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{{#Wiki_filter:Survey Unit Release Record Design # Snwey Unit #(s) Description FSSICharacterization Manager EP-Rx 126D Rx 126D 1) Embedded Pipe (EP) Survey Unit Rx 126D meets the definition of embedded pipe for Plum Brook Reactor Facility (PBRF). 2) EP Rx 126D 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 126D were performed using a scintillation detector optimized to measure gamma energies representative of Cd. Sample #EP2- 2 fiom Survey Request (SR)-13 was referenced for this decision.
{{#Wiki_filter:Survey Unit Release Record Design #             EP-Rx 126D        Revision #          Original      Page 1 of 3 Snwey Unit #(s)                                           Rx 126D
: 4) Survey Instructions for this survey unit are incorporated into and performed in accordance with (IAW) 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.
: 1) Embedded Pipe (EP) Survey Unit Rx 126D meets the definition of embedded pipe for Plum Brook Reactor Facility (PBRF).
: 2) EP Rx 126D 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 126D were performed using a scintillation detector optimized to measure gamma energies representative of C d . Sample #EP2-2 fiom Survey Request (SR)-13 was referenced for this decision.
: 4) Survey Instructions for this survey unit are incorporated into and performed in accordance with (IAW) the Babcock Services Incorporated (BSI)/LVS-002, Work Execution Package (WEP) 05-006. Survey instructions described in this Description 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 BSVLVS-002, WEP 05-006, these determinations are appropriate for the types of radiation involved and the media being surveyed.
: 5) Instrument efficiency determinations are developed in accordance with the BSVLVS-002, WEP 05-006, these determinations are appropriate for the types of radiation involved and the media being surveyed.
Revision # Original Page 1 of 3 
FSSICharacterization Manager
, FSS Design # EP Rx 126D Survey Unit Rx 126D 1.0 HistoryDescription 1 1 The subject pipe system is the 0.75" drain located in room 22 of the Rx building.
 
