cmZ) 63.333 8.679 4.505 __ 30,000 4,111 30,000 4,111 43.333 5.939 3.082 5339 ~ 261667 3,654 1,897 7,309 3,793

___- lf 9 30.000 4.111 2.134 53,333 ____ . 46:667 6,395 3,319 3,556 15 50,000 6,852 14 46,667 6,395 3,319 11 36,667 5,025 2,608 8 26.667 3.654 1,897

____ __ - - -_ __ ____ 7 23,333 3,198 1,660 Eu-152 activity .. 72 34 49 34 ______ 30 45 ______ ~- 19 42 Eu-I54 activity (dpmll OOcm2) 51 24 35 24 ~___ 40 38 ~__- 22 30 __ 30 23 16 - Nb-94 actlvity Ag-lO8m activity (dpmll OOcm2) (dpmllOOcm2) - Unity - 0.03* 0.01* 0.02E 0.011 0.02E 0.01E 0.03; 0.011 0.02E 0.03C 0.02 0.02; 0.011 O.OlE 0.021 0.02 0.02; 0.02; 0.01: 0.02; 0.02( 0.01(

0.02: 0.03; - __ ___ __ -~ -- -~ _I_ __ -- __- -__- ~ _- __ - __ 0.05 __ - - ._--- __- - O.Olt - 00% 0.02I 0.0lt 0.02: 0.02: 0.01: - __ --

EP 1.31 3" Pipe TBD 06-004 Group 2 ~ 33 34 35 36 37 38 39 40 41 - I ._ - ncpm 6 6 11 11 9 9 14 14 9 s 9 E 9 E 7 7 13 1: - 45 46 47 48 49 50 51 52 53 54 55 56 57 58 59 60 61 62 63 - -. __ - __ ~ 1E 6 f 7 i 9 I 14 14 12 1i 11 11 13 1: 13 1: 5 14 Id 8 t 10 1( 1: 13 4 1 1 8 5 ! 1: 12 12 1: __-_ 18 I - - ~- __ -- - ~. -_ __ 20,000 36,ssf 46,667 30,000 30,000 30,000 23,333 43,333 43,333 60,000 36,667 60,000 ~ 20,000 23,333 30,000 46,667 40,000 36,667 43,333 43,333 16,667 46,667 26,667 _-_____ ~- ______ ~- _____~ _____- ____- ~___ 33,333 43,333 13,333 26,667 16,667 40,000 40,000 ___ -~ - ~- Cd)o activity (dpmll ODcm2) 2,741 5,025 4,111 6,395 4,111 4,111 4,111 3,198 5,939 5,939 8,223 5.025 ___- -__ _______ 8,223 2,741 3.198 __ __ 4,111 6,395 5,482 5,025 5,939 5,939 2,284 6,395 3,654 4,568 1,827 3.654 __ _.__ -~ .___ 5,939 ____ 2,284 5,482 5,482 ____ - ~ Cs-137 activity (dpmll OOcm2) 1,423 2,608 2,134 3,319 2,134 2.134 -~ ___. - - - 2,134 1.660 3,082 - 3,082 4,268 2,608 4,268 1,423 1,660 2,134 3.319 ___ .__ .- ~ - - .- -. ___ 2,845 2,608 3,082 3,082 1,185 3,319 2,371 3,082 -- 948 1,897 - 1,185 - 2,845 2,845 __~__ - - _-- - - ___ -- ___- 1,897 _____- __ ____ -- ___ __ -~ Eu-152 actlvity Eu-154 activity Nb-94 activity (dpmllOOcm2) (dpmll Wcm2) (dpml100cm2) i I 42 2 53 3 Ag-lO8m activity (dpm1100cm2) 79 119 185 119 119 119 1 46 _ -- - - --~. -~ ~ 93 1 72 __ 172 230 185 159 Unity - 0.01: 0.02; 0.01 f 0.02t 0.01t 0.01 t 0.011 0.02f 0.02t 0.03( 0.02: 0.03f 0.01: 0.014 0.011 0.021 0.024 0.02: 0.02( 0.02( 0.01 I 0.021 0.011 0.02i 0.02( 0.001 0.011 0.011 0.021 - 0.01 t -__- -__ -- -~ -- - _-- -_ - -- __ __ __ - __ - -- - 0.028 EP 1.31 3" Pipe TBD 06404 Group 2 Unity 0.018 0.018 0.012 0.014 0.014 0.024 0.024 - 0.008 0.024 -~ - __ 0.024 CS-137 activity (dpm/lOOcm2)

Eu-152 actlvlty (dpmll OOcm2) Eu-164 activity (dpmll00cm2)

Nb-B4 activity (dpm1100cm2)

Ag-I 08m activity (dpm/100cm2)

DO I 4.111 34 2,134 2,134 - 1,423 1,660 1,660 2,045 2,045 948 2,845 2,371 948 2,134 2,134 2,371 2,371 2,134 1,897 - 2,608 2,134 1,423 2,134 2,134 2,134 1,423 - 3,319 3,082 1,897 -~ -~__ -___ __ 2,845 -____ ____~___ _______ -__ ___ ~~~ 2 119 2 1 119 79 20,000 2,741 23,333 3,198 23,333 3,198 12 12 40.000 5.482 93 93 _ 159 159 -__ - __ 2 2 .- __ 12 12 40,000 5,482 4 4 13,333 ___~ - 1,827 12 12 40,000 5,482 12 12 40,000 5,482 10 10 33,333 4,568 - 4 4 13,333 1,827 9 9 30,000 4,111 4,111 9 9 30,000 4,568 10 10 - 33,333 4,568 9 9 30,000 4,111 8 8 26,667 _- 3,654 11 11 36,667 5,025 9 9 30.000 4.111 _____ ___- 10 10 33,333 __ 45 15 45 45 38 34 _______ ___ ~-__ 15 1 53 159 1 59 .- ~ - -. ._ 32 32 _____ 3 3 ._ 132 53 2 1 ~~ 24 27 ___~ 34 38 2 2 ._ - 16 24 9 9 30:OOO 4,111 9 9 30,000 4,111 6 6 20.000 2.741 24 24 16 -~___ 185 172 -- - _ 30 ~ 49 _ 3,082 1,897 ~- ___ 30 22 2 106 EP 1.31 3" Pipe TBD 06-004 Group 2 - Unity - 0.01 t 0.01t 0.02r 0.02: 0.02t 0.02f 0.011 0.02: 0.02: 0.01I 0.011 0.01t 0.01; 0.021 0.02; 0.02( 0.02f 0.01A 0.01f 0.01f 0.02: 0.02: 0.01: 0.011 0.01t 0.01f 0.01t 0.02r 0.02( ___ ____ __ 0.011 - __ -~ __-- -~ -0.03 __ - -~ __- __ ___ __ -- - Co-60 activity (total dpm) Cos0 activity (dpdl OOcm2) Eu-154 acttvity (dpm1100cm2)

Nb-94 activlty (dpdl OOcm2) Ag-108111 activity (dpdl00cm2)

Cs-137 activlty Eu-152 activity (dpdl OOcm2) (dpmll OOcrnZ) 2.134 34 ncpm 9 9 12 11 14 -___ 4,111 4,111 5,482 5,025 6,395 5,939 2,284 3,198 5,025 5,025 - 4.1 11 _____.- __ 2 2 ~-__- 34 2.608 42 40,000 36.667 3 2 3 3 ______ - 461667 43.333 ~ 27 2.608 42 35 13 E 1: f 1' 1' $ $ 1 1 ___- 13 19 30 30 24 19 24 ~~ ~~ ._ I 16.667 7 11 23,333 36.667 ____._ 361667 30,000 23,333 30,000 20,000 40,000 36,667- 33,333 43,333 23,333 26,667 26,667 36,667 50,000 _-_ 42 --%+---34 11 E 7 E E 1: 11 146 119 93 119 1,860-27 2.134 34 3,198 4.111 2 2 79 159 146 132 172 ~____ 2,741 5,482 5,025 4,568 3,198 3,654 3,654 5,025 6,852 5,025 2,741 4,111 4,111 3.654 5,939 ___ -~ -~ __ -____ -- 3,654 __-_- 1 3 2- 1; 1' .- 1c 1: l( 1: I 1 2 3 19 22 7 E t 1' l! 1' 30 2 36,667 20,000 30,000 26,667 30,000 26,667 40,000 33,333 - -- -___ -__ - ~ _- - ___. _____. 16 - E E 1 24 22 - ___ 2 2 5.482 4,568 EP 1.31 3" Pipe TBD 06-004 Group 2

  • C E a Y) U 1 z 125 1 26 127 128 129 131 132 - 133 - 134 135 136 137 138 139 140 141 130 ~ __ - Co40 activity Cod0 activity Cs-I37 activity Eu-152 activity Eu-164 activlty Nb-94 acUvtty Ag-lO8m activity gcpm ncpm (total dpm) (dpml1W)cmZ) (dpm1100cm2) (dpm1100un2) (dpm1100cm2) (dpm1100cm2) (dprn1100cmZ) 6 6 20,000 2,741 1,423 23 16 1 79 7 7 ___ 23,333 - 3,198 1,660 27 19 2 93 93 2 7 7 23,333 3,198 1,660 27 19 13 13 43,333 5,939 3,082 49 35 3 1 72 79 1 13 1 66 5 5 16,667 2,284 79 6 6 20,000 2,741 1,423 23 16 1 6 __ 6 20,000 2,741 1,423 16 1 79 12 12 40,000 5,482 2,845 45 32 3 - 1 55 1 99 15 15 50,000 6,852 3,556 57 .- 40 9 9 30,000 4,111 34 24 2 119 2,134 9 - 9 30,000 __ - - 4,111 2,134 34 . 2 119 24 17 ~___ 17 56,667 7,766 4,030 64 46 4 - ___.__-- ___ -__ ~- - _- -_- -__ _____ __ ____ __ ___ __ 16 __ - 6 6 20,000 2,741 1,423 23 __ - -. _- -_- - _-___ 19__ ~- 1,185 _____ ~ __ -___ 23 ____-_______ - - ___ - __ ___ _~__ - 3 __- __ --__ __ - ______. __ - __ .- __- 225 11 11 36,667 5,025 __ 2,608 42 30 2 146 10 10 33,333 4,568 2,371 38 27 2 1 32 212 16 16 53,333 7,309 3,793 61 43 4 185 14 14 46,667 6,395 3,319 53 38 3 ___ - ~ __ ~~ ____, MEAN _____- ____ ~ .. _- _ - ~ ~ ___ MEELAN-- -- -~ STODEV -- MAX MIN ~ - - -_-__ ~ ____ - __ ____ ~_ .- __-- - - __ __-~ 0.012 E] 0.010 0.012 0.012 . .. - - 0.032 0.006 5 of 5 SECTION 7 ATTACHMENT 2 11 PAGE(S)

