ML20205B401

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Insp Rept 50-458/87-03 on 870209-13.Violation Noted:Failure to Ensure Capability to Obtain & Analyze post-accident Samples.One Unresolved Item Identified Re Failure to Conduct Training
ML20205B401
Person / Time
Site: River Bend Entergy icon.png
Issue date: 03/16/1987
From: Murray B, Nicholas J, Wise R
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:
Shared Package
ML20205B372 List:
References
50-458-87-03, 50-458-87-3, NUDOCS 8703270601
Download: ML20205B401 (18)
v • d • e


See also: IR 05000458/1987003

Text

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APPENDIX B

U.S. NUCLEAR REGULATORY COMMISSION

REGION IV

NRC Inspection Report: 50-458/87-03 License: NPF-47

Docket: 50-458L

Licensee: Gulf States Utilities (GSU)

P. O. Box 220

St. Francisville, Louisiana 70775

Facility Name: River Bend Station (RBS)

Inspection At: River Bend Station, St. Francisville, Louisiana

Inspection Conducted: February 9-13, 1987

Inspectors: J[Ad7

JfjB. Nicholas, Sedior Radiation Specialist Date

Mcilities Radiological Protection Section

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/K &

R. Wise, Radiation Specialist, Facilities

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Date

Radiological Protection Section

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Approved: U $bkl NlbObf

B. Murray, Chief, Faci ities Radiological

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Date'

Protection Section

Inspection Summary

Inspection Conducted February 9-13, 1987 (Report 50-458/87-03

Areas Inspected: Routine, unannounced inspection of the licensee's water

chemistry and radiochemistry programs, including: review of organization and

management controls, staffing and staff qualifications, training program,

procedures, facilities and equipment, quality assurance (QA) program of water

chemistry and radiochemistry activities, postaccident sampling system (PASS),

quality control of analytical measurements, and water chemistry and

radiochemistry confirmatory measurements.

8703270601 870324

PDR ADOCK 05000458

G PDR

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Results: 'Within the areas inspected, one violation was. identified.(failure-to

ensure the capability to obtain and analyze postaccident samples, paragraph 5).

One unresolved item was identified (failure to conduct training,

paragraph 6). .No deviations were identified.

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DETAILS

1. Persons Contacted

GSU

'*D. H. Barrow, Director, GSU

  • W. J. Cahill, Jr. Senior Vice President, GSU
  • J. C. Deddens, Senior Vice President, RBS Nuclear Group
  • T. F. Plunkett, Plant Manager
  • D. L. Andrews, Director, Nuclear Training
  • R. J. Backen, Acting Supervisor, Operations QA
  • J. E. Booker, Manager, Oversight

T. D. Burnett, Plant Chemist

  • J. L. Burton, Supervisor, Independent Safety Engineering Group
  • E. M. Cargill, Supervisor, Radiological Programs
  • J. W. Cook, Lead Environmental Analyst, Licensing

'K. C. Coffey, Nuclear Chemistry Technician

  • L. A. England, Supervisor, Licensing
  • K. J. Gladrosich, Supervisor, Operations Quality Control (QC)
  • D. R. Gipson, Director, Quality Services
  • E. R. Grant, Director, Nuclear Licensing
  • J. R. Hamilton, Director, Design Engineering

R. P. Hebert, QA Engineer

  • K. C.'Hodges,' Supervisor, QA Engineering
  • R. E. Horn, Nuclear ~ Training Coordinator - Technical
  • G. R. Kimmell, Supervisor, Operations QA
  • R. J. King, Supervisor, Nuclear Licensing

F. Kral, Nuclear Chemistry Technician

G. D. Lipham, Chemistry Foreman

A. S. Maryman, Nuclear Chemistry Technician

  • I. M. Malik,' Supervisor, Quality Systems
  • J. H. McQuirter,' Licensing Engineer
  • T. O. Maffitt, QA Engineer-
  • C. L. Nash, Chemistry Supervisor
  • V. J. Normand, Supervisor, Administrative Services
  • W.-H. Odell, Manager, Administration

E. R. Oswood, Lead Senior QA Engineer

  • J. J. Pruitt, Director, Management Systems

E. T. Rochelle, Lead Chemist

  • M. F. Sankovich, Manager, Engineering

C. S. Scott, Plant Chemist

J. E. Spivey, QA Engineer

  • R. B. Stafford, Director, Quality Operations
  • D. Williamson, Operations Supervisor

W. K. Woodcox, Chemistry Foreman

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Others

  • D. D. Chamberlain, NRC Senior Resident Inspector
  • G. A. Pick, NRC Reactor Engineer, Region IV
  • R. C. Stewart, NRC Reactor Inspector, Region IV
  • Denotes those present during the exit briefing on February 13, 1987.

The NRC inspectors also interviewed several other 58S employees during the

inspection.

