ML080590206
| ML080590206 | |
| Person / Time | |
|---|---|
| Site: | Plum Brook File:National Aeronautics and Space Administration icon.png |
| Issue date: | 02/14/2008 |
| From: | Case R, Wood G - No Known Affiliation |
| To: | NRC/RGN-III |
| References | |
| EP PPH-101 | |
| Download: ML080590206 (19) | |
Text
Description Survey Unit Release Record Design #
Survey Unit #(s) in accordance with (IAW) the Babcock Services Incorporated (BSI)/LVS-003, 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 BSI/LVS-003, WEP 05-006, these determinations are appropriate for the types of radiation involved and the media being surveyed.
FSSICharacterization Engineer CS-0911 EP PPH-10 1 PPH-1 0 1
- 1) Embedded Pipe (EP) Survey Unit PPH-101 meets the definition of embedded pipe for Plum Brook Reactor Facility (PBRF).
- 2) EP PPH-101 is a Class 1, Group 1 survey unit as per the PBRF Final Status Survey Plan (FSSP) and Technical Basis Document (TBD)-06-004.
- 3) Surveys in EP PPH-101 were performed using a scintillation detector optimized to measure beta energies 385 keV (IS0 7503-1 Table3, Tc99). This energy is lower than the beta energy for C060 (96 keV, IS0 7503-1 Table 3),
assuring the nuclide of concern for DCGL is assessed during data acquisition.
- 4) Survey Instructions for this survey unit are incorporated into and performed Page 1 of 4 Revision #
Original
FSS Design # EP PPH-101 Revision # Original Page 2 of 4 Survey Unit: PPH-101 1.0 History/Description 1.1 The subject pipe is the 24 secondary cooling supply line for the PCW system. The function of this piping was to convey water from the heat exchangers in PPH Room 4 to the RB-15 level.
1.2 EP PPH-101 consists of 24 diameter piping that is approximately 27 feet in length.
2.0 Survey Design Information 2.1 EP PPH-101 was surveyed IAW Procedure #BSI/LVS-003.
2.2 18 feet of the 24 pipe was accessible for survey. The inaccessible piping includes a 6 foot section of elbow and the three feet of piping between the 0 elevation and the -3 elevation in the PPH Room 4. The 6 elbow is inaccessible to the pipecrawler. The 3 in PPH Room 4 is released to the structural DCGL and will not be grouted. The survey for this piping will be accomplished as part of the structural release survey in PPH Room 4.
2.3 100% of the accessible piping was scanned.
2.4 Eight survey locations were selected by a random number generator for static measurements. Three of these locations were in the inaccessible elbow. At each accessible location four static measurements were acquired IAW BSI/LVS-003 for a total of 20 static measurements (Att. 1A).
2.5 The surface area for the 24 piping is 5837 cm2 for each foot of piping, corresponding to a piping surface area of 140088 cm2 (14 m2) for the 24 feet of embedded pipe 24 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 EP/Buried Pipe (BP) Survey Report provided in Attachment 1A & 1B.
5.2 This survey unit was assessed for compliance with the release criterion attributing all activity derived dose as a 100% Co60 nuclide distribution.
This is the most conservative DCGL for the facility.
5.3 All scan 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.
FSS Design # EP PPH-101 Revision # Original Page 3 of 4 Survey Unit: PPH-101 5.4 Scan measurements require a 90 second scan time to survey each section of accessible 24piping at < 1inch/second. The documented gross cpm measurement for each scan is the highest, instantaneous, cpm count rate observed during the 90 second scan. The derived activity from these scan measurements is the most conservative quantity for that section of assessed piping. This conservatism is replicated when determining compliance with the DCGL release criterion. (BSI/LVS 003, WEP 05-000-6).
5.5 All static 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.
5.6 When implementing the Unity Rule, provided in Section 3.6.3 of the FSSP, the survey unit that is constituted by EP PPH-101 passes FSS.
5.7 Background was not subtracted from the survey measurements and the Elevated Measurement Comparison (EMC) was not employed for this survey unit.
5.8 Based upon the results of the final survey measurements it is reasonable to conclude that the final survey of the accessible portion of this pipe system is appropriate to demonstrate the radiological condition of the entire pipe.
Survey Unit EP PPH-101 demonstrates compliance with the DCGL values, as presented in Sections 3.3, 7.5 and Attachment C of the PBRF FSSP.
5.9 Statistical Summary Table Statistical Parameter 24 Pipe Total Number of Static Survey Measurements 20 Number of Measurements >MDC 20 Number of Measurements Above 50% of DCGL 0
Number of Measurements Above DCGL 0
Mean 0.024 Median 0.023 Standard Deviation 0.004 Maximum 0.035 Minimum 0.016
FSS Design # EP PPH-101 Revision # Original Page 4 of 4 Survey Unit: PPH-101 6.0 Documentation of evaluations pertaining to compliance with the unrestricted use limit of 25 mrem/yr 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 PPH-101 to be less than 1 mrem/yr. The dose contribution is estimated to be 0.024 mrem/yr based on the average of the actual gross counts measured.
