• • Survey Unit Release Record

Design # EP-PPH 104 Revision # Original Page 1 of 3

Survey Unit #(s) PPH 104

Description

1) Embedded Pipe (EP) Survey Unit PPH 104 meets the defmition of embedded pipe for Plum Brook Reactor Facility (PBRF) for those portions of piping embedded in the building foundation walls (PPH ). The portion of piping which transits in soil under or between buildings does not meet the criteria for embedded piping. The complete piping will be grouted, the portions embedded in the building structure will remain embedded for any future reuse, those portions in the ground can be released for unrestricted use.

2) EP PPH 104 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 104 were performed using a scintillation detector optimized to measure gamma energies representative of Co-60. Sample #EP 3-7 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 (lAW) 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 BSI/LVS-002, WEP 05-006, these detenninations are appropriate for the types of radiation involved and the media being surveyed.

Approval Signatures Date:

FSS/Characterization Engineer

FSS/Characterization Manager /f;'ll// t'

R. Case /7/V~

Fonn CS-09/1 Rev 0

---~---~--.----

FSS Design # EP PPH 104 I Revision # Original Page 2 of3

Survey Unit: PPH 104

1.0 HistorylDescription

1.1 The subject pipe is an 8" DI water line from PPH Room 4 to the RB -15' level (Cold Pipe Tunnel).

1.2 EP PPH 104 consists of 8" diameter piping that is approximately 24 feet in length.

2.0 Survey Design Infonnation

2.1 EP PPH 104 was surveyed lAW Procedure #BSI/LVS-002.

2.2 100% of the 8" pipe was accessible for survey. The accessible 8" pipe was surveyed by static measurement at one foot increments, for a total of 24 survey measurements.

2.3 Surface area for the 8" piping is 1946 cm2 for each foot of piping, 2corresponding to a total 8" piping surface area of 46704 cm (4.7 m2

) for the entire length of (approximately 24') of 8" piping.

3.0 Survey Unit Measurement LocationslData

3.1 Pipe interior radiological survey fonns are provided in Attachment 2 of this release record.

4.0 Survey Unit InvestigationslResults

4.1 None

5.0 Data Assessment Results

5.1 Data assessment results are provided in the EPlBuried Pipe (BP) Survey Report provided in Attachment 1.

5.2 This survey unit was assessed as a building re-use scenario with all activity derived dose as a 100% C060 nuclide distribution. This is the most conservative DCGL for the facility (11 ,000dpm/l 00cm2

).

5.3 When implementing th€ Unity Rul8, provid8d in S@ction 3.6.3 of the FSSP, four survey measurements exceeded unity. The survey unit that is constituted by EP PPH 104 passes FSS after application of Elevated Measurement Comparisons (EMC) and Elevated Measurement Tests (EMT). The EMC Unity sum was 0.027 of unity, and the EMT Unity sum was 0.575 of unity.

5.4 DCGL's for the building reuse scenario are used to demonstrate compliance with the releas'e criterion for this release record. The DCGL's for embedded pipe are not applied, therefore the Structural Area Factors listed in Table 3-5 of the FSS are the appropriate area factors for EMC and EMT evaluations.

5.5 The area factor of 40.2 was utilized for this survey unit, this is the appropriate area factor listed in Table 3-5 of the PBRF FSSP.

FSS Design # EP PPH 104 I Revision # Original Page 3 of3 I

Survey Unit: PPH 104

5.6 Background was not subtracted from the survey measurements.

5.7 Statistical Summary Table

8" Statistical Parameter

I Pipe

Total Number of Survey Measurements 24 Number of Measurements >MDC 24

Number of Measurements Above 50% of DCGL 14 Number of Measurements Above DCGL 1

Mean 0.542 Median 0.526

Standard Deviation 0.151 Maximum 1.099 Minimum 0.368

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 ofthe survey results has shown that the dose contribution for EP PPH 104 to be less than 25 mrem/yr. The dose contribution is estimated to be 13.55 mrem/yr 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 - EP PPH 104 SURR & Spreadsheet Disc

