ML073111399
| ML073111399 | |
| Person / Time | |
|---|---|
| Site: | Plum Brook |
| Issue date: | 11/05/2007 |
| From: | US National Aeronautics & Space Admin (NASA) |
| To: | NRC/RGN-III/DNMS/DB |
| References | |
| EP-1.62 | |
| Download: ML073111399 (17) | |
Text
Survey Unit Release Record Design # Survey Unit #(s) Description Approval Signatures FSSICharacterization Engineer FSStCharacterization Manager CS09/1 EP-1.62 1.62 1) Embedded Pipe Q3P) Survey Unit 1.62 meets the definition of embedded pipe for Plum Brook Reactor Facility (PBRF). 2) EP 1.62 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 1.62 were performed using a scintillation detector optimized to measwe gamma energies representative of Cs-137. Sample #EP2-5 from Survey Request (SR)-13 was referenced for this decision.
- 4) Survey Instmctions 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) Instnunent efficiency determinations are developed in accordance with the BSI/LVS-002, WEP 05-006, these determinations are appropriate for the types of radiation involved and the media being surveyed.
Revision # Original Page 1 of 3
- - FSS Design # EP 1.62 Revision # Original Page 2 of 3 Survey Unit: 1.62 1.1 The subject pipe system is the 3" riser in canal "K". The piping is located in the Hot Lab, -25fi el. 1.2 EP 1.62 consists of 3" diameter piping that is approximately 55 feet in length. 2.0 Survey Design Information 2.1 EP 1.62 was surveyed IAW Procedure
- BSI/LVS-002.
2.2 100% of the 3" ID pipe was accessible for survey. The accessible 3" ID pipe was surveyed by static measurement at one foot increments, for a total of 55 survey measurements.
2.3 Surface
area for the 3" ID piping is 730 cm2 for each foot of piping, corresponding to a total 3" ID piping surface area of 40,13 1 cm2 (4.0 m2) for the entire length of (approximately 55') of 3" piping. 3.0 Survey Unit Measurement Locations/Data 3.1 Pipe interior radiological survey forms are provided in Attachment 2 of this release record.
4.0 Survey
Unit 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 rnredyr 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 1.62 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 Co-60 is designated as the primary nuclide of concern for Piping Group 2 per Technical Basis Document TBD-06-004, which would typically lead to a survey design based on the direct measurement of Co-60. The field measurements were acquired using a detector windowed for Cs-137 versus Co-60. The survey results documented in this release record are valid as Cs-137 was present in the nuclide distribution for this pipe group in sufficient abundance and the correct nuclide distribution was used to calculate total activity.
Survey Unit: 1.62 I 5.6 Statistical Summary Table Documentation of evaluations pertaining to compliance with the unrestricted use limit of 25 mredyr and dose contributions from Embedded Pipe and radionuclides contributing 10% in aggregate of the total dose for both structural scenarios and soils. 6.1 A review of the survey results has shown that the dose contribution for EP 1.62 to be less than 1 mrernlyr. The dose contribution is estimated to be 0.047 mrem/yr based on the average of the actual gross counts measured.
Attachments Attachment 1 - BSI EP/BP Survey Report Attachment 2 - Pipe Interior Radiological Survey Form Attachment 3 - DQA Worksheet Attachment 4 - Disc containing RR for EP 1.62 & Spreadsheet SECTION 7 ATTACHMENT 1 3 PAGE@)
BSI EPlBP SURVEY REPORT PassIFail FSS MREMNR Contribution Pass <1 COMMENTS:
ACTIVITY VALUES NOT BACKGROUND CORRECTED RP Engineer I Date
EP 1.62 3" Pipe TBD 06-004 Group 2 SECTION 7 ATTACHMENT 2 & PAGE(S)
,.. ~ ..,-...-----
~*.----. --i - *,.~- ~ . - . ..... . . --- . .BSI/LVSPipeCrawler-002 Revision 4 Pipe Interior Radiological Survey Form Date: 11/13/0G Time: 101 1 Pipe ID#: !+ c'z Pipe Diameter:
11 Access Point Area:
[< Building:
l-,kr tLrk17 Elevation:
-2s) System: - Type of Survey Investigation Characterization Final Survey 6 Other Gross C06O Cs Detector ID# I Sled ID# 44 4 23~3'69 / hl0 SLED Detector Cal Date: ~/S/OG Detector Cal Due Date: ?/ 5/07 Instrument:
Z3 CO-1 Instrument ID #: 2.03982 Instrument Cal Date: ~/s-/o 6 Instrument Cal Due Date: 7 ! r.10 7 From the Daily Pipe Survey Detector Control Form for the Selected Detector Background Value f cpm 6.0 cp!~ / MDCkmtic 111 > CPm Efficiency Factor for Pipe Diameter 0 .0 -6 (firom detector efficiency determination)
MDCststic 2% 4 8 d~m/ LO 0 cm2 Is the kfD(Zsm* acceptable?