7.0 Attachments A -
BSI EP/BP Survey Report Static & Random Number Generated Static Locations B -
BSI EP/BP Survey Report Scan Pipe Interior Radiological Survey Form DQA Worksheet EP PPH-101 SURR & Spreadsheet Disc
SECTION 7 ATTACHMENT 1A 3 PAGES
BSl EPJBP SURVEY REPORT (STATIC)
RP Engineer I Date
EP PPH-101 24" Pipe TBD 06-004 Group 1 Measure ment ID #
gcpm net cpm Co-60 activity (total dpm)
Co-60 activity (dpm/100 cm2)
Unity 4
309 309 5,558 5,558 0.023 5
296 296 5,324 5,324 0.022 6
465 465 8,363 8,363 0.035 8
280 280 5,036 5,036 0.021 18 301 301 5,414 5,414 0.022 19 298 298 5,360 5,360 0.022 20 326 326 5,863 5,863 0.024 21 416 416 7,482 7,482 0.031 30 311 311 5,594 5,594 0.023 31 276 276 4,964 4,964 0.021 32 406 406 7,302 7,302 0.030 33 365 365 6,565 6,565 0.027 42 218 218 3,921 3,921 0.016 43 297 297 5,342 5,342 0.022 44 326 326 5,863 5,863 0.024 45 351 351 6,313 6,313 0.026 50 267 267 4,802 4,802 0.020 51 343 343 6,169 6,169 0.026 52 298 298 5,360 5,360 0.022 53 309 309 5,558 5,558 0.023 MEAN 0.024 MEDIAN 0.023 STD DEV 0.004 MAX 0.035 MIN 0.016 1 OF 1
RANDOM GENERATED STATIC MEASUREMENT LOCATIONS PPH 101 SURVEY LOCATION COMMENTS 5
7 10 INACCESSIBLE 11 INACCESSIBLE 15 INACCESSIBLE 17 21 26
SECTION 7 ATTACHMENT 1B 2 PAGES
L V
BSl EPlBP SURVEY REPORT (SCAN)
Pipe ID Survey Date Survey Time Pipe Size DCGL (dprnllOOcm2) 50% DCGL (dprnl1W)cmZ)
ACTIVITY VALUES NOT BACKGROUND CORRECTED.
PPH 101 09-Aug-06 1600 24" 240800 120400 Survey Location 2360-1 #
Detector-Sled #
Detector Efficiency Pipe Area Incorporated by Detector mciency (in c m ~ )
Field BKG (cpm)
PPH RM4 203488 22321 0-LVS CRLR24 0.0481 100 280
EP PPH-101 24" Pipe TBD 06-004 Group 1 Measure ment ID #
gcpm net cpm Co-60 activity (total dpm)
Co-60 activity (dpm/100 cm2)
Unity 1
474 474 9,854 9,854 0.041 2
428 428 8,898 8,898 0.037 3
413 413 8,586 8,586 0.036 8
396 396 8,233 8,233 0.034 9
458 458 9,522 9,522 0.040 10 413 413 8,586 8,586 0.036 11 466 466 9,688 9,688 0.040 12 312 312 6,486 6,486 0.027 13 297 297 6,175 6,175 0.026 14 389 389 8,087 8,087 0.034 15 466 466 9,688 9,688 0.040 16 421 421 8,753 8,753 0.036 17 409 409 8,503 8,503 0.035 22 506 506 10,520 10,520 0.044 23 419 419 8,711 8,711 0.036 24 381 381 7,921 7,921 0.033 25 511 511 10,624 10,624 0.044 26 489 489 10,166 10,166 0.042 27 319 319 6,632 6,632 0.028 28 501 501 10,416 10,416 0.043 29 417 417 8,669 8,669 0.036 34 509 509 10,582 10,582 0.044 35 404 404 8,399 8,399 0.035 36 489 489 10,166 10,166 0.042 37 551 551 11,455 11,455 0.048 38 417 417 8,669 8,669 0.036 39 449 449 9,335 9,335 0.039 40 311 311 6,466 6,466 0.027 41 381 381 7,921 7,921 0.033 46 479 479 9,958 9,958 0.041 47 483 483 10,042 10,042 0.042 48 431 431 8,960 8,960 0.037 49 463 463 9,626 9,626 0.040 54 499 499 10,374 10,374 0.043 55 506 506 10,520 10,520 0.044 56 527 527 10,956 10,956 0.045 57 461 461 9,584 9,584 0.040 MEAN 0.038 MEDIAN 0.039 STD DEV 0.005 MAX 0.048 MIN 0.026 1 OF 1
SECTION 7 ATTACHMENT 2 4 PAGES
BSI/LVSPipeCrawler-003 Original Pipe Interior Radiological Survey Form Date:
$?-q-o(u.
