ML073170358: Difference between revisions
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{{#Wiki_filter:Description Survey Unit Release Record Design # Survey Unit | {{#Wiki_filter:Description Survey Unit Release Record Design # Survey Unit | ||
#(s) FSS/Characterktion Manager CS-0911 EP-1.64 1.64 1) Embedded Pipe (EP) Survey Unit 1.64 meets the def~tion of embedded pipe for Plum Brook Reactor Facility (PBRF). 2) EP 1.64 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 1.64 were performed using a scintillation detector optimized to measure gamma energies representative of Co-60. Sample #EP2-2 from Survey Request (SR)-13 was referenced for this decision. | #(s) FSS/Characterktion Manager CS-0911 EP-1.64 1.64 1) Embedded Pipe (EP) Survey Unit 1.64 meets the def~tion of embedded pipe for Plum Brook Reactor Facility (PBRF). 2) EP 1.64 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 1.64 were performed using a scintillation detector optimized to measure gamma energies representative of Co-60. Sample #EP2-2 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 (L4W) 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. | : 4) Survey Instructions for this survey unit are incorporated into and performed in accordance with (L4W) 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 BSIILVS-002, WEP 05-006, these determinations are appropriate for the types of radiation involved and the media being surveyed. | : 5) Instrument efficiency determinations are developed in accordance with the BSIILVS-002, WEP 05-006, these determinations are appropriate for the types of radiation involved and the media being surveyed. | ||
Revision # Original Page 1 of 3 1.1 The subject pipe system is the 4" header and risers for canal "K" -- 1.2 EP 1.64 consists of 4" diameter piping that is approximately 60 feet in length. 2.0 Survey Design Information FSS Design # EP 1.64 2.1 EP 1.64 was surveyed IAW Procedure | Revision # Original Page 1 of 3 1.1 The subject pipe system is the 4" header and risers for canal "K" -- 1.2 EP 1.64 consists of 4" diameter piping that is approximately 60 feet in length. 2.0 Survey Design Information FSS Design # EP 1.64 2.1 EP 1.64 was surveyed IAW Procedure | ||
#BSVLVS-002. | #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 60 survey measurements. | 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 60 survey measurements. | ||
Survey Unit: 1.64 Revision # Original 2.3 Surface area for the 4" ID piping is W3 cm2for each foot of piping, corresponding to a total 4" ID piping surface area of 58,373 cm2 (5.8 m2) for the entire length of (approximately 60') of 4" piping. Page 2 of 3 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 EPIBuried Pipe (BP) Survey Report provided in Attachment | Survey Unit: 1.64 Revision # Original 2.3 Surface area for the 4" ID piping is W3 cm2for each foot of piping, corresponding to a total 4" ID piping surface area of 58,373 cm2 (5.8 m2) for the entire length of (approximately 60') of 4" piping. Page 2 of 3 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 EPIBuried 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 mremlyr 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 1.64 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. 5.2 All measurement results are less than the Derived Concentration Guideline Level (DCGL) for radionuclide specific EP that corresponds to the 1 mremlyr 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 1.64 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. | ||
5.5 Statistical Summary Table - FSS Design # EP 1.64 I Revision # Original 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. | |||
Summary Table - FSS Design # EP 1.64 I Revision # Original 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. | |||
Page 3 of 3 6.1 A review of the survey results has shown that the dose contribution for EP 1.64 to be less than 1 mrendyr. The dose contribution is estimated to be 0.060 mredyr baed on the average of the actual gross counts measured. Survey Unit: | Page 3 of 3 6.1 A review of the survey results has shown that the dose contribution for EP 1.64 to be less than 1 mrendyr. The dose contribution is estimated to be 0.060 mredyr baed on the average of the actual gross counts measured. Survey Unit: | ||
1.64 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 1.64 & Spreadsheet SECTION 7 ATTACHMENT 1 4 PAGE(S) | 1.64 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 1.64 & Spreadsheet SECTION 7 ATTACHMENT 1 4 PAGE(S) | ||
BSI EPlBP SURVEY REPORT Sutvey Techdcian(s) | BSI EPlBP SURVEY REPORT Sutvey Techdcian(s) | ||
: 1. ACTWINVALUES NOT BACKGROUND CORRECTED RP Engines I Date EP 1.64 4" Pipe TBD 06-004 Group 2 EP 1.64 4" Pipe TBD 06-004 Group 2 EP 1.64 4" Pipe TBD 06-004 Group 2 - | : 1. ACTWINVALUES NOT BACKGROUND CORRECTED RP Engines I Date EP 1.64 4" Pipe TBD 06-004 Group 2 EP 1.64 4" Pipe TBD 06-004 Group 2 EP 1.64 4" Pipe TBD 06-004 Group 2 - | ||
* C E E g! a 0 B ncpm - gcpm Cc.40 activity fotaldpm) | * C E E g! a 0 B ncpm - gcpm Cc.40 activity fotaldpm) |
Revision as of 17:42, 12 July 2019
ML073170358 | |
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 1.64 | |
Download: ML073170358 (18) | |
Text
Description Survey Unit Release Record Design # Survey Unit
- (s) FSS/Characterktion Manager CS-0911 EP-1.64 1.64 1) Embedded Pipe (EP) Survey Unit 1.64 meets the def~tion of embedded pipe for Plum Brook Reactor Facility (PBRF). 2) EP 1.64 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 1.64 were performed using a scintillation detector optimized to measure gamma energies representative of Co-60. Sample #EP2-2 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 (L4W) 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 BSIILVS-002, WEP 05-006, these determinations are appropriate for the types of radiation involved and the media being surveyed.
