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{{#Wiki_filter:Description r Survey Unit Release Record Design # Survey Unit #(s) Work Execution Package (WEP) 05-006. Survey instructions descrikd in this document constitute "Specid Methods" and the survey design used in the acquisition of sumy measurements.
{{#Wiki_filter:r Survey Unit Release Record Design #               EP RX 206H          Revision #        Ori@          P a g e 1 of 3 Survey Unit #(s)         EP RX 206H
: 5) Instrument efficiency determinations are developed in accordance with the BSVtVS-002, WEP 05-006, these determinations are appropriate for the types of radiation involved and the media being surveyed.
: 1) Embedded P i p p)    Survey Unit EP RX 206H meets the definition of embedded pipe for Plum Brook Reactor Facility (PBRF).
FSS1Chamct~on Engineer EP RX 206H EP RX 206H 1) Embedded Pip p) Survey Unit EP RX 206H meets the definition of embedded pipe for Plum Brook Reactor Facility (PBRF). 2) EP RX 206K is a Class 1, Group 2 survey unit as per the PBRF Final Status Sunrey Plan (FSSP) and Technical Basis Document (TBD)-06-004.
: 2) EP RX 206K is a Class 1, Group 2 survey unit as per the PBRF Final Status Sunrey Plan (FSSP) and Technical Basis Document (TBD)-06-004.
: 3) Surveys in EP RX 206H were performed using a scintillation detector optimbed to measure gamma energies representative of Co-60. Sample #EP 2- 1 hm Survey Request @R)-13 was referend for this decision.
: 3) Surveys in EP RX 206H were performed using a scintillation detector optimbed to measure gamma energies representative of Co-60.
: 4) Survey Instructions for this survey unit are incorporated into and performed in accordance witb (JAW) the Babcock Services Lncorpotated (BSI)/LVS-002, Revision # Ori@ Page1 of 3 FSS Design # EP RX 20;~ Revision # Original Page 2 of 3 Survey Unit:
Sample #EP 2- 1 h m Survey Request @R)-13 was referend for this decision.
EP RX 206H EP RX 206H is a 2.5" instrument line in Quad B. EP RX 206H consists of 7' of instrument piping beginning in Quad B and terminating in a manifold access enclosure.
: 4) Survey Instructions for this survey unit are incorporated into and performed in accordance witb (JAW) the Babcock Services Lncorpotated (BSI)/LVS-002, Description Work Execution Package (WEP) 05-006. Survey instructions descrikd in this document constitute "Specid Methods" and the survey design used in the acquisition of sumy measurements.
The enclosure is above the access tunnel fiom Quad B to the reactor vessel.
5 ) Instrument efficiency determinations are developed in accordance with the BSVtVS-002, WEP 05-006, these determinations are appropriate for the types of radiation involved and the media being surveyed.
2.0 . Survey Design Information EP RX 206H was surveyed IAW Procedure
F S S 1 C h a m c t ~ o nEngineer
#BSI/LVS-002. 100% of the 2.5" ID pipe was accessible for survey. The accessible 2.5" ID pipe was surveyed by static measurement in one foot increments, for a total of 7 survey measurements. Surface area for the 2.5" ID piping is 608 cm2 for each foot of piping, corresponding to 4256 cm2 for the 7'of 2.5" piping. Total surface area for EP RX 206H is 4.26m2. 3.0 Survey Unit Measurement Locations/Data 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 Data assessment results are provided in the EP/Buried Pipe (BP) Survey Report provided in Attachment
 
