ML072850766
| ML072850766 | |
| Person / Time | |
|---|---|
| Site: | Plum Brook |
| Issue date: | 08/09/2007 |
| From: | Peecook K US National Aeronautics & Space Admin (NASA), John H. Glenn Research Ctr at Lewis Field |
| To: | Snell W NRC/RGN-III/DNMS/DB |
| References | |
| Download: ML072850766 (365) | |
Text
National Aeronautics and Space Administ ration John H. Glenn Research Center Lewis Field Plum Brook Station Sandusky, OH 44870 August 9,2007 Reply I O Attn of QD U.S. NRC Region I11 Mr. William G. Snell, RIII/DNMS/DB 2443 Warrenville Road Suite 2 10 Lisle, IL 60532-4352
Subject:
Submittal of Embedded Pipe Survey Unit Release Records, Plum Brook Reactor Facility, License No. TR-3, Docket No. 50-30, and License No. R-93, Docket No, 50- 185
Dear Mr. Snell:
Enclosed for your review and assessment are copies of the following completed embedded pipe survey unit release records:
Survey Unit Release Record EP- 1.13 Survey Unit Release Record EP-Rx 127 Survey Unit Release Record EP- 1.14 Survey Unit Release Record EP-Rx 148 Survey Unit Release Record EP- 1.41 Survey Unit Release Record EP-Rx 152 Survey Unit Release Record EP- 1.43 Survey Unit Release Record EP-Rx 157 Survey Unit Release Record EP- 1.93 Survey Unit Release Record EP- 1.31 Survey Unit Release Record EP- HPT 102 Survey Unit Release Record EP- 1.33 Survey Unit Release Record EP-Rx 139 Survey Unit Release Record EP 1.82 Survey Unit Release Record EP-Rx 151 Survey Unit Release Record EP-Rx 150 Survey Unit Release Record EP-Rx 162 Survey Unit Release Record EP-Rx 160 Survey Unit Release Record EP-Rx 163 Survey Unit Release Record EP-Rx 204 Survey Unit Release Record EP- I .37 Survey Unit Release Record EP-Rx 207 Survey Unit Release Record EP- 1.81 Survey Unit Release Record EP-Rx 208 As discussed during your on site inspection on June 25 through June 27, 2007, we will periodically submit the completed survey unit release records for your inspection. Further, as discussed at the exit meeting, it is our intention to begin grouting of the embedded piping that has been shown by the Final Status Survey to meet the dose criteria of Subpart E, Section 20.1402, 10 CFR Part 20.
RECEIVED AUG 1 0 2001,
2 If you have no issues with the records under this submittal, we will begin the grouting process on August 20,2007.
Should you have any questions or need additional information, please contact Mr. William Stoner of my staff, NASA Plum Brook Station, 6100 Columbus Avenue, Sandusky, OH 44870, at (4 19) 62 1- 3349, or Mr. John Thomas of my staff, NASA Plum Brook Station, 6100 Columbus Avenue, Sandusky, OH 44870, at (419) 621- 3357.
Sincerely, Keith M. Peecook Decommissioning Program Manager
Survey Unit Release Record Design ## EP-1.13 1 Revision ## 1 Original 1 Page 1 of 3 Survey Unit #(s) 1.13
- 1) Embedded Pipe (EP) Survey Unit 1.13 meets the definition of embedded pipe for Plum Brook Reactor Facility (PBRF).
- 2) EP 1.13 is a Class 1, Group 1 survey unit as per the PBRF Final Status Survey Plan (FSSP) and Technical Basis Document (TBD)-06-004.
- 3) Surveys in EP 1.13 were performed using a scintillation detector optimized to measure gamma energies representative of CO-60. Sample #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 Methodsand the survey design used in the acquisition of survey measurements.
- 5) Instrument efficiency determinations are developed in accordance with the BSVLVS-002, WEP 05-006, these determinations are appropriate for the types of radiation involved and the media being surveyed.
--
I FSS Design # EP 1.13 I Revision # Original I Survey Unit: 1.13 I 1.o History/Description 1.1 The subject pipe is the 2 drain line for the 24 Rx Coolant return loop piping. The function of this piping was to convey water from the coolant loop to the sump in the sub pile room corridor on the -47.
1.2 EP 1.13 consists of 2 diameter piping that is approximately 39 feet in length and has three elbows from 45 to 90.
2.0 Survey Design Information 2.1 EP 1.13 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 39 survey measurements.
2.3 Surface area for the 2 ID piping is 486 cm2for each foot of piping, corresponding to a total 2 ID piping surface area of 18,971 cm2(1.9 m2) for the entire length of (approximately 39) of 2 piping.
3.0 Survey Unit Measurement Locations/Data 3.1 Pipe intenor 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 Level (DCGL) for radionuclide specific EP that corresponds to the 1 mrern/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 1.13 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 1 FSS Design # EP 1.13 Revision # Ori@
I Page 3 of 3 5.5 Statistical Summary Table 2
Statistical Parameter Pipe I Total Number of Survey Measurements I 39 I Number of Measurements >MDC 5 Number of Measurements Above 50% of DCGL 0 Number of Measurements Above DCGL 0 I Mean 10.0224 I I Median I 0.0184 1 Standard Deviation 0.01 35 Maximum 0.0797 Minimum I 0.0065 I 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 1.13 to be less than 1 mredyr. The dose contribution is estimated to be 0.0224 mredyr based on the average of the actual gross counts measured.
7.0 Attachments Attachment 1 - BSI EPBP Survey Report Attachment 2 - Pipe Interior Radioiogical Survey Form Attachment 3 - DQA Worksheet Attachment 4 - EP 1.13 SURR & Spreadsheet Disc
SECTION 7 ATTACHMENT 1 3 PAGE(S)
BSI EP/BP SURVEY REPORT 159#238367/nosled I
COMMENTS:
ACTIVIlY VALUES NOT BACKGROUNDCORRECTED.
RP Engineer I Date 8 ) 7-13-97 711312007
EP 1.13 2" Pipe TBD 06-004 Group I I I C060 activity Co60 activity Cs-I 37 activity Eu-I 52 activlty Eu-164 activity Nb-84 activity Ag108m actlviiy (dpmllOOern2) (dpmllOOcrn2) (dpmllWcrn2) (dpm1100cm2) (dpm1100cm2) (dptn/IOOm2)
(total dpm) 39 25 25 0.021
- 25 0.021 25 21 39 32 0.028 21 0.018 18 0.015 47 39 21 18 18 29 93 a
15 30 1s le 2E 5:
3 4%
l!
2:
3(
I!
.__ l!
I l!
1 of2
EP 1.13 2" Pipe TBD 06-004 Group I
-
Cos0 actlvlty C060 actlvlty Cs-137 actlvlty Eu-162 actlvfty Eu-154 advlty Nb-94 activity Ag-108m activlty gcpm ncpm (totaldpm) (dpm1100cm2) (dpmllOOcm2) (dpm1100cm2) (dpm1100cm2) 1 (dpm1100cm2) (dpml100cm2)
Unity I
I 3 - 3 7,895 _-__1,623 ____
409 I
1 47 I
I 11
-0.01(
4 4 10,526 2,164 2.053 546j 63 15 0.01:
3 3- 7,895 1,623
- 409 47 11 0.01(
2 2 __ 5,263 1,082 1.026 273 32 8 0.ON 3 3 7,895 1,623 409 47 11 O.Ol(
_-
4 4 __10,526
-
2,164 __- 546 63 15 0.01:
10 26,316 5,410 5,132 158 38 0.03; 1,364
-
10.. - _-_
I
__
I I
MEAN 0.02:
I I
MEDIAN 0.011 STD DEV 0.01:
!I MAX 0.081 MIN -0.oa 2of2
SECTION 7 ATTACHMENT 2 6 PAGE(S)
I BSILVSPipeCrawler-002 Re\.ision 4 Pipe Interior Radiological Survey Form Date: 2 - r Z -a G Time: / o s 27 Pipe ID#: / ./J Pipe Diameter: <,'
Building: c,c Elevation: -Y r
- ,d Type of Survey Investigation Characterization Final Survey A "wPp/t' Other Lop Gross Co60 J cs 1
Detector ID# / Sled ID# V'f-62 Zi?,70/ 1 1t/
Detector Cal Date: //-f7-ug Detector Cal Due Date: I/-/ 7 - (3 G Instrument: 2 3J - 4 I Instrument ID #: ur2z3 Instrument Cal Date: //-[ 7 -0J- Instrument Cal Due Date: 1 1 4 7-d L From the Daily Pipe Survey Detector Control Form for the Selected Detector Background Value Lf( 4 cpm MDCRS,,, i & b cpm Efficiency Factor for Pipe Diameter 0 t WZ, 2 (from detector efficiency determination)
MDCSWlC bb3b dPd \DD cm2 Is the MDCrahCacceptable? @ N o (if no, zd~usts a i i l e comlt time and recalculate IvIDCb,,)
I I\ u
.. .
LY Technician Signature Pipe Interior Radiological Survey Position
Feet into Pipe from Opening Count Time (min)
Gross Coullts Gross cpm Net cprn dprd100cm' 1 1 \ I // r ,r- ala !a 2 7 3 7 3 .F I 3 3 z 3 t . r - I 4 "i 1 7 t .>
5 ? 7 ,31 5- I 6 (a z b 3 7
8 0 z I t s *3 I 7 el y l 9 9 z (Q I I 10 I IO 2 2 4- J d s>
Package Page 1 of - 3 REFERENCE COPY
- Attac'ment 3, Page 1
BSb'LVSPipeCrawler-002 Revision 4 Pipe Interior Radiological Survey Form (Continuation Form)
Building: n .fl Elevation:
Package Page 2of 2 0 REFERENCE COPY Attachment 3, Page 2
7"'
I m
REFERENCE COPY
BSILVSPipeCrawler-002 Revision 5 Pipe Interior Radiological Survey Form Date: 6-17-6') Time: \I95 Pipe ID#:
Building:
.
\ \3 C ad Pipe Diameter:
Elevation: 4
'XI' Access Point Area:
System:
5& QLk J
QUddwL-Type of Survey Investigation Characterization Final Survey % Other Gross Co60 d cs Detector ID# / Sled ID# 4 q-15 9 /x3s3L7 / & SLA Detector Cal Date: (n-al- 0 b Detector Cal Due Date: 6 - &\- 07 Instrument: Instrument ID #: \E;? o?"!
Instrument Cal Date: 1- It- o] Instrument Cal Due Date: \ - \ \- d 8 From the Daily Pipe Survey Detector Control Form for the Selected Detector Background Value 1 cpm MDCRSMiiC 7 A CPm Efficiency Factor for Pipe Diameter ok0 0 038 @om detector efficiency determination)
(ifno, adjust sanple count tine and recalculate b D C L h i )
Technician Signature Q->L a, Pipe Interior Radiological Survey Package Page 1 o f 3 REFERENCECOPY Attachment 3, Page 1
B S I/LVSPipeCrawler-002 Revision 5 Pipe Interior Radiological Survey Form (Continuation Form)
Date: xT - 03 Pipe ID#: \ ,13 Pipe Diameter: xt Access Point Area: sb!! fi\u Building: c Md Elevation: 43. System:
Package Page 2 of%
REFERENCE COPY Attachment 3, Page 2
SECTION 7 ATTACHMENT 3 PAGE(S)
Design # EP 1.13 Revision # Original Survey Unit # EP 1.13 Answers to the following questions should be fully documented in the Survey Unit Release Record Yes No NIA I. Have surveys been performed in accordance with survey instructionsin the Survey Design?
- 2. Is the instrumentation MDC for strudure static measurements below the DCGLw for Class 1 and 2 survey units, or below 0.5 DCGLWfor Class 3 survey units?
cz
- 3. Is the instrumentation MDC for embeddedlburied 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 static measurements or soil samples addressed in the survey design?
- 5. Was the instrumentation MDC for volumetric measurements and smear analysis 10% DCGLW?
- 6. Were the MDCs and assumptions used to develop them appropriate for the instruments and techniques used to perfon the survey?
- 7. Were the survey methods used to collect data proper for the types of radiation involved and for the X I I
~~
media beina SUNeved? X I
- 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 radiologicalstatus 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? 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 < DCGLEM~ (Class I), DCGLw (Class 21, or ~ 0 . DCGLW 5 (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 c r i t i i l value? X e
Form CS-09/2 Rev 0 Page 1 of 1
i SECTION 7 ATTACHMENT 4 1 DISC
!
Survey Unit Release Record Design # EP-1.14 1 Revision# 1 Original 1 Page 1 of 3 Survey Unit #(s) 1.14
- 1) Embedded Pipe (EP) Survey Unit 1.14 meets the definition of embedded pipe for Plum Brook Reactor Facility (PBRF).
- 2) EP 1.14 is a Class 1, Group 1 survey unit as per the PBRF Final Status Survey Plan (FSSP) and Technical Basis Document (TBD)-06-004.
- 3) Surveys in EP I . 14 were performed using a scintillation detector optimized to measure gamma energies representative of CO-60. Sample #EP 3-9 from Survey Request (SR)-13 was referenced for this decision.
- 4) Survey Instructions for this survey unit are incorporated into and performed in accordance with (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 1.14 Revision # Original Page 2 of 3 1.o History/Description 1.1 The subject pipe is the 2 drain line for the 24 Rx Coolant return loop piping. The fimction of this piping was to convey water from the coolant loop to the sump in the sub pile room corridor on the -47 foot elevation. .
1.2 EP 1.14 consists of 2 diameter piping that is approximately 35 feet in length and has three elbows from 45 to 90.
2.0 Survey Design Information 2.1 EP I . 14 was surveyed IAW Procedure #BSL/LVS-002.
2.2 1W/o of the 2 ID pipe was accessible for survey. The accessible 2 ID pipe was surveyed by static measurement at one foot increments, for a total of 35 survey measurements.
2.3 Surface area for the 2 ID piping is 486 cm2for each foot of piping, corresponding to a total 2 ID piping surface area of 1 7,025 cm2(1.7 m2) for the entire length of (approximately 35) of 2 piping.
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 InvestigationslRedts 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 @CGL) 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 constitutedby EP 1.14 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 1.14 I Revision ## Original Page 3 of 3 Survey Unit: 1.14 5.5 Statistical Summary Table 2
Statistical Parameter Pipe
~ ~~
Total Number of Survey Measurements 35 Number of Measurements >MDC 12 Number of Measurements Above 50% of DCGL 0 Number of Measurements Above DCGL 0 I Mean 10.0391 I I- I 0.03071
~
Median I Standard Deviation I 0.0519 I I
~
Minimum 10.0032 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 1.14 to be less than 1 mredyr. The dose contribution is estimated to be 0.0391 mredyr based on the average of the actual gross counts measured.
7.0 Attachments Attachment 1 - BSI EPBP Survey Report Attachment 2 - Pipe Interior Radiological Survey Form Attachment 3 - DQA Worksheet Attachment 4 - EP 1.14 SURR & Spreadsheet Disc
I SECTION 7 ATTACHMENT 1 3 PAGE(S)
BSI EP/BP SURVEY REPORT
~
Pipe ID 1.14 Survey Location I Primary Coolant Drain 4 2 2/22/2006, Survey Date 2350-1 # 2122231189094 612612007 Sunrey Time Pipe Size 0851,1600 2
I/ DetectorSled #
Detector Efficiency 44-62#2127011121 44-159#238367/nosled 0.000U0.00038 DCGL m m m a m z i 2.41E 9 5 Plp -Inml=-d w- orurrvm CmZ) 486
~ Inmrponm
- rr p f 1
1.7 Field BKG ~ c p m ~ 4.411.3 Routine Survev X Field MDCR 10.616.9 survey I 11 Nominal YDC IdPnnmCmt) 663615314
~~
Number of Measurements >MDC 12 Number of Measurements Above 50% DCGL 0 Number of Measurements Above DCGL 0 Mean 0.0391 Median I 0.0307 Standard Deviation 0.0519 Maximum I 0.3227 Minimum 0.W32 DEBRAUX, FOWLER Survey Technician(s) 1
- OMMENTS:
CTlVlTY VALUES NOT BACKGROUND CORRECTED.
I RP Engineer I Date
/7- /pa7
EP 1.14 2" Pipe TBD 06-004 Group 1
-
Co-60 activity C0-60 activity Cs-137 activity Nb-94 activity Ag-108111 activity ncpm (total dpm) (dpm1100cm2) (dpmllOOcm2) (dpm1100crn2) (dpmllOOcm2)
Unity
~~
25,000 5,139 ___- 4,875 1,296 150
- 0.031 17,500 _ _ _3,598 _ . _ ~ ___-3,413 907
- _ ~
105
. -
0.021 15,000
_ _ _ - ~ ____.-
3,084 2,925 778 90 -___ -_0.0lE
_
_____-- 25,000 5,139
__ -
4,875 1,296 150 36 0.031 3 -.____ 15,006 __-____ 3,084 2,925 778 90 21 O.Olf 3.5 17,500 3,598 3.413 907 105 25 0.021
-Lgw
- _ _ ~ ~~- __---
.~
3
-. ~
15,000 _ ~
3,084
___
_ _ _ _ ~_ ~ 122 90 21 0.01 E
- 2 -- 10,000 2,056 - _ _ 81 _ ~ 1.950 518 60 14 0.012 7.5 37,500 _____ 7,709 _- 306 -
225 54 0.04E 6 -___-- 30,000 -___- 6,167 244 __ 1,555 18 0 43 0.037 5.5
.-
27,500 _c_-
5,653 224 1,426 165 39 0.034 6 30,000 _____ 6,167 _- 244 1,555 180 43 0.037
__- 4.5 22.500-
- -
4,625 ia3 . --
4.388 1.166
-,--- 135 32 0.02f 5 -____-- 25,000 5,139
__ 4,875 1,296 150 36 0.031 4.5 22.500 4.625
--___ 4.388
. - 1.166
, - 135 32
-~ 0.02f
_-
_c-351000
- ~ _ _ _
__ 7: 195 285 . 6,825 1,814 210 50 0.04:
-~-__ 18.421 3,787 - 150 3,592 955 111 26 0.02:
-- __
- ---- 39,474 _ _ _ _ _ ~8,115 322 -_ 7,698 2,046 57 0.04
---
- ~28.947 - - -- - ~ 5,951 _ - 236 5,645 1,501 41 0.03:
151789 -__-3,246 ___ - _ _ _ _ - ~ 129 3,079 819 23 0.01E 14 _ _ ~ 36,842
_ _ _ _- 7,574
_- -- 300 -
- 7,185 1,910 22 1 --____ 53 0.04:
100 -___ 263,158 - 54,099 -.-____ 2,144 ___- 51,318 13,642 1,579 377 -
0.32:
- ~
8 ____- --
21,053 4,328 172
-.
4,105 1,091
-__.
126 ____--___ 30 0.02 16 42,105 8,656 - 343 8.211 2.183 253 60 0.05; 7 18,421 - 3,787 150 111 - ~ _26__ 0.02:
l o _26,318 _ ..
31,579 _
5,410 -~
6,492 214 257 5.132 6,158 1.364 1,637 158 189 38 45
-_0.032 0.03s
___---~ - ~ _ _
~- -.
- .~
15,789 - 3,246 ~- 129 3,079 819 ~ 95
_ _ 23 --0.01I
.a
~
__~-.-
26,316
_____..~_ __ - 5,410 - _ _ _ _
214 5.132 1 158
_. 38 -0.03;
__
6 15.789 _._____3.246 129 95 23 _ 0.01:
-
27 - 141607 -. 579 13.856 426 102 0.08i 4 2,164 86 2,053 I 546 63 15 - 0.01 I 1 of2
EP 1.14 2" Pipe TBD 06-004 Group 1
-
Co-60 activity C0-60 acuvity Cs-137 activity Eu-162 activity Eu-164 actlvity Nb-94 actMty Ag-1O8m acffvity ncpm (total dpm) (dpm1100cm2) (dpm1100cm2) (dpmll00cm2) (dpmllOOcm2)
Un-Hy (dpmllOOcm2) (dpmllOOcm2) 21 --__.___
513 16 4
-0.002
____- _ - 429 10,264 316 - ~
75 0.065
- ~
-
10.526 86 2.053 63 15 0.013
.-
MEAN 0.035
--t- MEDIAN 3TD DEV 0.031 0.052 MAX 0.329 MlN -0.00:
2of2
SECTION 7 ATTACHMENT 2 6 PAGE(S)
! B SVLVSPipeCrawler-002 Revision 4 Pipe Interior Radiological Survey Form T p e of Survey Investigation Characterization Final Survey ?( Other 1 Gross Co60 J cs Detector Ib#/ Sled ID# 97-62-* u 7 7 o/ f I L f Detector Cal Date: //-I 7-c9C Detector Cd Due Date: //-/7-06 Instrument: ?a S o 4 Instrument ID #: i%LZZJ Instrument Cal Date: 4 (-17 -d-J Instrument Cal Due Date: //7 7-0c From the Daily Pipe Survey Detector Co~trolForm for the Selected Detector Background Value 4!* 4 cpm MDCRS,,, 10% C cpm Efficiency Factor for Pipe Diameter dl moa (from detector efficiency determination) mcstatlc bb36 dpd LVD Cm2 Is the h4DCSbbc acceptable? No (ifno, adjust sample count time mil recalculate MI-,)
/
Technician Signature Pipe Interior Radiological Survey Position
Feet into Pipe from Opening Count Time (min)
Gross counts Gross cpm Net cpm dpm/100cm2 I I
1 1 7 tO -r //3 I 2 2 7, 7 3 >
-t h 1 3 c z (0 3 4 4 2. 1 0 I I 5 s 2 h 6 2 31s 7 7 2, c 2 8 2 y 9 9 z d 7 s I 10 /E z /A cl, .I/
Package Page 1 of 2 REFERENCE COPY Attachment 3, Page 1
I BSbLVSPipeCrawler-002 Revision 3 Pipe Interior Radiological Survey Form (Continuation Form)
Date:
Pipe ID#: Pipe Diameter: Access Point Area:
Building: Elevation: System:
Position f!
Feet into Pipe fi-om Opening Count Time (min)
Gross Counts Gross cpm Net cpm dpm/100cm2 B .
1 Pi // 3 // A5 la, Y1@
fa 12- 2 /. P (0 I 13 /,-? 9- 9 45
/d /4 a ,b C- 5-
/c 1- c a ? 4 4
.7 I
I& /G 2 II./
, 4, d f
Y
\ I I
Package Page 2of 2 n
IREFERENCE COPY I Attachment 3, Page 2
.
I b
.-
. QL 7
f I-1 REFERENCECOPY
'I BSI/LVSPipeCrawler-O02 Revision 5 Pipe Interior Radiological Survey Form Date: c-m -b> Time: \\\9 PipeD#: I.I Pipe Diameter: Access Point Area: S H ~ e,\+&,
Building: GU Elevation: -4 a' System:
N n n Type of Survey Investigation Characterization Final Survey ,?(- Other J Gross Co60 \f cs -
Detector ID# / Sled ID# 44 / 2283 d 7 / d 5 Detector Cal Date: c- I\- 06 Detector Cal Due Date: c a-l-97 Instrument: 4 Instnunent ID #: I8elOS-l Instrument Cal Date: I- I 0 c) Instrument Cal Due Date: I 4 1 - 0 6, From the Daily Pipe Sumey Detector Control Form for the Selected Detector BackgroundValue \. b cpm MDCRskh, Y,.t CPm Efficiency Factor for Pipe Diameter 0 'D 003 8 0 (fiom detector efficiency determination)
MDcstatic 5314 IO73 cm2 Is the MDCsuticacceptable? No (if no, adjust sample count time and recalculate MDCR,,,,)
Comments: 34 ~ , b\ o n F8-3-9 \007! L+&-,
c4\ L 14 LJ t4L:n \ ~ m , l l t t k 6 s md n e , t d I , w f i -,
Technician Signature Pipe Interior Radiological Survey 0
Package Page 1 o f 3 REFERENCE COPY Attachment 3, Page 1
I i BS VLVSPipeCrawler-002 Revision 5 Pipe Interior Radiological Survey Form (Continuation Form)
Date: c-27 07 Pipe ID#: 'Lj\ Access Point Area:
Building: Pipeexa;:: System:
Attachment 3, Page 2
SECTION 7 ATTACHMENT 3 I PAGE(S)
Design # EP 1.14 Revision# Original Survey Unit# I EP 1.14 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.
3.
Is the instrumentation MDC for structure static measurements below the DCGLw for Class 1 and 2 survey units, or below 0.5 DCGLw for Class 3 survey units?
Is the instrumentation MDC for embeddedhuried piping static measurements below the DCGLw ?
I X lx
- 4. Was the instrumentation MDC for structure scan measurements, soil scan measurements, and 5.
embeddedhuried piping scan measurements below the DCGLw, or, if not, was the need for additional static measurements or soil samples addressed in the survey design?
Was the instrumentation MDC for volumetric measurements and smear analysis z 10% DCGLw ? I 1
1 I X
X 6.Were the MDCs and assumptions used to develop them appropriate for the instruments and techniques used to Derform the survev?
- 7. Were the survey methods used to collect data proper for the types of radiation involved and for the
~
media beina surveved?
~~ ~
jxj I
- 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?
- 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 Data Analysis
- 1. Are all sample measurements below the DCGLw (Class 1 & Z ) , or 0.5 DCGLW(Class 3)? X
- 2. Is the mean of the sample data < DCGLw? X
- 3. If elevated areas have been identified by scans and/or sampling, is the average activity in each X elevated area < DCGLEMC(Class 1). .C 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) 2 the critical value? X FSSCharadedzation Engineer (prinUsign) Date 7 - 1 7 4 7 F S S / Characterization Meneger (printlsign) Date 7hfl/07 Page 1 of 1
SECTION 7 ATTACHMENT 4 1 DISC
Survey Unit Release Record Design # EP-1.41 1 Revision# 1 Original 1 Page 1 of 3 Survey Unit #(s) 1.41
- 1) Embedded Pipe (EP) Survey Unit 1.41 meets the definition of embedded pipe for Plum Brook Reactor Facility (PBRF).
- 2) EP 1.41 is a Class 1, Group 2 survey unit as per the PBRF Final Status Survey Plan (FSSP) and Technical Basis Document (TBD)-06-004.
- 3) Surveys in EP 1.41 were performed using a scintillation detector optimized to measure gamma energies representative of CO-60. Sample #EP 2-2 from Survey Request (SR)-13 was referenced for this decision.
- 4) Survey Instructions for this survey unit are incorporated into and performed in accordance with (IAW) the Babcock Services Incorporated (BSI)/LVS-002, Work Execution Package (WEP)05-006. Survey instructions described in this 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 Date:
FSS/Characterization Manager CS-09/1 0 COPY
-
FSS Design # EP 1.41 Revision # Original Page 2 of 3 1.0 HistoxyDescription 1.1 The subject pipe system is the 6 inch header from the hot drain system service ring to the drain trench on the Rx building -25 foot elevation.
1.2 The pipe section has one 90 degree along its 45 foot length.
2.0 Survey Design Information 2.1 EP 1.41 was surveyed IAW Procedure #BSYLVS-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 45 survey measurements.
2.3 Surfixe area for the 6" ID piping is 1,459 cm2for each foot of piping, corresponding to a total 6" ID piping surface area of 65,655 cm2(6.6 m2) for the entire length of (approximately 45') of 6" piping..
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 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 1.41 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 1.41 Revision # Original Page 3 of 3 5.5 Statistical Summary Table Statistical Parameter Total Number of Survey Measurements 45 Number of Measurements>MOC 44 Number of MeasurementsAbove 50% of DCGL 0 Number of Measurements Above DCGL l o l I Mean Io.0192I I Median 10.01721 Standard Deviation 0.0126 Maximum 0.0876 6.0 Documentation of evaluations pertaining io compliance with the unrestricted use limit of 25 m r 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 1.41 to be less than 1 mredyr. The dose contribution is estimated to be 0.019 mredyr based on the average of the actual gross counts measured.
7.0 Attachments Attachment 1 - BSI EPBP Survey Report Attachment 2 - Pipe Interior Radiological Survey Form Attachment 3 - DQA Worksheet Attachment 4 - EP 1.41 SURR & Spreadsheet Disc
SECTION 7 ATTACHlMENT 1 3 PAGEIS)
Pipe ID 1.44 Survey Location Quad B Trench Drain Survey Date 02-Apr-07 2350-1 # 189094 Survey Time 13:27 Detector-Sled # lMG1 LVS-11107 rpipI eshI I.