• •

SECTION 7 ATTACHMENT 1

2 PAGES

• • . .,

I Pf U VEY PORT

Pipe 10 PPH 104 Survey Location PPH RM .. to RB-1S' (CPT)

Survey Date 21-Mar~8 2350-1 # 189094 1---­ -

Survey Time 1550 Detector-Sled # B577A-108

Pipe Size 8" Detector Efficiency 0.0069

DCGl(cfpIr.I1oo_1 1 10E+04 ~ l\,n In............" by D".etor ElIi<1utcy {in -1 1946 Pipt A....a lncorp~.d by

4.7 Field BKG (<pm) See Survey Sheets §Y'Y'Y Oar:~ (mJ'1

Routine Survey X Field MDCR,-, See Survey Sheets

QA Survey Nominal MDC (oIpWtDlca2l 221 Survey Measurement Results

Total Number of Survey Measurements 24

Number of Measurements >MDC 24

Number of Measurements Above 50% DCGL 14

Number of Measurements Above DCGL 1 Mean 0.542

Median 0526

Standard Deviation 0.151

Maximum 1.099

Minimum 0.368 PHELPS

Survey Technician(s)

SlIl'Vey Umt Classrficatlon 1

TBD 06--004 Piping Group 1

SR-13 Radionuclide Distribution Sample 3-7

Measured Nuclide CD-60

Area FactorlEMC Used Yes

PasslFail FSS Pass

MREMIYR Contribution <25

COMMENTS:

ACTIVITY VALUES NOT BACKGROUND CORRECTED.

RP Engineer I Date vllAlJ/.5- / DJ' 7?'

• • PPH 104 8" Pipe

TBD 06-004 Group 1

:u:-c: I CII E CII... ;:, III

gcpm ncpm Co-60 activity

(total dpm) Co-60 activity (dpm/100cm2) Unity

EMC Unity

EMT Unity

eu CII ~

1 598 598 86,667 I 4,454 0.405 0.405 2 574 574 83,188 4,275 0.389 0.389 3 544 544 78,841 4,051 0.368 0.368 4 825 825 119,565 6,144 0.559 0.559 5 938 938 135,942 6,986 0.635 0.635 6 900 900 130,435 6,703 0.609 0.609 7 1062 1062 153,913 7,909 0.719 0.719 8 942 942 136,522 7,016 0.638 0.638 9 -­ 814 814 117,971 6,062 0.551 0.551

10 857 857 124,203 8,382 0.580 0.580

11 775 775 112,319 5,772 0.525 0.525

12 777 777 112,609 5,787 0.526 0.526

13 723 723 104,783 5,385 0.490 0.490

14 777 777 112,609 5,787 0.526 0.526

-+~ 660 638

680 638

98,551 92,464

5,064 4,751

0.460 0.432

0.460 0.432

17 676 676 97,971 5,034 0.458 0.458 18 793 793 114,928 5,906 0.537 0.537

19 698 698 101,159 5,198 0.473 0.473

20 637 637 92,319 4,744 0.431 0.431

21 573 573 83,043 4,267 0.388 0.388 0.057

22 1623 1623 235,217 12,087 1.099 I 0.027

23 806 806 116,812 6,003 I 0.546 0.546

24 993 993 143,913 7,395 0.672 0.672

5,162 0.027 0.575

MEAN 0.542 EMC Unity

EMT Unity

MEDIAN 0.526 STD DEV 0.151

MAX 1.099

MIN 0.368

1 of 1

• •

SECTION 7 AT ACHMENT2

3 PAGES

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• • BSIJLVSPipeCrawler-002 Revision 5