: 1. 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, all measurement results are less than the DCGLw. The survey unit that is constituted by EP RX 206H passes FSS. 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 20;~            Revision # Original                    Page 2 of 3 Survey Unit: EP RX 206H EP RX 206H is a 2.5" instrument line in Quad B.
'V FSS Design # EP RX 206H Revision # Original Page 3 of 3 Survey Unit: EP RX 206H Statistical Summary Table Statistical Parameter Number of Measurements Above 50% of DCGL Standard Deviation 6.0 Documentation of evaluations pertaining to compliance with the unrestricted use limit of 25 mremlyr and dose contributions from Embedded Pipe and radionuclides contributing 10% in aggregate of the total dose for both structural scenarios and soils. A review of the survey results has shown that the dose contribution for EP RX 206H to be less than 1 rnrem/yr. The dose contribution is estimated to be 0,042 mredyr based on the average of the actual gross counts measured.
EP RX 206H consists of 7' of instrument piping beginning in Quad B and terminating in a manifold access enclosure. The enclosure is above the access tunnel fiom Quad B to the reactor vessel.
7.0 Attachments Attachment 1 - BSI EPIBP Survey Report Attachment 2 - Pipe Interior Radiological Survey Form Attachment 3 - DQA Worksheet Attachment 4 -Disc containing RR for EP RX 206H & Spreadsheet SECTION 7 ATTACHMENT 1 2 PAGES BSI EPlBP SURVEY REPORT LUES NOT BACKGROUND CORRECTED RP Engineer ] Date EP RX 206H 2.5" Pipe TBD 061004 Group 2 %kt c. E ! E CO-60 aetlvlty CM wtlvity CS-137 a~thrity ~u-152 adlvily i EW~S ec ; NW aetklty t gcPm ncpm (total dpm) (dprnll OOan2) Ag.1 oh aetlvlty fdpmll00em2) (dpmrt00M2) (d~~m2) (dpdlMcm2)
2.0 . Survey Design Information EP RX 206H was surveyed IAW Procedure #BSI/LVS-002.
Unity (dpmhWcm2) 0.086 I 1 P I 1' 40 -- .. -- %!-- . ?211212 19,936 .. 10,347 165 118 I ....... -, I0 - 578 -- - 25 18 I 87 1 o.di3 -SF:--' , --- , -.. 3 4 . . -. 4,984 . ... 47 29 ' 2 !-- -. -. 5 2li 78,788 12,959 8,725. 108 . ' --... 78 i .. . 6 - - - ........ 34,390 - -. 17,848 285 , '7. -- ---. ,, 203 . 7 _ 62 ._-_ _ _ -_ mi 187,879 30,901 16,038 -. 258 , - . - 182 . . , . , 16 1% ....... 145 376 . .- 997 ..... . 896 - I - , - ..? - 0.026 0.022 0.056 0.m 0.134 .........  
100% of the 2.5" ID pipe was accessible for survey. The accessible 2.5" ID pipe was surveyed by static measurement in one foot increments, for a total of 7 survey measurements.
.... , ! .... -. .- .... i ...... ....... - -- .- - -- .........  
Surface area for the 2.5" ID piping is 608 cm2for each foot of piping, corresponding to 4256 cm2for the 7'of 2.5" piping.
+ ... - ...........
Total surface area for EP RX 206H is 4.26m2.
I - ...... I ,- . -, - I -. MAX i 0.086- mi / 0.013 , MEAN ' 0.042 . . . . I .... - .. -. ..... MEDIAN : 0.026 -..... - - . STD Dl3 0.039 SECTION 7 ATTACHMENT 2 1 PAGE
3.0    Survey Unit Measurement Locations/Data Pipe interior radiological survey forms are provided in Attachment 2 of this release record.
_ BSVLVSPipeCrawler-002 Revision 5 Pipe Interior Radiological Survey Form Date: /D-I/- Time: /fm Pipe ID#: j$$m;k7 Pipe Diameter:
4.0    Survey Unit Investigations/Results 4.1    None 5.0  Data Assessment Results Data assessment results are provided in the EP/Buried Pipe (BP) Survey Report provided in Attachment 1.
2,d 3' Access Point Area: a v& 6 Building:
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, all measurement results are less than the DCGLw. The survey unit that is constituted by EP RX 206H passes FSS.
Elevation:
Background was not subtracted from the survey measurements and the Elevated Measurement Comparison (EMC) was not employed for this survey unit.
-25 System: Zlh5-f LaE Type of Survey Investigation Characterization Final Survey X other& Gross Co60 %. Cs Detector lD# I Sled ID# LVs 1 / b% 3& Detector Cal Date: 1- L \- 07 Detector Cal Due Date: 1 - 1 1 - 0 8 Instrument:
 
