ML073400165
| ML073400165 | |
| Person / Time | |
|---|---|
| Site: | Plum Brook File:National Aeronautics and Space Administration icon.png |
| Issue date: | 11/29/2007 |
| From: | US National Aeronautics & Space Admin (NASA) |
| To: | NRC/RGN-III/DNMS/DB |
| References | |
| EP-RBDL-2(RX-147) | |
| Download: ML073400165 (16) | |
Text
Description Survey Unit Release Record Design #
-147)
Revision #
Suwey Unit #(s)
RBDL-2 (Rx-1 47)
- 1) Embedded Pipe (EP) Survey Unit RBDL-2 (Rx-147) meets the definition of embedded pipe for Plum Brook Reactor Facility (PBRF).
- 2) EP RBDL-2 (Rx-147) is a Class 1, Group 1 survey unit as per the PBRF Final Status Survey Plan (FSSP) and Technical Basis Document (TBD) 004.
- 3) Surveys in EP RBDL-2 (Rx-147) 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 Original
- 4) Survey Instructions for this survey unit are incorporated into and performed in accordance with (IAW) the Babcock Services Incorporated (BSI)/LVS-002, Work Execution Package (WEP)05-006. Survey instructions described in this document constitute "Special Methods" and the survey design used in the acquisition of survey measurements.
- 5) Instrument esciency 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.
CS-0911 Page 1 of 3
FSS Design # EP RBDL-2 (Rx-147)
Revision # Original Page 2 of 3 Survey Unit: RBDL-2 (Rx-147) 1.0 History/Description 1.1 The subject pipe system is a 4 drain line located in the trench on the -27 el. of the Rx building.
1.2 EP RBDL-2 (Rx-147) consists of 4 diameter piping that is approximately 44 feet in length.
2.0 Survey Design Information 2.1 EP RBDL-2 (Rx-147) 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 44 survey measurements.
2.3 The total surface area for the 4 ID piping is 42,807 cm2 (4.3 m2) for the entire length of (approximately 44) 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 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 RBDL-2 (Rx-147) 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 RBDL-2 (Rx-147)
Revision # Original Page 3 of 3 Survey Unit: RBDL-2 (Rx-147) 5.5 Statistical Summary Table Statistical Parameter 4
Pipe Total Number of Survey Measurements 44 Number of Measurements >MDC 34 Number of Measurements Above 50% of DCGL 0
Number of Measurements Above DCGL 0
Mean 0.0203 Median 0.0159 Standard Deviation 0.0172 Maximum 0.0778 Minimum 0.0042 6.0 Documentation of evaluations pertaining to compliance with the unrestricted use limit of 25 mrem/yr and dose contributions from Embedded Pipe and radionuclides contributing 10% in aggregate of the total dose for both structural scenarios and soils.
6.1 A review of the survey results has shown that the dose contribution for EP RBDL-2 (Rx-147) to be less than 1 mrem/yr. The dose contribution is estimated to be 0.020 mrem/yr based on the average of the actual gross counts measured.
