ML080670264

Survey Unit Release Record, EP-S2, Embedded Pipe Survey Unit S2

ML080670264
Person / Time
Site:	Plum Brook  File:National Aeronautics and Space Administration icon.png
Issue date:	03/05/2008
From:	- No Known Affiliation
To:	NRC/RGN-III
References
Download: ML080670264 (12)

Text

Survey Unit Release Record Design #

EP-S2 Revision #

Original Page 1 of 3 Survey Unit #(s)

S2

1) Embedded Pipe (EP) Survey Unit S2 meets the definition of embedded pipe for Plum Brook Reactor Facility (PBRF).

2) EP S2 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 S2 were performed using a scintillation detector optimized to measure gamma energies representative of Co-60. Sample #EP 3-9 from I Survey hues st (sR):~,

referenced for this decisidn.

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

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

FSS/Characterization Engineer FSSICharacterization Manager

FSS Design # EP S2 Revision # Original Page 2 of 3 Survey Unit: S2 1.0 History/Description 1.1 The subject pipe system is a 2 service conduit adjacent to the 1.51 drain system access box in the annulus on the -25 elevation of the Reactor Building.

1.2 EP S2 is approximately 16 feet in length.

1.3 Any contamination of this service conduit is expected to be cross contamination from the remediation efforts of RX1.51 which is adjacent to this service conduit in a valve box on the RB -25 annulus. Service conduit S2 was open to cross contamination during those remediation efforts.

2.0 Survey Design Information 2.1 EP S2 was surveyed IAW Procedure #BSI/LVS-002.

2.2 100% of the 2 ID pipe was accessible for survey. The accessible 2 ID pipe was surveyed by static measurement at one foot increments, for a total of 16 survey measurements.

2.3 Surface area for the 2 ID piping is 486 cm2 for each foot of piping, corresponding to a total 2 ID piping surface area of 7776 cm2 (0.8 m2) for the entire accessible length of (16) of 2 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 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 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 (NF), provided in TBD-06-004, the survey unit that is constituted by EP S2 passes FSS.

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

FSS Design # EP S2 Revision # Original Page 3 of 3 Survey Unit: S2 Statistical Summary Table Statistical Parameter 2 Pipe Total Number of Survey Measurements 16 Number of Measurements >MDC 15 Number of Measurements Above 50% of DCGL 0

Number of Measurements Above DCGL 0

Mean 0.030 Median 0.030 Standard Deviation 0.006 Maximum 0.042 Minimum 0.018 6.0 Documentation of evaluations pertaining to compliance with the unrestricted use limit of 25 mrem/yr and dose contributions from Embedded Pipe and radionuclides contributing 10% in aggregate of the total dose for both structural scenarios and soils.

6.1 A review of the survey results has shown that the dose contribution for the accessible portion of EP S2 to be less than 1 mrem/yr. The dose contribution is estimated to be 0.030 mrem/yr based on the average of the actual gross counts.

7.0 Attachments - BSI EP/BP Survey Report -Pipe Interior Radiological Survey Form - DQA Worksheet -Disc containing RR for EP S2 & Spreadsheet

SECTION 7 ATTACHMENT 1 2 PAGES

BSI EPlBP SURVEY REPORT Detector-Sled #

247697-NO SLED Detector Efficiency Survey Technician@)

ACTIVINVALUES NOT BACKGROUND CORRECTED RP Engineer I Date

&& /$-I/-

o b

/

EP S2 2" Pipe TBD 06-004 Group 1 Measurement #

gcpm ncpm Co-60 activity (total dpm)

Co-60 activity (dpm/100cm2)

Cs-137 activity (dpm/100cm2)

Eu-152 activity (dpm/100cm2)

Eu-154 activity (dpm/100cm2)

Nb-94 activity (dpm/100cm2)

Ag-108m activity (dpm/100cm2)