2. Follow-up on Previous Inspection Finding

(Closed) Violation (458/8605-01): Failure to Maintain Calibration Records

- This item involved the failure to maintain the required instrument

calibration data and records for the gas partitioner prior to performing

hydrogen analyses of the offgas hyr.cogen recombiner effluent. The NRC

inspector reviewed the licensee'F Corrective actions including revisions

to Chemistry Section Procedures CSP-0100, " Chemical / Radiochemical Technical

Specifications Surveillances," Revision 2, dated March 24, 1986, and

CSP-0206, " Operation of the *cisher Gas Partitioner Model 1200," Revision 1,

dated February 12, 1986. The NRC inspector also reviewed documentation of

calibrations performed or, the gas partitioner prior to use for hydrogen

analyses during 1986 apJ found the calibrations performed and recorded in

accordance with appro',ed procedures. This violation is considered closed.

3. Follow-up on Licen<,ee Event Report

(Closed) License.e Event Report (458/86-046): Missed Technical Specification

Requirement on Fuel Building Radiation Monitor - This item involved the

wide range gas monitor on the fuel building exhaust stack being inoperable

for greater than 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> without an alternate means of stack sampling and

monitoring in service. Auxiliary sampling equipment for particulates and

iodines was not placed in service within the 8-hour time period and the

release was not suspended. The NRC inspector reviewed the monitoring

conditions of the fuel building exhaust stack and the reasons for the

licene,ee event report. The NRC inspector also reviewed the licensee's

corrective actions, including the Condition Report 86-0726 and the

revision to Chemistry Operating Procedure C0P-0046, " Sampling Gaseous

Ef/luents via the Wide Range Gas Monitors," Revision 5, dated January 27,

1987. This item is considered closed.

4. Program Areas Inspected

The following program areas were inspected. Unless otherwise noted, the

inspection was completed and identified no violations, deviations,

unresolved items, or open items. Notations after a specific inspection

item are used to identify the following: I = item was not inspected or

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was only partially inspected and may require further review and evaluation

during the current inspection cycle, V = violation, D = deviation,

U = unresolved item, and 0 = open item.

Inspection Procedure Inspection Requirements

83722 Plant Chemistry: Organization and

Management Controls (Minimum / Basic)

02.01 - Organization

02.02 - Staffing

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02.03 - Chemistry Supervisor

02.04 - Identification and Correction of

Weaknesses

02.05 - Audits and Appraisals

83522 Plant Chemistry: Organization and

Management Controls (Preoperational and

Supplemental)

02.01 - Organization, Responsibilities,

and Authorities

02.02 - Staffing

02.03 - Identification and Correction

of Weaknesses

02.04 - Audits and Appraisals

02.05 - Communication to Employees

02.06 - Documentation and Implementation

83723 Plant Chemistry: Training and

Qualifications (Minimum / Basic)

02.01 - Responsibilities

02.02 - New Personnel

02.03 - Audits and Appraisals

83523 Plant Chemistry: Training and

Qualifications (Preoperational and

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Supplemental)

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02.01 - Training and Qualifications

Program

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02.02 - Education and Experience

02.03 - Adequacy

84725 Quality Assurance and Confirmatory

Measurements For In-Plant Radiochemical

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Analysis (Minimum / Basic)

02.01 - Audits and Appraisals

02.02 - Changes

02.03 - Confirmatory Measurements

02.04 - Postaccident Sample Analysis-V

(see paragraph 5)

02.05 - Implementation of the Quality

Assurance Program

02.06 - Contractor Activities

84525 ('uality Assurance and Confirmatory

Measurements For In-Plant Radiochemical

Analysis (Preoperational and

Supplemental)

02.01 - Facilities, Equipment, and

Supplies

02.02 - Procedures

02.03 - Confirmatory Measurements

02.04 - Postaccident Sample Analysis-U

(see paragraph 5)

02.05 - Quality Assurance Program

02.06 - Contractor Activities

79701 Light Water Reactor Water Chemistry

Control and Chemical Analysis (Basic)

02.01 - Audits and Appraisals

02.02 - Changes

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02.03 - Implementation of the Water

Chemistry Control Program

02.04 - Implementation of the Quality

Assurance Program for. Chemical

Measurements

79501 Light Water Reactor Water Chemistry

Control and Chemical Analysis

(Preoperational and Supplemental)

02.01 - Establishment of a Water

Chemistry Control Program-I

02.02 - Implementation of the Water

Chemistry Control Program-I

02.03 - Water Sampling

02.04 - Chemistry Measurements:

Facilities and Equipment

02.05 - Establishment of a Quality

Assurance Program for Chemical

Measurements-I

02.06 - Implementation of a Quality

Assurance Program for Chemical

Measurements-I

02.07 - Laboratory Safety

79502 Plant Systems Affecting Plant Water

Chemistry (Preoperational and

Supplemental) ,

-02.01 - Audits and Appraisals

02.02 - Primary and Secondary Water

Systems-I

02.03 - Auxiliary Water Systems-I

02.04 - Demineralizers-I

5. Violation

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84725, Item 02.04 - Postaccident Sample Analysis

Technical Specification 6.8.4(c) requires that a program be established,

implemented, and maintained which will ensure the capability to obtain and

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analyze reactor coolant, radioactive iodines and particulates in gaseous

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effluents, and containment atmosphere samples, under accident conditions.