Pipe Interior Radiological Survey Form

Date:)' 17. ,Og Time: IS'S 0 Pipe ID#: PPHIt) 1 Pipe Diameter: __-=;:8::-' Access Point Area: fff! Rrv1 J-j Building~=Ff2'dj!,"d,Jl~..=.=.==="'.-....;!E:=:l:;;:.ey;;.;.a~ti~og~:'-._~=~f2~=~="'__S~:Y.ste~, orwq:jeA<:---­

Type of Survey Investigation Characterization Final Survey A Other v --~ -- ­I

Gross ' Co60 v' Cs

Detector 1I,)# I Sled ID# _----'='6=::.......»1'~"---'2 _7L-&.L.--_ 1_----4-(-=-O.LL-lfl

Detector Can Date: (-dS, C) If Detector Cal Due Date: I' ,;;.5 '0 r Instnirntnt: a3 S-o - I Instrument ID #: d- () 3 c.(3d:

Instrument Cal Date: -'-1-"-0_,--'-1-'-[._·_0......:.7 Instrument Cal Due Date: . .lL1_'.><..o......,R----'/--'()~'1'"-. _

From the Daily Pipe Survey Detector Control Form for the Selected Detector

Background Value 86. b cpm

MDCRstatic 35 cpm () ......... / a ----':::'-=--- • u· ~ '" (

Efficiency Factor for Pipe Diameter -0 i GQO ~ (from detector efficiency determination) 2wIDCstatic Z z..l dprn/ { DV cm

Is the MDCstatic acceptable? ~ No (if no, adjust sample count time and recalculate MDCR,tahc)

Comments:

Technician Signature

Pipe Interior Radiological Survey

. Position Feet into Pipe Count Time Gross Counts Gross

# from Opening (min) cpm 1 I t 5'1 t, 5Cjf 2 J. / 57£ 671{ 3 , I C; 1.-1 1 S J-) 'f 4 ~

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REFERENCE COpy

Package Page 1 of3

Attachment 3, Page 1

SERVICES INC,

• • BSIILVSPipeCrawler-002 Revision 5

Pipe Interior Radiological Survey Form (Continuation Form)

Date: 3-d7-00 c;J{t'

Pipe ID#: -LP-=-'-p=-"-H.:....-J,.{--=-(J_t('-----_ Pipe Diameter: __0=-=-- Access Point Area: fJflf /<(/1/} I-( Building: (Jeff Elevation: 0 System: [):r: Wt<.1,(,

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Count Time (min)

Position Feet into Pipe # from Opening

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Gross Counts

77S­777 7d.3 717 fooO h s9 h 16 7q3toqg

Gross cpm·

77S 777 7)3 727 h 80 6 .3 /) 076 7'(3 /; q~

Net cpm

~ 37 ~ J? 573 b73 Ih~3 It;) '5

3U(o ~66 q15 1q3

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REFERENC COpy

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Attachment 3, Page 2

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REFERENCE C,OPY

• •

SECTION 7 A ACHM- N 3

1 PAGE

DQA Check Sheet

Design # EP PPH-104 I Revision # I Original I

I Survey Unit # EP PPH-104

Preliminary Data Review'

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 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 embedded/buried 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?

Graphical Data Review

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?

Data Analysis

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 and/or sampling, is the average activity in each elevated area < DCGLEMC (Class 1), < DCGLw (Class 2), or <0.5 DCGLw (Class 3)?

4. Is the result of the Elevated Measurements Test < 1.0?

5. Is the result of the statistical test (5+ for Sign Test or W, for WRS Test) ~ the critical value?

Comments:

See Section 5 of this Survey Unit Release Record

I

Yes No N/A

X

X

X

X

X

X

X

X

X

X

X

X

X

X

X

X

X

R.case

DateFSS/Characterization Engineer (print/sign)

DateFSSI Characterization Manager (print/sign)

Page 1 of 1

Form CS-09/2

Rev 0

• •

SECTION 7 A 'fACHMENT 4

1 DiSC