I 1
I 6" Detector Efficiency 0.00038 DCGL (dpnn-1 2.41E 9 5 1459 Field BKG-) 3.6 I Routinesurvey I X II I 9.5 Number of Measurements >MDC 44 Number of Measurements Above 50% DCGL 0 Number of Measurements Above DCGL 0 Mean 0.0192 Median 0.0172 Maximum 0.0876 Minimum 0.0086 I I NOT BACKGROUND CORRECTED RP Engineer I Date D& 7d3-07
EP 1.41 1
6" Pipe TBD 06-004 Group 2 C0-60 activlty C0-60 activity Cs-137 activity Eu-152 acUvity Eu-I 54 activity Nb-94 aetivity Ag-108111activity gcpm ncpm (total dpm) (dpml100cm2) (dpmlIOOcm2) (dpmlIOOcm2) (dpd100cm2) (dpmll OOcm2) (dpmll OOcm2) 3
_- 1,496 24 17 1 83 0.013 2,245 36 25 2 _- 125 1,683 27 19 _____- 2 93 1,309 21 __15 1 73 2,151 34 24 2 119
_-
~ 2,058_ _ 33 ~ 23
- 2 114 2,899 46 33 3 161
_- 2,245 36 25
_- 2 125
-_ 1,871 30 21 2 104 2,058 33 23
- 2 114 2,619 42 30
- 2 145 2,058 33 23
_- 2 114
- 1,871 30 21 2 104
_- 2,245 36 25 2 125 1,964 -~ 31 ~~
22 2 109
_ _ _ 2,434 _ ~ 39 _-27 2 135 1,305
_- 21 15
- 1 73 0.01 1 1,305 21 15 1 73 0.01 1 1,w 3 22 2 109 0.016 2,052 3 23 ~
2 114 0.017 1,59( 25 ia 1 88 0.013 1,4% 24 17 1 83 -3 0.01 ---
2,52! 4c 25 ~~
4 --
140 0.021 2,15' 34 24 4 0.018 c
31 1 0.016 3( L 0.016
~~
1 0.009 I It I 1: 0.009 45 3; 3 156 0.023 24 1; I 1 83
- 0.013 28 20 1 2 99 0.015 30 21 1 2 104 0.016 1of2
SECTION 7 ATTACHMENT 2 3 PAGE(S)
BSVLVSPipeCrawler-002 Revision 4 Pipe Interior Radiological Survey Form Date: 4/2/07 Time: 1327 Pipe ID#: 114I Pipe Diameter: 6 Access Point Area: 7pElUCt-l Building: a Elevation: -27 System:
QUM /&- !h Type of Survey Gross Investigation Co60 Finalsurvey cs x Other /
Detector ID# I Sled ID# ( f l G / LVS- / 1 1 Detector Cal Date: , / t i /07 Detector Cal Due Date: t/rr/o8 I
Instrument: z3~0-f Instrument ID #: / s90 ?+
Instrument Cal Date: l f i , /07 Instrument Cal Due Date: h / O &
From the Daily Pipe Survey Detector Control Form for the Selected Detector Background Value 3.6 cpm MDCRStiltiC 485 cpm Efficiency Factor for Pipe Diameter 0 , 0 0 03 % (from detector efficiency determination)
~fDC,tatlc ZDbb Is the I b C s t a h acceptable?
c a dpd No cm (ifno, adjust sample count time and recalculate MDCR,)
Technician Signature Pipe Interior Radiological Survey Package Page 1 of-3 REFERENCE COPY Attachment 3, Page 1
BSI/LVSPipeCrawler-O02 Revision 4 Pipe Interior Radiological Survey Form (Continuation Form)
Date:
Pipe ID#: Pipe l b n e t e r : 6 ', Access Point Area: 7'flEIVc-d Building:? '
Elevation:
I- -27 System: QUAD R &-ow a REFERENCE COPY Package Page -2 of 2 Attachment 3, Page 2
I I SECTION 7 ATTACHMENT 3 PAGE(S)
DQA Check Sheet Design # I EP 1.41 I Revision # I Original I Survey Unit #
- ~
1 ~ ~~~
EP 1.41
-~ ~
Preliminary Data Review' Answers to the following questions should be fully documented in the Survey Unit Release Record Yes No N,A
- 1. Have surveys been performed in accordancewith survey instructions in the Survey Design? X
- 2. Is the instrumentation 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 embeddedlburied piping static measurements below the DCGLw ? X
- 4. Was the instrumentation MDC for structure Scan measurements, soil Scan measurements, and embeddedlburied piping scan measurementsbelow 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 survey3
- 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 resub dMed in accordance with the survey X design, which accurately reflects the radiological status of the facillty3 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 Analysls
- 1. Are all sample measurementsbelow 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 identified by scans andor sampling, is the average activity in each elevated area DCGLEMC X (Class l), < DCGLW(Class 2), or e0.5 DCGLW(Class 3)?
- 4. Is the result of the Elevated MeasurementsTest 1.O? X I
~
- 5. Is the result of the statisticaltest (S+ for Sign Test or W, for WRS Test) 2 the critical value? X 2omments:
Form CS-091'2 Rev 0 Page 1 of I
SECTION 7 ATTACHMENT 4 1 DISC
Survey Unit Release Record Design # EP-1.43 Revision # Original Page 1 of 3 Survey Unit #(s)
- 1) Embedded Pipe (EP) Survey Unit 1.43 meets the definition of embedded pipe for Plum Brook Reactor Facility (PBRF).
- 2) EP 1.43 is a Class 1, Group 2 survey unit as per the PBRF Final Status Survey Plan (FSSP) and Technical Basis Document (TBD)-06-004.
- 3) Surveys in EP 1.43 were performed using a scintillation detector optimized to measure gamma energies representative of Co-60. Sample #EP 2-2 from Survey Request (SR)-13 was referenced for this decision.
- 4) Survey Instructions for this survey unit are incorporated into and performed in accordance with (IAW) the Babcock Services Incorporated (BSI)/LVS-002, Work Execution Package (WEP)05-006. Survey instructions described in this 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 Approval Signatures I Date:
1 FSS/CharacteMonEngineer I ,q,/ I 74-07 FSS/Charactdzation Manager cs-o9/1 0 COPY
-
FSS Design # EP 1.43 Revision # Original Page 2 of 3 Survey Unit: 1.43 1.0 Hi story/Description 1.1 The subject pipe system is the 6 inch return header from the cooling water service ring to the drain trench on the Rx building -25 foot elevation.
1.2 A vertical 90 degree elbow is 34 feet into the pipe section. The pipe is approximately 47 feet in length.
2.0 Survey Design Information 2.1 EP 1.43 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 47 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 68,573 cm2(6.9 m2) for the entire length of (approximately 47') of 6" 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 inredyr 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 1.43 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 1.43 Revision # Original Page 3 of 3 5.5 Statistical Summary Table I-Statistical Pammeter 1 Pipe Total Number of Survey Measurements 47 Number of Measurements >MDC 47 Number of Measurements Above 50% of DCGL 0 Number of Measurements Above DCGL 0 Mean 0.0177 Median 0.0172 Standard Deviation 0.0041 Maximum 0.0258 Minimum 0.0094 6.0 Documentation of evaluations pertaining to compliance with the unrestricted use limit of 25 llzfemjyT and dose contributions from Embedded Pipe and radionuclides contributing 10% in aggregate of the total dose for both structural scenarios and soils.
6.1 A review of the survey results has shown that the dose contribution for EP 1.43 to be less than 1 mredyr. The dose contribution is estimated to be 0.018 mredyr based on the average of the actual gross counts measured.
7.0 Attachments Attachment 1 - BSI EP/BP Survey Report Attachment 2 - Pipe Interior Radiological Survey Form Attachment 3 - DQA Worksheet Attachment 4 - SURR EP 1.43 & Spreadsheet Disc
_-
I SECTION 7 ATTACHMENT 1 3 PAGE@)
i ai&@
-_ - BSI EPIBP SURVEY REPORT Pipe ID I I.43 II Survey Location I Trench Service Ring Survey Date 02-Apr-07 I1 2350-1 #
I 189094 Detector-skd # 1MGl LVS-VI07 I
I I 1 L II I I I I PipeSke Debector Efficiency O.OOO38 I 6 Total Number of Survey Measurements 47 Number of Measurements *MDC 47 Number of MeasurementsAbove 50% DCGL 0 Number of MeasurementsAbove DCGL 0 Mean 0.0177 Median 0.0172 Standard Deviation 0.0041
~~
Maximum 1 0.0258 Minimum 0.0094 Stodc Survey Technician(8)
ZOMMENTS:
9CTMTY VALUES NOT BACKGROUND CORRECTED RP Engineer I Date 1 B C p u ?-/Po7
EP 1.43 6" Pipe TBD 06-004 Group 2 COM) activity Cs-137 activity Eu-1I 2 activity Eu-I 64 activity NbQ4activity Ag-1O8m activity gcpm ncpm (dpmllOOcm2) (dpmllOOcm2) (dpm1100cm2) (dpm1100cm2) (dpm1100cm2) (dpml100crn2) unw 28 28 5,050 2,619 - 42 I 30 2 145
-0.02; 20 20 ~~
- 3,607 1,871 30 -21 2 104 0.01C 27 ____ 27 711053 - 4,870 - 2,525 40 29 0.02' 20 2a
-_ 52,632 _-___ 3,607 _____ 1,871 30
__ 21 0.OlC 25 25 65,789 - 4,509 2 ,338 37 26 0.02(
20 2c 52,632 3,607 1,871 30 21
- O.Olf
__-26 2e 68,421 4,690 - 2,432 39 27 2 135 0.02(
52,632 3.607 1.871 30 21
- 2 104 O.Olf L o 15- 39,474 22 16 1, 78 0.01:
15 1E 39,474 -
22 16 1 78 0.01:
-- 17 17 44,737 25 18 1 88 0.01:
19 1: 50,000 34.27 1.777 -. 28 26 2 99 O.Ol!
18 1E 47,368 -
27
-. 19 2 93 O.OlA 23 2: 60,526 .-
2,151 34 24 2 119 0.011 19 _ _ 1E 50,066 1.777 28 20
- 2 99 O.Ot!
22 22 57,895 - 3,968 2,058 33 23 2 114 0.01;
- 22 22 57,895 - 3,968 2,058 33 23
__ 2 114 0.01:
29 2s 76,316 - 5@!-. 2,712 43 31
__ 3 151 0.02:
~. .
31 _ _ _31 81,579 - 5,591 2,899 ~-
46 33
__ 3 161 0.024 18 1E 47,368 ___ 3,247 1,683 27 19 2 93 0.014 12 1; 31,579 2,164 - 1,122 18 13
- 1 62 O.OO!
33 ____ 3: 86,842 - 5952 3,086 49 35
- 3 171 0.02(
25 2: 65,789 - 4,509 2,338 37 26 2 130 0.021
~ _ _
22 2: 57,895 3,968 2,058 33 23 2 114 0.01' 30 3( 78,947 - 5,411 - 2,806 45 32
-.
3- 156 0.02:
24 2r 63,158 -
4,329 - 2,245 36 25 2 125 O.Ol!
27 2; 71,053 - 4,870 2,525 40 29 2 140 0.02 29 2! 76,316 5,231 2,712 43 31 3 151 0.02:
-
21 2' 55,263 - 3,788 1,964 2 106 0.011 17 1; 44,737 3,066 1,590 1 8E 0.01 65,789 - 4,509 2,338 0.021 60.526 4,148 2,151 -0.011 1o f 2
EP 1.43 6" Pipe TBD 06-004 Group 2
- I
-
E E
I AQ-108m-CdK) activlty Cs-137 activity Eu-I52 actlvlty Eu-164 activity e! QcPm ncpm Unity 3 (dpm1100cm2) (dpm1100cm2) .. (dpm1100cm2) (dpm1100cm2) (dpn1100crnZ) 00 z
z Nb-gq-7 33 _14_ __~ 14 _-
36,842 21 15 1 73 0.01' 34 23 23 60,526 ____-.
~
4.148 _____ 34 24 2 119 0.01I
__-
29 25 - 76,316 5,231 2,712 43 31 3 151 0.02:
- 35 ___-
36 22 22 57,895 3,968 2,058 33 23 2 114 0.01;
-37 22 22 57,895 3,968 2,058 33 23 2 114 0.01; 50,000 ____- 3,427 _ _1,777
__ 28 20 2 99 0.01!
76,316 ____- 5,231 2,712
.~
43 31 3 151 0.02:
50,000 -___- 3,427 1,777 28 20 2 99 0.01!
71,053 4,870
__---
2,525 40 29
- 2 140 0.02' 36,842 2,525 1,309 15 1 73 0.01' 84,211 5,772 2,993 48 34 3 166 0.02!
73,684 5,050 2,619
____ 42 30 2 145 0.02:
63,158 _____ 4,329 2,245
-__
36 25 2 125 0.01!
2; 57,895 3,968 2,058 33 23 2 114 0.01' 42,105 2,886 1,496 24 17 1 83 0.01:
-
+---
-
MEAN 0.01I MEDIAN 0.01' STD DEV 0.00
-+---I MAX IMIN 0.021 0.00 20f2
SECTION 7 ATTACHMENT 2 4 PAGE(S)
I) 1 BSVLVSPipeCrawler-002 Revision 4 Pipe Interior Radiological Survey Form Date: 4(2/07 Time: a 0 U
Pipe ID#: I443 Pipe Diameter: Access Point Area:
Building: Elevation: -27' System:
Type of Survey Investigation Characterization Final Survey A, Other v Gross C06O V cs Detector ID# / Sled ID# /w,/ l-vs c 1 I io7 Detector Cal Date: L&,167 Detector Cal Due Date: Ill1 lo6 Instrument: 23m-/ Instrument ID #: /gq 69 4-Instrument Cal Date: 1 / 1 1 103 Instrument Cal Due Date: I I f ok I 1 From the Daily Pipe Survey Detector Control Form for the Selected Detector Background Value 3a 6 cpm MDC% tahc 9 s cpm Efficiency Factor for Pipe Diameter 0 0 0038 I (from detector efficiency determination) mcstatic 7% CP dpd \ cm2 Is the MDCSahcacceptable?
Comments:
,a No (if no, adjust sample count time and recalculate MDC%,,J Pipe Interior Radiological Survey Package Page 1 of&
0 REFERENCE COPY Attachment 3, Page 1
I I BWLVSPipeCrawler-002 Revision 4 Pipe Interior Radiological Survey Form (Continuation Form)
Package Page zof Ll-REFERENCE COPY Attachment 3, Page 2
BSYLVSPipeCrawler-002 Revision 4 Pipe Interior Radiological Survey Form (Continuation Form)
Date: +/z/a7 Pipe ID#: I t43 Pipe Diameter: 6 " Access Point Area: e Y
3 Package Page -of$
U REFERENCECOPY Attachment 3, Page 2
I SECTION 7 ATTACHMENT 3 I PAGE(S)
Design # EP 1.43 Revision # Original Survey Unit # EP 1.43 PreliminaryData Revlew Answers to the following questions should be fully documented in the Survey Unlt 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 1 and 2 X survey units, or below 0.5 DCGLw for Class 3 survey units?
- 3. Is the instrumentationMDC for embeddediburied piping static measurements below the DCGLw 7 X
- 4. Was the instrumentation MDC for structure scan measurements, soil scan measurements, and embeddediburiedpiping 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?
-~
- 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 beina surveved?
~
- 8. Were Special Methods for data collection properfy 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? 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
~~
- 1. Are all sample measurements below the DCGLw (Class 1 812), 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 sans andlor sampling, is the average activity in each X elevated area DCGLutc (Class l),DCGLW(Class 2), or ~ 0 . 5 DCGLw (Class 317
- 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
SECTION 7 ATTACHMENT 4 1 DISC
I I Survey Unit Release Record Design # EP 1.93 1 Revision# I Original I Page 1 of 3 Survey Unit #(s) 1.93
- 1) Embedded Pipe (EP) Survey Unit 1.93 meets the definition of embedded pipe for Plum Brook Reactor Facility (PBRF).
- 2) EP 1.93 is a Class 1, Group 3.2 survey unit as per the PBRF Final Status Survey Plan (FSSP) and Technical Basis Document (TBD)-06-004.
- 3) Surveys in EP 1.93 were performed using a scintillation detector optimized to measure gamma energies representative of Cs-137. Sample #EP 3-1 1 from Survey Request (SR)-13 was referenced for this decision.
- 4) Survey Instructions for this survey unit are incorporated into and performed in accordance with (IAW) the Babcock Services Incorporated (BSI)/LVS-002, Work Execution Package (WEP)05-006. Survey instructions described in this 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
- I I
nata.
-e
.-.
Form cs-o9/1 Rev 0 0 COPY
FSS Design # EP 1.93 Revision # Original Page 2 of 3 I Survey Unit: 1.93 I 1.0 HistoryLDescription 1.1 The subject pipe is a drain system overflow pipe servicing the Hot Dry Storage (HDS) pit in the Hot Lab. The header runs fiom the northwest side of the HDS pit to the valve pit on the -25 ft elevation of the Hot Lab.
1.2 EP 1.93 consists of 3 diameter piping that is approximately 24 feet in length.
2.0 Survey Design Information 2.1 EP 1.93 was surveyed IAW Procedure #BSYLVS-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 24 survey measurements.
2.3 Surface area for the 3 ID piping is 486 cm2for each foot of piping, corresponding to a total 3 ID piping surface area of 17,5 12 cm2(1.8 m2) for the entire length of (approximately 24) 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 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 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 1.93 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 1.93 Revision # Original Page 3 of 3 5.5 Statistical Summary Table 3
Statistical Parameter Pipe I
Total Number of Survey Measurements I 24 Number of Measurements >MDC 12 Number of MeasurementsAbove 50% of DCGL 0 1 Number of MeasurementsAbove DCGL l o 1 Mean 0.0020 Median 0.0019 Standard Deviation 0.0007 Maximum 0.0034 I Minimum Io.0009 6.0 Documentation of evaluations pertaining to compliance with the unrestricted use limit of 25 mdyr and dose contributions fiom Embedded Pipe and radionuclides contributing 10% in aggregate of the total dose for both structural scenarios and soils.
6.1 A review of the survey results has shown that the dose contribution for EP 1.93 to be less than 1 mredyr. The dose contribution is estimated to be 0.002 mredyr based on the average of the actual gross counts measured.
7.0 Attachments Attachment 1 - BSI EPBP Survey Report Attachment 2 - Pipe Interior Radiological Survey Form Attachment 3 - DQA Worksheet Attachment 4 - EP 1.93 SURR & Spreadsheet Disc
SECTION 7 ATTACHMENT 1 7 PAGE(S)
I- BSI EP/BP SURVEY REPORT Pipe ID EP 1.93 Survey Location HDS riser -25' Survey Date 16-W-06 23!500-1# 203488 I Survey Time DetectorSkd # 44-159 #238369/101 L
Median 0.0019 Standard Deviation 0.0007 Maximum 0.0034 Minimum o.Ooo9 STOCK Survey Technician(s)
I r
Survey Unit Classifcation 1 TBD 06-004 Piping Group 3.2 SR-I3 Radionudie DistributionSample EP 3-1 1
-
Measured Nuclide CS-137 Area FactorEMC Used No PasslFaii FSS Pass M R E W R Contribution el COMMENTS:
ACTIVITY VALUES NOT BACKGROUND CORRECTED.
RP Engineer I Date o&' 7-13-07
EP 1.93 3" Pipe TBD 06-004 Group 3.2 C A O activity Cb137 activity Eu-164 activity Nb-94 activity Ag-lO&n activity Unity (dpml100cm2) (dpml100cm2) ..
ld~m/lOOcm2) (dpmllOOcm2) (dpmllOOcm2) 2,492 __ 273 17
-0.00; 1,958
.__ -
214 14 0.001
-~
1,424 _ _ _ _156 - ~ 10 0.001 12 ._.____
2,136 234 15 0.00; 2.136 234 15 0.00:
22,078 3,026 331 21 0.00:
14.286 1,958 214 14 0.00'
-~ -
15 19:481 2,670 ______ 292 19 0.00:
___
15 19,481 2,670 -__- 2 19 0.00:
13 16,883 2,314 2 16 0.00:
~.
11 14,286 1,958
.__ -_
214 14 0.00' 9- 11,688 1,602 175 11 0.00'
~-
19 24,675 3,382 _______ 370 24 0.00:
20 25,974 ____--- 3,560 390 25 0.00:
7 9,091 1,246
__ 13 9 0.00'
___-
24 31,169 4.272 __ 46 30
__ 0.00:
20 25,974 3,560 390 -25 0.00:
_-
12 15,584 ____-__ 2.136 -
234 15 0.00:
lo 12,987 1,780 _ _ 195 12 0.00' 15 19,481 2,670 ~ _ 292 _ - 19 0.00:
19 24,675 3,382 370 24 0.00:
18 23,377 3,204 - 351 22 0.00:
26 33,766 4,628 507 32 0.00:
23 29,870 4.094 448 29-0.00: --
__
MEAN MEDIAN STD DEV
-
MAX
_-
MIN 1of1
SECTION 7 ATTACHMENT 2
-3 PAGE(S)
BSYLVSPipeCrawler-002 Revision 4 Pipe Interior Radiological Survey Form Date: ~ O / cI / , 6 Time: 0344 Pipe Diameter: 7 I1 Pipe ID#:
Building: k: ;,q+~ Elevation: ..- 1 Access Point Area:
System:
/&,r 1 3 9 RI s wbf-c.
.~ 5m@e Type of Survey Investigation Characterization Final Survey Gross C060 cs1 /
7 -
Detector ID##/ Sled ID# 44 / W 2 3 8 36 9 1 f D f Detector Cal Date: 9/5!&7L Detector Cal Due Date: 9/s/4 7 Instrument: Z3m-/ Instrument ID #: &?+W Instrument Cal Date: 7Id06 Instrument Cal Due Date: 7/s/o7 From the Daily Pipe Survey Detector Control Form for the Selected Detector Backgroundvalue Ge4 cpm MDCRstatic I/. 7 cpm Efficiency Factor for Pipe Diameter 0, m O ? 7 (from detector efficiency determination)
MDCtatIC z-lo b 0 \aD cm2 T
-Lstahc
.-i
-
d bM I - 7 1 .
I (u
,. count time ana recdcuiate M U C G , )
Comments: rys- I /
Technician Signature Pipe Interior Radiological Survey 0 REFERENCECOPY Package Page 1 o -
Attachment 3, Page 1 m
BSVLVSPipeCrawler-002 Revision 4 Pipe Interior Radiological Survey Form (Continuation Form)
Date: 43 Pipe ID#: t o / / t /a 6 Pipe Diameter: 3l Access Point Area: & r Dpq c m m g Building: A )4l,n Elevation: -25 System: El s 6R Package Page 3 f 3 0 REFERENCECOPY Attachment 3, Page 2
I SECTION 7 ATTACHMENT 3
Design # EP 1.93 Revision # Original Survey Unit # EP 1.93 Answers to the following questions should be fully documented in the Survey Unit I Release Record Yes
- 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
- 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 embeddedhuried piping scan measurementsbelow the DCGLW,or, if not, was the need for additional static measurementsor soil samples addressed in the survey design?
- 5. Was the instrumentation MDC for volumetric measurementsand smear analysis 10%DCGLw ?
- 6. Were the MDCs and assumptions used to develop them appropriate for the instruments and techniques used to perform the survey? I
~
- 7. Were the survey methods used to collect data proper for the types of radiation involved and for the media beinn surveyed? lx
- 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 facilrty?
- 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 graphicaldata tools been created 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)? 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
---
- 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/ Characterization Manager (prinUsign) I I Date 17/zJ-f&
I Form cs-0912 Rev 0 Page 1 of 1
SECTION 7 ATTACHMENT 4 1 DISC
Survey Unit Release Record
~~~~~ ~ ~ ~ ~ ~ ~~
Design # EP HPT-I 02 Revision # Original Page 1 of 3 Survey Unit #(s)
- 2) EP HPT-102 is a Class 1, Group 3.2 survey unit as per the PBRF Final Status Survey Plan (FSSP) and Technical Basis Document (TBD)-06-004.
- 3) Surveys in EP HPT- 102 were performed using a scintillation detector optimized to measure gamma energies representative of Cs-137. Sample #EP 3-1 1 from Survey Request (SR)-l3 was referenced for this decision.
- 4) Survey Instructions for this survey unit are incorporated into and performed in accordance with (IAW) the Babcock Services Incorporated (BSI)/LVS-002, Work Execution Package (WEP)05-006. Survey instructions described in this 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.
0 COPY
FSS Design # EP HPT-I 02 Revision # Original Page 2 of 3 1.o HistoryDescription 1.1 The subject pipe is part of the the 2 drain line for the 24 Rx Coolant return loop piping. The function of this piping was to convey water from the coolant loop to the sump in the sub pile mom corridor on the -47.
1.2 EP HPT-102 consists of 4 diameter piping that is approximately 23 feet in length.
2.0 Survey Design Information 2.1 EP HPT-102 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 23 survey measurements.
2.3 Surface area for the 4 ID piping is 486 cm2for each foot of piping, corresponding to a total 4 ID piping surface area of 18,971 cm2(1.9 m2) for the entire length of (approximately 23) of 4 piping.
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 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 Level (DCGL) for radionuclide specific EP that corresponds to the 1 mrem/yr 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 HPT-102passes 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 1 1 FSS Design # EP HPT-102 I Revision # Ori@ I I I
Page3of3 Survey Unit: HPT- 102 5.5 Statistical Summary Table Statistical Parameter 1 Pipe Total Number of Survey Measurements 23 Number of Measurements N D C 14 1-~ Number of Measurements Above 50% of DCGL 1 0 Number of Measurements Above DCGL 0 Mean 0.0017 I Median 1 0.0017 I Standard Deviation 10.0007 I Maximum 10.0037 I Minimum I 0.0006 6.0 Documentation of evaluations pertaining io compliance with the unrestricted use limit of 25 m r 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 HPT-102 to be less than 1 mredyr. The dose contribution is estimated to be 0.002 mredyr based on the average of the actual gross counts measured.
7.0 Attachments Attachment 1 - BSI EPBP Survey Report Attachment 2 - Pipe Interior Radiological Survey Form Attachment 3 - DQA Worksheet Attachment 4 - EP HPT 102 S U R R & Spreadsheet Disc
SECTION 7 ATTACHMENT 1 2 PAGE(S)
I
.- .. - BSI EP/BP SURVEY REPORT I
I PipeID I I
HPTIO2 II Survey Loution I Valve Pit fkmr drains -25 2350-1 I 203488 I Survey Time Pipe Size 4 DetectorSkd #
Detector EfRckncy 44-1 59 #238369/101 0.00071 WGL iwooant) 3.79E+06 9.--4--(kCnll) 973
-*rrLrOrpm(.dw m4 2.2 Fkld BKG(qn) 5 Routine Survev X Field MDCRccai 10.7 Total Number of Survey Measurements 23 Number of Measurements >MDC 14 Number of Measurements Above 50% DCGL 0 Number of MeasurementsAbove DCGL 0 Mean 0.0017 Median 0.0017 Standard Deviation 0.0007 Maximum 0.0037 Minimum O.OOO6 TBD 06-004Piping Group 3.2 SR-13 Radionudie Distribution Sample EP 3-1 1 Measured Nuclide cs-137 Area FactarEMC Used Nn
- ~~
PasdFail FSS Pass M R E W R Contribution <l I
COMMENTS:
ACTIVITY VALUES NOT BACKGROUND CORRECTED.
" A RP Engineer I Date
HPT 102 4" Pipe TBD 06-004 Group 3.2 a t
-
Us I I Co60actlvity 1 Co-60activity 1 Cs-137activity Eu-I52 activity ELI-I54activity Nb-94 activity Ag-108m activity ncpm (total dpm) (dpmllOOcm2) (dpm1100cmZ) (dpm1100cm2) (dpm1100cm2) (dpm/100cm2) (dpm1100cm2) UnW 1 15 15 21,127 2,172 238
-
-0.002 2 13 - 13 18,310 1,882 206 0.001
- 3 16 16~- 2233L-.- ____2,316- 254 0.002
___ 4 20 20 28.169 2.895 317 0.002 5 11 11 15:493 ~- 0.001 6 6 6 8,451 0.001 7 16 16 22,535 ~_ -
.
