Text

Nasa - Plum Brook, Embedded Pipe Survey Records
	ML073450100
Person / Time
Site:	Plum Brook File:National Aeronautics and Space Administration icon.png
Issue date:	06/08/2007
From:	Case R; US National Aeronautics & Space Admin (NASA)
To:	Snell W; NRC/RGN-III/DNMS/DB
References
	Download: ML073450100 (67)
	v • d • e

PLUM BROOK REACTOR FACILITY DECOMMISSIONING PROJECT OFFICE 6100 Columbus Avenue, Sandusky, OH 44870 Phone: (419)621-3269 Fax: (419) 621-3318 MEMORANDUM June 8,2007 To:

Mr. William Snell, NRC From:

Subject:

Rod Case, NASA Project Assistant RSO PBRF Project Embedded Pipe Survey Unit Release Records P

Enclosed please find the following copies of the PBRF embedded pipe survey unit release records for your review in preparation for your upcoming site inspection.

Survey Unit Release Record EP 1.24 Survey Unit Release Record EP 1.25 Survey Unit Release Record EP 1.26 Survey Unit Release Record EP 1.36 If you have any questions, please feel free to contact Bill Stoner (419) 621-3349 or myself at (419) 621-3269.

We are looking forward to meeting with you in June.

cc: Keith Peecook Project File

COPY EP-1.24 Design #

Revision #

Original Page 1 of 3 Survey Unit #(s)

Description

~

~~

1.24

1) Embedded Pipe (EP) Survey Unit 1.24 meets the definition of embedded pipe for Plum Brook Reactor Facility (PBRF).

2) EP 1.24 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 1.24 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 ) Instmment efficiency determinations are developed in accordance with the BSJILVS-002, WEP 05-006, these determinations are appropriate for the types of radiation involved and the media being surveyed.

FSS Design # EP 1.24 1.o 2.0 3.0 4.0 5.0 Revision # Original Page 2 of 3 HistoryDescription 1.1 The subject pipe system is the 3 purge line for Canal G. The function of this pipe was to convey water from the one 3 inch riser in Canal G to the. HD sump in Pump Room #22 on the Rx Building -25 ft, where the pipe is currently breached.

EP 1.24 consists of approximately 39 feet in length from the pump room to the riser in Canal G. The pipe section has a three mitered elbows ranging between 45 and 90.

1.2 Survey Design Information 2.1 2.2 EP 1.24 was surveyed IAW Procedure #BSYLVS-O02.

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 30 survey measurements.

Surface area for the 3 ID piping is 729.7 cm2 for each foot of piping, corresponding to a total 3 ID piping surface area of 21,891 cm2 (2.2 m2) for the entire length of (30) of 3piping..

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

Survey Unit Investigatiodtesults 4.1 None Data Assessment Results 5.1 5.2 5.3 5.4 Data assessment results are provided in the EPBuried Pipe (BP) Survey Report provided in Attachment 1.

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

When implementing the UNty 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 1.24 passes FSS Background was not subtracted fiom the survey measurements and the Elevated Measurement Comparison (EMC) was not employed for this survey unit.

FSS Design # EP 1.24 5.5 Statistical Summary Table Revision # Original Page 3 of 3 Statistical Parameter Total Number of Survey Measurements Number of Measurements >MDC Number of Measurements Above 50X of DCGL Number of Measurements Above DCGL Mean Median Standard Deviation Maximum Minimum 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 1.24 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 - BSI EPBP Survey Report -Pipe Interior Radiological Survey Form - DQA Worksheet -Disc containing RR for EP 1.24 & Spreadsheet Pipe 30 28 0

0 0.019,..<c-

/&

0.020 0.005 0.031 0.01 1

SECTION 7 ATTACHMENT 1 3 PAGE(S)

I I

Standard Deviation 0 CQ5 Maximum 0.031 Minim u m 0.01 1 I

ROSENHAGEN Sufvey Technbian(s) 1 La!%!%

BSI EPlBP SURVEY REPORT MREMNR Contribution

<I n i Classibation 1

Survey UI TED o6004 Piping Group 2

SR-13 Radionuclide Distribution Sample EP 2-1 Measured Nuclide cow Area FactwEMC Used NO I &&d 6-7-07 I

RP Engineer I Date I

EP 1.24 3" Pipe TBD 06-004 Group 2 Cs-IS7 activity (dpm1lWcrnZ) 3,201 1,524 2.540 3,048 2,337 3,556 3,709 2.337 2,032 2,337 2,540 2,032 2,185 2,032 1,321 2,032 2,185 2,337 2,693 2,845 Co-M).ctMty (total dpml 45,000 21,429 35,714

~

42,857 32,857 50,000 52,143 32,857 28.571 32,857 35,714 28,571 30,714 28,571 18,571 28,571 30,714 32,85i 37,85i 40,00(

37,85i 37,851 30,71d 25,71r

- 25,71r 18,57' 35,71r 23.57' 32,85; 21,42!

Eu-I52.ctMty (dpnllOOm2) 51 24 41 49 37 57 59 37 32 37 41 32 35 32 21 32 35 37 43 I

45 Coco ac-(dpm1100cmZ) 6,167 2,937 4,894 5,873 4,503 6.852 7,146 4,503 3,916 4,503 4,894 3,916 4,205 3,9X 2,545 3,91 4,20E 4,502 5,18 5.482 5,18 5,18 4,201 3.52d 3,524 2,54t 4.89 3,23(

4,50:

2,93;

-~

kl-1m.ctMty (dpnllOOmz) 179 85 142 170 131 199 207 131 114 13t 142 114 122 114 74 114 122 131 150 159 150 150 U n b 0.oz 0.01:

0.02' 0.02!

