ML081330329

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Survey Unit Release Record - EP-RD-1, Rev 1
ML081330329
Person / Time
Site: Plum Brook  File:National Aeronautics and Space Administration icon.png
Issue date: 05/07/2008
From: Case R, Wood G
US National Aeronautics & Space Admin (NASA), John H. Glenn Research Ctr at Lewis Field
To:
NRC/RGN-III
References
EP-RD-1, Rev 1
Download: ML081330329 (15)
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{{#Wiki_filter:* Survey Unit Release Record Design # EP-RD-l Revision # 1 Page 1 of 3 Survey Unit #(s) RD-l Description I) Embedded Pipe (EP) Survey Unit RD-I was remediated and surveyed in December of2007 as Embedded Pipe, at that time meeting the definition of embedded pipe as per the PBRF Final Status Survey Plan (FSSP). All measurement results were less than the Derived Concentration Guideline Level (DCGL) for radionuclide specific EP that corresponds to the I mrem/yr dose goal established in Table 3-3 of the FSSP. This survey was documented in Revision oof this Release Record.

2) Since December of2007, the envisioned end-state configuration of the Primary Pump House (PPH) was revised. Subsequently, the portions ofEmbedded Pipe (EP) Survey Unit RD-l which transits in soil under and between the buildings no longer meets the criteria for embedded piping. The portions of Embedded Pipe (EP) Survey Unit RD-J that are embedded in the building foundation walls (PPH and Hot Pipe Tunnel) remain classified as embedded pipe.
3) This FSS survey documented in Revision I of this release record was performed after the performance of additional remediation to this system. Upon demonstration of compliance with the release criteria, the complete piping system will be grouted, including the portions embedded in the building structure that will remain embedded for any future reuse and those portions in the ground that can be released for unrestricted use.
4) EP RD-l is a Class I, Group I survey unit as per the PBRF Final Status Survey Plan (FSSP) and Technical Basis Document (TBD)-06-004.
5) Surveys in EP RD-I were performed using a scintillation detector optimized to measure gamma energies representative ofCo-60. Sample #EP 3-7 from Survey Request (SR)-13 was referenced for this decision.
6) Survey Instructions for this survey unit are incorporated into and performed in accordance with (lAW) the Babcock Services Incorporated (BSI)ILVS-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.
7) Instrument efficiency determinations are developed in accordance with the BSIILVS-002, WEP 05-006, these determinations are appropriate for the types of radiation involved and the media being surveyed.

Approval Signatures Date: FSS/Characterization Engineer FSS/Characterization Manager Form CS-09/1 Rev 0

.~~ FSS Design # EP RD-1 I Revision # 1 -I Page 2 of3 Survey Unit: RD-1 1.0 HistorylDescription 1.1 The subject pipe system is a 4" line running from the Resin Pit -10'. 1.2 EP RD-1 consists of 4" diameter piping that is approximately 20 feet in length. 2.0 Survey Design Information 2.1 EP RD-1 was surveyed lAW Procedure #BSI/LVS-002. 2.2 100% of the 4" 10 pipe was accessible for survey. The accessible 4" 10 pipe was surveyed by static measurement at one foot increments, for a total of 20 survey measurements. 2.3 Surface area for the 4" 10 piping is 973 cm2 for each foot of pi~ing, corresponding to a total 4" 10 piping surface area of 19460 cm (1.9 m2) for the entire length of (approximately 20') of 4" piping.. 3.0 Survey Unit Measurement LocationslData 3.1 Pipe interior radiological survey forms 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 (l1,000dpm/l00cm 2). 5.3 When implementing the Unity Rule, provided in Section 3.6.3 of the FSSP, one survey measurement exceeded unity. The survey unit that is constituted by EP RD-1 passes FSS after application of Elevated Measurement Comparisons (EMC) and Elevated Measurement Tests (EMT). The EMC Unity sum was 0.026 of unity, and the EMT Unity sum was 0.627 of unity. 5.4 DCGL's for the building reuse scenario are used to demonstrate compliance with the release 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. 5.6 Background was not subtracted from the survey measurements.

FSS Design # EP RD-1 I Revision # 1 Page 3 of3 I Survey Unit: RD-1 5.7 Statistical Summary Table Statistical Parameter Totall\\lumber of Survey Measurements Number of Measurements >MDC Number of Measurements Above 50% of DCGL Number of Measurements Above DCGL Mean Median Standard Deviation Maximum Minimum 4" Pipe 20 20 16 1 0.641 0.635 0.191 1.030 0.311 6.0 Docwnentation 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 RD-I to be less than 25 rnrem/yr. The dose contribution is estimated to be 16.0 rnrem/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 RD-1 & Spreadsheet

