ML073330652: Difference between revisions

From kanterella
Jump to navigation Jump to search
(Created page by program invented by StriderTol)
 
(StriderTol Bot change)
 
(2 intermediate revisions by the same user not shown)
Line 16: Line 16:


=Text=
=Text=
{{#Wiki_filter:I Survey Unit Release Record I Survey Unit #(s) Desigrl# Description CRT-3 1) Embedded Pipe (EP) Survey Unit CRT-3 meets the definition of embedded pipe fbr Plum Brook Reactor Facility (PBRIF). EP-CRT-3 2) EP CRT-3 is a Class 1, Group 1 survey unit as per the PBRF Final Status Survey Plan (FSSP) and Technical Basis Docurnent (TBD)-06-004.  
{{#Wiki_filter:I                             Survey Unit Release Record                                         I Desigrl#        EP-CRT-3            Revision #        Original      Page 1 of 3 Survey Unit #(s)                                     CRT-3
: 3) Surveys in EP CRT-3 were performed using a scintillation detector optimized to measure gamma ener3ies representative of Co-60. Samplc #EP 3- 9 faom Swvey Request (SR)-13 was referenced for this decision.
: 1) Embedded Pipe (EP) Survey Unit CRT-3 meets the definition of embedded pipe fbr Plum Brook Reactor Facility (PBRIF).
Revision # 4) Survey Instructions for this survey unit are incorporated into and performed in accordance with (1AW j the Babcock Services incorporated (BSi)lLVS-002, Work Execution Package (WEP) 05-006. Survey instructions described in this document constitute "Special Methods" and the survey design used in the acqrri sit ion of survey measurements.  
: 2) EP CRT-3 is a Class 1, Group 1 survey unit as per the PBRF Final Status Survey Plan (FSSP) and Technical Basis Docurnent (TBD)-06-004.
: 5) Tnstrvment eficiet~cy determinations are developed in accordance with etre BSIlLVS-002, WEP 05-006, these determinations are appropriate for the types of radiation involved and the media being surveyed.
: 3) Surveys in EP CRT-3 were performed using a scintillation detector optimized to measure gamma ener3ies representative of Co-60. Samplc #EP 3-9 faom Swvey Request (SR)-13 was referenced for this decision.
Original - Page 1 of 3 --
: 4) Survey Instructions for this survey unit are incorporated into and performed in accordance with (1AW j the Babcock Services incorporated (BSi)lLVS-002, Work Execution Package (WEP) 05-006. Survey instructions described in this Description document constitute "Special Methods" and the survey design used in the acqrrisit ion of survey measurements.
FSS Design # El? CRT-3 Revision # Original Page 2 of 3 Survey Unit: CRT-3 1.1 The subject pipe system is a 2.5" diameter penetration located on the CRT plate witilin the Sub Pile Room.
: 5) Tnstrvment eficiet~cydeterminations are developed in accordance with etre BSIlLVS-002, WEP 05-006, these determinations are appropriate for the types of radiation involved and the media being surveyed.
The system access point is located on the -34' el. of the Rx building.
2.2 EP CRT-3 consists of2.5" diameter piping that is approximately 3 feet in length. Survey Design Information 2.1 EP CRT-3 was surveyed IAW Procedure
#BSI/LVS-002.
2.2 100% of the piping was accessible for survey. The accessible pipe was surveyed by static measurement at one foot increments, for a total of 3 survey measurements.
2.3 The tot4 surface area for the piping system is approximately 1,824 cm2 (0.2 m" for the entire length of (3') of piping. Survey Unit Measurement Locations/Data 3.1 Pipe interior radiological survey forms are provided in Attachment 2 of this release record. Survey Unit Tnvestigations/Results 4.1 None Data Assessment Results 5.1 Data assessment results are provided in the EP/Buried Pipe (BP) Survey Report provided in Attachment
: 1. 5.2 All measurement results are less than the Derived Concentration Guideline Level (DCGL) for radionuclide specific EP that corresponds to the 1 mrem/yr dose goal established in Table 3-3 of the FSSP. 5.3 When implementing the Unity Rule, provided in Section 3.6.3 of the FSSP, and applying the Nuclide Fraction (NF), provided in TBD-06-004, the survey unit that is constituted by EP CRT-3 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.
I FSS Design # EP CRT-3 I Revision # Original I Page 3 of3 1 Sunrey Unit: CRT-3 5.5 Statistical Summary Table Minimum 0.0030 6.0 Documentation of evaluations pertaining to compliance with the unrestricted use limit of 25 mrem/yr 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 CRT-3 to be less than 1 mrem/yr. The dose contribution is estimated to be 0.063 mrem/yr based on the average of the actual gross counts measured.  