1 2 EP Rx 126D consists of 0 75" diameter piping that is approximately 15 feet in length 2.0 Survey Design Information 2.1 EP Rx 126D was surveyed IAW Procedure  
                          ,
#BSI/LVS-002.
FSS Design # EP Rx 126D             Revision # Original                  Page 2 of 3 Survey Unit Rx 126D 1.0   HistoryDescription 11    The subject pipe system is the 0.75" drain located in room 22 of the Rx building.
2.2 1W? of the 0.75" ID pipe was accessible for survey The accessible 0.75" ID pipe was surveyed by static measurement at one foot increments, for a total of 15 survey measurements. 2 3 Surface area for the 0.75" ID piping is 182 cm2for each foot of pi in& P corresponding to a total 0.75" ID piping surface area of 2,736 cm (0.3 m2) for the entire length of (approximately 15') of 0 75" piping. 3.0 Survey Unit Measurement LocationslData 3 1 Pipe interior radiological survey forms ate provided in Attachment 2 of this release record.
12    EP Rx 126D consists of 0 75" diameter piping that is approximately 15 feet in length 2.0   Survey Design Information 2.1   EP Rx 126D was surveyed IAW Procedure #BSI/LVS-002.
4.0 Survey Unit InvestigatiodResults 4.1 None 5.0 Data Assessment Results 5.1 Data assessment results are provided in the EPtBuried Pipe (BP) Survey Report provided in Attachment
2.2     1 W ?of the 0.75" ID pipe was accessible for survey The accessible 0.75" ID pipe was surveyed by static measurement at one foot increments, for a total of 15 survey measurements.
: 1. 5 2 All measurement results are less than the Derived Concentration Guideline Level (DCGL) for radionuclide specific EP that corresponds to the 1 mreidy-r 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 0, provided in TBD-06-004, the survey unit that is constituted by EP Rx 126D passes FSS. 5.4 Background was not subtracted  
23    Surface area for the 0.75" ID piping is 182 cm2foreach foot of pi in&
&om the survey measurements and the Elevated Measurement Comparison (EMC) was not employed for this survey unit Revision # Original Page 2 of 3 Statistical Parameter . . - FSS Design  
P corresponding to a total 0.75" ID piping surface area of 2,736 cm (0.3 m2) for the entire length of (approximately 15') of 0 75" piping.
# EP Rx 126D Survey Unit: Rx 126D 5.5 Statistical Summary Table 6.0 Documentation of evaluations pertaining to compliance with the. unrestricted use limit of 25 mremlyr and dose contributions from Embedded Pipe and radionuclides contributing 100/o 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 126D to be less than 1 mremlyr. The dose contribution is estimated to be 0.038 mrem/yr based on the average of the actual gross counts measured.
3.0   Survey Unit Measurement LocationslData 3 1 Pipe interior radiological survey forms ate provided in Attachment 2 of this release record.
7.0 Attachments Attachment 1 - BSI EPBP Survey Report Attachment 2 -Pipe Interior Radiological Survey Form Attachment 3 - DQA Worksheet Attachment 4 -Disc containing RR for EP Rx 126D & Spreadsheet Revision # Original Page 3 of 3 SECTION 7 ATTACHMENT 1 z PAGE(S)
4.0   Survey Unit InvestigatiodResults 4.1   None 5.0   Data Assessment Results 5.1   Data assessment results are provided in the EPtBuried Pipe (BP) Survey Report provided in Attachment 1.
BSI EPlBP SURVEY REPORT FOll.5L-X 00471 no sled Number of Measurements Abanre DCGL Survey Technician(s)
52    All measurement results are less than the Derived Concentration Guideline Level (DCGL) for radionuclide specific EP that corresponds to the 1 mreidy-r dose goal established in Table 3-3 of the FSSP.
TBD 06-004 Piping Gmup SR-13 Radionudii Di6bibution Sample Measured Nuclide Area FaotorlEMC Used PassFaa FSS MREMNR Contribution 2 EP 2 COa, No Pass <1 COMMENTS:
5.3   When implementing the Unity Rule, provided in Section 3.6.3 of the FSSP, and applying the Nuclide Fraction 0,     provided in TBD-06-004, the survey unit that is constituted by EP Rx 126D passes FSS.
ACTIVITY VALUES NOT BACKGROUND CORRECTED RP Engineer I Date I DJ /o-2s-07 <
5.4   Background was not subtracted &omthe survey measurements and the Elevated Measurement Comparison (EMC) was not employed for this survey unit
EP Rx 126D 0.75" Pipe TBD 06-004 Group 2 SECTION 7 ATTACHMENT 2 z PAGE(S)
 
/ BSYLVSPipeCrawler-002 Revision 4 Pipe Interior Radiological Survey Form Date: 31 1 2 /07 Time: /3 SO Pipe ID#: & 126 D Pipe Diameter:  
                          ..                                       -
#?sf' Access Point Area: & 2 Z TlZffM Building:  
FSS Design # EP Rx 126D           Revision # Original                    Page 3 of 3 Survey Unit: Rx 126D 5.5     Statistical Summary Table Statistical Parameter 6.0   Documentation of evaluations pertaining to compliance with the. unrestricted use limit of 25 mremlyr and dose contributions from Embedded Pipe and radionuclides contributing 100/oin aggregate of the total dose for both structural scenarios and soils.
? Elevation:  
6.1     A review of the survey results has shown that the dose contribution for EP Rx 126D to be less than 1 mremlyr. The dose contribution is estimated to be 0.038 mrem/yr based on the average of the actual gross counts measured.
-2 7 I System: &/WE ~R~P//I/ Type of Survey Investigation Characterization Final Survey p Other / Gross C06O r/ Cs hk Detector ID# / Sled ID# /I L- ~047 1 AID SLED l Detector Cal Date: 111( 107 Detector Cal Due Date: r I/ ok Instrument:
7.0   Attachments Attachment 1 - BSI EPBP Survey Report Attachment 2 -Pipe Interior Radiological Survey Form Attachment 3 - DQA Worksheet Attachment 4 -Disc containing RR for EP Rx 126D & Spreadsheet
23fOH/ Instrument ID #: 189094t Instrument Gal Date: /-/I -0 7 Instrument Cal Due Date: 14- 0 r+ From the Daily Pipe Survey Detector Control Form for the Selected Detector Background Value 6 , I cpm lr .C MDcktatic CPm Efficiency Factor for Pipe Diameter 0 . 0 00 bq (fiom detector efficiency determination)
 