0.002
~ 8 -~17 17 23,944 2,461 0.002 9 18 18 25,352 2,606 -___ 285- 0.002
- 10_ ~ _-16_ _ 16 22,535 2,316 -I - I - 0.002 11 15 15 21,127 2,172 -I 15 I - I 0.002 12 11 11 15,493 - 0.001 1 3 - 16 16 22,535 254 0.001 0.001 0.002
._______
222 0.001
__ - 25.352 2.606 285 0.002
_ _18 8 8 11,268 0.001
- 19 14 14 19,718 0.001
~-
20 11 11 15,493 1,592 -I 11 I - I 0.001 21 19 19 26,761 0.002 22 35 35 49,296 555 0.004 23 31 31 43.662 4.488 492 -I - I 0.00:
-0.00; 0.00; 0.001 0.004
- 0.001 1 of 1
L SECTION 7 ATTACHMENT 2 3 PAGE(S)
I
-
I BSIILVSPipeCrawler-002 Revision 4 Pipe Interior Radiological Survey Form Date:
- I Time: /$y%
Pipe ID#: )spr102 Pipe Diameter: Access Point Area: y#L V E i ? j Building: '.& L&E Elevation: -25 I System:
Type of Survey GrOSS Investigation C060 Characterization FinalSurvey cs 2L-d.-
x Other 4 Detector ID# / Sled ID# - 7
/s9 Z%&369 I 10 1 Detector Cal Date: 9/S/OG Detector Cal Due Date: ?/ 5.h7 Instrument: 7-3 TO -1 Instrument ID #: 34Er Instrument Cal Date: t/Shb Instrument Cal Due Date: 7[r /a 7 From the Daily Pipe Survey Detector Control Form for the Selected Detector Background Value ,qP cpm MDCLtic /O 7 I C P ~
Efficiency Factor for Pipe Diameter 0.0 00 7 I (from detector efficiency determination) mcsta,c 'Z\ G 5 dpd 100 cm2 Technician Signature Pipe Interior Radiological Survey 0 REFERENCE COPY Package Page 1 o Attachment 3, Page 1 a
I I
BSYLVSPipeCrawler-002 Revision 4 Pipe Interior Radiological Survey Form (Continuation Form)
!$/8/46 Date:
Pipe ID#:
Building:
~d Pipe Diameter:
Elevation:
CF- I'
- zr I Access Point Area:
System:
V*VE PLF Pl r oe.u Package Page 7of 5 SiX/ICEY th'C.
a REFERENCE COPY Attachment 3, Page 2
SECTION 7 ATTACHMENT 3 I PAGE(S)
DQA Check Sheet Design # HPT 102 Revision # Original Survey Unit # HPT 102 Preliminary Data Review' 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 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 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 6 Were the MDCs and assumptions used to develop them appropriate for the instruments and techniques used to wrform the survev?
7.Were the survey methods used to collect data proper for the types of radiation involved and for the 1 x 1 I
~~
media beina surveyed?
- 8. Were 'Special Methods" for data collection properly applied for the survey unit under review? X B. Is the data set comprised of qualified measurement results collected in accordance with the survey X design, which accurately reflects the radiologicalstatus of the facillty3 Graphical Data Review
- 1. Has a posting plot been created?
~~
I 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 Analysis
~~
- 1. Are all sample measurements below the DCGLw (Class 1 8 2), or 0.5 DCGLw (Class 3)? X
- 2. Is the mean of the sample data DCGLW? X
- 3. If elevated areas have been identified by sans and/or sampling, is the average activity in each X elevated area c DCGL- (Class l),DCGLw (Class 2), or <0.5 DCGLw (Class 3)?
- 4. Is the result of the Elevated Measurements Test c 1.O? X
~~ ~
- 5. Is the result of the statisticaltest (S+ for Sign Test or Wr for WRS Test) 2 the critical value? X Comments:
F SS/Characterization Engineer (printlsign) Date 7434'7 I
FSSl Characterization Manager (printlsign) R. Case Date 7/23~0-7 I
Page 1 of 1
SECTION 7 ATTACHMENT 4 1 DISC
Design # EP-RX 139 Revision # Original Page 1 of 3 Survey Unit #(s) Rx 139
- 1) Embedded Pipe (EP) Survey Unit Rx 139 meets the definition of embedded pipe for Plum Brook Reactor Facility (PBRF).
- 2) EP Rx 139 is a Class 1, Group 1 survey unit as per the PBRF Final Status Survey Plan (FSSP) and Technical Basis Document (TBD)-06-004.
- 3) Surveys in EP Rx 139 were performed using a scintillation detector opthized to measure gamma energies representative of Co-60. Sample #EP 3-9 from Survey Request (SR)-13 was referenced for this decision.
- 4) Survey Instructions for this survey unit are incorporated into and performed in accordance with (IAW) the Babcock Services Incorporated (BSI)/LVS-002, Work Execution Package (WEP)05-006. Survey instructions described in this Description document constitute Special Methods and the survey design used in the acquisition of survey measurements.
5 ) Instnunent efficiency determinations are developed in accordance with the BSILVS-002, WEP 05-006, these determinations are appropriate for the types of radiation involved and the media being surveyed.
Approval Signatures I Date:
-
FSS/Characterization Engineer I
h d d /t V-7/fAdA/r
/ / r Y
/ 7 - / 1 I
Technical Reviewer (FSS/Characterization Engineer) 7-/b-D7
,J FSS/Characterization Manager .case 7LJd97 El
- v -
cs-o9/1 0 COPY
FSS Design # EP Rx 139 Revision # Original Page 2 of 3 1.0 HistoryiDescription 1.1 The subject pipe is the drain line from the Rx tank penetration on the Rx Building -8 foot elevation. .
1.2 EP Rx 139 consists of 1 diameter piping that is approximately 4 feet in length.
2.0 Survey Design Information 2.1 EP Rx 139 was surveyed IAW Procedure #BSI/LVS-002.
2.2 100% of the 1 ID pipe was accessible for survey. The accessible 1 ID pipe was surveyed by static measurement at one foot increments, for a total of 4 survey measurements.
2.3 Surface area for the 1 ID piping is 243 cm2for each foot of iping, 4
corresponding to a total 1 ID piping surface area of 973 cm (0.1 m2)for the entire length of (approximately 4) of 1 piping..
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) S w e y 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 e 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 Nuclide Fraction (NF), provided in TBD-06-004, the survey unit that is constituted by EP Rx 139passes 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 FSS Design ## EP Rx 139 I Revision ## Original 1 Page3 of3 1 1 Survey Unit: Rx 139 I 5.5 Statistical Summary Table 1
Statistical Parameter Pipe I Total Number of Survey Measurements I 4 1 Number of Measurements >MDC 4 Number of Measurements Above 50% of DCGL 0 Number of Measurements Above DCGL 0 Mean 0.1247 Median 0.1165 Standard Deviation 0.0335 Maximum 0.1717 Minimum 0.0940 6.0 Documentation of evaluationspertaining to compliance with the unrestricted use limit of 25 mredyr and dose contributions fiom Embedded Pipe and radionuclides contributing 10% in aggregate of the total dose for both structural scenarios and soils.
6.1 A review of the survey results has shown that the dose contribution for EP Rx 139 to be less than 1 mredyr. The dose contribution is estimated to be 0.125 mredyr based on the average of the actual gross counts measured.
7.0 Attachments Attachment 1 - BSI EPBP Survey Report Attachment 2 - Pipe Interior Radiological Survey Form Attachment 3 - DQA Worksheet Attachment 4 - SURR EP RX 139 & Spreadsheet Disc
SECTION 7 ATTACHMENT 1 Z PAGE(S)
I I BSI EP/BP SURVEY REPORT c
Number of MeasurementsAbove DCGL 0 Mean 0.1247 Median 0.1165 Standard Deviation 0.0335 1 ~- Maximum I I
0.1717 I Minimum I 0.0940 Survey Technician(s) I STOCK
. - I SR-13 Radionudi Distribution Sample EP 3-1 Measured N u d i CO-60 Area FadorlEMC Used No PasdFail FSS Pass MREMNR C o n t r i i n 4 I
COMMENTS:
ACTMTY VALUES NOT BACKGROUND CORRECTED RP Engineer I Date 7-13 -U 71132007
-
60'0
- L1'0 0'0 II C'O
-ZC'O
- LC'O 102 18L'8Z 000'OL !P ZP P I C C'O 62 1 EEL 209'81 OOO'SP !Z LZ E 60'0 01 C 929 19L'SC E '8E :Z EZ 2
- zc*o
- 9 18 8ss'oz 000'09 )E OE C 0
H 4wn wdau urd38 i!
3*
-
I SECTION 7 ATTACHMENT 2 I PAGE(S)
BSILVSPipeCrawler-002 Revision 4 Pipe Interior Radiological Survey Form Date: 2fZZ ,/07 Time: 1230 Pipe ID#: Rc ,139 Pipe Diameter: 1b o " Access Point Area: Rc c IfWK Building: L V Elevation: - I System:
";
Type of Survey Investigation Characterization Final Survey Gross C06O t/ cs
&-
Detector ID# I Sled ID# FO//.YL -% 0047 I N o 5LED Detector Cal Date: 1/11 117 Detector Cal Due Date: 1 I / I / / Co Y Instrument : 18409+
Instrument Cal Date: 07 bZZ:Ee:ate: I / I I /
.u From the Daily Pipe Survey Detector Control Form for the Selected Detector BackgroundValue 7.7 cpm MDcRstatlc Iz,5 CPm Efficiency Factor for Pipe Diameter 0 , 0 0306 (from detector efficiency determination)
MDcstatlc b/OW dPd /OD cm2 m
tb, : I YO sample cOunt m e and recalculate MDCK, ntu)
Technician Signature I
Pipe Interior Radiological Survey Package Page 1 o f 1 Attachment 3, Page 1
I SECTION 7 ATTACHMENT 3 I PAGE(S)
I I
DQA Check Sheet
- Design# I EP Rx 139 I Revision# I Original I EP Rx 139 Preliminary Data Review' 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 X
~
survey units, or below 0.5 DCGLWfor Class 3 sunrey units?
- 3. Is the instrumentationMDC for embeddedlburied piping statk 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 statii measurements or soil samples addressed in the sunrey 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 X
used to perform the survey?
- 7. Were the survey methods used to collect data proper for the types of radiation invoked and for the medii being surveyed?
X
- 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 radidoaical status of the facilitv?
- 1. Has a posting plot been created? I X
- 2. Has a histogram_
(or _other
_ ~
frequency plot) been created? I I I 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 c DCGLW?
3.
4.
5.
If elevated areas have been identifiedby scans and/or sampling, is the average activity in each elevated area DCGLEMC (Class l),DCGLw (Class 2), or ~ 0 . 5DCGLw (Class 3)?
Is the result of the Elevated Measurements Test < 1.O?
Is the result of the statisticaltest (S+ for Sign Test or W for WRS Test) 2 the critical value? I j-' I I x Comments:
ElCS-0912 Page 1 of 1
I SECTION 7 ATTACHMENT 4 1 DISC
Survey Unit Release Record Design # EP-Rx 151 I Revision # I Original I Page 1 of 3 Survey Unit #(s) Rx 151
- 1) Embedded Pipe (EP) Survey Unit Rx 151 meets the definition of embedded pipe for Plum Brook Reactor Facility (PBRF).
- 2) EP Rx 151 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 151 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.
0 COPY 1 1CS-0911
FSS Design # EP Rx 151 Revision ## Original Page 2 of 3 1.0 HistoryDescription 1.1 The subject pipe system is the 3 Quad B spare DI water system line.
1.2 EP Rx 15 1 consists of approximately 2 1 feet in length from the Reactor Building -25 elevation to Quad B.
2.0 Survey Design Information 2.1 EP Rx 15 1 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 21 survey measurements.
2.3 Surface area for the 3 ID piping is 729.7 cm2for each foot of piping, corresponding to a total 3 ID piping surface area of 15,330 cm2(1.5 m2) for the entire length of (21) of 3 piping..
3.0 Survey Unit Measurement LOcationslData 3.1 Pipe interior radiological survey forms are provided in Attachment 2 of this release record.
4.0 Survey Unit 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 m r e d y 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 15 1 passes FSS.
5.4 Background was not subtracted f?om the survey measurements and the Elevated Measurement Comparison (EMC) was not employed for this survey unit.
t I 1
-
FSS Design # EP Rx 151 Revision # Original I Page 3 of 3 Survey Unit: Rx 151
-
5.5 Statistical Summary Table 3"
Statistical Parameter Pipe Total Number of Survey Measurements 21 Number of Measurements >MDC 7 1 Number of Measurements Above 50% of DCGL I 0 I Number of Measurements Above DCGL I o I Mean I0.0105 Median 0.0098 Standard Deviation 0.0048 Maximum 0.0199 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 Rx 151 to be less than 1 rnredyr. The dose contribution is estimated to be 0.011 mredyr based on the average of the actual gross counts.
7.0 Attachments Attachment 1 - BSI EPBP Survey Report Attachment 2 - Pipe Interior Radiological Survey Form Attachment 3 - DQA Worksheet Attachment 4 - EP RX 15 1 SURR & Spreadsheet Disc
SECTION 7 ATTACHMENT 1 z PAGE(S)
1 1 1 c- l a i
._
PipeID Survey Date BSI EP/BP SURVEY REPORT Rx151 13-De005 Survey Location 2350-1 # 1 Quad B Spare line 212223
!
- -
I I
I Survey Time Pipesize DCGL ~spnnmau)
Routine Survey I
1 3 08:24
2.41EM5
/I II Detector-Sled #
Detector Efficiency Pb.ClllncorpmdwD.Maemdnq(lnsllq Field BKG (cpl)
I 44-62204402/101 0.00014 730 5.2 Field MDCR (opn) 10.8 Mean 0.0105 Median 0.0098 Standard Deviation 0.0048 Maximum I 0.0199 Minimum 0.0042 ROSENHAGEN Survey Technician(s)
I SR-13 Radionudie Distribution Sample EP 2-1 Measured N u d i C0-60 Area FactorlEMC Used No Pass/Feil FSS PaSS MREhWR Contribution 4 COMMENTS:
ACTIVITY VALUES NOT BACKGROUNDCORRECTED RP Engineer 1 Date 7-/c/-D 7
EP Rx 151 3" Pipe TBD 06-004 Group 2 Unity 7
0.001 0.001 0.00 0.01
-~._
0.011 0.01I 0.011 0.001 1of1
SECTION 7 ATTACHMENT 2 3 PAGE(S)
Pipe Interior Radiological Survey Form Date: / 2 - i 3 Time: 0.232Y Building: a)<&w- Elevation: - 2)- Access Point Area:
System: &d Pipe Diameter: 3 r f Pipe ID #
~~
Type of Survey Investigation Characterization c - 2 Other rx Sled Size 3 inch Detector: Yc/-crr- Detector ID #: ZUYO2, Cal Date: / / - I7 - e.J- Cal Due Date: ,/- 7 - ag fnstrument:
-- - .-.
7-3--- (
, 0 - ., . -*._...... .c.---
Instrument ID #:
. - -*
3/zzZ3
. . ~. -- ..
Cal Date: f / + f 7 - Lstr Cal Due Date: 0 d3=
From the Daily Pipe Survey Detector Control Form for the Selected Detector BackgrouTld Value J - 6 2 cpm MDCRtatlC 0. Cpm Efficiency Factor of: Pipe Diameter 0-OV 0 14 (taken from MDCStatlC zIT42 d p d l OOcm2 Is the MDCStabcacceptable? No (ifno, adjxSt sample count t i m e and recalculate hDCR,,,)
_- -
Comments:
Pipe Interior Radiological Survey Radiological Survey Commenced: Date: / 2-13 The: a&. Y Package Page 1 o f 2 0 REFERENCE COPY Attachment 3, Page 1
I
/ 2 - f3 \
I I
I i I 0
REFERENCE COPY Attachment 3, Page 2
SECTION 7 ATTACHMENT 3 I PAGE(S)
~ ~
DQA Check Sheet
-~ ~~ -~ ~~ ~
Design # EP Rx 151 Revision # Original Survey Unit # EP Rx 151 Answers to the following questions should be fully documented In the Survey Unit Yes No NIA 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 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 embeddedburiedpiping static measurements below the DCGLw ? X
- 0. Was the instrumentation MDC for structure scan measurements, soil scan measurements, and embeddedlburied piping scan measurements below the DCGLw,or, if not, was the need for additional 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 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?
- 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 reflectsthe radiological status of the facility3 I. Has a posting plot been created? I 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 Analysis 1.
~
Are all sample measurements below the DCGLw (Class 1 8 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 and/or sampling, is the average activity in each X
elevated area DCGLEMC (Class l), c DCGLw (Class 2), or c0.5 DCGLw (Class 3)?
$. 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) 2 the critical value? X Y
El CS-0912 Page 1 of 1
SECTION 7 ATTACHMENT 4 1 DISC
.
Survey Unit Release Record Design # EP-Rx 162 I Revision# I Original I Page 1 of 3 Survey Unit #(s) Rx 162
- 1) Embedded Pipe (EP) Survey Unit Rx 162 meets the definition of embedded pipe for Plum Brook Reactor Facility (PBRF).
- 2) EP Rx 162 is a Class 1, Group 1 survey unit as per the PBRF Final Status Survey Plan (FSSP) and Technical Basis Document (TBD)-06-004.
- 3) Surveys in EP Rx 162 were performed using a scintillation detector optimized to measure gamma energies representative of CO-60. Sample #EP 3-9 from Survey Request (SR)-13 was referenced for this decision.
- 4) Survey Instructions for this survey unit are incorporated into and performed in acmrdance with (IAW) the Babcock Services Incorporated (BSI)/LVS-002, Work Execution Package (WEP)05-006. Survey instructions described in this 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.
ipproval Signatures 0 COPY
+
FSS Design # EP Rx 162 Survey Unit: Rx 162 Revision # Original I Page 2 of 3 1.0 History#escription 1.1 The subject pipe is the drain line fiom the dry annulus inside the CV to the drain trench on the Rx Building -25 foot elevation.
1.2 EP Rx 162 consists of 2 diameter piping that is approximately 27 feet in length.
2.0 Survey Design Information 2.1 EP Rx 162 was surveyed JAW Procedure #BSVLVS-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 27 survey measurements.
2.3 Surface area for the 2 ID piping is 486 cm2for each foot of piping, corresponding to a total 2 ID piping surface area of 13,134 cm2(1.3 m2) for the entire length of (approximately 27) of 2 piping..
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 162 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 Rx 162 Revision # 0rigma.I Page 3 of 3 1 Survey Unit: Rx 162 I 5.5 Statistical Summary Table Statistical Pammeter I Total Number of Survey Measurements I 27 I Number of Measurements >MDC 0 Number of Measurements Above 50% of DCGL 0 I Number of Measurements Above DCGL l o t Mean 0.0116 Median 0.0094 Standard Deviation 0.0055 Maximum 0.0259 r- ~~ Minimum 10.0024 1 6.0 Documentation of evaluations pertahhg to compliance with the unrestricted Use limit of 25 mrexdyr and dose contributions from Embedded Pipe and radionuclides contributing 10% in aggregate of the total dose for both structural scenarios and soils.
6.1 A review of the survey results has shown that the dose contribution for EP Rx 162 to be less than 1 mredyr. The dose contribution is estimated to be 0.012 mredyr based on the average of the actual gross counts measured.
7.0 Attachments Attachment I - BSI EP/BP Survey Report Attachment 2 - Pipe Interior Radiological Survey Form Attachment 3 - DQA Worksheet Attachment 4 - EP RX 162 SURR & Spreadsheet Disc
I SECTION 7 ATTACHMENT 1 3 PAGE(S)
BSI EPtBP SURVEY REPORT Pipe ID Rx 162 Survey Location cv -2531.
1/26/06,1130/06, 2350-1 # 212223,203488 26/06 i3 2/09/06 0805,1250,1324 8 Detector-Sled # 1 44-62/204402-121
~~ ~
Maximum I 0.0259 Minimum 0.0024 ROSENHAGEN Survey Technician@)
r
-~ ~ ~
COMMENTS:
ACTIVITY VALUES NOT BACKGROUNDCORRECTED 7115Roo7
-
00'0
'10'0 00'0
'LOX 100'0 L l
- OO'O Cl i 10'0 16 IZO'O LZ 1
- 10'0 89 __
- 10-0
- - 89 i00'0 11 9P i00'0 11 9P i00'0 11 9P i00'0 CC 9P
.OO'O a S
____.
i00'0 11 9P 110-0 zz 26 iOO'0 11 9P
.OO'O a
- 10.0 PC
- oo*o 3 i00'0 9 i 10'0 zz Z6
.lO'O 61 18
- oo*o E 21 I10.0 6L 18 i10'0
- zz 26 bun
-
I N
Y-O cv
I SECTION 7 ATTACHMENT 2 7 PAGE(S)
I1 Pipe Interior Radiological Survey Form Date: 1-26-06 Time: 080r Building: (%& ! Elevation: -L3- Access Point Area: AN M CClxx System: Pipe Diameter: zfl Pipe ID # R--x / (o 2 Type of Survey Investigation Characterization Other 1/
Sled Size z / ' v , u y~ &&&L 7 LI inch Detector: b-WL Detector ID #: p . 7 ClCfr & -7d /2/
Cal Date: I- 0 F I /-7 Cal Due Date: / / - f 7 -0 6 Instrument: 23m-( Instrument ID #: 7-/22ZJ Cal Date: It-f 7 Cal Due Date: /f-f 7-0 G From the Daily Pipe Survey Detector Control Form for the Selected Detector Background Value $ 4 cpm MDCRStatlC /I/ 7 cpm Efficiency Factor for Pipe Diameter OImo2b (taken from detector MDcstatlc 7&3b d p d l 00cm2 A N U @CL-Pipe Interior Radiological Survey Radiological Survey Commenced: Date: / - Lb-06 Time: o&c Package Page 1 of 1 Attachment 3, Page I
Pipe Interior Radiological Survey Form Date: /- <30 -0 c. Time: / tm t
Building: \<x Elevation Access Point TRdL L-- IR m':I+
System: S C ~ + . . ,d ~ ~ \ Pipe
~ ~Diameter: 2 " Area: Pipe ID RX I G L
-
Type of Survey Investigation Characterization Ozu- # Other f l Sled Size z ' ' i i d y ~ h ~ t c a ~inch
/L/
Detector: YY-62 Detector ID #: @V+a-T-- I Cal Date: //-/7 -05
- Cal Due Date: / /-/7 - 0 6 Instrument: 2 . 3 $3 4 Instrument ID #: z / rp 2 3 I
Cal Date: / / - / 7 -05 Cal Due Date: //-/ 7 - d b From the Daily Pipe Survey Detector Control Form for the Selected Detector Background Value 5.7 CPm MDCRstahc. //. 3 CPm eGd-y &m!nAW C?LWoZb Efficiency Factor for Pipe m e tStahC er 7 8-3 b dpm/100cm2 (taken from detector
?+
-
Is the MDCStabc (if no, adjust sample count tune and recalculate MDCbt,,)
- - -__ _- -
c&3iaZzF?--/vi -@*&
7,nJLtaYrd 7/c,r-]"/ 7-??/&-$ fyL W G4-a.L&- 7Vzfdft4f PA M PLG-e-Pipe Interior Radiological Survey Radiological Survey Commenced: Date: /-26)-0 6 Time: /2 3 a Package Page 1 of 4
0 REFERENCE COPY Attachment 3, Page 1
I Package Page 2of 3d I
Attachment 3, Page 2 REFERENCECOPY
I r I I
.. . .
0 REFERENCECOPY
Pipe Interior Radiological Survey Form Date: 8 - f$ c o c Time: 1 3 e Building: Z X , Elevation: 2. Access Point Area: A-uvu~J System:
elmj-J-4t*2 I.$\
Pipe Diameter: 2 " PipeIDfC z' /LJ' L/ k/A rL' l/ CL25AC Type of Survey Investigation Charzcterization Other 1 2 1 Sled Size inch Detector: 4+i$ P Detector ID #: Jaw.>
Cal Date: // -/7-3r Cal Due Date: lf ' I 7-047 Instrument: 235.6 - I Instrument ID #: 2--3 Cal Date: // 1 7 0-c, 0 Cal Due Date: / { P / ?
- 0c From the Daily Pipe Survey Detector Control Form for the Selected Detector Background Value .sr CPm MDCRStatiC 164 7 cpm Efficiency Factor for Pipe Diameter De am& (taken from detector
~Cstaoc --?- &3 i5
.. (if no, adiust s- m l e count time and recalc- ,I __-
- ~ --
Coanents:
Pipe Interior Radiological Survey Radiological Survey Commenced: Date: d ' k- 0 b Time: /3PL/
Package Page 1 of 9 0 REFERENCE COPY Attachment 3, Page 1
't BSL'LVSPipeCrawler-002 Revision 4 Pipe Interior Radiological Survey Form Date: J *7 - 0 c Time: / e 50 Pipe ID#: zlx [d 2 yrb& Pipe Diameter: % Access Point Area: c 4 AJ I-)' L: L L ~ 5 Building: '75E AL ~ - Elevation:
i c LA-- System:
Type of Survey Investigation Characterization Final Survey Other J Gross Co60 cs DetectorID#/SledID# .tLf- 6.b 3 S J d f L I p/
Detector Cal Date: -
t 7 9' J b - Detector Cal Due Date: /7 e p ' o L J -0 G Instrument: 2333 I - Instrument ID #: $lo3 qrdo Instrument Cal Date: /7- /d)d - c7 5- Instrument Cal Due Date: /? -@dU --d co From the Daily Pipe'Survey Detector Control Form for the Selected Detector BackgroundValue J7 cpm MDCRS~Lc 7
/e- cpm Efficiency Factor for Pipe Diameter 0-S & o a (from detector efficiency determination) 2 7 83 L?
MDC,ta,C Is the MDC,,,, acceptable? a+(T J~l:&y&--e~,A 2 c --.q+A&t+
1 -
no, adjust sarnple couot tinx md recalcu!a?e MDCR,,,,)
8
.- _.__- -- - -
Technician Signature Pipe Interior Radiological Survey Position
Feet into Pipe from Opening Count Time (min)
Gross counts Gross cpm Net cpm I dpm/lOOcm* 1 1
1 t d. /. r n ILL nI u I A 2 I 4\
2 c/ 3 3 3 2 3 1-I- ?(
4 5
-- I 6
7 1 I
8 I 9
10 Package Page 1 of 2 0 REFERENCE COPY Attachment 3, Page 1
I SECTION 7 ATTACHMENT 3 I PAGE@)
SECTION 7 ATTACHMENT 1 PAGE(S)
DQA Check Sheet Design # EP Rx 162 Revision # Original Survey Unit # EP 162 Prelimlnary Data Review' Answers to the following questions should be fully documented in the Survey Unit Yes No NfA Release Record 1
- 1. Have surveys been performed in accordance with survey instructions in the Survey Design? X
- 2. Is the instrumentation MDC for strudure 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 instrumentationMDC for embeddedhuried 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 c 10% DCGLw ? X
~~
- 6. Were the MDCs and assumptions used to develop them appropriate for the instruments and techniques used to mrfom the survev? IxI I
- 7. Were the survey methods used to collect data proper for the types of radiation involved and for the media beina sunreved?
~
1 x 1 I
- 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 faallty3 Graphical Data Review
~
- 1. Has a posting plot been created? X
- 2. Has a histogram (or other frequency plot) been created? X
- 3. Have other graphical data tools been created to assist in analyzing the data? X Data Analysis
-~ - ~- -
- 1. Are all sample measurements below the DCGLw (Class 1 & 2), or 0.5 DCGLw (Class 3)? X
- 2. Is the mean of the sample data DCGLW? X
- 3. If elevated areas have been identified by scans and/or sampling, is the avemge activity in each X elevated area e DCGLEMC(Class l),DCGLW(Class 2), or ~ 0 . 5 DCGLw (Class 3)?
- 4. Is the result of the Elevated MeasurementsTest e 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 Comments:
Form cs-0912 Rev 0 Page 1 of 1
SECTION 7 ATTACHMENT 4 1 DISC
Survey Unit Release Record
_-
-~
~
Design # EP-Rx 163 1 Revision# 1 Original I Page 1 of 3 Survey Unit q s ) Rx 163
-
- 1) Embedded Pipe (EP) Survey Unit Rx 163 meets the definition of embedded pipe for Plum Brook Reactor Facility (PBRF).
- 2) EP Rx 163 is a Class 1, Group 1 survey unit as per the PBRF Final Status Survey Plan (FSSP) and Technical Basis Document (TBD)-06-004.
- 3) Surveys in EP Rx 163 were performed using a scintillation detector optimized to measure gamma energies representative of CO-60. Sample #EP 3-9 fiom Survey Request (SR)-13 was referenced for this decision.
