ML072851270

Nasa Plum Brook Reactor, Embedded Pipe Survey Records

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

Text

National Aeronautics and Space Administration John H. Glenn Research Center Lewis Field Plum Brook Station Sandusky, OH 44870 August 16,2007 Reply to Attn of: QD U.S. NRC Region I11 Mr. William G. Snell, RIII/DNMS/DB 2443 Warrenville Road Suite 210

___

Lisle. IL 60532-4352

Subject:

Submittal of Embedded Pipe Survey Unit Release Records, Plum Brook Reactor Facility, License No. TR-3, Docket No. 50-30, and License No. R-93, Docket No, 50- 185

Dear Mr. Snell:

Enclosed for your review and assessment are copies of the following completed embedded pipe survey unit release records:

Survey Unit Release Record EP-Rx 130 Survey Unit Release Record EP-Rx 13 1 Survey Unit Release Record EP-1.38 Survey Unit Release Record EP- 1.4 1A-6 Survey Unit Release Record EP- 1.41A-4 Survey Unit Release Record EP- 1.42A-4 Survey Unit Release Record EP-Rx 155 Survey Unit Release Record EP-Rx 1 13D Survey Unit Release Record EP- 1.64 1-8 Survey Unit Release Record EP- 1.641-4 Survey Unit Release Record EP- Rx 150D Survey Unit Release Record EP-HL- 1 1 1 Survey Unit Release Record EP-Rx 161 Survey Unit Release Record EP-Rx 137 Survey Unit Release Record EP- 1.44 Survey Unit Release Record EP-Rx 084 Survey Unit Release Record EP-Rx 148D Survey Unit Release Record EP- 152D Survey Unit Release Record EP-Rx 149 As discussed during your on site inspection on June 25 through June 27, 2007, we will periodically submit the completed survey unit release records for your inspection. Further, as discussed at the exit meeting, it is our intention to begin grouting of the embedded piping that has been shown by the Final Status Survey to meet the dose criteria of Subpart E, Section 20.1402, 10 CFR Part 20.

-.

RECEIVED AUG 1 7 2007

2 If you have no issues with the records under this submittal, we will begin the grouting process on August 20,2007.

Should you have any questions or need additional information, please contact Mr. William Stoner of my staff, NASA Plum Brook Station, 6100 Columbus Avenue, Sandusky, OH 44870, at (4 19) 62 1 - 3349, or Mr. John Thomas of my staff, NASA Plum Brook Station, 6 100 Columbus Avenue, Sandusky, OH 44870, at (419) 621- 3357.

Sincerely, Keith M. Peecook Decommissioning Program Manager

Survey Unit Release Record

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Design # EP-Rx-084 1 Revision# I Original 1 Page 1 of 3 Survey Unit #(s) Rx-084

1) Embedded Pipe (EP) Survey Unit Rx-084meets the definition of embedded pipe for Plum Brook Reactor Facility (PBRF).

2) EP Rx-084is a Class 1, Group 3.1 survey unit as per the PBRF Final Status Survey Plan (FSSP) and Technical Basis Document (7BD)-06-004.

3) Surveys in EP Rx-084were performed using a scintillation detector optimized to measure gamma energies representative of Cs-137. Sample #EP 3-8 fiom Survey Request (SR)-13 was referenced for this decision.

4) Survey Instructions for this survey unit are incorporated into and performed in accordance with (IAW) the Babcock Services Incorporated (BSI)/LVS-002, Work Execution Package (WEP)05-006. Survey instructions described in this Description 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 Date:

FSS/Characterization Engineer I n /

cs-o9/1 0 COPY

FSS Design # EP Rx-084 Revision # Original Page 2 of 3 1.0 HistoryDescription 1.1 The subject pipe system is the 4 floor drain line from the Room 22 trench, which drains to the sump.

1.2 EP Rx-084 consists of 4 diameter piping that is approximately 6 feet in length.

2.0 Survey Design Information 2.1 EP Rx-084was surveyed IAW Procedure #BSL/LVS-002.

2.2 1W ! of the 4 ID pipe was accessible for survey. The accessible 4 ID pipe was surveyed by static measurement at one foot increments, for a total of 6 survey measurements.

2.3 Surface area for the 4 ID piping is 973 cm2for each foot of pi ing, P

corresponding to a total 4 ID piping surface area of 5,837 cm (0.6 m2) for the entire length of (approximately 6) of 4 piping..

3.0 Survey Unit Measurement hations/Data 3.1 Pipe interior radiological survey forms are provided in Attachment 2 of this release record.

4.0 Survey Unit Investigations/Results 4.1 None 5.0 Data Assessment Results 5.1 Data assessment results are provided in the EP/Buried Pipe (BP) Survey Report provided in Attachment 1.

5.2 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.

5.3 When implementing the Unity Rule, provided in Section 3.6.3 of the FSSP, and applying the Nuclide Fraction (NF), provided in Tl3D-06-004, the survey unit that is constituted by EP Rx-084 passes FSS.

5.4 Background was not subtracted fi-om the survey measurements and the Elevated Measurement Comparison (EMC) was not employed for this survey unit.

I I I FSS Design # EP Rx-084 I Revision # Original 1 ~age3of3 1 Survey Unit: Rx-084 5.5 Statistical Summary Table 4

Statistical Parameter Pipe L

Total Number of Survey Measurements 1 6 Number of Measurements >MDC

- ~

6 Number of MeasurementsAbove 50% of DCGL 0 Number of Measurements Above DCGL 0 Mean 0.0052 Median 0.0051 Standard Deviation 0.0009 Maximum 0.0065 Minimum 10.0037 6.0 Documentation of evaluations pertaining to compliance with the unrestricted use limit of 25 mredyr and dose contributions fiom Embedded Pipe and radionuclides contributing 10% in aggregate of the total dose for both structural scenarios and soils.

6.1 A review of the survey results has shown that the dose contribution for EP Rx-084to be less than 1 mredyr. The dose contribution is estimated to be 0.005 rnredyr based on the average of the actual gross counts measured.

7.0 Attachments Attachment 1 - BSI EPBP Survey Report Attachment 2 - Pipe Interior Radiological Survey Form Attachment 3 - DQA Worksheet

SECTION 7 ATTACHMENT 1 z PAGE(S)

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I BSI EPIBP SURVEY REPORT Pipe ID RxQW Survey Location Rm-22 trench Survey Date 19-Apr-07 23!500-1# 2 1223 Detector-Sled # 44-1 591247696101 Median 0.0051 Standard Deviation 0.0009 Maximum 0.0065 Minimum 0.0037 STOCK Sunrey Technician(s)

ACTIVITY VALUES NOT BACKGROUND CORRECTED RP Engineer I Date BJ & wo-07 711012007

EP Rx-084 4" Pipe TBD 06404 Group 3.1 1of1

I SECTION 7 ATTACHMENT 2 2PAGE(S)

BSULVSPipeCrawler-002 Revision 4 Pipe Interior Radiological Survey Form Date: 4//9/0 7 Time: 0817 Pipe ID#: - 5?4 Pipe Diameter: -4 , Access Point Area: k,&- mw,+

Building: @ Elevation: 7.7 System: &j- /lv g SUP4 Type of Survey Investigation Characterization Final Survey 3( Other /

Gross C06O A b cs /

Detector ID#/ Sled ID# 49- yq -2 $76 4G I lo1 Detector Cal Date: 11 / I >-/&I 6 Detector Cal Due.Date: II 1 5/07 Instrument: 3,3 1 1 Instrument ID #: Zfrtz3 Instrument Cal Date: 1 5+(& Instrument Cal Due Date: I ( / [ +q I

From the Daily Pipe Survey Detector Control Form for the Selected Detector BackgroundValue GI 7 cpm MDCR,,fic I it 2 CPm Efficiency Factor for Pipe Diameter 0 000Zb (from detector efficiency determination)

Is the MDC,,,,, acceptable? @ No (if no, adjust sample count time and recalculate h4DC%,,,,)

Comments: I7 - t - Is;?&

v ~rrirPuvE Technician Signature Pipe Interior Radiological Survey Package Page 1 of &

0 REFERENCE COPY Attachment 3, Page 1

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SECTION 7 ATTACHMXNT 3 I PAGE(S)

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DQA Check Sheet

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Design # EP Rx-084 Revision # Original Survey Unit # EP Rx-084 Preliminary Data Review' Answers to the following questions should be fully documented in the Survey Unit Yes No NIA Release Record 1, Have surveys been performed in accordance with survey instructions in the Survey Design? X

2. Is the i n x m e k t i o n MDC for structure static measurements below the DCGLWfor Class 1 and 2 X survey units, or below 0.5 DCGLw for Class 3 survey units?

3. Is the instrumentation MDC for embeddedburied piping static measurements below the DCGLw ? X

4. Was the instrumentation MDC for structure scan measurements, soil scan measurements, and embeddedhuried piping scan measurements below the DCGLW,or, if not, was the need for additional X static measurements or soil samples addressed in the survey design?

5. Was the instrumentation MDC for volumetric measurements and smear analysis z. 10% DCGLw ? X 5, Were the MDCs and assumptions used to develop them appropriate for the instruments and techniques 7.

used to perform the survey?

Were the survey methods used to collect data proper for the types of radiation involved and for the Ix/

media being surveyed?

3. Were 'Special Methods" for data collection property applied for the survey unit under review? X

3. Is the data set comprised of qualified measurement results collected in accordance with the survey X design, which accurately reflects the radiologicalstatus of the facility?

Graphical Data Review

1. Has a posting plot been created? I I l x

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

3. Have other graphical data tools been created to assist in analyzing the data? X Data Analysis I.

~~

Are all sample measurements below the DCGLw (Class 1 & 2), or 0.5 DCGLw (Class 3)? 1 x 1 I

2. Is the mean of the sample data DCGLw? X

3. If elevated areas have been identified by scans andlor sampling, is the average activity in each X elevated area DCGLEMC (Class l), < DCGLW(Class 2), or ~ 0 . 5 DCGLW(Class 311

4. Is the result of the Elevated Measurements Test < 1.O? X

5. Is the result of the statistical test (S+ for Sign Test or W, for WRS Test) the critical value? X

mments:

I' pZ-l CS-0912 I Rev0 1 Page 1 of 1

Design # EP-Rx 148D Revision ## Original Page 1 of 3 Survey Unit #(s) Rx 148D

1) Embedded Pipe (EP) Survey Unit Rx 148D meets the definition of embedded pipe for Plum Brook Reactor Facility (PBRF).

2) EP Rx 148D is a Class 1, Group 2 survey unit as per the PBRF Find Status Survey Plan (FSSP) and Technical Basis Document (TBD)-06-004.

3) Surveys in EP Rx 148D were performed using a scintillation detector optimized to measure gamma energies representative of CO-60.Sample #EP 2-1 from Survey Request (SR)- 13 was referenced for this decision.

4) Survey Instructions for this survey unit are incorporated into and performed in accordance with (IAW) the Babcock Services Incorporated (BSI)/LVS-002, Work Execution Package (WEP)05-006. Survey instructions described in this Description document constitute Special Methods and the survey design used in the acquisition of survey measurements.

5) Instrument efficiency determinations are developed in accordance with the BSVLVS-002, WEP 05-006, these determinations are appropriate for the types of radiation involved and the media being surveyed.

FSS Design # EP Rx 148D Revision # Original Page 2 of 3 1.o HistoryDescription 1.1 The subject pipe system is the 0.75 Quad B system line.

1.2 EP Rx 148D is approximately 16 feet in length.

2.0 Survey Design Information 2.1 EP Rx 148D was surveyed IAW Procedure #BSI/LVS-002.

2.2 100% of the 0.75 ID pipe was accessible for survey. The accessible 0.75 ID pipe was surveyed by static measurement at one foot increments, for a total of 16 survey measurements.

2.3 Surface area for the 0.75 ID piping is 182 cm2for each foot of pi ing, 4

corresponding to a total 0.75 ID piping surface area of 3,101 cm (0.3 m2) for the entire length of (16) of 0.75 piping..

3.0 Survey Unit Measurement Locations/Data 3.1 Pipe interior radiological survey forms are provided in Attachment 2 of this release record.

4.0 Survey Unit InvestigationslResults 4.1 None 5.0 Data Assessment Results 5.1 Data assessment results are provided in the EP/Buried Pipe (BP) Survey Report provided in Attachment 1.

5.2 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.

5.3 When implementing the Unity Rule, provided in Section 3.6.3 of the FSSP,and applying the Nuclide Fraction (NF), provided in TBD-06-004, the survey unit that is constituted by EP Rx 148D passes FSS.

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

FSS Design ## EP Rx 148D Revision # Original Page 3 of 3 5.5 Statistical Summary Table I I 0.75" Statistical Parameter Total Number of Survey Measurements 16 Number of Measurements >MDC 12 Number of Measurements Above 50% of DCGL 0 Number of Measurements Above DCGL 0 Mean 0.0441 '

Median 0.0423 Standard Deviation 0.0147 Maximum 0.0725 I Minimum 0.0161 6.0 Documentation of evaluations pertaining to compliance with the unrestricted use limit of 25 mredyr and dose contributions from Embedded Pipe and radionuclides contributing 10% in aggregate of the total dose for both structural scenarios and soils.

6.1 A review of the survey results has shown that the dose contribution for EP Rx 148D to be less than I mredyr. The dose contribution is estimated to be 0.044 mredyr based on the average of the actual gross counts.

7.0 Attachments Attachment 1 - BSI EPBP Survey Report Attachment 2 - Pipe Interior Radiological Survey Form Attachment 3 - DQA Worksheet Attachment 4 -Disc containing RR for EP Rx 1.48D & Spreadsheet

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SECTION 7 ATTACHMENT 1 2 PAGE(S)

clii BSI EPJBP SURVEY REPORT

-I Pipe ID Survey Date survey Time 02-Aug-06 1O:%

Survey Location 2350-1 #

DetectorSled #

-27 Trench Loop Drain 189094 0047-no sled Pipe Size 0.75 DCGL 1- 2.41 E 4 5 Field BKG11- 18.3 Routine Survey Field MDCRmm) 17.8 Nominal MDC wpnnooantl 7,631

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Survey Measurement Results Total Number of Survey Measurements 16 Number of MeasurementsM D C 12 Number of Measurements Above 50% DCGL 0 Number ofMeasurementsAbove DCGL 0 Mean 0.0611 Median 0.0423 Standard Deviation 0.0147 Maximum 0.0725 Minimum 0.0161 STOCK Survey Technician@)

Measured Nuclide C0-60 Area FactorlEMC Used NO Pass/Fail FSS Pass MREM/YR Contribution <l OMMENTS:

CTlVlTY VALUES NOT BACKGROUND CORRECTED RP Engineer IDate 7117RM17

EP Rx 1480 0.75" Pipe TBD 06-004 Group 2

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C0-80 activity Cos0 activity Cs-137 activity Eu-162 activity Eu-154activity Nb-94 activity AglOBm activity ncpm (dpmllOOcm2) (dpmll OOcm2) (dpmll OOcm2)

Unity (total dpm) (dpmll OOcm2) (dpmll OOcm2) (dpmll OOcm2)

._~~

10 16.949 9,292 4,818

- 0.04(

11 __ 5,300

__ ___ .- - -0.04~

-_

___ ~ _ _ _ ._ _- 7,433

._ -

3,855 62 ~ 44 4 .- 214 -

0.03; 4 .__ -

161949 9.292

- -~_ _ 4.818 77 54 5 .- ~ ______ 267 0.04(

___

_ _ _ _ 20,339 ___ 11,150 5,782- _-

92 65 5 321 - 0.04I

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30,508 16,725 8,673

__ - 139 98 8 -_

48 1 ~-0.07;

__.

23,729 13,009

__ 6,745 _ _ 108 76 6 374 0.0%

6,780 3,717 1,927 31 22 __ 2 107 0.01t 11,864 _ ~~

6,504 _ _ . _3,373

___ ~ _ _ _ 54 _ 38 3 187 __0.021

__

- 25,424 -- _ _13,938 -~

7,227

-- 116 .

..

82 7 ____- 401 ~-0.06(

___15,254 --

8,363 4,336 .__ 69- 49 4 24 1 0.03t

_ _ 15- 25,424 13,938- - 7,227 ___- 116 82

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7 401 0.06(

7 11,864 __ 6,504

- __ - 3,373

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54 38 3 ____ 187 0.021

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14 _ _ 23,729 _ ~ -13,009 6,745

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108

-._-_______________76 6 ~ _ _374 _ _

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0.03 E - __

15,254 ____ 8, 3 63 ~- ___ 4,336 - 69 49 __--- 4 24 1 0.03t 1; 207339 11~150

__ - ~-___ 5,782 92 65 5 321 0.041

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0.01!

0.07:

- 0.0m lofl

SECTION 7 ATTACHMENT 2 3 PAGE(S)

I BSI/L,VG~~~C~

Revision 4 Pipe Interior Radiologid Survey

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I BSYLVSPipeCrawler-002 Revision 4 Pipe Interior Radiological Survey Form (Continuation Form)

Date: Ic!z Pipe ID#: Pipe Diameter: 75 -

Access Point Area: 2 7 ' w d

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• v Building: (!& Elevation: I System: k D P Drnrt/

Package Page 2of 3 I REFERENCE COPY I Attachment 3, Page 2

SECTION 7 ATTACHMENT 3 I PAGE(S)

DQA Check Sheet Design #

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EP Rx 148D I Revision # I Original I Survey Unit # EP Rx 148D Preliminary Data Review' Answers to the following questions should be fully documented in the Survey Unit Yes No NIA Release Record

1. Have surveys been performed in accordance with survey instructions in the Survey Design? X

2. Is the instrumentationMDC for structure static measurements below the DCGLw for Class 1 and 2 X survey units, or below

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0.5 DCGLw for Class 3 survey units?

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3. Is the instrumentation MDC for embeddedlburiedpiping static measurements below the DCGLw ? X

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 X static measurements or soil samples addressed in the survey design?

5. Was the instrumentationMDC for volumetric measurements and smear analysis < 10% DCGLW? X

6. Were the MDCs and assumptions used to develop them appropriate for the instruments and techniques X

used to perform the survey?

7. Were the survey methods used to collect data proper for the types of radiation involved and for the X

media being surveyed?

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

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

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

1. Are all sample measurements below the DCGLw (Class 1 812), or 0.5 DCGLW(Class 3)? 1 x 1 I

2. Is the mean of the sample data DCGLW? X

3. If elevated areas have been identified by scans andlor sampling, is the average activity in each elevated area .C DCGLEMC (Class l),< DCGLW(Class 2), or <0.5 DCGLw (Class 3)?

x

4. Is the result of the Elevated Measurements Test 1.O? X

~

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

1 ::1 cs-0912 Page 1 of 1

SECTION 7 ATTACHMENT 4 1 DISC

Survey Unit Release Record Design # EP-Rx 137 Revision # Original Page 1 of 3 Survey Unit #(s)

2) EP Rx 137 is a Class 1, Group 2 survey unit as per the PBRF Final Status Survey Plan (FSSP) and Technical Basis Document (TBD)-06-004.

3) Surveys in EP Rx 137 were performed using a scintillation detector optimized to measure gamma energies representative of CO-60. Sample #EP 2-1 h m 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 Description 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 Date:

1 FSS/Characterization Manager I ,/////fl 1 1 Y

cs-o9/1

FSS Design # EP Rx 137 Revision # Original Page 2 of 3 1.o HistoryDescription 1.1 The subject pipe system is the 1.5 inch line 1.2 The pipe is approximately 9 feet in length.

2.0 Survey Design Information 2.1 EP Rx 137 was surveyed IAW Procedure #BSI/LVS-002.

2.2 100% of the 1.5 ID pipe was accessible for survey. The accessible 1.5 ID pipe was surveyed by static measurement at one foot increments, for a total of 9 survey measurements.

2.3 Surface area for the 1.5 ID piping is 365 cm2for each foot of pi ing, 4

corresponding to a total 1.5 ID piping surface area of 3,283 cm (0.3 m2) for the entire length of (approximately 9) of 1.5 piping..

3.0 Survey Unit Measurement LocationsData 3.1 Pipe interior radiological survey forms are provided in Attachment 2 of this release record.

4.0 Survey Unit InvestigationsResults 4.1 None 5.0 Data Assessment Results 5.1 Data assessment results are provided in the EPBuried Pipe (BP)Survey Report provided in Attachment 1.

5.2 All measurement results are less than the Derived Concentration Guideline Level (DCGL) for radionuclide specific EP that corresponds to the 1 mrem/yr dose goal established in Table 3-3 of the FSSP.

5.3 When implementing the Unity Rule, provided in Section 3.6.3 of the FSSP, and applying the Nuclide Fraction 0, provided in TBD-06-004,

_ _ ~ - __ _ ~ - _ ~

the survey untt that is co&tuted bY Kri37p a s s e m r

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5.4 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 137 Revision # Ori@ Page 3 of 3 5.5 Statistical Summary Table 1.5 Statistical Parameter Pipe I Total Number of Survey Measurements 1 9 Number of Measurements >MDC 4 Number of MeasurementsAbove 50% of DCGL 0 Number of Measurements Above DCGL 0 Mean 0.0097 Median 0.0085 I Standard Deviation 10.0034 I Maximum 10.0149 Minimum 10.0042 6.0 Documentation of evaluations pertaining to compliance with the unrestricted use limit of 25 mrem4r and dose contributions h m Embedded Pipe and radionuclides contributing 10% in aggregate of the total dose for both structural scenarios and soils.

6.1 A review of the survey results has shown that the dose contribution for EP Rx 137 to be less than 1 mredyr. The dose contribution is estimated to be 0.010 mrendyr based on the average of the actual gross counts

~-~ __ meas ured.

___ _____.____--- ___

7.0 Attachments Attachment I - BSI EPBP Survey Report Attachment 2 - Pipe Interior Radiological Survey Form Attachment 3 - DQA Worksheet Attachment 4 - SURR EP RX 137 8z Spreadsheet Disc

SECTION 7 ATTACHMENT 1 z PAGE(S)

BSI EPIBP SURVEY REPORT I Pi- ID Rx 137 Survey Location Drain Line 44.2 Survey Date 22-Few 23500-1# 212223 Survey Time 10:50 DetectorSkd# 4442# 212701l121 L

I Pipe Size 1.5 2.41E W Detector Efficiency 0.00028 365 0.3 4.9 X 10.6 Nominal MDC 1dpn-4 9,688 jurvey Measurement Results Total Number of Survey Measurements 9 Number of Measuments >MDC 4 Number of Measurements Above 50% DCGL 0 Number of Measurements Above DCGL 0 Mean 0.0097 Median 0.0085 Standard Deviation 0.0034 Maximum 0.0149 Minimum I 0.0042 DEBRAUX Survey Technician(s)

Survey Unit Classification I 1 TBD OR004 Piaina G ~ U D 7 I SR-13 RadionudideDistribution Sample Measured Nudide I EP 2-1 A m Factor/EMC Used No Pass/FailFSS Pass MREMlYR Contribution <l COMMENTS:

ACTMTY VALUES NOT BACKGROUNDCORRECTED RP Engineer I Date 7 07 1

EP Rx 1.37 1.5" Pipe TBD 06-004 Group 2 1

I I

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Cogg activity Cs-137 actlvity Eu-IS2 activity Nb-94 aetlvity (dpm1100cm2) (dpm/100cm2) (dpmllOOcm2)

Unity (dpm1100cm2) 3,426 1,777 28 2 99

-0.01 f 1,958 1,015 16 1 56 O.OOE

__ 1.5 ~- 5,357 1,468 76 1 12 1 42 0.OM 1 3,571 979 508 8 0 28 O.O@

2 7.143 1,958 1,015 16 1 56 O.OOE 21 7.143 1,958 1,015 16 i 11 1 56 0.001 TJ-7 2,937 2,937 1,523 1,523 24 24 --I-+ 1 1

85 85 0.01 I 0.01:

-+= 2.2 2.5 8.929 2.447 1,269 20 14 1 70

-0.011

-+----+--

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I MEAN MEDIAN 5TD DEV 0.01(

0.001 0.00:

w 0.01!