===7.0 Attachments===
FSS Design # El? CRT-3              Revision # Original                  Page 2 of 3 Survey Unit: CRT-3 1.1    The subject pipe system is a 2.5" diameter penetration located on the CRT plate witilin the Sub Pile Room. The system access point is located on the
              -34' el. of the Rx building.
2.2    EP CRT-3 consists of2.5" diameter piping that is approximately 3 feet in length.
Survey Design Information 2.1    EP CRT-3was surveyed IAW Procedure #BSI/LVS-002.
2.2    100% of the piping was accessible for survey. The accessible pipe was surveyed by static measurement at one foot increments, for a total of 3 survey measurements.
2.3    The tot4 surface area for the piping system is approximately 1,824 cm2 (0.2 m" for the entire length of (3') of piping.
Survey Unit Measurement Locations/Data 3.1    Pipe interior radiological survey forms are provided in Attachment 2 of this release record.
Survey Unit Tnvestigations/Results 4.1    None Data Assessment Results 5.1    Data assessment results are provided in the EP/Buried Pipe (BP) Survey Report provided in Attachment 1.
5.2    All measurement results are less than the Derived Concentration Guideline Level (DCGL) for radionuclide specific EP that corresponds to the 1 mrem/yr dose goal established in Table 3-3 of the FSSP.
5.3    When implementing the Unity Rule, provided in Section 3.6.3 of the FSSP, and applying the Nuclide Fraction (NF), provided in TBD-06-004, the survey unit that is constituted by EP CRT-3 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.


Attachment 1 - BSI EPiBP Survey Report Attachment 2 - Pipe Interior Radiological Survey Form Attachment 3 - DQA Worksheet Attachment 4 -Disc containing RR for EP CRT-3 & Spreadsheet SECTION 7 ATTACHMENT 1 .z PAGE@)
I FSS Design # EP CRT-3             I Revision # Original            I     Page 3 of3      1 Sunrey Unit: CRT-3 5.5    Statistical Summary Table Minimum                          0.0030 6.0   Documentation of evaluations pertaining to compliance with the unrestricted use limit of 25 mrem/yr and dose contributions fiom Embedded Pipe and radionuclides contributing 10% in aggregate of the total dose for both structural scenarios and soils.
BSI EPIBP SURVEY REPORT 1 MG1 LVS-11 no ?BDO&OW~Group SR-13 Radtucb Oistribuliwl Sample -Ma Area F-MC kd P&ai FSS MREMNR 7 EP 3-9 ha No Pass <I COWENTS: ACTMTY VALES NOT BACKGROUND CORRECTED RPEngiilLW
6.1      A review of the survey results has shown that the dose contribution for EP CRT-3 to be less than 1 mrem/yr. The dose contribution is estimated to be 0.063 mrem/yr based on the average of the actual gross counts measured.
&-It 4.7 EP CRTS 2.5" Pipe TBD 06404 Group 1
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 CRT-3 & Spreadsheet
* I M actmy Go# aWty Cs-I37 actmy EU-482 Wlty Eu-1W dvlty NbM adldty Ag-la%m mvlQ 2 ' 7 ' 1 3,030 4 08 20 473 128 15 3. 6.003 3 81 81 184,848 30,400 1.245 28,838 7,866 887 212 0.181 ----------
v- 0.003 MEDIAN 0.m I + STD OEV 0.102 MAX 0.Z 81 1 1 LAIN 0.003 SECTION 7 ATTACHMENT 2 
-+ BSh'LVSPip eCrawler-002 Revision 5 Pipe Interior Radiological Survey Form Date: 10-3,C.l-Q7 Time: \b3S PipeID#: WT -3 Pipe Diameter:
3 . 5' ' Access Point Area: %\o $ R? Building:
Ld Elevation:
r I - System: *+A 0 0 Type of Survey Investigation Characterization FinalSwey
%, Other J Gross C060 o.tector ID# 1 ~1.a LD- 1 9 aw s - \ i J . S~J Detector Cal Date; \ -I\- 07 Detector Cal Due Date: \--I\ -06 Instrument:
2.32350- 1 Instrument JD #: \ 24 oVL\ - hstmnent Cal Date: \- \\ -07, Instrument Cal Due Date: \ -0 $ From the Daily Pipe Survey Detector Control Form for the Selected Detector ~ackpmd~alue 39 cpm MDrnmtic 10 =Pm Eficiency Factor for Pipe Diametcr 0. 0 00 33 (from detector efficiency determination)
MDG~~~, C 3427 dp,d r OD ,,2 Is the MDCStatic acceptable?
& No (if no, adjust sample count time and recalculate MD-) Cornla: Po S+ hldb
* Technician Signature Pipe Interior Radiological Survey REFERENCE COPY 0 Z Package Page 1 of - Attachmmt 3, Page 1 