0.021 0.031 0.03 0.021 0.01' 0.021 0.02 0.01 0.01!

0.01 0.01 0.01 0.01 0.02 0.02 0.02 0.02 0.02 Eu-154 adlvily (dpm1100unZ) 36 17 29 35 27 40 42 27 23 27 29 23 25 23 15 23 25 27 31 32 31 31 25 21 21 15 29 IS 27 17 2,693 2,693 2,185 1.829 1,829 1,321 2,540 1.677 Nb-04 sahrlty (dpnll WmZ) 3 1

2 3

4 2

2 2

1 2

2 2

3 3

7 7

2 2

2 1

2 i

2 1

43 35 29 29 21 41 27 43 ii' 0.01 0.02 0.01 0.02 0.01

EP 1.24 3" Pipe TBD 06404 Group 2 6

E e

a E

0 2

Cod0 activity Co40 aaivlty Cs-137 sdlvlty Eu-152 rctlvlty Eu-IS4.caVlty Nb-94.ctMty A g - l o h activity gcpm ncpm (tobl dpm)

(dpmllWmZ)

(dpmIlWcm2)

(dpn1100cmZ)

(dpmlI00un2)

(dpmllWcm2)

(dpmlI00cmZ)

""b MEAN 0.019 MEDIAN 0.020 STD DEV 0.005 MAX 0.031 MIN 0.011 -

2 o f 2

SECTION 7 ATTACHMENT 2 5-PAGE(S)

Pipe Interior Radiological Survey Form Date:

/ A

. &r Time:

,/A Type of Survey Investigation Charactenzatlon-m Other v

Building: q w

.q-i=i=

Elevation:

,- a 5 Access Point Area:

9 7 WJC System: @&d&, G Bd/~cr&

PipeDiameter:

3 Pipe ID #

/- a./

Detector:

w-kp-Detector ID #:

9 (LtLfB 2- - rz\\

Cal Date:

/ / - / 7 - a 5 ;

Cal Due Date:

1//7+4 Sled Size 3

inch

~

Instrument:

2 3T-c -I Instrument ID #:

2 / s 7 3 Cal Date:

// - / -7 3 5 Cal Due Date:

/ [ #

I 7

-0 b From the Daily Pipe Survey Detector Control Form for the Selected Detector Background Value 5.1 CPm MDCktatIc

/ D, 7 CPm e@d:emy,

&+,!nwC!@fi Efficiency Factor for Pipe Diameter m c s t a h c 2-dpm/lOOcmZ 0-0001. 4 (taken from d e

t e

c t

0 7

1s the bfDcJhpc acceptable? Q NO (Ifno, adjust sample count time and recalculate MDCK,,)

Comments:

,c P,L4,&7

b-

& 8--

Y $ ?,, n -

h Y

Pipe Interior Radiological Survey Package Page 1 of &

REFERENCE COPY, Page 1 I

/

/-a G

d4L G ?Uk&.E Pipe Interior Radiological Survey Form (Continuaiion Form)

Package Page 2 of 2 REFERENCECOPY, Page 2

Pipe Interior Radiological Survey Form Date:

f L-Lo-0)

Time:

( 9 2 0 Building:

Elevation:

-Lj-Access Point Area: C 4 / v 4 ~ G System:

PW2LVLC Pipe Diameter:

3 4 PipeID#

l. t y Type of Survey Investigation Characterization Other /

Sled Size 3

inch Detector:

4Y-/, 2 Detector ID #:

20 Yf003--\\2\\

Cal Date:

//-/ 7-UJ-Cal Due Date:

//-/ 7v,L Instrument:

z3-B --(

Instrument ID #:

2f.LL7 Cal Date:

f77 7 - 6 Cal Due Date:

/ / 7 7 -uh r

From the Daily Pipe Survey Detector Control Form for the Selected Detector Background Value

/ p f cpm MDC%,C 14 CPm Efficiency Factor for Pipe Diameter MDCStatlC z BqG dpm/lOOcmz Is the IvlDCstatlc acceptable? @ No 0-0001 4 (taken fiom detect0 (if no, adjust sample count tlme and recalculate MDCR,,,,)

Comments f

d/V7iNLA 47-cM J-Li/zll(-lj Pipe Interior Radiological Survey Radiological Survey Commenced: Date: 1 2-2 d*J-Time: / Y L 0 9

10

'-c Package Page 1 of -

REFERENCE COPY, Page 1

SECTION 7 ATTACHMENT 3 PAGE(S)

DQA Check Sheet Answers to the following questions should be fully documented in the Survey Unit Release Record Have surveys been performed in accordance with survey instructions in the Survey Design?

!. 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.

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

~

Design #

I -EP 1.24 I Revision # 1 Original I Yes No NIA X

X X

Survey Unit# I EP 1.24 I.

Was the instrumentation MDC for structure scan measurements, soil scan measurements, and static measurements or soil samples addressed in the survey design?

embeddedbuned piping scan measurements below the DCGLw or, if not, was the need for adddional Was the instrumentation MDC for volumetnc measurements and smear analysis c 10% DCGLw ?

i.

I.

j.

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 collect data proper for the types of radiation involved and for the media being surveyed?

Were Special Methods for data wllection properly applied for the survey unit under review?

Is the data set comprised of qualified measurement results collected in accordance with the survey desion. which accuratelv reflects the radioloaical status of the facilitv?

