ML073110263
| 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