ML080590195

Plum Brook Reactor Facility (Pbrf Survey Unit Release Record EP PPH-102

ML080590195
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-102
Download: ML080590195 (19)

Text

I I

Survey Unit Xeiease Record I

I embedded pipe for Plum Brook Reactor Facility (PBRF).

I I

I Design #

Survey Unit #(s)

2) EP PPH-102 is a Class 1, Group 1 survey unit as per the PBRF Find Status Survey Plan (FSSP) and Technical Basis Document (TBD)-06-004.

I Revision #

EP PPH-102 PPH-102

3) Surveys in EP PPH-102 were performed using a scintillation detector optimized to measure beta energies 285 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.

I I 1) Embedded Pipe (EP) Survey Unit PPH-102 meets the definition of Description Original

4) Survey Instructions for this survey unit are incorporated into and performed 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.

Page 1 of 4

5) Instrument efficiency determinations are developed in accordance with the BSIILVS-003, WEP 05-006, these determinations are appropriate for the types of radiation involved and the media being surveyed.

Date:

z - / + o ~

Approval Signatures rl

\\

FSSICharacterization Engineer FSSICharacterization Manager R. C

FSS Design # EP PPH-102 Revision # Original Page 2 of 4 Survey Unit: PPH-102 1.0 History/Description 1.1 The subject pipe is the 24 secondary cooling return line for the PCW system. The function of this piping was to convey water to the heat exchangers in PPH Room 4 from the RB-15 level.

1.2 EP PPH-102 consists of 24 diameter piping that is approximately 28 feet in length.

2.0 Survey Design Information 2.1 EP PPH-102 was surveyed IAW Procedure #BSI/LVS-003.

2.2 19 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. Four 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 16 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 145925 cm2 (14.6 m2) for the 25 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-102 Revision # Original Page 3 of 4 Survey Unit: PPH-102 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-102 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-102 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 16 Number of Measurements >MDC 16 Number of Measurements Above 50% of DCGL 0

Number of Measurements Above DCGL 0

Mean 0.023 Median 0.023 Standard Deviation 0.003 Maximum 0.031 Minimum 0.015

FSS Design # EP PPH-102 Revision # Original Page 4 of 4 Survey Unit: PPH-102 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-102 to be less than 1 mrem/yr. The dose contribution is estimated to be 0.023 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-102 SURR & Spreadsheet Disc

SECTION 7 ATTACHMENT lA 3 PAGES

BSI EPIBP SURVEY REPORT (STATIC]

PPH 102 Pipe Size I

Detector-Sled #

1 22321 0-LVS CRLR24 Survey ~ ~ c a t i o n 2350-1 #

I Detector Efficiency I

0.0556 PPH RM4 203488 DCGL (dprnMOOcrn2)

!50% DCGL (dpm1lM)cmZ)

I Field BKG ( C P ~ )

I 280 240800 120400 Pipe Area Incorporated by Detector Efficiency (in cm2)

Routine Survey I X

I I

Field M D C R ( C P ~ )

I 61 100 QA Survey 1

I I Nominal MDC (

d

~

~

m 2

)

I 1,092 Survey Measurement Results I

Total Number of Survey Measurements 16 I

I Number of Measurements >MDC 16 I

Mean I

0.023 Number of Measurements Above 50% DCGL Number of Measurements Above DCGL 0

0 Median Standard Deviation Survey Technician(s)

I WOOD 0.023 0.003 Maximum Minimum 0.031 0.01 5 Survey Unit Classification TBD 06-004 Piping Group SR-13 Radionuclide Distribution Sample Area FactorIEMC Used I

COMMENTS:

ACTIVITY VALUES NOT BACKGROUND CORRECTED.

1 1

EP 3-9 Nn PassIFail FSS MREMNR Contribution RP Engineer I Date Pass c I

EP PPH-102 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 8

313 313 5,629 5,629 0.023 9

411 411 7,392 7,392 0.031 10 296 296 5,324 5,324 0.022 11 244 244 4,388 4,388 0.018 24 296 296 5,324 5,324 0.022 25 313 313 5,629 5,629 0.023 26 368 368 6,619 6,619 0.027 27 351 351 6,313 6,313 0.026 30 292 292 5,252 5,252 0.022 31 310 310 5,576 5,576 0.023 32 333 333 5,989 5,989 0.025 33 300 300 5,396 5,396 0.022 50 206 206 3,705 3,705 0.015 51 291 291 5,234 5,234 0.022 52 303 303 5,450 5,450 0.023 53 283 283 5,090 5,090 0.021 MEAN 0.023 MEDIAN 0.023 STD DEV 0.003 MAX 0.031 MIN 0.015 1 OF 1

RANDOM GENERATED STATIC MEASUREMENT LOCATIONS PPH 102 SURVEY LOCATION COMMENTS 3

11 INACCESSIBLE 12 INACCESSIBLE 13 INACCESSIBLE 16 INACCESSIBLE 18 19 25

SECTION 7 ATTACHMENT 1B 2 PAGES

L h#$

BSl EPlBP SURVEY REPORT (SCAN)

Pipe ID Survey Date Survey Time Pipe Size DCGL (dprnl1W)crnZ) 50% DCGL ( d p m l l ~ m 2 )