SECTION 7 ATTACHMENT 1 2 PAGES

llilJIt BSI EP/BP SURVEY REPORT Pipe 10 RD-1 Survey Location RESIN PIT Survey Date 14-Apr-08 2350-1 # 203438 Survey Time See Survey Sheets Detector-5led # LVS1 -101 Pipe Size 4" Detector Efficiency 0.00039 DCGL (dpm/l00cm21 1.10E+04 Pipe Area Incorporated by Detector Efficiency (In cm21 973 Plpc Area Incorporated by 1.9 Field BKG (CjlfT1) 2.8 Survey Data (ml ) Routine Survey X Field MDCR (opm) 9.0 QA Survey Nominal MDC (dpml1000m2) 2.366 Survey Measurement Results Total Number of Survey Measurements 20 Number of Measurements >MDC 20 Number of Measurements Above 50% DCGL 16 Number of Measurements Above DCGL 1 Mean 0.641 Median 0.635 Standard Deviation 0.191 Maximum 1.030 Minimum 0.311 PHELPS Survey Technician(s) Survey Unit Classification 1 TBD 06-004 Piping Group 1 SR-13 Radionuclide Distribution Sample EP 3-7 Measured Nuclide Co-60 Area Factor/EMC Used Yes Pass/Fail FSS Pass MREMNR Contribution <25 COMMENTS: ACTIVITY VALUES NOT BACKGROUND CORRECTED RP Engineer I Date Du~ /<5-5-7) 8 ./

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I- ~ I I i Co-50 Co-50 EMC activity EMT I activity ncpm Unity Unity Unity (total dpm) (dPm~1)oocm 0.575 0.575 ?.'3~?._ 0_575 6,325 0.575 0_815 0.815 ~~60 0.575 6,325 0.575 7,115 0.647 0.647 0.623 0.623 ~~~2 0.767 _8,i.33 _ 0.767 -f 0.743 31 0.743 79,~87 8,169 26 0.623 0.623 66,667t 6,852 1.030 0.026 43 ~0,256 11 ~~_~.? 0.982 0.982 41 105,12~ 19!805 0.719 30 76,923 !,906 _ 0.719 -f------- I 0.791 0791 ~L _84,615 8,696 0.671 28 71,795 7,379 0.671 0.407 0.407 ~c-43,590 ~I 4,480 0.695 0.695 ?.9 74,3~_9 7,642 0.311 0.311 0.455 0.455 1:; -;N~~ }~~~ 0.503 0.503 21 53,846 5,534 -~ 0.311 0.311 13_~ ~3,33}_ ~~6 0.627 5,402 0.026 EMT EMC MEAN 0.641 Unity Unity - I MEDIAN 0.635 STD DEV 0.191

MAX 1.030 i'MIN 0.311 1 of 1

SECTION 7 ATTACHMENT 2 5 PAGES

BSIJLVSPipeCrawler-002 Revision 6 Pipe Interior Radiological Survey Form Date: lJ-Il-{* err Time: 10 (J5-- LJ Pipe ID#: Pipe Diameter: I( t\\ 0-1 Access Point Area: Res:" Of'cf,'" Sl.f "1 P Building: .11/(4 Elevation: 't{ System: .....;.I<...L..>oC:Do--- Type of Survey Investigation Characterization Final Survey -&- Other v= Gross Co60./ Cs Detector ID# I Sled ID# ~ V 5- ( I I () {

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Detector Cal Date: I, J.S.0 r Detector Cal Due Date: Instrument: Instrument ill #: ffoie5 cJ -I. Instrument Cal Date: ~ ( '7. LOr (6 JF Instrument Cal Due Date: ()7 From the Daily Pipe Survey Detector Control Fonn for the Selected Detector Background Value J. 1 cpm MDCRstatic 4 cpm Efficiency Factor for Pipe Diameter 0 {) 0031 (from detector efficiency detennination) I 2 MDCstatic 2,31.o LP dpm/ l ()D cm Is the MDCstatic acceptable? ~ No (if no, adjust sample count time and rec~lculate MDCRstatic) Cormnents: S((IV" lJ ey ec/ +"'- '?, !J {0rt? \\VI Rvn. (; Fa r\\ f< (J ~ I Technician Signature Pipe Interior Radiological Survey Position Feet into Pipe from Opening Count Time (min) Gross Counts Gross c13m Net cpm dprn/100cm2 I 1 I fJ ItdoO I I 3 i3 2 J. {j (Obi I I 1 I 4 3 ~ (J (Jp r .2l

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SECTION? ATTACHMENT 3 1 PAGE

DQA Check Sheet Design # EP RD-1 I Revision # 1 I I Survey Unit # EP RD-1 Preliminary Data Review' Answers to the following questions should be fully documented in the Survey Unit Yes No N/A Release Record

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 survey units, or below 0.5 DCGLw for Class 3 survey units? X

3.

Is the instrumentation MDC for embedded/buried 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 X static measurements or soil samples addressed in the survey design? X

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 X 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? X

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 X design, which accurately reflects the radiological status of the facility? Graphical Data Review X

1.

Has a posting plot been created? X

2.

Has a histogram (or other frequency plot) been created? X Data Analysis

3.

Have other graphical data tools been created to assist in analyzing the data? X

1.

Are all sample measurements below the DCGLw (Class 1 & 2), or 0.5 DCGLw (Class 3)? X

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 X elevated area < DCGLEMC (Class 1), < DCGLw (Class 2), or <0.5 DCGLw (Class 3)? X

4.

Is the result of the Elevated Measurements Test < 1.0? X

5.

Is the result of the statistical test (5+ for Sign Test or W, for WRS Test).::: the critical value? Comments: See Section 5 Date FSS/Characterization Engineer (prinUsign) Sh/V% &I-WeeJ) jLiAkQ Date FSS/ Characterization Manager (prinUsign) tJ!7fctt R. Case 1t7~ Fonn CS-09/2 Page 1 of 1 RevO

SECTION 7 ATTACHMENT 4 1 DISC}}

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