MAN I -0.001 lofl

SECTION 7 ATTACHMENT 2 z PAGE@)

I BSVLVSPipeCrawler-002 Revision 4 Pipe Interior Radiological Survey Form Date: 2-tZ-06 Time: 1o m 5 m?,

Pipe ID#: k p 37 Pipe Diameter: f .a- AccessPointArea: c Building: e* Elevation: - System:

Type of Survey Investigation Characterization FinalSurvey7( 0th Gross Co60 J cs DetectorID#/SledID# YY-62 @ Z # 270f / /z/

Detector Cal Date: //-/7 - - Detector Cal Due Date: d //I7-3&

Instrument: 23- -t Instnunent ID #: UILLL3 Instrument Cal Date: //-r 7 ~ 4 - Instrument Cal Due Date: // 7 7 - 0 6 From the Daily Pipe Survey Detector Control Form for the Selected Detector BackgroundValue qcr) cpm MDcRstaac p b cpm Efficiency Factor for Pipe Diameter 0.0 0 0 2 8 @om detector efficiency determination)

MDCStati, 468s- dpm/ too - - -cm2 Is the MDCsuc acceptable? @ No (if no, adjust sample count time and recalculate M D C L )

_ _

tW

/ -

Technician Signature C.0 Pipe Interior Radiological Survey Package Page 1 of 2 0 REFERENCECOPY Attachment 3, Page 1

/

i 0

REFERENCE COPY

I I I I SECTION 7 ATTACHMENT 3 PAGE(S)

Design # EP Rx 137 Revision # Original Survey Unit# [ EP Rx 137 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

2. Is the instrumentation MDC for structure static measurements below the DCGLw for Class 1 and 2 survey units, or M o w 0.5 DCGLw for Class 3 sunrey units? I I l x

3. Is the instrumentation MDC for embeddedlburied piping static measurements below the DCGLw ? X

4. Was the instrumentationMDC for structure scan measurements, soil scan measurements, and embeddedlburied piping scan measurements below the DCGLW,or, if not, was the need for additional X static measurements or soil samples addressed in the survey design?

5. Was the instrumentation MDC for volumetric measurementsand smear analysis 10% DCGLw ? 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 colled data proper for the types of radiation involved and for the media being surveyed? X

3. Were Special Methods for data collection properly applied for the survey unit under review? X

3. Is the data set comprised of qualified measurement results collected in accordance with the survey design, which accurately reflects the radiolosicat status of the f a c i l i i

1. Has a posting plot been created? I x

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

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

2. Is the mean of the sample data < WGLw? X

3. If elevated areas have been identified by scans and/or sampling, is the average activity in each X

elevated area < DCGLEMC (Class l), < DCGLW(Class 2), or (0.5 DCGLw (Class 3)?

4. Is the result of the Elevated Measurements Test < I.O? X

5. Is the result of the statistical test (S+ for Sign Test or Wr for WRS Test) 2 the critical value?

I X Kl Y

cs-0912 Page 1 of 1

I SECTION 7 ATTACHMENT 4 1 DISC

Survey Unit Release Record Design ## EP-1.44 I Revision ## 1 Original 1 Page 1 of 3 Survey Unit #(s) 1.44

1) Embedded Pipe (EP) Survey Unit 1.44 meets the definition of embedded pipe for Plum Brook Reactor Facility (PBRF).

2) EP 1.44 is a Class 1, Group 1 survey unit as per the PBRF Final Status Survey Plan (FSSP) and Technical Basis Document (TBD)-06-004.

3) Surveys in EP 1.44 were performed using a scintillation detector optimized to measure gamma energies representative of Co-60. Sample #EP 3-9 ffom Survey Request (SR)-13 was referenced for this decision.

4) Survey Instructions for this survey unit are incorporated into and performed in accordance with (LAW) the Babcock Services Incorporated (BSI)/LVS-002, Work Execution Package (WEP)05-006. Survey instructions described in this Description document constitute Special Methods and the survey design used in the acquisition of survey measurements.

5 ) Instrument efficiency determinations are developed in accordance with the BSILVS-002, WEP 05-006, these determinations are appropriate for the types of radiation involved and the media being surveyed.

COPY 1 Approval Signatures Date:

FSS/Characterkation Engineer aractenzahon cs-o9/1

I I

-

FSS Design ## EP 1.44 Revision # Original Page 2 of 3 1.O History/Description 1.1 The subject pipe system is the 2 and 2.5 suction header from the Sub Pile Room sump to the drain trench on the Rx Building -25 foot elevation.

The function of this pipe was to convey water from the top of the Sub Pile Room sump to the drain trench on the Rx building -25ft., where the pipe is currently breached.

1.2 EP 1.44 consists of 2 and 2.5 diameter piping that is approximately 54 feet.

2.0 Survey Design Information 2.1 EP 1.44 was surveyed MW Procedure #BSVLVS-O02.

2.2 100% of the 2 and 2.5 ID pipe was accessible for survey. The pipe was surveyed by static measurement at one foot increments, for a total of 54 survey measurements.

2.3 Surface area for the 50 run of 2 ID piping is 486 cm2for each foot of piping and the 4 run of 2.5 ID piping is 603 cmzfor each foot of piping corresponding to a total piping surface area of 26,756 cm2(2.7 m2) for the entire length (approximately 54) of piping.

3.0 Survey Unit Measurement LocationsData 3.1 Pipe interior radiological survey forms are provided in Attachment 2 of this release record.

4.0 Survey Unit InvestigatiordResults 4.1 None 5.0 Data Assessment Results 5.1 Data assessment results are provided in the EPBuried Pipe (SP) Survey

__Report provided in Attachment 1. ~ -~

5.2 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.

5.3 When implementing the Unity Rule, provided in Section 3.6.3 of the FSSP, and applying the Nuclide Fraction (NF), provided in TBD-06-004, the survey unit that is constituted by EP 1.44 passes FSS.

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

FSS Design # EP 1.44 Revision # Original Page 3 of 3 5.5 Statistical Summary Table 212.5 Statistical Parameter Pipe Total Number of Survey Measurements 54 Number of Measurements >MDC 54 Number of Measurements Above 5Oohof DCGL 0 Number of Measurements Above DCGL 0 Mean 0.2112 Median 0.1898 Standard Deviation 0.0697 I Maximum I 0.4079 I I Minimum [ 0.1085 I Documentation of evaluations perbining to compliance with the unrestricted use limit of 25 d y r and dose contributions fiom Embedded Pipe and radionuclides contributing 10% in aggregate of the total dose for both structural scenarios and soils.

6.1 A review of the survey results has shown that the dose contribution for EP 1.44 to be less than 1 mredyr. The dose contribution is estimated to be 0.21 1 mredyr based on the average of the actual gross counts measured.

-

--

~

Attachment 1 - BSI EPBP Survey Report Attachment 2 - Pipe Interior Radiological Survey Form Attachment 3 - DQA Worksheet Attachment 4 - SURR EP 1.44 & Spreadsheet

1 SECTION 7 ATTACHMENT 1

.3 PAGE(S)

P i p ID 1.u Survey Location Subpile suctions -27 1-19-06,1-20-06 8 2350-1 # 212223 survey Date 2-22-06 Sunmy Time 1400 I0810 / 0846 Detector-Sled It 204402-121, 212701-121 Pipe size 2- Detector Efficiency 0.00026 / 0.0002 Measured Nudide c0-60 Area FactorEMC Used No P d a i l FSS Pass MREMNR Contribution el

-

I COMMENTS:

ACTlvlTY VALUES NOT WCKGROUND CORRECTED RP Engineer IDate fld 7-10-07 7HM007

EP 1.44 I w l I Cs-137 activity (dpm11ooCm2)

Eu-162 activity (dpm1100cm2)

Eu-164 activity (dpm1100cm2)

Nb-94 actlvlty (dpmn00cm2)

Ag-1OSm activity (dpm1100em2) 1 0.179 12 421 331208 13 321 321 123.077 1 1 25,302

~~

1.222 I 29.251 I 7.776 I 900 I 215 924 22,126 5,882 68 1 163 1,207 28,876 7,677 888 __- 212 987 23,626 6,281 727 174

_ - -

1,159 27,751 7,377 - 854 -_____ 204

__ 1,301 31,127 8,275 958 -229-1.536 36.752 9.770 1.131 270 25 39.5 39.5 1511923 j 311232 1,238 29,627 7,876 911-- 21a 26 31.5 31.5 121,154 1 24,906 _- 987 23,626 6,281 727 174 27 40 40 153,846 ~ 31,627 1,254

~- 30,002 7,976 923 _ _220 28 49 49 188,462 1 38,743 1,536 36,752 9,770 1,131 27c) 29 37.5 37.5 144,231 I 29,65(3 - 1,175 28,126 7,477 865 207 30 32 32 123,077 I 25,302 1,003 24,001

___- 6,380 738 178 31 43.5 43.5 167,308 34,394 1,363 32,627 - 8,673 1,004 240 40.5 40.5 155,769 1 32,022 1,269 30,377 8,075 934~- 223 1o f 2

-

to 1'0 IOP'O ILO'O

. I

_

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___

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'I 1 If Qun

-

SECTION 7 ATTACHMENT 2 7 PAGE(S)

Pipe Interior Radiological Survey Form Date: /4P L Time: l $ m Building:

System:

7& fh I+

1 sifd / ;d GL<+

Elevation:

,

Pipe Diameter:

- 25 Access Point Area: -2.7 p ~ ~ k 4 Pipe ID # 1. f14/

Type of Survey Investigation Characterization 6 a - a Other f Sled Size av,;.-/~ ZQ&?$Z, inch Detector: LJY-I 7 Detector ID #: do yJ0 a

• 4.is /a/

Cal Date: I / 0b

- Cal Due Date: //- / 7 - 4 Instrument: 33S-l-4 Instrument ID #: ai aaa3 Cal Date: I I 17 -0)- Cal Due Date: / / 9-7 VL -

From the Daily Pipe Survey Detector Control Form for the Selected Detector Background Value $9 cpm MDCRStatX /iff cpm Efficiency Factor for Pipe Diameter 0 I 0 0 0 3 (taken fiom detector

- +, -.,

MDCSCltlC 783b dpm/100cm2 Is the MDC,,, acceptable?

- @ No (if no, adjust sample count time and recalculate M D C b Q C )

Comiients: A/ i4c 7 1 Pipe Interior Radiological Survey Radiological Survey Commenced: Date: /# / F

• LJ L Time: / yd3 Package Page 1 of 2 0 REFERENCECOPY Attachment 3, Page 1

Pipe Interior Radiological Survey Form Date: /-LO -0 1& Time: OB/ 0 Building: y Elevation: -2 7 Access Point Area: 7-7Z-d L, t(

System: q q G p 1 CG 5 uc7f8 Pipe Diameter: ir Pipe ID # 1, YL(

Type of Survey Investigation Characterization @ - y o Other /

Sled Size 3 " d I NyC hlLbe 6 / 2 1 inch Detector: 9Yf-L72 Detector I D #: L O Y"1Z -5&p-/

Cal Date: //-/ 7-0 6 Cal Due Date: /k/7-049 Instrument: am-, Instrument ID #: Z M Z 2 3 Cal Date: / /L/ 7-QT Cal Due Date: //-I73 6 From the Daily Pipe Survey Detector Control Form for the Selected Detector Background Value - 5 4 1 cpm MDcRstatlc /O47 cpm Efficiency Factor for Pipe Diameter 0, O o O a (taken from detector MDcstatlc 5305 dpm/100cm2 Is the MDCsUhc acceptable? @ No (if no, adjust sample count time and recalculate MDCb,)

Comments: C L W ~ ~ / U L ~ Q V I~~- 5 1 d & ~ 31 2 6 P(f'@-

/ VT~~/ O Pipe Interior Radiological Survey ClAvS?

-

fk/m Package Page 1 of - z-u c

REFERENCE COPY Attachment 3, Page 1

I Package Page &of - z REFERENCE COPY Attachment 3, Page 2

1 B WLVSPipeCrawler-002

• /

Revision 4 Pipe Interior Radiological Survey Form Date: I-22-0 b Time:

L'UD\yL 6.~471L :

Pipe ID#: 1 , qc( Pipe Diameter: f&S Access Point Area: ,I p R-e?d#- S.1 Building:  % Elevation: * -Y S System: /t;/mpu CliL L/&S Type of Survey Investigation Characterization Final Survey ->( Other J Gross Co60 J cs Detector ID# 1 Sled ID# ry-6 2 a770r I f 21 Detector Cal Date: I / - I 7- 0 Detector Cal Due Date: I/-/ 7-0 b Instrument: 7 3 m-( Instrument ID #: a27 v Instrument Cal Date: //77-0c Instrument Cal Due Date: /l-f7-06 From the Daily Pipe Survey Detector Control Form for the Selected Detector Background Value y c cpm MDCRstatic 13.b cpm Efficiency Factor for Pipe Diameter 01 ooaz (from detector efficiency determination)

MDCStatK 5305 dPd \vQ cm2 Is the MDCSbticacceptable? (if no, adjust sampTe count time and recalculate MDCR,&

@ No Comments: f N 1 J t G -3clfLJW Technician Signature r ,ot&

Pipe Interior Radiological Survey

-

9

-

10 Package Page 1 of 3 REFERENCE COPY Attachment 3, Page 1

SECTION 7 ATTACHMENT 3

.I PAGE(S)

Design # EP 1.44 Revision # Original Survey Unit # EP 1.44 Answers to the following questions should be fully documented in the Survey Unit Yes No NIA Release Record

1. Have surveys been performed in accordance with survey instructionsin the Survey Design? X

2. Is the instrumentation MDC for structure static measurements below the DCGLw for Class 1and 2 X survey units, or below 0.5 DCGLw for Class 3 sunrey units?

3. Is the instrumentation MDC for embeddedhuried piping static measurements below the DCGLw ? X

4. was theinstrumentation MDC for structure scan measurements, soil scan measurements, and embedded/buriedpiping scan measurements below the DCGLw,or, if not, was the need for additional X static measurements or soil samples addressed in the survey design?

5. Was the instrumentation MDC for volumetric measurements and smear analysis 10% DCGLw ? X

5. Were theMDCs 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 involvedand for the media being surveyed? X

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

9. Is the data set comprised of qualied measurement results collected in accordancewith the survey X

design, which accurately reflectsthe radiological status of the facility?

1. Has a posting plot been created? X

2. Has a histoaram (or other freauency plot) been created? X

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

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

3. If elevated areas have been identifiedby scans andlor sampling, is the average activity in each X

elevated area < DCGLEMC(Class l),DCGLW(Class 2), or ~ 0 . DCGLw 5 (Class 3)?

I

4. Is the result of the Elevated MeasurementsTest 1.O? X

5. Is the result of the statistical test (S+ for Sign Test or W, for WRS Test) 2 the criticalvalue? X Comments:

FSS/Charaderization Engineer (prlnt/$ign) a4 FSS/ Characterization Manager (prinffsign)

Page 1 of 1

SECTION 7 ATTACHMENT 4 1 DISC

Survey Unit Release Record Design # EP-Rx 152D Revision # Original Page 1 of 3 Survey Unit #(s)

2) EP Rx 152D is a Class I , Group 2 survey unit as per the PBRF Final Status Survey Plan (FSSP) and Technical Basis Document (TBD)-06-004.

3) Surveys in EP Rx 152D were performed using a scintillation detector optimized to measure gamma energies representative of CO-60. Sample #EP 2-1 from Survey Request (SR)-13 was referenced for this decision.

4) Survey Instructions for this survey unit are incorporated into and performed in accordance with (IAW) the Babcock Services Incorporated (BSI)/LVS-002, Work Execution Package (WEP)05-006. Survey instructions described in this Description 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:

I I I FSS/Characterization Engineer 9 / 7 - / ? -07 Technical Reviewer (FSS/Characterization Engineer) 7-23-07

/ /

FSS/Characterization Manager Y

El CS-0911 0 COPY

FSS Design # EP Rx 152D Revision # Original Page 2 of 3 1.o HistoryDescription 1.1 The subject pipe system is the 0.75 Quad B system line.

1.2 EP Rx 152D is approximately 15 feet in length.

2.0 Survey Design Information 2.1 EP Rx 152D was surveyed IAW Procedure #BSI/LVS-002.

2.2 100% of the 0.75 ID pipe was accessible for survey. The accesslulc 75 ID pipe was surveyed by static measurement at one foot increments, for a total of 15 survey measurements.

2.3 Surface area for the 0.75 ID piping is 182 cm2for each foot of pi ing, 4

corresponding to a total 0.75 ID piping surface area of 2,736 cm (0.3 m2) for the entire length of (15 ) of 0.75 piping..

3.0 Survey Unit Measurement Locations/Data 3.1 Pipe interior radiological survey forms are provided in Attachment 2 of this release record.

4.0 Survey Unit InvestigationsResults 4.1 None 5.0 Data Assessment Results 5.1 Data assessment results are provided in the EPBuried Pipe (BP) Survey Report provided in Attachment 1.

5.2 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.

5.3 When implementing the Unity Rule, provided in Section 3.6.3 of the FSSP, and applying the Nuclide Fraction (NF), provided in TBD-06-004, the survey unit that is constituted by EP Rx 152D passes FSS.

5.4 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 152D Revision # Original Page 3 of 3 Survey Unit: Rx 152D J

5.5 Statistical Summary Table 0.75" Statistical Parameter Pipe I Total Number of Survey Measurements I 15 I Number of Measurements >MDC 12 Number of Measurements Above 50% of DCGL 0 Number of Measurements Above DCGL 0 I Mean 0.0513 I Median 10.0524 I I Standard Oeviation 10.02161 Maximum 0.1047 Minimum 0.0201 6.0 Documentation of evaluations pertaining to compliance with the unrestricted use limit of 25 mredyr and dose contributions fiom Embedded Pipe and radionuclides contributing 10% in aggregate of the total dose for both structural scenarios and soils.

6.1 A review of the survey results has shown that the dose contribution for EP Rx 152D to be less than 1 mredyr. The dose contribution is estimated to be 0.05 1 mredyr based on the average of the actual gross counts.

7.0 Attachments Attachment 1 - BSI EPBP Survey Report Attachment 2 - Pipe Interior Radiological Survey Form Attachment 3 - DQA Worksheet Attachment 4 -Disc containing RR for EP Rx 1.52D & Spreadsheet

SECTION 7 ATTACHMENT 1 z PAGE(S)

Fl!r

. .. BSI EP/BP SURVEY REPORT Survey Location -27' Trench Loop Drain SurveyDate 1 02-Aug-06 II 2350-1 # 189094

~~ ~

Survey Time 13:08 I1 DetectorSled # 004740 sled

,

I I

I Pipe Size DCGL idpnn-ml) 0.75" 2.41E95 0.3 II p l p h b=wmd b~ -

Detector Efficiency Field BKGmt BMns),Iln -4 0.00059 182 18.3 Routine Survey I X II Field MDCR (spn) I 17.8 Total Number of Survey Measurements 15 Number of Measurements >MDC 12 Number of MeasurementsAbove 50% DCGL 0 Number of MeasurementsAbove DCGL 0 Mean 0.0513 Median 0.0524 Standard Deviation 0.0216 Maximum 0.1047 Minimum I 0.0201 STOCK Survey Technician(s)

OMMENTS:

CTIVITY VALUES NOT BACKGROUND CORRECTED RP Engineer I Date B d M / 747-07 7/17/2007

EP Rx 152D 0.75" Pipe TBD 06-004 Group 2

-

Cod0 activity Cs-137 activity Eu-lS2 activlty Eu-164 activity Nb-94 activity Ag-108rn activity (dpmll OOcrn2) (dpmll00cm2)

Unity (dpm1100cm2) (dpm/l OOcm2) (dpd100cm2) (dpmllOOcrn2) 23,729 - 13,009 -__ 6,745 374

-0.03

- _25,424

__ --

13,938

-__--

7,227

-

~. -

40 1 0.06(

15,254 8,363 ___ 4,336 69 49 0.03t 24 1 ___

_- _ _ - __ _ _ _-

28,814 15,796 _ _ 8,191 131 _- 92 8 455 _ 0.061

_

_ _ _ -~~ --

20,339 11,150 - __ 5,782 92 65 5 ~-

32 1 -~0.04f 17,654 9,154 146 103 9 508 0.07;

_ _32,203_ - -- -__ _ _ _ I f _ _ _8,475_- 4,646 2,409

_ _ ~ _ _ _- 39 ~- 27 2 134 ___0.02(

--5! 11 11 ~~

18,644 10,221

~ __ 5,300

-- ~-

85 60 5 -__.

294 0.W

- 22,034

_~ - - ___-_

12,079 -__ 6,264 100 71 6 ._

348 0.05:

__.

24,159 _____12,527 200 141 12 - 695 0.10!

_ _ _44,068

_ _ .___ - --

____- 7,433 13,559 ____ __ -_ _ _ 3,855 62 44 -4 214 _ 0.03:

-

15,254 8,363 __ 4,336 __- 69 49 4 24 1 0.03(

22,034

- ___. _____-

12,079 6,264

_- 100 71

- 6 - Ma 0.05:

23,729

_ _ _ ____ _ _ 13,009 - 6,745 108 76

- 6 374 ___0.05 2.891 46 33 3 i60 0.024 10,169 ____

_ 5,575

___ -

MEAN

- 0.05 V~EDIAN 0.05:

S

-

DD

. _- N 0.02:.

MAX --0.10!