BSYLVSPipeCrawler-002 Revision 4 Pipe Interior Radiological Survey Form Date: 715-p 6 Time: /o 2 %r Pipe ID#: 1.3 / Pipe Diameter:

3.0 Access Point Area:

47 TZrF4 Building:

-@ Elevation: - 27' System: D(2fifl5 Type of Survey Investigation Characterization Finalsurvey Other - Gross Co60 cs Detector ID# / Sled ID# M - f S' 4 &Z3r369 I I2.I Detector Cal Date: 3/6/0 6 Detector Cal Due Date: 3/~/4 Instrument:

z3m- I Instrument ID #: IgqDq4 ' Instrument Cal Date: 3 irr/loG Instrument Cal Due Date:

3 /f r/o , I I From the Daily Pipe Survey Detector Control Form for the Selected Detector Background Value 1 3 9 cpm MDcIistatic 15.9 CPm Efficiency Factor for Pipe Diameter 0 - 00 03 mcstatic 12(0,83 dpd 1 cm2 Is the MDCSktic acceptable?

a No (if no, adjust sample count time and recalculate MDCR,,,,,)

Comments:

f~,zc/,zr i fiP 2 -,3 (from detector efficiency determination) 1I Technician Signature Pipe Interior Radiological Survey REFERENCE COPY 0 l!&iia@ SERVICES JNC. Package Page 1 of& Attachment 3, Page 1 BSYLVSPipeCrawler-002 Revision 4 Pipe Interior Radiological Survey Form (Continuation Form) Date: ?/slob I Building:

7 Elevation:

-27 Pipe Diameter:

343 " Access Point Area: - 2 7 rw I System: - Pipe ID#: 183 t L.7 Package Page - of __ REFERENCE COPY Attachment 3, Page 2

Pipe Interior Radiological Survey Form BSYLVSPipeCrawler-002 Revision 4 Date: Pipe ID*: Building:

7 /C/O 6 Time: 1313 1~3 1 Pipe Diameter:

3.0 Access Point Area:

t Elevation:

-2s ' System : Type of Survey Investigation Characterization Final Survey,)( Other Gross Co60 cs - Detector ID# I Sled ID# ff-/Sf ZW369 I 1 Z{ Detector Cal Date: 3fGb G Detector Cal Due Date: d6h 7 Instrument:

23 sa -I Instrument ID #: /flow Instrument Cal Date: 3//sJd 4 Instrument Cal Due Date: 3//s/o 7 From the Daily Pipe Survey Detector Control Forrn for the Selected Detector Background Value

13. 9 cpm MDCRSktlC 115. 9 CPm Efficiency Factor for Pipe Diameter MDcstatlc 12683 dpd !f7m cm2 Is the MDCSbhc acceptable?

m- No Gf no, adjust sample count time and recalculate MDCR,,,,,)

0 a 'I9 0 03 (fiom detector efficiency determination)

Comments:

Technician Signature

& Pipe Interior Radiological Survey REFERENCE COPY Package Page 1 of3 Attachment 3, Page 1 BSI/LVSPipeCrawler-002 Revision 4 Pipe Interior Radiological Survey Form (Continuation Form) Date: 7/r/b 6 Pipe ID$: !'3/ Pipe Diameter: Access Point Area:

E - ,L~.h//et Building:

6V ., Elevation:

System: nr2t+tn)s BEHWIGPS INC. Package Page - 73 of __ Attachment 3, Page 2

BSVLVSPipeCrawler-002 Revision 4 Pipe Interior Radiological Survey Form Date: Pipe ID#: Building : OW0 -2s' System: - 7/6/06 Time: ?/ Pipe Diameter:

2,o Access Point Area:

act,,+ D CV Elevation:

Type of Survey Investigation Characterization Final Survey

'>( Other L, Gross Co60 c/' cs Detector ID# / Sled ID# 1 57 ' Z383Lq / Instrument:

2350 - I Instrument ID #: fsL9094- 121 Detector Cal Date: 3/6 /o G Detector Cal Due Date:

3/6h 7 Instrument Cal Date: 3// b-16 G Instrument Cal Due Date: 3/[5/0 7 From the Daily Pipe Survey Detector Control Form for the Selected Detector Background Value 1.7 cpm Efficiency Factor for Pipe Diameter MDCSLtlC e.. MDCRStatlC 14,8 cpm 0. 0 0 0 3 (&om detector efficiency determination) (If no, adjust sample count time and recalculate MDCbaUc) 00 cm2 Is the MDCshbc acceptable?

Comments:

mf ,,, om Pd SUlzvEd: E ?Z- 3 CQ)WPLI?T=

i2be;3 & A0 Technician Signature Pipe Interior Radiological Survey REFERENCE COPY Package Page 1 of 5 __ Attachment 3, Page 1 BSYLVSPipeCrawler-002 Revision 4 Pipe Interior Radiological Survey Form (Continuation Form) Pipe Diameter:

3.0" Access Point Area: a Date; 7/hk,b Pipe ID#: Building:

2' Elevation:

-2s' System: - 5 Package Page of __ REFERENCE COPY Attachment 3, Page 2 BSL'LVSPipeCraw-ler-002 Revision 4 Pipe Interior Radiological Survey Form (Continuation Form) II 3 I Pipe Diameter:

3 .o 'I Access Point Area:

QU,q i> Date: y,/~!o~ Pipe ID#: Building:

<I/ Elevation: - 2s System: iWr+f#Y REFERENCE COPY 0 Package Pag e3J - of __ Attachment 3, Page 2

.. 1 .. ..____.. .. I . ._, . SEE bWG. - PF- 0031 6 I I SECTION 7 ATTACHMENT 3 I PAGE(S)

DQA Check Sheet Design # EP 1.31 Revision # Original Survey Unit# I EP 1.31 Preliminary Data Review' Yes No NIA 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. X X 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 embeddedlburied piping static measurements below the DCGLw ? X ~ 4. 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?

lx 5. Was the instrumentation MDC for volumetric measurements and smear analysis c 10% DCGLW ? I I 1 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. X X 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 design, which accurately reflects the radiological status of the facility?

Gmphlcal 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 21, or 0.5 DCGLW (Class 317 X Data Anslysir 1x1 2. Is the mean of the sample data c DCGLw? 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? X 5. X X DCGLEMC (Class 11, < DCGLW (Class 21, or ~0.5 DCGLw (Class 3)? Is the result of the statistical test (S+ for Sign Test or W, for WRS Test) 2 the critical value? Comments:

Date 6 ./i;,o? FSS/ Characterization Manager (printlsign)

R. Case Date 7/3/17 FSS/Characterization Engineer (printlsign)

Page 1 of 1 SECTION 7 ATTACaMENT 4 I DISC Survey Unit Release Record Design # Survey Unit #(s) Description EP-1.33 I Revision # I Original I Page 1 of 3 1.33 1) Embedded Pipe (EP) Survey Unit 1.33 meets the definition of embedded pipe for Plum Brook Reactor Facility (PBRF). 2) EP 1.33 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 1.33 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.

I CS-0911 1 I 0 COPY I I Page 2 of 3 Survey Unit:

1.33 1 .o 2.0 3.0 4.0 5.0 History Description 1.1 The subject pipe system is the 3" purge line for Quad "C". The function of this pipe was to convey water from the one 3 inch riser in Quad "C" to the HD sump in Pump Room #22 on the Rx Building -25 A, where the pipe is currently breached.

EP 1.33 consists of approximately 90 feet in length fiom the pump room to the riser in Quad "C". The pipe section has a approximately six mitered elbows ranging hm 45" to 90". 1.2 Survey Design Information 2.1 2.2 EP 1.33 was surveyed IAW Procedure

  1. BSL/LVS-002.

IW? 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 90 survey measurements.

Surface area for the 3" ID piping is 729.7 cm2 for each foot of piping, corresponding to a total 3" ID piping surface area of 65,700 cm2 (6.6 m2) for the entire length of (90') of 3" 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 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 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 1.33 passes FSS. Background was not subtracted from the survey measurements and the Elevated Measurement Comparison (EMC) was not employed for this survey unit.