SECTION 7 ATTACHMENT 3 ! PAGE(S)
SECTION 7 ATTACHMENT 1
DQACk~kSheet Design # EP CRT-3 Revision # Survey Unit # EP-CRT-3 Preliminary Data Review' Answers to the following questions shoukd be firliy documenw in the Survey Unl Yes No NIA Release Record I. Have surveys been performed in accordance with survey instructiorrs in the Survey Design? X 2. Is the instrumentation MOC for struhre static measurements Mowthe DCGh for Class t and 2 survey units, or Mow 0.5 DCGh Ibr Class 3 survey unL? X 3. Is the insbumentation MDC for embgddedlbulied piping static measurements below the DCGh 7 X 4. Was the instrumentation MDc for skucture mn measurements, soit scan measuremerrts, and ernbeddedlburied piplng scan rneasuremgnts below the DCGLw, or, if not, was the nd for Plcldinal X Wc measurements w soil samples addressed in the survey design? 5. Was the instrumentation MDC for volumetric measurements and smear analysis < 10% DC- 7 X 6. W~theMDCsandassumptlonsusedtodevelopthmapproptiateTortheinsttummtsandtechniques used to perfwm the survey? 7. Wsre the suwey methads used to mifeet data proper for the types of radiatbn invalved and for the media being suweyd? X 8. Were 'Special Methodsm for data collection properly applied for the survey unit under review? X 9. Is the data sd comprised of qualified messment resu Its collected in accordance wfth the survey deslgn, whii accurately rdeets the radiological status of the faellky7 x 2. Has a histogram (or other frequency plot) been mated? CS49f2 Page 1 of 1 SECTION 7 ATTACHMENT 4 1 DISC}}
  .z PAGE@)
 
BSI EPIBP SURVEY REPORT 1MG1 LVS-11 no
                  ?BDO&OW~Group                              7 SR-13 R a d t u c b Oistribuliwl Sample      EP 3-9
                      - M a                                ha Area F-MC          k d                  No P&ai      FSS                      Pass MREMNR                                  <I COWENTS:
ACTMTY VALES NOT BACKGROUND CORRECTED RPEngiilLW
                                                      &-It 4 . 7
 
EP CRTS 2.5" Pipe TBD 06404 Group 1 Mactmy I Go# a W t y    Cs-I37 actmy    EU-482W l t y Eu-1W d v l t y N b M adldty  Ag-la%m mvlQ 2      7 '
1    3,030          4 08              20            473            128            15            3 . 6.003 3    81  81  184,848      30,400            1.245        28,838        7,866            887          212  0.181 v-              0.003 MEDIAN          0.m I                                            +              STD MAX OEV 0.102 0.Z 81 1                                                  1                                            LAIN            0.003
 
SECTION 7 ATTACHMENT 2
 
                                                                                    -+    BSh'LVSPip eCrawler-002 Revision 5 Pipe Interior Radiological Survey Form Date:    10-3,C.l-Q7              Time:        \b3S PipeID#:
Building:
W T -3 Ld Pipe Diameter:
Elevation:      -3  . 5'r    '        Access Point Area:
System:
                                                                                                    %\o $
                                                                                                        *+A R?I 00 Type of Survey    Investigation          Characterization              FinalSwey        %,      Other    J Gross o.tectorID#1 ~1.a LD-Detector Cal Date; C060 19
                            \ -I\- 07 a ws-\                  i J S ~  .
Detector Cal Due Date:
J
                                                                                          \--I\ -06 Instrument:            2.32350- 1                  Instrument JD #:                  \ 24 oVL\                -
hstmnent Cal Date:          \ - \ \ -07,          Instrument Cal Due Date:                \        -0 $
From the Daily Pipe Survey Detector Control Form for the Selected Detector
~ a c k p m d ~ a l u e39        cpm MDrnmtic              10        =Pm Eficiency Factor for Pipe Diametcr      0.00033              (from detector efficiency determination)
MDG~~~,        C3427              dp,d        r O D 2, Is the MDCStaticacceptable?      &          No        (if no, adjust sample count time and recalculate MD-)
Cornla:        P o S+  hldb
* Technician Signature Pipe Interior Radiological Survey Package Page 1 of -  Z 0 REFERENCE COPY Attachmmt 3, Page 1
 