MIN - 0.021 1 of 1

I I

SECTION 7 ATTACHMENT 2 3 PAGE(S)

BSL'LVSPipeCrawler-002 Revision 4 Pipe Interior Radiological Survey Form Date: Time: /,'3u8' Pipe ID#: Pipe Diameter: a 75 Access Point Area: -2 7 m t +

Lbpp r>&H KJq Building:

vp Elevation: c. I System:

Positioc Feet h t o Pipe Count Time Gross counts Gross Net fiom Opening (min) cpm cpm d p d 1OOcm'

1 f le- /e fl //=L fl \a 1 2 2  ! I$ fE 3 3 - 4 4 9 17 17 5

6 6 1 %

Fj a

'I 9 l 17 7 Y S ~

i I

8 9

I + I 11 li 1 I 9 13 13 I 10 i /D 26 26 I 4 / . I Package Page 1 of 3 REFERENCECOPY Attachment 3, Page 1

BSYLVSPipeCrawler-002 Revision 4 Pipe Interior Radiological Survey Form (Continuation Form)

Date: g[z/O6 Pipe ID#: iYL Pipe Diameter: 875 Access Point Area:

Building: kg Elevation: - 27 d

System:

/

I

/

I 0 REFERENCE COPY Attachment 3, Page 2

SECTION 7 ATTACHMENT 3

/ PAGE(S)

DQA Check Sheet

-

Design #

~-

1 EP Rx 152D I Revision # I Original

~~

I Survey Unit # EP Rx 152D Preliminary Data Review' Answers to the following questions should be fully documented in the Survey Unit Yes No N/A Release Record I. Have surveys been performed in accordance with survey instructions in the Survey Design? X

~

2.

~

Is the instrumentation MDC for structure static measurementsbelow the DCGLw for Class 1and 2 survev units, or below 0.5 DCGLWfor Class 3 survev units?

~ ~~ ~~

I

3. Is the instrumentation MDC for embeddedlburied piping static measurements below the DCGLw ? X

-

t , Was the instrumentation MDC for structure scan measurements, soil scan measurements, and

__

embeddedhried piping scan measurements below the DCGLw,or, if not, was the need for additional static measurements or soil samples addressed in the survey desian?___ I X I

~ ~~~ ~ ~ ~ ~~

5. Was the instrumentation MDC for volumetric measurements and smear analysis 10%DCGLw ? T 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? IxI

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

3. Is the data set comprised of qualified measurement results collected in accordancewith the survey X design, which accurately reflects the radiologicalstatus of the facility?

Graphical Data Review I . Has a posting plot been created? I I I x

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

3. Have other graphical data tools been created to assist in analyzing the data? X Data Analysis I. Are all sample measurementsbelow the DCGLw(Class 1 8 2), or 0.5 DCGLw (Class 3)? 1 x 1 I

?. Is the mean of the sample data c DCGLW? X

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

t. Is the result of the Elevated Measurements Test 1.O? X

5. Is the result of the statistical test (S+ for Sign Test or W, for WRS Test) 2 the critical value? X hrnments:

- -

KlCS-09/2 Page 1 of 1

SECTION 7 ATTACHMENT 4 1 DISC

I Design # EP-Rx 149 Revision # Original Page 1 of 3 Survey Unit #(s)

2) EP Rx 149 is a Class 1, Group 1 survey unit as per the PBRF Final Status Survey Plan (FSSP) and Technical Basis Document (TBD)-06-004.

3) Surveys in EP Rx 149 were performed using a scintillation detector optimized to measure gamma energies representative of CO-60. Sample #EP 3-9 from Survey Request (SR)-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 Description 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.

1 :1 cs-0911 0 COPY

Survey Unit: Rx 149 1.o HistoryDescription 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.

1.2 EP Rx 149 consists of 3 diameter piping that is approximately 20 feet in length.

2.0 Survey Design Information 2.1 EP Rx 149 was surveyed LAW Procedure #BSI/LVS-002.

2.2 100% of the 3 ID pipe was accessible for survey. The accessible 3 ID pipe was surveyed by static measurement at one foot increments, for a total of 20 survey measurements.

2.3 Surface area for the 3 ID piping is 730 cm2for each foot of piping, corresponding to a total 3 ID piping surface area of 14,593 cm2(1.5 m2) for the entire length of (approximately 20) of 3 piping..

3.0 Survey Unit Measurement Locations,Data 3.1 Pipe interior radiological survey forms are provided in Attachment 2 of this release record.

4.0 Survey Unit Investigations/Results 4.1 None 5.0 Data Assessment Results 5.1 Data assessment results are provided in the EPBuried Pipe @P) Survey Report provided in Attachment 1.

5.2 All measurement results are less than the Derived Concentration Guideline Level (DCGL) for radionuclide specific EP that corresponds to the 1 rnredyr dose god established in Table 3-3 of the FSSP.

5.3 When implementing the Unity Rule, provided in Section 3.6.3 of the FSSP, and applying the Nuclide Fraction (NF), provided in TBD-06-004, the survey unit that is constituted by EP Rx 149 passes FSS.

5.4 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 149 Revision # Origrnal Survey Unit: Rx 149 5.5 Statistical Summary Table Statistical Parameter

~~ ~~

Total Number of Survey Measurements 20 Number of Measurements >MDC 1 Number of MeasurementsAbove 50% of DCGL 0 Number of Measurements Above DCGL 0 Mean 0.0106 I I Median I0.0100 I Standard Deviation 0.0038 Maximum 0.0188 Minimum 0.0025 6.0 Documenbtion of evaluations pertaining to compliance with the unrestricted use limit of 25 mrem/yr and dose contributions from Embedded Pipe and radionuclides contributing 10%in aggregate of the total dose for both structural scenarios and soils.

6.1 A review of the survey results has shown that the dose contribution for EP Rx 149 to be less than 1 mredyr. The dose contribution is estimated to be 0.01 m d y r based on the average of the actual gross counts measured.

7.0 Attachments Attachment 1 - BSI E P 5 P Survey Report Attachment 2 - Pipe Interior Radiological Survey Form Attachment 3 - DQA Worksheet Attachment 4 - SURR EP RX 149 & Spreadsheet Disc

_ -

I SECTION 7 ATTACHMENT 1 2 PAGE(S)

__ . . B S I EP/BP SURVEY REPORT Pipe ID I Rx 149 I! Survey Location I CV -38el.

Survey Date 20-Feb-06 2350-1 # 212223 Survey T i m 07:55 Detector-Sled W 44-62/212701-121 Pipe S b 3 Detector Efficiency 0.00013 DCGL imooau) 2.41E95 g.*trit=pm~-em-wman2) 730 PlPAm-m Routine Survey

- 1.5 - -

Field BKG 1cpm1 4.7 X Field WDCRrpl) 10.4 QA survey

- 'ij l r: ?' <

.

, &*.,

' '

i

'

• .... Nominal MDC 2,779 Total Numberof Survey Measurements 20 Number of Measurements >MDC 1 Number of MeasurementsAbove 50% DCGL 0 Number of MeasurementsAbove DCGL 0 Mean 0.0106 Median 0.0100 Standard Deviation 0.0038 Maximum 0.0188 Minimum 0.0025

OMMENTS:

CTNITY VALUES NOT BACKGROUNDCORRECTED RP Engineer I Date 7/12/2007

EP Rx 149 3" Pipe TBD 06-004 Group 1

-

• C Q)

E 3 gcpm ncpm Cos0 actlvtty (totaldpm)

C0-60 acthrlty (dpm1100cm2)

Cs-137 activity (dpm1100cm2)

Eu-152 activity (dpmllOOcm2)

Eu454actlvlty (dpm1100cm2)

, Nb-Wactivity (dpm1100crn2)

Ag-106m-l (dpmllOOcm2) L!!iIyf 346 1 _40

_

346 40 -

__ -- 518 I 60 .

397 ~ 46 11 0.00s 5s-~ - 40

_ _ 10 -0:OOE 622 72 17 O.Ol?

~-397 46 11 0.00s Om

~~

622 72 17 449 52 ___-- 12 0.011

_______ 570 66 16 ___0.01:

518 60 14 0.01; 346 40 10 0.oot 346 40 10 0.oot 449 . __ 52 12 0.01*

570 66 16 0.01:

795 92 ___. 22 om

.____

225 26 6 O.OO!

104 12 3 0.00:

622 72 17 O.Ol!

397 46 11 0.03 0.01 MEDIAN STD DEV 0.00:

1of1

SECTION 7 ATTACEIMENT 2 3 PAGE(S)

BSyLVSPipeCrawler-002 Revision 4 Pipe Interior Radiological Survey Form Date: 2-2 &)& Time: 02.rr Pipe ID#: IYCj Pipe Diameter: Access Point Area: s p a ccwkfQ ~ \ I Building: RX Elevation: System:

Type of Survey Investigation I

Characterization Final Survey Other /

Gross (2060 J cs Detector ID# / Sled ID# 4Y42 Z / 2 7 @ / i /a/

Detector Cal Date: /j-[7-&+ T Detector Cal Due Date: I / - /7- O b Instrument: 7 m?-( Instrument ID #: 2i27 23 Instrument Cal Date: Instrument Cal Due Date: / I-/7 0 c From the Daily Pipe Survey Detector Control Form for the Selected Detector BackgroundValue q.7 cpm hDC%lZtIC / P I 9 CPm Efficiency Factor for Pipe Diameter 0 00017 (from detector efficiencpdeterrnination)

MDCstatx Is the MDCSbuC 277G acceptable?

F . l . - m f i l I NII\ a f i l l 2-Lt dpd !Do No c

cmz (if no, adjwt s a q l e count time and recalculate MDCL,,)

b r( L/N(B e.sz, /

r m P /e775 Technician Signature Pipe Interior Radiological Survey Packagepage 1 o f 2 REFERENCE COPY Attachment 3, Page 1

I BSVLVSPipeCrawler-002 Revision 4 Pipe Interior Radiological Survey Form (Continuation Form)

Date: 2'7 0- G3 PipeD#: Rx iyC) Pipe Diameter: I t Access Point Area: 5 P / L c wi21f3 T ) f Building: j2-x Elevation: System:

Package Page A o f J Attachment 3, Page 2

i SECTION 7 ATTACHMENT 3 I PAGE@)

~ ~

DQA Check Sheet Design # EP Rx 149 Revision # Original Survey Unit # EP 149 Preliminary Data Review Answers to the following questions should be fully documented in the Survey Unit Yes No NIA Release Record

1. Have surveys been performed in accordance with survey instructions in the Survey Design? X

2. Is the instrumentation MDC for structure static measurements below the DCGLw for Class 1 and 2 X survey units, or below 0.5 DCGLw for Class 3 survey units?

3. Is the instrumentation MDC for embeddedlburied piping static measurementsbelow 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 X static measurementsor soil samples addressed in the survey design?

5.

-~

Was the instrumentation MDC for volumetric measurementsand smear analysis 10% DCGLW? I I 1 X

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

~~

used to nerform the survey?

~

7. Were the survey methods used to collect data proper for the types of radiation involved and for the X

media being surveyed?

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

9. Is the data set comprised of qualified measurement results collected in accordance with the survey X design, which accurately refleds the radiological status of the facility?

Graphical Data Review

~~~~ ~

1. Has a posting plot been created? X

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

3. Have other graphical data tools been m a t e d to assist in analyzing the data? X Data Analysis

1. Are all sample measurementsbelow the DCGLw (Class 1 8 2), or 0.5 DCGLw (Class 3)? 1 x 1

2. Is the mean of the sample data DCGLw? X

3. If elevated areas have been Mentitied by scans and/or sampling, is the average activity in each X elevated area < DCGLEW(Class l),< DCGLW(Class 2), or <0.5 DCGLW(Class 3)?

4. Is the result of the Elevated MeasurementsTest < 1.O? X

5. Is the result of the statistical test (S+ for Sign Test or Wr for WRS Test) 2 the critical value? X Comments:

FSS/CharaderizationEngineer (prinVsign) Date 7-12 4 7 FSSl Characterization Manager (print/sign) Date &D7 I -

Page 1 of 1

SECTION 7 ATTACIXMENT 4 1 DISC

I a COPY Survey Unit Release Record 1 I 1

~~ ~

Design ## EP-Rx 130 Revision# Original Page 1 of 3 Survey Unit #Is) Rx 130

1) Embedded Pipe (EP) Survey Unit Rx 130 meets the definition of embedded pipe for Plum Brook Reactor Facility (PBRF).

2) EP Rx 130 is a Class 1, Group 2 survey unit as per the PBRF Final Status Survey Plan (FSSP) and Technical Basis Document (TBD)-06-004.

3) Surveys in EP Rx 130 were performed using a scintillation detector optimized to measure gamma energies representative of CO-60.Sample #EP 2-2 from Survey Request (SR)-13 was referenced for this decision.

4) Survey Instructions for this survey unit are incorporated into and performed in accordance with (IAW) the Babcock Services Incorporated (BSI)/LVS-002.

Work Execution Package (WEP)05-006. Survey instructions described in this Description document constitute Special Methods and the survey design used in the acquisition of survey measurements.

5 ) Instrument efficiency determinations are developed in accordance with the BSYLVS-002, WEP 05-006, these determinations are appropriate for the types of radiation involved and the media being surveyed.

FSS Design # EP Rx 130 Revision # Original Page 2 of 3 I Survey Unit: Rx 130 I 1.0 HistoryDescription 1.1 The subject pipe system is the 3 Quad A spare system line.

1.2 EP Rx 130 consists of approximately 2 1 feet in length from the Reactor Building -25 elevation, Quad A to the Sub Pile Room.

2.0 Survey Design Wormation 2.1 EP Rx 130 was surveyed LAW Procedure #BSI/LVS-002.

2.2 100% 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.

2.3 Surface area for the 3 ID piping is 730 cm2for each foot of piping, corresponding to a total 3 ID piping surface area of 15,323 cm2(1.5 m2) for the entire length of (21 ) of 3 piping.

3.0 Survey Unit Measurement LocationsData 3.1 Pipe interior radiological survey forms are provided in Attachment 2 of this release record.

4.0 Survey Unit InvestigationslResults 4.1 None 5.0 Data Assessment Results 5.1 Data assessment results are provided in the EPBuried Pipe (BP) Survey Report provided in Attachment 1.

5.2 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.

5.3 When implementing the Unity Rule, provided in Section 3.6.3 of the FSSP, and applying the Nuclide Fraction (NF), provided in TBD-06-004, the survey unit that is constituted by EP Rx 130 passes FSS.

5.4 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 130 Revision # Original Page 3 of 3 i

Survey Unit: Rx 130 I 5.5 Statistical Summary Table 3

Statistical Parameter Pipe Total Number of Survey Measurements 21 Number of Measurements >MDC 17 Number of Measurements Above 50% of DCGL 0 Number of Measurements Above DCGL 0 Mean 0.0358 Median 0.0183 Standard Deviation 0.0481 Maximum 0.2070 Minimum 0.0105 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 130 to be less than 1 d y r . The dose contribution is estimated to be 0.036 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 130 & Spreadsheet

I SECTION 7 ATTACHMENT 1 z PAGE(S)

BSI EP/BP SURVEY REPORT Pipe ID Survey Location -25 el. Quad A Survey Date 12-Jan-06 2350-1 # 203488

~~

Survey Time 08:33 DetectorSled # 44-62 2127011121 I

I ~

1 pipesire DCGL #pyrmsmli 3

2.41E 9 5 1.5 PIP- hmmmdLY -

Detector Efficiency Fild BKGmm)

Emdmwlln-21 0.00013 730 22 RoutineSurvey X Field MDCRlm) 385 Nominal MDC ~dpnnmsnq 2,779 3Zev-MeasurementResults Total Number of Survey Measurements 21 Number of Measurements >MDC 17 Numberof MeasurementsAbove 50% DCGL 0 Number of MeasurementsAbove DCGL 0 SR-13 Radionuclide Distribution Sample EP 2-2 Measured Nuclide CO-60 Area FaaorEMC Used No Pass/Fail FSS Pass MREWR Conbibution <l

OMMENTS:

CTIVITY VALUES NOT BACKGROUNDCORRECTED RP Engineer I Date 8-124 7 8/13/2007

EP Rx 130 3" Pipe TBD 06-004 Group 2

-

3t u

C Ee! gcpm ncpm Cod0 activity (total dpm)

COS0 activity (dpmllOOcm2)

Cs-137 activity (dpm1100cm2)

Eu-152 activity (dpm11Wcm2)

Eu-154 activity (dpm1100cm2)

N M 4 activity (dpn\rlOOcm2)

Ag-108m activity (dpmllOOcm2)

Unity a

(1D

__-

14

-

837 _0.121

_

3 161 _0.02'

_ ~

2 ~ _ 91 0.01,

_ --_

2

___. ___91 0.01 3 152 0.02 3 . 152 0.02 2 91 0.01 1 70 0.01 2 109 0.01 3 152 ~.0.02 1 79 0.01 2 100 0.01 0.01 0.02 1 79 0.01 23 1,374 1 79

~- 2 140

__.

2 .-

100 5 303 9 555

,

lofl

SECTION 7 ATTACHMENT 2 3 PAGE(S)

Pipe Interior Radiological Survey Form Date: /-/t-oG, Time: 0 5.33 --* *-

Building: Elevation - L>

Pipe Diameter:

- 3I f Access Point Area:

qVAO 4 System: 5WpT .. -G SPR PipeID k g /a@

Type of Survey Investigation Characterization (F;;als i urver> # Other /-

Sled Size inch Detector: y+ht Detector ID #: 7fZ7@//-

Cal Date: 1 / 7 7 Cal Due Date: AI-/7-u 6 Instrument: lri3-/ Instrument ID #: z/rz23 Cal Date: //-7 7-7.J- Cal Due Date: //-/ 7-c7 6 From the Daily Pipe Survey Detector Control Form for the Selected Detector Background Value 3.2 CPm PVIIDCRStatiC 3 RJ- CPm Efficiency Factor for Pipe 0. 0 00 [ 3 (taken from

. Pipe Interior Radiological Survey Radiological Survey Commenced: Date: I 7 t - 0 @ Time: 33 Package Page 1 of&

REFERENCE COPY Attachment 3, Page 1

Pipe Interior Radiological Survey Form (Continuation Form)

..

I I I I I Package Page &of 2 Attachment 3, Page 2 REFERENCECOPY

SECTION 7 ATTACHMENT 3 I PAGE(S)

DQA Check Sheet Design # I EP Rx 130 1 Revision # 1 Original 1

~~~

Survey Unit# I EP Rx 130 Preliminary Data Review' Answers to the following questions should be fully documented in the Survey Unit Yes No N,A Release Record 1, Have surveys been performed in accordance with survey instructions in the Survey Design? X

2. Is the instrumentation MDC for structure static measurements below the DCGLw for Class 1 and 2 survey units, or below 0.5 DCGLw for Class 3 survey units? I I Ix

3. Is the instrumentation MDC for embeddedhuried piping static measurementsbelow the DCGLW? I X I 1 4.

5.

Was the instrumentation i D C for structure scan measurements, soil scan measurements, and embeddedhuned piping scan measurements below the DCGLW.or, if not, was the need for additional static measurements or soil samples addressed in the survey design?

Was the instrumentation MDC for volumetric measurements and smear analysis < 10% DCGLW?

I i

Ix I

l 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 X

media being surveyed?

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

9. Is the data set comprised of qualified measurement results collected in accordance with the survey desinn, which accurately reflects the radiological status of the facility?

Graphical Data Review

1. Has a posting plot been created? X

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

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

1. Are all sample measurementsbelow the DCGLw (Class 1 8 2), or 0.5 DCGLW(Class 311 1 x 1

2. Is the mean of the sample data DCGLw? X

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

4. Is the resuli of the Elevated Measurements Test c 1.O? X

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

Form CS-0912 Rev 0 Page 1 of 1

SECTION 7 ATTACHMENT 4 1 DISC

0 COPY Design # EP-Rx 131 Revision # Original Page 1 of 3 Survey Unit kys)

2) EP Rx 131 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 131 were performed using a scintillation detector optimized to measure gamma energies representative of CO-60. Sample #EP 2 from Survey Request (SR)-13 was referenced for this decision.

4) Survey Instructions for this survey unit are incorporated into and performed in accordance with (IAW) the Babcock Services Incorporated (BSI)/LVS-002, Work Execution Package (WEP)05-006. Survey instructions described in this Description 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.

Approval Signatures I Date:

FSS Design # EP Rx 131 Revision # Original Page 2 of 3 1.o HistoryDescription 1.1 The subject pipe system is the 3 Quad B spare system line.

1.2 EP Rx 13 1 consists of approximately 25 feet in length from the Reactor Building -25 elevation, Quad B to the Sub Pile Room. The line has one 90 degree elbow along its length.

2.0 Survey Design Information 2.1 EP Rx 131 was surveyed IAW Procedure #BSI/LVS-002.

2.2 100%of the 3 ID pipe was accessible for survey. The accessible 3 ID pipe was surveyed by static measurement at one foot increments, for a total of 25 survey measurements.

2.3 Surface area for the 3 ID piping is 730 cm2for each foot of piping, corresponding to a total 3 ID piping surface area of 18,241 cm2(1.8 m2) for the entire length of (25) of 3 piping.

3.0 Survey Unit Measurement LocationsData 3.1 Pipe interior radiological survey forms are provided in Attachment 2 of this release record.

4.0 Survey Unit InvestigationsResults 4.1 None 5.0 Data Assessment Results 5.1 Data assessment results are provided in the EPBuried Pipe (BP) Survey Report provided in Attachment 1.

5.2 All measurement results are less than the Derived Concentration Guideline Level (DCGL) for radionuclide specific EP that corresponds to the 1 mrexdyr dose goal established in Table 3-3 of the FSSP.

5.3 When implementing the Unity Rule, provided in Section 3.6.3 of the FSSP, and applying the Nuclide Fraction (NF), provided in TBD-06-004, the survey unit that is constituted by EP Rx 13 1 passes FSS.

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

I FSS Design ## EP Rx 131 I Revision ## Original I ~age3of3 I Survey Unit: Rx 131 5.5 Statistical Summary Table I Statistical Parameter I

I Total Number of Survey Measurements 1 25 Number of Measurements >MDC 18 Number of Measurements Above 50% of DCGL 0 Number of Measurements Above DCGL 0 Mean 0.0286 Median 0.0171 I Standard Deviation 0.0256 I I ~ ~

Maximum 10.1107 I Minimum 10.0054 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 131 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.

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 13 1 & Spreadsheet

SECTION 7 ATTACHMENT 1 2 PAGE(S)

I@k& BSI EPIBP SURVEY REPORT Pipe ID Survey Location -25 el. Quad B Survey Date 2350-1 f 203488 Survey Time 13:38 DetectorSled # 44-159 2383691101 I

Detector Efficiency O.OOO66 Field YDCR ~cpn) iurvev Measurement Results Total Number of Survey Measurements 25 Number of Measurements >MDC 18 Number of MeasurementsAbove 50% DCGL 0 Number of MeasurementsAbove DCGL 0 Mean 0.0286 Median I 0.0171 Standard Deviation 0.0256 Maximum I 0.1107 Minimum 0.0054 Survey Technician@)

I STOCK MKtMlYK COntnbutlOn I

OMMENTS:

CTIVITY VALUES NOT BACKGROUND CORRECTED nr cnginwr 1 uaw 8/13/2007

EP Rx 131 3" Pipe TBD 06-004 Group 2

-

c C

Ee! I Cog0 activity I Cog0 activity Cs-137 activity Eu-162 activity E u - l U activity Nb-94 activity AglOBm activity Unity ncpm (total dpm) (dpmllOOcm2) (dpm/lOOcm2) ( d p d l OOcm2) (dpmllOOcm2) (dpmll OOcm2) (dpm1100cm2) a (I) m 3

28 42,424 _-__ 5,814 3,015 48

__-__ 34 3 _-

-

167 0.025-

_ _ 35 ~ - . 53,030 _ _ _ _ _ _ .