X X

X I.

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

Graphical Data Review X

I.

Has a Dosting plot been created?

I I

I x

I.

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

Has a histooram (or other freouencv dot) been created?

I I

I x

X

1.

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

X

?. Is the mean of the sample data c DCGLw?

1 x 1 I

5.

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

X 3

If elevated areas have been identified by scans andlor sampling. is the average activity Ineach elevated area < DCGLEMC (Class 1). < DCGLw (Class 2). or ~0 5 DCGLw (Class 3)7 X

ommenk:

Form CS-09R Rev 0 Page 1 of 1

SECTION 7 ATTACHMENT 4 1 DISC

COPY EP-1.25 Revision #

Original Design #

Page 1 of 3 Survey Unit #(s)

Description

~~

1.25 1 ) Embedded Pipe (EP) Survey Unit 1.25 meets the definition of embedded ipe for Plum Brook Reactor Facility (PBRF).

!) EP 1.25 is a Class 1, Group 2 survey unit as per the PBRF Final Status Survey Plan (FSSP) and Technical Basis Document (TBD)-06-004.

I) Surveys in EP 1.25 were performed using a scintillation detector optimized o measure gamma energies representative of co-60. Sample #EP 2-1 fiom Survey Request (SR)-13 was referenced for this decision.

I) Survey Instructions for this survey unit are incorporated into and performed n accordance with (IAW) the Babcock Services Incorporated (BSI)LVS-O02, Work Execution Package (WEP)05-006. Survey instructions described in this iocument constitute Special Methods and the survey design used in the tcquisition of survey measurements.

5) Instrument efficiency determinations are developed in accordance with the SSVLVS-002, WEP 05-006, these determinations are appropriate for the types

,f radiation involved and the media being surveyed.

FSS Design # EP Rx155 I Revision # Original Survey Unit: Rx155 1.0 HistoryiDescription 1.1 The subject pipe is the floor drain line from Canal "F" to the -25 ft of the Rx Building in Pump Room #22. The function of this pipe was to convey water from a floor drain located in Canal "F" to the Hot Drain (HD) sump in Pump Room #22 on the Rx Building -25 ft, where the pipe is currently breached.

EP 1.25 consists of 20 linear feet (') of 6 inch (") Inside Diameter (ID) piping from the breach point in Pump Room #22 to the floor drain in Canal "F". The pipe section is relatively straight with no bends.

1.2 2.0 Survey Design Information 2.1 2.2 EP 1.25 was surveyed IAW Procedure #BSI/LVS-002.

1W? of the 6" ID pipe was accessible fm survey. The accessible 6" ID pipe was surveyed by static measurement at one foot increments, for a total of 20 survey measurements.

Surface area for the 6" ID piping is 1,459 cm2 for each foot of piping, corresponding to a total 6" ID piping surface area of 29,180 cm2 (2.9 m2) for the entire length of (20') of 6" piping..

2.3 3.0 Survey Unit Measurement Locations/Data Pipe interior radiological survey forms are provided in Attachment 2 of this release record.

3.1 4.0 Survey Unit InvestigatiodResults 4.1 None 5.0 Data Assessment Results 5.1 5.2 Data assessment results are provided in the EPlSuried Pipe (BP) Survey Report provided in Attachment 1.

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

When implementing the Unity Rule, provided in Section 3.6.3 of the FSSP, and applying the nuclide fractions, provided in TBD-06-004, the survey unit that is constituted by EP 1.25 passes FSS.

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

5.3 5.4 Page 2 of 3 I

Number of Measurements Above 50% of DCGL Number of Measurements Above DCGL Mean Median Standard Deviation Maximum Minimum Survey Unit: &I55 0

0 0.003 0.002 0.002 0.012 0.001 5.5 Statistical Summary Table Statistical Parameter Total Number of Survey Measurements Number of Measurements >MDC Pipe 6.0 7.0 Documentation of evaluations pertaining to compliance with the unrestricted use limit of 25 mredyr and dose contributions h r n 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 1.25 to be less than 1 mredyr. The dose contribution is estimated to be 0.003 mredyr based on the average of the actual gross counts measured.

Attachments - BSI EPBP Survey Report - Pipe Interior Radiological Survey Form - DQA Worksheet -Disc containing RR for EP 1.25 & Spreadsheet

SECTION 7 ATTACHMENT 1 z

PAGE(S)

BSI EPIBP SURVEY REPORT Pipe ID I.25 Survey Location

-27 TRENCH Survey Date I 04-Jan-06 PiDeSize 1

6 I

I DetectorEfficiency I

0.002 2350-1 #

134208 RoutineSurvey I X

I SurveyTime I 0823 1459 P i p Ares Incorporated by btecbor Efficiency (in cm2)

Detector-Sled #

BICRON IMGI Field BKG Icpm) 18 Field MDCR (cpm) 22 Median I

0.002 QA Survev I Nominal MDC fdPWlODcm2l I 333 I

Total Number of Survey Measurements Number of Measurements >MDC Number of Measurements Above 50% DCGL RP Engineer I Date 1 && )'&,&f 6 0 7 20 18 0

6/6/2037 Number of Measurements Above DCGL 0

Mean 0.003 Survey Unit Classification TBD 06-004 Piping Group SR-13 Radionuclide Distribution Sample Measured Nuclide Area Factor/EMC Used PasslFail FSS MREMNR Contribution 1

2 EP 2-1 Go60 No Pass

<V -0 F-Cal Due Date:

1.z " S d 4 Instrument:

2590 - f Instrument ID #:

/ 7 4 > 0 %

Building:

&2+-il.n Elevation:

-25 Access Point Area: - 2 7 %hfwLk Type of Survey Investigation Characterization

(&=$

Other 4

Sled Size b ', - / 0 7 inch Cal Date:

,>->a

- 0 F Cal Due Date.

p - Z d - 6 From the Daily Pipe Survey Detector Control Form for the SelectedDetector Background Value

/ e CPm rnCRSt.¶tlC Efficiency Factor for Pipe Diameter M D C S t Z t I C 333 dpm/lOOcm*

cpm ZL 0 I W (taken from detect0 Is the MDCsrahc acceptable? &&

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

<N,%*L s - i a. cq

/

-5 T r / O'WflC S G 1

Pipe Interior Radiological Survey Radiological Survey Commenced: Date.

/ -. /. f l ' L

~

h

~

89~'"

REFERENCECOPY Package Page 1 of 2 I, Page 1

I Pipe Interior Radiological Survey Form (Continuation Form)

Package Page '

a of-, Page 2

h

SECTION 7 ATTACHMENT 3 I

PAGE(S)

DQA Check Sheet Survey Unit #

Design #

I EP 1.25 I Revision # I Original I EP 1.25 Answers to the following questions should be fully documented in the Survey Unit Release Record Have surveys been performed in accordance with survey instructions in the Survey Design?

I.

?.