1 FSS Design ## EP 1.33 Number of Measurements

>MDC Number of Measurements Above 50% of DCGL 1 Revision # Original 71 0 Survey Unit: 1.33 Number of Measurements Above DCGL Mean 5.5 Statistical Summary Table 0 0.020 I Statistical Parameter I Pipe I Total Number of Survey Measurements 1 90 I Median I 0.018 Standard Deviation I 0.019 I Maximum 1 0.184 Minimum I 0.006 6.0 7.0 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 1.33 to be less than 1 mredyr. The dose contribution is estimated to be 0.020 mdyr 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 1.33 k Spreadsheet SECTION 7 ATTACHMENT 1 5 PAGE(S)

- _i - BSI EPBP SURVEY REPORT survey Location -27 TRENCH 2350-1 # 212223 Detector EHickncy 0.00013 44-62/204402-101 730 Detector-Sbd f cl~lrrkcorpon(.d 4 D.llsbr -th an9 Fkld BKG (sp) 5.2/5.116.4l7.0 FkM MDCR-I 10.8/10.7/11.7/13.0 II Nomi~l MDC (dpnq I284212842/2779/2779 Survey Measurement Results Total Number of Survey Measurements Number of Measurements Above 50% DCGL Number of Measurements Above DCGL 90 Number of Measurements

>MIX 71 0 0 Mean 0.020 Median 0.01 8 Standard Deviation 0.019 Maximum 0.184 Minimum 1 0.006 ROSENHAGEN Survey Technician(s) r TBD 06-004 Piping Group 2 SR-13 Radionuclide Distribution Sample EP 2-1 Measured Nudide C060 PasslFail FSS Pass Area Factor/EMC Used No MREM/YR Contribution I COMMENTS:

ACTIVITY VALUES NOT BACKGROUND CORRECTED Co-I37 activity (dpmll OOcmZ) Eu-I62 activity (dpmll OOcm2) CI C E f Cod0 activity gcpm ncpm (totaidpm) 1 2 3 4 6 6 46,154 4.3 4.3 33,077 4 4 30,769 3.6 3.6 27,692 I 91 5 101 4 ~___ 5 38,462 4 30.769 11 - 12 13 14 15 16 17 18 ~. 3.3 3.3 25,385 3.6 3.6 27,692 5.3 . 5.3 40,769 25,385 3.3 3.3 43,077 5.6 5.6 3 3 23,077 2.3 2.3 17,692 4 4 30.769 __- ___ - 22 23 24 25 26 27 28 - __ 4.6 4.6 351385 46,154 6 6 5 5 38,462 5.3 5.3 40,769

~-_____ 40,769 5.3 5.3 2.6 2.6 20,000 4 4 30,769 __. __-- _.__ ~ ___- - ___-_____

29 3 30 3 - 31 3.6 __ __ 32 2.6 3 23,077 3 23,077 3.6 27,692 2.6 2o:ooa EP 1.33 3" Pipe TBD 06-004 Group 2 - Unity - 0.02; 0.02( 0.01 I 0.01f 0.01! 0.01' 0.011 0.014 0.02: 0.011 0.01! 0.01(

0.024 0.011 0.021 0.01d 0.01 0.01 0.02 __ - __ __-_ - _. 0.02 0.01 0.02 -~ #I Co-80 activity (dpm1100cm2)

Eu-154 activity (dpm1100cm2)

Nb-S4 activity (dpm1100cm2)

Agl08m activity (dpm1100cm2)

I 37 27 25 - ______ 3 2 2 ~____ 183 6,325 4.533 131 122 110 ~- 4,217 3,795 3,479 2,425 4,217 3,163 5,271 4,217 3,479 3,795 5,587 3,479 5,903 3,163 2,425 6,325 5,587 3,479 4,849 6,325 5,271 - 5,587 5,587 4,217 3,163 3,163 3,795 2.741 __.____ __-__ ___-- ___ - 4,217 _____ - ___ 2,741 - .- ~__ ______ 2 2 _-- 1,805 1,258 - ____ - _.__ - 26 __ 2.736 44 101 70 51 3.31 3.31 25,385 61 2.31 2.31 17.692 14 25 ~____ 1 122 92 -_ 153 122 101 ______.- 1 lo 162 101 171 92 70 __ 22 33 31 2.900 .- 21 35 19 -___ 26 ___ 1,641 1,258 20 2,188 35 3,283 52 46 - - 2,900 -. 29 1,805 40 2,517 - 52 3,283 44 2,736 2,900 . 46 48 2,900 1,423 22 23 - 88.- - 35 2E 1,641 -- ._ 1.641 2E -~___ - ._ .__-___ __ - ~- _- ~ - __ - __ __ - - - 14 25 ~__ .. 37 33 .__ . 21 29 ___- 3.3 3.3 25.385 141 2 3 -- 3 3 ____ 3 1 2 19 22 16 ___ - - 1,970 1,423 22 EP 1.33 3" Pipe TBD 06-004 Group 2 COM) activity (dpm1100cm2) - gcpm - 2 2.3 3 2.6 4 3.e 4.2 2.2 2.e 4.e 2 3.E 1 .E 4 3.2 2.7 3.2 2.2 4 6.7 7.2 6.2 5.i 6.2 4.7 4.i 5.7 n b C - __ - .- _- & ___ L Cs-137 activlty (dpmMOOcm2) ncpm Eu-154 activity (dpm1100cm2)

_____ 12 ___- 19 16 25 2 2.3 3 2.6 4 3.6 4.3 2.3 2.6 4.6 2 3 3.6 - Nb-94 activlty Ag-1OBm activity (dpm1100cmZ) (dpm1100cm2)

""@ - 1 61 0.009 _-__ _____ 70 0.011 1 1 2 -- 2 ~ 92 -om 122- -Om8 1.6 2,108 2,425 3,163 2,741 4,217 3,795 4,533 2,425 2,741 4,849 2,108 3,163 3.795 ___~ 4 1,094 1,258 1,641 1,423 2,188 1,970 2,353 1,258 1,423 2,517 1,094 1,641 1.970 -______ - - ._ .. ___ __~ ___ ___- ______ 3.3 2.7 3.3 2.3 5 ___-. 22 2 27 2 ______ 16- -_ - _-__ 14 1 1 2 29 12 1 19 2 22 2 1 25 2 21 2 17 1 21 2 - - - 14 1 31 3 25- --__ - ~ 42 _ 3 _______ 45 4 39 3 35 3 ~- - 39 ~. - - - - 3 29 2 31 3 35 3 12 1 ~ -- __..___ - __-__ -~ __ 10 ~___ - - -__ ~- __ _ _________~

__ ____________

___ 29 - -~ 2 - - - - _._ A __ _. 110 -5016 131 0.020 70 0.011 79 0.012 141 0.021 61 0.009 92 0.014 110 0.016 122 0.018 101 0.015 ~- 101 0.015 70 0.011 153 0.023 122 0.018 ~____ 205 0.031 223 0.033 ___ 193 0.029 _-_ 174- 0.026 193 -0y029 ~ - -_ . ___-_____ - - - __ 49 .- 0.007 __ 83 0.012 - _- ___ - 144 0.021 1-44 -0.021 -- 153 0.023 174 - - 0026 61 0009 __ 6.7 7.3 6.3 5.7 6.2 -___ .-. I- 3,479 2.846 c G 5.7 1,805 1.477 15,385 17,692 23,077 30,769 27,692 33,077 17,692 20,000 35,385 15,385 23,077 27,692 12,308 ___- 30,769 25,385 20,769 25,385 17,692 38,462 30,769 20,000 ~- ___-_ 3,479 2,425 5.271 511538 1,805 1,258 2.736 I -~ 56,154 48.462 ____.___ 7,695 6,641 - 6,009 6,641 4,955 5,271 - - 6,009 2,108 ~- 4955 __ . ~- - - ._ 43,846 48,462 36,154 36,154 38.462 _____. _.____ - 3,994 3,447 3,119 3,447 2571 2,571 2,736 3,119 1,094 ___ -_ -~ -_ -- . - __ - - 875 4.217 2.188 2,188 +-3x Eu-152 activity (dpnVlOOcm2) 23 40 17 26 31 2of4 EP 1.33 3" Pipe TBD 06-004 Group 2 ncpm 4.2 4.7 2.: 3.: 4.7 4.i 2.7 2.i 5.: 2.3 2.: Co-60 activity Cog0 activity (total dpm) (dpm1100cm2) 38.462 I 5.271 33.077 4.533 _____ 17,692 33,077 33.077 4.533

._____ 77x2rTMi 2,425 23,077 3,163 20,769 1,370 10,000 30.769 4.21 7 _____ ____ ___- 17,692 2,425 25,385 3,479 28,462 3,900 4,955 36,154 ___ 13,077 1,792 20,769 2,846 36,154 4,955 40,769 5,587 _____ 17,692 2,425 30,769 4,217 4,533 33,077 23,077 3,163 310,000 42,483

_- _- __ __ -~ ~- _____ - ' Cb-137 actlvily Eu-152 activity Eu-154 activity Nb-B4 activity (d pmll OOcm 2) (dpmll OOcm2) (d pmll OOcm2) (d pmll OOcm 2) 2,736 44 1,641 26 2,353 38 41 2,571 61 44 3,830 2,571 41 __ 1,258 20 14 2,353 38 27 2,353 __ ~- ____ ______~ ~ __ 29 ___ -~ _____ __._ 1,258 1,477 24 71 1 38 I 2 20 I 1 2,188 35 25 2 20 14 1 2 21 2,024 32 23 2 2,571 41 29 2 15 11 1 1477 24 17 1 2,571 41 29 2 2,900 46 33 3 __ _.__ _______ 1,258 1,805 29 _-_ __ - ____ -_ - ___- 930 __ - ~ -- - -__ 22: 049-t - - 35312511-

-21 Ag-1 O8m actlvity (dpm/l OOcm2) 153 - 92 131 144 . .____--_ 214 144 7c 131 131 _ ~~~ ._ - - Unity 7 0.02: 0.01A 0.02( 0.02' 0.03:

0.02' 0.01 ' 0.02(

0.02( 0.01 0.014 0.01: 0.01 I 0.01 0.01! 0.01' 0.02 0.00; 0.01: 0.02 0.021 0.01 0.011 0.021 0.01' ___ - _. - 0.oa - ___ ___ ~- ___- 3of4 EP 1.33 3" Pipe TBD 06-004 Group 2 c C E a E" #I I I I I I I I I CO-BO activity gcpm ncpm (totaidpm)

Codd activity (dpm1100cm2)

-. _- Cs-137 activity Eu-152 activity Eu-I64 activity Nb-94 activity Ag-1OEm activh (dpm1100cm2) (dpm1100cm2) (dpmllOOm2) (dpm1100cm2) (dpm1100cmZ)

MEAN MEDIAN STD DEV MAX MI N .- _. __ -~~.~____

__ - - ~- __ . - .. - -. __ - . 0.020 0.01 8 0.019 0.006 SECTION 7 ATTACHMENT 2

Pipe Interior Radiological Survey Form Time: Date: Building:

S ys tern : ~ Elevation:

c zs Access Point Area: c", _. 7ZebTA Pipe Diameter:

3 " PipeID# /- 33 Type of Survey Investigation Characterization Other / Sled Size 3 If inch Detector:

slcj-L2 Detector ID #: pv++-/o/ Cal Date: /I. I %-or Cal Due Date: //* 13- 0 G Instrument:

GcroL/LIm 2 35 Instrument ID #: 3) 3@3 Cal Date: // ) 3 . 05 Cal Due Date: /lv7- c"6 From the Daily Pipe Survey Detector Control Form for the Selected Detector BackgroundValue r cpm d*:d, MDCRstatic

/CY. f cpm &LL P 7.- Efficiency Factor for Pipe Diameter 0 . 000 /d MDCStatiC 2,B 2 dpdl 00cm2 (taken from detector exAh&m~~~

i Is the MDC,,,, acceptable?