- 4) Survey Instructions for this survey unit are incorporated into and performed in accordance with (IAW) the Babcock Services Incorporated (BSI)/LVS-002, Work Execution Package (WEP)05-006. Survey instructions described in this 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 163 Revision # Ori@ Page 2 of 3 1.0 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 163 consists of 2 diameter piping that is approximately 23 feet in length.
2.0 Survey Design Information 2.1 EP Rx 163 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 23 survey measurements.
2.3 Surface area for the 2 ID piping is 486 cm2for each foot of pi ing, corresponding to a total 2 ID piping surface area of 7,783 cm4(0.8 mz) for the entire length of (approximately 23) 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 EPBuried Pipe (BP) Survey Report provided in Attachment I ,
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 163 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 I 1
FSS Design # EP Rx 163 Revision # Origrnal Page 3 of 3 5.5 Statistical Summary Table 2" '
Statistical Parameter Pipe I Total Number of Survey Measurements I 26 I Number of Measurements>MDC 0 Number of MeasurementsAbove 50% of DCGL 0 1 ~~
Number of Measurements Above DCGL
~
1 0 1 Mean 0.0129 Median 0.0130 J
Maximum 0.0234 r
Minimum 6.0 Documenbtion of evaluations pertaining to compliance with the unrestricted use limit of 25 mredyr and dose contributions fiom Embedded Pipe and radionuclides contributing 10% in aggregate of the total dose for both structural scenarios and soils.
6.1 A review of the survey results has shown that the dose contribution for EP Rx 163 to be less than 1 mredyr. The dose contribution is estimated to be 0.013 mredyr based on the average of the actual gross counts measured.
7.0 Attachments Attachment 1 - BSI EP/BP Survey Report Attachment 2 - Pipe Interior Radiological Survey Form Attachment 3 - DQA Worksheet Attachment 4 - EP RX 163 SURR & Spreadsheet Disc
I SECTION 7 ATTACHMENT 1 3 PAGE(S)
BSI EP/BP SURVEY REPORT Pipe ID Rx 163 Survey Location Annulus -291.
1126106,1130106, Survey Date 2350-1 I 212223 2/6/06 Survey Time 0815,1350,1250 Detectorsled w 44-62/204402-121,44-62/204402-no sled Number of Measurements >MDC 0 Number of MeasurementsAbove 50% DCGL 0 Number of MeasurementsAbove DCGL 0 Mean 0.0129 Median 0.0130 Standard Deviation 0.0051 Maximum 0.0234 Minimum 0.0047 Survey Unit Classification 1 TED O6-004 Piping Group 1 SR-13 Radionudide Distribution Sample EP 3-9 Measured Nuclide Cb60 Area FactorlEMC Used No PasGail FSS Pass M R E W R Contribution el I
RP Engineer I Date
EP Rx 163 2" Pipe TBD 06-004 Group 1 I r l
-
Co-80 activity Cs-137 activity Eu-162 activity Eu-164 activity Nb94 activity Ag-108m activity (dpm1100cm2) (dpm1100cm2) (dpm/l OOcm2) (dpm1100cm2) (dpm1100cm2) (dpm1lOOcmZ) UnitV 1,581 __ 63 1,500 399 46
- 11
- 0.00s 1,977 78 1,875 498 58
- .~
14 0.01:
___..
2,767 - -_
110 - 2,625 698 81 19 0.01i 791 -31 750 199 23 6 O.OOf 7,692 1,581- - 63 1,500 399 46 11 0.00s 7,692 1,581 63 1,500 399 46 11 0.001 7.692 1,581 -63 1,500 399 46 11 0.00:
8 2.5
-~ 2.5 9,615 1,977 - 78 1,875 498 58 14 0.01:
9 4
___.______.
4 15,385 - 3,163 - 125 3,000 798 92
- 22 0.01(
10 2 2 7,692 1,581 63 1,500 399 46 11 O.OO!
11 4.5 4.5 17,308 141 3,375 897 104 25
- 0.02' 12 3.5 3.5 13,462 19 0.01;
-
13 3 3 11,538 17 0.01r 14 1.5 1.5
- 5,769 8 0.00:
_ _ 15 -2 2 7,692 11 O.OO!
- -
16 2 2 7,692 11 O.OO!
17 3 3 11,538 17 0.034 18 1 1 3,846 6 0.001 19 1 1 3,846 6 O.OO!
20 3 3 11,538 17 0.014 21 4 4 15,385 22 0.01!
___
22 3.5 3.5 13,462 19 0.01' 23 4 4 19,048 27 0.02:
24 2.5 2.5 11,905 17 O.Ol!
25 3 3 14,286 2c 0.011 26 3 3 14,286 2c - 0.01; 1 of2
EP Rx 163 2" Pipe TBD 06-004 Group 1 Cs-137 activity Eu-152 activity Eu-154 actlvky Nb-B4 actlvlty AglOlm activity (dpm1100cm2) (dpm1100cm2) (dpm1100cm2) (dpmllOOcm2)
Unity (dpm1100cm2)
k----t----IlsT~
-+- MEAN MEDIAN DEV 0.01 0.01 I 0.00
...
I I I 2of2
I SECTION 7 ATTACHMENT 2 7 PAGE(S)
Pipe Interior Radiological Survey Form Date: /-ZG-Ob Time: ox/i-Building: prp Elevation: - L Access Point Area: A-p' N u L C L i J System: Pipe Diameter: 2 - Pipe ID #
Type of Survey Investigation Sled Size 2 d I I J y ( BLUOZ- 7 LC inch Characterization c&Gy> Other 2 S/!!U Detector: "py-8 L Detector ID #: aW-- f2-l Cal Date: 1/ - ( 7 - 0 5 - Cal Due Date: -
/ I - /7 0 lQ Instrument : 2357?--r Instrument ID #: ZL? 2 2 3 Cal Date: rf-f7 - 0 5 c Cal Due Date: t p f 7-Lqb From the Daily Pipe Survey Detector Control Form for-the Selected Detector BackgroundValue b. f cpm MDCRstatic lfp7 cpm Efficiency Factor for Pipe Diameter 0 0002b (taken from detector MDcstatlc 7 83 b n dp d l 00cm2 Is the M D C d , acceptable? No '
(ifno, adjust sample count time and recalculate MDC&,'I .
-
Pipe Interior Radiological Survey n
Package Page 1 of J'-
Attachment 3, Page 1 REFERENCE COPY
Pipe Interior Radiological Survey Form Date: / I 30-a d Time: 135-0 I Building: qw 7d-A Elevation d Access Point D u d &'--F--+
System: J"D*MW'+' d x / L 3 Type of Survey Investigation Pipe Diameter:
Characterization &->'
I' Area: Pipe ID Other <
Sled Size J //~;,,I\V+\\C~ inch c
Detector: cl+- 6 a Detector ID #: &2oyye ' Z
=4.FF
/3(
Cal Date: / [ - ' / 7 r O ~ Cal Due Date: 11. / 7 - d Instrument: 2353- I Instrument ID #: gt 2 2 3 3 Cal Date: //*r7-5 Cal Due Date: [(- 1 7 -8 c-1 From the Daily Pipe Survey Detector Control Form for the Selected Detector Background Value 6 7 CP*
MDCRstatic / f *3 CP*
Efficiency Factor for Pip e 0 tODb2.b (taken from detector m e tstatlc er 783L - d p d l 00cm2 Pipe Interior Radiological Survey Package Page 1 of&
Attachment 3, Page 1
I I "( /
Pipe Interior Radiological Survey Form (Continuatihn Form) 1. 30*@6 Z X / C J Package Page L o f g f Attachment 3, Page 2
r I
Pipe Interior Radiological Survey Form Date:
Building: G F E m L L 7P.y Elevation: /*-f Access Point Area:
System: g - c TO)-^) Pipe Diameter: 2 Pipe ID #
J -Dh;->iL Type of Survey Investigation Characterization Survey) Other Sled Size c c u inch Detector: q4- L T Detector ID #: 26 c/s/ 2-
/ / 1740 > / P 17-8 L h
Cal Date: Cal Due Date:
Instnunent: 260 Instrument ID #: aGv a ?
Cal Date: / / * // - d - ? g Cal Due Date: //-/7d 6 From the Daily Pipe Survey Detector Control Form for the Selected Detector BackgroundValue s4- 1 cpm MDCRS,,, / 0 / 7 cpm Efficiency Factor for Pipe Diameter 8 9 Oms\ (taken from detector MDCSWX 970 1 d p d l OOcm2 n
Is the MDCSt,ti,acceptable? [xes > No (if no, adjust sample count time and recalculate MD1-Comments: fo~*-Ju&-, ~ & . /
Pipe Interior Radiological Survey Radiological Survey Commenced: Date: 0 L 6 Time: / ab P Package Page 1 of 2 0 REFERENCE COPY Attachment 3, Page 1
aj I
Pipe Interior Radiological Survey Form Date: a4 4 Time: 13 1 7 Building: EA , Elevation: 5 Access Point Area: ~*L,CLS System:
C&+*-I
- 7; I , <\ Pipe Diameter: 2 Pipe ID # % /b3 3 pcur Pfi+d-+ &X%
e Type of Survey Investigation Characterization Other /
Sled Size r / . 54a inch Detector: r f ? 4 3- Detector ID #: P W O 3.
Cal Date: //T7 r-0 >- Cal Due Date: / / / 7 . 0 G Instrument: 2 3 3 I Instrument ID #: d@aa3 Cal Date: (Pf7d 5; Cal Due Date: l(flf7 From the Daily Pipe Survey Detector Control Form for the Selected Detector Background Value $-I cpm MDCRstatic 10.7 cpm Efficiency Factor for Pipe Diameter 0 00 00 a\ (taken from detector MDCStatiC 9 70 1 Am/100cm*
Is the h/lDCsta6cacceptable? Yes 1 No (if no, adjust sample count time and recalculate MDCR,,ti,)
Comments: pBF+mzLL3,d s ~ ~ A ~ ~
f3z4c/p krt:
4 Pipe Interior Radiological Survey Radiological Survey Commenced: Date: (;2
- k 0 b Time. /97 Package Page 1 of 2 0 REFERENCECOPY Attachment 3, Page 1
.L SECTION 7 ATTACHMENT 3 I PAGE(S)
DQA Check Sheet Design # EP Rx 163 Revision # Original Survey Unit # EP Rx 163 Preliminary Data Review' Answers to the following questions should be fully documented in the Survey Unit Yes No Release Record
- 1. Have surveys been performed in accordancewith survey instructionsin 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?
- 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 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 instrumentation MDC for volumetric measurements and smear analysis 10% DCGLw ?
- 6. Were the MDCs and assumptions used to develop them appropriate for the instruments and techniques used to perform the survey?
- 7. Were the survey methods used to collect data proper for the types of radiationinvolved and for the IxI 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 collectedin accordance with the survey X design, which accurately reflects the radiological status 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 1, Are all sample measurementsbelow 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 identifiedby scans andlor sampling, is the average activity in each X elevated area < DCGLEMC (Class I), < DCGLw (Class 2), or e0.5 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 W for WRS Test) 2 the critical value? X Comments:
El r
CS-0912 Page 1 of 1
SECTION 7 ATTACHMENT 4 1 DISC
Survey Unit Release Record Design # EP-1.37 Revision # Original Page 1 of 3 Survey Unit #(s)
- 2) EP 1.37 is a Class 1, Group 2 survey unit as per the PBRF Final Status Survey Plan (FSSP) and Technical Basis Document (TBD)-06-004.
- 3) Surveys in EP 1.37 were performed using a scintillation detector optimized to measure gamma energies representative of CO-60. Sample #EP 2-1 from Survey Request (SR)-13 was referenced for this decision.
- 4) Survey Instructions for this survey unit are incorporated into and performed in accordance with (IAW) the Babcock Services Incorporated (BSI)/LVS-002, Work Execution Package (WEP)05-006. Survey instructions described in this 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 I Date:
0 COPY F! CS-09/1
FSS Design # EP 1.37 Revision # Original Page 2 of 3 1.0 History/Description 1.1 The subject pipe system is the 3 purge line for Canal E. The function of this pipe was to convey water from the one 3 inch riser in Canal E to the HD sump in Pump Room #22 on the Rx Building -25 ft, where the pipe is currently breached.
1.2 EP 1.37 consists of approximately 32 feet in length from the pump room to the riser in Canal E. The pipe section has an approximately three m i t d elbows ranging from 45to 90.
2.0 Survey Design Information 2.1 EP 1.37 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 36 survey measurements.
2.3 Surface area for the 3 ID piping is 729.7 cm2for each foot of piping, corresponding to a total 3 ID piping surface area of 26,280.6 cm2(2.6 m2) for the entire length of (36) of 3 piping..
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 1.37 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.
r i- I FSS Design # EP 1.37 Revision # Original Page 3 of 3 5.5 Statistical Summary Table 3
Statistical Parameter Pipe I I Total Number of Survey Measurements 36 Number of Measurements >MDC 31 Number of MeasurementsAbove 50% of DCGL 0 Number of MeasurementsAbove DCGL 0 Mean I 0.018 11 Median 0.020 Standard Deviation 0.007 Maximum 0.034 Minimum 0.004 6.0 Documentation of evaluations pertaining to compliance with the unrestricted use limit of 25 mredyr and dose contributions from Embedded Pipe and radionuclides contributing 10%in aggregate of the total dose for both structural scenarios and soils.
6.1 A review of the survey results has shown that the dose contribution for EP 1.37 to be less than 1 mredyr. The dose contribution is estimated to be 0.018 mredyr based on the average of the actual gross counts measured.
7.0 Attachments Attachment 1 - BSI EP/BP Survey Report Attachment 2 - Pipe Interior Radiological Survey Form Attachment 3 - DQA Worksheet Attachment 4 -Disc containing RR for EP 1.37 & Spreadsheet
SECTION 7 ATTACHMENT 1
BSI EPIBP SURVEY REPORT Total Number of Survey Measurements 36 Number of Measurements>MDC 31 Number of MeasurementsAbove 50% DCGL 0 Number of MeasurementsAbove DCGL 0 Mean 0.018 Median 0.020 Standard Deviation 0.007 Maximum 0.034 Minimum 0.004 1 - I c Survey Unit Classification
. - Grow TBD 06404 Pimna SR-13 Radionudie Distribution Sample I 1 2
EP 2-1 I
Measured Nuclide c060 Area FactorlEMC Used No PasdFail FSS P&SS MREMPlR Contribution <l COMMENTS:
ACTIVITY VALUES NOT BACKGROUND CORRECTED
EP 1.37 3" Pipe TBD 06-004 Group 2
-
Eu-154 activity Nb-Q4activHty Ag-1OBm activity C&O acthrky Co-Bo activity Cs-137 activity Eu-152 activity (dpmlqOOcm2)
Jnity gcpm ncpm (total dpm) (dpm1100cm2) (dpm1100cm2) (dpm1100cm2) (dpmllOOcm2) (dpm1100crn2)
I -
~
0.001
__0.01-
___-- 94 - 0.014
._ -
.
122 - _ 0.011
_
131 0.021
__
~
0.014
~
0.011
---171 1 ._
0.01
-
- 0.02:
__0.02
~
0.01
- __ ~ _ 0.01
_-
102 0.01
___
28 ~
0.00
- 0.02
__0.01 0.01
_0.02
_ -
0.02
-- -
0.02
__0.02 0.03
~-
~
0.02
_ 0.02
_
0.02 0.02
__ 0.02
-__ 19s __ 0.03 114 _ 0.01
-
~
0.02 0.02 1 of2
P 3
0 N
c 0
(v
I SECTION 7 ATTACHMENT 2 PAGE(S)
Pipe Interior Radiological Survey Form
/l3a-Date:
Building:
System:
E- 1 3 -0 5-
&$ &Lo@
Pr.4EiS-6 llm/h3 Type of Survey Sled Size Investigation 3 r(
Time:
Elevation:
PipeDiameter:
inch
-3 3-Characterization 3 ->Pipe
~
Final Survey rh:r Access Point Area: C
/I 3 .,r L Lf Detector: Yy-4 Detector ID #: zd Y Y i ? ; I -101 Cal Date: //-/7-0 Cal Due Date: t 1-/ 7 -0@
Instrulnent: ZJ JT-I Instrument ID #: 2 / 2 5 2 3 Cal Date: I/-/ 7-c;tjI Cal Due Date: -/ 7 - 0 &
From the Daily Pipe Survey Detector Control Form for the Selected Detector Backgroundvalue 52 CPm
/O-f Adc*cy A&,,:nrXI
-
MDCRStatIC cpm Efficiency Factor for Pipe Diameter 000 4 (taken from detector-MDCSbtiC 2 Is the MDCSb,, acceptable?
Comments: I u \TL ax d p m / l 00cm2 P;L- S u ,wJ No (if no: adjust sample count m e and recalculate MD%b,)
\
/
Pipe Interior Radiological Survey Radiological Survey Commenced: Date: 1z-13 Time: f 30 Package Page 1 of -3 Attachment 3, Page 1
Pipe Interior Radiological Survey Form (Continuation Form I I I I I I I 7
Package Page -of - 3 REFERENCE COPY Attachment 3, Page 2
\ -
.. . .
. 1 ._
.
Drawing PF-00376 -
arious drains.
i
Pipe Interior Radiological Survey Form Date: /Z/ /JVG Time: //m Elevation: -32 Access Point Area: /d*cd ipeD# /* 37 Type of Survey Investigation Other I/
Sled Size 3 inch Detector: W - G G Detector ID #: ;1../c/ 2-1 D(
Cal Date: // - / 6- Cal Due Date: / / - f 7 . 0Q Instrument: J,3 50 I - Instrument I D#: A32623 Cal Date: //. 1 7
- 6.5 Cal Due Date: / I - (?,-bL From the Daily Pipe Survey Detector Control Form for the Selected Detector Background Value 5~ f cpm 4 MDCRstatic D.3 Efficiency Factor for Pipe Diameter mcstatx 2 N z d p m / l OOcrn' Is the hMDC,tahc acceptable? NO (if no, adjust sample count t h e and recalculate MDCR,,,,)
Comments: p a r r , Ub477dR) J a I z b ' 6 c s /
p 8 .DC&-ZC4 Pipe Interior Radiological Survey Radiological Survey Commenced: Date: 18 '/I* 0 Time: /Y-3 m
Package Page 1 of -
REFERENCE COPY Attachment 3, Page 1
Pipe Interior Radiological Survey Form (Continuation Form)
I 7
Package Page -of - 3 REFERENCECOPY Attachment 3, Page 2
--.
REFERENCECOPY
SECTION 7 ATTACRRlENT 3 1 PAGE(S)
DQA Check Sheet Design # I EP 1.37 1 Revision # 1 Original 1 Survey Unit# I EP 1.37 Preliminary Data Review' Answers to the following questions should be fully documented in the Survey Unit Release Record yes No
- 1. Have surveys been performed in accordance with survey instructions in the Survey Design? X 2.
3.
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?
Is the instrumentationMDC for embeddedlburied piping static measurements below the DCGLw ?
I X
I I x
- 4. Was the instrumentationMDC 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 instrumentationMDC for volumetric measurements and smear analysis 10% DCGLw ? I X
- 5. Were the MDCs and assumptions used to develop them appropriatefor the instruments and techniques usedto 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?
B. 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 accordancewith the survey design, which accurately reflects the radiological status of the faciliW Graphical Data Review
- 1. Has a posting plot been created? l x
- 2. Has a histogram(or other frequency plot) been created? I I I x
- 3. Have other graphical data tools been created to assist in 8nalyzing the data? x Data Analysis 1, Are all sample measurements below the DCGLW(Class I8 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 I), < DCGLW(Class 21, or ~ 0 . DCGLW 5 (Class 3)?
- 6. 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 W S Test) 2 the critical value? I I I x FSS/ChamcterizatioflEngineer (prinffsign) Date 6--/2-07 7//g/u-7 El FSS/ Characterization Manager (printlsign) Date
/Y cs-0912 Page 1 of 1
SECTION 7 ATTACEIMENT 4 1 DISC
- I Design # EP-1.81 Revision # Original Page 1 of 3 Survey Unit #(s) 1.81
- 1) Embedded Pipe (EP) Survey Unit 1.81 meets the definition of embedded pipe for Plum Brook Reactor Facility (PBRF).
- 2) EP 1.81 is a Class 1, Group 2 survey unit as per the PBRF Final Status Survey Plan (FSSP) and Technical Basis Document (TBD)-06-004.
- 3) Surveys in EP 1.81 were performed using a scintillation detector optimized to measure gamma energies representative of CO-60.Sample #EP 2-1 from Survey Request (SR)-13 was referenced for this decision.
- 4) Survey Instructions for this survey unit are incorporated into and performed in accordance with (IAW) the Babcock Services Incorporated (BSI).ILVS-002, Work Execution Package (WEP)05-006. Survey instructions described in this 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.
Date:
I I I CY
FSS Design # EP 1.8 1 Revision # Original Page 2 of 3 1.o HistorylDescription 1.1 The subject pipe is the floor drain line from Canals J & K to the -25 A of the Rx Building in Pump Room #22. The function of this pipe was to convey water from floor drains located in Canals J & K to the HD sump in Pump Room #22 on the Rx Building -25 ft, where the pipe is currently breached.
1.2 EP 1.81 consists of approximately 30 feet in length from the valve pit in the Hot Laboratory Building to the Pump Room #22. The pipe section has at least 5 mitered elbows ranging between 300 and 500.
2.0 Survey Design Information 2.1 EP 1.81 was surveyed IAW Procedure #BSILVS-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 20 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 29,180 cm2(2.9 m2) for the entire length of (20) of 6 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 InvestigatiodResults 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 ofthe FSSP, and applying the Cesium-1 37Kobalt-60 ratios, provided in TBD-06-004, the survey Unit that is constituted by EP 1.81 passes FSS.
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 1.81 Revision ## Original Page 3 of 3 5.5 Statistical Summary Table Statistical Parameter Total Number of Survey Measurements I I 6" Pipe 20 Number of Measurements >MDC 19 Number of Measurements Above 50% of DCGL 0 Number of MeasurementsAbove DCGL 0 Mean 0.005 Median 0.003 Standard Deviation 0.004 Maximum 0.018 Minimum 0.001 6.0 Documentation of evaluations pertaining to compliance with the unrestricted use limit of 25 rnredyr and dose contributions fiom Embedded Pipe and radionuclides contributing 1oo/o in aggregate of the total dose for both structural scenarios and soils.
6.1 A review of the survey results has shown that the dose contribution for EP 1.81 to be Iess than 1 mredyr. The dose contribution is estimated to be 0.005 mredyr based on the average of the actual gross counts measured.
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 1.81 & Spreadsheet
SECTION 7 ATTACHMENT 1 2 PAGE(S)
BSI EP/BP SURVEY REPORT Total Number of Survey Measurements 20 Number of Measurements >MDC 19 Number of Measurements Above 50% DCGL 0 Number of Measurements Above DCGL 0 Mean 0.005 Median 0.003 Standard Deviation 0.004 Maximum 0.018 I Minimum I 0.001 ROSENHAGEN Survey Technician(s)
I Survey Unit Classification I 1 I TBD 06-004 Piping Group I 2 SR-13 Radionuclide Distribution Sample EP 2-1 Measured Nuclide Co60 Area Factor/EMC Used No Pass/Fail FSS Pass MREMNR Contribution <1 COMMENTS:
ACTIVITY VALUES NOT BACKGROUND CORRECTED RP Engineer I Date 6-12-07
EP 1.81 3" Pipe TBD 06-004 Group 2 I I I I I
-
cod0 activity -437 activity Eu-152 actMty Eu-164 acthflty Nb-94 a c t I W Ag-lO8m acthrlty ncpm (dpm1100cm2) (dpmll OOcm2) (dpm1100cm2) (dpmll OOm2) (dpmll OOcm2) (dpm/l OOcm2) JnW II I
-
1 18 18 9,000 617 320 5 41 1
0 18 3.003 2 19 19 9,500 651 338 5 19 3.00=
__
3 21 21 10,500
__ - 720 374 6 21 D.001
-__
4 17 17 8,500
-_ 583 302 5 17 0.001 5 13 _ _13 6,500 446 231
__
__
4
--
13 m 6 28 28 14.000 960 .-
498 8 D.004 7 62 62 31;OOO 2,125 1,103 ____8 1 D.00C
-_
8 25 25 12,500 857 445 7 D.OW
___
9 15 15 7,500 7.500
-_ 514 267 4 0.002 10 101 8 81 8) 4,000 1 274 I 142 -- 2 0.oo.l 11 111 13 131 13 131 .-
6.500 - - I 446 4461 231 4 13 o.00; 12 13 14 20 i4 45 20 14 45 10,000 7.000 221500 685
__ 1,542 1
480 --%$
800 -~
6 4
13 I
-
20
- 14 45 o.00:
0.00; 0.OOi 15 62 62 31,OOO 2,125 1,103 18 ~ __- 62 0.001
-_
16 35 35 17,500 1,199
_______-__---- 623 10 35 O.OOf
-17 33 33 16,500 1,131 587
___.
9 -__ 33 653 18 32
- 32 16.000 1.097 569 9 -
32 O.ODt
-__
19 20 I 53 123 I 53 123I 26150-61SO0
_
4.215
' I 943 2.188
___ 15_
35
=
~ 53 122
~
-
O.OOt
-_
0.011
- I
_
MEAN --
0.00:
~
oool MAX 0.011 MIN -
0.00' lofl
SECTION 7 ATTACHMENT 2 3 PAGE(S)
Pipe Interior Radiological Survey Form Date: /. + d L Time: 0 3 p Building: RQtzSii 8 d,5 Elevation: - zc-r Access Point Area: -z7 /354 c d
'
System: PW M +ttq b n ~ r3r Pipe Diameter: ~ *rP eP i.-.---~
/ Lk/T /
I Type of Survey Investigation Characterization inal Suve Sled Size 6" inch Detector: 2)cfiu fJ /#6 Detector ID #:
'c 6VS-j - (07 Cal Date: / A 02-0 5- Cal Due Date: /3-2 a -
- L Instrument: 9357 -I Instrument ID #: 13Y7d v Cal Date: - 03- Cal Due Date: i3 $4 From the Daily Pipe Survey Detector Control Form for the Selected Detector BackgroundValue / 8- cpm MDCRstatic 7 s CPm Efficiency Factor for Pipe Diameter mcstatlc Is the MDCstaticacceptable?
Comments: J+/pw-7 a
3 3 3 d m/100cm2 No Jq 6 I/ eC/
I (if no, adjust sample count time and recalculate MDCR,,,,)
I V
Pipe Interior Radiological Survey Radiological Survey Commenced: Date: /, 9- O The: 07 re)
Position Feet into Pipe Count Time Gross counts Gross Net d p d l 00cm2
- fiom Opening (&> cpm cpm 1 f* 1 /r /r nZe r\1A 2 26- / /$ t? E 1 3 I at 81 4 9 k I (7 17
- r3 y -
5 3 .f I I /3 6 && ) 2Y 7 7.t; I ha+
8 8f.i / PX r3.S 9 %- I fY /$
10 /6P I 8 4 JI Package Page 1 of 2 U REFERENCE COPY Attachment 3,Page-k
_-- __
I Pipe Interior Radiological Survey Form (Continuation Form) 7 Package Page -of - F
- REFERENCECOPY 0 Attachment 3, Page 2
SECTION 7 ATTACHMENT 3 I PAGE(S)
DQA Check Sheet
~~
Design # 1 EP 1.81 I Revision # I Original I Survey Unit # EP 1.81 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 accordancewith survey instructions in the Survey Design? X 2.Is the instrumentation MDC for structure static measurements below the DCGLw for Class 1 and 2 survev units. or below 0.5 DCGLw for Class 3 survev units?
~
Is the instrumentation MDC for embeddedhuried piping static measurements below the DCGLW?
I Ix
- 3. X
- 4. Was the instrumentation MDC for stnicture scan measurements, soil scan measurements, and embeddedburied piping scan measurements below the DCGLw,or, if not, was the need for additional X static measurements or soil samples addressedin the survey design?
~ ~~
- 5. Was the instrumentation MDC for volumetric measurements and smear analysis 10% DCGLW? X
- 6. Were the MDCs and assumptionsused to develop them appropriate for the instruments and techniques used to perform the survep
- 7. Were the survey methods used to collect data proper for the types of radiation involved and for the X
medii being surveyed?
- 8. Were Special Methodsfor data collection properly applied for the survey unit under review? X
-~ ~
- 9. Is the data set comprised of qualified measurement results collected in accordancewith the survey desian. which acwratelv reflects the radiolwical status of the facility? (XI
- 1. Has a postinn plot been created? I x
- 2. Has a histogram (or other frequency plot) been created?