7,268 _.____

3,769 ._ --

60 ___.____

209 0.032

- 27 40,909 5,607 2.907

- 46 161 -- 0.024 40 60,606 .--__

8,306 69 4 239 0.03E

-~ ~

__! 61 92,424 - 12,667

__ - 6.568 ___- 105 6 365 0.05E

-_ 55 83,333 ~

11,421 5,922 95 6 329 ___0.05C 1

-- 71 107,576 14,743

__ ._ 7,645 122 86 7 424 0.064 I ~ 27,273 3,738

-~ ____

1,938 -___ 31 22 -2 108 0.01E

---

30 45,455 6,230 3,230 52

__ 36-3 179 _ 0.02i

_

- 78 118182 16,19f _-

8399 134 95 8- 466 __-0.07(

38 57.576 7.891 4,092 65 46 - 4 __-_ 227 _ _0.0s

_

_____ 186,364 25,541 - 13,244 212 150 12

-_ 735 0.111 54 81.818 _______ 11.213 5.814 93 66 -5 323 0.04E 1 3 ~ _____._

191697 __ 2,699

-~ __ -.__ 1,400 16._

1 70 0.01;

__ 6 _ _9,091

_ ~- 1,246 ___

7 1 36 0.00:

___ 13

- -.

19,697 2,699 -~ 1.400 22 1 _ _ _ _ ___-

78 0.01;

. ~

13 - 19,697 ~_____- 2,699 - 1,400 22 1 78 0.01; 7 10,606 _____-__ 1,454 ___ 754 12 ~-

1 42 0.OQ 11 16,667 2,284 1,184 ___ 19 1 66 0.01(

~- 10

-

15,152 2,077 1,077.. 17 12-1 60 0.00:

7~- 10,SW- 1,454 754 12 9 1 42 0.oa 2,284 ____ - 1,184 19 13 1 66 0.01(

11 16,667 ~

~ _~ ___-

10 15,152 2,077 1,077 - 17 12 1 __ .~

60 O.OO!

16 - 24,242 - 3,322 __-__ 1,723 -

28 - .- -19 2 96 0.01r 3,945 2,046 33 23 2 114 0.01;

-_ _ _ .

19- 28,780

_________-

__ ______

-

MEAN

- 0.02!

MEDIAN 0.01;

--__

STD D N 0.021 MAX 0.11'

___-

Mii O.OO!

lofl

SECTION 7 ATTACHMENT 2 3 PAGE(S)

BSVLVSPipeCrawler-002 Revision 4 Pipe Interior Radiological Survey Form Time: 3 3%-

Pipe ID#:

Date: PipeDiameter: 3" Access Point Area: 0m t 5 Building: L V Elevation: -2s' System: 5phpE- TD 5PR

-

Type of Survey Investigation Characterization Final Survey ->( Other Gross Co60 cs Detector ID# / Sled ID# #4 - / 7 I /

Detector Cal Date: 9/r/o G Detector Cal Due Date: 9 I , ,

Instrument: Z%O-/ Instrument ID #: Instrument Cal Date: 7 / 5 /Ob Instrument Cal Due Date: 3-/a7 I /

From the Daily Pipe Survey Detector Control Form for the Selected Detector BackgromdValue 2 cpm MDcRsmc LJ,$ cpm Efficiency Factor for Pipe Diameter 0 . 0 0 o bb (from detector efficiency determination)

MDCSWI, Zb48 dpml iC.0 cm' Is the MDC,,,, acceptable? @ No (ifno, adjust sample count tune and recalculate MDCK,,,)

Comments: (L A - %3zqs W R U ' /0O0~ -z5/

Technician Signature Pipe Interior Radiological Survey

- - .. -

-

, Package Page 1 o f 3 Attachment 3, Page 1

BSULVSPipeCrawler-002 Revision 4 Pipe Interior Radiological Survey Form (Continuation Form)

Package Page o f 3 REFERENCECOPY Attachment 3, Page 2

SECTION 7 ATTACHMENT 3 PAGE(S)

DQA Check Sheet Design # I EP Rx 131 1 Revision # I Original I Survey Unit# I EP Rx 131 Preliminary Data Review Answers to the following questions should be fully documented in the Survey Unit Yes No NIA 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 survey units? I I l x

3. 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 embeddedlburied piping scan measurements below the DCGLW,or, if not, was the need for additional X static measurements or soil samples addressed in the survey design?

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 X media being surveyed?

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

9. is the data set comprised of qualified measurement results collected in a m d a n c e with the survey design, which accurately reflects the radiological status of the facility?

1. Has a posting plot been created? I x

2. Has a histogram (or other frequency plot) been created? I I l x

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

1. Are all sample measurements below the DCGLw (Class 1 & 2), or 0.5 DCGLw (Class 3)? X

2. Is the mean of the sample data DCGLW? X

3. If elevated areas have been identified by scans and/or sampling, is the average activity in each X elevated area c DCGLEMC (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 result of the statisticaltest (S+ for Sign Test or W, for WRS Test) 2 the critical value? I I I x Comments:

Page 1 of I

SECTION 7 ATTACHMENT 4 1 DISC

0 COPY Survey Unit Release Record Design # EP 1.38 Revision # Original Page 1 of 3 Survey Unit #(s)

Description I

FSS/Characterization Engineer

FSS Design # EP 1.38 Revision # Original 1 Page 2 of3 1.o History/Description 1.1 EP 1-38 was the Quad BDrain.

1.2 The subject pipe is the drain from Quad B in the Containment Building to the -25 ft of the Rx Building in mUnp Room #22. The function of this pipe was to convey water fiom Quad B in the Containment Building to the HD sump in Pump Room #22 on the Rx Building -25 ft, where the pipe is currently breached.

1.3 EP 1.38 consists of approximately 37 linear feet of piping, consisting of 6 and 10 diameter pipes, running from the breach point in Pump Room

1. 22 to the two strainer grates adjacent to the wall in Quad B, involving two bends of approximately 30 each and a tee to a secondary inlet at the Quad B end A diagram of the piping is included in Section 7, Attachment 2.

2.0 Survey Design Information 2.1 EP 1.38 ti^ S U ~ V VIAW~ froced~re#BSEILVS-OOZ.

2.2 100% of the 10 and 6 ID pipe was accessible for survey. The accessible 10 and 6 ID pipe was surveyed by static measurement at one foot increments, for a total of 37 survey measurements.

2.3 Surface area for the 10 ID piping is 2,432 cm2for each foot of piping, corresponding to a total 10 ID piping surface area of 80,256 cm2(8.0 m2) for the entire length of (33) of 10 piping.

2.4 Surface area for the 6 ID piping is 1,459 cm2for each foot of iping, corresponding to a total 6 ID piping surface area of 5,836 cm;P(0.6 m) for the entire length (4) of 6 piping.

2.5 Total surface area for both the 10 and 6 piping that constitutes EP 1.38 is 8.6 m2.

3.0 Survey Unit Measurement L o c a . t i o ~ a t a 3.1 Pipe interior radiological survey forms are provided in Attachment 2 of this release record.

4.0 Survey Unit InvedgatiomRmdb 4.1 None 5.0 Data Assessment Results 5.1 Data assessment results are provided in the EP/Buried Pipe (BP) Survey Report provided in Attachment 1.

5.2 All measurement results are less than the Derived Concentration Guideline Level (DCGL) for radionuclide specific EP that corresponds to the 1 m d y r dose goal established in Table 3-3 of the FSSP.

I I I FSS Design # EP 1.38 1 Revision # Original 1 I

/ Page3of3 I Survey Unit: 1.38 1 5.3 When implementing the Unity Rule, provided in Section 3.6.3 of the FSSP, and applying the Cesium-l37/Cobalt-60 ratios, provided in TBD-06-004, the survey unit that is constituted by EP 1.38 passes FSS.

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

5.5 Statistical Summary Table 1 I O Pipe I 6 Pipe I Total Number of Survey Measurements 33 4 Number of Measurements>MDC 0 4 Number of Measurements Above 50% of 0 0 DCGL Number of MeasurementsAbove DCGL 0 0

~

Mean 0.015 0.002 Median 0.015 0.002 Standard z)eviation 0.003 0.001 Maximum 0.021 0.003 Minimum 0.010 0,001 6.0 Documentation of evaluations pertaining to compliance with the unrestricted use limit of 25 mremyr and dose contributions from Embedded Pipe and radionuclides contributing 10% in aggregate of the total dose for both structural scenarios and soils.

6.1 A review of the survey re- has shown tbt the dose contribution for EP 1.38 to be less than 1 mredyr. The dose contribution is estimated to be

<0.015 mredyr based on the actual gross counts measured.

7.0 Attachments Attachment 1 - BSI EPBP S w e y Report Attachment 2 - Pipe Interior Radiological Survey Form Attachment 3 - DQA Worksheet Attachment 4 -Disc containing RR for EP 1.38 & Spreadsheet

SECTION 7 ATTACHMENT 1 J PAGE(S)

BSI EPlBP SURVEY REPORT Median 0.015 0.002 Standard Deviation 0.003 0.001 Maximum 0.021 0.003 Minimum 0.019 0.001 II Survey Technician@)

t Survey Unit Classification 1 TBD Of3404 Piping Group 2 SR-13 Radionuclide Distribution Sample EP 2-1 Measured Nudide COG0 Area FactwEMC Used No P a M a i l FSS Pass MREMNR ConbibutJon 4 RP Engineer I Date

@A /7.3,=07

EP 1.38 I O " Pipe TBD 06-004 Group 2

\

Cs-137 acUvlty p 5 2 activity Eu-154 a&ty Nb-94activity Ag-lO8m activity gcpm ncpm (dpm1100cm2) dpdlOOcm2) (dpm1100cm2) (dpmllOOcm2) (dpm11Okm2)

- c J

'1 30E _~ 30t 102,667 4,221 2,191 - 35

__2% 2% 78,667 3,235 1,679 27 33E -- 33c 110,000 --- 4,523 2,347 __38 32: 32: 108,333 4,454 2,312 __ 37 31( 31E - 103,333 4,249 2,205 -

35 30: 30: ____- 101,000 4,153 2,155 34 31i 31i 105,667 4,345 - 2,255 36 31t 31f ~ _105,333 _ _ - 4.331 -_.- 2,248 - 36 35! 35! 118.333 4,866 __ _.__ 2,525 40 314 31~ ~~

4,304 2.234 36 31! 31! 4,317 28 28' 93I667 --__3,851 281 28( 93,333 ~ 3,838

_ _

32: 32; 107,333 4,413 21! 21! 73,000 3,002 19: 19: 64,000 2,632 19 19 64,667 2,659 22 17 17! 58,333 __

2,399 1,245 20 - 20: 67,333 2,769 1,437 17 ___ 171 56,667 2,33C _ _ _ _ _ 1,209 18 18, 61,667 2,53

- _-___

19 63,667 ____

19 _ _ _ _ _.__- 2,61 .

19 19 64,667- 2,655 - _ _ _ _22 1-75 76.667 3,152 1.636

-_

2E r-78,335 70,00[

73.661 I 3,221 2,87 3.02s 1 of2

Cos0 actMty Co-60 activity Cs-I 37 a a t y Eu-152 activity Eu-164 activity Nb-94 activity Ag-108m activity ncp(total dpm) (dpm1100cmZ) (dpm/lWcmZ) (dpm1100cm2) (dpm1100cm2) (dpdl00cmZ) (dpmllOOun2) 235 78,333 3,221 1,672 27 __ -19 2 - 93-

_____- - _- - -

- __ ~ . _ _ _ _ _

__ ___ - ~. --___ ~ ~.

MEAN 0.015

_. ~

MEDIAN 0.015

___ ~ _ _____ _ -~ ~ __ ~ __ -. --

- STDDEV -

0.003

_- - ~ __ _ _ - ---____-_ - __ - _ _- MAX

.

MIN 0.010 2of2

EP 1.38 6" Pipe TBD 06-004 Group 2

+,

E Cog0 cs-137 Eu-152 Eu-I54 Nb-94 Ag-108m Ee! 'Os' activity activity activity activity activity acUvity Unity 3 gcpm ncpm activity (total dpm)

(dpm/lM)cm (dpm1100cm (dpm1100cm (dpmllWcm (dpm/lM)cm (dpm/lOOcn 8 2) 2) 2) 2) 2) 2) 3 1 lo 10 .___---5,000 343 178 ____ 3 _ _ _ _ _ _ _2_ _ _ 0

-

10 ____ 0.001

-~ 2

.

10 10 5,000 .- ~ _ 343

__ - - 178

______ 3 2 -_ _ _ 0

- -~ __ 10

-

0.001

__ 3 __ 12

__ . _ _ _ 12 6,000 411 ___ 213 3 2 ___ 0 -- -12 -0.00;

-.--

4 19 19 9,500 65 1 338 5 4 0 19 0.00:

- - _0.00;

_

-- _0.00;

-_ _

0.00'

~

~ -0.0

_0: _

0.00' 1 of 1

SECTION 7 ATTACHMENT 2 PAGE(S)

Pipe Interior Radiologid Survey Form Date: / L OJ/

Type of Survey Investigation Sled size 10 I Pipe Interfor Radiologleal Survey Package Page I of&

Attachment 3, Page 1

I i

Pipe Interior Radiological Survey Form (Continuation Form)

- . _ _ -- __ I I I - . .

I Package Page & of=

Attachment 3, Page 2

Pipe Interior Radiological Survey Form Date: 1-,7-06 Time: /ox-Building: (2-x Elevation -ZJ Access Point System: Plra J PipeDiameter: 6 Area: PipeD / , 3 g /a-tn Type of Survey Investigation Characterization - 9 ## Other J Sled Size 6 f l inch /3,~~.?+7 //K&r s/,J Detector: Lu5 i t +

1 4 9 4 L.--G Detector ID #: [eLd - f +/c7 Cal Date: [ L-ZO -c3 >- Cal Due Date: / t - Z O -0G Instrument: 2-3JT9-I Instrument ID #: /3P7JS Cal Date: IZ-LO -or Cal Due Date: / 2 -Ld Q From the Daily Pipe Survey Detector Control Form for the Selected Detector Background Value Jb. 3 cpm MDCRstatic /g0s cpm Efficiency Factor for Pipe 0.00 7 (taken from detector

-

M e tstatlc er 3.33 dpm/100cm2 Is the MDC,,,, No (if no, adjust sample count time and recalculate MDW,,)

C&%ERB? r ~)lV7/nld&lT~ 0 4l 3edcy - /nrp p C p l 4 2 r*L /,3GA pa5*3*( Wrr /.sa4 f c>rnf l [ ~ T K Pipe Interior Radiological Survey Radiological Survey Commenced: Date: ( -/ Time: O L ? ~

I I Package Page 1 o f I Attachment 3, Page 1

-

--

I SECTION 7 ATTACHMXNT 3 I PAGE(S)

~~

DQA Check Sheet Design # - 1 ~~

EP 1.38

~

I ~

Revision #

~

I Original 1 Survey Unit # EP 1.38 Preliminary Data Review Answers to the following questions should be fully documented in the Survey Unit Yes No NIA 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 DCGLWfor Class 3 survey units? I X lx

3. Is the instrumentation MDC for embeddedhuried piping static measurements below the DCGLw ?

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 X static measurements or soil samples addressed in the survey design?