No (if no, adjust sample count time and recalculate MDCR,,ti,)

Comments:

/ nm- 5 cALd('L-;/

1 Pipe Interior Radiological Survey Radiological Survey Commenced: Date:

1 -/3 Time: 1 Lf- 3 ~3 Package Page 1 of 2- Attachment 3, Page 1

Pipe Interior Radiological Survey Form Date: /d. 1 Ip Time: 8 9) b Building:

2&AIG& Elevation:

-2.c Access Point Area: ,2/7 7h%fc++ System: fiu~i-, \ C ?uuvc PipeDiameter: Pipe ID # // 3 3 Type of Survey Investigation Other / Detector:

4g-Q > Detector ID #: 3c(/q0a--/or Sled Size 3 " inch Cal Date: 11. 17 '65 Cal Due Date: /I- 1'7 c'c Instrument:

93s) I Instrument ID #: 02 r XLa3 Cal Date: 11 J'7,Or Cal Due Date: /I- (7.0-3 From the Daily Pipe Survey Detector Control Form for the Selected Detector MDCRStatlC

/a. 7 CPm e@b C: Adsen:nA~

Efficiency Factor for Pipe Diameter 0 I 0 00 Id MDCStatIC 2 dpdl 00cm2 Background Value 3-3 CPm (taken fkom detector Is the MDCsUnc acceptable?

Yes No (Ifno, adjust sample count hme and recalculate MDCR,,,) Comments:

r&lI7/Ak4 41( d J a/ld w Pipe Interior Radiological Survey Radiological Survey Commenced:

Date: /a 1 b 03 The: 0 706 REFERENCE COPY Package Page Attachment 3 ofL Page 1

Pipe Interior Radiological Survey Form Date: /- 3. a4 Time: /b3d Building:

FlfcP tl- Elevation: - %.si Access Point Area:

-27 /'a 4 Type of Survey Investigation Characterization c-3 Final Survey Other Sled Size 3 '$ ' p u/WA inch ~, ~~ - PipeD# /. 33 F System: ,CL F Pipe Diameter:

3 fr Detector:

Detector ID #: dr23D?-/Z( Cal Date: Cal Due Date: /7-rJfW/UG Instrument:

23%-4 Instrument ID #: 21222 Y Cal Date: /? - f&f -fir Cal Due Date: l7 -+/-aC From the Daily Pipe Survey Detector Control Form for the Selected Detector Backgroundvalue t& { cpm MDCRSt,tlC

//r 7 CPm Efficiency Factor for Pipe Diameter MDCStatlC Comments:

cde71 kLt&7~0r3 JLcb3C;v 0

  • b 0 0 27 7 9 dpdl 00crn2 (taken from detector Is the MDCStatic acceptable?

a No (if no, adjust sample count time and recalculate MDCR,,,,)

/ Pipe Interior Radiological Survey Radiological Survey Commenced:

Date: / ' 3 - Time: / 030 REFERENCE COPY 0 Package Page 1 of A Attachment 3, Page 1 Pipe Interior Radiological Survey Form (Continuation Form) Package Page AWCRENCE COPY Attachment 3, Page 2

I Pipe Interior Radiological Survey Form Date: Building:

S ys tem : /c + 0 G Time: 0 g/= -f-&?& CT&\ Elevation: - L;)c && f-2 PipeDiameter: ,t Access Point Area: - 27 @ i. Pipe ID # /, 33 Type of Survey Investigation-. Characterization Final Survey Other K/ Detect or : 49'-L % Cal Date: ,I -J 3 -or Cal Due Date: /I -3 7-0 L9 Instrument:

23Tfl-I Instrument ID #: 91 9 a23 Cal Date:. 1'" 3 --d 5- Sled Size '3d:fiy' Sfed blhinch Detector ID #: 317-7 O)-/Z( Cal Due Date: ri-- I? -u b From the Daily Pipe Survey Qetector Control Form for the Selected Detector Backgroundvalue 7 cpm MD CRStat,, 17 CPm eR&y & P VL Efficiency Factor for Pipe Diameter MDCstatic 2 777 dpm/100cm2 Is the MDCstabc acceptable?

@ No 0 , 0001 3 (taken from detector7 (if no, adjust sample count time and recalculate MDCR,,,,)

Comments:

f ,/J q 47Ibf-f .fd/L,d 4-j I -y$P / A-3 /< 7-6 I Pipe Interior Radiological Survey Radiological Survey Commenced: Date:

1 ' qfl ' Time: b Package Page 1 of 2 Attachment 3, Page 1 j-Pipe Interior Radiological Survey Form (Continuation Form) /. 73 Package Page 3- of 21. Attachment 3, Page 2 EFERENCECOPY I E .- 3 .o n L m B SECTION 7 ATTACHMENT 3 I PAGE(S)

Design # EP 1.33 Prelimlnary Data Review' Revision # Original Survey Unit # EP 1.33 Answers to the following questlons should be fully documented in the Survey Unit Release Record Yes 6. Were the MDCs and assumptions used to develop them appropriate for the instruments and techniques used to perform the survey?

No IXI 7. Were the survey methods used to collect data proper for the types of radiation involved and for the media kina surveyed?

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. Have surveys been performed in accordance with survey instructions in the Survey Design? Is the instrumentation MDC for embeddedlburied piping static measurements below the DCGLw ? X X X 4. 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? Was the instrumentation MDC for volumetric measurements and smear anatysis .Z 10% DCGLw ? 5. 3. Have other graphical data tools been mated to assist in analyzing the data? I I Ix X X -~ ~~ 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? Comments:

X X 1. 2. Has a posting plot been created?

Has a histogram (or other frequency plot) been created?

Page 1 of 1 X X ~ ~ ~~ - -~ __ - ~ ~- ~ ~ ~ ~ - - 1. 2. 3. 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 e0.5 DCGLw (Class 3)7 4. Is the result of the Elevated Measurements Test e I .O? 5. Is the result of the statistical test (S+ for Sign Test or W, for WRS Test) 2 the critical value? Are all sample measurements below the DCGLW (Class 1 81 2), or 0.5 DCGLW (Class 3)? Is the mean of the sample data e DCGLw? X X X X X FSSlCharaderization Engineer (printlsign)

FSSI Characterization Manager (pfint/sign)

&fC Re&]/ R be SECTION 7 ATTACHMENT 4 1 DISC I Survey Unit Release Record Design # Survey Unit #(s) Description EP-1.82 1 Revision # 1 Original 1 Page 1 of 3 1.82 1) Embedded Pipe (EP)

Survey Unit 1.82 meets the definition of embedded pipe for Plum Brook Reactor Facility (PBRF). 2) EP 1.82 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 1.82 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 BSILVS-002, WEP 05-006, these determinations are appropriate for the types of radiation involved and the media being surveyed.

Date: Approval Signatures 0 COPY FSS Design

  1. EP 1.82 1 .o 2.0 3.0 4.0 5.0 Revision # Original Page 2 of 3 History/Description 1.1 The subject pipe system is the 3" purge line for Interim Storage Area. The function of this pipe was to convey water from the one 3 inch riser in Interim Storage Area to the HD sump in Pump Room #22 on the Rx Building -25 ft, where the pipe is currently breached.

EP 1.82 consists of approximately 34 feet in length from the pump room to the riser in Interim Storage Area. The pipe section has an approximately five mitered elbows ranging from 45" to 90". 1.2 Survey Design Information 2.1 2.2 EP 1.82 was surveyed IAW Procedure

  1. BSYLVS-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 16 survey measurements. Surface area for the 3" ID piping is 729.7 cm2 for each foot of piping, corresponding to a' total 3" ID piping surface area of 1 1,680 cm2 (1.1 m2) for the entire length of (1 6') of 3" piping.. 2.3 Survey Unit Measurement LOcationdData 3.1 Pipe intenor 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 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 1.82 passes FSS. Background was not subtracted from the survey measurements and the Elevated Measurement Comparison (EMC) was not employed for this survey unit.

I 5.5 Statistical Summary Table I J FSS Design # EP 1.82 Survey Unit:

1.82 Revision # Original Page 3 of 3 Statistical Parameter Total Number of Survey Measurements Number of Measurements

>MDC 13' Pipe 16 14 Mean Median I Number of Measurements Above 50% of DCGL I 0 0.019 0.018 ~~ r Number of Measurements Above DCGL Io Standard Deviation Maximum 0.008 0.037 Minimum I 0.006 I 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 1O?h 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 1.82 to be less than 1 mredyr. The dose contribution is estimated to be 0.01 9 mrerdyr based on the average of the actual gross counts measured.