~~ ~
I I I x 3, Have other graphical data tools been created to assist in analyzingthe data? X
- 2. Is the mean of the sample data DCGLw? X
- 3. If elevated areas have been identified by scans andor sampling, is the average activity in each X
elevated area < DCGLEMC (Class I), 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 ctitical value? X
.-
Form CS-09/2 Rev 0 Page 1 of 1
SECTION 7 ATTACHMENT 4 1 DISC
Design # EP-Rx 127 Revision # Original Page 1 of 3 Survey Unit #(s)
- 2) EP Rx 127 is a Class 1, Group 1 survey unit as per the PBRF Final Status Survey Plan (FSSP) and Technical Basis Document (TBD)-06-004.
- 3) Surveys in EP Rx 127 were performed using a scintillation detector optimized to measure gamma energies representative of CO-60. Sample #EP 3-8 from Survey Request (SR)-13 was referenced for this decision.
- 4) Survey Instructions for this survey unit are incorporated into and performed in accordance with (IAW) the Babcock Services Incorporated (BSI)/LVS-002, Work Execution Package (WEP)05-006. Survey instructions described in this 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.
COPY
FSS Design ## EP Rx 127 Revision # Original Page 2 of 3 1.o History/Description 1.1 The subject pipe is the drain line on the Rx Building -25 foot elevation.
The b c t i o n of this pipe was to convey waste water from the drain openings to the drain trench on the Rx building -27ft.
1.2 EP Rx 127 consists of 4 diameter piping that is approximately 2 1 feet in length.
2.0 Survey Design Information 2.1 EP Rx 127 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 21 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 20,430 cm2(2.0 m2) for the entire length of (approximately 2 1) of 4 piping..
3.0 Survey Unit Measurement LocationslData 3.1 Pipe interior radiological survey forms are provided in Attachment 2 of this reiease record.
4.0 Survey Unit InvestigationdResults 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 127 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 127 Revision # Origrnal Page 3 of 3 5.5 Statistical Summary Table 4
Statistical Parameter Pipe I Total Number of Survey Measurements
~
I 21 I Number of Measurements >MOC 17 Number of Measurements Above 50% of DCGL 0 Number of Measurements Above DCGL 0 Mean 0.0177 Median 0.0141 Standard Deviation 0.0184 Maximum 0.0943 Minimum 0.0059 6.0 Documentation of evaluations pertaining to compliance with the unrestricted use limit of 25 mredyr and dose contributions from Embedded Pipe and radionuclides contributing 10% in aggregate of the total dose for both structural scenarios and soils.
6.1 A review of the survey results has shown that the dose contribution for EP Rx 127 to be less than 1 mredyr. The dose contribution is estimated to be 0.018 mredyr based on the average of the actual gross counts measured.
7.0 Attachments Attachment I - BSI EP/BP Survey Report Attachment 2 - Pipe Interior Radiological Survey Form Attachment 3 - DQA Worksheet Attachment 4 - EP RX 127 SURR & Spreadsheet Disc
SECTION 7 ATTACHMENT 1 L PAGE(S)
I BSI EP/BP SURVEY REPORT Pipe ID I Rx 127 Survey Location 1 -27el. RBDL-1 23%-1 I 203488 08:05 Detector-Skd # LVS-lI101
~-~ ~~
Maximum I 0.0943 Minimum 0.0059 ROSENHAGEN Survey Technician(s)
~~ ~ ~~~ ~ ~~ ~~ ~~
ACTIVITY VALUES NOT BACKGROUNDCORRECTED RP Engineer 1 Date 7/14/2007
EP Rx 127 4" Pipe TBD 06-004 Group 1
-
I Cod0 activity C0-60 activity Cs-137 activity Eu-152 activity Eu-154 actlvlty Nb-94 activity Ag-1OBm activity gcpm ncpm (total dpm) (dpm1100cm2) (dpml100cm2) (dpmllOOcm2) (dpm1100cm2) (dpm1100Grn2) (dpm1100cm2)
- 15 15 28.846 2.965 11 2,174 5 9,615 1c 10 19.231 1.977
_-
7 __ 7 13,462 1,384 e 8 15,385 1,581 14 14
~- 26,923 2,767
--
8C _ _ _ _80 153,846 15,813
- --
14 _ _ _ 14 ____ 26,923 2,767
._ ~-
____ 6 11.538 1.186 14 14 E
1C
_- 4 1
1E
-~
_.__
___ i 1: 2,570 11 21,154 2,174 2E 50,000 5,139 li 32,692 3,360
- I -~
STD DEV 0.01 I MAX 0.09 lofl
SECTION 7 ATTACHMENT 2 3 PAGE@)
BSI/LVSPipeCrawler-O02 Revision 4 Pipe Interior Radiological Survey Form Date: 2-9-d 6 Time : OBGJ-Pipe (-ZF PMX-L) Pipe Access Point
/f rf ID#: ipx m7 D i m e ter : Area: TlE-i-il H Building: -x Elevation: -27 System: R p V r n CCfQ M q ( i +
Type of Survey Investigation Characterization Final Survey -%- Other J Gross Co60 d cs Detector ID# / Sled ID# LV5-1 / /ol Detector Cal Date: //-/7-C F Detector Cal Due Date: 1I-/7- I9 6 Instrument: 23rO-/ Instrument ID #: z o 3 y f 30d Instrument Cal Instrument Cal Due Date: i-f 7 - 0 c Date: //.-I74 &
From the Daily Pipe Survey Detector Control Form for the Selected Detector Background Value )4,3 cpm MDCRStatIC / 6 / 4 cpm Efficiency Factor for Pipe 0-0 T> 052 (from detector efficiency determination)
Diameter f -9 I --
l V l Y Lstatlc /do / a mi f v u cm Is the PVfDCsUQcacceptable? & r ( i f n o , adjust sampie count time and recalculate MDW,)
Comments:
Technician Signature Pipe Interior Radiological Survey
I Position Feet into Pipe I from Opening
' Count Time (min)
Gross Counts Gross CPm Net cpm 1 dpd100crn'
BSI/LVSPipeCrawler-002 Revision 4 Pipe Interior Radiological Survey Form (Continuation Form)
Date: 2-g-o 6 Pipe ID#: j ~ 7& @ ~ 1 - I) Pipe Diameter: 4 I( Access Point Area: f72c13L.r M Building: QLx Elevation: '27 System: 4 x 2 j- I*T (ho n i k,G Package Page 2 of 3 REFERENCECOPY Attachment 3, Page 2
!
I I
t
SECTION 7 ATTACHMENT 3 1 PAGEIS)
I I i
~ - ~- ~ ~
DQA Check Sheet Design # Rx 127 Revision # Original Survey Unit # Rx 127 Preliminary Data Review 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 insbuctions in the Survey Design? X
- 2. Is the instrumentation 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 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 X static measurements or soil samples addressed in the survey design?
- 5. Was the instrumentation MOC for volumetric measurements and smear analysis < 10% DCGLw ? X 6.
7.
Were the MDCs and assumptions used to develop them appropriate for the instruments and techniques used to perfom the survey?
Were the survey methods used to collect data proper for the types of radiation involvedand for the IxI media being surveyed?
- 8. Were Speaal Methods for data collection properly applied for the survey unit under review? X Q. 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
- 7. 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 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 identified by scans and/or sampling, is the average activity in each X elevated area < D C G L w (Class l), < 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 statisticaltest (S+ for S i n Test or W, for WRS Test) 2 the critical value? X Comments:
Form CS-0912 Rev 0 Page 1 of 1
SECTION 7 ATTACHMENT 4 1 DISC
I I Survey Unit Release Record Design ## EP-Rx 148 1 Revision# 1 Original I Page 1 of 3 Survey Unit #(s) Rx 148
- 1) Embedded Pipe (EP) Survey Unit Rx 148 meets the definition of embedded pipe for Plum Brook Reactor Facility (PBRF).
- 2) EP Rx 148 is a Class 1, Group 2 survey unit as per the PBRF Final Status Survey Plan (FSSP) and Technical Basis Document (TBD)-06-004.
- 3) Surveys in EP Rx 148 were performed using a scintillation detector optimized to measure gamma energies representative of Co-60. Sample #EP 2-1 from Survey Request (SR)-13 was referenced for this decision.
- 4) Survey Instructions for this survey unit are incorporated into and performed in accordance with (IAW) the Babcock Services Incorporated (BSI)/LVS-002, Work Execution Package (WEP)05-006.Survey instructions described in this 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.
ipproval Signatures I Date:
ewewer -
FSS/Characterhation Manager -
Form CS-0911 Rev 0 tG=h li_l COPY
FSS Design # EP Rx 148 Revision # Original Page 2 of 3 1.0 HistoryDescription 1.1 The subject pipe system is the 4 Quad B system line.
1.2 EP Rx 148 consists of approximately 21 feet in length from the Reactor Building -25 elevation to Quad B.
2.0 Survey Design Information 2.1 EP Rx 148 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 21 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 20,430 cm2(2.0 m2) for the entire length of (2 1) 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 InvestigationsResdts 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 medyr 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 148 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 148 Revision # Original Page 3 of 3 Survey Unit: Rx 148 1
5.5 Statistical Summary Table Statistical Parameter Total Number of Survey Measurements 21 Number of Measurements >MDC 2 Number of MeasurementsAbove 50% of DCGL 0 Number of Measurements Above DCGL 0 Mean 0.0098 Median 0.0094 Standard Deviation 0.0019 Maximum 0.0129 Minimum 0.0060 6.0 Documentation of evaluations pextaining to compliance With the unrestricted use limit of 25 mrerdyr and dose contributions from Embedded Pipe and radionuclides contributing 10% in aggregate of the total dose for both structural scenarios and soils.
6.1 A review of the survey results has shown that the dose contribution for EP Rx 148 to be less than 1 mredyr. The dose contribution is estimated to be 0.010 mredyr based on the average of the actual gross counts.
7.0 Attachments Attachment 1 - BSI EPBP Survey Report Attachment 2 - Pipe interior Radiological Survey Form Attachment 3 - DQA Worksheet Attachment 4 - EP RX 148 S U R R & Spreadsheet Disc
SECTION 7 ATTACHMENT 1 2 PAGE(S)
BSI EP/BP SURVEY REPORT Survey Location Quad B I
Survey Date 11-Jan46 2350-1 # 134738 I
Sunrey Time 10:55 DetectorSled I 1MGl LVS-11101 Pipe Size 4" Detector Efficiency 0.00052 FDCGL-I Routine Survey I 2.41EN5 X
PipD&alllmPmmby-*Fcm5)
Field BKG(cpn)
Field MDCR1-i 973 22.2 19.3 Nominal MDC ~dpnn-) 1,557 I I Sumv Measurement fieSUltS Total Number of Survey Measurements 21 Number of Measurements>MDC 2 Number of MeasurementsAbove 50% DCGL 0
- Number of MeasurementsAbove DCGL Mean 0
. 3098 1 U.L.
Median 0.0094 Standard Deviation 0.0019 Maximum 0.0129 Minimum 0.0060 Survey Technician@)
I I I
COMMENTS:
ACTIVITY VALUES NOT BACKGROUNDCORRECTED
. I 711512007
=.
EP Rx 148 4 Pipe TBD 06404 Group 2
- I CI I I I I I I I I C
E Cos0 activity Co-60 activity Cr-137 activity Eu-152 activity Eu-IS4 actlvity Nb94 activity Ag-108m activity La ncpm (totaidpm) (dpmllOOcm2) (dpmllOOcm2) (dpmllOOcm2) (dpm1100cm2) (dpmlIWcm2) (dpml100cm2)
QD J ,
__.____-
1,977 _- 1,025 16 - 12 1 57 0.009
_____-.
15 . 1 74 0.01 1
-13 1 ____ 63 0.009 0.012 16 1 80
____.
__ -
2.174 -
-
--
___- 2,174
-
- 1,127 18
~.
-____ 2,767 - 1,435- 23 12 13 13 25:OOO - 2,570 . 7,332 21 13 9 9 17.308 1,779 - _ 922 15
- 2,965 1,537 25
-. _~___ - 1,384 717 11 16 12 12 -- ____ 2,372 1,230 ___ 20 17 10 10 19.231 ___ ~ 1,977 1,025 16
-
- 18 15 15 281846 -___- 2,965 _- 1,537 25 19 10 - 10 19,231 - 1,977 1,025 16 0.009 20 13 13 25,000 - 2,570 - 1,332 21 21 . 13 13 25,OOT 2.570 1.332 21 1 of 1
SECTION 7 ATTACHMENT 2 3 PAGE(S)
.-
I Pipe Interior Radiological Survey Form Date: t - / f -06 Time: 1UJ-3 Building: 47% Elevation System: Bdc,t a ) ~ ( r p , % c L 7 3 Pipe Diameter:
- 2, 4 if Access Point Area: Pipe JD QLw0 L3 Type of Survey Invesigation Characterization a inal sun;$ # Other IZk /%?
rM Sled Size O&&IUE / 01 inch Detector: 13Kmd irn6-I Detector ID #: L V S -1 Cal Date: 1 L-Le -Of Cal Due Date: /2-- 20-06 Instrument: 3577 -I Instrument ID #: /3V7JB Cal Date: / L-2 0 Cal Due Date: /-U -0 L From the Daily Pipe Survey Detector Control Form for the Selected Detector Background Value 22-Rcpm 17.3 MDCRstatic Efficiency Factor for Pipe CPm
-
0 000- (taken from detector M e tstatlc er 1557 d p d l OOcm Is the MDC,,,,, @ No (if no, adjust sample count tune and recalculate
~ -- MDCR,,)
_---
c$jiE.@e ?
Pipe Interior Radiological Survey Radiological Survey Commenced: Date:
Package Page 1 of&
- REFERENCE COPY 0 -4ttachment 3, Page 1
Package Page &of 0
REFERENCE COPY Attachment 3, Page 2
i SECTION 7 ATTACHMENT 3 I PAGEIS)
t I DQA Check Sheet Design # EP Rx 148 Revision # Original Survey Unit # EP Rx 148 Preliminary Data Review' Answers to the following questions should be fully documented in the Survey Unit 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 1 and 2 X survey units, or below 0.5 DCGLw for Class 3 suwey units?
- 3. Is the instrumentation MDC for embeddedhuried piping static measurements below the DCGLw ? X
- 4. Was the instrumentation MDC for strudure 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 wrform the-~ survev? ~
- 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 'SDecial Methods" for data collection properly applied for the survey unit under review? X
- 9. Is the data set comprised of qualified measurement results collected in accordance with the survey 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 cteated? 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 8 2), or 0.5 DCGLw (Class 3)? X
- 2. Is the mean of the sample data DCGLW? X
- 3. I f elevatedareas 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 . DCGLw 5 (Class 3)?
- 4. Is the result of the Elevated MeasurementsTest 1.O? X
- 5. Is the m u t t of the statistical test (S+ for Sign Test or W, for WRS Test) 2 the critical value? X Comments:
El r
CS-09/2 Page 1 of 1
SECTION 7 ATTACHMENT 4 1 DISC
Design # EP-Rx 152 Revision # Original Page 1 of 3 Survey Unit #(s)
- 2) EP Rx 152 is a Class 1, Group 2 survey unit as per the PBRF Final Status Survey Plan (FSSP) and Technical Basis Document (TBD)-06-004.
- 3) Surveys in EP Rx 152 were performed using a scintillation detector optimized to measure gamma energies representative of CO-60. Sample #EP 2-1 fiom Survey Request (SR)-13 was referenced for this decision.
- 4) Survey Instructions for this survey unit are incorporated into and performed in accordance with (LAW) the Babcock Services Incorporated (BSI)/LVS-002, Work Execution Package (WEP)05-006. Survey instructions described in this 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:
FSS/Characterhlion Engineer COPY
FSS Design # EP Rx 152 Revision # Original Page 2 of 3 1.0 HistoryDescription 1.1 The subject pipe system is the 3 Quad BDe-ionized (DI) water line.
The function of this pipe was to convey DI.
1.2 EP Rx 152 consists of approximately 21 feet in length from the Reactor Building -25 elevation to Quad B.
2.0 Survey Design Information 2.1 EP Rx 152 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 21 survey measurements.
2.3 Surface area for the 3 ID piping is 729.7 cm2for each foot of piping, corresponding to a total 3 ID piping surface area of 15,330 cm2(1.5 m2) for the entire length of (21 ) of 3 piping..
3.0 Survey Unit Measurement LocatiodData 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 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 152 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 I I FSS Design # EP Rx 152 Revision # Original Page 3 of 3 5.5 Statistical Summary Table Statistical Parameter r I
~~
Total Number of Survey Measurements I 21 Number of Measurements >MDC 8 Number of Measurements Above 50% of DCGL 0 I I I Number of Measurements Above DCGL 0 Mean 0.011 Median I 0.011 I Standard Deviation 0.003 Maximum 0.018 Minimum I 0.007 I 6.0 Documentation of evaluations pertaining to compliance with the unrestricted use limit of 25 mredy-r and dose contributions from Embedded Pipe and radionuclides contributing 10% in aggregate of the total dose for both structural scenarios and soils.
6.1 A review of the survey results has shown that the dose contribution for EP Rx 152 to be less than 1 mredyr. The dose contribution is estimated to be 0.01 1 mredyr based on the average of the actual gross counts.
7.0 Attachments Attachment 1 - BSI EPBP Survey Report Attachment 2 - Pipe Interior Radiological Survey Form Attachment 3 - DQA Worksheet Attachment 4 -Disc containing RR for EP Rx 152 82 Spreadsheet
SECTION 7 ATTACHMENT 1 L- PAGE(S)
~~
Maximum 0.01a I I I
I COMMENTS:
A C T M M VALUES NOT BACKGROUND CORRECTED 6/12/2007
SECTION 7 ATTACHMENT 2
$ PAGE(S)
I .-
I Pipe Interior Radiological Survey Form Date: 19- / A b S Time:
i%
- %
df&
Building:
?:&
t Type of Survey a 4 6 u
Investigation (d
Elevation:
Pipe Diameter:
Characterization c3f Accesspoint Area:
_=
Final Surve
.3 P(pe r~:r ,$%%>
j?
Lf 15-3 Sled Size 3 / inch Detector: Lcy-4 % Detector ID #: &Jqq 3 7 +fN Cal Date: //
, , / 7 . 03- Cal Due Date: / ) - / 7
- d Instrument: 2 3 5&I-( Instrument ID #: 3 02 a 3 Cal Date: f / . / ?
- 8s- Cal Due Date: //- / 3 4 6 From the Daily Pipe Survey Detector Control Form for the Selected Detector Backg-roundValue fc 2 cpm m c k t a h c pr Efficiency Factor for Pipe Diameter 2 W-Z m/100cm2 MDcstatic Is the MDC,,a,, acceptable?
Comments:
& No (if no, adjust sample count time and recalculate MDCR*&
Pipe Interior Radiological Survey Radiological Survey Commenced: Date: /3
- 13 OrTke:
I Pipe Interior Radiological Survey Form (Continuation Form)
I I 1 I I I I Package Page 2of 2 REFERENCE COPY Attachment 3, Page 2
\9 c-,.
-c P-II
i Pipe Interior Radiological Survey Form Date: / L-/3 '0 f Time: /05=
Elevation: - z >- Access Point Area: 0, c t m n Pipe Diameter: 3 '(
Type of Survey Investigation Characterization Other 7 Sled Size 3 '( inch Detector: yY-& 7 Detector ID #: 2 0 Y vc 2 - 1 DI Cal Date: //-17-0 5 Cal Due Date: //77 4 3 6 Instrument: 2 3 \m-\ Instrument ID #: 2Jzzz3 Cal Date: //-/7-0>- Cal Due Date: //-f7-d 6 From the Daily Pipe Survey Detector Control Form for the Selected Detector BackgroundValue 5.L cpm MDCRStatlC 181 B CPm Efficiency Factor fo; Pipe Diameter z 84 3A m/100cm2
&
MDCStahC Is the MDC,,,, acceptable? No (if no, adjust sample count time and recalculate MDCK,,,)
Comments: 7/r2Jc(4 P f d o c PIP6 5ul) />4d?l4 /L-/z - c 4 I
Pipe Interior Radiological Survey Radiological Survey Commenced: Date: / L-f3 - 6 Time: 1 3 ) v Package Page 1 o f 1 Attachment 3, Page 1
SECTION 7 ATTAC-NT 3 PAGE(S)
Design # EP h l 5 2 Revision # Original Survey Unit # EP Rx152 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 instrumentationMDC 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 embeddedhuriedpiping 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 radiationinvolved and for the X
-
media beina 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 mated? 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 I& 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 identifiedby scans andor sampling, is the average activity in each X elevated area < DCGLEMC (Class I),DCGLW(Class 2), or e0.5 DCGLw (Class 3)?
- 4. Is the result of the Elevated Measurements Test I.O? X
~~
- 5. Is the result ofthe statisticaltest (S+for Sign Test or W, for WRS Test) 2 the uitical value? X Page 1 of 1
SECTION 7 ATTACHMENT 4 1 DISC
I Design # EP-Rx 157 Revision # Original Page 1 of 3
~
Survey Unit #(s)
- 2) EP Rx 157 is a Class 1,Group 1 survey unit as per the PBRF Final Status Survey Plan (FSSP) and Technical Basis Document (TBD)-06-004.
- 3) Surveys in EP Rx 157 were performed using a scintillation detector optimized to measure gamma energies representative of Co-60. Sample #EP 3-9 fiom Survey Request (SR)-13 was referenced for this decision.
- 4) Survey Instructions for this survey unit are incorporated into and performed in accordance with (LAW) the Babcock Services Incorporated (BSI)/LVS-002, Work Execution Package (WEP)05-006. Survey instructions described in this 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 FSS Design # EP Rx 157 Revision # Original Page 2 of 3 1.o History/Description 1.1 The subject pipe is the drain line from the dry annulus inside the CV to the drain trench on the Rx Building -25 foot elevation.
1.2 EP Rx 157 consists of 4" diameter piping that is approximately 5 feet in length.
2.0 Survey Design Information 2.1 EP Rx 157 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 5 survey measurements.
2.3 Surface area for the 4" ID piping is 973 cm2for each foot of pi ing, 4
corresponding to a total 4" ID piping surface area of 4,864 cm (0.5 m2) for the entire length of (approximately 5 ' ) of 4" piping..
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 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 I.
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 157 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 157 Revision # Original Page 3 of 3 5.5 Statistical Summary Table Statistical Parameter
-~
Total Number of Survey Measurements 5 Number of Measurements >MDC 4
~ ~
Number of Measurements Above 50% of DCGL 0 Number of Measurements Above DCGL 0 Mean 0.0288 Median 0.0307 Standard Deviation 0.0064 Maximum 0.0337 I Minimum I 0.0184 I 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 157 to be less than 1 mredyr. The dose contribution is estimated to be 0.029 mredyr based on the average of the actual gross counts measured.
7.0 Attachments Attachment I - BSI EPBP Survey Report Attachment 2 - Pipe Interior Radiological Survey Form Attachment 3 - DQA Worksheet Attachment 4 - EP RX 157 S U R R & Spreadsheet Disc
I I
SECTION 7 ATTACHMENT 1 z PAGE(S)
BSI EPIBP SURVEY REPORT Pipe ID I Rx 157 Survey Location cv -25el.
Survey Date 2350-1 # 1890%
survey rime 13:17 DedectorSJed# 44-159D38369-101 Total Number of Survey Measurements 5 Number of Measurements >MDC 4 Number of MeasurementsAbove 50%DCGL 0 Number of Measurements Above DCGL 0 Mean 0.0288 Median 0.0307 Standard Deviation 0.0064 Maximum I 0.0337 Minimum 0.0184 STOCK Survey Technician(s)
COMMENTS:
ACTIVITY VALUES NOT BACKGROUND CORRECTED 711512007
EP Rx 157 4" Pipe TBD 06-004 Group 1 iL CI C
Q)
E 3 gcpm ncpm C0-60 activity (total dpm)
C0-60 activity (dpm1100cm2)
Cs-137 activity (dpmllO0cm2)
Eu-152 acUvky (dpm1100cm2)
Eu-154 acUvity (dpm110Ocm2)
Nb94 actlvfty (dpm1100cm2)
IAglOBm activity (dpmllOOcm2)
Unity 3
8 1 9 9 45,000 4,625 183 4,388 1,166
- -. 135 2 10 10 50,000 5,139 204 4,875 1,296 150 3 11 -~11 55,000 5,653 224 5,363 1,426 165
__- -
4 11 11 55w- 5,653 _ _ -
224 5,363 1,426 165 5 6 6 30,000 3,084 - 122 2,925 778 90
- - __
__-.
0.02!
-
MEDIAN 0.03'
__- _- - . _ _ _ _ _ ~
STD DEV 0.01I 1 of1
SECTION 7 ATTACHMENT 2 3 PAGE(S)
P BSILVSPipeCrawler-002 Revision 4 Pipe Interior Radiological Survey Form Date: Time:
7/.t/b 6 1317 1 62 /,s7 mr\Cl 1/L I-U2FS*
I)
Pipe ID#: Pipe Diameter: Access Point Area: AR/WLG~
Building: <L/ Elevation: -ZS' System:
Type of Survey Investigation Characterization Final Survey Other Gross cs Detector ID# / Sled ID#
c060 --G 49 - (2'1 2 3 T 3 6 9 i /oI Detector Cal Date: 9-/&/o E, Detector Cal Due Date: 3/6/0 7 Instrument: 7 3 saL/ Instrument ID #: f 5#o/m+
Instrument Cal Date: 3//,/or2 c
Instrument Cal Due Date: 7//d o 7 l
From the Daily Pipe Survey Detector Control Form for the Selected Detector Background Value 12 ,3 cpm MDCRstaoc 15.1 cpm Efficiency Factor for Pipe Diameter 6,000 a (from detector efficiency determination)
M-DCStatlC
- - - - - 404q - -
1s m t stabc ~LL-' e and recalculate MUCRm c )
Commciits: Zdl mypL C3W=,G=
Technician Signature Pipe Interior Radiological Survey Package Page 1 of z 0 REFERENCECOPY Attachment 3, Page 1
I
!
SECTION 7 ATTACHMENT 3 I PAGE(S)
DQA Check Sheet
~ ~~
Design # EP Rx 157 Revision# Original Survey Unit #l EP 157 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 structuk 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 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.
7.
Were the MDCs and assumptions used to develop them appropriate for the instruments and techniques used to perform the survey?
Were the survey methods used to coflect data proper for the types of radiation involvedand for the Ixl I media beinn 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?
~
- 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 DoGl Analysis
- 1. Are all sample measurements below the DCGLW(Class 1 & 2), or 0.5 DCGLw (Class 3)? 1 x 1 1
- 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), 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) 2 the critical value? X Form cs-o9/2 Rev 0 Page 1 of 1
SECTION 7 ATTACHMENT 4 1 DISC
.
Survey Unit Release Record
~- -
1 I I Page
~~ ~
Design # EP-1.31 Revision # Original 1 of 3 survey Unit kys) 1.31
- 1) Embedded Pipe (EP) Survey Unit 1.31 meets the definition of embedded pipe for Plum Brook Reactor Facility (PBRF).
- 2) EP 1.3 1 is a Class 1, Group 2 survey unit as per the PBRF Final Status Survey Plan (FSSP) and Technical Basis Document (TBD)-06-004.
- 3) Surveys in EP 1.31 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 BSI/LVS-002, WEP 05-006, these determinations are appropriate for the types of radiation involved and the media being surveyed.
Approval Signatures Date:
w CQPY
FSS Design # EP 1.3 1 Revision # Original Page 2 of 3 1.0 HistoryAIescription 1.1 The subject pipe system is the 3 purge line for Quad D. The function of this pipe was to convey water from the one 3 inch riser in Quad D to the HD sump in Pump Room #22 on the Rx Building -25 ft, where the pipe is currently breached.
1.2 EP 1.3 1 consists of approximately 150 feet in length f h m the pump room to the riser in Quad D. The pipe section has approximately eight elbows ranging from 45 to 90.
2.0 Survey Design Information 2.1 EP 1.31 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 141 survey measurements.
2.3 Surface area for the 3 ID piping is 729.7 cm2for each foot of pi ing, P
corresponding to a total 3 ID piping surface area of 102,930 cm (10.3 m2) for the entire length of (141) of 3 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 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 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 1.3 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 1.3 1 Revision # Original Page 3 of 3 5.5 Statistical Summary Table 3
Statistical Parameter Pipe I
I Total Number of Survey Measurements 141 Number of Measurements>MDC 0 Number of MeasurementsAbove 50% of DCGL 0 Number of MeasurementsAbove DCGL 0 Mean 0.020 Median I 0.020 1 Standard Deviation 0.006 Maximum 0.038 I Minimum I 0.008 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 1.31 to be less than 1 mredyr. The dose contribution is estimated to be 0.020 mredyr based on the average of the actual gross counts measured.