Unity 1

14 14 34,146 7,020 278 6,659 1,770 205 49 0.042 2

10 10 24,390 5,014 199 4,756 1,264 146 35 0.030 3

12 12 29,268 6,017 238 5,708 1,517 176 42 0.036 4

11 11 26,829 5,515 219 5,232 1,391 161 38 0.033 5

10 10 24,390 5,014 199 4,756 1,264 146 35 0.030 6

9 9

21,951 4,513 179 4,281 1,138 132 31 0.027 7

8 8

19,512 4,011 159 3,805 1,012 117 28 0.024 8

9 9

21,951 4,513 179 4,281 1,138 132 31 0.027 9

6 6

14,634 3,008 119 2,854 759 88 21 0.018 10 9

9 21,951 4,513 179 4,281 1,138 132 31 0.027 11 10 10 24,390 5,014 199 4,756 1,264 146 35 0.030 12 10 10 24,390 5,014 199 4,756 1,264 146 35 0.030 13 10 10 24,390 5,014 199 4,756 1,264 146 35 0.030 14 13 13 31,707 6,518 258 6,183 1,644 190 45 0.039 15 9

9 21,951 4,513 179 4,281 1,138 132 31 0.027 16 10 10 24,390 5,014 199 4,756 1,264 146 35 0.030 MEAN 0.030 MEDIAN 0.030 STD DEV 0.006 MAX 0.042 MIN 0.018 1 of 1

SECTION 7 ATTACHMENT 2 2 PAGES

BSVLVSPipeCrawler-002 Revision 5 Pipe Interior Radiological Survey Form Date:

1-lb-9 8 rime:

1 4 ~ 4 Pipe ID#: J"z Pipe Diameter:

2 "

Access Point Area: &B ~ j d v ~ v - 3 Building:

Elevation:

-2s' System:

(33n/0~7 T Type of Survey Investigation Characterization Final Survey X Other,A Gross C06O

,A Cs Detector ID# I Sled ID#

247bc?7 1

n/0 5 b ~ b Detector Cal Date:

/ ~ - / b

-07 Detector Cal Due Date: _

,/D - / b - ~ 9 Instrument:

2338

- 1 Instrument ID #:

~0311/3f Instnunent Cal Date:

/D - 1 b - b' 7

Instrument Cal Due Date:

/ ~ * / 6 - 0

• From the Daily Pipe Survey Detector Control Fo,m for the Selected Detector Background Value

1. 8 cpm MDCRStatic 70 b CPm Efficiency Factor for Pipe Diameter 0. OooJ/

(from detector efficiency determination)

MDCmtic dpmf L DD cm2 (if no, adjust sample count time and recalculate M D a t 3 Technician Signature Pipe Interior Radiological Survey Package Page 1 of 5, Page 1

Pipe Interior Radiological Survey Form (Continuation Form)

BSVLVSPipeCrawler-002 Revision 5 Date:

1 - 1 19-0 &

Pipe ID#:

. 5 3 Pipe Diameter:

2" Access Point Area:

An/@i/L~-s Building:

Elevation:

-76 '

System:

& & ~ 1 7 Count Time

~ r o s s Counts min)

Gross cpm

/ D

/ D l o

/3 4

/ v Package Page ?of

& \\, P:i I

SECTION 7 ATTACHMENT 3 1 PAGE

I DQA Check Sheet I

I Design #

I EP S2 I Revision # I Original

/

I I

Preliminary Data Review' I

I Answers to the following questions should be fully documented in the Survey Unit Release Record Yes No NIA 1 1.

Have survevs been performed in accordance with survev instructions in the Survev Desian?

1 x 1 I

1

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

survev units. or below 0.5 DCGLW for Class 3 sunrev units?

I I

1. 1 1 3.

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

/

X I

I 1

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?

5. Was the instrumentation MDC for volumetric measurements and smear analvsis c 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 media being surveyed?

X

8. Were 'Soecial Methods" for data collection oro~erlv a ~ ~ l i e d for the survev unit under review?

X 9

Is the data set comprise0 of qualified measurement resd Is collected in accordance wlth the sdrvey design. wnlch accurate y reflects the raoio.ogical stalus of !he faclllly7

.. I I

1 Graphical Data Review I

I 1. Has a posting plot been created?

I 1

1 x 1 1 2.

Has a histoeram (or other freauencv plot) been created?

I I

1 x 1

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

X Data Analvsis

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 andior sampling, is the average activity in each elevated area c DCGLEMC (Class 1). c DCGLw (Class 2), or c0.5 DCGLw (Class 3)?

X

4.

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

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

I I

1 x 1 I

Comments:

FSSICharacterization Engineer (printlsign)

FSSI Characterization Manager (printlsign)

Page 1 of 1

SECTION 7 ATTACHMENT 4 1 DISC