MDcstatii, 480s' Is the MDCstatic acceptable?  
SECTION 7 ATTACHMENT 1 z PAGE(S)
&&(if:fadjist sample count time and recalculate MOCE&,tic) - I?/% 5 EPZ-'2, Comments:
 
19lz~lZV C LvtPLrz~.
BSI EPlBP SURVEY REPORT FOll.5L-X 00471 no sled Number of MeasurementsAbanre DCGL Survey Technician(s)
Pipe Interior Radiological Survey Attachment 3, Page 1 BSYLVSPipeCrawler-002 Revision 4 Pipe Interior Radiological Survey Form (Continuation Form) Pipe Diameter:
TBD 06-004 Piping Gmup                 2 SR-13 Radionudii Di6bibution Sample         EP 2-2          -
WZS" Access Point Area: & 22 p~d Elevation: - 27 I System: I (5 ~~ZJCI~ Package Page 3 Attachment 3, Page 2
Measured Nuclide                 COa, Area FaotorlEMC Used                 No PassFaa FSS                     Pass MREMNR Contribution                   <1 COMMENTS:
ACTIVITY VALUES NOT BACKGROUND CORRECTED
<
RP Engineer I Date I DJ           /o-2s-07
 
EP Rx 126D 0.75" Pipe TBD 06-004 Group 2
 
SECTION 7 ATTACHMENT 2 z PAGE(S)
 
                                                                                  /
BSYLVSPipeCrawler-002 Revision 4 Pipe Interior Radiological Survey Form Date:       31 1 2 /07                 Time:           /3SO Pipe ID#:     & 126 D               Pipe Diameter:       #?sf'           Access Point Area: & 2 Z T l Z f f M Building:       ?                     Elevation:         -2 7 I                 System:         &/WE ~ R ~ P / / I /
Type of Survey     Investigation           Characterization         Final Survey     p       Other
                                                                                                          /
Gross                               C06O   r/                           Cs hk Detector ID# / Sled ID#           / I   L     - ~ 0 4 71            AID     SLED l
Detector Cal Date:           111(1 0 7              Detector Cal Due Date:             r   I/ o k Instrument:           23fOH/                         Instrument ID #:             189094t Instrument Gal Date:         / - / I -0 7             Instrument Cal Due Date:         1 4 - 0 r+
From the Daily Pipe Survey Detector Control Form for the Selected Detector Background Value         6 , I cpm MDcktatic        l r .C             CPm Efficiency Factor for Pipe Diameter 0 0 0 0 bq.                (fiom detector efficiency determination)
MDcstatii,         480s' Is the MDCstaticacceptable? &&(if:fadjist
                                    -
sample count time and recalculate MOCE&,tic)
Comments:            I?/%           51 9 l z ~ l Z V E P Z - ' 2 ,                                         LvtPLrz~.
C Pipe Interior Radiological Survey Attachment 3, Page 1
 
BSYLVSPipeCrawler-002 Revision 4 Pipe Interior Radiological Survey Form (Continuation Form)
Pipe Diameter:     WZS"     Access Point Area:   & 22   p ~ d Elevation:       - 27 I       System:       I ( 5 ~ ~ Z J C I ~
Package Page       3 Attachment 3, Page 2


SECTION 7 ATTACHMENT 3 I PAGE(S)
SECTION 7 ATTACHMENT 3 I PAGE(S)
DQA Check Sheet Design # Rx 126D Revision # Original Survey Unit  
 