7.0 Attachments - BSI EP/BP Survey Report - Pipe Interior Radiological Survey Form - DQA Worksheet -Disc containing RR for EP RBDL-2 (Rx-147) & Spreadsheet
SECTION 7 ATTACHMENT 1 3
PAGE(S)
BSI EPlBP SURVEY REPORT DetactorSled #
159 2476971101 Detector Efficiency 0.00052, 0.00044 MREMlYR Contribution RP Engineer I Date
EP RBDL-2 (Rx 147) 4" 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
13 13 25,000 2,570 102 2,438 648 75 18 0.015 2
66 66 126,923 13,046 517 12,376 3,290 381 91 0.078 3
10 10 19,231 1,977 78 1,875 498 58 14 0.012 4
60 60 115,385 11,860 470 11,251 2,991 346 83 0.071 5
9 9
17,308 1,779 71 1,688 449 52 12 0.011 6
8 8
15,385 1,581 63 1,500 399 46 11 0.009 7
7 7
13,462 1,384 55 1,313 349 40 10 0.008 8
7 7
13,462 1,384 55 1,313 349 40 10 0.008 9
13 13 25,000 2,570 102 2,438 648 75 18 0.015 10 13 13 25,000 2,570 102 2,438 648 75 18 0.015 11 6
6 11,538 1,186 47 1,125 299 35 8
0.007 12 16 16 30,769 3,163 125 3,000 798 92 22 0.019 13 14 14 26,923 2,767 110 2,625 698 81 19 0.017 14 11 11 21,154 2,174 86 2,063 548 63 15 0.013 15 6
6 11,538 1,186 47 1,125 299 35 8
0.007 16 11 11 21,154 2,174 86 2,063 548 63 15 0.013 17 15 15 28,846 2,965 118 2,813 748 87 21 0.018 18 11 11 21,154 2,174 86 2,063 548 63 15 0.013 19 16 16 30,769 3,163 125 3,000 798 92 22 0.019 20 15 15 28,846 2,965 118 2,813 748 87 21 0.018 21 28 28 53,846 5,535 219 5,250 1,396 162 39 0.033 22 43 43 82,692 8,500 337 8,063 2,143 248 59 0.051 23 17 17 32,692 3,360 133 3,188 847 98 23 0.020 24 15 15 28,846 2,965 118 2,813 748 87 21 0.018 25 13 13 25,000 2,570 102 2,438 648 75 18 0.015 26 15 15 28,846 2,965 118 2,813 748 87 21 0.018 27 61 61 117,308 12,058 478 11,438 3,041 352 84 0.072 28 7
7 13,462 1,384 55 1,313 349 40 10 0.008 29 15 15 28,846 2,965 118 2,813 748 87 21 0.018 30 18 18 34,615 3,558 141 3,375 897 104 25 0.021 31 15 15 28,846 2,965 118 2,813 748 87 21 0.018 1 of 2
EP RBDL-2 (Rx 147) 4" 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 32 14 14 26,923 2,767 110 2,625 698 81 19 0.017 33 12 12 23,077 2,372 94 2,250 598 69 17 0.014 34 35 35 67,308 6,918 274 6,563 1,745 202 48 0.041 35 31 31 59,615 6,128 243 5,813 1,545 179 43 0.037 36 11 11 21,154 2,174 86 2,063 548 63 15 0.013 37 4
4 9,091 934 37 886 236 27 7
0.006 38 4
4 9,091 934 37 886 236 27 7
0.006 39 9
9 20,455 2,102 83 1,994 530 61 15 0.013 40 3
3 6,818 701 28 665 177 20 5
0.004 41 12 12 27,273 2,803 111 2,659 707 82 20 0.017 42 5
5 11,364 1,168 46 1,108 295 34 8
0.007 43 18 18 40,909 4,205 167 3,989 1,060 123 29 0.025 44 12 12 27,273 2,803 111 2,659 707 82 20 0.017 MEAN 0.020 MEDIAN 0.016 STD DEV 0.017 MAX 0.078 MIN 0.004 2 of 2
SECTION 7 ATTACHMENT 2
,gj p R ~ ~ ~ ~ ( s )
Pipe Interior Radiological Suwey Form BSI/LVSPipeCrawler-002 Revision 4 Date:
3:- gyo&
Time:
/ @ 3 0 Pipe ID#: I;?X I ~7 &,Tm.a Pipe Diameter:
4 n
Access Point Area:
m L - ' C k f Building:
lLlc Elevation:
- 2 7 System: C L ~ Z V
~ 0 7 D R ~
r LI Type of Survey Investigation Characterization Final Survey,A Other Gross C06O J
Cs Detector ID# / Sled ID#
5
- I I
Q /
Detector Cal Date:
//-f 7 -OF Detector Cal Due Date:
//-/7-d 6 hstrument:
2-3~x7 -(
Instnunent ID #:
Z 0 3 Y b B Instrument Cal Date:
//-I 7- 0~'-
Instrument Cal Due Date.