SECTION 7 ATTACHMENT 3
  ! PAGE(S)
 
DQACk~kSheet Design #           EP CRT-3         Revision #
Survey Unit #                                                         EP-CRT-3 Preliminary Data Review' Answers to the following questions shoukd be firliy documenw in the Survey Unl Release Record                                              Yes No NIA I. Have surveys been performed in accordance with survey instructiorrs in the Survey Design?             X
: 2. Is the instrumentation MOC for struhre static measurements Mowthe D C G h for Class t and 2 X
survey units, or Mow 0.5D C G h Ibr Class 3 survey unL?
: 3. Isthe insbumentation MDC for embgddedlbulied piping static measurements below the DCGh 7               X
: 4. Was the instrumentation MDc for skucture m n measurements, soit scan measuremerrts, and ernbeddedlburied piplng scan rneasuremgnts below the DCGLw, or, if not, was the n d for Plcldinal             X W c measurements w soil samples addressed in the survey design?
: 5. Was the instrumentation MDC for volumetric measurements and smear analysis < 10% DC-               7           X
: 6. W~theMDCsandassumptlonsusedtodevelopthmapproptiateTortheinsttummtsandtechniques used to perfwm the survey?
: 7. Wsre the suwey methads used to mifeet data proper for the types of radiatbn invalved and for the X
media being suweyd?
: 8. Were 'Special Methodsmfor data collection properly applied for the survey unit under review?           X
: 9. Is the data sd comprised of qualified m e s s m e n t resuIts collected in accordance wfth the survey deslgn, w h i i accurately rdeets the radiological status of the faellky7                             x
: 2. Has a histogram (or other frequency plot) been mated?
CS49f2 Page 1 of 1
 
SECTION 7 ATTACHMENT 4 1 DISC}}

Latest revision as of 07:53, 13 March 2020

EP-CRT-3, Nasa, Survey Unit Release Record
ML073330652
Person / Time
Site: Plum Brook
Issue date: 11/15/2007
From:
US National Aeronautics & Space Admin (NASA)
To:
NRC/RGN-III/DNMS/DB
References
EP-CRT-3
Download: ML073330652 (12)


Text

I Survey Unit Release Record I Desigrl# EP-CRT-3 Revision # Original Page 1 of 3 Survey Unit #(s) CRT-3

1) Embedded Pipe (EP) Survey Unit CRT-3 meets the definition of embedded pipe fbr Plum Brook Reactor Facility (PBRIF).
2) EP CRT-3 is a Class 1, Group 1 survey unit as per the PBRF Final Status Survey Plan (FSSP) and Technical Basis Docurnent (TBD)-06-004.
3) Surveys in EP CRT-3 were performed using a scintillation detector optimized to measure gamma ener3ies representative of Co-60. Samplc #EP 3-9 faom Swvey Request (SR)-13 was referenced for this decision.
4) Survey Instructions for this survey unit are incorporated into and performed in accordance with (1AW j the Babcock Services incorporated (BSi)lLVS-002, Work Execution Package (WEP)05-006. Survey instructions described in this Description document constitute "Special Methods" and the survey design used in the acqrrisit ion of survey measurements.
5) Tnstrvment eficiet~cydeterminations are developed in accordance with etre BSIlLVS-002, WEP 05-006, these determinations are appropriate for the types of radiation involved and the media being surveyed.

FSS Design # El? CRT-3 Revision # Original Page 2 of 3 Survey Unit: CRT-3 1.1 The subject pipe system is a 2.5" diameter penetration located on the CRT plate witilin the Sub Pile Room. The system access point is located on the

-34' el. of the Rx building.

2.2 EP CRT-3 consists of2.5" diameter piping that is approximately 3 feet in length.

Survey Design Information 2.1 EP CRT-3was surveyed IAW Procedure #BSI/LVS-002.

2.2 100% of the piping was accessible for survey. The accessible pipe was surveyed by static measurement at one foot increments, for a total of 3 survey measurements.

2.3 The tot4 surface area for the piping system is approximately 1,824 cm2 (0.2 m" for the entire length of (3') of piping.

Survey Unit Measurement Locations/Data 3.1 Pipe interior radiological survey forms are provided in Attachment 2 of this release record.

Survey Unit Tnvestigations/Results 4.1 None Data Assessment Results 5.1 Data assessment results are provided in the EP/Buried Pipe (BP) Survey Report provided in Attachment 1.