Attachments 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 1.82 & Spreadsheet

___I I SECTION 7 ATTACHMENT 1 3, PAGE(S)

BSI EPIBP SURVEY REPORT TBD Oe-004 Piping ~mup SR-13 Radionudie Distribution Sample Measured Nudide Area Factor/EMC Used PasslFail FSS MREWR Contribution Pipe ID 1.82 Survey Location -27 TRENCH Survey Date 21-DeC-05 2350-1 # 212223 Pipe size 3" Detector Efficiency 0.00014 survey Time 0815 Detector-Sled

  1. 44-62/204402-101 DCGL o 240800 RP -w- bv - ~lkhq 730 1.1 FkM BKG 1-1 5.9 np.--bl Routine Survev X Field HDCR -I 11.3 2 EP 2-1 co60 No Pass 4 Total Number of Survey Measurements Number of Measurements Above 50% DCGL Number of Measurements Above DCGL 16 Number of Measurements

>MDC 14 0 0 Mean 0.019 Median 0.018 Standard Deviation 0.008 I 0.037 Maximum Minimum 0.006 ROSENHAGEN Survey Technidan(s) ~ ~~ COMMENTS:

ACTIVITY VALUES NOT BACKGROUND CORRECTED r r 1 6-/2-o7 RP Engineer 1 Date 8/12/2007 SECTION 7 ATTACHMENT 2 3 PAGE(S)

Pipe Interior Radiological Survey Form Date: / 2- 2 / -QI Time: 8 t7/T Building:

fLf Elevation: - Access Point Area: ChlCM Type of Survey Investigation Characterization Other J Sled Size -3 inch System: jj&,dfi~ &j~ Pipe Diameter:

3, I' Pipe ID # .I. 92 Detector:

hf 5'-6 2 Detector ID #: 2.0 YYO L - /o / Cal Date: I /-/7-0 3- Cal Due Date: I/-/ 7-6 6 Instrument:

23sv-/ Instrument ID #: az-22-7 Cal Date: f7Y 7- or Cal Due Date: / /-/ 7 -06 From the Daily Pipe Survey Detector Control Form for the Selected Detector Background Value L87 cpm Efficiency Factor for Pipe Diameter MDCStatlC 2 f?qz dpm/100cm2 r \% mmstaac /b3 CPm *?? Jebm, nhC1 T 0 - ~~'/~@aken from detector ' Is the MDCShh, acceptable?

ad No (ifno, adjust sample count the and recalculate MDCR,,,,)

Pipe Interior Radiological Survey Radiological Survey Commenced:

Date: / 1 /L'-flJ- Time: 0 *3/ 3- REFERENCE COPY 0 Package Page Attachment 3 Page 1 I I dpdl 00cm2 Position Feet into Pipe Count Time Gross counts Gross Net # from Opening (Inin) cpm cpm I1 @a/ I 3 Y ($3 ).I/& fllP IL 1 ?- 3 15 I 7 ' 13 '1 3 3 to 3.3 i I REFERENCE COPY U tY ir 3 Pt . IC 1s 3 rU tb 16 lb Attachment 3, Page 2 I I 9' 7 3 -3 5; ,3 I

SECTION 7 ATTACHMXNT 3 PAGE(S) t I ~ Design # Survey Unit # DQA Check Sheet ~ EP 1.82 Revision # Original EP 1.02 1. Has a posting plot been created?

I I ~ - 3. Is the instrumentation MDC for embedded/buried piping static measurements below the DCGLw ? Q. 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? 5, Was the instrumentation MDC for volumetric measurements and smear analysis < 10% DCGLW ? X 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?

2. Has a histogram (or other frequency plot) been created?
3. Have other graphical data tools been created to assist in analyu'ng the data?

X X 1. Are all sample measurements below the DCGLw (Class 1 & 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 DCGLEw (Class l), 4. Is the result of the Elevated Measurements Test

< 1 .O? Is the mean of the sample data

< DCGLw? X DCGLW (Class 2), or 4.5 DCGLw (Class 3)? 5. Comments:

Is the result of the statistical test (S+ for Sign Test or W, for WRS Test) 2 the critical value? X I' - Page 1 of 1 Form cs-o9/2 Rev 0 SECTION 7 ATTACHMENT 4 1 DISC Design # Survey Unit #(s) Description Survey Unit Release Record EP-Rx 150 I Revision#

I Original Page 1 of 3 EP-Rx 150 1) Embedded Pipe (EP) Survey Unit 150 meets the definition of embedded pipe for Plum Brook Reactor Facility (PBRF). 2) EP 150 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 150 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 performec 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. Approval Signatures Date: Form CS-09/1 Rev 0 0 COPY FSS Design # EP Rx 150 1 .o 2.0 3.0 4.0 5.0 Revision # Original Page 2 of 3 History/Description 1.1 The subject piping described in this report is an air supply line for equipment and accessories utilized in Quad B. This survey unit involves - 20' of air supply piping. Survey Design Information 2.1 2.2 EP Rx 150 was surveyed IAW Procedure
  1. BSILVS-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 729.7 cm2 for each foot of piping, corresponding to a total 3" ID piping surface area of 14,594 cm2 (1.5 m2) for the entire length of (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 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 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 150 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 1 FSS Design # EP Rx 150 Revision # Original Page 3 of 3 5.5 Statistical Summary Table Statistical Parameter Total Number of Survey Measurements Number of Measurements

>MDC 3" Pipe 21 12 Number of Measurements Above 50% of DCGL Number of Measurements Above DCGL 0 0 Mean Median 0.01 2 0.013 6.0 Documentation of evaluations pertaining to compliance with the unrestricted use limit of 25 mredyr and dose contributions fkom Embedded Pipe and radionuclides contributing 10% in aggregate of the total dose for both structural scenarios and soils. 6.1 A repeat QA survey was performed on this survey unit. It was concluded that the QA comparison results were acceptable based on the fact that all results differing by more than 20% were calculated to be less than 3% of the DCGL. A review of the survey results has shown that the dose contribution for EP Rx 150 to be less than 1 mrem/yr. The dose contribution is estimated to be 0.0 12 mrem/yr based on the average of the actual gross counts measured.

6.2 7.0 Attachments 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 Rx 150 & Spreadsheet Standard Deviation Maximum 0.004 0.022 Minimum 0.004 SECTION 7 ATTACFIMENT 1 3 PAGE@)

I - RP Engineer I Date &,J'U 6-20-07 l!iikw i. _i . BSI EP/BP SURVEY REPORT Pi- ID I Rxlso 11 Suwev Locatton 1 -25TRENCH 1 I survey Lhta 12112105 12113m I 23500-1 I 2 1 2223 Suwev fime I 1350/0756 I I OeQctor-Skd

  1. I 44-62/204402-101 Maximum I 0.022 Minimum 0.004 I ROSENHAGEN Survey Technician(s) - COMMENTS:

ACTMTY VALUES NOT BACKGROUND CORRECTED r

EP Rx 150 3" Pipe TBD 06-004 Group 2 I I I , I I 7 Unity - 0.014 0.013 0.014 0.010 0.01 0 0.007 0.010 0.022 0.01 3 0.015 0.016 0.01 3 - 0.008 0.004 0.01 1 0.016 0.016 0.010 0.01 3 0.014 0.008 0.012 0.01 3 - -- -- -- --- __- __- -__ - - 1 of 1 Survey Unit EP Rx 150 QA Worksheet I -. 1 1.7 1.7 12,143 1,664 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 19 20 2 3.7 1.3 4.3 3 4.7 3 4 2.3 4.3 2.7 3 4 1.7 2.7 2.3 2.3 3.3 3.3 2 3.7 1.3 4.3 3 4.7 3 4 2.3 4.3 2.7 3 4 1.7 2.7 2.3 2.3 3.3 3.3 14,286 26,429 9,286 30,714 21,429 33,571 21,429 28,571 16,429 30,714 19,286 21,429 28,571 12,143 19,286 16,429 16,429 23,571 23,571 1,958 3 , 622 1,273 4,209 2,937 4,601 2,937 3,916 2,251 4,209 2,643 2,937 3,916 1,664 2,643 2,251 2,251 3,230 3,230 21 4.3 4.3 30,714 4,209 ORlG Jnity Value 0.014 0.013 0.014 0.010 0.010 - 0.007 0.010 0.022 0.013 0.01 5 0.016 0.013 0.008 0.004 0.01 1 0.016 0.016 0.010 0.013 0.014 0.008 NOTE: ALL QUALITY ASSURANCE RESULTS DIFFERING BY MORE THAN 20% WERE LESS THAN 3% OF THE DCGL 1 3.3 3.3 23,571 3,230 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 19 20 3 3.3 2.3 2.3 1.6 2.3 5.3 3 3.6 3.7 3 2 1 2.7 3.7 3.7 2.3 3 3.3 3 3.3 2.3 2.3 1.6 2.3 5.3 3 3.6 3.7 3 2 1 2.7 3.7 3.7 2.3 3 3.3 21,429 23,571 16,429 16,429 11,429 16,429 37,857 21,429 25,714 26,429 21,429 14,286 7,143 19,286 26,429 26,429 16,429 21,429 23,571 2,937 3,230 2,251 2,251 1,566 2,251 5,188 2,937 3 , 524 3,622 2,937 1,958 979 2,643 3,622 3,622 2,251 2,937 3,230 1.958 % DlFF - 484 33.3 12.1 43.5 87.0 87.5 104.3 43.4 33.3 36.1 16.2 10.0 so.0 300.0 37.0 27.0 37.8 0.0 10.0 0.0 I 15.0 -

SECTION 7 ATTACEFMENT 2 7 PAGE(S)

Date: Building : System: f4 Pipe Interior Radiological Survey Form Elevation:

J zcp Access Point Area:

0- Mz:g" Pipe Diameter:

3 Pipe ID # - 1 Type of Survey Investigation Characterization QFal Survey 3 Other r Detector:

QW-4 s Detector ID #: &LjLJL; 7. --/u Cal Date: // f/7'05 Cal Due Date: f/ -/ 7 '06 Instrument:

LOL4M H33 1 Instrument ID #: 2233 Cal Date: //-/7 .dX Cal Due Date: //-/7 'U b From the Daily Pipe Survey Detector Control Form for the Selected Detector Background Value C- 9 cpm MDCRStatIC PrW cpm Efficiency Factor for Pipe Diameter MDCstatlc Z 842 dpm/100cm2

/f Sled Size inch 0 - 0 0 01 L/ (taken from detector Is the MDCskbc acceptable?