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 embeddedburied DiDina static measurements below the DCGLw ?
Yes No N,f X
X X
1.
Was the instrumentation MDC for structure scan measurements, soil scan measurements, and static measurements or soil samples addressed in the survey design?
embeddedburied piping scan measurements below the DCGLW, or, if not. was the need for additional Was the instrumentation MDC for volumetric measurements and smear analysis < 10% DCGLw ?
5.
5.
7.
3.
3.
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 collect data proper for the types of radiation involved and for the media being Surveyed?
Were Special Methods for dafa collection properly applied for the survey unl under review?
Is the data set comprised of qualified measurement results collected in accordance with the survey design, which accurately reflects the radiological status of the faciliip Data Analysis X
X X
X X
1.
2.
3.
Has a posting plot been created?
Has a histogram (or other frequency plot) been created?
Have other graphical data tools been created to assist in analyzing the data?
5. Is the result of the statistical test (S+ for Sign Test or W, for WRS Test)? the critical value?
I I
I x
X X
X Comments:
1.
2.
3.
4.
Are all sample measurements below the DCGLw (Class 1 & Z), or 0.5 DCGLw (Class 3)?
Is the mean of the sample data < DCGLw?
If elevated areas have been identified by scans andlor sampling, is the average activity in each elevated area < DCGLEMC (Class l),
< DCGLw (Class 2), or <0.5 DCGLw (Class 3)?
Is the result of the Elevated Measurements Test c 1.O?
Form cs-09n Rev 0 X
X X
X Page 1 of 1
SECTION 7 ATTACHMENT 4 1 DISC
COPY Survey Unit Release Record Design #
Survey Unit #(s)
Description EP-1.26 I
Revision#
I Original I Page 1 of 3 1.26 I) Embedded Pipe (EP) Survey Unit 1.26 meets the definition of embedded
)ipe for Plum Brook Reactor Facility (PBRF).
!) EP 1.26 is a Class 1, Group 2 survey unit as per the PBRF Final Status 3urvey Plan (FSSP) and Technical Basis Document (TBD)-06-004.
1) Surveys in EP 1.26 were performed using a scintillation detector optimized o measure gamma energies representative of CO-60. Sample #EP 2-1 from Survey Request (SR)-13 was referenced for this decision.
1) Survey Instructions for this survey unit are incorporated into and performed n accordance with (IAW) the Babcock Services Incorporated (BSI)/LVS-002, Work Execution Package (WEP)05-006. Survey instructions described in this iocument constitute Special Methods and the survey design used in the scquisition 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 3f radiation involved and the media being surveyed.
FSS Design # EP 1.26 Survey Unit: 1.26 Revision # original Page 2 of 3
FSS Design # EP 1.26 Revision # Original Page 3 of 3 5.5 Statistical Summary Table Statistical Parameter Total Number of Survey Measurements Number of Measurements >MDC Pipe 21 21 Number of Measurements Above 50% of DCGL Number of Measurements Above DCGL Mean t
I 0.021 I
Median 0
0 0.022 Standard Deviation 0.005 Maximum 0.033 Minimum 0.013
~
6.0 Documentation of evaluations pertaining to compliance with the unrestricted use limit of 25 mrerdyr and dose contributions ffom 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 1.26 to be less than 1 mredyr. The dose contribution is estimated to be 0.022 mredyr based on the average of the actual gross counts measured.
7.0 Attachments - BSI EPBP Survey Report -Pipe Interior Radiological Survey Form - DQA Worksheet -Disc containing RR for EP 1.26 & Spreads1
SECTION 7 ATTACHMENT 1 z PAGE(S)
mw BSI EPlBP SURVEY REPORT Survev Date I --atton I
-27TRENCH I
71 797.1 -
44-62EU4402-121 tlclencv 0.00014 5.1B.8 PI P b lu.lk-.d4D.l..t~Emrhn(h rlnn C k l
m w e.
240800 10.7H1.9 QA Survey I
I /
Nominal MDC IWC+W I
2.542 Survey Measurement Resuiis Total Number of Survey Measurements Number of Measurements Above 50% DCGL Number of Measurements Above DCGL 21 Number of Measurements >MDC 21 0
0 Mean 0.022 Median 0.021 Standard Deviation 0.005 I
Maximum I
0.033 Minimum 0.013 I
DncChlUAGEN I I Survey Technician@)
Survey Unit Classification 1
TED oMx)4 Piping Grwp 2
SR-I3 Radionuclide Distribution Sample EP 2-1 Measured Nuclide COM)
Area FactorEMC Used NO MREMNR Contribution
< I PassiFail FSS Pass I
COMMENTS:
ACTMTYVALUES NOT BACKGROUND CORRECTED 6-7-07 RP Engineer I Date
EP 1.26 3 Pipe TBD 06-004 Group 2 Unity -
0.018 0.025 0.020 0.020 0.020 0.031 0.020 0.025 0.021 0.022 0.024 0.025 0.025 0.033 0.014 0.024 0.018 0.013 0.021 0.020 0.016 7
0.022 0.021 0.005 0.033 0.013 a
/
I I
I I
I I
I MEAN MEDIAN STD D N
]MAX IMIN
).
c :
CO-BO activity CdiO scUvKy Cs-137 activity Eu-I52 acttvlty Eu-154 lctivity N
W activity AQ-108m ScUvlty e
gcpm ncpm (total dpm)
(dpdlOOcmZ)
(dprn1100cmZ)
(dpfnIlOOcm2)
(dpm1100crnZ)
(dpm1100cmZ)
(dpn1100cm2) a I
I I
I I
I I
I I
l o f l
SECTION 7 ATTACHMENT 2 5
PAGE(S)
Pipe Interior Radiological Survey Form Date:
/2-/6 O b Time:
/ # L a Building:
E X Elevation:
Access Point Area:
R&CI{
System:
~, + J A L F-Pam6 Pipe Diameter:
PipeID#
I, 2 6 Type of Survey Investigation Characterization Sled Size
-3 If inch Detector:
9 9 6 Z-Detector ID #:
26vvC)z-lZ(
Cal Date:
J]-f 7 - 0 (6-Cal Due Date:
//-f 7-o't Cal Date:
/ / - f 7 - 0 Cal Due Date:
//-r 7 - (3-(2 Background Value
,r.