189 D& Instrument ID #: z=Q- I Instrument Cal Date:
                        'V FSS Design # EP RX 206H           Revision # Original                   Page 3 of 3 Survey Unit: EP RX 206H Statistical Summary Table Statistical Parameter Number of Measurements Above 50% of DCGL Standard Deviation 6.0   Documentation of evaluations pertaining to compliance with the unrestricted use limit of 25 mremlyr and dose contributions from Embedded Pipe and radionuclides contributing 10% in aggregate of the total dose for both structural scenarios and soils.
1-1 1- 07 Instrument Cal Due Date:  
A review of the survey results has shown that the dose contribution for EP RX 206H to be less than 1 rnrem/yr. The dose contribution is estimated to be 0,042 mredyr based on the average of the actual gross counts measured.
-) 1- 7 From the Daily Pipe Survey Detector Control Form for the Selected Detector Background Value cpm MDC%tattc  
7.0   Attachments Attachment 1 - BSI EPIBP Survey Report Attachment 2 - Pipe Interior Radiological Survey Form Attachment 3 - DQA Worksheet Attachment 4 -Disc containing RR for EP RX 206H & Spreadsheet
/b CPm Efficiency Factor for Pipe Diameter detector efficiency determination)
 
MDCstz+tr,t, ~/47~ Is the MDC,,,, acceptable?
SECTION 7 ATTACHMENT 1 2 PAGES
NO (if no, adjust sample count tlme and recalculate MDCK,) Comments:
 
2- 1 h?z? vvl~ ~~?TA?L(W~ Technician Signature Pipe Interior Radiological Survey Package Page 1 of 1 REFERENCE COPY Attachment 3, Page 1 SECTION 7 ATTACHMENT 3 1 PAGE 1 DQA Check Sheet 1 ~ulvey unit # I EP RX 206H I Design # 4. Was the instrumentation MDC for structure scan measurements, soil scan measurements, and embeddedlouned ol~ina scan measurements below tne DCGL* or. if not. was the need for additional 1 I IX EP RX206H Preliminary Data Review' ,. - static measurements or soil samples addressed in the survey design?
BSI EPlBP SURVEY REPORT LUES NOT BACKGROUND CORRECTED RP Engineer ] Date
Answers to the following questions should be fully documented in the Survey Unit Release Record 1. Have surveys been performed in accordance with survey instructions in the Survey Design? 2. Is the instrumentation MDC for structure static measurements below the DCGLw for Class 1 and 2 1 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 7 ~-~p 5. Was tne instrumentation MDC for volumetr~c measurements and smear analysis < 10% DCGLw  
 
? ... . . . 6 Were the MDCs and assumptions dsed to develop them appropriate for the instruments and techniques Revision # Original Yes X X .. ~ used to perform the survey?
EP RX 206H 2.5" Pipe TBD 061004 Group 2
: 7. Were the survey methods used to collect data proper for the types of radiation involved and for the media being surveyed?
  % k t c.
: 8. Were 'Special Methods" for data collection properly applied for the survey una under review? 9. Is the data set comprised of qualied measurement results collected in accordance with the survey design, which accurately reflects the radiological status of the facility?
E                                                                                                                     !
No A X X X 1. Has a posting plot been created?
t E                                 CO-60 aetlvlty       CM wtlvity                                                     i CS-137 a ~ t h r i t y ~u-152adlvily E W ~ S                 e c;           NW aetklty           Ag.1 o h aetlvlty Unity gcPm       ncpm           (total dpm)       (dprnllOOan2)
: 1. Are all sample measurements below the DCGLw (Class 1 & 2), or 0.5 DCGLw (Class 3)? 1x1 I N,A X Gra~hical Data Review X 2. Has a histogram (or other frequency plot) been created? 2. Is the mean of the sample data < DCGLw? 1x1 I X 3. If elevated areas have been identified by scans andlor sampling, is the average activity in each elevaled area < DCGk (Clasg 1). <DCGLH (Class 2). or_<_O5.DCGLw (Class 3)? - X .. 4. Is the result of the Elevated Measurements Test < 1.0? I I I X 3. Have other graphical data tools been created to assist in analyzing the data?
(dpmrt00M2) ( d ~ ~ m 2(dpdlMcm2)                 )                        (dpmhWcm2)             fdpmll00em2)
X Page 1 of I Data Analysis 5. Is the result of the statistical test (S+ for Sign Test or W, for WRS Test) ,the critical value? X Comments:
I                                                                         1 P                               I                                                                                                                                          I
--    1'
      . . --   40            %!-- . ?211212                   19,936               .. 10,347                   165                         118         ....... -, I-0                  578       0.086
                                                                                                        -- - -SF:--'25                           18                       I                   87 1 o.di3
                                                                              ---   , -..                                                                              .3. . . . . .       1% 0.026 4                                                                                                              47   !--                            '                 2                   145 0.022
                      ..                              ... -. 4,984                              .                                  -. -. 29                                          . . -
5       2li                         78,788               12,959- -                  8,725.                 108. --...
                                                                                                                          '                      78 i . .       .         6                   376        0.056 7
_62
_ _ mi 187,879 34,390 -
30,901
                                                                                -   . 17,848 16,038        -.
285---.
258 203 .
                                                                                                                                            - .- 182
                                                                                                                                                                        '7.
16 997
                                                                                                                                                                                            . 896 -
0.m 0.134
- ,             I            ..?      -                                                                         ,      ! ....                           .........
. .   .   .                                         ,                                       MEAN                  '  0.042
              .-                                             ......                         . . . . . . . . .+                        .... . .-.
MEDIAN          . . . .: .0.026
      -- .-                  -          --                        -.......                           ...-. . . . . . . . . . .                         -.....     - -. STD D l 3                      0.039
-......             -            I             ..                         I ..                                                   ,- .-,                               -.
MAX                   i 0.086-I I                                                                                                  mi                     / 0.013
 