@ No (Ifno, adjust sample count tune and recalculate MDCR,,,,)

Comments:

/'d/7,/?( sLcad6y Pipe Interior Radiological Survey REFERENCE COPY U Package Page 1 ofL& Attachment 3, Page -1 .. '-

Pipe Interior Radiological Survey Form Date: I& /3-a,- Time: /3 7mr-6 Building:

>r &f)G Elevation: - 2 J~ Access Point Area:

@L14 0 System: Cv I itn. Pipe Diameter:

3y PipeID# Rrr 133 Sled Size 3 inch u lU7f Type of Survey Investigation Characterization-Other rl Detector:

CfY-G'L- Detector ID #: 20 vyfl2.r Cal Date: I/-/ 7-0)' Cal Due Date:

// -1 7 -0 c; Instrument:

7 3m-I Instrument ID #: Cal Date: /I-( 7 ~QJ- Cal Due Date:

From the Daily Pipe Survey Detector Control Form for the Selected Detector BackgroundValue

<g cpm MDCRStatiC

/os T cpm Efficiency Factor for Pipe Diameter 0- *DO&/ 4 MDcstatlc 2 %Lfz dpm/100cm2 Is the MDCstallc acceptable?

a- No (taken om detector (Ifno, adjust sample count time and recalculate iMDa,,) Comments:

COn,7/RltlAT'fBR) of' /%& $L,(Qbhy Fddm ]2-/2-03--

Pipe Interior Radiological Survey Package Page 1 of2 Attachment 3, Page 1 REFERENCE COPY

!I /' Pipe Interior Radiological Survey Form (Continuation Form) Position Feet into Pipe Count Time Gross Net # from Opening (min) cprn cpm ZD,fl #7x 150 (id{ &O f3 Z( (0 #I& dpdl 00cm2 Gross Counts I I I Package Page #- of&-. REFERENCE COPY Attachment 3, Page 2

_-- If Pipe Interior Radiological Survey Form Date: /- 6-t2f Time: o?ov Building:

Elevation: - LJ- Access Point Area: Qd A 0 d A;>c Pipe Diameter:

&-% UT Type of Survey Investigation Characterization Final Swey Qfl Sled Size gv17yl K\bt inch Detector:

YV-Q 21 Detector ID #: 21270/- I Cal Date: //-/ 7 Cal Due Date: / /- / 7- 54 Instntment:

23 m- I Instnrmerrt ID #: Zf ZLZ I Cal Date: //77-0 5- Cal Due Date: //47-a From the Daily Pipe Survey Detector Control Form for the Selected Detector BackgroundValue xr 7 cpm MDCRtatic

/or $7 CPm Efficiency Factor for Pipe Diameter 0 - 00 f3 (taken fiom detect0 MDC,,hC 2 7 74 dpdl OOcm' Is the MDCStatic acceptable?

No (ifno, adjust sample count time and recalculate MDCK,,) Comments:

Pipe Interior Radiological Survey Radiological Survey Commenced:

Date: /- 6 -0 6 Time: ofCrO Package Page 1 of/ Attachment 3, Page 1 Package Page *of - 7 REFERENCE COPY Attachment 3, Page 2

SECTION 7 ATTACHMENT 3 / PAGE@)

DQA Check Sheet Design # EP Rx150 Revision # Original Survey Unit # EP Rx 150 Preliminary Data Revlew' Answers to the following questions should be fully documented in the Survey Unit Release Record Yes No N/A I 1. 2. 3. 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? Is the instrumentation MDC for embedded/buried piping static measurements below the DCGLw ? X X X S,- 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 static measurements or soil samples addressed in the survey design? 5. Was the instrumentation MDC for volumetric measurements and smear analysis < 10% DCGLw ? I 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. X X Were "Special Methods" for data collection properly applied for the survey unit under review?

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 1. Has a posting plot been created?

X 2. Has a histogram (or other frequency plot) been created? 3. Have other araDhml data tools been created to assist in analyzing the data? X X 1. Are all sample measurements below the DCGLW (Class 1 8 2), or 0.5 DCGLw (Class 3)? If elevated areas have been identified by scans andlor sampling, is the average activity in each elevated area < DCGLEMC (Class l), Is the result of the Elevated Measurements Test

< 1 .O? X 2. Is the mean ofthe sample data < DCGLW? X 3. 4. X X DCGLW (Class 2), or e0.5 DCGLw (Class 3)? 5. Comments:

Is the result of the statistical test (S+ for Sign Test or W, for WRS Test) L. the aitiil value? X Page 1 of 1 SECTION 7 ATTACHMENT 4 1 DISC I I EP-Rx 1 60 Revision ## Original Design ## Page 1 of 3 Survey Unit

  1. (s) Description
2) EP RX160 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 Rx160 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 (JAW) the Babcock Services Incorporated (BSI)KVS-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.

0 COPY r FSS Design # EP Rx160 Revision I# Original 1.0 2.0 3.0 4.0 5.0 Page 2 of 3 HistoryDescription 1.1 EP Rx160 is a RT drain that terminates in the sump. The subject piping described in this report is integral to the drain system for the Reactor Building. The purpose of the system is to convey waste water from the RT to the sump. This system involves approximately 2 liner feet of drain system piping. EP Rx160 consists of 2 linear feet (') of 8 inch (") Inside Diameter (ID) piping starting in the -25 foot elevation RT to the sump. The total piping for EP Rx160 is 2'. Survey Design Information 2.1 2.2 1.2 EP Rx160 was surveyed IAW Procedure

  1. BSI/LVS-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 2 survey measurements.

Surface area for the 8" ID piping is 1,946 cm2 for each foot of iping, corresponding to a total 8" ID piping surface area of 3.982 cm (0.4 m2) for the entire length of (2') of 8" piping.. 2.3 P Survey Unit Measurement LocationdData 3.1 Pipe interior radiological survey forms are provided in Attachment 2 of this release record. Survey Unit InvestigationdResults 4.1 None Data Assessment Results Survey Unit:

Rx160 L 5.1 5.2 5.3 5.4 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 applyhg the Nuclide Fraction (NF), provided in TBD-06-004, the survey unit that is constituted by EP Rx160 passes FSS. Background was not subtracted

&om the survey measurements and the Elevated Measurement Comparison (EMC) was not employed for this survey unit.

I FSS Design # EP Rx 160 Revision # Original 5.5 Statistical Summary Table Page 3 of 3 r 8" Pipe Statistical Parameter Total Number of Survey Measurements Number of Measurements

>MDC 2 2 Mean Number of Measurements Above 50% of DCGL Number of Measurements Above DCGL I 0.016 I 0 0 I Median 1 0.016 t I 0.000 1 I Standard Deviation 1 0.016 I Maximum Minimum I 1 0.016 6.0 7.0 Documentation of evaluations pertaining to compliance with the unrestricted use limit of 25 mredyr and dose contributions fkom 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 160 to be less than 1 mredyr. The dose contribution is estimated to be 0.016 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 EP Rxl60 & Spreadsheet SECTION 7 ATTACHMENT 1 2 PAGE(S)

BSI EP/BP SURVEY REPORT Total Number of Survey Measurements Number of Measurements

>MDC Number of Measurements Above 50% DCGL Survey Measurement Results 2 2 0 Number of Measurements Above DCGL Mean 0 0.016 Median Standard Deviation

~ Maximum 0.016 Minimum 0.01 6 0.016 0.000 Survey Technician@)

I Rosen hanen Activity values are not background corrected.

OMMENTS:

RP Engineer I Date &/eI%&L+P 6-/2-o? 6/12/2007

  • C - : E" t gcpm =I (R tu 1 11 11 I 73.333 2(- -111- 73:333 EP Rx160 TBD 06-004 Group 2 1,956 I I -----+------

~~ Eu-152 activitv .. 31 31 -~___ ELI-164 activity .. 22 22 Nb-94 activity (dpmll M)crnZ) 2 Ag-108m activity (dpmM 00cm2) 109 109 MEAN MEDIAN - O.Olf 0.01t O.OO( 0.01f 0.01t - ___ __ __ .~ - 1 of 1 SECTION 7 ATTACmNT 2 [ PAGE(S)

, Position # I dpdl 00cm2 Feet into Pipe Count Time Gross Counts Gross Net from Opening (fin) cpm cpm B WLVSPipeCrawler-002 Revision 4 Pipe Interior Radiological Survey Form Time: /R KO Access Point Area: - Z 7 /A nqc Pipe ID#: / 6 0 Pipe Diameter:

I/ Building:

>( Elevation: -p7 System: Type of Survey Investigation Characterization Final Survey d* Other 4 Gross Co60 d cs Detector ID# 1 Sled ID# /M6/ ,/ LVS -y I /Q? Detector Cal Date: 20 D,5C - 03 Detector Cal Due Date:

2/3 - >sL Hd 6 Instrument:

9350 ,I Instrument ID #: a d39r~ Instrument Cal Date: / 7 a ,do 4 B5 htrument Cal Due Date:

/7rdcd*oc From the Daily Pipe Survey Detector Control Form for the Selected Detector Background Value 3,3 cpm MDCRstatic

/p.J cpm Efficiency Factor for Pipe Diameter OQOl4 (fiom detector efficiency determination) mcstatic 33'4 dpd 100 cm2 Is the MDC,,,, acceptable? Yes No (if no, adjust sample count time and recalculate MDCR,,,,)

/ Comments:

/W+&-L Swcvc y x/ fl w &&,.Me& bAj t7C P Technician Signature Pipe Interior Radiological Survey Package Page 1 ofJ Attachment 3, Page I SECTION 7 ATTACHMENT 3 / PAGE(S)

DQA Check Sheet Design # I EP Rx160 I Revision#

I Original I Surveyunit#

I EP Rx160 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? 1. X X 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 embeddedhuried piping stabc measurements below the DCGLw ? embeddedlburied piping Scan measurements below the DCGLW, or, if not, was the need for additional X X 5. Was the instrumentation MDC for volumetric measurements and smear analysis 10% DCGLW ? 1 I 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 invoked and for the media being surveyed?

5. X X Were "Special Methods" for data cdlectiin properly applied for the survey unit under review? 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?

Graphical Data Review 1. Has a posting plot bean created? X 2. Has a histogram (or other frequency plot) been mated? X 3. Have other graphical data tools been created to assist in analyzing the data?