I cpm 7J3 SG Instrument ID #:
2 / 2 2 - 2 3 Instrument:
From the Daily Pipe Survey Detector Control Form for the Selected Detector MDCRstahc 7 CPm ecr:c;eney Op&/4
,a)-*.\\
Efficiency Factor for ;:Diameter 0 I 0 0 0 1 4 (taken from detector?
m c s t a h c 2 8'!* dpm/lOOcmz Comments:
,mt 7; A-c
$.c/&&+/
Is the MDCsb+,, acceptable? a No (Ifno, adjust sample count tune and recalculate M D C L J Pipe Interior Radiological Survey Radiological Survey Commenced Date: / 2- /6-% 5-Time: / 6 0
Pipe Interior Radiological Survey Form (Continuation Form E-REFERENCE COPY 0 Package Page 2 of &, Page 2
Pipe Interior Radiological Survey Form Date:
I L-L&-GS Time:
/ f d 25 Building:
ag Elevation:
-2 Access Point Area: C,qdpsc F System:
P d
W Pipe Diameter:
3 lf Pipe ID #
f.,2 Type of Survey Investigation Characterization Other J Sled Size 3
inch Detector:
92-6 Z Detector ID #.
L O Y Y 0 2-L-12' Cal Date:
//-/ 7-0 5-Cal Due Date:
/ / 7 7 - t 7 Q Instrument:
23 m i Instrument ID #:
u 7 2 2 3 Cal Date:
1/77
-8 >-
Cal Due Date:
//17-0 G From tke Daily Pipe Survey Detector Control Form for the Selected Detector BackgroundValue I.f cpm Efficiency Factor for Pipe Diameter 0 - 0 001 4 MDcstahc 2 8.I 2-dpm/100cm2 MDCRs-nc
4.
4 CPm e@dmcq,
&..?yrn:FJ;d
/I r
(taken fiom detector Is the MDCsbUc acceptable? a No (Ifno, adjust sample count h m e and recalculate MDCR&
Comments:
rdnffAJt/4 7f d r J JUfLdW Pipe Interior Radiological Survey Radiological Survey Commenced: Date: /<- 2 Time:
/ y o M z
Package Page 1 of-REFERENCE COPY 0, Page 1
f.
r.
r' REFERENCE COPY
SECTION 7 ATTACHMENT 3 I
PAGE(S)
Survey Unit #
Design #
I EP 1.26 I Revision# I Original I EP 1.26 Yes X
Answers to the following questions should be fully documented in the Survey Unit Release Record I.
Z.
3.
Have surveys been performed in accordance with survey instructions in the Survey Design?
Is the instrumentation MDC for structure static measurements below the DCGLw for Class 1 and 2 survey units, or below 0.5 DCGLw for Class 3 survey units?
Is the instrumentation MDC for embeddedburied piping static measurements below the DCGLw ?
X No N/A X
~
~
X
9.
Is the data set comprised of qualified measurement results collected in accordance with the survey design, which accurately reflects the radiological status of the facility?
GraDhical Data Review
1.
Was the instrumentation MDC for structure scan measurements, soil scan measurements. and static measurements or soil samples addressed in the survey design?
embeddedhuried piping scan measurements below the DCGLw, or, if not, was the need for addaional Was the instrumentation MDC for volumetric measurements and smear analysis -z 10% DCGLw ?
5.
5.
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 collect data proper for the types of radiation involved and for the media being surveyed?
Were 'Soecial Methods" for data collection oroDerlv aoolied for the survev unit under review?
8.
1.
Has a oostina 0101 been created?
I I
I x
X X
X X
~
~~
2.
Has a histogram (or other frequency plot) been created?
Data Analysis X
1. Are all sample measurements below the DCGLw (Class 1 8 Z), or 0.5 DCGLw (Class 3)?
1 x 1 I
3.
Have other graphical data tools been created to assist in analyzing the data?
X
5. Is the result of the statistical test (S+
for Sign Test or W, for WRS Test)? the critical value?
I I
I x
2.
3.
4.
Is the mean of the sample data < DCGLw?
If elevated areas have been identified by scans andlor sampling, is the average activity in each elevated area < DCGLEMC (Class 1). < DCGLw (Class 2). or ~0.5 DCGLw (Class 3)?
Is the result of the Elevated Measurements Test < 1.O?
Comments:
X X
X Page 1 of 1
SECTION 7 ATTACHMENT 4 1 DISC
Design #
Survey Unit #(s)
Description Survey Unit Release Record EP 1.36 1
Revision# I Original 1 Page 1 of 4 EP 1.36
1) Embedded Pipe (EP) Survey Unit EP 1.36 meets the defmition of embedded pipe for Plum Brook Reactor Facility (PBFW). The survey unit consists of the drain line from Canal E in the Containment Building to the -25 ft of the Rx Building in Pump Room #22.
2) EP 1.36 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 1.36 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)&VS-O02, Work Execution Package (WEP)05-006. Survey instructions described in this document constitute Specid 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:
Approval Signatures FSS/Characterization Engineer 1
A, fl 2-(FSS/Characterization Engineer)
FSS/Characterization Manager I
k - d - 0 7 h - 7-a7 Technical Reviewer
FSS Design # EP 1.36 Revision # Original Page 2 of 4 1.0 2.0 3.0 4.0 5.0 HistoryDescription 1.1 1.2 1.3 EP 1.36 is the drain line from Canal E.
The subject pipe is the drain line from Canal E in the Containment Building to the -25 ft of the Rx Building in Pump Room #22. The function of this pipe was to convey water from three floor drains, identified as hole A, hole B and hole C, in Canal F of the Containment Building to the HD sump in Pump Room #22 on the Rx Building -25 ft, where the pipe is currently breached.
EP 1.36 consists of approximately 56 feet in length from the breach point in Pump Room #22 to the furthermost floor drain in Canal E, involving slight bend of approximately 30 and two Y connections to the ancillary floor drains in the canal. The pipe diameter reduces from a 10 inch ID to 8 and 6 inch ID toward the canal floor drain openings.