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

5.3 When implementing the Unity Rule, provided in Section 3.6.3 of the FSSP, and applying the Nuclide Fraction (NF), provided in TBD-06-004, the survey unit that is constituted by EP CRT-3 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.

I FSS Design # EP CRT-3 I Revision # Original I Page 3 of3 1 Sunrey Unit: CRT-3 5.5 Statistical Summary Table Minimum 0.0030 6.0 Documentation of evaluations pertaining to compliance with the unrestricted use limit of 25 mrem/yr 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 CRT-3 to be less than 1 mrem/yr. The dose contribution is estimated to be 0.063 mrem/yr 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 CRT-3 & Spreadsheet

SECTION 7 ATTACHMENT 1

.z PAGE@)

BSI EPIBP SURVEY REPORT 1MG1 LVS-11 no

?BDO&OW~Group 7 SR-13 R a d t u c b Oistribuliwl Sample EP 3-9

- M a ha Area F-MC k d No P&ai FSS Pass MREMNR <I COWENTS:

ACTMTY VALES NOT BACKGROUND CORRECTED RPEngiilLW

&-It 4 . 7

EP CRTS 2.5" Pipe TBD 06404 Group 1 Mactmy I Go# a W t y Cs-I37 actmy EU-482W l t y Eu-1W d v l t y N b M adldty Ag-la%m mvlQ 2 7 '

1 3,030 4 08 20 473 128 15 3 . 6.003 3 81 81 184,848 30,400 1.245 28,838 7,866 887 212 0.181 v- 0.003 MEDIAN 0.m I + STD MAX OEV 0.102 0.Z 81 1 1 LAIN 0.003

SECTION 7 ATTACHMENT 2

-+ BSh'LVSPip eCrawler-002 Revision 5 Pipe Interior Radiological Survey Form Date: 10-3,C.l-Q7 Time: \b3S PipeID#:

Building:

W T -3 Ld Pipe Diameter:

Elevation: -3 . 5'r ' Access Point Area:

System:

%\o $

  • +A R?I 00 Type of Survey Investigation Characterization FinalSwey  %, Other J Gross o.tectorID#1 ~1.a LD-Detector Cal Date; C060 19

\ -I\- 07 a ws-\ i J S ~ .

Detector Cal Due Date:

J

\--I\ -06 Instrument: 2.32350- 1 Instrument JD #: \ 24 oVL\ -

hstmnent Cal Date: \ - \ \ -07, Instrument Cal Due Date: \ -0 $

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

~ a c k p m d ~ a l u e39 cpm MDrnmtic 10 =Pm Eficiency Factor for Pipe Diametcr 0.00033 (from detector efficiency determination)

MDG~~~, C3427 dp,d r O D 2, Is the MDCStaticacceptable? & No (if no, adjust sample count time and recalculate MD-)

Cornla: P o S+ hldb

  • Technician Signature Pipe Interior Radiological Survey Package Page 1 of - Z 0 REFERENCE COPY Attachmmt 3, Page 1

SECTION 7 ATTACHMENT 3

! PAGE(S)

DQACk~kSheet Design # EP CRT-3 Revision #

Survey Unit # EP-CRT-3 Preliminary Data Review' Answers to the following questions shoukd be firliy documenw in the Survey Unl Release Record Yes No NIA I. Have surveys been performed in accordance with survey instructiorrs in the Survey Design? X

2. Is the instrumentation MOC for struhre static measurements Mowthe D C G h for Class t and 2 X

survey units, or Mow 0.5D C G h Ibr Class 3 survey unL?

3. Isthe insbumentation MDC for embgddedlbulied piping static measurements below the DCGh 7 X
4. Was the instrumentation MDc for skucture m n measurements, soit scan measuremerrts, and ernbeddedlburied piplng scan rneasuremgnts below the DCGLw, or, if not, was the n d for Plcldinal X W c measurements w soil samples addressed in the survey design?
5. Was the instrumentation MDC for volumetric measurements and smear analysis < 10% DC- 7 X
6. W~theMDCsandassumptlonsusedtodevelopthmapproptiateTortheinsttummtsandtechniques used to perfwm the survey?
7. Wsre the suwey methads used to mifeet data proper for the types of radiatbn invalved and for the X

media being suweyd?

8. Were 'Special Methodsmfor data collection properly applied for the survey unit under review? X
9. Is the data sd comprised of qualified m e s s m e n t resuIts collected in accordance wfth the survey deslgn, w h i i accurately rdeets the radiological status of the faellky7 x
2. Has a histogram (or other frequency plot) been mated?

CS49f2 Page 1 of 1

SECTION 7 ATTACHMENT 4 1 DISC