Time:
1 bl?(2 Pipe ID#: gpd 1 D l Pipe Diameter:
24 "
I Access Point Area: PPp R fl$
Building:
BBH-Elevation:
System:
$&d Type of Survey Investigation Characterization Final Survey 7(
Other X Gross C06O Cs137 Detector ID# 1 Sled ID#
ZZ-SZI D I L ~ 5 P C i k ' d 4 Detector Cal Date:
7..
5 - O &
Detector Cal Due Date:
7 0 7 Instrument:
2 3 50--
I Instrument ID #:
-20 3 4 Q F Instrument Cal Date:
70 5 d D b Instrument Cal Due Date:
70 5-C! 7 From the Daily Pipe Survey Detector Control Form for the Selected Detector Background Value 7-YO cpm MDCRstatic G I CPm Efficiency Factor for Pipe Diameter 0,
D SS(c (fi-om detector efficiency determination)
/ 0 7~
d p d
/ D D cm2 IS the MDC,,
acceptable? a NO (if no, adjust sample count time and recalculate MDCI&,,ti,)
Comments:
/ h l f l ~ ~ i & r ~
7
~
7 51/12<~f FR0lYl,a1,$
9: - J.. J 1 P??//#&.ps Technician Signature Pipe Interior Radiological Survey REFERENCE COPY r
l Measur-ment ID #
1 2
3 3
7
'3
/ 0 Package Page 1 of 2, Page 1 Location in Pipe 27/
Z[O& 5 Z4G' ZO' 4D"
-a,/
( W V Zb' 270' Z&'
3 m "
/
2 4' z ~ J '
Scan/Count Time (rnin/sec) 40.5 q9.5 9ns
/* B m
/
- O m
/-Gbf~
/ l f 2 ? 4
~ Q - s m.5 qos Gross Counts 47+
4 2.9 4/\\3 307 zr3b 4&.
z m L
3
/fi 4%
5 8 4/3 Gross
- cpm, 74 42%
413 307 z q h 3 fa 4rJg
-4B Net cpm f 9 /a 1
I -
dprn/l 00cm2 I&
\\
'-2 Pipe Interior Radiological Survey Form (Continuation Form)
BSI/LVSPipeCrawler-003 Original Date:
9 2) 6 Pipe ID#: P&
/ z; /
Pipe Diameter:
2-4 I
Access Point Area: p, / g flfl Building:
w / q Elevation:
System:
Package Page &of 3 REFERENCE COPY, Page 2
1-Pipe Interior Radiological Survey Form (Continuation Form)
BSYLVSPipeCrawler-003 Original Date:
p-q-oh; Pipe ID#: @m 1 Q (
Pipe Diameter:
2-4 Access Point Area: /f/f RA#
Building:
f'6'l-f Elevation:
System:
p@?d Package page 3 of 2 REFERENCECOPY, Page 2
i d :
SECTION 7 ATTACHMENT 3 1 PAGE
b l-r' Page 1 of 1 L
DQA Check Sheet Design #
Survey Unit #
EP PPH-101 Preliminary Data Review' EP PPH-I01 Revision #
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 I and 2 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 ?
- 4.
Was the instrumentation MDC for structure scan measurements, soil scan measurements, and embeddedlburied piping scan measurements below the DCGLw, or, if not, was the need for additional static measurements or soil samples addressed in the survey design?
- 5. Was the instrumentation MDC for volumetric measurements and smear analysis < 10% DCGLw ?
- 6.
Were the MDCs and assumptions used to develop them appropriate for the instruments and techniques used to perform the survey?
- 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 results collected in accordance with the survey design, which accurately reflects the radiological status of the facility?
Original Yes X
X X
X X
X Graphical Data Review No
- 1.
Has a posting plot been created?
- 2.
Has a histogram (or other frequency plot) been created?
- 3. Have other graphical data tools been created to assist in analyzing the data?
N,A X
X X
X X
Data Analysis X
X X
- 1. Are all sample measurements below the DCGLw (Class 1 & 2), or 0.5 DCGLw (Class 3)?
- 2.
Is the mean of the sample data < DCGLW?
- 3.
If elevated areas have been identified by scans andlor sampling, is the average activity in each elevated area < DCGLEMC (Class I), < DCGLw (Class 2), or ~0.5 DCGLw (Class 3)?
- 4.
Is the result of the Elevated Measurements Test c 1.O?
- 5.
Is the result of the statistical test (S+ for Sign Test or Wr for WRS Test) 1 the critical value?
X X
Comments:
I n
FSSICharacterization Engineer (printlsign)
FSSl Characterization Manager (prinffsign)
CS-09/2 a h& / a $
R. Case Date Date Zy/f/-
of
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SECTION 7 ATTACHMENT 4 1 DISC