Survey Design Information 2.1 2.2 2.3 2.4 2.5 2.6 EP 1.36 was surveyed IAW Procedure #BSIILVS-002.
100% of the 10 and 8 ID pipe was accessible for survey. However, due to an obstruction caused by a pipe weld, only 6 of the estimated total of 9 pipe length of hole C piping was accessible. The accessible IO, 8 and 6 ID pipe was surveyed by static measurement at one foot increments, for a total of 53 survey measurements. Approximately 3 of 6 piping was not accessible.
Surface area for the 10 ID piping is 2,432 cm2 for each foot of piping, corresponding to a total 10 ID piping surface area of 72,960 cm2 (7.3 m2) for the entire length of (30) of 10 piping.
Surface area for the 6 ID piping is 1,459 cm2 for each foot of piping, corresponding to a total 6 ID piping surface area of 18,967 cm2 (1.9 m2) for the accessible length (13) of 6 piping.
Surface area for the 8 ID piping is 1,946 cm2 for each foot of piping, corresponding to a total 8 ID piping surface area of 19,458 cm2 (1.9 m2) for the entire length of (IO) of 8 piping.
Total accessible surface area for the lo, 6 and 8 piping that constitutes EP 1.36 is 11.1 m2.
Survey Unit Measurement LocationsData 3.1 Pipe interior radiological survey forms are provided in Attachment 2 of this release record.
Survey Unit InvestigationdResults 4.1 None Data Assessment Results
FSS Design # EP 1.36 5.1 5.2 5.3 5.4 5.5 Revision # Original Page 3 of 4 Data assessment results are provided in the EP/Buried Pipe (BP) Survey Report provided in Attachment 1.
All measurement results are less than the Derived Concentration Guideline Level (DCGL) for radionuclide specific EP that corresponds to the 1 mredyr dose goal established in Table 3-3 of the FSSP.
When implementing the Unity Rule, provided in Section 3.6.3 of the FSSP, and applying the nuclide hctions, provided in TBD-06-004, the survey unit that is constituted by EP 1.36 passes FSS.
Background was not subtracted fiom the survey measurements and the Elevated Measurement Comparison (EMC) was not employed for this survey unit.
Statistical Parameter IO" Pipe Total Number of Survey 30 Number of Measurements >MDC 3
Measurements Statistical Summary Table 6 Pipe 8" Pipe 13 10 10 3
Number of Measurements Above 50% of DCGL 0
0 0
DCGL Mean I
0.029 Number of Measurements Above n
0 0
0.002 0.066 6.0 7.0 Median Standard Deviation Maximum Minimum 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 1.36 to be less than 1 mredyr. The dose contribution is estimated to be 0.029 mredyr based on the average of the a c i d gross counts measured.
Attachments - BSI EP/BP Survey Report -Pipe Interior Radiological Survey Form 0.022 0.002 0.0%
0.019 0.001 0.039 0.084 0.003 0.150 0.013 0.001 0.030
FSS Design # EP 1.36 Revision # Original Page 4 of 4
SECTION 7 ATTACHMENT 1 S PAGE(S)
I I
RP Engineer I Date BSI EPlBP SURVEY REPORT DJ'-
6 0 7 Maximum 0.084 I 0.003 1 0.150 I
L Minimum 0.013 1
0.w1 I 0.030 ROSENHAGEN Survey Technician(6) i hl..
ACTIVITY VALUES NOT BACKGROUND CORRECTED.
survey measurements on 6' pip? were conducted in Hole A (measurements I
& Z), Hole B (measurements 3-7) and Hole C (measurements 8-13). Aaess was denied to the remaining piping due to a pipe weld Obshcting the path of the survey skd. However. since activky levels both uptream and downstream of the ObStNdion were slgnificently less than the DCGL R can be concluded that the a d i W levels in the inawssible section of the embedded piping is a b signifcantly less than the DCGL. Therefore, it can be concluded that the dose to the public from the inamssible section of embedded I
EP 1.36 I O " Pipe TBD 06-004 Group 2 UnW -
0.040 0.022 0.020 0.018 0.024 0.023 0.020 0.029 0.019 0.019 0.018 0.020 0.026 0.022 0.029 0.027 0.024 0.018 0.016 0.013 0.016 0.017 0.022 0.018 0.024 0.048 0.045 0.084 0.079 0.072
~
~
~
~
~
~ __
~
~ __
~
~
~
~
~
~
~
~
~
~
~
~
~ __
~
~ -
~ -
I I
I 1
I Eu-I54 activity (dpm1100cmZ)
~
Eu-162 activity (dpmnoOcrn2) 76 43 38 34 47 44 39 56 36 37 34 38 49 42 55 52 45 34 31 25 31 33 42 35 45 92 87 161 151 137 NbW activity (dpd100crnZ) 54 30 27 24 33 31 28 40 26 26 24 27 35 30 39 37 32 24 22 18 22 23 30 25 32 66 62 114 108 97 4
3 2
2 3
3 2
3 2
2 2
2 3
2 3
3 3
2 2
2 2
2 2
2 3
5 I C 5
C e
Ap100m activity (dpm/lOOunZ) 265 15C 134 11E 16:
152 13E 19E 12i 13C 12c 13:
17; 14L 19; 18:
151 11t 1 O i 8:
10:
11:
14t 12r 1%
32; 56; 521 47:
301 1 of2
I t
c)
E E
e! %
EP 1.36 10" Pipe TBD 06404 Group 2 Cs-13J activity (dpmll OOcmZ)
Eu-162 adivlty (dpMOOcm2)
Eu-I54 activity
( d m 1 Wm2) 2 o f 2
EP 1.36 6" Pipe TBD 06-004 Group 2 MEAN MEDIAN STD DEV MAX MIN gcpm -
I S 2? I?
14 13 17 I S 5
14 11 e
I C e
0.00:
0.00:
0.00' 0.00:
0.00' ncpm -
I!
2:
1:
I d 1: li 11 I
11 1'
t I(
t l o f l
EP 1.36 8" Pipe TBD 06-004 Group 2 4
7 8
9 10 gcpm -
126t 91:
51 $
50t 40C 41c 53c WC 2024 1347 1of1
SECTION 7 ATTACaMENT 2 8' PAGE(S)
Pipe Interior Radiological Survey Form Date:
/ 2 0 r Time:
/,36(
C ~ G L
,q/o q~ b m d Pipe Diameter:
Building:
LO&
Elevation: -ZJ-Access Point Area:
7-Q W C M System:
Type of Survey Investigation Characterization other i/
Sled Size
/ Q inch
/ O H PipeID#
/. z ~
pem P Detector:
G 3 / b C a d Detector ID #:
LF? k - / / I Cal Date:
//-/ 7- 0 >p Cal Due Date:
//-/ 7-0 6 Instrument:
2 z ~ Z Y.- 1 Instrument ID #
2 0 3 Y P b p Cal Date:
f/ -/7 -0 >-
Cal Due Date:
//-/7-@ 6 From,the Daily Pipe Survey Detector Control Form for the Selected Detector Backgro~dValue '. L/qb cpm
MDCRBAi, 2 9. Y cpm
&Ic; my &&--.ItA' 0 7\\
Efficiency Factor for Pipe Diameter MDC8tatiC 13177 dpml100cm2 0 -'Do (taken from detector.
Is the MDCSktic acceptable? @ No (if no, adjust sample count time and recalculate M D a &
Comments:
bmz+
rcal/l p c w 4 m ~ i c c 3 : m w J ~ i
~
e*+&? re
_c__
Pipe Interior Radiological Survey Radiological Survey Commenced: Date: / 2-7-L7>-
Time:
3C7r REFERENCE COPY 0 Package Page 1 of -, Page 1
Pipe Interior Radiological Survey Form (Continuation Form) dpm/lOOcmz x
I I
I I
I I
I I
I I
Package Page -
2 of -, Page 2 REFERENCE Copy
l - - l REFERENCE COPY
Pipe Interior Radiological Survey Form Date:
. '/% *23'. 0s..
Time:
f / 3 0 Building:
.. e fibrz Elevation:'. '
z g Access Point Area: Lfl E
PipeID#
ff] 4 2 Pipe Diameter:
other J
sysiem:
M/#L.. E. sat, Type of Survey. Investigation U 5 -/ -I v7 SM Size Ir. I d '
Detector:
/M6/
Detector ID #:
Instrument:
p3CQ 1
Instrument ID #:
13373d r/
Characterization <
inal s w e u )
inch Cal Date:
C B W - e F Cal Due Date:
-,De - c Cal Date:
P - DG- -0s Cal Due Date:
~, a - b & ~ -
b Frctm-the-D'irily Pip~Smyey Detector Csntml Form for the Selected Defector Background Value 17-4 cpm MDC%tatiC
/ 7 - f CPm Comments:
psf.k;dd f.f 2- ;J-k=& /$
' /.3&
Efficiency Factor for Pipe Diameter MDCstatic 333 dpm/100cm2 0 - 0 0 7-
. (taken from detector Is the MDCstatic acceptable? a No (ifno, adjust sample count time and recalculate MDCQtiJ lLpl_J,T,'O1J L/r&@tl E ;'s 2 /. 3.4 I
3rI?;3 J
-16 mII_ L( &. & ~&
f-7.G
/ A + e T & U * - r / -. d
. ' Fa-Pipe Interior Radiological Survey Radiological Survey Commenced: Date: /i2 3F Time:
//?6
&..cd-o.*t~
c p
o+ ~ + ~, ; p ' i N '. c c [ ~ ~ L
L ; ~, ~ '
C T & h $
f i p p e i o q S c r P Package Page 1 of 2 REFERENCE COPY, Page 1
/< 3 6 A= c GAfliJ u*T,b J Pipe Interior Radiological SuNey Form (Continuation Form)
I I
I I
I I
\\
I
\\
Package Page 2 of, Page 2 REFERENCE COPY
I I
I REFERENCECOPY 0
Pipe Interior Radiological Survey Form Date:
/-/o e * &
Time:
d r/J-Building:
z T A Elevation:
z5-Access Point Area: -2 7 System: /A.J &L C D
&,;/
Pipe Diameter:
f r Pipem#
e 3'4 Sled Size V f inch Type of Survey Investigation Characterization -
Other J
Detector:
Z I k A D d /6 3 Detector ID #:
ZT5-&5ff-
/
P Cal Date:
/ P C d
- 4 5 Cal Due Date:
17 - P " q -0L Instrument:
J3;O 1
Instrument ID #:
2b3'1 w Cal Date:
/7 PDd -0 5 Cal Due Date:
/? - +b\\l -u c From the Daily Pipe Survey Detector Control Fom for the Selected Detector BackgroundValue 3bft 7 cpm Efficiency Factor for Pipe Diameter 0 0 03 (taken fiom detector m c s i a b c MDCbtlC b $ ?.
CPm
/6/ I 42 dpmfl OOcmz Is the MDCshbc acceptable? a No (Ifno, adjust sample count time and recalculate MDCR,,)
Comments:
/=7EflhJ LtffT,b + 3 w
PJ gq f
MSP /cG~mi.40) c7r Pipe Interior Radiological Survey I /
Radiological S w e y Commenced. Date: / -1"-
~3 6 Time:
b f/J' Package Page 1 of 1_
RECRRENCE COPY, Page 1
SECTION 7 ATTACHMENT 3
[
PAGE(S)
DQA Check Sheet Design #
Survey Unit #
EP 1.36 Revision #
Original EP 1.36 Answers to the following questions should be fully documented in the Survey Unit Release Record Have surveys been performed in accordance with survey instructions in the Survey Design?
I.
2.
Is the instrumentation MDC for structure static measurements below the DCGLw for Class 1 and 2 survey units, or below 0.5 DCGLw for Class 3 survey units?
3.
4.
Is the instrumentation MDC for embeddedburied piping static measurements below the DCGLw ?
embeddedlburied piping scan measurements below the DCGLw, or, if not. was the need for additional Was the instrumentation MDC for structure scan measurements, soil scan measurements, and static measurements or soil samdes addressed in the survev desian?
5.
Was the instrumentation MDC for volumetric measurements and smear analysis c 10% DCGLw ?
I I
I x
Yes No
~/~
X X
X 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 collect data proper for the types of radiation involved and for the media being surveyed?
5.
9.
Were "Special Methods" for data collection properly applied for the survey unit under review?
Is the data set comprised of qualified measurement results collected in accordance with the survey design, which accurately reflects the radiological status of the facility?
3. Have other graphical data tools been created to assist in analyzing the data?
I I
l x X
X X
Data Analysis
1.
Has a posting plot been created?
1. Are all samDle measurements below the DCGLW (Class 1 8 2). or 0.5 DCGLw (Class 3)?
1 x 1 I
X
2. Has a histogram (or other frequency plot) been created?
5. Is the result of the statistical test (S+ for Sign Test or W, for WRS Test) 5 the critical value?
I I
I x
X Comments :
2.' Is the mean of the sample data c DCGLw?
3.
4.
If elevated areas have been identied by scans andlor sampling, is the average activity in each elevated area c DCGLEMC (Class 1)..= DCGLW (Class 2). or <0.5 DCGLw (Class 3)?
Is the result of the Elevated Measurements Test c 1.O?
X X
X Form CS-09/2 Rev 0 FSSICharacterization Engineer (prinusign)
Page 1 of 1 WI Date Il-C-07
SECTION 7 ATTACHMENT 4 1 DISC

ML073450100

Text

Subject:

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