7.0 Attachments Attachment 1 - BSI EP/BP Survey Report Attachment 2 - Pipe Interior Radiological Survey Form Attachment 3 - DQA Worksheet Attachment 4 -Disc containing RR for EP 1.3 1 & Spreadsheet
- SECTION 7 ATTACMENT 1 (n PAGE(S)
BSI EPIBP SURVEY REPORT Survey Measurement Results Total Number of Survey Measurements 141 Number of Measurements >MDC 0 Number of Measurements Above 50% DCGL 0 Number of Measurements Above DCGL 0 Mean 0.020 Median 0.020 Standard Deviation 0006 Maximum 0 038 Minimum 0.008 ROSENHAGEN Survey Technician($)
SR-13 Radionudde Distribution Sample EP 2-1 Measured N u d i Co60 Area FadorEMC Used No Pass/Fail FSS Pass MREMNR Contribution <l
~~
COMMENTS:
ACTIVITY VALUES NOT BACKGROUND CORRECTED RP Engineer I Date 6/11/2007
EP 1.31 3" Pipe TBD 06-004 Group 2
-
C0-60 activity ncpm19~ (total dpm) 63.333 1 1 c060 activtty (dpm1100cmZ) 8.679 Cs-137 activity (dpm1100cmZ) 4.505 Eu-152 activity
..
72 Eu-I54 activity (dpmllOOcm2) 51 Nb-94 actlvity (dpmllOOcm2)
Ag-lO8m activity (dpmllOOcm2)
-
Unity 0.03
-_ _
30,000 4,111 __ 34 24 ___0.01
__
5339 ______ 49 ~ _ 35
_ _ 0.02E 30,000 4,111 34 24 -~ 0.011 43.333 5.939 3.082 0.02E
~ 261667 3,654 1,897 0.01E
___- 53,333 7,309 3,793 0.03; lf9 30.000 4.111 2.134 -- 0.011
____ 14
- -.
____46:667 __6,395 3,319 -~
0.02E 15 50,000 6,852 3,556
-- -_ __ 40 0.03C 14 46,667 6,395 3,319 38 0.02 11 36,667 5,025 2,608 0.02;
____ 7 23,333 3,198 1,660 _
0.011 I _
8 26.667 3.654 1,897 ______ 30 O.OlE 45 ~ _ _ - _ 0.021
_
22 --
0.02 30 __-0.02;
-_ 0.02;
_-
~
0.01:
_-
_0.02;
_
0.05
- __
~- _ 0.02(
_ -
19 -0.01(
._---
0.02:
It _ _0.03;
-
- O.Olt
-00%
lr 0.02I 1' -0.02:
__
1' __ 42 0.02:
I -
30 -- 0.0lt t 23 16 0.01:
EP 1.31 3" Pipe TBD 06-004 Group 2 i I Cd)o activity Cs-137 activity Eu-152 actlvity Eu-154 activity Nb-94 activity Ag-lO8m activity ncpm (dpmllOOcm2) (dpmllWcm2) (dpml100cm2) (dpm1100cm2) Unity (dpmllODcm2) (dpmllOOcm2)
~
-33 6 6 20,000 2,741 1,423 79
- 0.01:
34 11 11 36,ssf ___-5,025 2,608 42 146 0.02; 35 9 9 4,111 2,134 2 119 0.01f 36 14 14 _-_____ 46,667 -__ 6,395 -~ 3,319 53 3 185 0.02t 37 9 s 30,000 4,111 ___.2,134 - --
119 0.01t I
38 9 E 30,000 4,111 2.134 _ --
119 -0.01 t
- - --~.
._
39 9 E ~- 30,000 4,111 2,134 -~ ~
119 -__-
0.01t
- 40 7 7 ______23,333 3,198 1.660 93 -__0.011 41 13 1: 43,333 5,939 3,082 172
__ 0.02f 43,333 _______ 5,939 - 3,082 172 0.02t 60,000 8,223 4,268 230 0.03(
- ~- 36,667 5.025 ___ .__ 2,608
.- ~ - --0.02:
45 18 __-_1E _ _ 60,000 _ _ _ ~ 8,223
__ 4,268
- .- -~0.03f
--
46 6 f ~ 20,000 2,741 1,423 0.01:
- _--
47 7 i 23,333 __ 3.198 1,660 0.014 48 9 I 30,000 4,111 2,134
-.
0.011 49 14 14 46,667 6,395 3.319
___ 185 0.021 50 12 1i _____- 40,000 5,482 2,845 159 0.024 51 11 11 ____- 36,667 5,025 2,608 0.02:
52 13 1: 43,333 __ _.__ _ _ ~3,082 5,939 _ _ -_0.02(
-
53 13 1: ~ 43,333
_ _ _ 5,939 - - _-- 3,082--
0.02(--
54 5 -
I 16,667 2,284 _ _ _ 1,185 - -
0.01I 55 14 - I d 46,667 6,395 _ _ _ -3,319 _0.021
_
56 8 t 26,667 -~ 3,654 _____- 1,897 __ __0.011 57 10 1( 33,333 4,568 2,371 0.02i
- -. ~- __ .___ __
__58 13 -
1:
-
43,333 5,939
____ 3,082
-- - 0.02(
__
59 4 13,333 1,827 ____ 948 - 0.001
-
1
___ -- --
60 8 1 26,667 3.654 ____ 1,897
_ -~
0.011
- -~
5 ~. ! 16,667 2,284 1,185 0.011
_ _61
-
____ - ~
0.028
~
62 12 -___1: - ~-
40,000 5,482 - 2,845 -
63 12 1: 40,000 5,482 2,845 0.021
EP 1.31 3 Pipe TBD 06404 Group 2 CS-137 activity Eu-152 actlvlty Eu-164 activity Nb-B4 activity Ag-I 08m activity (dpm/lOOcm2) (dpmllOOcm2) (dpmll00cm2) (dpm1100cm2) (dpm/100cm2) Unity DO I 4.111 -~ 2,134 34 2 119 0.018 2,134 2 119 -~ 0.018 20,000 2,741 - 1,423 1 79 0.012 23,333 3,198 - ~ 1,660 _ _ 2
.- -__ 93 0.014 23,333 3,198 -___1,660 __ 2 -
93
__ 0.014 12 12 40.000 5.482
__ 2,045 _ 159 0.024 12 12 40,000 _ _ _ _5,482
_ 2,045 _______45 159 0.024-4 4 _ _ _ ~-
13,333 1,827 948 15 ._
1 53.- -0.008
__
12 12 40,000 5,482 2,845 _ _ _ 45 _____ 32 3 ~
159
- -. 0.024 12 12 40,000 5,482 2,845 45 32 3 159
._ 0.024 10 10 33,333 4,568 2,371 ~ - _ _ 38 ~~
2 132
- 4 4 13,333 1,827 -____ 948 15 1 53 9 9 30,000 4,111 _ _ _ _ ~ _ 2,134
__ 34 9 9 30,000 4,111 _______2,134
___- 34 _ _ 24
_ ~
10 10 33,333 4,568
__ 2,371
-__ 38 27 10 10 - 33,333 4,568 2,371 ._
2-9 9 30,000 4,111 2,134 2 8 8 _-
26,667 3,654 1,897
-
11 11 36,667 5,025 ___ 2,608 9 9 30.000 4.111 2,134 1,423 16 2,134 24 9 9 30:OOO 4,111 2,134 - ~ _ _24 _
9 9 30,000 4,111 2,134 24 6 6 20.000 2.741 ~~~
1,423 16
- 3,319 - - - _ 185 3,082 172
_ 1,897 ~
30
~- 3,082
___ 49 1,897 30 22 2 106
EP 1.31 3" Pipe TBD 06-004 Group 2
-
Co-60 activity Cos0 activity Cs-137 activlty Eu-152 activity Eu-154 acttvity Nb-94 activlty Ag-108111activity ncpm (totaldpm) ( d p d lOOcm2) ( d p d l OOcm2) (dpmllOOcrnZ) (dpm1100cm2) ( d p d lOOcm2) (dpdl00cm2) Unity 9 4,111 2.134 ~ - _ 34
_ - 2
- 0.01t
___
-___ 9 4,111 34 2 0.01t 12 40,000 5,482 ______ 3 0.02r 11 36.667 _____.-
5,025 2.608 42 2 0.02:
14 - 461667 6,395
__ ~
3 _0.02t
___
1: 13 43.333 5,939 ___- 35 3 _0.02f
_
f E 16.667 2,284 ~~
13 I 0.011
- __
1 7 23,333 3,198 27 ~~
19 0.011 1' 11 36.667 5,025 2.608 42 30
._
0.02:
1' 11 ____._ 361667 5,025
- 42 30 146 0.02:
4.1 11 --%+---34
$
$
1 E
7 E
30,000 23,333 30,000 3,198 4.111 1,860-27 2.134 34 24 19 24 2
2 119 93 119 0.01I 0.011 0.01t E 20,000 2,741 1 79 -~0.01; 1; 1: 40,000 5,482 3 159 0.021 1' 11
.- 36,667- 5,025 2- ~ _ _ _ 146
_ 0.02; l( 1c 33,333 4,568 2 132 0.02(
__--
1: 1: 43,333 5,939
___ 3 172 0.02f 1 7 23,333 3,198 19 0.01A I E 26,667 3,654 22 0.01f t 26,667 3,654
-~ 0.01f
-~
1' 36,667 5,025
-~ 0.02:
l! 50,000
_-_ 6,852 _-0.03
_ -
1' - 36,667
- -- -___
5,025
__ _____. 30 2 -~0.02:
E 20,000 -____ 2,741
--
16 1 0.01:
E -__ 30,000 4,111 - ___24 2 0.011
__-
26,667 3,654 22 2 __0.01t
- 30,000
~ _- __-_- 4,111 0.01f
___
26,667 3.654 0.01t
__
- __ 40,000
_.
5.482 --0.02r 33,333 4,568 - 0.02(
EP 1.31 3" Pipe TBD 06-004 Group 2
- U C
E Co40 activity Cod0 activity Cs-I37 activity Eu-152 activity Eu-164 activlty Nb-94 acUvtty Ag-lO8m activity a gcpm ncpm (total dpm) (dpml1W)cmZ) (dpm1100cm2) (dpm1100un2) (dpm1100cm2) (dpm1100cm2) (dprn1100cmZ)
Y) 1 z
125 6 6 20,000 2,741 1,423
- ___.__-- ___ 23 16 1 79 126 7 7 ___23,333 - 3,198 1,660 27 19 2 93 127 7 7 23,333 3,198 1,660 27 19 2
- _- -__ ~- 93 128 13 13 43,333 5,939 3,082 49 _ _ _ _ 35 _ _ -_- -__ 3 _____ 1 72
__
129 130 131
~
6 5
6 6
5 6
20,000 16,667 20,000 2,741 2,284 2,741 1,423
__--. _- -_- -
1,185
_____
1,423 23
_-___ 19__ ~-
23
__ 16_ _
13 16 1
1 1
-
~
79
___
66 79 E]
0.012 0.010 0.012 132 6 __
6 20,000 2,741 1,423 ____-_______ 23 16 __ - _ 1_ _ 79 0.012
-133 12 12 40,000 5,482 2,845 155
- __ 45 _ _ _ 32_ ~ _ _ - - _ _3_ -
- 134 15 15 50,000 6,852 3,556 57 .- 40 __- 3 199
-
135 9 9 30,000 4,111 ______.
2,134 __ 34- - _ _ 24 __ - 2 119 136 9 9
- 30,000
_ _- - 4,111 .- __- 2,134 34 . _ 24
_ __ - 2 119 137 17~ _ _17_ 56,667 7,766 4,030 64 46 4 225
___ - ...- -
138 11 11 36,667 5,025 __ 2,608 42 30 2 146 139 10 10 33,333 4,568 2,371 38 27 2 132 140 16 16 53,333 7,309 3,793 61 43 4 ~
212
__ 0.032 141 14 14 46,667 6,395 3,319 53 38 3 ~~
185
_ _ _ _ ,
_____- ____ ~ . . _- _ - ~ ~ ___ MEAN
~ - - -_-__ ~ ____ - _ _ MEELAN-- --
__ - - ____ ~_ .- __--
-~ STODEV -- 0.006
- __ MAX
_ _ - ~
MIN 5 of 5
SECTION 7 ATTACHMENT 2 1 1 PAGE(S)
BSYLVSPipeCrawler-002 Revision 4 Pipe Interior Radiological Survey Form Date: 715-p6 Time: /o 2 %r Pipe ID#: 1.3 / Pipe Diameter: 3.0 Access Point Area: 4 7 T Z r F 4 Building: -@ Elevation: - 27 System: D(2fifl5 Type of Survey Gross Investigation Co60 Characterization Finalsurvey cs Other -
Detector ID# / Sled ID# -
M f S 4 & Z 3 r 3 6 9 I I2.I Detector Cal Date: 3/6/0 6 Detector Cal Due Date: 3/~/4 Instrument: z3m- I Instrument ID #: IgqDq4 Instrument Cal Date: 3 irr/loG Instrument Cal Due Date: 3 I
/ f r/o I
,
From the Daily Pipe Survey Detector Control Form for the Selected Detector Background Value 13 9 cpm MDcIistatic 15.9 CPm
-
Efficiency Factor for Pipe Diameter 0 00 03 (from detector efficiency determination) 12(0,83 dpd 1 cm2 mcstatic Is the MDCSkticacceptable? a No (if no, adjust sample count time and recalculate MDCR,,,,,)
Comments: f~,zc/,zri f i P 2 -,3 1 I Technician Signature Pipe Interior Radiological Survey l!&iia@
SERVICES JNC.
0 REFERENCE COPY Package Page 1 of&
Attachment 3, Page 1
BSYLVSPipeCrawler-002
-
Revision 4 Pipe Interior Radiological Survey Form (Continuation Form)
Date:
Pipe ID#:
?/slob 183 t Pipe Diameter: 343 " Access Point Area: -2 7 I r w Building: 7 Elevation: -27 I System:
Package Page L
-. of 7
__
REFERENCE COPY Attachment 3, Page 2
BSYLVSPipeCrawler-002 Revision 4 Pipe Interior Radiological Survey Form Date: 7 /C/O 6 Time: 1313 Pipe ID*: 1 ~ 13 Pipe Diameter: 3.0 Access Point Area:
Building: t Elevation: -2s' System:
Type of Survey Investigation Characterization Final Survey,)( Other Gross Co60 cs -
Detector ID# I Sled ID# f f - / S f ZW369 I 1 Z{
Detector Cal Date: 3 f G bG Detector Cal Due Date: d6h 7 Instrument: 2 3 sa - I Instrument ID #: /flow Instrument Cal Date: 3//sJd 4 Instrument Cal Due Date: 3//s/o 7 From the Daily Pipe Survey Detector Control Forrn for the Selected Detector Background Value 13. 9 cpm MDCRSktlC 115. 9 CPm Efficiency Factor for Pipe Diameter 0 'I9 0 03 a (fiom detector efficiency determination)
MDcstatlc 12683 d p d !f7m cm2 Is the MDCSbhcacceptable? m- No Gf no, adjust sample count time and recalculate MDCR,,,,,)
Comments:
Pipe Interior Radiological Survey Technician Signature &
Package Page 1 o f 3 REFERENCE COPY Attachment 3, Page 1
BSI/LVSPipeCrawler-002 Revision 4 Pipe Interior Radiological Survey Form (Continuation Form)
Date: 7/r/b 6 Pipe ID$: !'3/ Pipe Diameter: Access Point Area: E - ,L~.h//et Building: .,
6 V Elevation: System: nr2t+tn)s Package Page -7 of __ 3 Attachment 3, Page 2 BEHWIGPS INC.
BSVLVSPipeCrawler-002
-
Revision 4 Pipe Interior Radiological Survey Form Date: 7/6/06 Time: OW0 Pipe ID#: ?/ Pipe Diameter: 2,o Access Point Area: act,,+D Building : CV Elevation: -2s' System:
Type of Survey Investigation Characterization Final Survey '>( Other L, Gross Co60 c/' cs Detector ID# / Sled ID# 15 7 ' Z383Lq / 121 Detector Cal Date: 3/6 /o G Detector Cal Due Date: 3/6h 7 Instrument: 2350 -I Instrument ID #: fsL9094-Instrument Cal Date: 3// b-16 G Instrument Cal Due Date: 3/[5/07 e . .
From the Daily Pipe Survey Detector Control Form for the Selected Detector Background Value 1.7 cpm MDCRStatlC 14,8 cpm Efficiency Factor for Pipe Diameter 0. 0 00 3 (&om detector efficiency determination)
MDCSLtlC i2be;3 Is the MDCshbcacceptable? & A0 00 cm2 (If no, adjust sample count time and recalculate MDCbaUc)
Comments: mf ,,omPd SUlzvEd: E?Z- 3 CQ)WPLI?T=
Technician Signature Pipe Interior Radiological Survey 5
Package Page 1 of __
REFERENCE COPY Attachment 3, Page 1
BSYLVSPipeCrawler-002
-
Revision 4 Pipe Interior Radiological Survey Form (Continuation Form)
Date; Pipe ID#:
Building:
7/hk,b
'2 Pipe Diameter:
Elevation:
3.0" Access Point Area: a
-2s' System:
Package Page 5 of __
REFERENCE COPY Attachment 3, Page 2
BSLLVSPipeCraw-ler-002 Revision 4 Pipe Interior Radiological Survey Form (Continuation Form)
Date: y,/~!o~
Pipe ID#: I I 3 I Pipe Diameter: 3 .o I Access Point Area: QU,q i>
Building: <I/ Elevation: - 2s System: iWr+f#Y 0 REFERENCE COPY Package Page - 3 of __
J Attachment 3, Page 2
. . . . . . _ _ _ _ . . .. 1
. ._,. I SEE bWG.
I
- PF- 0031 6 I
SECTION 7 ATTACHMENT 3 I PAGE(S)
DQA Check Sheet Design # EP 1.31 Revision # Original Survey Unit# I EP 1.31 Preliminary Data Review' 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 instrumentation 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 embeddedlburiedpiping static measurements below the DCGLw ? X
~
4.
5.
Was the instrumentation MDC for structure scan measurements, soil scan measurements, and embeddedhuriedpiping 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 c 10%DCGLW?
~~ ~
I I l1 xX
- 6. Were the MDCs and assumptions used to develop them appropriatefor the instrumentsand 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 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 collected in accordance with the survey X design, which accurately reflects the radiological status of the facility?
Gmphlcal Data Review
- 1. Has a posting plot been created? X
- 2. Has a histogram (or other frequency plot) been created? X
- 3. Have other graphical data tools been created to assist in analyzing the data? X Data Anslysir
- 1. Are all sample measurements below the DCGLw (Class 1 8 21, or 0.5 DCGLW(Class 317 1 x 1
- 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 DCGLEMC (Class 11, < DCGLW(Class 21, or ~ 0 . DCGLw 5 (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 W, for WRS Test) 2 the critical value? X Comments:
FSS/CharacterizationEngineer (printlsign) Date 6 ./i;,o?
FSS/ CharacterizationManager (printlsign) R. Case Date 7/3/17 Page 1 of 1
SECTION 7 ATTACaMENT 4 I DISC
Survey Unit Release Record Design # EP-1.33 I Revision # I Original I Page 1 of 3 Survey Unit #(s) 1.33
- 1) Embedded Pipe (EP) Survey Unit 1.33 meets the definition of embedded pipe for Plum Brook Reactor Facility (PBRF).
- 2) EP 1.33 is a Class 1, Group 2 survey unit as per the PBRF Final Status Survey Plan (FSSP) and Technical Basis Document (TBD)-06-004.
- 3) Surveys in EP 1.33 were performed using a scintillation detector optimized to measure gamma energies representative of CO-60. Sample #EP 2- 1 from Survey Request (SR)-13 was referenced for this decision.
- 4) Survey Instructions for this survey unit are incorporated into and performed in accordance with (IAW) the Babcock Services Incorporated (BSI)/LVS-002, Work Execution Package (WEP)05-006. Survey instructions described in this 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 1 CS-0911 I
0 COPY
I I Page 2 of 3 Survey Unit: 1.33 1.o HistoryDescription 1.1 The subject pipe system is the 3 purge line for Quad C. The function of this pipe was to convey water from the one 3 inch riser in Quad C to the HD sump in Pump Room #22 on the Rx Building -25 A, where the pipe is currently breached.
1.2 EP 1.33 consists of approximately 90 feet in length fiom the pump room to the riser in Quad C. The pipe section has a approximately six mitered elbows ranging h m 45 to 90.
2.0 Survey Design Information 2.1 EP 1.33 was surveyed IAW Procedure #BSL/LVS-002.
2.2 IW?of the 3 ID pipe was accessible for survey. The accessible 3 ID pipe was surveyed by static measurement at one foot increments, for a total of 90 survey measurements.
2.3 Surface area for the 3 ID piping is 729.7 cm2for each foot of piping, corresponding to a total 3 ID piping surface area of 65,700 cm2(6.6 m2) for the entire length of (90) of 3 piping..
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 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 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 1.33 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.
1 FSS Design ## EP 1.33 1 Revision # Original Survey Unit: 1.33 5.5 Statistical Summary Table I Statistical Parameter I Pipe Total Number of Survey Measurements 1 I
90 Number of Measurements >MDC 71 Number of Measurements Above 50% of DCGL 0 Number of Measurements Above DCGL 0 Mean 0.020 I Median I 0.018 Standard Deviation I 0.019 1 0.184 I
Maximum Minimum I 0.006 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 1.33 to be less than 1 mredyr. The dose contribution is estimated to be 0.020 mdyr based on the average of the actual gross counts measured.
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 1.33 k Spreadsheet
SECTION 7 ATTACHMENT 1 5 PAGE(S)
- _i - BSI EPBP SURVEY REPORT survey Location -27 TRENCH 2350-1 # 212223 Detector-Sbd f 44-62/204402-101 Detector EHickncy 0.00013 cl~lrrkcorpon(.d4 D.llsbr -th an9 730 Fkld BKG(sp) 5.2/5.116.4l7.0 F k M MDCR-I 10.8/10.7/11.7/13.0 II N o m i ~MDC l ( d p n q I284212842/2779/2779 Survey Measurement Results Total Number of Survey Measurements 90 Number of Measurements >MIX 71 Number of MeasurementsAbove 50% DCGL 0 Number of MeasurementsAbove DCGL 0 Mean 0.020 Median 0.018 Standard Deviation 0.019 Maximum 0.184 Minimum 1 0.006 ROSENHAGEN Survey Technician(s) r TBD 06-004 Piping Group 2 SR-13 Radionuclide Distribution Sample EP 2-1 Measured Nudide C060 Area Factor/EMC Used No PasslFail FSS Pass MREM/YR Contribution I
COMMENTS:
ACTIVITY VALUES NOT BACKGROUND CORRECTED
EP 1.33 3" Pipe TBD 06-004 Group 2
- I
-
CI C
E Cod0 activity Co-80 activity Co-I37 activity Eu-I62 activity Eu-154 activity Nb-S4 activity Agl08m activity Unity f gcpm ncpm (totaidpm) (dpm1100cm2) (dpmll OOcmZ) (dpmll OOcm2) (dpm1100cm2) (dpm1100cm2) (dpm1100cm2) 1 6 6 46,154 6,325 I
- 37 3
-
183 0.02; 2 4.3 4.3 33,077 4.533 ______ 27 ~ _ _ _2 _ 131 0.02(
3 4 4 30,769 4,217 _--
25 ______ 2 122
~- 0.01I 4 3.6 3.6 27,692 __.____ 3,795 2 110 _ 0.01f
_
51 3.31 3.31 25,385 _ _ - _ _ 3,479 ____ 1,805
-
2 101 0.01!
61 2.31 2.31 17.692 ___-- 2,425 _.__ 1,258 - ~ _ _ 14 _ _ 1 70 0.01' 4,217 -
25 122
-_ 0.011 I ~___ 3,163 26
__
92 0.014 91 5 5 38,462 5,271 2.736 44 153 0.02:
101 4 4 30.769 4,217 122 0.011 11 3.3 3.3 25,385 3,479 ______.- - __
101 0.01!
-12 3.6 3.6 27,692 ___ 3,795 31 22 1l o 0.01(
13 5.3 . 5.3 40,769 5,587 2.900 33
.-
162 0.024 14 3.3 3.3 25,385
__- 3,479 21 __ 101 0.011 15 5.6 5.6 43,077
___ 5,903 -___ 35 171 0.021 16 3 3 23,077 - 3,163 1,641 ___ 26 19 92 0.01d
__-_
~.
17 2.3 2.3 17,692 2,425 1,258 20 ~ 14
_ _
70 0.01 18 4 4 30.769 4,217 - ~ _ _ _ 2,188 35 25 0.01 6,325 - ._ 3,283 52 .. 37 0.02
- _.
___- 5,587 - - 2,900 46
-. .__ .
33 -~0.02 3.3 3.3 _25.385
_ 3,479 1,805 .__-___ 29 21 0.01 4.6 4.6 351385 4,849 40 29 2 141 0.02
- 22 2,517 -
23 6 6 46,154 6,325 3,283 52 3
- __-- __._____- __ - --
24_.__ 5 5 38,462 5,271
___ _- ~
2,736 ~-
44 3 25 5.3 5.3 ~
40,769 - 5,587 2,900 . 46 ____ 3 26 _ ~_-5.3 _5.3
_ _ 40,769 5,587 2,900 48 3
__ --____-_____ - _ _ -
27 2.6 2.6 20,000 2,741 _ _ 1,423 22 1 28 4 4 30,769 4,217 2 3-88.-
-
__ - -35 -
29 3 3 2 3 0
, 77 3,163 1,641 -- 2 E 2
_ _ __ -.- ._
30 3 3 23,077 ~ 3,163
_ _
1.641 2E ___ 19
- 31 3.6 3.6 27,692 3,795 1,970 - -
22 32 2.6 2.6 2o:ooa 2.741 1,423 22 16
EP 1.33 3" Pipe TBD 06-004 Group 2
-
COM) activity Cs-137 activlty Eu-152 activity Eu-154activity Nb-94 activlty Ag-1OBm activity gcpm ncpm (dpm1100cm2) (dpmMOOcm2) (dpnVlOOcm2) (dpm1100cm2) (dpm1100cmZ) (dpm1100cm2) ""@
-2 2 15,385 2,108 1,094 - 1 61 0.009
_____ 12 2.3 2.3 17,692 2,425 1,258 ___- _-__ 1 _____ 70 0.011 3 3 23,077 _ _ 3,163 _ ~ - _ _ _ _1,641 __ 19 --2 ~ 9 2- om 2.6 2.6 20,000 2,741 - -1,423
._ ..___ 16 1 4 4 30,769 4,217 2,188
_ _ ~ 25 2 122-
__ -Om8 3.e 3.6 27,692 3,795 1,970 ___-.22 2 _. 110 - 5 0 1 6 4.2 4.3 33,077 4,533 _2,353
__ _-__ 27 2 1 3 1 0.020 2.2 2.3 ~- 17,692 2,425 1,258 ~
14
- - __..___
1 70 0.011 2.e 2.6 20,000 2,741 1,423 23 ______ 16- -_ - 1 ~
79- 0.012 4.e 4.6 35,385 4,849 ___-2,517 40 29 2
___-_____ 141
- -_0.021.
2 2 15,385 2,108 ______ 1,094 17 12 1 - - __ 61 0.009 n
b
- 3 23,077 3,163 1,641 26 - __-__ 19 2 92 0.014 3.E 3.6 27,692 3.795 1.970 31 -~ 22
__ 2 110 0.016 1.E 1.6 12,308 875 10 ~ _ _1 _ _ _ 49 0.007
.-
4 4 ___- 30,769 4.217 I-2.188
- 1 - 25 2 122 0.018 3.2 3.3 ___-_ 25,385 3,479 1,805 21 2 101 0.015 2.7 2.7 20,769 2.846 1.477 17 1 83 0.012 3.2 3.3 25,385 3,479 1,805 21 2 ~- 101 0.015 2.2 2.3 17,692 2,425 1,258 - -- 14 1 70 0.011 C 5 38,462 5.271 2.736 31
- - -__ 25- --__ --
3 2 153 0.023 4 A 30,769 2,188 ~- __ 122 - 0.018 6.7 6.7 511538 I -~ + - 3 x
____.___ - -~ 42 _ 3 ~ _ _ _ _205 0.031
- __7.2 7.3 56,154 7,695 ___ 3,994-_ _______ 45 4 223 0.033
- .-
6.2 -___ 6.3
.-. - .
