ML073400156

EP-RX-116, Nasa, Survey Unit Release Record

ML073400156
Person / Time
Site:	Plum Brook  File:National Aeronautics and Space Administration icon.png
Issue date:	11/29/2007
From:	US National Aeronautics & Space Admin (NASA)
To:	NRC/RGN-III/DNMS/DB
References
EP-RX-116
Download: ML073400156 (12)

Text

I Survey Unit Release Record I

I Design #

I EP-Rx 116 1

Revision #

/

Original I Page 1 of 3 I

Survey Unit #(s)

Description

1) Embedded Pipe (EP) Survey Unit Rx 116 meets the definition of embedded pipe for Plum Brook Reactor Facility (PBRF).

2) EP Rx 1 16 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 Rx 11 6 were performed using a scintillation detector optimized to measure gamma energies representative of Co-60. Sample #EP 2-3 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 (JAW) 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 BSULVS-002, WEP 05-006, these determinations are appropriate for the types of radiation involved and the media being surveyed.

FSSICharacterization Manager CS-0911 Approval Signatures a

Date:

FSS Design # EP Rx 116 Revision # Original Page 2 of 3 Survey Unit: Rx 116 1.0 History/Description 1.1 The subject pipe system is an 8 cooling supply line located on the quad D vessel wall at the -24 el. of the Rx building.

1.2 EP Rx 116 consists of 8 diameter piping that is approximately 3 feet in length.

2.0 Survey Design Information 2.1 EP Rx 116 was surveyed IAW Procedure #BSI/LVS-002.

2.2 100% of the 8 ID pipe was accessible for survey. The accessible 8 ID pipe was surveyed by static measurement at one foot increments, for a total of 3 survey measurements.

2.3 The total surface area for the 8 ID piping is 5,873 cm2 (0.6 m2) for the entire length of (approximately 3) of 8 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 1.

5.2 All 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.

5.3 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 Rx 116 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.

FSS Design # EP Rx 116 Revision # Original Page 3 of 3 Survey Unit: Rx 116 5.5 Statistical Summary Table Statistical Parameter 8

Pipe Total Number of Survey Measurements 3

Number of Measurements >MDC 3

Number of Measurements Above 50% of DCGL 0

Number of Measurements Above DCGL 0

Mean 0.1549 Median 0.1294 Standard Deviation 0.0826 Maximum 0.2472 Minimum 0.0880 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 Rx 116 to be less than 1 mrem/yr. The dose contribution is estimated to be 0.155 mrem/yr based on the average of the actual gross counts measured.

7.0 Attachments - BSI EP/BP Survey Report - Pipe Interior Radiological Survey Form - DQA Worksheet -Disc containing RR for EP Rx 116 & Spreadsheet

SECTION 7 ATTACHMENT 1 2

PAGE(S)

BSI EPlBP SURVEY REPORT Detector-Sled #

IMGI LVS-11106 LUESNOTBACKGROUNDCORRECTED RP Engineer / Date

EP Rx 116 8" Pipe TBD 06-004 Group 2 Measurement #

gcpm ncpm Co-60 activity (total dpm)

Co-60 activity (dpm/100cm2)

Cs-137 activity (dpm/100cm2)

Eu-152 activity (dpm/100cm2)

Eu-154 activity (dpm/100cm2)

Nb-94 activity (dpm/100cm2)

Ag-108m activity (dpm/100cm2)

Unity 1

233 233 1,109,524 57,023 29,568 473 334 28 1,641 0.247 2

83 83 395,238 20,313 10,533 168 119 10 585 0.088 3

122 122 580,952 29,857 15,482 248 175 15 859 0.129 MEAN 0.155 MEDIAN 0.129 STD DEV 0.083 MAX 0.247 MIN 0.088 1 of 1

SECTION 7 ATTACHMENT 2 z PAGE(S)

BSvLvsPipeCmwkr-002 Revision 5 Pipe Zgtepiov Radialogicat &uwy Form Dete:

// :a6. fl Time:

139'7 Y

~rpem#: RY fib Pipe Diameter.

Access Poi& Area: QLI@ '2 1

Building: i?f QUAD "D' Bevation:

System:

IM I

I Ch-Type of Survey Inv&gffim m

Find Snrvey f o w w i r Gross Co60 J Cs net&

ID# I SI&ID#

1 m G 1 /LVY-1

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106 Detector Cal Date:

f.11 07 Detector Cd Due Date:

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~nsmenr:

J3'5 - I rl~~tmm&rnk l80q'f Instrument Cal Date:

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• 1 a fl Instrument Cal h e Date:

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From the Daily Pipe Survey Detector Control Form for the Selected Detector Background Value 3.5 cpm M D C k C i4.4 C P ~

Efficiency Factor for Pipe Diameter 0,00 02 /

(&om detector efficiency d e t m t i o n )

MDCsfatic Z

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Z dpm/

O D cmZ 1s t h e l ~ ~ ~ ~ ~ ~ ~, x c e p t a b k ?

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(if na, a d p i sample cauntlime and m u l a t e MDc&.*)

Commegts:

&Jf+7 CIN4 sc?e 6hf Lk7.F - 4 & //

2' 7 Technician Signature Pipe Interior Radiological Survey

SECTION 7 ATTACHMENT 3 I

PAGE(S)

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I I,'

DQA Check Sheet f

i '

I Design #

I Rx 116

/ Revision # 1 Original

/

I I -

Preliminary Data ~ 6 v i e w.

- 1 I

Answers to the following questions should be fully documented in Ute Survey Unit Release Record Yes No N/A 1 1.

Have surveys been ~rformed in accorclance with survsv instructions in the Survev Des~sn?

I X. I I

1

2.

Is the instrumentation MDC for structure static measurements below the DCGLw for Class 1 and 2 I survev units. or below 0 5 DCGLW for Class 3 survev unds?

1 3.

Is the instrumentation MDC forembeddedhuried piping static measurements below the DCGLw ?

1 X I I

1

4. Was the instrunentabon MDC for structLre scan measurements, so:l scan measurements, and I embedded/b~ried piping scan measurements below the DCGLn or, if not, was the need for addlional I

I 1 x 1 static measureme& oisoil samples addressed in the survey design?

5.

Was the instrumentation MDC for volumetric measurements and smear analvsis < 10% DCGLW ?

I X

6,?

6.

Were the MDCs and assumptions used to develop them appmpriate for the instruments and techniques L~

used to perform the survey?

. x.

7. Were the Survey methods used to collect data proper for the types of radiation involved and for the

,.i media being surveyed?

. x

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8.

Were "Special Methods" for data collection properly applied for the survey unit under review?

X'

9.

Is the data set comprised of qualified measurement results collected in accordance with the survey design, which accurately reflects Me radiological status of the facility?

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Has a posting lot been created?

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Has a histoaram (or other freouencv lot) been created?

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Have otherara~hical data tools been mated to assist in analvzino the data?

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Are all sample measurements below the DCGLw (Class 1 8 2). or 0.5 DCGLw (Class 3)?

X

2.

Is the mean of the sample data < DCGLw?

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3.

If elevated areas have been identified by scans andlor sampling, is the average activity in each elevated area < DCGLEMC (Class 1). < DCGLw (Class 2), or ~ 0. 5 DCGLw (Class 3)?

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4.

Is the result of the Elevated Measurements Test < 1.O?

X 1 5.

Is the result of the stattstical test (S+ for Sisn Test or W, for WRS Test) > the critical value?

I

- I 1 x 1 I

Comments:

Page 1 of 1

SECTION 7 ATTACHMENT 4 1 DISC