1. Are all sample measurements below the DCGLW (Class I d 21, or 0.5 DCGLW (Class 313 X Data Analysl. 1x1 2. Is the mean ofthe sample data

< DCGLw? X X 3. If elevated areas have been identified by scans andor sampling, is the average activi in each elevated area DCGLEMC (Class 1), < DCGLw (Class 2), or e0.5 DCGLw (Class 3)? 4. Is the result of the Elevated Measurements Test 1 .O? X 5. X Is the result of the statistical test (S+ for Sign Test or W, for WRS Test) 1 the critical value? I- - Page 1 of I SECTION 7 ATTACHMENT 4 1 DISC

-- EP-RX 204 Revision # Original I Page 1 of 3 Design # Survey Unit #(s) Description

2) EP 204 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 204 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 (XAW) 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 I FSS/Characterization Engineer

/- 6 07 Technical Reviewer n , 7/3/07 FSS/Characterization Manager - csm/ 1 0 COPY FSS Design # EP Rx 204 I .o 2.0 3.0 4.0 5.0 Revision # On'ginal page 2 of 3 History/Description 1.1 The subject piping described in this report is an instrumentation line for equipment and accessories utilized in Quad B. This survey unit involves - 10' of instrument piping.

Survey Design Wormation 2.1 2.2 EP Rx 204 was surveyed IAW Procedure

  1. BSVLVS-002.

100% of the 2.5" ID pipe was accessible for survey. The accessible 2.5" ID pipe was surveyed by static measurement at one foot increments, for a total of 10 survey measurements. Surface area for the 2.5" ID piping is 608 cm2 for each foot of iping, corresponding to a total 3" ID piping surface area of 6,080 cm (0.61 m2) for the entire length of (10') of 2.5" piping.. 2.3 P 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 5.3 5.4 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 204 passes FSS. Background was not subtracted from the survey measurements and the Elevated Measurement Comparison (EMC) was not employed for this survey unit.

FSS Design # EP Rx 204 6.0 7.0 Revision # Original Page 3 of 3 5.5 Statistical Summary Table ~ ~ Total Number of Survey Measurements Number of Measurements