5. Was the instrumentation MDC for volumetric measurements and smear analysis 10% DCGLW? 1 X

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

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

~~~~~ ~ ~~ ~

3. Were Special Methods for data collection properly applied for the survey unit under review? 1 x 1 I

3. Is the data set comprised of qualified measurement results collected in accordance with the survey X design, which accurately reflects the radiological status of the facility?

GraDhical Data Review

1. Has a posting plot been created? X

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

3. Have other graphical data tools been created to assist in analyzing the data? I I I x Data Analysis

1. Are all sample measurements below the DCGLw (Class 1 & 2). or 0.5 DCGLw (Class 3)? X

2. Is the mean of the sample data < DCGLw? X

3. If elevated areas have teen identifiedby scans and/or sampling, is the average activity in each X elevated area < DCGLam: (Class f), c DCGLw (Class 2), or ~ 0 . DCGLW 5 (Class 3)?

4. Is the result of the Elevated Measurements Test c 1.O? X

5. Is the result of the statistical test (S+for Sign Test or W, for WRS Test) ? the critical value? X hnments:

FSSICharacteriration Engineer @tintisign) Date L-L-07 FSSl Characterization Manager (prinvsign)

Form CS-Q9/2 Rev 0 Page 1 of 1

SECTION 7 ATTACHMENT 4 1 DISC

t 1 0 COPY Design # EP- 1.41 A-4 Revision # Original Page 1 of 3 Survey Unit #(s)

2) EP 1.41A-4 is a Class 1, Group 1 survey unit as per the PBRF Final Status Survey Plan (FSSP) and Technical Basis Document (TBD)-06-004.

3) Surveys in EP 1.41A-4 were performed using a scintillation detector optimized to measure gamma energies representative of CO-60.Sample #EP 3-9 from Survey Request (SR)-13 was referenced for this decision.

4) Survey Instructions for this survey unit are incorporated into and performed in accordance with (IAW) the Babcock Services Incorporated (BSI)/LVS-002, Work Execution Package (WEP)05-006. Survey instructions described in this Description document constitute Special Methods and the survey design used in the acquisition of survey measurements.

5 ) Instrument efficiency determinations are developed in accordance with the BSVLVS-002, WEP 05-006, these determinations are appropriate for the types of radiation involved and the media being surveyed.

I I I FSS Design # EP 1.41A-4 Revision # Original Page 2 of 3 1.0 HistorylDescription 1.1 The subject pipe system is a 4" Quad "C" system line.

1.2 EP 1.41A-4 consists of approximately 48 feet in length fkom the Reactor Building -25' elevation to Quad "C".

2.0 Survey Design Information 2.1 EP 1.41A-4 was surveyed IAW Procedure #BSL/LVS-002.

2.2 100% of the 4" ID pipe was accessible for survey. The accessible 4" ID pipe was surveyed by static measurement at one foot increments, for a total of 48 survey measurements.

2.3 Surface area for the 4" ID piping is 973 cm2for each foot of piping, corresponding to a total 4" ID piping surface area of 46,698 cm2(4.7 m2) for the entire length of (48') of 4" piping..

I 3.0 Survey Unit Measurement Locations/Data 3.1 Pipe interior radiological survey forms are provided in Attachment 2 of this release record.

4.0 Survey Unit InvestigationdResults 4.1 None 5.0 Data Assessment Results 5.1 Data assessment results are provided in the EP/Buried Pipe (BP) Survey Report provided in Attachment 1.

5.2 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.

5.3 When implementing the U n i i thp-FSSP, and applying the Nuclide Fraction (NF), provided in TBD-06-004, the survey unit that is constituted by EP 1.41A-4 passes FSS.

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

-

FSS Design # EP 1.41A-4 Revision # Original Page 3 of 3 Survey Unit: 1.4 1A-4 5.5 Statistical Summary Table

~

4" Statistical Parameter Pipe Total Number of Survey Measurements 48 Number of Measurements >MDC 48 Number of Measurements Above 50% of DCGL 0 Number of Measurements Above DCGL 0 Mean 0.0891 Median 0.0784 Standard Deviation 0.0532 Maximum 0.3065 Minimum 10.0212 Documentation of evaluations pertaining to compliance with the unrestricted use limit of 25 mredyr and dose contributions from Embedded Pipe and radionuclides contributing 10% in aggregate of the total dose for both structural scenarios and soils.

6.1 A review of the survey results has shown that the dose contribution for EP 1.41A-4 to be less than 1 mdyr. The dose contribution is estimated to be 0.089 mredy-r based on the average of the actual gross counts.

-

mments Attachment 1 - BSI EP/BP Survey Report Attachment 2 - Pipe Interior Radiological Survey Form Attachment 3 - DQA Worksheet Attachment 4 -Disc containing RR for EP 1.41A-4 & Spreadsheet

I SECTION 7 ATTACHMENT 1 3 PAGE(S)

i lliiki@.-

-L- _ L BSI EP/BP SURVEY REPORT t

I' Pipe ID Survey Location II -27 Trench I Survey Date 01-Mar-06 1I 2350-1 P I

203488 I

I SunreyTime I 10:15 II DetectorSled P I lMG1 LVS-lI101 I Pipesize I 4" II Detector Efficiency 1 0.00052 DCGL m m aq 2.41 EM5 RphIncopon.dbY-Lmdrryh=Ul 973 Field BKGIWI 21.7 Routine Survey Field MDCR4m) 19 Maximum I 0.3065 Minimum 0.0212 ROSENHAGEN Survey Technician@)

__

LUES NOT BACKGROUND CORRECTED RP Engineer I Date 8-2-07

Z P1

m'O 99 1EZ P66'1 1 004'L 160'0 so 1 8EP 88L'E 1SZ'P1 190'0 08 SEE 168'2 9L8'0 1 vsv 99p'cc 190.0 PL 116 Z69'Z 921'01 EZP PL9'0 1 K)1-0 PZ 1 619 98P'P 9L8'91 82 ilC'0 6E 1 E8S 980'9 866'8 1 CEZ'p6 1 LO1 LZ i60'0 91 1 CSL'91 - 91

LO'O 98 919' 11 1Z'6L L 59 91 MOO vs ElE'L - 90E 60L'L 000'9L 68 ?E PZ 180'0 EO 1 ESO'PL 88s 9Z8'P 1 CEZ'W1 ~

SL

--__

.60'0 901 PPP 8EP'P 1 - 09 OZZ'4 1 LLO'8Pl LL rLO'O L8- 98 I OW' I 18'11 - p6P ESP'Z 1 vsc'czc 9 360'0 P11 6LP LEL'P E S ' S1 099 WP'9 1 S19'691 8 301'0 PZ 1 619 98P'P 9L8'91 SOL 06L'L 1 LLO'ELC 181'0 112 E88 LZ9'L 689'81 - 661'1 EPZ'OE lEZ'p6Z ESl

)P1'0 P9C 989 ZE6'9 PlB'ZZ - 166 1 EZS'EZ 9P8'8ZZ 611

)Z 1'0 1Pl 889 WO'S 911'61 - 66L 1 191'02 s1'961 101

!OE'O 8SE 005'1 096'11 ZGL'8P

______ LEO'Z t6'19 000'009 091 iLO'O Z6 988 OW' ES'Z1 SZS PPZ'E 1 9p8'8Z1 L9 3Zl.O LPl m'oz 8E8 CSl'lZ 69L'SOZ LO1 361'0 182 696 PLE'8 ZOS'lE 9CE'l 80Z'EE LLO'EZE 891

.E1'0 9 1 OP9 EES'9 P18'0Z OL8 1P6'1z Z9p'ElZ 111

$11'0 6E 1 E89 SEO'S I 866'8 1 - l6L 996'6 1 lEZ'P61

!9 1'0 68 1 06L 618'9 ~ 180'LZ 689'92 -_ LO'1

6 C '0 LZZ Z96 921'8 686'OE E6Z' 1 I Sl9'ZE 80E'L 16

,CC'O 6Z 1 ZW 989'P 919'L 1 9EL

- _- I . _- .

18S'81 20.0 98 8% 160% 919' 11 98P 94z'z 1 iLO.0 88 6% 06C'E 100'11 - 104 1S9'Z1

$80'0 EO 1 EEP 6EL'E I E90'P 1 SZ8'Pl UO.0 16 18E 9LE'Zl 0 6 Z ' E /

so-o 091 EPZ'Z 1 8P'8 968'8 869'98

__-

90.0

- 90E lzm'z 1 866'6 S 19 9LP'O 1 16' 10 1 I ~

Qun urd3u urd36

-

EP 1.41A-4 4" Pipe TBD 06-004 Group I

-

C0-60 acUvity Cs-137 activity Eu-152 activity Nb-B4 acUvity Ag-108m activity (dpm/lWcm2) (dpm/lOOcm2) (dpmllOOcm2) (dpmllWcm2) (dpm1100cm2) Unrty

-

I I

155,769 16,011 ______ 635 15,188 1 4,038 0.09:

-_

___ 73 140,385 .

. 14,430 572 13,688 1 3,639 0.08E

-~ 36 69,231 7,116 282 - 6,750 1 1,795 208 0.04; 26 5,139 204 4,875 150 . 36 0.03*

18 34,615 3.558 141 3,375 104 25 0.021 27 27 51,923 5,337 212 5,063 156 37 0.03; 38 38 73.077 7,511 298 - 7,125 219 52 0.04:

___ 40 7,907 313 7.500 231 55 0.04; 27 5,337 212 - 5,063 156 37 0.03; 28 5,535 219 5.250 162 39 0.03:

42 8,302 329 7,875 242 58 0.05(

32 6,325 251_.

- 6,000 185 44 0.03E 47 90,385 9,290 368 - 8,813 271 65 0.05:

51 98,077 10,081 400 9,563 294 70 0.06(

~- 77 15,220 603

_ _ _ 14,438 444 106 0.09' 43 43 82,692 8.500 337 8,063 248 59 0.05'

___--

t

_____

-0.08s MEDIAN 0.07t STD DEV 0.05:

__

0.30;

-

~-

0.02; T

2of2

I SECTION 7 ATTACHMENT 2 4 PAGE(S)

I BSYLVSPipeCrawler-002 Revision 4 Pipe Interior Radiological Survey Form Date: 3 -- /.+c c Time: /d/<

L+&-J c Pipe ID#: / /W 4 Pipe Diameter: 4' I Access Point Area: dp Jczz&

Building: Z6 Elevation: 'ZZ &)fiD p, System: &w n Type of Survey Investigation Characterization Final Survey K Other u~

140

~ % - b Gross Co60 o/ cs Detector ID# I Sled ID# d/k+?oN /hf e 1 I /& 1

-

Detector Cal Date: zt' PEc YL' Detector Cal Due Date: P - 9Ec 0 t Instrument: 2363 - t Instrument ID #: 2d3~VJ'

-

Instrument Cal Date: / 7 r ; .J~ - aii- Instrument Cal Due Date: i7- d o / -o&

From the Daily Pipe Survey Detector Control Form for the Selected Detector Background Value 18 ? cpm MDCRStat,, cpm Efficiency Factor for Pipe Diameter 0. 0 0052 (from detector efficiency determination)

MDcstatlc 155 7 dPd lrr0 cm2 Is the MDCstatIcacceptable? @ No (if no, adjust sample count time and recalculate MDCR,,,)

Comments: <

4 / t i , &-L Techcian Signature

//

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

I BSI/LVSPipeCrawler-O02 Revision 4 Pipe Interior Radiological Survey Form (Continuation Form)

Date: 7 ob Q M ~ e{ESJeL Pipe ID#: /e 49 Pipe Diameter: +I Access Point Area: /J=+ c/p Lurj.cL Building:  ;;3g Elevation:

-dah- QW3 & System: 7 / n& 5 A  :>.E /;r Package Page of 3 REFERENCECOPY Attachment 3, Page 2

I BSYLVSPipeCrawler-002 Revision 4 Pipe Interior Radiological Survey Form (Continuation Form)

Date: / e d 6 Cya4-3 r Pipe ID#: t4 t// Pipe Diameter: dC Access Point Area: 5- up d.cJ S f L Building: K P-+- Elevation: -23 qrA*D c System: 7Zt6n%C t i r ~ 3 ~ , R Package Page 2 of $

0 REFERENCE COPY Attachment 3, Page 2

REFERENCE COPY 2 .

SECTION 7 ATTACHMENT 3 1 PAGE(S)

I I Design # EP 1.41A-4 Revision # Original Survey Unit # EP 1.41A-4 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

2. Is the instrumentation MDC for structure static measurements below the DCGLw for Class 1 and 2 X

survey units, or below 0.5 DCGLWfor Class 3 survey units?

3. Is the instrumentation MDC for embedded/buriedpiping static measurements below the DCGLW? X

1. Was the instrumentation MDC for structure Scan measurements, soil scan measurements, and embeddedlburied piping scan measurements below the DCGLw,or, if not, was the need for additional X static measurements or soil samples addressed in the survey design?

5. Was the instrumentation MDC for volumetric measurements and smear analysis 10% DCGLw ? X

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 X

media being surveyed? ~ ~~

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

3. Is the data set comprised of qualified measurement results collected in accordance with the survey X design, which accurately reflects the radiologicalstatus of the facility?

~ -

I. Has a posting plot been created? X

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

3. Have other graphical data tools been created to assist in analyzing the data? I I I x Data Analyds I. Are all sample measurements below the DCGLW(Class 1 8 2), or 0.5 DCGLw (Class 3)? X

!. Is the mean of the sample data DCGLW? X

3. If elevated areas have been identifiedby scans andor sampling, is the average activity in each X elevated area < DCGLEMC(Class l),DCGLw (Class 2), or ~ 0 . DCGLw 5 (Class 3)?

1. Is the result of the Elevated MeasurementsTest e 1.O? X

i. Is the result of the statisticaltest (S+ for Sign Test or W, for WRS Test) 2 the critical value? X hmments:

/I cs-0912 Page 1 of 1

,

SECTION 7 ATTACHMENT 4 1 DISC

i Design ## EP- 1.41A-6 Revision # Original Page 1 of 3 Survey Unit #(s)

2) EP 1.41A-6 is a Class 1, Group 1 survey unit as per the PBRF Final Status Survey Plan (FSSP) and Technical Basis Document (TBD)-06-004.

3) Surveys in EP 1.41A-6 were performed using a scintillation detector optimized to measure gamma energies representative of CO-60.Sample #EP 3-9 fiom Survey Request (SR)-13 was referenced for this decision.

4) Survey Instructions for this survey unit are incorporated into and performed in accordance with (IAW) the Babcock Services Incorporated (BSI)/LVS-002, Work Execution Package (WEP)05-006. Survey instructions described in this Description document constitute Special Methods and the survey design used in the acquisition of survey measurements.

5 ) Instrument eficiency determinations are developed in accordance with the BSI/LVS-002, WEP 05-006, these determinations are appropriate for the types of radiation involved and the media being surveyed.

I J 1 FSS Design # EP 1.41A-6 1 Revision # Original I ~age2of3 I Survey Unit: 1.41A-6 I

1.o History/Description 1.1 The subject pipe system is a 6 Quad C system line.

1.2 EP 1.41A-6 consists of approximately 16 feet in length from the Reactor Building -25 elevation to Quad C.

2.0 Survey Design Information 2.1 EP 1.41A-6 was surveyed IAW Procedure #BSI/LVS-002.

2.2 100% of the 6 ID pipe was accessible for survey. The accessible 6 ID pipe was surveyed by static measurement at one foot increments, for a total of 16 survey measurements.

2.3 Surface area for the 6 ID piping is 1,459 cm2for each foot of piping, corresponding to a total 6 ID piping surface area of 23,344 cm2(2.3 m2) for the entire length of (16) of 6 piping..

3.0 Survey Unit Measurement LocationdData 3.1 Pipe interior radiological survey forms are provided in Attachment 2 of this release record.

4.0 Survey Unit InvestigationslResults 4.1 None 5.0 Data Assessment Results 5.1 Data assessment results are provided in the EP/Buried Pipe (BP) Survey Report provided in Attachment 1.

5.2 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.

.-

5.3

--

When implementing the Unity Rule, provided in Section 3.6.3 of the FSSP, and applying the Nuclide Fraction (NF), provided in TBD-06-004, the survey unit that is constituted by EP 1.41A-6 passes FSS.

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

I J FSS Design # EP 1.41A-6 Revision # Original Page 3 of 3 5.5 Statistical Summary Table 6"

Statistical Parameter Pipe Total Number of Survey Measurements 16 Number of Measurements >MDC 16 I Number of MeasurementsAbove 50% of DCGL I 0 I Number of Measurements Above DCGL 0 Mean 0.0857 I Median 10.0644 I I Standard Deviation 10.0737 I r 10.3495 I I Minimum 10.0429 1 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 1.41A-6 to be less than 1 mredyr. The dose contribution is estimated to be 0.086 mredyr based on the average of the actual gross counts.

73- ~

Attachment 1 - BSI EPBP Survey Report Attachment 2 - Pipe Interior Radiological Survey Form Attachment 3 - DQA Worksheet Attachment 4 -Disc containing RR for EP 1.4 1A-6 & Spreadsheet

SECTION 7 ATTACHMENT 1 PAGE(S)

B%I EP/BP SURVEY REPORT I PipeID I EPlAlA-6 Survey Location -27 Trench sunmy Date 1WuI-07 2350-1 # 189094 S U ~n Ym DebctorSled P 1MGl LVS-lI101 6" Detector Efficiency 0.0002 DCGL 2.41E 9 5 4 ne 4 1 L.a I

I RoutineSurvey ] X I 10 J Nominal MDC (dpnnLmw Survey MeasurementResults 3,143 ACTMTY VALUES NOT BACKGROUNDCORRECTED RP EngineerI Date 81MDo7

EP 1.41A-6 6" Pipe TBD 06-004 Group 1

• U I

1 C

E Cos0 activity C060 activity Cs-137 activity Eu-152 activity E M S 4 activity Nb-94 actiVyr Ag-108m activity gcpm ncpm (total dpm) (dpm1100cm2) (dpmllWcm2) (dpmllOOcm2) (dpm1100cm2) (dpm1100cm2) (dpm11OOcm2) unw 8

3 1 31 31 155,000 10,624 42 1 10,078 2,679 310 74 0.063 2 3 0 30 150,000 10,281 407 9,753 2,593 300 72 0.061 3 3 4 34 170,000 11,652 462 11,053 2,938 340 81 0.069 4 26 26 130,000 8,910 353 8,452 2,247 260 62 0.053 5 35 35 175,000 11,995 475 11,378 3,025 350 - &I 0.072 6 27 27 135,000 9,253 367 8,777 2,333 270 64 0.055 7 5 6 56 280,000 19,191 76 1 18,205 - 4,840 560 -__

134 0.114 8 171 171 855,000 58,602 2,323 55,590 14,778 1,710 408 - 0.350 9 3 6 36 180,000 12,337 489 11,703 3,111 360 86 0.074 10 53 53 265,000 18,163 720 17,230 4,580 530 127 0.108 11 49 49 245,000 16,792 666 15,929 4,235 490 117 0.100 12 24 24 120,000 8,225 326 7,802 2,074 240 57 0.049 13 21 21 105,000 7,197 285 6,827 1,815 210 - 50 0.043 14 23 23 115,000 7,882 312 7,477 1,988 -230 55 0.047 15 32 32 160,000 10,966 435 10,403 2,765 320 76 0.065 16 23 23 115,000 7,882 312 7,477 1,988 230 55 0.047 MEAN 0.086

- ~

MEDIAN __ 0.064 1

I STD DEV 0.074 I MAX -_ 0.350 1 MIN 0.043 1 of1

SECTION 7 ATTACHMENT 2 z PAGE(S)

I BSYLVSPipeCrawler-002 Revision 5 Pipe Interior Radiological Survey Form Date: 7 - 1 I b> - Time: lL30 Pipe ID#: .q I )A Pipe Diameter:

'I Access Point Area: &A\Zk*>S$*&

Building: C\/ Elevation: -27' System:

Type of Survey Investigation Characterization Finalsurvey x- Other \/

Gross Co60 J cs Detector ID# / Sled ID# \ mG\ -

/ U J5 1 f 101 Detector Cal Date: \ - \ 1 - 03 Detector Cal Due Date: \ -\b ok lnstrumen t :  %>So- \ Instrument ID #: N?\B1q Instrument Cal Date: -

1 11 0 7 Instrument Cal Due Date: \ - \ I -'uG From the Daily Pipe Survey Detector Control Form for the Selected Detector Backgroundvalue 3 . 3 cpm MDCRStatiC \D CPm Efficiency Factor for Pipe Diameter 0.0 0 02 @om detector efficiency determination) mcstatic 31U d p d cm2 Is the MDCsuQcacceptable? @ No (if no, adjust sample count time and recalculate h4Dmmec)

Comments: -JXA;~\ KP 3-7 \b'dVkh.LI$/C 0 \.\)O% CI)

Technician Signature Pipe Interior Radiological Survey 7

a Package Page 1 of -

REFERENCE COPY Attachment 3, Page 1

BSbLVSPipeCrawler-002 Revision 3 Pipe Interior Radiological Survey Form (Continuation Form)

Date:

Pipe ID#: Pipe Diameter: 6 Access Point Area: b& -35 Building : Elevation: J System:

Attachment 3, Page 2

SECTION 7 ATTACHMENT 3 I PAGE(S)

I I DQA Check Sheet Design # EP 1.41A-6 Revision # Original Survey Unit # EP 1.41A-6 Preliminary Data Review' Answers to the following questions should be fully documented In the Survey Unit Yes No N,A Release Record

1. Have surveys been performed in accordance with survey instructionsin the Survey Design? X

2. Is the instrumentation MDC for structure static measurements below the DCGLw for Class 1 and 2 X survey units, or below 0.5 DCGLw for Class 3 survey units?

3. Is the instrumentation MDC for embeddedlburied piping static measurements below the DCGLw ? X

4. Was the instrumentation MDC for structure scan measurements, soil scan measurements, and embedded/buried piping scan measurements below the DCGLW,or, if not, was the need for additional X static measurements or soil samples addressed in the survey design?

5. Was the instrumentation MDC for volumetric measurements and smear analysis < 10% DCGLw ? X

6. Were the MDCs and assumptions used to develop them appropriate for the instruments and techniques 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. 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 collectedin accordance with the survey X

design, which accurately reflects the radiologicalstatus of the facility?

Graphical Data Review

1. Has a posting plot been created? X

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

3. Have other graphical data tools been created to assist in analyzing the data? I I 1 x

1. Are all sample measurements below the DCGLW(Class 1 & 2), or 0.5 DCGLw (Class 3)? X

2. Is the mean of the sample data DCGLW? X

3. If elevated areas have been identitiedby scans and/or sampling, is the average activity in each X

elevated area DCGLEK (Class I), < DCGLW(Class 2),or ~ 0 . DCGLw 5 (Class 3)?

4. Is the result of the Elevated MeasurementsTest < 1.O? X

5. Is the result of the statisticaltest (S+ for Sign Test or W, for WRS Test) 2 the critical value? X FSS/CharacterizationEngineer (printlsign)

F S S Characterization Manager (printlsign)

FI

• -

CS-09J2 Page 1 of 1

SECTION 7 ATTACHMENT 4 1 DISC

Survey Unit Release Record

-

Design # EP-1.42A-4 1 Revision # 1 Original 1 Page 1 of 3 Survey Unit #(s) 1.42A-4

1) Embedded Pipe (EP) Survey Unit 1.42A-4 meets the definition of embedded pipe for Plum Brook Reactor Facility (PBRF).

2) EP 1.42A-4 is a Class 1, Group 1 survey unit as per the PBRF Final Status Survey Plan (FSSP) and Technical Basis Document (TBD)-06-004.

3) Surveys in EP 1.42A-4 were perfurmed using a scintillation detector optimized to measure gamma energies representative of (20-60. Sample #EP 3-9 from Survey Request (SR)-13 was referenced for this decision.

4) Survey Instructions for this survey unit are incorporated into and performed in accordance with (IAW) the Babcock Services Incorporated (BSI)/LVS-002, Work Execution Package (WEP)05-006. Survey instructions described in this Description document constitute Special Methods and the survey design used in the aquisition of survey measurements.

5 ) Instrument efficiency determinations are developed in accordance with the BSYLVS-002, WEP 05-006, these determinations are appropriate for the types of radiation involved and the media being surveyed.

1 FSS Design ## EP 1.42A-4 Revision # Original Page 2 of 3 Survey Unit: 1.42A-4 1.o History/Description 1.1 The subject pipe system is a 4 Quad C system line.

1.2 The piping designated EP 1.42A-4 is approximately 48 feet in length from the Reactor Building -25 elevation to Quad (2.

2.0 Survey Design Information 2.1 EP 1.42A-4 was surveyed IAW Procedure #BSI/LVS-002.

2.2 100% of the 4 ID pipe was accessible for survey. The accessible 4 ID pipe was surveyed by static measurement at one foot increments, for a total of 48 survey measurements.

2.3 Surface area for the 4 ID piping is 973 cm2for each foot of piping, corresponding to a total 4 ID piping surface area of 46,698 cm2(4.7 m2) for the entire length of (48) of 4 piping..

3.0 Survey Unit Measurement LocationdData 3.1 Pipe interior radiological survey forms are provided in Attachment 2 of this release record.

4.0 Survey Unit Investigations/Results 4.1 None 5.0 Data Assessment Results 5.1 Data assessment results are provided in the EPBuried Pipe (BP) Survey Report provided in Attachment 1.

5.2 All measurement results are less than the Derived Concentration Guideline LeveI (DCGL) for radionuclide specific EP that corresponds to the 1 mredyr dose goal established in Table 3-3 of the FSSP.

5.3 When implementing the Unity Rule, provided in Section 3.6.3 of the - -

Fssp,and appIying the Nuclide Fraction 0,

~

~

provided in TBD-06-004, the survey unit that is constituted by EP 1.42A-4 passes FSS.

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

I t

~~ ~

FSS Design ## EP 1.42A-4 Revision # Original Page 3 of 3

!

I Survey Urd: 1.42A-4 I 5.5 Statistical Summary Table 4"

Statistical Parameter Pipe Total Number of Survey Measurements 48 Number of Measurements >MDC 47 I ~~

Number of Measurements Above 50% of DCGL

~~ ~

I 0 Number of Measurements Above DCGL 0 Mean 0.0374 Median 10.0330 Standard Deviation I 0.0209 Maximum 10.0931 Minimum 10.0083 Documentation of evaluations pertaining to compliance with the unrestricted use limit of 25 m r e d y 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 1.42A-4 to be less than 1 mredyr. The dose contribution is estimated to be 0.037 mredyr based on the average of the actual gross counts.

A-p--- -~

Attachment 1 - BSI EPBP Survey Report Attachment 2 - Pipe Interior Radiological Survey Form Attachment 3 - DQA Worksheet Attachment 4 -Disc containing RR for EP 1.42A-4 & Spreadsheet

SECTION 7 ATTACHMENT 1 3 PAGE(S)

liiw.-

iLI BSI EP/BP SURVEY REPORT Pipe ID EP 4.4-4 Survey Locatlon Quad C I-27 Trench I Suwey Date 2350-1 # 203488 Detector-SkdY 1MGl LVS-lI101 1- Pipe Size DCGL 2.41EM5 P(P-Detector Efficiency kcorpon*dbY Ef===Y m-1 I 0.00052 973

1. p.*rrksffpaMbY un5 4.7 Field BKG 1-1 21.7 I ~outinesurvey I X Field MDCR-I 19 Nominal MDC (dpnmnu) 1,557 I

irvey Measurement Results Total Number of Survey Measurements 48 Number of Measurements N D C 47 Number of Measurements Above 50% DCGL 0 Number of Measurements Above DCGL 0 Mean 0.0374 Median 0.0330 Standard Deviation 0.0209 Maximum 0.0931 Minimum I 0.0083 ROSENHAGEN Survey Technician(s)

TBD O6-004 Piping Group 1 SR-13 RadionuclideDistribution Sample EP 3-9 MeasuredN u d i Ca-60 Area Factor/EMC Used No Pasflail FSS Pass MREMNRContribution <l COMMENTS:

ACTIVITY VALUES NOT BACKGROUNDCORRECTED RP Engineer I Date P -B-07

EP 1.42A-4 4" Pipe TBD 06-004 Group 1

- -

'1" c660 actlvity Cs-I 37 activity Eu-IS2 advlty Nb-Q4activity Ag-108m activity Unity gcpm (dpm1100cm2) (dpmll OOcm2) (dpm1100cm2) (dpmllOOcm2)

-i a -

_-__

14 32 27

~ --

61,538 51,923 1,977 2,767 6,325 5,337 78

.- -

110 251 212 -

1,875 2,625 6,000 5,063 a

-+GE j 1,346 58 81 185 156 14 19 44 37 0.01L 0.01i 0.031 0.03; 2e - 28 53,846 5,535 219 5,250 1 1.396 162 39 0.03:

25 29 55.769 5,732 227 5,438 167 40- 0.03 2e 5,139 204 - 4,875 150 36 0.03' 32 63.462 6,523 259 - 6,188 190 45 0.031 24 _____ 4.744 188 4,500 138 33 0.02I

_-

2 28 53,846 5,535 219 5,250 162 39 0.03:

__ - -

3c 30 57.692 5.930 235 5,625 173 41 0.03f I

21

-zJ--2m 40.385 3,558 4,151 141 165 3,375 3,938 104 121 25 29 0.02' 0.02!

-

3; - 32 61,538 6,325 251 - 6 ,000 185 44 0.03(

7E 79 151,923 ___I_

15,616 619 14,813 456 109 0.09:

__--

7( ~-

70 134,615 13,837 _ _ _ ~ 548 ____- 13,126 404 96 0.08:

45 49 94,231 9,686 384

__ 9,188 2,443 283 67 0.051 6 66 126,923 13,046 517 12,376 38 1 91 0.07l

___ 5E 56 107,692 11,069 439 10,501 323 77 0.oa 4: 43 82.692 8,500 337 8,063 248 59 0.05' 4t 92,308 9,488 376 9.000 277 66 0.05; 4i 90,385 9,290 368 8,813 ~ 2,343 271 65 0.05!

___-

4: 82,692 8,500 337 - 8,063 i 2,143 ~.

248 59 0.05' l! 28.846 _ _ _ - _ _ 2,965 ______ 118 2,813 i 748 87 21 0.011

__--

li 3,360 133 3,188 i 847 98 23 0.02(

41 48 92.308 9,488 376 - 9,000 i 2,393 277 66 0.05 5; 11,267 447 _- 10,688 329 79 0.06' 9 10,674 ~ I 423

_ _

10,126 - 31 1 74 0.W

___ 41 9,488 376 9,000 2,393 277 6 0.05' 4! 94,231 9,686 384 - 9,188 283 67 0.051

- 21 53,846 5,535 219 5.250 162 - 0.03:

1o f 2

EP 1.42A-4 4" Pipe TBD 06-004 Group 1 7

• I I Cs-137 activity Eu-162 activity E"-& activity Nb-91 activity Ag-1O8m activity Unity (dpmll OOcrn2) (dpm1100cm2) (dpnirlOOem2) (dpm1100cm2) (dpm1100cm2) 125 3,000 92 22

-0.01s 102 _____ 2,438

_ 75- 18 0.01E 102 2,438 75 18 0.01:

7 55 1,313 40 10 O.OOE 78 58 14 0.012

-37)-;

38 16 1c 23,077 30,769 2,372 3,163 94 125

-

___-___

1,875 2,250 3,000 69 92 17 22 0.014 0.015 32,692 3,360 133 - 3,188 98 23 0.02c 17,308 1,779 71 - 1,688- 52 12 0.011 41 15 1f 28,846 2,965 118 2,813 87 21 0.01E

__-

42 16 1 30,769 3,163 125 3,000 92 22 0.015 43 25 2f 48,077 4,942

_____ 196 4,688 144 34 0.022 44 35 3i 67,308 6,918 274 6,563 I 1,745 202 48 0.041 45 28 2f 53,846 5,535 _ _ _ _ - 219 5,250 162 39 0.03:

46 46 4 88,462 9,093 360 8,625 , 2,293 , 265 63 0.09 47 49 42 94,231 9,686 384 9,188 i 2,443 283 67 0.05t i

48 27 2i 51.923 5.337 212 5,063 1,346 156 37

-0.03; s!=

I I

A- MEAN 0.03i

--+---

MEDIAN 0.03:

~.

STD DEV 0.02' MAX-_ 0.09:

MIN -0.00l 2of2

SECTION 7 ATTACHMENT 2 4 PAGE(S)

I I BSVLVSPipeCrawler-002 Revision 4 Pipe Interior Radiological Survey Form Date: 3' /'ob Time: 08-27 5-c' Pipe ID#: /. Y d - 4 PipeDiameter: L/ Access Point Area: / 5 f r r p J s 5 s ~ c Building: RX Elevation: z-51;3utb c System: x';'~ ,+,+mC L/

• i uJAs7-5 ,+;

Type of Survey Investigation Characterization Final Survey Other / p n ~ EJ; r

Gross C060 I/ cs-Detector ID#/ Sled ID# &?/@P/ /fib/ LJPI 1 / o f Detector Cal Date: zl9- lSE.5 -o Detector Cal Due Date: u- D t - --oi Instrument: A39 I Instrument ID #: 2-35/n7 Instrument Cal Date: /7 - d d d- 0 Instrument Cal Due Date: / 7 dov- o b From the Daily Pipe Survey Detector Control Form for the Selected Detector Background Value 3/#? cpm MDCRStatlC MDC,,,, 1557 14 cpm Efficiency Factor for Pipe Diameter dPd

.

8 b 0 05 100 cm2 (from detector efficiency determination)

Is the MDCstabcacceptable? @ No (ifno, adjust sample count time and recalculate MDCR,,,,)

Technician Signature Pipe Interior Radiological Survey Package Page 1 of 2 REFERENCECOPY Attachment 3, Page 1

BSI/LVSPipeCrawler-O02 Revision 4 Pipe Interior Radiological Survey Form (Continuation Form)

Date: 3+ b b qJwdd c Pipe ID#: 1 ./ 3 Pipe Diameter: /(

Access Point Area: /SW Lip v ~ p ~ E&. &c Building: 2 K Elevation: - 2 5 ?l/ptD c Systern: 7 ? r > # d2-23b IC.

Attachment 3, Page 2

BSELVSPipeCrawler-002 Revision 4 Pipe Interior Radiological Survey Form (Continuation Form)

Building : Elevation: -25 ,?UP%& c S ystern :

Package Page 2:f

\

REFERENCE COPY Attachmen{;, Page 2

SECTION 7 ATTACHMENT 3 I PAGE(S)

DQA Check Sheet Design # I EP 1.42A-4 I Revision# I Original I Answers to the following questions should be fully documented in the Survey Unit Yes No N,A Release Record I.

~~

Have surveys been performed in accordance with survey instructions in the Survey Design?

~

1 x 1 I

2. Is the instrumentationMDC for structure static measurements below the DCGLw for Class 1 and 2 X

survey units, or below 0.5 DCGLw for Class 3 survey units?

3. Is the instrumentation MDC for embeddedhuried piping static measurements below the DCGLw ? X

0. Was the instrumentation MDC for structure scan measurements, soil scan measurements, and embeddedhuried piping scan measurements below the DCGLW,or, if not, was the need for additional X static measurementsor 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. Wem the survey methods used to colled data proper for the types of radiation involved and for the media being surveyed?

3. Were "Special Methods" for data collection properly applied for the survey unit under review? 1 x 1 I

3. Is the data set comprised of qualified measurement results collected in accordancewith t h e r v e y X

design, which accurately reflects the radiological status of the facility?

Graphical Data Review

1. Has a posting plot been created? I I I x

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

3. Have other graphical data tools been created to assist in analyzing the data? I I I x Data Analysls I. Are all sample measurementsbelow the DCGLW(Class 1 8 2), or 0.5 DCGLw (Class 3)?

~ ~~ ~ ~~

?. Is the mean of the sample data DCGLW? X

3. If elevated areas have been identified by scans and/or sampling, is the average activity in each X

elevated area DCGLEMC (Class l), < DCGLW(Class 2),or <0.5 DCGLw (Class 3)?

1. Is the result of the Elevated Measurements Test 1.O? X

~ ~

5. Is the result of the statistical test (S+ for Sign Test or W, for WRS Test) 1.the critical value? X FSSCharaderization Engineer (printlsign)

• p FSSl Characterization Manager (print/sign)

Form cs-0912 Rev 0 Page 1 of 1

SECTION 7 ATTACHMENT 4 1 DISC

Survey Unit Release Record Design # EP-Rx155 1 Revision# 1 Original I Page 1 of 3 Survey Unit #(s) Rx155

1) Embedded Pipe (EP) Survey Unit Rxl55 meets the definition of embedded pipe for Plum Brook Reactor Facility (PBRF).

2) EP RX155 is a Class 1, Group 2 s w e y unit as per the PBRF Final Status Survey Plan (FSSP) and Technical Basis Document (TBD)-06-004.

3) Surveys in EP Rx155 were performed using a scintillation detector optimized to measure gamma energies representative of CO-60.Sample #EP 2-1 from Survey Request (SR)-l3 was referenced for this decision.

4) Survey Instructions for this survey unit are incorporated into and performed in accordance with (IAW) the Babcock Services Incorporated (BSI)/LVS-002, Work Execution Package (WEP)05-006. Survey instructions described in this Description document constitute Special Methods and the survey design used in the acquisition of survey measurements.

5) Instrument efficiency determinations are developed in accordance with the BSIZVS-002, WEP 05-006, these determinations are appropriate for the types of radiation involved and the media being surveyed.

_-

I

FSS Design # EP Rx155 Revision # Original Page 2 of 3 1.0 HistoryiDescription 1.I EP Rxl55 is a sump trench vent that is located in the pump room on the -

25 foot of the Reactor Building. The purpose of the system is to ventilate the sump trench. This system involves approximately 7 liner feet of drain system piping.

I .2 EP Rx155 consists of 7 linear feet () of 10 inch () Inside Diameter (ID) piping starting in the -25 foot elevation trench and running to Quad B. The total piping for EP Rx155 is 7.

2.0 Survey Design Information 2.1 EP Rx155 was surveyed IAW Procedure #BSULVS-002.

2.2 IOP?of the 10 ID pipe was accessible for survey. The accessible 10 ID pipe was surveyed by static measurement at one foot increments, for a total of 7 survey measurements.

2.3 Surface area for the 10 ID piping is 2,432 cm2for each foot of piping, corresponding to a total 10 ID piping surface area of 17,024 cm2(1.7 m2) for the entire length of (7) of IO piping..

3.0 Survey Unit Measurement LocationsData 3.1 Pipe interior radiological survey forms are provided in Attachment 2 of this release record.

4.0 Survey Unit Investigationshtesults 4.1 None 5.0 Data Assessment Results 5.1 Data assessment results are provided in the EPBuried Pipe (BP) Survey Report provided in Attachment 1.

5.2 43ukkh&

Level (DCGL) for radionuclide specific EP that corresponds to the 1 mredyr dose goal established in Table 3-3 of the FSSP.

5.3 When implementing the Unity Rule, provided in Section 3.6.3 of the FSSP, and applying the Cesium-137/Cobalt-60 ratios, provided in TBD-06-004, the survey unit that is constituted by EP Rx155 passes FSS.

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

FSS Design # EP Rx155 Revision # Original Page 3 of 3 5.5 Statistical Summary Table I 10 I Statistical Parameter Total Number of Survey Measurements 7 Number of Measurements >MDC 0 Number of MeasurementsAbove 50% of DCGL 0 Number of MeasurementsAbove DCGL 0 Mean 0.012 Median 0.012 Standard Deviation 0.002 Maximum 0.015 Minimum 0.010 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 Rx155 to be less than 1 mredyr. The dose contribution is estimated to be less than 0.012 mrerdyr based on the average of the actual gross counts measured.

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 Rxl55 & Spreadsheet

I SECTION 7 ATTACHMENT 1 2 PAGE(S)

I I 8SI EP/BP SURVEY REPORT Pipe ID Rx155 Survey Location -25 RX Survey Date 10-Jan-06 2350-1 # B566A-108 Survey Time 1030 Detector-Sled # BI CRON/G3 Pipe Size 10" Detector Efficiency 0.003 Plpe Area Incorporabed by Detsctor EWtciency (in cm2) 2432 I

~~ ~ ~~

I DCGL (dpmM0OcrnZ) 240,800 Field BKG(crm) 369.7 Routine Survev X Field MDCR 1-1 I 69.3 QA Survey I I I Norninal~~~(dW-2) 1 11,223 Survey Measurement Results Total Number of Survey Measurements I 7 Number of Measurements >MDC 0 Number of Measurements Above 50% DCGL 0 Number of Measurements Above DCGL 0

~- ~

Mean

~~

I 0.012 Median 0.012 Standard Deviation 0.002

~~ ~

Maximum I 0.015 Minimum 0.010 2OMMENTS: Activity values are not background corrected.

RP Engineer I Date L 07 6/6/2007

EP Rx155 TBD 06-004 Group 2

• c.

C f

2 a gcpm Co-60 activity (total dpm)

I i

Cs-137 activity (dpmllWcm2)

Eu-152actlvity (dpm1100cm2)

Eu-154 actMty (dpn\nOOcm2)

Nb-S4 activity (dpm/lOOcm2)

I Agl08m activity (dpmfl00cmZ)

Unity Q)

(P s _ ~ _ _ __

1 247 247 82,333 ~ 3,385 98 0.015 2 231 231 77,000 i

___+A 3166 92- 0.0%

3 188 188 62,667 I 2,577

-. 75 00%

4 182 182 60,667 ' 2,495 72 0.011 5 174 174 58,000 2,385 69 0.01C

-

6 7

206 196 206 196 68,667 65,333 2,823 17t_: 16 ~

82 78 0.01;

___

0.01;

_Ti- L i

--t--- i I I 1of1

SECTION 7 ATTACHMENT 2 2 PAGE(S)

I Pipe Interior Radiological Survey Form Date: /. / P - U b Time: /636 Building :  ?!rkT* Elevation / '

s 2 Access Point - 32 A; S++

System: b T - c + ? M P i p e Diameter: &/Area: Pipe ID Zf - />-A '

Type of Survey Investigation Characterization Final Survey # Other ,/

Sled Size L' inch Detector: B f k # d / cp 3 Detector ID #: 3 5 b ( d k - / b d Cal Date: 17 - rood 'dei- Cal Due Date: /'7- N o d - 0 (&.

Instrument: 3 3 s --I Instrument ID #: 2Q3~mY Cal Date: jq- h ) D d - 05- Cal Due Date: /'7-+JtI: -uc From the Daily Pipe Survey Detector Control Form for the Selected Detector Background Value 2k 7 7 cpm MDCRstatic b 7-3 CPm Efficiency Factor for Pipe (3c on3 (taken from detector m e tstatlc er /) 2 2 3 dpm/100cm2 IS the MDCSQtic (ifno, adjust sample count time and recalculate MDCR,,,ic) c&%&?fitli!e?

0 REFERENCECOPY Attachment 3, Page 1

REFERENCECOPY I-I

SECTION 7 ATTACHMENT 3 I PAGE(S)

I I Design # EP Rx155 Revision # Original Survey Unit # EP Rx155 Answers to the following questions should be fully documented in the Survey Unit Release Record Yes No NIA

1. Have surveys been performed in accordance with survey instructions in the Survey Design? X

~~

2. Is the instrumentationMDC 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 instrumentationMDC for embeddedlburiedpiping static measurements below the DCGLw ?

I X Ix

4. Was the instrumentation MDC for structure scan measurements, soil scan measurements, and embeddedlburiedpiping 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 instrumentationMDC for volumetric measurements and smear analysis < 10% DCGLW?