SECTION 7 ATTACHMENT 2 1 PAGE
 
_        BSVLVSPipeCrawler-002 Revision 5 Pipe Interior Radiological Survey Form Date:      /D-I/-                 Time:      /fm Pipe ID#:
Building:
j$$m;k7             Pipe Diameter:
Elevation:
2,d3'
                                                      -25 Access Point Area:
System:
a     v&
Zlh5-f L a E 6
Type of Survey     Investigation         Characterization             Final Survey   X       other&
Gross                           Co60   %.                                 Cs Detector lD# I Sled ID#           LVs   1               /       b%     3&
Detector Cal Date:       1- L \- 0 7            Detector Cal Due Date: 1 1 1       - - 08 Instrument:           189 D&                     Instrument ID #:             z=Q-             I Instrument Cal Date:     1-1 1- 0 7            Instrument Cal Due Date:               -)   1-     7 From the Daily Pipe Survey Detector Control Form for the Selected Detector Background Value                 cpm MDC%tattc           /b           CPm Efficiency Factor for Pipe Diameter                                 detector efficiency determination)
MDCstz+tr,t,     ~ / 4 7 ~
Is the MDC,,,, acceptable?               NO       (if no, adjust sample count tlme and recalculate MDCK,)
Comments:           2- 1                   h?z?   v v l ~ ~ ~ ? T A ? L ( W ~
Technician Signature Pipe Interior Radiological Survey Package Page 1 of   1 REFERENCE COPY Attachment 3, Page 1
 
SECTION 7 ATTACHMENT 3 1 PAGE
 
1                                                           DQA Check Sheet I
Design #           EP RX206H            Revision #        Original 1  ~ulvey  unit #    I                                                        EP RX 206H Preliminary Data Review' Answers to the following questions should b e fully documented in the Survey Unit Release Record Yes  No  N,A
: 1. Have surveys been performed in accordance with survey instructions in the Survey Design?                          X
: 2. Is the instrumentation MDC for structure static measurements below the DCGLw for Class 1 and 2                                X 1   survey units, or below 0.5 DCGLw for Class 3 survey units?
: 3. Is the instrumentation MDC for embeddedlburied piping static measurements below the DCGLW7                        X
: 4. Was the instrumentation MDC for structure scan measurements, soil scan measurements, and embeddedlouned ol~ina, .  -  scan measurements below tne DCGL* or. if not. was the need for additional static measurements or soil samples addressed in the survey design?
1    I    I  X
~   -     ~   p
: 5. Was tne instrumentation MDC for volumetr~cmeasurements and smear analysis < 10% DCGLw ?
6 Were the MDCs and assumptions dsed to develop them appropriate   ..        for the instruments and techniques A
                                                                            ~
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 una under review?                       X
: 9. Is the data set comprised of qualied measurement results collected in accordance with the survey X
design, which accurately reflects the radiological status of the facility?
G r a ~ h i c aData l    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)?                             1 x 1      I
: 2. Is the mean of the sample data < DCGLw?                                                                        1 x 1     I
: 3. If elevated areas have been identifiedby scans andlor sampling, is the average activity in each                              X
          .. area < D C G k (Clasg 1). <DCGLH (Class 2). or_<_O5.DCGLw(Class 3)?
elevaled                                                                                              -
: 4. Is the result of the Elevated Measurements Test < 1.0?                                                          I    I    I  X
: 5. Is the result of the statistical test (S+ for Sign Test or W, for WRS Test) ,the      critical value?                       X Comments:
Page 1 of I
 