>MDC 2.5" Pipe Statistical Parameter

~~~ ~~~-~~ 10 10 Number of Measurements Above 50% of OCGL Number of Measurements Above DCGL Mean 1 0 0.257 Median Minimum Standard Deviation I 0.123 0.078 I Maximum I 0.521 I 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 204 to be less than 1 mredyr. The dose contribution is estimated to be 0.257 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 EP Rx 204 & Spreadsheet I I SECTION 7 ATTACHMENT 1 z PAGE@)

t Mean Median Standard Deviation Maximum Minimum BSI EP/BP SURVEY REPORT 0.257 0.227 0.123 0.521 0.078 I Number of Measurements Above DCGL i 0 I COMMENTS:

ACTIVITY VALUES NOT BACKGROUND CORRECTED 4 Eu-152 activity (dpm/100cm2) - 51.5 16.5 109.5 42 44 33.5 73.5 58 70 4a Eu-1 W actMty Nb-94 ectivily Ag-108m activity (dpm/100cm2) (dpm/100Gm2) (dpm/IWcm2) - 51.5 16.5 109.5 7c 42 469 150 44 33.6 73.5 333 28 1,638 107 9 525 5s 4c 997 I 708 343,333 110,000 730,000 466,667 280,000 293,333- 223,333 490,OO~ 393,333 266,667 59 3.482 EP Rx 204 2.5" Pipe TBD 06-004 Group 2 -~ 453 272 cos0 activ-ay cs-137 activity (dpm1100cm2) (dpm1100cm2) , -- 38 2,226 23 1.336 56,469 29,308 .~ --_ 400 305 669 537 364 _____ -- ___ ~- ___ 25,039 36,732 80,592 41,827 64.693 43,860 22,763 285 __ 24 1,399 217 18 1,065 475 39 2,337 1,876 382 32 259 21 1,272 --__ __ MEAN MEDIAN STD DEV MAX MIN __ - ___ - Unity - 0.245 0.07E 0.521 0.33: 0.20c 0.2E 0.15s 0.34E 0.281 0.19c 0.257 0.227 0.12: 0.521 0.071 - - 1 of 1 SECTION 7 ATTACHMENT 2 '4 PAGE(S) 1' 1 BSI/LVSPipeCrawler-002 Revision 4 Pipe Interior Radiological Survey Form &u"i. $ QCAlQD Date: 3-7 -Ob Time: 0 Y z,j" Pipe ID#: kx v Pipe Diameter:

2 *s'r Access Point Area: s~fi~~'~~~~ -LL+ Building:

FL% Elevation: - 2#- system: *JmuL&tJr L,:v'f Type of Survey Investigation Characterization Finalsurvey )d Other J Gross C060 J cs Detector ID# / Sled ID# YY-hZ #2/27dll /Z/ Detector Cal Date: 1 /- 7 -d3- Detector Cal Due Date:

/I-f 7 Instrument:

77 5m-Y Instrument ID #: Z43Vi98 //-f 7 -d b Instrument Cal Date: , /- i 3 -0 J- Instrument Cal Due Date:

From the Daily Pipe Survey Detector Control Form for the Selected Detector Background Value q17 cpm MDCRS,, 104 cpm Efficiency Factor for Pipe Diameter MDcstatlc 4m dPd /OD cm2 Is the MDC,,,, acceptable? Yes No (ifno, adjust sample count time and recalculate MDCl&J Comments:

POL *I = @F 20 R\ GMl- $OVt =fRy 7f2 q / [--(2p - >L rua\lw fLw&-T- k -e 0 0 V 0)s (from detector efficiency determination) Technician Signature Pipe Interior Radiological Survey Package Page 1 of- I REFERENCE COPY 0 Attachment 3, Page 1 i I 1 i j ! i , I i I I ! I I I I ! i I ! i ~ j I ,

d BSI/LVSPipeCrawler-O02 Revision 4 Date: Pipe ID#: Building: Pipe Interior Radiological Survey Form Time: LO YL / Type of Survey Investigation Characterization

~indsumey fl Other Gross (2060 / cs Detector ID# / Sled ID# VY-GZ 1 2 i Detector Cal Date: //I 772r Detector Cal Due Date: I/-/ 7-0 b ' Instrument:

23 s3-( Instrument ID #: 2 GXVE3&3 Instrument Cal Date: /I-/ 7 - CE Instrument Cal Due Date: // -f 7-0 From the Daily Pipe Survey Detector Control Form for the Selected Detector BackgroundValue q#7 cpm MDCRstatx

\**Y CPm Efficiency Factor for Pipe Diameter MDCSUtlC 4DW dPd /OD cm2 Is the MDC,,, acceptable?

m# No (Ifno, adjust sample count time and recalculate MDCL,,) Comments:

/~/,77,&<

i/ CY 0 0 t7 045 (from detector efficiency determination)

Package Page 1 of1 REFERENCE COPY 6ERVtCe5 INC. Attachment 3, Page 1 I ! i I 1 ! ! I I i i ! I ~ 1 ! I I I I i I I i ! p 0 i SECTION 7 ATTACHMENT 3 I PAGE(S)

I 1 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. OQA Check Sheet No Design # I EP Rx 204 I Revision # I Original I 5. Was the instrumentation MDC for volumetric measurements and smear analysis 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?

B. 10% DCGLw ? Were 'Special Methods" for data collection properly applied for the survey unit under review?

Survey Unit# I X X EP Rx 204 ~~~ ~~ ~ 1. 2. Has a posting plot been created?

Has a histogram (or other frequency plot) been created?

Preljminary Data Review' X X 3. Have other graphical data tools been created to assist in analyzing the data?

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? I X 3. Is the instrumentation MDC for embedded/buried piping static measurements below the DCGLW ? 1 X I 2. Is the mean of the sample data DCGLw? 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 5. Is the result of the statistical test (S+ for Sign Test or W, for WRS Test) 2 the critical value? DCGLEMC (Class 1 ), DCGLw (Class 2), or e0.5 DCGLw (Class 3)? 1 .O? ~~ 4. 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? X X X X Ix 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?

Graphical Data Revlew NIA - X X X Zomments:

CJ Page 1 of 1 Form cs-o9/2 Rev 0 SECTION 7 ATTACHMENT 4 1 DISC I Design # Survey Unit kys) EP-Rx 207 Revision # Description Original Page 1 of 3 2) EP 207 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 207 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 BSI/LVS-002, WEP 05-006, these determinations are appropriate for the types of radiation involved and the media being surveyed. Approval Signatures FSS/Characterization Manager 091 1 COPY FSS Design # EP Rx 207 Revision # Original 1.0 2.0 3.0 4.0 5.0 Page 2 of 3 History/Description 1.1 The subject piping described in this report is an instrumentation line for equipment and accessories utilized in Quad B. This survey unit involves - 3' of instrument piping. Survey Design Information 2.1 2.2 EP Rx 207 was surveyed IAW Procedure
  1. BSI/LVS-002.

100% of the 2" ID pipe was accessible for survey. The accessible 2.5" ID pipe was surveyed by static measurement at one foot increments, for a total of 3 survey measurements.

Surface area for the 2" ID piping is 486 cm2 for each foot of pi ing, corresponding to a total 2" ID piping surface area of 1,459 cm (0.15 m2) for the entire Iength of (3') of 2" 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 InvestigationslResults 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 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 207 passes FSS.

Background was not subtracted hm the survey measurements and the Elevated Measurement Comparison (EMC) was not employed for this survey unit.

FSS Design # EP Rx 207 Revision # Original 5.5 Statistical Summary Table Page 3 of 3 2* Pipe Statistical Parameter

-~ Total Number of Survey Measurements 3 Number of Measurements

>MDC 1 Number of Measurements Above 50% of DCGL Number of Measurements Above DCGL Mean 0 0 0.153 r Median Standard Deviation Maximum I 0.125 I 0.084 0.248 Minimum I 0.086 6.0 Documentation of evaluations pertaining to compliance with the unrestricted use limit of 25 rnredyr 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 207 to be less than 1 rnredyr. The dose contribution is estimated to be 0.153 mredyr based on the average of the actual gross counts measured.

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 207 & Spreadsheet c SECTION 7 ATTACHMENT 1 2 PAGE(S)

I Mean Median Standard Deviation Maximum Minimum * ~ La . BSI EPIBP SURVEY REPORT 0.153 0.125 0.084 0.248 0.086 TBD 06-004 Piping Group SR-13 Radiinudide Distribution Sample Measured Nuclide Area FactorEMC Used PasslFail FSS MREMNR Contribution 2 EP 2-1 C060 No Pass 4 ~ I COMMENTS:

ACTIVITY VALUES NOT BACKGROUND CORRECTED 6-21-0) RP Engineer I Date

?t C c, E e! a i I I gcpm EP Rx 207 2" Pipe TBD 06-004 Group 2 -137 aCtlvIty (dpm1100cm2)

EU-162 sctivity EU-l&4 actMty (dpm1100cm2) (dpmll~2)

Nb-94 actlvity (dpm1100cm2) 15,005 10,337 29.677 475 337 __~__ 14 .. 10 28 578 0.OM w I 0.24 JIlN I 0.08 1 of 1

.. SECTION 7 ATTACHMENT 2 Z PAGE(S)

I Position Feet into Pipe Count Time

). ' BSVLVSPipeCrawler-002 Revision 4 dpm/100cm2 1 Gross Counts Gross Net . Pipe Interior Radiological Survey Form fq?P5> n Qqao s 6-i me-3 5 5ltc-C Date: 3 8 6 Time: / Qc? Y Pipe ID#: 7 0 7 Pipe Diameter:

z 't Access Point Area: a 0 - RlGl.{ 7 Building:

Elevation:

--L 5- System: rjc;ip~ ntp,Cr L :L'% 72 rLrrL *\ J Type of Survey Investigation Characterization Final Survey A Other Gross Co60 J cs Detector ID# I Sled ID# VYy-62 &'/270/ J /2 1 Detector Cal Date: A/-/ 7-0 Detector Cal Due Date: //-/ 7-0 6 Litnunent Cal Date: / (7 7-0 5- Instrument Cal Due Date: rf-174d. Instrument:

urn- Instrument ID #: ZOJY88' From the Daily Pipe Survey Detector Control Form for the Selected Detector Background Value I? cprn MDCRSbtIC lt?Hq cpm Efficiency Factor for Pipe Diameter , 0 0 olb MDCStatlC 3,32109 dpd /Pp cm2 Is the MDCSbn, acceptable?

a No (dno, adjust sample count time and recalculate MDCL,) Cements: (,vi I; ec , S~Q Jt\/ (from detector efficiency determination)

/ - &%%&m-F 7- Technician Signature - -b f=& pc QLL~V Pipe Interior Radiological Survey Package Page 1 of I REFERENCE COPY Attachment 3, Page 1 I i ! I i 1. 1 I i ! c.

SECTION 7 ATTACHMENT 3 1 PAGE( S)

DQA Check Sheet Design # EP Rx207 Revision # Original Survey Unit # EP Rx 207 Preliminary Data Review' 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 NIA 1. 2. 3. 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 ? X ~~ 4. Was the instrumentation MDC for structure scan measurements, soil scan measurements, and static measurements or soil samples addressed in the survey design? embeddedlburied piping scan measurements below the DCGLw, or, if not, was the need for additional X 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 used to perform the suwey? 7. Were the survey methods used to collect data proper for the types of radiation involved and for the media being surveyed?

8. 9. X X Were 'Special Methods" for data collection properly applied for the survey unit under review?

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 facillfy3 Graphical Data Review ~ I. 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? X X ~~~~ ~ Data Analysis 1. X 2. Is the mean of the samnle data DCGLw? X Are all sample measurements below the DCGLw (Class 1 81 2), or 0.5 DCGLw (Class 3)? X X X 3. 4. 5. If elevated areas have been identifted by scans and/or sampling, is the avw activity in each elevated area < DCGLEW (Class l), 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) L the critical value? DCGLw (Class 2), or ~0.5 DCGLw (Class 3)? Comments: -r Page 1 of 1 CS-0912 1 1 SECTION 7 ATTACHMENT 4 1 DISC 7 Design ## Survey Unit Release Record EP-Rx208 I Revision#

I Original I Page 1 of 3 I 1 I EP-Rx 208 1) Embedded Pipe (EP) Survey Unit EP Rx-208 meets the definition of embedded pipe for Plum Brook Reactor Facility (PBRF). 2) EP 208 is a Class 1, Group 2 survey unit as per the PBRF Final Status Survey Plan (FSSP) and Technical Basis Document (TBD)-O6-004.

3) Surveys in EP 208 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 BSULVS-002, WEP 05-006, these determinations are appropriate for the types of radiation involved and the media being surveyed.

I Approval Signatures I Date: 0 COPY I I I I I i FSS Design # EP Rx 208 1 Revision # Original Page 2 of 3 1.0 2.0 3.0 4.0 5.0 HistoryDescription 1.1 The subject piping described in this report is an instrumentation line for equipment and accessories utilized in Quad B. This survey unit involves - 4' of instrument piping. Survey Design Information 2.1 2.2 EP Rx 208 was surveyed IAW Procedure

  1. BSI/LVS-002.

100% of the 2" ID pipe was accessible for survey. The accessible 2" ID pipe was surveyed by static measurement at one foot increments, for a total of 4 survey measurements. Surface area for the 2" ID piping is 486 cm2 for each foot of pi ing, corresponding to a total 2" ID piping surface area of 1,944 cm (0.19 m2) for the entire length of (4') of 2" piping.. 2.3 P Survey Unit Measurement Locatiom'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 mredyx 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 208 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 FSS Design # EP Rx 208 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 Number of Measurements Above DCGL 2" Pipe 4 0 0 0 I Maximum I 0.056 I Mean Median Standard Deviation r- Minimum 0.042 0.046 0.017 I 0.020 I 6.0 7.0 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 Rx 208 to be less than 1 mredyr. The dose contribution is estimated to be 0.042 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 EP Rx 208 & Spreadsheet I I SECTION 7 ATTACHMENT 1 z PAGE(S)

I Standard Deviation BSI EP/BP SURVEY REPORT 0.01 7 Maximum I 0.056 Minimum 0.020 i .- SR-13 Radionuclide Disttibution Sample Measured Nudide Area FactodEMC Used PasslFail FSS MREWR Contribution Survey Technician(s)

EP 2-1 C060 No PaSS 4 I Rosenhagen r- I 1 Survey Unit Classification TBD O6-004 PiDina Group 2 COMMENTS:

ACTMTY VALUES NOT BACKGROUND CORRECTED RP Engineer I Date 6 -Z/-O? I 8/21/2007 71 1 EP Rx 208 2" Pipe TBD 06-004 Group 2 Cos0 activity COS0 actlvity (total dpm) (dpm1100crn2)

CS-1 37 activity (dpm1100cm2) 21,875 4,497 62.500 12.850 8,995 -m 121257 .- ____- 4 2,334 6,669 4,668 6.335 _- Eu-1st activity (dpmll OOcm2) Eu-I S4 activity (dpm1100cm2) 2 6 4 130 373 26 1 -_ 354 LMX ulIN - Unity - 0.02( 0.03 ~ 0.031 0.05: 0.04: 0.04f 0.01: 0.oa 0.02( - - 1 of 1

! SECTION 7 ATTACHMENT 2 2 PAGE(S)

I BSI/LVSPipeCrawler-002 Revision 4 Pipe Interior Radiological Survey Form Date: 3-2 SOL Time: 130 0 px. 3 -2 L Pipe ID#: OF Pipe Diameter:

2 It Access Point Area:

de~s 2 bc9 K Type of Survey Investigation Characterization Final Survey

?Q Other fl Building:

p% Elevation: - z S pLI,+~ a System: TiJJfl4fl<.%r L;c/ 2, Gross (2060 4' cs , Detector ID# / Sled ID# Y4-62 /ZrZ70/ I /*/ Detector Cal Date: /7- dllJ .5r Detector Cal Due Date: /7 - ' 3 b Instrument:

>3!s+r Instrument ID #: 3.034w Tc :*-c Instrument Cal Date: 17 - d c' 4

  • cJL lnstnunent Cal Due We: /?'fie./ *c(.r From the Daily Pipe Survey Detector Control Form for the Selected Detector Backgroundvalue 4r? cpm M'DCRstatic r0.q cpm Efficiency Factor for Pipe Diameter MDCStatlC 33&$ dpd 10- cm2 Is the MDC,,,, acceptable?

a No (if no, adjust sample count time and recalculate MDa,,) 0 0 0 \ b (from detector efficiency determination)

/ Comments:

KMi-'7-f#L 5wLd L/ *)dTf: ?!.f,-TILd ) #2 p.Gg 12 jjax Sd/tiqiqLcd j) 04t; 'iu tp&-zorqv~

-?*?E AWE ?og*'fi-d ,sF 3d C/.J+L ;4 &fiC< Rdd@ (fl Lev fi 8 &~-z@bTfiL

@?i?EtP&L'"Tr w - Technician Signature I - Pipe Interior Radiological Survey REFERENCECOPY z/ Package Page 1 of- Attachment 3, Page 1 I j I ! j 1 I ! I ! I I ! ! i I ! I I I I I I i I I , b SECTION 7 ATTACHMENT 3 1 PAGE(S)

DQA Check Sheet 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. Design # 1 EP Rx208 I Revision#

1 Original 1 Yes No NIA X Survey Unit# I 3. 4. Was the instrumentation MDC for stnrcture 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? Is the instrumentation MDC for embeddedlburied piping static measurements below the DCGLW ? EP Rx 208 X 5. Was the instrumentation MDC for volumetric measurements and smear analysis < 10% DCGLw ? 0. 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. Were "Special Methods" for data collection properly applied for the survey unit under review? 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 X X X lx I. Has a posting plot been created?

Ix 3. Have other graphical data tools been created to assist in analyzing the data? 0. Is the data set comprised of qualified measurement results collected in accordance with the survey desian, which accurately relkts the radiological status of the facility?

X 2. Is the mean ofthe sample data DCGLW?

3. If elevated areas have been identi by scans andlor sampling, is the average activity in each elevated area < DCGLEK (Class l), 4. Is the result of the Elevated Measurements Test < 1 .O? DCGLw (Class 2), or e0.5 DCGLw (Class 3)? 2. Has a histogram (or other frequency plot) been created? I I lx 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:

'Y Page 1 of 1 Form Rev 0 CS-0912 SECTION 7 ATTACHMENT 4 1 DISC

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