~~~ ~~ ~

I I I X

6. Were the MDCs and assumptions used to develop them appropriatefor 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 X

media being surveyed?

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

9. Is the data set comprised of qualified measurement results collected in accordance with the survey X

design, which accurately reflects the radiological status of the facility?

GraDhical Data Review

~~

1. Has a posting plot been created? X

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

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

~- ~

Data Analysis

~- - - ___ ___ ~- -

1. Are all sample measurements below the DCGLw (Class 1 & 2). or 0.5 DCGLw (Class 3)? X

2. Is the mean of the sample data DCGLw? X

3. If elevated areas have been identified by scans andlor sampling, is the average activity in each X

elevated area < DCGLEMC(Class l), < DCGLw (Class Z),or <0.5 DCGLw (Class 3)?

4. Is the result of the Elevated Measurements Test 1.O? X

~~~~~ ~

5. Is the result of the statistical test (S+ for Sign Test or W , for WRS Test) 2 the critical value? X Form CS-09D Rev 0 Page 1 of 1

SECTION 7 ATTACHMENT 4 1 DISC

43 COPY Design ## EP-Rx 113D Revision ## Original Page 1 of 3 Survey Unit #(s)

2) EP Rx 113D is a Class 1, Group 2 survey unit as per the PBRF Final Status Survey Plan (FSSP) and Technical Basis Document (TBD)-06-004.

3) Surveys in EP Rx I 13D were performed using a scintillation detector optimized to measure gamma energies representative of Co-60. Sample #EP 2-1 fiom Survey Request (SR)-13 was referenced for this decision.

4) Survey Instructions for this survey unit are incorporated into and performed in accordance with (IAW) the Babcock Services Incorporated (BSI)/LVS-002, Work Execution Package (WEP)05-006. Survey instructions described in this Description document constitute Special Methods and the survey design used in the acquisition of survey measurements.

5 ) Instrument efficiency determinations are developed in accordance with the BSVLVS-002, WEP 05-006, these determinations are appropriate for the types of radiation involved and the media being surveyed.

FSS Design ## EP Rx 113D Revision # Original Page 2 of 3 1.o HistoryDescription 1.1 The subject pipe system is the 0.75 Quad B system line.

1.2 EP Rx 113D is approximately 17 feet in length.

2.0 Survey Design Information 2.1 EP Rx 113D was surveyed IAW Procedure #BSI/LVS-002.

2.2 100% of the 0.75 ID pipe was accessible for survey. The accessible 0.75 ID pipe was surveyed by static measurement at one foot increments, for a total of 17 survey measurements.

2.3 Surface area for the 0.75 ID piping is 182 cm2for each foot of pi ing, P

corresponding to a total 0.75 ID piping surface area of 3,101 cm (0.3 m2) for the entire length of (17) of 0.75 piping..

3.0 Survey Unit Measurement Locations/Data 3.1 Pipe interior radiological survey forms are provided in Attachment 2 of this release record.

4.0 Survey Unit InvestigationsResults 4.1 None 5.0 Data Assessment Results 5.1 Data assessment results are provided in the EP/Buried Pipe (BP) Survey Report provided in Attachment 1.

5.2 All measurement results are less than the Derived Concentration Guideline Level (DCGL) for radionuclide specific EP that corresponds to the 1

&yr dose goal established in Table 3-3 of the FSSP.

5.3 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 113D passes FSS.

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

I I FSS Design # EP Rx 113D Revision # Original Page 3 of 3 5.5 Statistical Summary Table I 0.75 Statistical Parameter 1 Pipe Total Number of Survey Measurements 17 Number of Measurements >MDC 12 Number of Measurements Above 50% of DCGL 0 Number of Measurements Above DCGL 0 Mean Io.0464 Median 10.0483 Standard Deviation 0.0138 Maximum 0.0685 Minimum 0.0242 Documentation of evaluations pertaining to compliance with the unrestricted use limit of 25 m e d y r and dose contributions fiom Embedded Pipe and radionuclides contributing 10% in aggregate of the total dose for both structural scenarios and soils.

6.1 A review of the survey results has shown that the dose contribution for EP Rx 113D to be less than 1 mredyr. The dose contribution is estimated to be 0.046 rnredyr based on the average of the actual gross counts.

______ -- _ _

-

-

Attachment 1 - BSI EPBP Survey Report Attachment 2 - Pipe Interior Radiological Survey Form Attachment 3 - DQA Worksheet Attachment 4 -Disc containing RR for EP Rx 1.13D & Spreadsheet

SECTION 7 ATTACRNIENT 1 Z PAGE(S)

BSI EPlBP SURVEY REPORT Pipe ID SurveyDate Survey Time 1 1

; ;20 Rx 113D

,

Survey Location 2350-I#

DetectorSled#

-27' Trench Loop Drair 189094 0047-no sled Pipe Size 0.75" 11 Detector Efficiency I 0.00059 DCGL 14mno~a2) 2.41E+05 P(p-kapon(.d w- Emancr 182 Fkld BKG iSp.1 18.3 Routine Survey I X II Field MDCR 1-1 I 17.8 Total Number of Survey Measurements 17 Number of Measurements >MDC 12 Number of MeasurementsAbove 50% DCGL 0 Number of Measurements Above DCGL 0 Mean 0.0464 Median 0.0483 Standard Deviation 0.0138 Maximum I 0.0685 Minimum 0.0242 STOCK Survey Technician(s)

Survey Unit Classification 1 1 TED 06-004Piping Group 2 SR-13 Radionuclide Distribution Sample EP 2-1 Measured N u d i e I c m Area FactodEMC Used No PasslFail FSS Pass M R E W R Contribution <f COMMENTS:

ACTIMTY VALUES NOT BACKGROUNDCORRECTED RP Engineer IDate

&e 7-/7-07

EP Rx 113D 0.75" Pipe TBD 06-004 Group 2

-

Co60 activity COS0 actlvity Cs-137 activlty Ag-lO8m activity ncpm (total dpm) (dpm1100cm2) (dpm1lOOcm2) (dpmll OOcm2)

Unity 13,559

_- 62 44 4

~- 214

- ._

-0.03;

- ~-

13,559 ~- - ___ ____ 62 44 4 214 0.03;

-. - 27,119 14,867

._ 7,709

-- -_ 123 i 87 7 428 0.06

-.

11.864 6,504 3,373

-- ___ 54 38 3 -..

187 0.021 10;169 5,575 __

2,891 46 33 3 160 0.021 13

-

22.034 12,079 6,264 100 71 6 348 0.05; 13 12,079 6,264 .__ 100 71 6 348 0.05; 15

- .~ 13,938 7,227 _ _ 116 I 82 7 401 0.06(

12 11,150 5,782 -_ 92 I 65 5 - 32-1. 0.041 12

-

- 11,150 5,782 92 65 5 321 0.041 12 11.150

, - 5.782 92 65 5 321 0.041

~.

15 25,424 13,938 7,227 401 0.06(

-~ 11 18,644 10.221 5.300 - 294 0.W

_-___ 12 - -___ 20,339 5,782 -- 92 I 65 5 __ 321 0.04I

~-

17 _____ 28,814 - 8,191 131 I I 92 8 - 455 0.061 6 10,169 5,575 46 I  ! 33 1 3 160 0.024 100 I 12 22.034 ____-12,079 6,264 6 dEAN 348

-0.05; 0.04t T lllEDlAN 0.04 3 D DEV -O.Olr

._

dAx 0.061 dlN -0.024 1of1

SECTION 7 ATTACHMENT 2 3 PAGE(S)

-

I I BSYLVSPipeCrawler-002 Revision 4 Pipe Interior Radiological Survey Form Date: T/Z,/OG Time: 1025 Pipe I D X :

Building:

& I t 9 Pipe Diameter:

Elevation:

.7d

- 2 7I System:

-

Access Point Area: 2 7 ~ r E z~ J/+

I L W ? OR#/n/

C Type of Survey Investigation Characterization Final Survey )( Other f Gross Co60 4 cs Detector ID# / Sled ID# e//A- % y m 4 7 I No SLED Detector Cal Date: 2 [I 2 d / IO g Detector Cal Due Date: 2/za/,7

Instrument: 2 3 co- 1 Instrument ID #: g q D9 Instrument Cal Date: 31) >/a t

Instrument Cal Due Date: 3/r t

r&7 From the Daily Pipe Survey Detector Control Form for the Selected Detector Background Value r.3 cpm MDCRstatlc 17, 8 CPm EfficiencyFactor for Pipe Diameter 0.0006 (from detector efficiency determination) mcstahc 763 I dpm 100 cm2 Is-the-MDCskhcacceptable? @ No (if n q adj.st-.saqk aunt tmeand.redadattC Ccments: -L ~ J n-I 5Q.T UI?+ Efz- / L L W P L - 1 ~ ~

Technician Signature

I I BSULVSPipeCrawler-002 Revision 4 Pipe Interior Radiological Survey Form (Continuation Form)

Pipe ID#: Pipe Diameter: 8 7s" Access Point Area:

Building: Elevation: -21 S ystern:

n REFERENCECOPY Package Page 3 of 3 Attachment 3, Page 2

I 11 I

L I

SECTION 7 ATTACHMENT 3 I PAGE(S)

~~ -

DQA Check Sheet Design # T EP Rx 113D

_ _

1 Revision # 1

~

Original 1 Survey Unit # EP Rx 113D Answers to the following questions should be fully documented in the Survey Unit Yes No NIA Release Record

1. Have surveys been performed in accordance with survey instructions in the Survey Design? X

2. Is the instrumentation MDC for structure static measurements below the DCGLw for Class 1 and 2 X

survey units, or below 0.5 DCGLw for Class 3 survey units?

~~

3. Is the instrumentation MDC for 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?

5. Was the instrumentation MDC for volumetric measurements and smear analysisz. 10% DCGLw ?

6. Were the MDCs and assumptions used to develop them appropriate for the instruments and techniques used to perform the survey3

7. Were the survey methods used to collect data proper for the types of radiation involved and for the X

media being surveyed?

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

9. Is the data set comprised of qualified measurement results collected in accordance with the survey X design, which accurately reflects the radiological status of the facility?

1.

~

Has _

_

a posting plot been created?

~~ ~

I I l x

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

3. Have other graphical data tools been created to assist in analyzing the data? I I I x

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 c DCGLw? X

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

4. Is the result of the Elevated Measurements Test < 1.O? X

~~

5. Is the resuli of the statistical test (S+ for Sign Test or Wr for WRS Test) 2 the critical value? X Form cs-0912 Rev 0 Page 1 of 1

SECTION 7 ATTACHMENT 4 1 DISC

I 0 copy Design # EP- 1.64 1-8 Revision ## Original Page 1 of 3 Survey Unit #(s) 1.641-8

1) Embedded Pipe (EP) Survey Unit 1.641-8 meets the definition of embedded pipe for Plum Brook Reactor Facility (PBRF).

2) EP 1.641-8 is a Class 1, Group 1 survey unit as per the PBRF Final Status Survey Plan (FSSP) and Technical Basis Document (TBD)-06-004.

3) Surveys in EP 1.641-8 were performed using a scintillation detector optimized to measure gamma energies representative of CO-60. Sample #EP 3-8 from Survey Request (SR)-13 was referenced for this decision.

4) Survey Instructions for this survey unit are incorporated into and performed in accordance with (IAW) the Babcock Services Incorporated (BSI)/LVS-002, Work Execution Package (WEP)05-006. Survey instructions described in this Description document constitute Special Methods and the survey design used in the acquisition of survey measurements.

5 ) Instrument efficiency determinations are developed in accordance with the BSVLVS-002, WEP 05-006, these determinations are appropriate for the types of radiation involved and the media being surveyed.

r I

FSS Design # EP 1.641-8 Revision # Original Page 2 of 3 1.o HistoryDescription 1.1 The subject pipe system is the header fiom the 4 inch overflow to Canals H & G to the -25A of Rx Building in Pump Room #22. The h c t i o n of this pipe was to convey water fiom the 4 inch overflow piping leading to canals H and G to the HD sump in Pump Room #22, where the pipe is currently breached. Survey Unit 1.641-8 represents all the 8diameter piping associated with pipe ID 1541.

1.2 EP 1.641-8 consists of 8 diameter piping that is approximately 5 1 feet in length.

2.0 Survey Design Information 2.1 EP 1.641-8 was surveyed IAW Procedure #BSVLVS-002.

2.2 100% of the 8 ID pipe was accessible for survey. The accessible 8 ID pipe was surveyed by static measurement at one foot increments, for a total of 5 1 survey measurements.

2.3 Surface area for the 8 ID piping is 1,946 cm2for each foot of piping, corresponding to a total 8 ID piping surface area of 99,234 cm2(9.9 m2) for the entire length of (approximately 5 1) of 8 piping..

3.0 Survey Unit Measurement Locations/Data 3.1 Pipe interior radiological survey forms are provided in Attachment 2 of this release record.

4.0 Survey Unit InvestigationsResults 4.1 None 5.0 Data Assessment Results 5.1 Data assessment results are provided in the EP/Buried Pipe (BP) Survey Report provided in Attachment 1. ____.__ ~ __

5.2 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.

5.3 When implementing the Unity Rule, provided in Section 3.6.3 of the FSSP, and applying the Nuclide Fraction (NF), provided in TBD-06-004, the survey unit that is constituted by EP 1.641-8 passes FSS.

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

-

FSS Design # EP 1.641 -8 Survey Unit: 1.641-8 Revision I# Original I Page 3 of 3 5.5 Statistical Summary Table Statistical Parameter Total Number of Survey Measurements 51 Number of Measurements >MDC 25 Number of Measurements Above 50% of DCGL 0 Number of Measurements Above DCGL 0 Mean 0.0171 Median 0.0161 Standard Deviation 0.0085 Maximum 0.0628 Minimum 0.0058 Documentation of evaluations pertaining to compliance with the unrestricted use limit of 25 mdyr and dose contributions from Embedded Pipe and radionuclides contributing 10% in aggregate of the total dose for both structural scenarios and soils.

6.1 A review of the survey results has shown that the dose contribution for EP 1.641-8 to be less than 1 m r d y r . The dose contribution is estimated to be 0.017 rnredyr based on the average of the acW gross counts measured. - ~- - ~

Attachments Attachment 1 - BSI EP/BP Survey Report Attachment 2 - Pipe Interior Radiological Survey Form Attachment 3 - DQA Worksheet Attachment 4 - SURR EP 1.641-8 & Spreadsbeet Disc

SECTION 7 ATTACHMENT 1 3 PAGE(S)

BSI EPlBP SURVEY REPORT Pipe ID  ! 1.641-8 11 Survey Location 1 I

Canal GBH overflow Survey Date 18-Jul-07 2350-1 # 189094

-

I SuweyTime 1 13:s 11 I 1MGI LVS-Ill07 Survey Technidan(s)

Survey Unit Classifmtion I 1 TBD O6-004 Piping

. - Group 1 SR-13 Radionudide DistributionSample EP 3-8

___- - Measured Nuclide ~-

Area Fador/EMC Used No PasslFail FSS Pass MREMNR Contribution 4 RP Engineer IDate I 8Ll u 7-2E-07 7/25/2007

EP 1.641-8 8" Pipe TBD 06-004 Group 1 Cs-137 activity Eu-152 activrty Nb-94 activity (dpmllOOcmZ) (dpmllOOcmZ) (dpml100cmZ) 555 64

__-

~-

136 97 __

3.250 27322 1864 1 617 100 71 126 3,018 I 802 93 165 3,947 121 184 4,411 1,173 136 107 2,554 79 145 3,482 926 107 155 3,714 -/9871864 114 100 136 3,250 126 3,018 93 116 2,786 86 78 1,857 57 78 1.857 57 88 864 1oa I

=p 68 1,625 432 5c 97 I 2.322 71

-- 71 l -

555 64 107 1o f 2

EP 1.641-8 8" Pipe TBD 06-004 Group 1 11

~~

co80 activity Cs-137 activity Eu-152 activity Eu-1 activity Nb-94 activity AglOBm activity ncpm Unity (dpmll00cm2) (dpmllOOcm2) (dpm1100cm2) 00cm2) (dpm1100cmZ) (dpm1100cm2) 32 7

7 33,333

-

O.Ol(

1c 47,619 0.011 14 57,143 0.011 IC 47,619 0.01!

1: 61,905 0.01!

E 38,095 0.01:

1 f 23,810 0.00 33,333 0.01' 1

23,810 0.00 57,143 0.01

--1; l! 90,476 0.02 14 66,667 1: 80,952

.

-

4. 4: 204,762 1 l! 71,425 0.02 L

___- 1' 66,667 1 1' 61,905 0.01 57,142 0.01 52,381 0.01 t----t- MEAN MEDIAN 1

STD DEV

__ _- 1 MAX .___

MIN 2of2

SECTION 7 ATTACHMENT 2 4 PAGE(S)

I BSYLVSPipeCrawler-002 Revision 5 Pipe Interior Radiological Survey Form Date: 7 - 1 9 - 0 7 Time: 139.4 Pipe ID#: \ b4 \ Pipe Diameter: s It Access Point Area: -dl &

Building: h% a\&- U Elevation: 4 System: k\6aH W%&

Type of Survey Investigation Characterization Finalsurvey >( Other d Gross Co60 \I cs

/kWI Detector CalDate:

Instrument:

Detector ID# / Sled ID#

13Sd I Inhi

- 07

-

1 107 Detector Cal Due Date:

Instnunent ID #:

1 d m y d 1 u jj Instrument Cal Date: 1 - f) - 07 Instrument Cal Due Date: \@\\ 0 5-From the Daily Pipe Survey Detector Control Form for the Selected Detector Background Value 3 L cpm MDCRStiLtiC 9,5 cpm Efficiency Factor for Pipe Diameter 010 Dz1 (from detector efficiency determination)

PvlDCstatic 2 dpd LOP cm2 Is the MDCstabcacceptable? No (if no, adjust sample count time and recalculate M D a t i c )

Comments: Q.4 sV\lmf*du Em-% 1Ih34 c,*LL /

Technician Signature 3 A Pipe Interior Radiological Survey Package Page 1 of 2 REFERENCECOPY Attachment 3, Page 1

I BSVLVSPipeCrawler-002 Revision 5 Pipe Interior Radiological Survey Form (Continuation Form)

Pi;eaz#:

Building:

$2* Pipe Diameter:

Elevation:

Access Point Area:

System: L\

TM GCN Q~

O~LU Package Page zof*

REFERENCECOPY Attachment 3, Page 2

I BSULVSPipeCrawler-002 Revision 5 Pipe Interior Radiological Survey Form (Continuation Form)

I Position Feet into Pipe Count Time Gross Counts Gross Net dpm/100cm2 1

1. fiom Opening (min) cpm cpm 4b uc I 97 y3 n I& J1 47 9 7 1s 15 I I

4Y 4 % (4 lq

-47 u q \? \3 S O S-) \z la.

s\ 4 \ 11 I\ lv I

\

Package Page 5 of &

REFERENCE COPY Attachment 3, Page 2

0 REFERENCE COPY

SECTION 7 ATTACHMENT 3 1 PAGE(S)

_-

I SECTION 7 ATTACHMENT 4 1 DISC

Survey Unit Release Record Design # EP-1.641-4 1 Revision # I Original I Page 1 of 3 Survey Unit #(s) 1.641-4

1) Embedded Pipe (EP) Survey Unit 1.6414 meets the definition of embedded pipe for Plum Brook Reactor Facility (PBRF).

2) EP 1.641-4 is a Class 1, Group 1 survey unit as per the PBRF Final Status Survey Plan (FSSP) and Technical Basis Document (TBD)-06-004.

3) Surveys in EP 1.641-4 were performed using a scintillation detector optimized to measure gamma energies representative of CO-60. Sample #EP 3-8 from Survey Request (SR)-13 was referenced for this decision.

4) Survey Instructions for this survey unit are incorporated into and performed in accordance with (IAW) the Babcock Services Incorporated (BSI)/LVS-002, Work Execution Package (WEP)05-006. Survey instructions described in this Description document constitute Special Methods and the survey design used in the acquisition of survey measurements.

5 ) Instrument efficiency determinations are developed in accordance with the BSVLVS-002, WEP 05-006, these determinations are appropriate for the types of radiation involved and the media being surveyed.

FSS Design # EP 1.641-4 Revision ## Original Page 2 of 3 1.0 Historyfiscription 1,1 The subject pipe section is the 4 inch overflow header to Canals F, G & H.

The function of this pipe was to convey water fiom the 4 inch risers in each of the canals to the 8 inch header leading to the HD sump in Pump Room #22 on the Rx -25ft,where the pipe is currently breached. Survey Unit 1.641-4 represents all the 4"diameter piping associated with pipe ID 1.641.

1.2 EP 1,641-4 consists of 4" diameter piping that is approximately 34 feet in length.

2.0 Survey Design Information 2.1 EP 1.641-4 was surveyed IAW Procedure #BSVLVS-002.

2.2 100% of the 4" ID pipe was accessible for survey. The accessible 4" ID pipe was surveyed by static measurement at one foot increments, for a total of 34 survey measurements.

2.3 Surface area for the 4" ID piping is 973 cm2for each foot of piping, corresponding to a total 4" ID piping surface area of 33,078 cm2(3.3 r n')

for the entire length of (approximately 34') of 4" piping..

3.0 Survey Unit Measurement Locations/Data 3.1 Pipe interior radiological survey forms are provided in Attachment 2 of this release record.

4.0 Survey Unit InvestigationsAXesults 4.1 None 5.0 Data Assessment Results 5.1 Data assessment results are provided in the EP/Buried Pipe (BP) Survey Report provided in Attachment 1. - ~ _ _ -

5.2 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.

5.3 When implementing the Unity Rule, provided in Section 3.6.3 of the FSSP, and applying the Nuclide Fraction (NF), provided in TBD-06-004, the survey unit that is constituted by EP 1.641-4 passes FSS.

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

FSS Design # EP 1.641-4 Revision # 0rigm.d Page 3 of 3 5.5 Statistical Summary Table Statistical Parameter Total Number of Survey Measurements 34 Number of Measurements >MDC 21 Number of Measurements Above 50% of DCGL 0 Number of Measurements Above DCGL 0 Mean 0.0194 Median 0.0187 Standard Deviation 0.0053 Maximum 0.0324 Minimum 0.0085 6.0 Documentation of evalrtations periaining to compliance with the unrestricted use limit of 25 mdyr and dose contributions from Embedded Pipe and radionuclides contributing 10% in aggregate of the total dose for both structural scenarios and soils.

6.1 A review of the survey results has shown that the dose contribution for EP 1.641-4 to be less than 1 mrerdyr. The dose contribution is estimated to be 0.019 mredyr based on the average of the actual gross counts measured. ~ ~ ~

7.0 Attachments Attachment I - BSI EP/BP Survey Report Attachment 2 - Pipe Interior Radiological Survey Form Attachment 3 - DQA Worksheet Attachment 4 - SURR EP 1.641-4 & Spreadsheet

SECTION 7 ATTACHMlENT 1 3 PAGE(S)

BSI EPIBP SURVEY REPORT I Pipe ID Survey Date

! 1.6414 19Jul-07

!! Survey Location 2350-1 t II Canal G8H overflow 189094 I Survey Time Pipe Size 4" I1 I Detector-SM #

Detector Efficiency II lMGl LVS-IIlOl O.OOO36 I

I Maximum Minimum 0.0324 0.0085 I Survey Technician(s)

FOWLER TBD O6-004 Piping Group 1 SR-I3 Radionuclide Distribution Sample EP 3-8 Measured Nuclide co-60 ~

Area FactorlEMC Used No PasslFail FSS Pass MREMlYR Contribution <l COMMENTS:

ACTIVITY VALUES NOT BACKGROUND CORRECTED.

RP Engineer I Date

-

EP 1.6414 4" Pipe TBD 06-004 Group 1 I

I I I I Ag-108m activlty (dpmllOOcm2)

Jnity 18

-

0.01!

-

20 -0.01'

.~

16 -0.01~

10 -O.OO!

14 -0.01:

0.01

___

-0.01 0.01

__

-0.01 0.02

__

28 -0.02 24

-

0.02

__

_-

22 0.01

__

24 -0.02 0.01

__

0.02

__

0.02 1 of2

EP 1.641-4 4" Pipe TBD 06-004 Group 1 Eu-152 activity Eu-164 activity Nb-94 activity Ag-108m activity activity Cs-137 activity ncpm (dpm1100cm2) (dpm1100crnZ) (dpm1100crn2) (dpml100cm2) (dpm1100crn2) 133 32 0.02; s

4,334 1,152 4,283 4,063 1,080 125 30 0.02(

I MEAN 0.01!

MEDIAN_- O.Ol!

STD D N -~ 0.ooi

- MAX 0.03:

-

MIN 0.00 2of2

SECTION 7 ATTACHMENT 2 3 PAGE(S)

I I BSYLVSPipeCrawler-002 Revision 5 Pipe Interior Radiological Survey Form 7-I 7- 0 7 O%S 6 Date:

Pipe ID#:

Building:

1 kb2j 1 ~

Time:

Pipe Diameter:

Elevation:

Y*

-25' Access Point Area:

System: G+)i d - &[

L\m SCJ

/

Type of Survey Investigation Characterization FinalSurveyx- Other /

Gross Co60 d cs Detector ID# / Sled ID# I mb 1 U f -1 /\ol Detector Cal Date: \ - \I- as

• Detector Cal Due Date: 1- l \ - b P Instrument: 23so - 1 . . Instrument ID #: 167 Q ? q Instrument Cal Date: 1- \ \ - 07 Instrument Cal Due Date: 1 -11 0 9 From the Daily Pipe Survey Detector Control Form for the Selected Detector BackgroundValue 3 \ cpm MDCRStiItlC 9 , \CPm Efficiency Factor for Pipe Diameter 61000367 (fiom detector efficiency determination)