SECTION 7 ATTACHMENT 4 1 DISC}}
SECTION 7 ATTACHMENT 4 1 DISC}}

Latest revision as of 09:41, 13 March 2020

EP-Rx 206H, Nasa, Survey Unit Release Record
ML073110263
Person / Time
Site: Plum Brook
Issue date: 10/31/2007
From:
US National Aeronautics & Space Admin (NASA)
To:
NRC/RGN-III/DNMS/DB
References
EP-Rx 206H
Download: ML073110263 (11)


Text

r Survey Unit Release Record Design # EP RX 206H Revision # Ori@ P a g e 1 of 3 Survey Unit #(s) EP RX 206H

1) Embedded P i p p) Survey Unit EP RX 206H meets the definition of embedded pipe for Plum Brook Reactor Facility (PBRF).
2) EP RX 206K is a Class 1, Group 2 survey unit as per the PBRF Final Status Sunrey Plan (FSSP) and Technical Basis Document (TBD)-06-004.
3) Surveys in EP RX 206H were performed using a scintillation detector optimbed to measure gamma energies representative of Co-60.

Sample #EP 2- 1 h m Survey Request @R)-13 was referend for this decision.

4) Survey Instructions for this survey unit are incorporated into and performed in accordance witb (JAW) the Babcock Services Lncorpotated (BSI)/LVS-002, Description Work Execution Package (WEP)05-006. Survey instructions descrikd in this document constitute "Specid Methods" and the survey design used in the acquisition of sumy measurements.

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

F S S 1 C h a m c t ~ o nEngineer

FSS Design # EP RX 20;~ Revision # Original Page 2 of 3 Survey Unit: EP RX 206H EP RX 206H is a 2.5" instrument line in Quad B.

EP RX 206H consists of 7' of instrument piping beginning in Quad B and terminating in a manifold access enclosure. The enclosure is above the access tunnel fiom Quad B to the reactor vessel.

2.0 . Survey Design Information EP RX 206H was surveyed IAW Procedure #BSI/LVS-002.

100% of the 2.5" ID pipe was accessible for survey. The accessible 2.5" ID pipe was surveyed by static measurement in one foot increments, for a total of 7 survey measurements.

Surface area for the 2.5" ID piping is 608 cm2for each foot of piping, corresponding to 4256 cm2for the 7'of 2.5" piping.

Total surface area for EP RX 206H is 4.26m2.

3.0 Survey Unit Measurement Locations/Data 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 Data assessment results are provided in the EP/Buried Pipe (BP) Survey Report provided in Attachment 1.

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, all measurement results are less than the DCGLw. The survey unit that is constituted by EP RX 206H passes FSS.

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

'V FSS Design # EP RX 206H Revision # Original Page 3 of 3 Survey Unit: EP RX 206H Statistical Summary Table Statistical Parameter Number of Measurements Above 50% of DCGL Standard Deviation 6.0 Documentation of evaluations pertaining to compliance with the unrestricted use limit of 25 mremlyr and dose contributions from Embedded Pipe and radionuclides contributing 10% in aggregate of the total dose for both structural scenarios and soils.

A review of the survey results has shown that the dose contribution for EP RX 206H to be less than 1 rnrem/yr. 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 EPIBP Survey Report Attachment 2 - Pipe Interior Radiological Survey Form Attachment 3 - DQA Worksheet Attachment 4 -Disc containing RR for EP RX 206H & Spreadsheet

SECTION 7 ATTACHMENT 1 2 PAGES

BSI EPlBP SURVEY REPORT LUES NOT BACKGROUND CORRECTED RP Engineer ] Date

EP RX 206H 2.5" Pipe TBD 061004 Group 2

% k t c.