@ NO (if no, adjust sample count time and recalculate MDCRetatiC)
Comments:
C~NTI~VY~TIW
,, ?hi-- HYDM -~UFVELT EPZ-5 CMMPLeT A Technician Signature d wwA3 Y Pipe Interior Radiological Survey Package Page 1 of 3 Attachment 3, Page 1
\. .. . , .C'... - .~. . . ~---,. . . . ., ..~. . BSWSPipeCrawler-002
-. Revision 4 Pipe Interior Radiological Survey ~orm (Continuation Form) Date: ///,~/oG , , Pipe ID#: 116 2 Pipe Diameter:
3 'I Access Point Area: (4urkL K Building:
/&T LI-LE Elevation:
- - 5 I System: FIS~. EFERENCE COPY Package Page sf3 Attachment 3, Page 2
.BSI/LVSPipeCrawler-002 - - Revision 4 Pipe Interior Radiological Survey Form Date: I !//5?0& Time: 13% Pipe ID#: IaLZ Pipe Diameter:
3" Access Point Area:
///)-L VE Building:
&?A- LA.# Elevation:
-27' System: p&. K Type of Survey Investigation Characterization Final Survey 8 Other W Gross C06O Cs LT Detector ID# I Sled ID# - 37 25z?lL? 1 MI SckP Detector Cal Date: 9/~ /06 Detector Cal Due Date: 9/l/p-) Instrument:
73W - / Instrument ID #: 7AMErP Instrument Cal Date:
~/s/o b Instrument Cal Due Date: 7 / c/n7 From the Daily Pipe Survey Detector Control Form for the Selected Detector Background Value
~C~~t,,, 4,7 cpm /o. C cpm Efficiency Factor for Pipe Diameter 0. 0~06b (from detector efficiency determination)
MDCmt,c ~04% d~m/ t OD cm2 IS the MDcstauc acceptable?
@ NO (duo, adjust sample count time and recalculate MDcR,,,J Comments:
5 I?@@, tisr ~ZCZ &B& EPZ -5 PP~FTIW Technician Signature 1 Pipe Interior Radiological Survey .- REFERENCE COPY 3 Package Page 1 of - Position # 1 2 2 Attachment 3, Page 1 Gross Counts 17 23 7 7 Feet into Pipe fiom Opening I t-. 3 Count Time (mi4 I Gross cpm 19 27 -7 7 Net cpm fl(s 4 dpm/100crn2 n (A I i- BSIILVSPipeCrawler-002
.-,- Revision 4 Pipe Interior Radiological Survey Form (Continuation Form) Date: 11!(3/6~ Pipe ID#: 1.6 z Pipe Diameter:
3.q Access Point Area: v&,,g fig- Building:
FfoT L& Elevation:
-2 ) 1 System: - 't Package Page - of 3 Attachment 3, Page 2
SECTION 7 ATTACHMENT 3 I PAGE(S)
I DQA Check Sheet I Design # I EP 1.62 1 Revision # I Original I I I ~unrey unit # 1 EP 1.62 I I Preliminary Data Review' I 4 Was the lnstrumentatlon MDC for structure scan measurements, so11 scan measurements, and embeddedlbuned plplng scan measurements below the DCGLw or if not, was the need for addlhonal statlc measurements or so11 samples aodressed In the survey des~gn? - - --- --- the lnstrumentatlon MDC for volumetr~c measurements 6 Were the MDCs and assumpuons used to develop tnem appropnate for the Instruments and techniques Answers to the following questions should be fully documented in the Survey Unl Release Record 1. Have surveys been performed in accordance wah survey instructions in the Survey Design? 2. Is the instrumentation MDC for structure static measurements belowthe DCGLw for Class 1 and 2 survey units, or below 0.5 DCGLw for Class 3 survey units? 3. Is the instrumentation MDC for embeddedlburied
~i~ina static measurements below the DCGLw ? .. . I used to oerform the survev? In( I 1 Yes X X I Graphical Data Review 1 7. Were the survey methods used to collect data proper for the types of radiation involved and for the media being surveyed?
- 8. Were 'Special Methods" for data collection properly applied for the survey unit under review?
- 9. Is the data set comprised of qualified measurement resuks collected in accordance with the survey design, which accurately reflects the radiological status of the facility?
I 1. Has a oostina lot been created? I I 1x1 No X X X 2. Has a histwram lor other freauencv dot) been created? I I I X NIA X 2. Is the mean ofthe sample data
< DCGW 1x1 I - - 3. Have other graphical data tools been created to asslst In analyzing the data? - 3 If elevated areas have been ~dent~fied by scans andlor sampling 1s the average act vity In each elevated area < DCG4.c (Class 1). < DCGL* (Class 2), or cO 5 DCGh (Class 3)? X X 4. Is the result of the Elevated Measurements Test < 1.0? I 1 I x 1 5. Is the result of the statistical test (S+ for Sign Test or W, for WRS Test)
? the critical value?
I I 1x1 Data Analysis I Comments:
- 1. Are all sample measurements below the DCGLw (Class 1 8 2), or 0 5 DCGh (Class 3)?
Page 1 of 1 X SECTION 7 ATTACHMENT 4 1 DISC