ML073111446

EP-1.43A+B, Nasa, Survey Unit Release Record

ML073111446
Person / Time
Site:	Plum Brook
Issue date:	10/31/2007
From:	US National Aeronautics & Space Admin (NASA)
To:	NRC/RGN-III/DNMS/DB
References
EP-1.43A+B
Download: ML073111446 (13)

Text

I Survey Unit Release Record I Design # Survey Unit #(s) Description 1) Embedded Pipe (EP) Survey Unit 1.43A+B meets the definition of embedded pipe for Plum Brook Reactor Facility (PBRF). EP-1.43A+B

2) EP 1.43A+B 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 1.43A+B were performed using a scintillation detector optimized to measure gamma energies representative of Co-60. Sample

1. EP3- 1 from Survey Request (SR)-13 was referenced for this decision.

Revision # 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 BSIfLVS-002, WEP 05-006, these determinations are appropriate for the types of radiation involved and the media being suveyed. Original a FS SIC haracterization Engineer Page 1 of 3 I Approval Signatures

-u - FSS Design # EP 1.43A+B Survey Unit: 1.43A+B 1.0 History/Description 1.1 The subject pipe system is the 6" pipe system with 4" couplings, the system was accessed fiom the ring header in Quad A.

1.2 EP 1.43A+B consists of 6" diameter piping that is approximately 24 feet in length. 2.0 Survey Design Information 2.1 EP 1.43A+B was surveyed IAW Procedure

1. BSI/L,VS-002.

2.2 100% of the 6" ID pipe was accessible for survey. The accessible 6" ID pipe was surveyed by static measurement at one foot increments, for a total of 24 survey measurements.

2.3 Surface area for the 6" ID piping is 1,459 cm2 for each foot of piping, corresponding to a total 6" ID piping surface area of 35,024 cm2 (3.5 m2) for the entire length of (approximately 24')

of 6" piping. Since the system also contained 4" diameter coupling sections, this estimate is believed to slightly overstate the actual surface area. Survey Unit Measurement LocationslData 3.1 Pipe interior radiological survey forms are provided in Attachment 2 of this release record. Survey Unit Investigations/Results 4.1 None Data Assessment Results 5.1 Data assessment results are provided in the EPIBuried 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 mrerntyr 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 1.43A+B passes FSS.

5.4 Background was not subtracted fiom the survey measurements and the Elevated Measurement Comparison (EMC) was not employed for this survey unit.

5.5 Although both 4" and 6" diameter piping were surveyed, the actual piping ID associated with each individual measurement was not specified in the survey documentation.

To compensate for this, the most conservative combination of detector geometry-efficiency was applied. For each measurement, this process was carried out by dividing the raw counts per minute by the efficiency value associated with the 6" ID pipe to determine Revision # Original Page 2 of 3 FSS Design # EP 1.43A+B Survey Unit: 1.43A+B the total Co-60 activity per foot of piping. These values were then divided by the 4" ID geometry factor to determine the area activity in dprn1100 2 cm . 5.6 Statistical Summary Table 6.0 Documentation of evaluations pertaining to compliance with the unrestricted use limit of 25 mrernfyr and dose contributions fiom 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 1.43A+B to be less than 1 mredyr. The dose contribution is estimated to be 0.261 mredyr based on the average of the actual gross counts measured.

7.0 Attachments Attachment 1 - BSI EP/BP Survey Report Attachment 2 - Pipe Interior Radiological Survey Form Attachment 3 - DQA Worksheet Attachment 4 -Disc containing RR for EP 1.43A+B & Spreadsheet Revision # Original Page 3 of 3 SECTION 7 ATTACHMENT 1

BSI EPIBP SURVEY REPORT TlVlTY VALUES NOT BACKGROUND CORRECTED RP Engineer I Date EP 1.43A+B 4", 6" Pipe TBD 06-004 Group 1 SECTION 7 ATTACHMENT 2 g PAGE(S)

BSIILVSPipeCrawler-002 Revision 4 Pipe Interior Radiological Survey Form Date: /~/Z/OG Time: I Pipe ID#: / , 4- 3 g* Pipe Diameter: -m 5 P Access Point Area: u*,, #- Building:

y' Elevation: -IS' System: - Type of Survey Investigation Characterization Final Survey Other Gross C06O Cs Detector ID# / Sled ID# # -159 23% 36 7 1 / 0 / Detector Cal Date: 6 /z/ /D 6 Detector Cal Due Date: L/L~ 07 Instrument:

23 bT- Instrument ID

1. 203- Instrument Cal Date: 7!</0 C Instrument Cal Due Date: 7/ >-/a 7 From the Daily Pipe Survey Detector Control Form for the Selected Detector Background Value 3 cpm - - Efficiency Factor for Pipe Diameter @ . 0 00 79 (fi-om detector efficiency determination)

MDCstatic

'

• 86 ' ~~(if~fadjust sample count time and recalculate MDCktatic)

Is the MDCsbtic acceptable?

Comments:

mjy m,jm ow &P3-/ rn~P~r3irr:

1,43g We P&Y~MY L~P Technician Signature Pipe Interior Radiological Survey REFERENCE COPY Package Page 1 of 5 Attachment 3,'~age 1 BSYLVSPipeCrawler-002 Revision 5 Pipe Interior Radiological Survey Form (Continuation Form) . . Date: / O/L%/DL Pipe ID#: /,43 A Pipe Diameter: Access Point Area:

Building:

ILV Elevation:

-/.GI System: REFERENCE COPY . - Package Page 2 of 2 Attachment 3, Page 2

SECTION 7 ATTACHMENT 3 1 PAGE(S)

DQA Check Sheet Design # EP 1.43A+B Revision # Original Sunrey Unit # EP 1.43A+B Preliminary Data Review' Answers to the following questions should be fully documented in the Survey Unit Release Record Yes No N/A 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 survey units, or below 0.5 DCGLw for Class 3 survey units? X 3. Is the instrumentation MDC for embeddedlburied piping static measurements below the DCGh ? X 4. Was the instrumentation MDC for structure scan measurements, soil scan measurements, and embeddedlburied piping scan measurements below the DCGh, or, if not, was the need for additional X static measurements or soil samples addressed in the survey design? 5. Was the instrumentation MDC for volumetric measurements and smear analysis < 10% DCGLw ? X 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?

X 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 the radiological status of the facility?

X Graphical Data Review

1. Has a posting plot been created? X 2. Has a histogram (or other frequency plot) been created? X 3. Have other graphical data tools been created to assist in analyzing the data? X Data Analysis 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

< DCGh? X 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)? X 4. Is the result of the Elevated Measurements Test

< 1 .O? X 5. Is the result of the statistical test (S+ for Sign Test or Wr for WRS Test) 1 the critical value? X Comments:

Page 1 of 1 SECTION 7 ATTACHMENT 4 1 DISC