# Rx 126D 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?
DQA Check Sheet Design #             Rx 126D           Revision #       Original Survey Unit #                                                         Rx 126D Preliminary Data Review' Answers to the following questions should be fully documented in the Survey Unit Release Record Yes No   N/A
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 DCGLw ? X 4. Was the instrumentation MDC for structure scan measurements, soil scan measurements, and embeddedfburied 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?
: 1. Have surveys been performed in accordance with survey instructions in the Survey Design?             X
: 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?
: 2. Is the instrumentation MDC for structure static measurements below the DCGLWfor Class 1 and 2                 X survey units, or below 0.5 DCGLw for Class 3 survey units?
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 facilltp 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 < DCGLw? X 3. If elevated areas have been identified by scans andlor sampling, is the average activity in each elevated area < DCGk (Class I), c DCGLW (Class 2), or e0.5 DCGLw (Class 3)?
: 3. Is the instrumentation MDC for embeddedlburied piping static measurements below the DCGLw ?         X
X 4. Is the result of the Elevated Measurements Test  
: 4. Was the instrumentation MDC for structure scan measurements, soil scan measurements, and embeddedfburied 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?
< 1 .O? X 5. Is the result of the statistical test (S+ for Sign Test or Wr for WRS Test) 2 the critical value?
: 5. Was the instrumentation MDC for volumetric measurements and smear analysis < 10% DCGLw ?                       X
X Comments:
: 6. Were the MDCs and assumptions used to develop them appropriate for the instruments and techniques used to perform the survey?
CS-0912 Page 1 of 1 SECTION 7 ATTACHMENT 4 1 DISC}}
: 7. Were the survey methods used to collect data proper for the types of radiation involved and for the X
media being surveyed?
: 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 X
design, which accurately reflects the radiological status of the facilltp 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 < DCGLw?                                                             X
: 3. If elevated areas have been identified by scans andlor sampling, is the average activity in each X
elevated area < D C G k (Class I), c DCGLW(Class 2), or e0.5 DCGLw (Class 3)?
: 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) 2 the critical value?               X Comments:
CS-0912 Page 1 of 1
 
SECTION 7 ATTACHMENT 4 1 DISC}}

Revision as of 01:45, 23 November 2019

Survey Unit Release Record EP Rx 126D
ML073170339
Person / Time
Site: Plum Brook
Issue date: 10/31/2007
From: Randall D
US National Aeronautics & Space Admin (NASA)
To:
NRC/RGN-III/DNMS/DB
References
EP Rx 126D
Download: ML073170339 (13)


Text

Survey Unit Release Record Design # EP-Rx 126D Revision # Original Page 1 of 3 Snwey Unit #(s) Rx 126D

1) Embedded Pipe (EP) Survey Unit Rx 126D meets the definition of embedded pipe for Plum Brook Reactor Facility (PBRF).
2) EP Rx 126D 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 126D were performed using a scintillation detector optimized to measure gamma energies representative of C d . Sample #EP2-2 fiom Survey Request (SR)-13 was referenced for this decision.
4) Survey Instructions for this survey unit are incorporated into and performed in accordance with (IAW) the Babcock Services Incorporated (BSI)/LVS-002, Work Execution Package (WEP)05-006. Survey instructions described in this Description 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 BSVLVS-002, WEP 05-006, these determinations are appropriate for the types of radiation involved and the media being surveyed.

FSSICharacterization Manager

,

FSS Design # EP Rx 126D Revision # Original Page 2 of 3 Survey Unit Rx 126D 1.0 HistoryDescription 11 The subject pipe system is the 0.75" drain located in room 22 of the Rx building.

12 EP Rx 126D consists of 0 75" diameter piping that is approximately 15 feet in length 2.0 Survey Design Information 2.1 EP Rx 126D was surveyed IAW Procedure #BSI/LVS-002.

2.2 1 W ?of the 0.75" ID pipe was accessible for survey The accessible 0.75" ID pipe was surveyed by static measurement at one foot increments, for a total of 15 survey measurements.

23 Surface area for the 0.75" ID piping is 182 cm2foreach foot of pi in&

P corresponding to a total 0.75" ID piping surface area of 2,736 cm (0.3 m2) for the entire length of (approximately 15') of 0 75" piping.

3.0 Survey Unit Measurement LocationslData 3 1 Pipe interior radiological survey forms ate provided in Attachment 2 of this release record.

4.0 Survey Unit InvestigatiodResults 4.1 None 5.0 Data Assessment Results 5.1 Data assessment results are provided in the EPtBuried Pipe (BP) Survey Report provided in Attachment 1.