E  !

t E CO-60 aetlvlty CM wtlvity i CS-137 a ~ t h r i t y ~u-152adlvily E W ~ S e c; NW aetklty Ag.1 o h aetlvlty Unity gcPm ncpm (total dpm) (dprnllOOan2)

(dpmrt00M2) ( d ~ ~ m 2(dpdlMcm2) ) (dpmhWcm2) fdpmll00em2)

I 1 P I I

-- 1'

. . -- 40  %!-- . ?211212 19,936 .. 10,347 165 118 ....... -, I-0 578 0.086

-- - -SF:--'25 18 I 87 1 o.di3

--- , -.. .3. . . . . . 1% 0.026 4 47  !-- ' 2 145 0.022

.. ... -. 4,984 . -. -. 29 . . -

5 2li 78,788 12,959- - 8,725. 108. --...

' 78 i . . . 6 376 0.056 7

_62

_ _ mi 187,879 34,390 -

30,901

- . 17,848 16,038 -.

285---.

258 203 .

- .- 182

'7.

16 997

. 896 -

0.m 0.134

- , I ..? - ,  ! .... .........

i . . . . , MEAN ' 0.042

.- ...... . . . . . . . . .+ .... - . .-.

MEDIAN . . . .: .0.026

-- .- - -- -....... ...-. . . . . . . . . . . -..... - -. STD D l 3 0.039

-...... - I .. I .. ,- .-, -.

MAX i 0.086-I I mi / 0.013

SECTION 7 ATTACHMENT 2 1 PAGE

_ BSVLVSPipeCrawler-002 Revision 5 Pipe Interior Radiological Survey Form Date: /D-I/- Time: /fm Pipe ID#:

Building:

j$$m;k7 Pipe Diameter:

Elevation:

2,d3'

-25 Access Point Area:

System:

a v&

Zlh5-f L a E 6

Type of Survey Investigation Characterization Final Survey X other&

Gross Co60  %. Cs Detector lD# I Sled ID# LVs 1 / b% 3&

Detector Cal Date: 1- L \- 0 7 Detector Cal Due Date: 1 1 1 - - 08 Instrument: 189 D& Instrument ID #: z=Q- I Instrument Cal Date: 1-1 1- 0 7 Instrument Cal Due Date: -) 1- 7 From the Daily Pipe Survey Detector Control Form for the Selected Detector Background Value cpm MDC%tattc /b CPm Efficiency Factor for Pipe Diameter detector efficiency determination)

MDCstz+tr,t, ~ / 4 7 ~

Is the MDC,,,, acceptable? NO (if no, adjust sample count tlme and recalculate MDCK,)

Comments: 2- 1 h?z? v v l ~ ~ ~ ? T A ? L ( W ~

Technician Signature Pipe Interior Radiological Survey Package Page 1 of 1 REFERENCE COPY Attachment 3, Page 1

SECTION 7 ATTACHMENT 3 1 PAGE

1 DQA Check Sheet I

Design # EP RX206H Revision # Original 1 ~ulvey unit # I EP RX 206H Preliminary Data Review' Answers to the following questions should b e fully documented in the Survey Unit Release Record Yes No N,A

1. Have surveys been performed in accordance with survey instructions in the Survey Design? X
2. Is the instrumentation MDC for structure static measurements below the DCGLw for Class 1 and 2 X 1 survey units, or below 0.5 DCGLw for Class 3 survey units?
3. Is the instrumentation MDC for embeddedlburied piping static measurements below the DCGLW7 X
4. Was the instrumentation MDC for structure scan measurements, soil scan measurements, and embeddedlouned ol~ina, . - scan measurements below tne DCGL* or. if not. was the need for additional static measurements or soil samples addressed in the survey design?

1 I I X

~ - ~ p

5. Was tne instrumentation MDC for volumetr~cmeasurements and smear analysis < 10% DCGLw ?

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

~

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 una under review? X
9. Is the data set comprised of qualied measurement results collected in accordance with the survey X

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

G r a ~ h i c aData l 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)? 1 x 1 I
2. Is the mean of the sample data < DCGLw? 1 x 1 I
3. If elevated areas have been identifiedby scans andlor sampling, is the average activity in each X

.. area < D C G k (Clasg 1). <DCGLH (Class 2). or_<_O5.DCGLw(Class 3)?

elevaled -

4. Is the result of the Elevated Measurements Test < 1.0? I I I X
5. Is the result of the statistical test (S+ for Sign Test or W, for WRS Test) ,the critical value? X Comments:

Page 1 of I

SECTION 7 ATTACHMENT 4 1 DISC