48.462
- ._
~- 6,641 3,447
-~ 39 3 _ _193
_ 0.029 5.i 43,846 5.7 _ _ _ _ _.
- 6,009 3,119 _
35
_ _ _ _ _ _ _ _ _ ~ 3 _-_ 174- 0.026
_ -
6.2 6.2 _.____48,462 ~- 6,641- _ -- 3,447 ~- -39 ~. - - - - 3 193 -0y029 4.7 36,154 4955 2571 ____________ 29 2 _ _ _- _ _ _ - 144 0.021 4.i 36,154 _ _ . -_ _ 2,571 4,955 -- ___ 29 - -~ 2 1-44 -0.021
& c G 38.462 5,271 2,736 31 3 - - 153 0.023
_ _ 5.7
_ 5.7 - - 6,009 3,119 - -- -
35 _._
3 __ 174 --0026 L 2,108 1,094 12 1 6 1 0009 2of4
EP 1.33
'
3" Pipe TBD 06-004 Group 2
-
Co-60 activity Cog0 activity Cb-137 actlvily Eu-152 activity Eu-154 activity Nb-B4 activity Ag-1O8m actlvity ncpm (dpmllOOcm2) (dpmllOOcm2) (dpmllOOcm2) (dpm/lOOcm2)
Unity (total dpm) (dpm1100cm2) (dpmllOOcm2) 7 38.462 I 5.271 2,736 44 153 -
_0.02:
__
1,641 26 92 0.01A 4.2 33.077 4.533 2,353 38 ..____--_
131 0.02(
4.7 ____ 2,571 __ ~- 41 144 0.02' 3,830 _ _ _ _ _ _ ~ 61 44 214 0.03:
_____ 2,571 41 ~ 29
__ ___ 144 0.02'
._____
17,692 __ 1,258
-~
20 14 _ ~~~
7c 0.01 '
._ - _.
33,077 2,353 _____ 38 27 131
-
0.02(
33.077 4.533 2,353
__._ 38 I 2 131 0.02(
7 7 x 2 r T 2,425 M i 1,258 20 I 1 0.01 23,077 3,163 0.014
_____ 20,769 1,477 24 0.01:
___- 10,000 ____1,370 711 - 0.oa 30.769 4.217 2,188
_ _ _.__ 35 25 2 -
0.01 I 2.: 17,692 2,425 1,258 _______ 20 14 1 0.01 3.: 25,385 3,479 1,805 29 __ 21 _-_ 2 0.01!
_____ 28,462 3,900 2,024 32 23 2 0.01' 4.7 4.i 36,154 4,955
___ - ____
2,571 41 29 2 0.02
___
13,077 1,792 __- 930 -_ - ___- 15 11 1 0.00;
___
2.7 2.i 20,769 2,846 ~
1477 --
24 17 1 0.01:
36,154 4,955 2,571 -
41 29 2 ~-0.02 5.: 40,769 5,587 2,900 46 -__33 3 0.021 2.3 2.: 17,692 2,425 0.01
___-
_- 30,769
_- 4,217 0.011
~-
33,077 ___ _ 4,533
-~
0.021 23,077 3,163 0.01'
_____
310,000 -
42,483 22:049-t - - 3 5 3 1 2 5 1 1 - -21 3of4
EP 1.33 3" Pipe TBD 06-004 Group 2
- c I I I I I I I I I C
E CO-BOactivity Codd activity Cs-137 activity Eu-152 activity Eu-I64 activity Nb-94 activity Ag-1OEm activh gcpm ncpm (totaidpm) (dpm1100cm2) (dpm1100cm2) (dpm1100cm2) (dpmllOOm2) (dpm1100cm2) (dpm1100cmZ) a E"
_.__ - ~ ~ . ~ _ _ _ _ .-
MEAN 0.020
-. _- - _ _ MEDIAN 0.018
__ - ~- STD DEV 0.019
. .- .. -
MAX-. __ -
MIN 0.006
SECTION 7 ATTACHMENT 2
Pipe Interior Radiological Survey Form Date: Time:
zs_ .Access Point Area:
~
Building: 7ZebTA Elevation: c c",
Systern : Pipe Diameter: 3" PipeID# / - 33 Type of Survey Investigation Characterization Other /
Sled Size 3I f inch Detector: slcj-L2 Detector ID #: pv++-/o/
Cal Date: / I .I % - o r Cal Due Date: //*13- 0 G Instrument: GcroL/LIm 235-0 - Instrument ID #: 3 ) 3@3 Cal Date: / / ) 3 . 05 Cal Due Date: / l v 7 -c"6 From the Daily Pipe Survey Detector Control Form for the Selected Detector BackgroundValue r- 2- cpm MDCRstatic /CY. f cpm &LL7.-d*:d, P Efficiency Factor for Pipe Diameter 0 . 000/d (taken from detector e x A h & m i~ ~ ~
MDCStatiC 2,B 2 d p d l 00cm2 Is the MDC,,,, acceptable? No (if no, adjust sample count time and recalculate MDCR,,ti,)
Comments: / nm- 5 cALd('L-;/
1 Pipe Interior Radiological Survey Radiological Survey Commenced: Date: 1 -/3 Time: 1 Lf- 3 ~3 Package Page 1 of 2-Attachment 3, Page 1
Pipe Interior Radiological Survey Form Date: / d . 1 Ip Time: 8 9) b Building: 2&AIG& Elevation: -2.c Access Point Area: ,2/7 7h%fc++
System: fiu~i-,
\ C ?uuvc PipeDiameter: Pipe ID # // 33 Type of Survey Investigation Other /
Sled Size 3 inch Detector: 4g-Q > Detector ID #: 3c(/q0a--/or Cal Date: 11.17 65 Cal Due Date: / I - 17 cc Instrument: 93s) I Instrument ID #: 02 r XLa3 Cal Date: 11 J 7 , O r Cal Due Date: /I- ( 7 . 0 - 3 From the Daily Pipe Survey Detector Control Form for the Selected Detector Background Value 3-3 CPm MDCRStatlC / a .7 CPm e@b C: Ads en:nA~
Efficiency Factor for Pipe Diameter 0 0 00 I d I (taken fkom detector MDCStatIC 2 d p d l 00cm2 Is the MDCsUncacceptable? Yes No (Ifno, adjust sample count hme and recalculate MDCR,,,)
Comments: r&lI7/Ak4 41(d J a / l dw Pipe Interior Radiological Survey Radiological Survey Commenced: Date: /a 1 b 0 3 The: 0 706 Package Page o f L REFERENCE COPY Attachment 3 Page 1
Pipe Interior Radiological Survey Form Date: / -3 . a4 Time: /b3d Building: F l f c P tl- Elevation: - %.si Access Point Area: -27 /'a 4 System:
Type of Survey
~, ,CL F
~~
Investigation
- Pipe Diameter:
Characterization c -
3fr 3Final Survey PipeD#
Other
/. 33 F
Sled Size 3 '$ ' p u / W A inch Detector: Detector ID #: dr23D?-/Z(
Cal Date: Cal Due Date: / 7 - r J f W / U G Instrument: 23%-4 Instrument ID #: 21222 Y Cal Date: /? - f&f -fir Cal Due Date: l 7 -+/-aC From the Daily Pipe Survey Detector Control Form for the Selected Detector Backgroundvalue &t { cpm MDCRSt,tlC //r 7 CPm Efficiency Factor for Pipe Diameter 0* b 0 0 (taken from detector 9
27 7 d p d l 00crn2 MDCStatlC Is the MDCStaticacceptable? a Comments: c d e 7 1kLt&7~0r3 JLcb3C;v No (if no, adjust sample count time and recalculate MDCR,,,,)
/
Pipe Interior Radiological Survey Radiological Survey Commenced: Date: / '3 - Time: / 030 Package Page 1 of A 0 REFERENCE COPY Attachment 3, Page 1
Pipe Interior Radiological Survey Form (Continuation Form)
Package Page AWCRENCE COPY Attachment 3,Page 2
I Pipe Interior Radiological Survey Form Date: /c + 0 G Time: 0 g/=
Building: -f-&?& CT&\ Elevation: - L;)c Access Point Area: - 27 @ i.
System : && f-2 PipeDiameter: ,t Pipe ID # /, 33 Type of Survey Investigation-. Characterization Final Survey Other K/
Sled Size '3d:fiy' Sfed b l h i n c h Detector : 49'-L % Detector ID #: 317-7 O ) - / Z (
Cal Date: , I -J 3- o r Cal Due Date: / I - 3 7-0 L9 Instrument: 23Tfl-I Instrument ID #: 9 1 9 a23 Cal Date:. 1'" 3 --d 5- Cal Due Date: ri-- I? -u b From the Daily Pipe Survey Qetector Control Form for the Selected Detector Backgroundvalue 7 cpm MDCRStat,, 17 CPm eR&y &P VL Efficiency Factor for Pipe Diameter 0 , 00013 (taken from d e t e c t o r 7 MDCstatic 2 777dpm/100cm2 Is the MDCstabcacceptable? @ No (if no, adjust sample count time and recalculate MDCR,,,,)
Comments: f ,/J q 47Ibf-f .fd/L,d 4-j I
-y$P / A-3 /< 7-6 I Pipe Interior Radiological Survey Radiological Survey Commenced: Date: 1' qfl ' Time: b Package Page 1 of 2 Attachment 3, Page 1 j-
Pipe Interior Radiological Survey Form (Continuation Form) /. 7 3 Package Page 3-of 21.
EFERENCECOPY Attachment 3, Page 2
I E
.-
3 .o L
n m B
SECTION 7 ATTACHMENT 3 I PAGE(S)
Design # EP 1.33 Revision # Original Survey Unit # EP 1.33 Prelimlnary Data Review' Answers to the following questlons should be fully documented in the Survey Unit Yes No 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 measurementsbelow 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 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 measurementsand smear anatysis Z. 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 involvedand for the
-~
media k i n a surveyed?
~~
IXI
- 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 accordancewith the survey X design, which accurately reflectsthe radiological status of the facility?
- 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 mated to assist in analyzing the data? I I I x
- -~ ~ _ _ ~ - ~ ~- ~~ ~ ~ ~ ~ - -
- 1. Are all sample measurementsbelow the DCGLW(Class 1 812), or 0.5 DCGLW(Class 3)? X
- 2. Is the mean of the sample data e 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 e0.5 DCGLw (Class 3)7
- 4. Is the result of the Elevated MeasurementsTest e I.O? X
- 5. Is the result of the statistical test (S+ for Sign Test or W, for WRS Test) 2 the critical value? X Comments:
FSSlCharaderization Engineer (printlsign) &fC Re&]/
FSSICharacterization Manager (pfint/sign) Rb e Page 1 of 1
SECTION 7 ATTACHMENT 4 1 DISC
I Survey Unit Release Record Design # EP-1.82 1 Revision # 1 Original 1 Page 1 of 3 Survey Unit #(s) 1.82
- 1) Embedded Pipe (EP) Survey Unit 1.82 meets the definition of embedded pipe for Plum Brook Reactor Facility (PBRF).
- 2) EP 1.82 is a Class 1, Group 2 survey unit as per the PBRF Final Status Survey Plan (FSSP) and Technical Basis Document (TBD)-06-004.
- 3) Surveys in EP 1.82 were performed using a scintillation detector optimized to measure gamma energies representative of CO-60.Sample #EP 2-1 fiom Survey Request (SR)-13 was referenced for this decision.
- 4) Survey Instructions for this survey unit are incorporated into and performed in accordance With (IAW) the Babcock Services Incorporated (BSI)/LVS-002, Work Execution Package (WEP)05-006. Survey instructions described in this 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 Date:
0 COPY
FSS Design # EP 1.82 Revision # Original Page 2 of 3 1.o History/Description 1.1 The subject pipe system is the 3 purge line for Interim Storage Area. The function of this pipe was to convey water from the one 3 inch riser in Interim Storage Area to the HD sump in Pump Room #22 on the Rx Building -25 ft, where the pipe is currently breached.
1.2 EP 1.82 consists of approximately 34 feet in length from the pump room to the riser in Interim Storage Area. The pipe section has an approximately five mitered elbows ranging from 45 to 90.
2.0 Survey Design Information 2.1 EP 1.82 was surveyed IAW Procedure #BSYLVS-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 16 survey measurements.
2.3 Surface area for the 3 ID piping is 729.7 cm2for each foot of piping, corresponding to a total 3 ID piping surface area of 11,680 cm2(1.1 m2) for the entire length of (1 6) of 3 piping..
3.0 Survey Unit Measurement LOcationdData 3.1 Pipe intenor 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 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 1.82 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 J FSS Design # EP 1.82 Revision # Original Page 3 of 3 Survey Unit: 1.82 5.5 Statistical Summary Table Statistical Parameter Total Number of Survey Measurements 13Pipe 16 Number of Measurements >MDC 14 I Number of MeasurementsAbove 50% of DCGL I 0 r
~~
Number of Measurements Above DCGL I o Mean 0.019 Median 0.018 Standard Deviation 0.008 Maximum 0.037 I Minimum I 0.006 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 1O?h in aggregate of the total dose for both structural scenarios and soils.
6.1 A review of the survey results has shown that the dose contribution for EP 1.82 to be less than 1 mredyr. The dose contribution is estimated to be 0.019 mrerdyr based on the average of the actual gross counts measured.
7.0 Attachments Attachment 1 - BSI EP/BP Survey Report Attachment 2 - Pipe Interior Radiological Survey Form Attachment 3 - DQA Worksheet Attachment 4 -Disc containing RR for EP 1.82 & Spreadsheet
___I I
SECTION 7 ATTACHMENT 1 3, PAGE(S)
BSI EPIBP SURVEY REPORT Pipe ID 1.82 Survey Location -27 TRENCH Survey Date 21-DeC-05 2350-1 # 212223
-
survey Time 0815 Detector-Sled# 44-62/204402-101 Pipe size 3 Detector Efficiency 0.00014 DCGL o 240800 RP -w- bv ~lkhq 730 np.--bl 1.1 F k M BKG1-1 5.9 Routine Survev X Field HDCRI- 11.3 Total Number of Survey Measurements 16 Number of Measurements>MDC 14 Number of MeasurementsAbove 50% DCGL 0 Number of MeasurementsAbove DCGL 0 Mean 0.019 Median 0.018 Standard Deviation 0.008 Maximum I 0.037 Minimum 0.006 ROSENHAGEN Survey Technidan(s)
TBD Oe-004 Piping ~ m u p 2 SR-13 Radionudie DistributionSample EP 2-1 Measured Nudide co60 Area Factor/EMC Used No PasslFail FSS Pass MREWR Contribution 4 r
~ ~~
COMMENTS:
ACTIVITY VALUES NOT BACKGROUNDCORRECTED r
RP Engineer 1 Date 1 6-/2-o7 8/12/2007
SECTION 7 ATTACHMENT 2 3 PAGE(S)
Pipe Interior Radiological Survey Form Date: / 2- 2 / -QI Time: 8 t7/T Building: fLf Elevation: - Access Point Area: ChlCM System: j j & , d f i ~ & j ~ Pipe Diameter: 3, I ' Pipe ID # .I.9 2 Type of Survey Investigation Characterization Other J Sled Size -3 inch Detector: hf 5'-6 2 Detector ID #: 2.0Y Y O L - / o /
Cal Date: I /-/7 Cal Due Date: I/-/ 7 -6 6 Instrument: 23sv-/ Instrument ID #: az-22-7 Cal Date: f7Y 7- o r Cal Due Date: / /-/ 7 -06 From the Daily Pipe Survey Detector Control Form for the Selected Detector Background Value L87 cpm r \ %
mmstaac /b3 CPm ? J e b ?m , n h C 1
-
T
'
Efficiency Factor for Pipe Diameter 0 ~ ~ ' / ~ @ a k from e n detector MDCStatlC 2 f?qzdpm/100cm2 Is the MDCShh,acceptable? ad No (ifno, adjust sample count t h e and recalculate MDCR,,,,)
Pipe Interior Radiological Survey Radiological Survey Commenced: Date: / 1/L'-flJ- Time: 0 3/ 3-Package Page 0 REFERENCE COPY Attachment 3 Page 1
I I
Position Feet into Pipe Count Time Gross counts Gross Net
- from Opening (Inin) cpm cpm d p d l 00cm2 I 1 @ aI / 3 Y ($3 ).I/& fllP IL 1 ?- 3 1 5 I 7
' 13 '1 3 3 to 3.3 i I tY ir 3 Pt 9' 7 II
. IC 1 s 3 rU 3 -3 tb 16 lb 5;,3 I
UREFERENCE COPY Attachment 3, Page 2
SECTION 7 ATTACHMXNT 3 PAGE(S)
t I DQA Check Sheet
~ ~
Design # EP 1.82 Revision # Original Survey Unit # EP 1.02
~ -
- 3. Is the instrumentationMDC for embedded/buried piping static measurements below the DCGLw ?
Q. 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 static measurements or soil samples addressed in the survey design?
5, Was the instrumentationMDC for volumetric measurements and smear analysis < 10% DCGLW?
- 3. Were the MDCs and assumptions used to develop them appropriate for the instruments and techniques used to perform the survey?
- 7. Were the survey methods used to collect data proper for the types of radiation involved and for the media being surveyed?
- 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 analyu'ng the data? X
- 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
- 3. If elevated areas have been identified by scans andlor sampling, is the average activity in each elevated area DCGLEw (Class l), DCGLW(Class 2), or 4 . 5 DCGLw (Class 3)?
- 4. Is the result of the Elevated Measurements Test < 1.O?
- 5. Is the result of the statistical test (S+ for Sign Test or W, for WRS Test) 2 the critical value? X Comments:
I
' -
Form cs-o9/2 Rev 0 Page 1 of 1
SECTION 7 ATTACHMENT 4 1 DISC
Survey Unit Release Record Design # EP-Rx 150 I Revision# I Original Page 1 of 3 Survey Unit #(s) EP-Rx 150
- 1) Embedded Pipe (EP) Survey Unit 150 meets the definition of embedded pipe for Plum Brook Reactor Facility (PBRF).
- 2) EP 150 is a Class 1, Group 2 survey unit as per the PBRF Final Status Survey Plan (FSSP) and Technical Basis Document (TBD)-06-004.
- 3) Surveys in EP 150 were performed using a scintillation detector optimized to measure gamma energies representative of Co-60. Sample #EP 2-1 from Survey Request (SR)-13 was referenced for this decision.
- 4) Survey Instructions for this survey unit are incorporated into and performec in accordance with (IAW) the Babcock Services Incorporated (BSI)/LVS-002, Work Execution Package (WEP)05-006. Survey instructions described in this 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:
Form CS-09/1 Rev 0 0 COPY
FSS Design # EP Rx 150 Revision # Original Page 2 of 3 1.o History/Description 1.1 The subject piping described in this report is an air supply line for equipment and accessories utilized in Quad B. This survey unit involves -
20of air supply piping.
2.0 Survey Design Information 2.1 EP Rx 150 was surveyed IAW Procedure #BSILVS-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 729.7cm2for each foot of piping, corresponding to a total 3 ID piping surface area of 14,594 cm2(1.5 m2) for the entire length of (20)of 3 piping..
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 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 150 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 1 FSS Design # EP Rx 150 Revision # Original Page 3 of 3 5.5 Statistical Summary Table 3
Statistical Parameter Pipe Total Number of Survey Measurements 21 Number of Measurements >MDC 12 Number of Measurements Above 50% of DCGL 0 Number of Measurements Above DCGL 0 Mean 0.012 Median 0.013 Standard Deviation 0.004 Maximum 0.022 Minimum 0.004 6.0 Documentation of evaluations pertaining to compliance with the unrestricted use limit of 25 mredyr and dose contributions fkom Embedded Pipe and radionuclides contributing 10% in aggregate of the total dose for both structural scenarios and soils.
6.1 A repeat QA survey was performed on this survey unit. It was concluded that the QA comparison results were acceptable based on the fact that all results differing by more than 20% were calculated to be less than 3% of the DCGL.
6.2 A review of the survey results has shown that the dose contribution for EP Rx 150 to be less than 1 mrem/yr. The dose contribution is estimated to be 0.0 12 mrem/yr based on the average of the actual gross counts measured.
7.0 Attachments Attachment 1 - BSI EP/BP Survey Report Attachment 2 - Pipe Interior Radiological Survey Form Attachment 3 - DQA Worksheet Attachment 4 -Disc containing RR for EP Rx 150 & Spreadsheet
SECTION 7 ATTACFIMENT 1 3 PAGE@)
I l!iikw
- i. _i .
BSI EP/BP SURVEY REPORT Pi- ID I Rxlso 11 Suwev Locatton 1 -25TRENCH 1 I
I survey Lhta Suwev fime I 12112105 12113m 1350/0756 II 23500-1I OeQctor-Skd # I 2 12223 44-62/204402-101 Maximum I 0.022 Minimum 0.004 Survey Technician(s)
I ROSENHAGEN r
-
COMMENTS:
ACTMTY VALUES NOT BACKGROUND CORRECTED
-
RP Engineer I Date &,J'U 6-20-07
EP Rx 150 3" Pipe TBD 06-004 Group 2 7
I I I , I I Unity
-
0.014 0.013 0.014 0.010 0.010 0.007
- --
0.010
--
0.022 0.013
--
0.015 0.016 0.013
---
-0.008 0.004 0.011 0.016 0.016 0.010 0.01
__- 3 0.014
__-
0.008
-
-__
-0.012 0.013 1 of 1
Survey Unit EP Rx 150 QA Worksheet I ORlG
% DlFF Jnity Value 1 1.7 1.7 12,143
-.
1,664 1 3.3 3.3 23,571 3,230
- 484 0.014 2 2 2 14,286 1,958 2 3 3 21,429 2,937 33.3 0.013 3 3.7 3.7 26,429 3,622 3 3.3 3.3 23,571 3,230 12.1 0.014 4 1.3 1.3 9,286 1,273 4 2.3 2.3 16,429 2,251 43.5 0.010 5 4.3 4.3 30,714 4,209 5 2.3 2.3 16,429 2,251 87.0 0.010 -
6 3 3 21,429 2,937 6 1.6 1.6 11,429 1,566 87.5 0.007 7 4.7 4.7 33,571 4,601 7 2.3 2.3 16,429 2,251 104.3 0.010 8 3 3 21,429 2,937 8 5.3 5.3 37,857 5,188 43.4 0.022 9 4 4 28,571 3,916 9 3 3 21,429 2,937 33.3 0.013 10 2.3 2.3 16,429 2,251 10 3.6 3.6 25,714 3,524 36.1 0.015 11 4.3 4.3 30,714 4,209 11 3.7 3.7 26,429 3,622 16.2 0.016 12 2.7 2.7 19,286 2,643 12 3 3 21,429 2,937 10.0 0.013 13 3 3 21,429 2,937 13 2 2 14,286 1,958 so.0 0.008 14 4 4 28,571 3,916 14 1 1 7,143 979 300.0 0.004 15 1.7 1.7 12,143 1,664 15 2.7 2.7 19,286 2,643 37.0 0.011 16 2.7 2.7 19,286 2,643 16 3.7 3.7 26,429 3,622 27.0 0.016 17 2.3 2.3 16,429 2,251 17 3.7 3.7 26,429 3,622 37.8 0.016 18 2.3 2.3 16,429 2,251 18 2.3 2.3 16,429 2,251 0.0 0.010 19 3.3 3.3 23,571 3,230 19 3 3 21,429 2,937 10.0 0.013 20 21 3.3 4.3 3.3 4.3 23,571 30,714 3,230 4,209 20 3.3 3.3 23,571 3,230 1.958 - 0.0 I15.0 0.014 0.008 NOTE: ALL QUALITY ASSURANCE RESULTS DIFFERING BY MORE THAN 20% WERE LESS THAN 3% OF THE DCGL
SECTION 7 ATTACEFMENT 2 7 PAGE(S)
f4 Pipe Interior Radiological Survey Form Date:
Building: Elevation: J zcp Access Point Area:
System: - 0 Type of Survey Mz:g" Investigation Pipe Diameter:
Characterization 3 -
QFal Survey 3 Other1 Pipe ID #
r
/ f Sled Size inch Detector: QW-4 s Detector ID #: &LjLJL; 7. --/u Cal Date: // f / 7 ' 0 5 Cal Due Date: f/ - / 7 '06 Instrument: LOL4M H33-0 -1 Instrument ID #: 2233 Cal Date: / / - / .7d X Cal Due Date: / / - / 7' U b From the Daily Pipe Survey Detector Control Form for the Selected Detector Background Value C- 9 cpm MDCRStatIC P r W cpm Efficiency Factor for Pipe Diameter -
0 00 0 1 L/ (taken from detector MDCstatlc Z 8 4 2 dpm/100cm2 Is the MDCskbc acceptable? @ No (Ifno, adjust sample count tune and recalculate MDCR,,,,)
Comments: /'d/7,/?( sLcad6y Pipe Interior Radiological Survey Package Page 1 ofL&
U REFERENCE COPY Attachment 3, Page -1..'-
Pipe Interior Radiological Survey Form Date: I& /3-a,- Time: /3 7mr-6 Building: >r &f)G u lU7fElevation: - 2 J~ Access Point Area: @L140 System: C I v i t n . Pipe Diameter: 3 y PipeID# Rrr 1 3 3 Type of Survey Investigation Characterization- Other rl Sled Size 3 inch Detector: CfY-G'L- Detector ID #: 2 0 vyfl2.r Cal Date: I / - / 7-0)' Cal Due Date: / / -1 7 -0c; Instrument: 7 3m-I Instrument ID #:
Cal Date: /I-( 7 ~QJ- Cal Due Date:
From the Daily Pipe Survey Detector Control Form for the Selected Detector BackgroundValue <g cpm MDCRStatiC /os T cpm EfficiencyFactor for Pipe Diameter 0-*DO&/ 4 (taken om detector 2 %Lfzdpm/100cm2 MDcstatlc Is the MDCstallcacceptable? a- No (Ifno, adjust sample count time and recalculate iMDa,,)
Comments: COn,7/RltlAT'fBR) of' /%& $L,(Qbhy Fddm ]2-/2-03--
Pipe Interior Radiological Survey Package Page 1 o f 2 REFERENCE COPY Attachment 3, Page 1
! I Pipe Interior Radiological Survey Form (Continuation Form)
ZD,fl #7x 150 (id{ &O f3 Position Feet into Pipe Count Time Gross Counts Gross Net d p d l 00cm2
- from Opening (min) cprn cpm Z( (0 #I&
I
/'
I I Package Page #- of&-.
REFERENCE COPY Attachment 3, Page 2
I f Pipe Interior Radiological Survey Form Date: /- 6-t2f Time: o?ov Building: Elevation: -LJ- Access Point Area: Qd A 0 d A;>c Pipe Diameter: &-% UT Type of Survey Investigation Characterization Final S w e y Qfl Sled Size gv17yl K \ b t I
inch Detector: YV-Q 21 Detector ID #: 21270/-
Cal Date: //-/ 7 Cal Due Date: / /- / 7- 5 4 Instntment: 23 m- I Instnrmerrt I D #: Zf Z L Z I Cal Date: / / 7 7 - 0 5- Cal Due Date: //47-a From the Daily Pipe Survey Detector Control Form for the Selected Detector BackgroundValue x r 7 cpm MDCRtatic / o r $7 CPm Efficiency Factor for Pipe Diameter 0 - 00f3 (taken fiom detect0 MDC,,hC 27 74 d p d l OOcm Is the MDCStaticacceptable? No (ifno, adjust sample count time and recalculate MDCK,,)
Comments:
Pipe Interior Radiological Survey Radiological Survey Commenced: Date: /- 6 -06 Time: ofCrO Package Page 1 o f /
Attachment 3, Page 1
Package Page *of -7 REFERENCE COPY Attachment 3, Page 2
SECTION 7 ATTACHMENT 3
/ PAGE@)
DQA Check Sheet Design # EP Rx150 Revision # Original Survey Unit # EP Rx 150 Preliminary Data Revlew Answers to the following questions should be fully documented in the Survey Unit Yes No N/A Release Record I
- 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 embedded/buried piping static measurements below the DCGLw ? X S,- was the instrumentation MDC for structure scan measurements, soil scan measurements, and embedded/buried piping scan measurements below the DCGLw, or, if not, was the need for additional static measurements or soil samples addressed in the survey design?