MDCS,tlC 3054 dpd IOa cm2 Is the MDCSQticacceptable? @ No (ifno, adjust sample count time and recalculate MDCR&

Pipe Interior Radiological Survey Technician Signature r Package Page 1 o f 3 0 REFERENCECOPY Attachment 3, Page 1

I BSYLVSPipeCrawler-002 Revision 5 Pipe Interior Radiological Survey Form (Continuation Form)

Pipe ID#: 2JJ

- ZJ-Date: 7 \ 9 0 7 Pipe Diameter: Access Point Area: H, Building:

Y Elevation: System: G +H cor.,*\ Duuclu.

Attachment 3, Page 2

I SECTION 7 ATTACHMENT 3 I PAGE(S)

DQA Check Sheet

~~

Design # 1 EP 1.6414 I Revision # I Original 1 Survey Unit # EP 1.641-4 Answers to the following questions should be fully documented in the Survey Unit Yes No N/A Release Record

1. Have surveys been performed in accordance with survey instructions in the Survey Design? 1 x 1 I 2.

-

Is the instrumentation MDC for structure static measurements below the DCGLw for Class 1 and 2 survey units, or below 0.5 DCGLWfor Class 3 survey units? I Ix

3. 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 embedded/buried piping scan measurements below the DCGLw,or, if not, was the need for additional X static measurements or soil samples addressed in the survey design?

~ ~~ ~ ~ ~ ~~ -

5. Was the instrumentation MDC for volumetric measurements and smear analysis < 10% DCGLw ? X

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

7. Were the survey methods used to collect data proper for the types of radiation involved and for the X

media being surveyed?

8. Were Special Methods for data collection properly applied for the survey unit under review? 1 x 1 I

1. Has a posting plot been created? X

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

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

2. Is the mean of the sample data < DCGLW? X

3. If elevated areas have been identified by scans and/or sampling, is the average activity in each X elevated area .Z DCGLEMC (Class l), .Z DCGLW(Class 2), or ~ 0 . DCGLW 5 (Class 3)?

4. Is the result of the Elevated Measurements Test .Z 1.O? X

5. Is the result of the statistical test (S+ for Sign Test or W , for WRS Test) 2 the critical value? X Page 1 of 1

I SECTION 7 ATTACHMENT 4 1 DISC

Design # EP-Rx 150D Revision # Original Page 1 of 3 Survey Unit #(s) Rx 150D

1) Embedded Pipe (EP) Survey Unit Rx 150D meets the definition of embedded pipe for Plum Brook Reactor Facility (PBRF).

2) EP Rx 150D is a Class 1, Group 2 survey unit as per the PBRF Final Status Survey Plan (FSSP) and Technical Basis Document (TBD)-06-004.

3) Surveys in EP Rx 150D were performed using a scintillation detector optimized to measure gamma energies representative of CO-60.Sample #EP 2-1 from Survey Request (SR)- 13 was referenced for this decision.

4) Survey Instructions for this survey unit are incorporated into and performed in accordance with (IAW) the Babcock Services Incorporated (BSI)/LVS-002, Work Execution Package (WEP)05-006.Survey instructions described in this Description document constitute Special Methods and the survey design used in the acquisition of survey measurements.

5 ) Instrument efficiency determinations are developed in accordance with the BSyLVS-002, WEP 05-006, these determinations are appropriate for the types of radiation involved and the media being surveyed.

FSS Design ## EP Rx 150D Survey Unit: Rx l5OD 1.o HistoryDescription 1.1 The subject pipe system is the 0.75 Quad B system line.

1.2 EP Rx 1SOD is approximately 15 feet in length.

2.0 Survey Design Information 2.1 EP Rx 1SOD was surveyed IAW Procedure #BSVLVS-002.

2.2 100% of the 0.75 ID pipe was accessible for survey. The accessible 0.75 ID pipe was surveyed by static measurement at one foot increments, for a total of 15 survey measurements.

2.3 Surface area for the 0.75 ID piping is 182 cm2for each foot of pi ing, B

corresponding to a total 0.75 ID piping surface area of 2,736 cm (0.3 m2) for the entire length of (1 5 ) of 0.75 piping..

3.0 Survey Unit Measurement LocationsData 3.1 Pipe interior radiological survey forms are provided in Attachment 2 of this release record.

4.0 Survey Unit InvestigationslResults 4.1 None 5.0 Data Assessment Resuits 5.1 Data assessment results are provided in the EPBuried Pipe (BP) Survey Report provided in Attachment 1.

5.2 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.

5.3 When implementing the Unity Rule, provided in Section 3.6.3 of the FSSP, and applying the Nuclide Fraction (NF), provided in TBD-06-004, the survey unit that is constituted by EP Rx 150D passes FSS.

5.4 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 l5OD Revision # Original Page 3 of 3 5.5 Statistical Summary Table 0.75 Statistical Parameter Pipe Total Number of Survey Measurements 15 Number of Measurements >MDC 10 Number of Measurements Above 50% of DCGL 0 Number of Measurements Above DCGL 0 Mean 0.0384 Median 0.0403 Standard Deviation 0.0130 Maximum 0.0564 Minimum 0.0161 4 Documentation of evaluations pertaining to compliance with the unrestricted use limit of 25 &yr and dose contributions from Embedded Pipe and radionuclides contributing 10% in aggregate of the total dose for both structural

-

scenarios and soils.

6.1 A review of the survey results has shown that the dose contribution for EP Rx 150D to be less than 1 mredyr. The dose contribution is estimated to be 0.038 mredyr based on the average of the actual gross counts.

____..~_______.

Attachment 1 - BSI EPBP Survey Report Attachment 2 - Pipe Interior Radiological Survey Form Attachment 3 - DQA Worksheet Attachment 4 -Disc containing RR for EP Rx 1SOD & Spreadsheet

SECTION 7 ATTACHMENT 1 2 PAGE(S)

! I BSI EPIBP SURVEY REPORT 2 Pipe ID Survey Date I 02-Aug-06 Survey Location -27' Trench Loop Drair Survey Time 12:50 Detector-Sled # 0047-no sled Pipe Size 0.75 Detector Etficiency 0.00059 DCGL wmmcm2) 2.41E 9 5 182 nP.Wlnsorpor*pW 0.3 D p ' 1 Routine Survey X Field MDCR (cp)

Survey Measurement Results Total Number oi iurvey Measurements 15 Number of Measurements >MDC 10 Number of Measurements Above 50% DCGL 0 Number of Measurements Above DCGL 0 Mean 0.0384 aurvey unn uassmtxion I 1 TBD O6-004 PiDitw

. - Group 1 2

SR-13 Radionuclide Distribution Sample EP 2-1 Measured Nudide C0-60 Area FactorlEMC Used No PasdFail FSS Pass MREMNR Contribution el

OMMENTS:

CTNITY VALUES NOT BACKGROUNDCORRECTED 7- /7-07

EP Rx 150D 0.75" Pipe TBD 06-004 Group 2 ncpm C060 activity (totaldpm)

C0-60 acthri (dpmllOOcm2)

Cs-137 activity (dpm1100cm2)

EU-152 activity

..

ldomllOOcm2l  ?

Eu-1 activity (dpml OOcm2)

I Nb-94 activity (dpmll00cm2)

Ag-lO8m activity (dpm1100cm2) i 9,292 4,818 77

~-10 16,949 11 11 18,644 10,221 5,300 85

___

7 - 7 11,864 6,504 3,373 54 11 18,644 10,221 --- 5,300 85 10 16,949 ~- 9,292

.~

4,818 77 10 16,949 9,292 4,818 - 77 13,009 6,745 108

___ 14 23,729 A 4 6,78C 3,717 1,927 - 31

_-

9 15,254 8,363 4,336 69 A 4 6,78C 3,717 1,927 31 I3 12 20,33E - 11,150 5,782 92 14 23,72E 13,009 6,745 108 8 13,552 7.433 3,855 62

13. __ 22,03 12:079 6,264

__ 1oa 6 10,161 5.572 ~ _ _ 2,891 _ - .

46 MEAN 0.038 MEDIAN 0.040

__ -

STD DEV 0.01 3 t-I _--

MAX 0.056 MIN 0.016 -

1 of 1

I SECTION 7 ATTACHMENT 2 3 PAGE(S)

I I I BSVLVSPipeCrawler-002 Revision 4 Pipe Interior Radiological Survey Form Time: I Z e Pipe Diameter: e75 -

Access Point Area: 2 7 7/2tWdf Elevation: -27 System: Loo? D/-w.rlLlf

-

c Type of Survey Investigation Characterization A Final Survey X Other Gross C06O .rl cs-Detector ID# / Sled ID# ~ o / / . I;L -x *ob471 &O SLiW3 Detector Cal Date: Z/ZO 1 0 6 Detector Cal Due Date: 07 I I Instrument: 23 523 -7 Instrument ID #: I69094 Instrument Cal Date: 3/45/06 Instrument Cal Due Date: 31 I S/O 7 f

I From the Daily Pipe Survey Detector Control Form for the Selected Detector BackgroundValue /%, 3 cpm MDCRStatl, l7*S CPm Efficiency Factor for Pipe Diameter 0.0 006 (from detector efficiency determination)

MDC,tab, 763\ dpd 10- cm2 Is &he MDC,tah, acceptable? No (ifao, adjust sample count time am? refikulate MI3?3,,)

Cclmlents: En, SURA/\-& Et32 L. I c9.M PLrSN

$Pytw)J E)b 576 n Technician Signature Pipe Interior Radiological Survey ~ _ _ _ _ ___~

_ _ _ _ _ ~ -~ ~~

Position

Feet into Pipe fiom Opening Count Time (min)

Gross Counts Gross cpm Net cpm 1 d p d l OOcm2 1 I IO 10 la /a/

2 3 1 j r 3 3 4 e iA /I I I

5 IO 10 6 L IC) JO I 4I 7 7 I+ 14 j 8 Q 4 I I 9 4 7 4 I I  !

10 io w 4 I d

Package Page 1 o f a REFERENCECOPY Attachment 3, Page 1

i I BSYLVSPipeCrawler-002 Revision 4 Pipe Interior Radiological Survey Form (Continuation Form) rzw Date:

Pipe ID#: Pipe Diameter: *75 b'

Access Point Area: -.y' m&.wgt Building: Elevation: -27' System: L@? D PPInl Package Page & o f 2 Attachment 3, Page 2

SECTION 7 ATTACHMENT 3 1 PAGE($)

DQA Check Sheet Design # I EP Rx 1500 I Revision # 1 Original 1 EP Rx 150D Answers to the following questions should be fully documented in the Survey Unit Yes No NIA Release Record 1, Have surveys been performed in accordance with survey instructions in the Survey Design? X

2. Is the instrumentation MDC for structure static measurements below the DCGLw for Class 1 and 2 X survey units, or below 0.5 DCGLWfor Class 3 survey units?

3. Is the instrumentation MDC for embeddedburied piping static measurements below the DCGLW? X

4. Was the instrumentation MDC for structure scan measurements, soil scan measurements, and embedd&uried piping scan measurements below the DCGLw,or, if not, was the need for additional X

-~

static measurements or soil samples addressed in the survey design?

~

5. Was the instrumentation MDC for volumetric measurements and smear analysis < 10% DCGLw ? X

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

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

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

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

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

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

1. Are all sample measurements below the DCGLw (Class 1 i 3 2), or 0.5 DCGLw (Class 3)? 1 x 1 I

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 X elevated area c DCGLEM (Class I),< DCGLW(Class 2), or ~ 0 . DCGLw 5 (Class 3)?

4. Is the result of the Elevated Measurements Test 1.O? X

5. Is the result of the statistical test (S+ for Sign Test or W, for WRS Test) 5 the critical value? X FSSlCharacterization Engineer (prinffsign) Date 7-17-07 FSS/ Characterization Manager (prinffsign) Date 8 ) N h Form CS-0912 Rev 0 Page 1 of 1

SECTION 7 ATTACHMENT 4 1 DISC

0 COPY Design # HL-111 Revision # Original Page 1 of 3 Survey Unit #(s)

2) HL-111 is a Class 1, Group 2 survey unit as per the PBRF Final Status Survey Plan (FSSP) and Technical Basis Document (TBD)-06-004.

3) Surveys in HL-111 were performed using a scintillation detector optimized to measure gamma energies representative of CO-60. Sample #EP 2-5 fiom Survey Request (SR)- 13 was referenced for this decision.

4) Survey Instructions for this survey unit are incorporated into and performed in accordance with (IAW) the Babcock Services Lncorporated (BSI)/LVS-002, Work Execution Package (WEP)05-006. Survey instructions described in this Description 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 Date:

FSS/Characterization Engineer ,.VL 7- /a- 0 7 Technical Reviewer (FS S/Characterization Engineer) 7-1 8-07 FSWChaacterization Manager

I FSS Design # HL-111 I Revision # Original I ~age2of3 I Survey Unit: HL-111 I

1.o HistoryDescription 1.1 The subject pipe system is the 3 vent line for Canal J. The function of this pipe was to convey water f?om the 3risers in Quad 3 to the HD sump in Pump Room#22 on the Rx building -25fi., where the pipe is currentIy breached.

1.2 HL-111 consists of 3 diameter piping that is approximately 3 feet in length.

2.0 Survey Design Idormation 2.1 HL-111 was surveyed IAW Procedure #BSVLVS-002.

2.2 100% of the 3 ID pipe was accessible for survey, The accessible 3 ID pipe was surveyed by static measurement at one foot increments, for a total of 3 survey measurements.

2.3 Surface area for the 3 ID piping is 730 cm2for each foot of pi ing, P

corresponding to a total 3 ID piping surface area of 2,190 cm (0.2 m2) for the entire length of (approximately 3) of 3 piping.

3.0 Survey Unit Measurement Locations/Data 3.1 Pipe interior radiological survey forms are provided in Attachment 2 of this release record.

4.0 Survey Unit InvestigationsResults 4.1 None 5.0 Data Assessment Results 5.1 Data assessment results are provided in the EPBuried Pipe (BP) Survey Report provided in Attachment 1.

5.2 All measurement results are less than the Derived Concentration Guideline r e - -

mredyr dose goal established in Table 3-3 of the FSSP.

5.3 When implementing the Unity Rule, provided in Section 3.6.3 of the FSSP, and applying the Nuclide Fraction 0, provided in TBD-06-004, the survey unit that is constituted by HL-111 passes FSS.

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

FSS Design # HL-111 Revision # Original Page 3 of 3 5.5 Statistical Summary Table

~~

Statistical Parameter

~

I Pipe Total Number of Survey Measurements 3

~

Number of Measurements M D C 3 Number of Measurements Above 50% of DCGL 0 Number of Measurements Above DCGL 0 Mean 0.0279

~ ~-

Median 0.0320 Standard Deviation 0.0083 Maximum 0.0333 Minimum 10.0183 6.0 Documentation of evaluations pertaining to compliance with the unrestricted use limit of 25 m e d y r and dose contributions &om Embedded Pipe and radionuclides contributing 10% in aggregate of the total dose for both structural scenarios and soils.

6.1 A review of the survey results has shown that the dose contribution for HL-111to be less than 1 mredyr. The dose contribution is estimated to be 0.028 m re d yr based on the average of the actual gross counts measured. ~- - ~ --

Attachments Attachment 1 - BSI EPBP Survey Report Attachment 2 - Pipe Interior Radiological Survey Form Attachment 3 - DQA Worksheet Attachment 4 -Disc containing RR for HL- 1 11 ?i Spreadsheet

SECTION 7 ATTACHMENT 1 2 PAGE(S)

c

._ e BSI EWBP SURVEY REPORT Pipe ID I HL-I 11 II Survey Location I Canal J Vent Survey Date 1 iwan-06 II 23500-1# 1 212223 I

___t____ll I t DetectorSM #

I 212701-121 Pipesize I 3 II Detector Efficiency 1 I

0.00013 DCGL #pnnmnai 2.41E 4 5 Rp-lnmP-wJw-emw 730 Field BKG1 ~ 1 5.6 Total Number of Survey Measurements 3 Number of Measurements >MDC 3 Number of MeasurementsAbove 50% DCGL 0 Number of Measurements Above DCGL 0 Mean 0.0279 Median 0.0320 Standard Deviation 0.0083 Maximum 0.0333 Minimum 0.0183

~~ ~

OMMENTS:

CTlVlTY VALUES NOT BACKGROUND CORRECTED RP Engineer I Date 7-7-07

HL-I I 1 9cpm ncpm Co40 activity 3" Pipe TBD 06-004 Group 2 Cs-137 activity (dpm/100cm2)

EulS2 activity (dpm/lOOcm2)

-

I

~~1~~ I AglO8m activity (dpm1100crn2) 7 4 4 30.769 ___ _4,215

___ 2,186 ______ 35 2 121

-

0.01t 7.3 SI154 7.3 ~- 7,692 3,989 64 4 221 0.03:

53.846 7.376 3,825 61 41 212 0.03; 7 7 1

-

0.021 I 0.03; 0.001 0.03:

-

0.011 1 of1

SECTION 7 ATTACHMENT 2 I PAGE(S)

i Pipe Interior Radiological Survey Form Date: / /Ifdt Time: / 3 lfJ- C4U4tfL Building :  ? A n d Elevation / 2s Access Point LA-System: 7 d297 Pipe Diameter: Area: Pipe ID L - / I f Type of Survey Investigation L Characterization > T Final Survey ## Other 4 Sled Size 3b44( sm?&l(oeinch Detector: 4 . 4t Detector ID #: 31r736P- / a /

Cal Date: f l W - 0 4 -0 5 Cal Due Date: 13-Fo\r - a d Instrument: 3 353 { Instrument ID #: aiasP.3 Cal Date: /7- &)Od Q 5 Cal Due Date: I 7 7 f a N -0 b From the Daily Pipe Survey Detector Control Form for the Selected Detector Background Value 30 6 cpm MDCRstatic 1/.1 CPm Efficiency Factor for Pipe ~,OOOI.3 (taken from detector calibration certificate)

Qpjyeter StahC 27 79 d p d l OOcm IS the M D C S t a t i c @ No (if no, adjust sample count time and recalculate MDCL6,)

C&%&&?!e? $&7& S d A 4Lf Pipe Interior Radiological Survey Radiological Survey Commenced: Date: / - / 6 b Time: / 36 f -

Package Page 1 o f 1 0 REFERENCE COPY Attachment 3, Page 1

I I SECTION 7 ATTACHMENT 3 I PAGE(S)

.

I I I

Design # HL-Ill Revision # Original Survey Unit # HL-111 Answers to the following questions should be fully documented in the Survey Unit Release Record Yes No N/A

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 Iand 2 X survey units, or below 0.5 DCGLw for Class 3 survey units?

3. Is the instrumentation MDC for embedded/buried piping static measurements below the DCGLw ? X

4. Was the instrumentation MDC for structure scan measurements, soil scan measurements, and embedded/buried piping scan measurements below the DCGLW,or,if not, was the need for additional X static measurements or soil samples addressed in the survey design?

5. Was the instrumentation MDC for volumetric measurements and smear analysis c 10% DCGLW? X

6. Were the MDCs and assumptions used to develop them appropriate for the instruments and techniques used to perform the survey3

7. Were the survey methods used to collect data proper for the types of radiation involvedand for the media being surveyed? X

8. Were 'Spedal Methods" for data collection property applied for the survey unit under review? X I, Has a posting plot been created? X

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

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

2. Is the mean of the sample data c DCGLw? X

3. If elevated areas have been identifiedby scans and/or sampling, is the average activity in each X

elevated area DCGLEW(Class I),< DCGLw (Class 2), or 4 . 5 DCGLW(Class 3)?

4. Is the result of the Elevated Measurements Test < 1.O? X

5. Is the result of the statistical test (S+ for Sign Test or W, for WRS Test) 2 the Critical value? X Page 1 of 1

I SECTION 7 ATTACHMENT 4 1 DISC

I I Design # EP-Rx 16 1 Revision # Original Page 1 of 3 Survey Unit #(s) Rx161

1) Embedded Pipe (EP) Survey Unit Rx161 meets the definition of embedded pipe for Plum Brook Reactor Facility (PBRF).

2) EP RX161 is a Class 1, Group 2 survey unit as per the PBRF Final Status Survey Plan (FSSP) and Technical Basis Document (TBD)-06-004.

3) Surveys in EP Rx161 were performed using a scintillation detector optimized to measure gamma energies representative of CO-60.Sample #EP 2-1 from Survey Request (SR)-13 was referenced for this decision.

4) Survey Instructions for this survey unit are incorporated into and performed in accordance with (IAW) the Babcock Services Incorporated (BSI)/LVS-002, Work Execution Package (WEP)05-006. Survey instructions described in this Description document constitute Special Methods and the survey design used in the acquisition of survey measurements.

5) Instrument efficiency determinationsare developed in accordance with the BSILVS-002, WEP 05-006, these determinations are appropriate for the types of radiation involved and the media being surveyed.

COPY Approval Signatures Form CS-09/1 Rev 0

I t FSS Design ## EP Rxl61 Revision # Original Page 2 of 3 1.o History/Description 1.1 EP Rx161 is a Canal E drain that terminates in Quad B. The subject piping described in this report is integral to the drain system for the Reactor Building. The piping that constitutes EP Rx 161 addressed in this report service floor and equipment drains on the -25 foot of the Reactor Building. The purpose of the system is to convey waste water from the Canal E drain openings to Quad B. This system involves approximately 3 liner feet of drain system piping.

1.2 EP Rx161 consists of 3 linear feet () of 6 inch () b i d e Diameter (ID) piping starting in the -25 foot elevation trench and running to Quad B. The total piping for EP Rx161 is 3.

2.0 Survey Design Information 2.1 EP Rx161 was surveyed IAW Procedure #BSI/L,VS-002.

2.2 100% of the 6 ID pipe was accessible for survey. The accessible 6 ID pipe was surveyed by static measurement at one foot increments, for a total of 3 survey measurements.

2.3 Surface area for the 6 ID piping is 1,459 cm2for each foot of iping, corresponding to a total 6 ID piping surface area of 4,377 cm4(0.4 m2) for the entire length of (3) of 6 piping..

3.0 Survey Unit Measurement LocationsData 3.1 Pipe inkxior radiological survey forms are provided in Attachment 2 of this release record.

4.0 Survey Unit Investigationshtesults 4.1 None 5.0 Data Assessment Results

___ ~~ ~-

5.1 Data assessment results are provided in the EPBuriedPipe (BP) Survey Report provided in Attachment 1.

5.2 All measurement results are less than the Derived Concentration Guideline Level (DCGL) for radionuclide specific EP that corresponds to the 1 m r d y r dose goal established in Table 3-3 of the FSSP.

5.3 When implementing the Unity Rule, provided in Section 3.6.3 of the FSSP, and applying the Cesium-l37/CobaltdO ratios, provided in TBD-06-004, the survey unit that is constituted by EP Rxl6 1 passes FSS.

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

FSS Design # EP Rx161 Revision # Original Page 3 of 3 5.5 Statistical Summary Table I Statistical Parameter 3

Total Number of Survey Measurements Number of Measurements >MDC 3 Number of MeasurementsAbove 50% of DCGL 0 Number of Measurements Above DCGL 0 Mean 0.002 Median I 0.002 I Standard Deviation 0.000 Maximum 0.002 I 0.002 I

Minimum 6.0 Documentation of evaluations pertaining to compliance with the unrestricted use limit of 25 m r e d y r and dose contributions fiom Embedded Pipe and radionuclides contributing 10% in aggregate of the total dose for both structural scenarios and soils.

6.1 A review of the survey results has shown that the dose contribution for EP Rx161 to be less than1 mredyr. The dose contribution is estimated to be 0.002 mredyr, based on the average of the actual gross counts measured.

7.0 Attachments

~~

Attachment 2 - Pipe Interior Radiological Survey Form Attachment 3 - DQA Worksheet Attachment 4 -Disc containing RR for EP Rx 161 & Spreadsheet

SECTION 7 ATTACHMENT 1 7 PAGE(S)

I I I