Revision # Original Page 1 of 3 1.1 The subject pipe system is the 4" header and risers for canal "K" -- 1.2 EP 1.64 consists of 4" diameter piping that is approximately 60 feet in length. 2.0 Survey Design Information FSS Design # EP 1.64 2.1 EP 1.64 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 60 survey measurements.
Survey Unit: 1.64 Revision # Original 2.3 Surface area for the 4" ID piping is W3 cm2for each foot of piping, corresponding to a total 4" ID piping surface area of 58,373 cm2 (5.8 m2) for the entire length of (approximately 60') of 4" piping. Page 2 of 3 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 EPIBuried 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 mremlyr 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 1.64 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.
5.5 Statistical Summary Table - FSS Design # EP 1.64 I Revision # Original 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.
Page 3 of 3 6.1 A review of the survey results has shown that the dose contribution for EP 1.64 to be less than 1 mrendyr. The dose contribution is estimated to be 0.060 mredyr baed on the average of the actual gross counts measured. Survey Unit:
1.64 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 1.64 & Spreadsheet SECTION 7 ATTACHMENT 1 4 PAGE(S)
BSI EPlBP SURVEY REPORT Sutvey Techdcian(s)
- 1. ACTWINVALUES NOT BACKGROUND CORRECTED RP Engines I Date EP 1.64 4" Pipe TBD 06-004 Group 2 EP 1.64 4" Pipe TBD 06-004 Group 2 EP 1.64 4" Pipe TBD 06-004 Group 2 -
- C E E g! a 0 B ncpm - gcpm Cc.40 activity fotaldpm)
-~ -. -. . ! I I cod0 activity [dpm/100cm2)
.- -- . MEDIAN -- STD DEV -- , . -- ~ 0.039 0.055 --- MAX 0.275 MIN 0.010 - Eu-164 activity (dpn1100cmZ) - - CS-137 activity (dpndlM)cmZ)
Unity 0.080 EU-152 activity (dpmi100an2)
' I Nb44aetivity (dpnllOOan2)
Ag-108111 activity (dpm/IOOcmZ)
MEAN SECTION 7 ATTACHMENT 2 PAGE(S)
Pipe Interior Radiological Survey Form Date: /-/ (7 -0 6 Time: // 0s- Building:
EX Elevation Access Point - CfllVkK k System: /&u OUS.$J=~.
Pipe Diameter:
/*by Type of Survey Investigation r/ Sled Size Y I' &O&&ld Ginch Detector:
/Me/ Detector ID #: LVf-/ -Lo/ Cal Date:
/ 2-2 05- Cal Due Date: / L'L~ '0 6 Instrument:
z&)Xrl Instrument ID #: /3 q73 25 Cal Date:
/ z-26 -8c Cal Due Date: /.L-zL~-D b From the Daily Pipe Survey Detector Control Form for the Selected Detector Background Value 2 I CPm MDCRs~atio I q CPm Efficiency Factor for Pipe fi ,WO 47 (taken from detector calibration certificate)
E~$M%' 33 77 dPm/100cm2 IS the .MDCSOtic 4s NO (if no, adjust sample count time and recalculate MDCK,,) ~&~fie&b!e?
/~/7/~d S~ILCL? -/ns:f / / Su~u~tq mmum(~j7j - &G&d 47 & t9-F PPIPC~ M 5?/&Gy / a.ci'i Pipe Interior Radiological Survey Radiological Survey Commenced:
Date: /-/fl1-D6 Time: / /f?~- - Package Page 1 of 3 1 REFERENCE COPY 1 Attachment 3, Page 1 Pipe Interior Radiological Survey Form (Continuation Form) Package Page
&ofg REFERENCE COPY Attachment 3, Page 2 Pipe Interior Radiological Survey Form (Continuation Form) REFERENCE COPY Package Page 3 of 2 Attachment 3, Page 2
Pipe Interior Radiological Suwey Form Date: /-// -0 6 Time: *770 7 &*3niw-L Building:
Elevation
-2 5- Access Point fb& Ctdcx23 System: CW~ T*K &I- j?ipe Diameter:
Area: Pipe I, (OY Type of Survey Investigation Characterization - inal Surve # Other ,A Sled Size DOC, /a/ inch Detector:
_K/(ldJ !I%'&/ Detector ID #: LVd- 1 Cal Date:
/Z-ZO-O.T Cal Due Date: /L--tO-O 6 Instrument:
W 5-0 el Instrument ID #: /t3Y7Js Cal Date:
i A-LO "i a- Cal Due Date: /&to -06 From the Daily Pipe Survey Detector Control Form for the Selected Detector Background Value
'p 'ib- cpm MDCRtatic Efficiency Factor for Pipe 0.00047 (taken from detector calibration certificate)
!&fY?z~~ 3377 dpmll 00cm2 Is the MDCsati, No (if no, adjust sample count time and recalculate MDCKtsfic) cdffi%t)&kle?
did d ~ua\7v RUM 1-lo-a4 - SL/$~M ~'SJ 4 -' r d CWA L 5 &! ITC-g- PC%@- 4-b 774- I/S.F~*C F &,&<mj pmtL 7-1 0 W&-W 1/5 chm C ?- /zits (7~ Pipe Interior Radiological Suwey Radiological Survey Commenced:
Date: - 6 Time: 0? 0 7 Package Page 1 of I Attachment 3, Page 1
SECTION 7 ATTACHMENT 3 I PAGE(S)
Page 1 of 1 SECTION 7 ATTACHMENT 4 1 DISC