- 5. Was the instrumentation MDC for volumetric measurements and smear analysis < 10% DCGLw ? I
- 6. Were the MDCs and assumptions used to develop them appropriate for the instruments and techniques used to perform the survey?
- 7. Were the survey methods used to collect data proper for the types of radiation involved and for the X 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 collected in accordance with the survey X 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 araDhml data tools been created to assist in analyzing the data? X
- 1. Are all sample measurements below the DCGLW(Class 18 2),or 0.5 DCGLw (Class 3)? X
- 2. Is the mean ofthe 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 e0.5 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) L.the aitiil value? X Comments:
Page 1 of 1
SECTION 7 ATTACHMENT 4 1 DISC
I I Design ## EP-Rx 160 Revision ## Original Page 1 of 3 Survey Unit #(s)
- 2) EP RX160 is a Class 1, Group 2 survey unit as per the PBRF Final Status Survey Plan (FSSP) and Technical Basis Document (TBD)-06-004.
- 3) Surveys in EP Rx160 were performed using a scintillation detector optimized to measure gamma energies representative of Co-60. Sample #EP 2-1 from Survey Request (SR)- 13 was referenced for this decision.
- 4) Survey Instructions for this survey unit are incorporated into and performed in accordance with (JAW) the Babcock Services Incorporated (BSI)KVS-002, Work Execution Package (WEP)05-006. Survey instructions described in this 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.
0 COPY
r FSS Design # EP Rx160 Revision I# Original Page 2 of 3 Survey Unit: Rx160 L
1.0 HistoryDescription 1.1 EP Rx160 is a RT drain that terminates in the sump. The subject piping described in this report is integral to the drain system for the Reactor Building. The purpose of the system is to convey waste water from the RT to the sump. This system involves approximately 2 liner feet of drain system piping.
1.2 EP Rx160 consists of 2 linear feet () of 8 inch () Inside Diameter (ID) piping starting in the -25 foot elevation RT to the sump. The total piping for EP Rx160 is 2.
2.0 Survey Design Information 2.1 EP Rx160 was surveyed IAW Procedure #BSI/LVS-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 2 survey measurements.
2.3 Surface area for the 8 ID piping is 1,946 cm2for each foot of iping, P
corresponding to a total 8 ID piping surface area of 3.982 cm (0.4 m2) for the entire length of (2) of 8 piping..
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 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 Unity Rule, provided in Section 3.6.3 of the FSSP,and applyhg the Nuclide Fraction (NF), provided in TBD-06-004, the survey unit that is constituted by EP Rx160 passes FSS.
5.4 Background was not subtracted &om the survey measurements and the Elevated Measurement Comparison (EMC) was not employed for this survey unit.
I FSS Design # EP Rx 160 Revision # Original Page 3 of 3 5.5 Statistical Summary Table r
8 Statistical Parameter Pipe Total Number of Survey Measurements 2 Number of Measurements >MDC 2 Number of Measurements Above 50% of DCGL 0 Number of Measurements Above DCGL 0 Mean I 0.016 I 1 0.016 I
Median t I 0.0001 I
Standard Deviation Maximum 1 0.016 I 1 0.016 I
Minimum 6.0 Documentation of evaluations pertaining to compliance with the unrestricted use limit of 25 mredyr and dose contributions fkom Embedded Pipe and radionuclides contributing 10% in aggregate of the total dose for both structural scenarios and soils.
6.1 A review of the survey results has shown that the dose contribution for EP Rx 160 to be less than 1 mredyr. The dose contribution is estimated to be 0.016mredyr 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 Rxl60 & Spreadsheet
SECTION 7 ATTACHMENT 1 2 PAGE(S)
BSI EP/BP SURVEY REPORT Survey Measurement Results Total Number of Survey Measurements 2 Number of Measurements >MDC 2 Number of Measurements Above 50% DCGL 0 Number of Measurements Above DCGL 0 Mean 0.016 Median 0.016 Standard Deviation 0.000
~
Maximum 0.016 Minimum 0.016 Survey Technician@)
I Rosenhanen
- OMMENTS: Activity values are not background corrected.
RP Engineer I Date &/eI%&L+P6 - / 2 - o ?
6/12/2007
-
- C
~~
t gcpm Eu-152activitv ELI-164 activity
.. ..
Nb-94 activity (dpmllM)crnZ)
Ag-108m activity (dpmM00cm2)
=I (R
tu E"
1 11 11 I 73.333 - ~ _ 31_ _ 22 2 109 2(- -111- 73:333 1,956 31 22 109 I
I MEAN
-
-O.Olf MEDIAN 0.01t
___
O.OO(
__
+------ _0.01f
-
_ .~
0.01t 1 of 1
SECTION 7 ATTACmNT2
[ PAGE(S)
I
,
B WLVSPipeCrawler-002 Revision 4 Pipe Interior Radiological Survey Form Time: / RK O Pipe ID#: / 60 Pipe Diameter: I/
Access Point Area: - Z 7 /A nqc Building: >( Elevation: -p7 System:
Type of Survey Investigation Characterization Final Survey d* Other 4 Gross Co60 d cs Detector ID# 1 Sled ID# /M6/ ,/LVS -y I /Q?
Detector Cal Date: 20 D,5C - 03 Detector Cal Due Date: 2/3 - >sL Hd6 Instrument: 9350 I, Instrument ID #: ad 3 9 r ~
Instrument Cal Date: /7 a ,do 4 B 5 htrument Cal Due Date: / 7 r d c d
- o c From the Daily Pipe Survey Detector Control Form for the Selected Detector Background Value 3 , 3 cpm MDCRstatic /p.J cpm Efficiency Factor for Pipe Diameter OQOl4 (fiom detector efficiency determination) mcstatic 33'4 d p d 1 0 0 cm2 Is the MDC,,,, acceptable? Yes No (if no, adjust sample count time and recalculate MDCR,,,,)
/
Comments: /W+&-L Swcvcy x/ P f lw &&,.Me& b A jt 7 C Technician Signature Pipe Interior Radiological Survey Position Feet into Pipe Count Time Gross Counts Gross Net d p d l 00cm2
- from Opening (fin) cpm cpm Package Page 1 ofJ Attachment 3, Page I
SECTION 7 ATTACHMENT 3
/ PAGE(S)
DQA Check Sheet Design # I EP Rx160 I Revision# I Original I Surveyunit# I EP Rx160 Preliminary Data Review 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 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 DCGLWfor Class 3 survey units?
- 3. Is the instrumentation MDC for embeddedhuried piping stabc 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?
- 5. Was the instrumentation MDC for volumetric measurements and smear analysis 10% DCGLW?
~ -~ ~
1 I
-
1 X
- 5. Were the MDCs and assumptions used to develop them appropriate for the instruments and techniques used to perform the survey?
- 7. Were the survey methods used to collect data proper for the types of radiation invoked and for the X
media being surveyed?
- 5. Were Special Methods for data cdlectiin properly applied for the survey unit under review? X
- 9. Is the data set comprised ofqualified measurement results collected in accordance with the survey design, which accurately reflects the radiologicalstatus of the facility?
Graphical Data Review
- 1. Has a posting plot bean created? X
- 2. Has a histogram (or other frequency plot) been mated? X
- 3. Have other graphical data tools been created to assist in analyzing the data? X Data Analysl.
- 1. Are all sample measurements below the DCGLW(Class Id 21, or 0.5 DCGLW(Class 313 1 x 1
- 2. Is the mean ofthe sample data < DCGLw? X
- 3. If elevated areas have been identified by scans andor sampling, is the average a c t i v i in each elevated area DCGLEMC (Class 1), < DCGLw (Class 2), or e0.5 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) 1the critical value? X I - -
Page 1 of I
SECTION 7 ATTACHMENT 4 1 DISC
- -
I Design # EP-RX 204 Revision # Original Page 1 of 3 Survey Unit #(s)
- 2) EP 204 is a Class 1, Group 2 survey unit as per the PBRF Final Status Survey Plan (FSSP) and Technical Basis Document (TBD)-06-004.
- 3) Surveys in EP 204 were performed using a scintillation detector optimized to measure gamma energies representative of Co-60. Sample #EP 2-1 from Survey Request (SR)-13 was referenced for this decision.
- 4) Survey Instructions for this survey unit are incorporated into and performed in accordance with (XAW) the Babcock Services Incorporated (BSI)/LVS-002, Work Execution Package (WEP)05-006. Survey instructions described in this 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:
I FSS/Characterization Engineer / - 6 07 Technical Reviewer n FSS/Characterization Manager
-
, 7/3/07 csm/1 0 COPY
FSS Design # EP Rx 204 Revision # Onginal page 2 of 3 I .o History/Description 1.1 The subject piping described in this report is an instrumentation line for equipment and accessories utilized in Quad B. This survey unit involves -
10 of instrument piping.
2.0 Survey Design Wormation 2.1 EP Rx 204 was surveyed IAW Procedure #BSVLVS-002.
2.2 100% of the 2.5 ID pipe was accessible for survey. The accessible 2.5 ID pipe was surveyed by static measurement at one foot increments, for a total of 10 survey measurements.
2.3 Surface area for the 2.5 ID piping is 608 cm2for each foot of iping, P
corresponding to a total 3 ID piping surface area of 6,080 cm (0.61 m2) for the entire length of (10) of 2.5 piping..
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 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 204 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 204 Revision # Original Page 3 of 3 5.5 Statistical Summary Table 2.5 Statistical Parameter Pipe
~ ~ ~~~ ~~~-~~
Total Number of Survey Measurements 10 Number of Measurements >MDC 10 Number of Measurements Above 50% of OCGL 1 Number of Measurements Above DCGL 0 Mean 0.257 Median Standard Deviation I 0.123 I Maximum I 0.521 I Minimum 0.078 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 204 to be less than 1 mredyr. The dose contribution is estimated to be 0.257 mredyr based on the average of the actual gross counts measured.
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 204 & Spreadsheet
I I
SECTION 7 ATTACHMENT 1 z PAGE@)
t BSI EP/BP SURVEY REPORT I Number of Measurements Above DCGL i 0 Mean 0.257 Median 0.227 Standard Deviation 0.123 Maximum 0.521 Minimum 0.078 I
COMMENTS:
ACTIVITY VALUES NOT BACKGROUND CORRECTED
EP Rx 204 2.5" Pipe TBD 06-004 Group 2
-
cos0 activ-ay cs-137 activity Eu-152 activity Eu-1W actMty Nb-94 ectivily Ag-108m activity (dpm1100cm2) (dpm1100cm2) (dpm/100cm2) (dpm/100cm2) (dpm/100Gm2) (dpm/IWcm2) Unity
--
51.5 51.5 343,333 56,469 29,308 469 333 28 1,638
-
0.245 16.5 16.5 110,000 150 107 9 525 0.07E 109.5 109.5 730,000 997 I 708
-~ 59 3.482
, -- 0.521 4 70 7c 466,667 453 38 2,226 0.33:
42 42 280,000 --_ .~ 272 23 1.336 0.20c 44 44 293,333- 25,039 400 285 __ 24 1,399 0.2E 33.5 33.6 223,333 36,732 305 --__ 217 18 1,065 0.15s 73.5 73.5 490,OO~ 80,592 41,827 669 475 39 2,337 0.34E 58 5s 393,333 64.693 537 382 32 1,876
__ 0.281 4a 4c 266,667 43,860 22,763 259 21 1,272 0.19c
-
_____ 364
--
___ MEAN 0.257
___ MEDIAN __ -
0.227
~- STD DEV 0.12:
___ MAX 0.521 MIN -
0.071 1 of 1
SECTION 7 ATTACHMENT 2 4 PAGE(S)
1' 1 BSI/LVSPipeCrawler-002 Revision 4 Pipe Interior Radiological Survey Form Date: 3 O b Time: 0 Y z,j"
&u"i. $
QCAlQD Pipe ID#: kx v Pipe Diameter: 2 *s'r Access Point Area: s ~ f i ~ -LL+ ~ '
Building: FL% Elevation: - 2#- system: *JmuL&tJr L,:v'f Type of Survey Investigation Characterization Finalsurvey )d Other J Gross C060 J cs Detector ID# / Sled ID# YY-hZ #2/27dll /Z/
Detector Cal Date: 1 /- 7 -d3- Detector Cal Due Date: / I - f7 Instrument: 7 7 5m-Y Instrument ID #: Z 4 3 V i 9 8 Instrument Cal Date: ,/- i 3 -0J- Instrument Cal Due Date: //-f 7 -d b From the Daily Pipe Survey Detector Control Form for the Selected Detector Background Value q17 cpm MDCRS,, 104 cpm Efficiency Factor for Pipe Diameter 0 0 V 0)s (from detector efficiency determination)
MDcstatlc 4 m dPd / O D cm2 Is the MDC,,,, acceptable? Yes No (ifno, adjust sample count time and recalculate MDCl&J Comments: POL
- I = @F 20 R \ GMl-
$ O V t =fRy 7f2 q -
/ [--(2p
> L rua\lw fLw&-T-k -e Technician Signature Pipe Interior Radiological Survey Package Page 1 of- I 0 REFERENCE COPY Attachment 3, Page 1
i I
i 1
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,
I i
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I I
I I
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i I
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d BSI/LVSPipeCrawler-O02 Revision 4 Pipe Interior Radiological Survey Form Date: Time: LO Y L Pipe ID#:
Building:
Type of Survey Investigation Characterization ~indsumey fl Other /
Gross (2060 / cs Detector ID# / Sled ID# VY-GZ 12 i Detector Cal Date: //I7 7 2r Detector Cal Due Date: I/-/ 7-0 b Instrument: 23 s 3 - ( Instrument ID #: 2 GXVE3&3 Instrument Cal Date: /I-/7 - C E Instrument Cal Due Date: / / -f 7-0 From the Daily Pipe Survey Detector Control Form for the Selected Detector BackgroundValue q#7 cpm MDCRstatx \**Y CPm Efficiency Factor for Pipe Diameter 0 0 t7 045 (from detector efficiency determination)
MDCSUtlC 4 D W dPd / O Dcm2 Is the MDC,,, acceptable? m#No (Ifno, adjust sample count time and recalculate MDCL,,)
Comments: /~/,77,&< i/ CY Package Page 1 o f 1 REFERENCE COPY Attachment 3, Page 1 6ERVtCe5 INC.
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i SECTION 7 ATTACHMENT 3 I PAGE(S)
I 1 OQA Check Sheet Design # I EP Rx 204 I Revision # I Original I Survey Unit# I EP Rx 204 Preljminary Data Review' 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 instructionsin 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 X 3.
~~
Is the instrumentation MDC for embedded/buried piping static measurements below the DCGLW? 1 X I
- 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
- 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?
B. 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 radiologicalstatus of the facility? I x Graphical Data Revlew
~~ ~~~ ~
- 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 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 1), DCGLw (Class 2), or e0.5 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 Zomments:
CJ Form cs-o9/2 Rev 0 Page 1 of 1
I SECTION 7 ATTACHMENT 4 1 DISC
Design # EP-Rx 207 Revision # Original Page 1 of 3 Survey Unit kys)
- 2) EP 207 is a Class 1, Group 2 survey unit as per the PBRF Final Status Survey Plan (FSSP) and Technical Basis Document (TBD)-06-004.
- 3) Surveys in EP 207 were performed using a scintillation detector optimized to measure gamma energies representative of CO-60.Sample #EP 2-1 from Survey Request (SR)-13 was referenced for this decision.
- 4) Survey Instructions for this survey unit are incorporated into and performed in accordance with (IAW) the Babcock Services Incorporated (BSI)/LVS-002, Work Execution Package (WEP)05-006. Survey instructions described in this 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 FSS/Characterization Manager 0 9 11 COPY
FSS Design # EP Rx 207 Revision # Original Page 2 of 3 1.0 History/Description 1.1 The subject piping described in this report is an instrumentation line for equipment and accessories utilized in Quad B. This survey unit involves -
3 of instrument piping.
2.0 Survey Design Information 2.1 EP Rx 207 was surveyed IAW Procedure #BSI/LVS-002.
2.2 100% of the 2 ID pipe was accessible for survey. The accessible 2.5 ID pipe was surveyed by static measurement at one foot increments, for a total of 3 survey measurements.
2.3 Surface area for the 2 ID piping is 486 cm2for each foot of pi ing, P
corresponding to a total 2 ID piping surface area of 1,459 cm (0.15 m2) for the entire Iength of (3) of 2 piping..
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 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 207 passes FSS.
5.4 Background was not subtracted h m the survey measurements and the Elevated Measurement Comparison (EMC) was not employed for this survey unit.
FSS Design # EP Rx 207 Revision # Original Page 3 of 3 5.5 Statistical Summary Table 2*
Statistical Parameter Pipe
-~
Total Number of Survey Measurements 3 Number of Measurements >MDC 1 Number of MeasurementsAbove 50% of DCGL 0 Number of MeasurementsAbove DCGL 0 Mean 0.153 r Median I 0.125 I Standard Deviation 0.084 Maximum 0.248 Minimum I 0.086 6.0 Documentation of evaluations pertaining to compliance with the unrestricted use limit of 25 rnredyr and dose contributions from Embedded Pipe and radionuclides contributing 10% in aggregate of the total dose for both structural scenarios and soils.
6.1 A review of the survey results has shown that the dose contribution for EP Rx 207 to be less than 1 rnredyr. The dose contribution is estimated to be 0.153 mredyr based on the average of the actual gross counts measured.
7.0 Attachments Attachment 1 - BSI EPBP Survey Report Attachment 2 - Pipe Interior Radiological Survey Form Attachment 3 - DQA Worksheet Attachment 4 -Disc containing RR for EP Rx 207 & Spreadsheet
c SECTION 7 ATTACHMENT 1 2 PAGE(S)
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BSI EPIBP SURVEY REPORT Mean 0.153 Median 0.125 Standard Deviation 0.084 Maximum 0.248 Minimum 0.086 TBD 06-004 Piping Group 2 SR-13 Radiinudide DistributionSample EP 2-1 Measured Nuclide C060 Area FactorEMC Used No PasslFail FSS Pass MREMNR Contribution 4
~
I COMMENTS:
ACTIVITY VALUES NOT BACKGROUND CORRECTED RP Engineer I Date 6-21-0)
EP Rx 207 2" Pipe TBD 06-004 Group 2
?t c,
C Ee! gcpm
-137 aCtlvIty EU-162 sctivity EU-l&4 actMty Nb-94 actlvity a (dpm1100cm2) (dpm1100cm2) ( d p m l l ~ 2 ) (dpm1100cm2) i I I 15,005 14
..
10,337
_ _ ~ _ _ 10 578 0.OM 29.677 475 337 28 w I 0.24 JIlN I 0.08 1 of 1
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SECTION 7 ATTACHMENT 2 Z PAGE(S)
) .
I BSVLVSPipeCrawler-002
. Revision 4 Pipe Interior Radiological Survey Form Date: 3 8 6 Time: / Qc? Y Qqao s 6-i fq?P5> n me-3 5 5 l t c - C Pipe ID#: 707 Pipe Diameter: z t Access Point Area: a 0 - R l G l . { 7 Building: Elevation: --L 5- System: rjc;ip~ ntp,Cr L :L% 7 2 Type of Survey Investigation Characterization Final Survey A Other J rLrrL *\
Gross Co60 J cs Detector ID# I Sled ID# VYy-62 &/270/ J /21 Detector Cal Date: A/-/ 7-0 Detector Cal Due Date: //-/ 7 - 0 6 Instrument: urn- Instrument ID #: ZOJY88 Litnunent Cal Date: / (77 Instrument Cal Due Date: rf-174d.
From the Daily Pipe Survey Detector Control Form for the Selected Detector Background Value I? cprn MDCRSbtIC lt?Hq cpm Efficiency Factor for Pipe Diameter ,0 0 olb (from detector efficiency determination)
MDCStatlC Cements:
3,32109 d p d Is the MDCSbn,acceptable?
(,vi a
I; ec , S ~ Jt\/ Q
/Pp No cm2 (dno,adjust sample count time and recalculate M D C L , )
/
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Technician Signature - -bf=& pc Q L L ~ V Pipe Interior Radiological Survey Position Feet into Pipe Count Time Gross Counts Gross Net dpm/100cm2 1 Package Page 1 of I REFERENCE COPY Attachment 3, Page 1
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SECTION 7 ATTACHMENT 3 1 PAGE(S)
DQA Check Sheet Design # EP Rx207 Revision # Original Survey Unit # EP Rx 207 Preliminary Data Review' Answers to the following questions should be fully documented in the Survey Unit Yes No NIA Release Record
- 1. Have surveys been performed in accordance with survey instructionsin 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 0.5 DCGLw for Class 3 survey units?
- 3. Is the instrumentationMDC 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 measurements and smear analysis 10% DCGLW? X
~~
- 6. Were the MDCs and assumptions used to develop them appropriate for the instruments and techniques used to perform the suwey?
- 7. Were the survey methods used to collect data proper for the types of radiation involved and for the 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 facillfy3 Graphical Data Review
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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
~~~~ ~
Data Analysis
- 1. Are all sample measurements below the DCGLw (Class 1 812), or 0.5 DCGLw (Class 3)? X
- 2. Is the mean of the samnle data DCGLw? X
- 3. If elevated areas have been identifted by scans and/or sampling, is the a v w activity in each X elevated area < DCGLEW(Class l), 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) L the critical value? X Comments:
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- r CS-0912 Page 1 of 1
SECTION 7 ATTACHMENT 4 1 DISC
Survey Unit Release Record 7 Design ## EP-Rx208 I I
Revision# I 1
Original I Page I
1 of 3 EP-Rx 208
- 1) Embedded Pipe (EP) Survey Unit EP Rx-208 meets the definition of embedded pipe for Plum Brook Reactor Facility (PBRF).
- 2) EP 208 is a Class 1, Group 2 survey unit as per the PBRF Final Status Survey Plan (FSSP) and Technical Basis Document (TBD)-O6-004.
- 3) Surveys in EP 208 were performed using a scintillation detector optimized to measure gamma energies representative of CO-60. Sample #EP 2-1 from Survey Request (SR)-13 was referenced for this decision.
- 4) Survey Instructions for this survey unit are incorporated into and performed in accordance with (IAW) the Babcock Services Incorporated (BSI)/LVS-002, Work Execution Package (WEP)05-006. Survey instructions described in this document constitute Special Methods and the survey design used in the acquisition of survey measurements.
- 5) Instrument efficiency determinations are developed in accordance with the BSULVS-002, WEP 05-006,these determinations are appropriate for the types of radiation involved and the media being surveyed.
I Approval Signatures I Date:
0 COPY
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FSS Design # EP Rx 208 1 Revision # Original I I Page 2 of 3 i
1.0 HistoryDescription 1.1 The subject piping described in this report is an instrumentation line for equipment and accessories utilized in Quad B. This survey unit involves -
4 of instrument piping.
2.0 Survey Design Information 2.1 EP Rx 208 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 4 survey measurements.
2.3 Surface area for the 2 ID piping is 486 cm2for each foot of pi ing, P
corresponding to a total 2 ID piping surface area of 1,944 cm (0.19 m2) for the entire length of (4) of 2 piping..
3.0 Survey Unit Measurement LocatiomData 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 mredyx 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 208 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 Rx 208 Revision # Original Page 3 of 3 5.5 Statistical Summary Table 2"
Statistical Parameter Pipe Total Number of Survey Measurements 4 Number of Measurements >MDC 0 Number of Measurements Above 50% of DCGL 0 Number of Measurements Above DCGL 0 Mean 0.042 Median 0.046 Standard Deviation 0.017 I Maximum I 0.056 I r- Minimum I 0.020 I 6.0 Documentation of evaluations pertaining to compliance with the unrestricted use limit of 25 mdyr and dose contributions from Embedded Pipe and radionuclides contributing 10% in aggregate of the total dose for both structural scenarios and soils.
6.1 A review of the survey results has shown that the dose contribution for EP Rx 208 to be less than 1 mredyr. The dose contribution is estimated to be 0.042 mredyr based on the average of the actual gross counts measured.
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 208 & Spreadsheet
I I SECTION 7 ATTACHMENT 1 z PAGE(S)
I BSI EP/BP SURVEY REPORT Standard Deviation 0.017 Maximum I 0.056 i
Minimum 0.020 Survey Technician(s) I Rosenhagen r-Survey Unit Classification I 1
. - Group TBD O6-004 PiDina 2 SR-13 Radionuclide DisttibutionSample EP 2-1 Measured Nudide C060 Area FactodEMCUsed No PasslFail FSS PaSS MREWR Contribution 4 COMMENTS:
ACTMTY VALUES NOT BACKGROUND CORRECTED I RP Engineer I Date 6 -Z/-O?
8/21/2007
EP Rx 208 2" Pipe TBD 06-004 Group 2
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Cos0 activity COS0 actlvity CS-137 activity Eu-1st activity Eu-I S4 activity (total dpm) (dpm1100crn2) (dpm1100cm2) (dpmllOOcm2) (dpm1100cm2) Unity 21,875 4,497 2,334 2 130
- 0.02(
-m 62.500 12.850 _- 6,669 6 373 0.03 71 1 8,995 4,668 4 - _1 26 ~ 0.031 121257 6.335 354 0.05:
- 0.04:
0.04f 0.01:
0.oa 4 .-____- LMX ulIN - 0.02(
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SECTION 7 ATTACHMENT 2 2 PAGE(S)
I BSI/LVSPipeCrawler-002 Revision 4 Pipe Interior Radiological Survey Form Date: 3 - 2S O L Time: 130 0 Access Point Area: d e ~ 2
-2 Pipe ID#: px. 3O F Pipe Diameter: 2 s bc9K L
-z It Building: p% Elevation: S pLI,+~ a System: TiJJfl4fl<.%r L;c/2, T c :*-c Type of Survey Investigation Characterization Final Survey ?Q Other fl Gross (2060 4 cs ,
Detector ID# / Sled ID# Y4-62 / Z r Z 7 0 / I /*/
Detector Cal Date: / 7 - dllJ .5r Detector Cal Due Date: /7 - 3 b Instrument: >3!s+r Instrument ID #: 3.034w Instrument Cal Date: 17 -d c 4
- cJL lnstnunent Cal Due W e : / ? f i e . / *c(.r From the Daily Pipe Survey Detector Control Form for the Selected Detector Backgroundvalue 4 r ? cpm MDCRstatic r0.q cpm Efficiency Factor for Pipe Diameter 0 00 \ b (from detector efficiency determination)
MDCStatlC Comments:
33&$ d p d Is the MDC,,,, acceptable?
/
KMi-7-f#L a 5 w L d 10-No L/
cm2 (if no, adjust sample count time and recalculate MDa,,)
- )dTf: ?!.f,-TILd ) # 2 p.Gg 1 2 jjax
-
Sd/tiqiqLcd j) 0 4 t ; iu t p & - z o r q v ~-?*?E AWE ?og*fi-d ,sF 3 d C/.J+L ;4 & f i C <
R d d @(fl Lev fi 8 &~-z@bTfiL @?i?EtP<r w
Technician Signature I
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Pipe Interior Radiological Survey Package Page 1 of-z/
REFERENCECOPY Attachment 3, Page 1
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SECTION 7 ATTACHMENT 3 1 PAGE(S)
DQA Check Sheet Design # 1 EP Rx208 I Revision# 1 Original 1 Survey Unit# I EP Rx 208 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 instrumentation MDC for structure static measurementsbelow the DCGLw for Class 1 and 2 survey units, or below 0.5 DCGLWfor Class 3 survey units? I lx
- 3. Is the instrumentation MDC for embeddedlburied piping static measurementsbelow the DCGLW? X
- 4. Was the instrumentation MDC for stnrcture scan measurements, soil scan measurements, and embeddedlburied piping scan measurements below the DCGLW,or, if not, was the need for additional static measurements or soil samples addressed in the survey design?
- 5. Was the instrumentation MDC for volumetric measurements and smear analysis < 10% DCGLw ? X
- 0. Were the MDCs and assumptions used to develop them appropriate for the instruments and techniques used to perform the survey?
- 7. Were the survey methods used to collect data proper for the types of radiation involved and for the X
media being surveyed?
- 8. Were "Special Methods" for data collection properly applied for the survey unit under review? X
- 0. Is the data set comprised of qualified measurement results collected in accordance with the survey desian, which accurately r e l k t s the radiological status of the facility?
I. 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
- 2. Is the mean ofthe sample data DCGLW? X
- 3. If elevated areas have been i d e n t i by scans andlor sampling, is the average activity in each X elevated area < DCGLEK (Class l),DCGLw (Class 2), or e0.5 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? I I I x comments:
'Y Form CS-0912 Rev 0 Page 1 of 1
SECTION 7 ATTACHMENT 4 1 DISC