~~~ ~ ~

Pipe ID Rxl61 Survey Location -25RX Survey Date 13-Jan-06 ~

2350-1 # 134738 Survey Time 1335 Detector-Sled ## LVSl -107 7 -

Pipe Size 6 Detector Efficiency 0.002 Pipe Area Incorporated by Detector DCGL (dpWlOOem2) 240,800 Efficiency (in cm2) 1459 Pipe Area Incorporated by survey ~ a itml i 0.4 Field BKG (cpm) 20.7 Routine Survey X Field MDCR (cpm) 18.6 QA Survey Nominal MDC (dpnJtoomrZ) 333 I Total Number of Survey Measurements I 3 7

Number of Measurements >MDC 3 Number of Measurements Above 50% DCGL 0 Number of Measurements Above DCGL 0 I

Mean 0.002 Median I 0.002 Standard Deviation 0.000 Maximum 0.002 Minimum 0.002 Survey Unit Classification 1 TBD 06-004Piping Group 2

-~ ~ SR-13 Radionuclide Distribution Sample _ ~ _ FP 7-1 _

_ . ~ ~ -_ _ ~

Measured Nuclide co60 Area FactorIEMC Used No Pass/Faii FSS Pass MREMNR Contribution <1 COMMENTS: Activity values are not background corrected.

61612007

EP Rx161 TBD 06-004 Group 2 ncpm Co-80 activity (total dpm) C7*ih (d lOOcm2)

Cs-137 activity (dpmll00cm2)

Eu-162 actMty (dpm1100an2)

Eu-1S4 acthrity (dpm110Ocm2)

Nb-04 activity (dpmHOOcm2)

Ag-l08m activity (dpmllOOcm2) 2

___

14 15 14 15

-

7,000 1 480 249 267 4

4

-

3 3

0 0

~ 7,500 3 16

_

16

_

8,000 3 ______

285

_____..

5 - 3 0 0.002 MEDIAN- 0.002

- 0.00:

0.009 1of1

SECTION 7 ATTACHMENT 2 2 PAGE(S)

1 Pipe Interior Radiological Survey Form

+ .

Date: i-I3-& Time: 13)-

Building:

System:

Q-f

,&iik'.&&W9da&

Elevation Pipe Diameter:

- 2)-

fn f(

Access Point Area: Pipe ID

&q@Al-- IG

- Q-% /I$/

Type of Survey Investigation Characterization Final Survey ## Other Sled Size hffp/07 inch Detector: d/ffZOAl /m&-/ Detector ID #: /- \IS 1 7 0 7 Cal Date: fL-/ 7- or Cal Due Date: /L-t 7 - 0 6 Instrument: 7,3J-V-- / Instrument ID #: rW7n3 Cal Date: 12-1 7 Cal Due Date: &-f 7-0 E.

From the Daily Pipe Survey Detector Control Form for the Selected Detector Background Value do 7 a cpm MDCRstabc /QIt cpm Efficiency Factor for Pipe 0 0o z (taken from detector m e tstatlc er c~ U dpm/100crn2 Is the MDCShhc r.-

a No (dno, adjust sample count tune and recalculate M D C L , , )

c&%Efitble?

I

&7&(-

. sas q a

s s p / C~rMPI-C,--c

/

Pipe Interior Radiological Survey Radiological Survey Commenced: Date: 1 -I3ab Time.- /33J---

Position Feet into Pipe Count Time - fi

- &QS %p-p _ _ ~ ~ - - -

~~

woss d p d l OOcm'

1. from Opening (min) CPm CPm Counts 1 1 I I/ Y /Y nle, a/@

2 3 I fG 1 6 I

3 .3 1 Id- / >-

4 nl& nla fl k w n b 5 I I I

6 7 I I 8 I I 9 I 10 J L 1 JI 4 Package Page 1 of[

0 REFERENCECOPY Attachment 3, Page 1

SECTION 7 ATTACHMENT 3 PAGE(S)

I I DQA Check Sheet Design #

~~

1 EP Rx161 I Revision # 1 Original I ~ ~

Survey Unit # EP Rx161 Answers to the following questions should be fully documented in the Survey Unit Release Record Yes No NIA

1. Have surveys been performed in accordance with survey inshuctions 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 survey units? I Ix

3. Is the instrumentationMDC for embeddedhuried piping static measurements below the DCGLW? X

4. Was the instrumentationMDC for structure scan measurements, soil scan measurements, and embeddedhuried piping scan measurements below the DCGLW,or, if not, was the need for additional static measurements or soil samples addressed in the survey design?

5. Was the instrumentation MDC for volumetric measurements and smear analysis < 10% DCGLW? X

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 X

media being surveyed?

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

9. Is the data set comprised of qualified measurement results collected in accordance with the survey design, which accurately reflects the radiological status of the facility?

Graphical Data Review IxI

~~ ~

1. Has a posting plot been created? X

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

3. Have other graphical data tools been created to assist in analyzing the data? I I l x Data Analysis

____- -. - -

1. Are all sample measurements below the DCGLw (Class 1 & 2), or 0.5 DCGLw (Class 3)? 1 x

2. Is the mean of the sample data < DCGLw? X

3. If elevated areas have been identied by scans andlor sampling, is the average activity in each X

elevated area < D C G k (Class I), c DCGLw (Class Z), or 6 . 5 DCGLw (Class 3)?

4. Is the result of the Elevated Measurements Test 1.O? X

~ ____ ~~ ~~ ~~

5. Is the result of the statistical test (S+ for Sign Test or W, for WRS Test) 2 the critical value? X FSS/Characterization Engineer (prinUsign) D4/e8w&&$(4&& XdL4 Date 6-06-07 FSS/ Characterization Manager (printlsign) I X/IY/Wk I3. Case Date 5//3107 Form CS-09/2 Rev 0 Page 1 of 1

SECTION 7 ATTACHMENT 4 1 DISC