Routine Survey QA Survey PPH 102 10-Aug-06 1600 24" 240800 120400 X

Survey Measurement Results Survey Location 2350-1 #

Detector-Sled #

Detector Efficiency Pipe Area Incorporated by Detector Emclency (In cm2)

Field BKG (cpm)

Field MDCR (cprn)

Nominal MDC (dpmn~0c~z)

Total Number of Survey Measurements Number of Measurements >MDC Number of Measurements Above 50% DCGL Number of Measurements Above DCGL Mean Median Standard Deviation Maximum Minimum PPH RM4 203488 22321 0-LVS CRLR24 0.0481 100 280 6 1 5,658 37 37 0

0 0.038 0.038 0.004 0.046 0.028 Survey Technician(s)

WOOD Survey Unit Classification TBD 06-004 Piping Group SR-13 Radionuclide Distribution Sample Area FactorIEMC Used PassIFail FSS MREMNR Contribution 7

1 EP 3-9 No Pass

< 1 COMMENTS:

CTlVlTY VALUES NOT BACKGROUND CORRECTED.

EP PPH-102 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

505 505 10,499 10,499 0.044 2

416 416 8,649 8,649 0.036 3

389 389 8,087 8,087 0.034 4

439 439 9,127 9,127 0.038 5

511 511 10,624 10,624 0.044 6

319 319 6,632 6,632 0.028 7

501 501 10,416 10,416 0.043 12 404 404 8,399 8,399 0.035 13 435 435 9,044 9,044 0.038 14 449 449 9,335 9,335 0.039 15 477 477 9,917 9,917 0.041 16 493 493 10,249 10,249 0.043 17 450 450 9,356 9,356 0.039 18 430 430 8,940 8,940 0.037 19 514 514 10,686 10,686 0.044 20 489 489 10,166 10,166 0.042 21 400 400 8,316 8,316 0.035 22 446 446 9,272 9,272 0.038 23 476 476 9,896 9,896 0.041 28 411 411 8,545 8,545 0.035 29 479 479 9,958 9,958 0.041 34 431 431 8,960 8,960 0.037 35 474 474 9,854 9,854 0.041 36 347 347 7,214 7,214 0.030 37 407 407 8,462 8,462 0.035 38 481 481 10,000 10,000 0.041 39 404 404 8,399 8,399 0.035 40 521 521 10,832 10,832 0.045 41 447 447 9,293 9,293 0.039 42 391 391 8,129 8,129 0.034 43 389 389 8,087 8,087 0.034 44 427 427 8,877 8,877 0.037 45 431 431 8,960 8,960 0.037 46 531 531 11,040 11,040 0.046 47 399 399 8,295 8,295 0.034 48 422 422 8,773 8,773 0.036 49 414 414 8,607 8,607 0.036 MEAN 0.038 MEDIAN 0.038 STD DEV 0.004 MAX 0.046 MIN 0.028 1 OF 1

SECTION 7 ATTACHMENT 2 4 PAGES

BSYLVSPipeCrawler-003 Original Pipe Interior Radiological Survey Form Type of Survey Investigation Characterization Final Survey X Other X Gross fi Co60 Cs137 Detector ID# 1 Sled ID#

27-33 % / L) 1 I - W ~ C & L /

Detector Cal Date:

.7-5 -

(Q Detector Cal Due Date: 5 - C 7 Instrument:

.2..3 3 c, -.- 1 Instrument ID #:

7-03 4 pf' Instrument Cal Date:

7 -- 5 C; b Instrument Cal Due Date:

7 - 5 - i-f 7 From the Daily Pipe Survey Detector Control Form for the Selected Detector Background Value Z= cpm MDCKtatic

( Q \\

CPm Efficiency Factor for Pipe Diameter O - 05.5 f;56

( b m detector efficiency determination) m c s t a t i c

/ 1'42 dpm/

/ p p cm2 Is the MDCsmtic acceptable? a NO (if no, adjust sample count time and recalculate MDCRsbnc)

Comments: j f i f i ~ t ~,

6~ c T o SI.g<~f

-,TI 1 k1'l

.kl q :

., fmA ; 7 ' fi-/,m PJ?~

l ; r c e ~

Technician Signature Pipe Interior Radiological Survey REFERENCE COPY Package Page 1 of 2, Page 1

BSI/LVSPipeCrawler-003 Original Pipe Interior Radiological Survey Form (Continuation Form) ate:

8-I G --D b Pipe ID#: P$'d I Q t Pipe Diameter: 24 Access Point Area:

Building:

fe id Elevation:

System:

Package Page of 2, Page 2

BSI/LVSPipeCrawler-003 Original Pipe Interior Radiological Survey Form (Continuation Form)

Date:

$ 4 ~ )

-- 2x9 Pipe ID#: qP1.t 1 2: -2 Pipe Diameter:

24 /'

h e s s Po, h a : qhf~d Building:

fP1-I-Elevation:

0' System:, Page 2

SECTION 7 ATTACHMENT 3 1 PAGE

Page 1 of 1 DQA Check Sheet Design #

Survey Unit #

EP PPH-102 Preliminary Data Review' EP PPH-102 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 instrumentat~on MDC for structure static measurements below the 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 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?

X X

X X

X FSSl Characterization Manager (printlsign)

CS-0912

SECTION 7 ATTACHMENT 4 1 DISC