/ /-/ 7-06 From the Daily Pipe Survey Detector Control Form for the Selected Detector Background Value b.3 cpm MDChtattc
/6/9 cpm Efficiency Factor for Pipe Diameter O e 0 o o J z (from detector efficiency determination)
d 0
8 No cm2 Is the MDCShh, acceptable?
(if no, adjust sample caunt time and recalculate MDCR,,bJ Comments:
Technician Signature Y V
Pipe Interior Radiological Suwey 3
Package Page 1 of, Page 1
'v Pipe Interior Radiological Suwey Form (Continuation Form)
BSI/LVSPipeCrawler-002 Revision 4 Date:
2-F?-'-06 n
Pipe ID#: ~j \\qi (-lfARbc.r) Pipe Diameter: 4 Access Point Area:
~ T - I C (d
Building:
c$
Elevation: - 2 7
System: RF-2b j+o=
~
c
~
o
~
4
,J, Page 2
BSVLVSPipeCrawler-002 Revision 5 Pipe Interior Radiological Survey Form From the Daily Pipe Survey Detector Control Form for the Selected Detector Background Value b 7 cpm
- MDCL, 8*&
cPm 44
( h m detector efficiency determination)
Efficiericy Factor for Pipe Diameter
- 0. 000 2 3 \\3 dpm/
\\m 2
MDCstatic an Is the MDCStatic acceptable?
No (if no, adjust sample count time and recalculate MDCR,,,)
Comenls: w9 5
Date:
/I 15 (77 Time:
/Y lo Pipe ID#: P
~
Q Pipe Diameter:
Y "
Access Point Area: -25 Building: &! fla.
Elevation:
System:
Im-lr\\l Type of Survey Investigation P
aracterization Final Survey Other J Gross C06O Cs Detector ID# 1 Sled ID#
4 - 5 b 1
io f Detector Cal Date:
16 &r 07 Detector Cal Due Date:
- 11. OCT 6
//. zL4-07 Technician Signature Instrument:
Pipe Interior Radiological Survey Instrument ID #:
REFERENCE COPY 0 m43z Instrument Cal Date:
1 (o 07 Instrument Cal Due Date:
b
- 08.
Package Page 1 of -
Z, Page 1
SECTION 7 ATTACHMENT 3 1
PAGE(S)
DQA Cheek Sheet Design #
RBDL-2(Rx-147)
Revision #
Original Survey Unit #
RBDL-2(Rx-147)
Prellmlnary Data Review'
- 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?
X
- 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 embeddedlburied piplng 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 tne instrumentat~on MDC for volumetric measurements and smear analysis c 10% DCGLvv 7 X
6 Were the MDCs and assum~tions used to develop them appropriate for the instruments and techniques I I
used to perform the survey?
A
- 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 "Special Methods" for data collechon properly appl~ed for the sulvey unit under review?
X 9
Is the data set comprised of qualified measurement results collected in accordance with the survey design, w h i i accurately refleds the rad~ological status of the faal~ty?
X Graphical Data Review 1
Has a posting pld 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)?
1 x 1 I
- 2.
Is the mean of the sample data < DCGLw?
/
x I
I
- 3.
If elevated areas have oeen ldentlfied by scans andlor sampling, is the average actlvlty in each elevated area < DCGL~MC rC.ass I),
c DCGLW (Class 2). or <0.5 DCGLw (Class 3)?
X
..........L.-
4 Is tne resdd of the Elevated Measurements rest c 1.07 X
- 5. Is the resdtt of tne statistical test (S+ for Sign Test or W, for WRS Test) > the critical value?
X Comments:
Page 1 of 1
SECTION 7 ATTACHMENT 4 1 DISC