52 All measurement results are less than the Derived Concentration Guideline Level (DCGL) for radionuclide specific EP that corresponds to the 1 mreidy-r 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 0, provided in TBD-06-004, the survey unit that is constituted by EP Rx 126D passes FSS.

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

.. -

FSS Design # EP Rx 126D Revision # Original Page 3 of 3 Survey Unit: Rx 126D 5.5 Statistical Summary Table Statistical Parameter 6.0 Documentation of evaluations pertaining to compliance with the. unrestricted use limit of 25 mremlyr and dose contributions from Embedded Pipe and radionuclides contributing 100/oin 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 126D to be less than 1 mremlyr. The dose contribution is estimated to be 0.038 mrem/yr based on the average of the actual gross counts measured.

7.0 Attachments Attachment 1 - BSI EPBP Survey Report Attachment 2 -Pipe Interior Radiological Survey Form Attachment 3 - DQA Worksheet Attachment 4 -Disc containing RR for EP Rx 126D & Spreadsheet

SECTION 7 ATTACHMENT 1 z PAGE(S)

BSI EPlBP SURVEY REPORT FOll.5L-X 00471 no sled Number of MeasurementsAbanre DCGL Survey Technician(s)

TBD 06-004 Piping Gmup 2 SR-13 Radionudii Di6bibution Sample EP 2-2 -

Measured Nuclide COa, Area FaotorlEMC Used No PassFaa FSS Pass MREMNR Contribution <1 COMMENTS:

ACTIVITY VALUES NOT BACKGROUND CORRECTED

<

RP Engineer I Date I DJ /o-2s-07

EP Rx 126D 0.75" Pipe TBD 06-004 Group 2

SECTION 7 ATTACHMENT 2 z PAGE(S)

/

BSYLVSPipeCrawler-002 Revision 4 Pipe Interior Radiological Survey Form Date: 31 1 2 /07 Time: /3SO Pipe ID#: & 126 D Pipe Diameter: #?sf' Access Point Area: & 2 Z T l Z f f M Building:  ? Elevation: -2 7 I System: &/WE ~ R ~ P / / I /

Type of Survey Investigation Characterization Final Survey p Other

/

Gross C06O r/ Cs hk Detector ID# / Sled ID# / I L - ~ 0 4 71 AID SLED l

Detector Cal Date: 111(1 0 7 Detector Cal Due Date: r I/ o k Instrument: 23fOH/ Instrument ID #: 189094t Instrument Gal Date: / - / I -0 7 Instrument Cal Due Date: 1 4 - 0 r+

From the Daily Pipe Survey Detector Control Form for the Selected Detector Background Value 6 , I cpm MDcktatic l r .C CPm Efficiency Factor for Pipe Diameter 0 0 0 0 bq. (fiom detector efficiency determination)

MDcstatii, 480s' Is the MDCstaticacceptable? &&(if:fadjist

-

sample count time and recalculate MOCE&,tic)

Comments: I?/% 51 9 l z ~ l Z V E P Z - ' 2 , LvtPLrz~.

C Pipe Interior Radiological Survey Attachment 3, Page 1

BSYLVSPipeCrawler-002 Revision 4 Pipe Interior Radiological Survey Form (Continuation Form)

Pipe Diameter: WZS" Access Point Area: & 22 p ~ d Elevation: - 27 I System: I ( 5 ~ ~ Z J C I ~

Package Page 3 Attachment 3, Page 2

SECTION 7 ATTACHMENT 3 I PAGE(S)

DQA Check Sheet Design # Rx 126D Revision # Original Survey Unit # Rx 126D 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 DCGLWfor Class 1 and 2 X 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 ? X
4. Was the instrumentation MDC for structure scan measurements, soil scan measurements, and embeddedfburied 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?
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 X

media being surveyed?

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 X

design, which accurately reflects the radiological status of the facilltp 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 < DCGLw? X
3. If elevated areas have been identified by scans andlor sampling, is the average activity in each X

elevated area < D C G k (Class I), c DCGLW(Class 2), or e0.5 DCGLw (Class 3)?

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) 2 the critical value? X Comments:

CS-0912 Page 1 of 1

SECTION 7 ATTACHMENT 4 1 DISC