The program shall include training of personnel, procedures for sampling

and analysis, and provisions for maintenance of sampling and analysis

equipment. Chemistry Section Procedure CSP-0150, " Chemistry Surveillance

of the Postaccident Sampling System," Revision 1, dated January 2, 1986,

requires that a monthly surveillance of the PASS be performed to ensure the

capability to obtain and analyze postaccident samples of reactor water and

containment atmosphere. Contrary to the above, On February 12, 1987, the

NRC inspectors reviewed the results of the monthly surveillance tests

attempted on the PASS and found that since the initial demonstration of

PASS operability on November 10, 1985, prior to exceeding 5 percent power,

none of the monthly surveillance tests throughout 1986 had been completed

successfully to demonstrate the capability of the PASS to obtain and

analyze reactor water and containment atmosphere postaccident samples. On

February 12, 1987, the NRC inspectors requested that the licensee

demonstrate the operability of the PASS under simulated accident conditions.

The attempt to operate the PASS was unsuccessful due to equipment

malfunction. The failure to establish, implement, and maintain a program

to ensure the capability to obtain and analyze reactor water and

containment atmosphere postaccident samples is an apparent violation of

Technical Specification 6.8.4(c). (458/8703-01)

6. Unresolved Item

84525, Item 02.04 - Postaccident Sample Analysis

Technical Specification 6.8.4(c) requires that a program be established and

implemented to provide training to personnel on the operation of the PASS.

The licensee's Chemistry Section Procedure CSP-003, " Chemistry Personnel

Qualifications," Revision 2, dated January 30, 1986, states in

paragraph 6.5.4 that continuing training of chemistry personnel shall

include annual PASS retraining. Contrary to the above, the NRC inspectors

determined on February 12, 1987, that the licensee had not conducted annual  ;

requalification training on the PASS for the nuclear chemistry technicians

since the initial training conducted in August 1985. The failure to

conduct the required annual requalification training is considered a

pntential violation. Since this matter is related to training, it is not

classified as a violation, but is considered to be an unresolved item in

accordance with the Commission Policy Statement on Training and

Qualification of Nuclear Power Plant Personnel (50 FR 11147 dated March 30,

1985). (458/8703-02)

7. Exit Briefing

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The NRC inspectors met with the NRC senior resident inspector and the

licensee representatives denoted in paragraph 1 at the conclusion of the

inspection on February 13, 1987. The lead NRC inspector summarized the

scope of the inspection and discussed the inspection findings and the

results of the confirmatory measurements.

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ATTACHMENT 1

Analytical Measurements

1. Chemistry Confirmatory Measurements

During the inspection, standard chemical solutions were submitted to the

licensee for analysis. The standard solutions were prepared by the

Brookhaven National Laboratory, Safety and Environmental Protection

Division, for the NRC. The standards were analyzed by the licensee using

routine methods and equipment. The analysis of chemical standards is used

to verify the licensee's capability to monitor chemical parameters in

various plant systems with respect to Technical Specification requirements

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and other industry standards. In addition, the analysis of standards is

used to evaluate tha licensee's analytical procedures with respect to

accuracy and precision.

The results of the measurements comparison are listed in Attachment 2.

Attachment 3 contains the criteria used to compare results. The

licensee's analytical results indicated that six of the seven results were

in agreement. All standards were analyzed in triplicate.

2. Radiological Confirmatory Measurements

Confirmatory measurements were performed on the following standards and

samples in the Region IV mobile laboratory at River Bend Station during

the inspection:

a. Reector Coolant Liquid (1 liter Marinelli)

b. Gas Sample (15 cc Off Gas Vial)

c. Particulate Filter Standard (21478-109)

d. Charcoal Cartridge Standard (21420-109)

e. Liquid Waste Sample (1 liter Marinelli)

f. Tritium Sample

The confirmatory measurements tests consisted of comparing measurements

made by the licensee and the NRC mobile laboratory. The NRC's mobile

laboratory measurements are referenced to the National Bureau of Standards

by laboratory intercomparisons. Confirmatory measurements are made only

for those nuclides identified by the NRC as being present in concentrations

greater than 10 percent of the respective isotopic values for liquid and

gas concentrations as stated in 10 CFR Part 20, Appendix B, Table II.

Attachment 5 contains the criteria used to compare results.

At the time of the inspection, the licensee utilized three detectors in

chemistry for comparison with the NRC results. The licensee performed the

tritium analysis on their liquid scintillation counting system. The

individual sample analyses and comparison of analytical results of the

radiological confirmatory measurements are tabulated in Attachment 4. The

licensee's gamma isotopic results from the listed samples in Attachment 4

showed 96 percent agreement with the NRC analysis results. The licensee's

tritium result was in agreement with the NRC analysis result.

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Confirmatory measurements were performed by the licensee on liquid samples

prepared by the Radiological Environmental Sciences Laboratory (RESL) in

Idaho Falls, Idaho. The Itcensee's analytical results were compared to

the known sample activities and the results of the comparisons are

presented in Attachment 4, Sample 7. The licensee's results were in

86 percent agreement for sample 7 analyzed in 1986.

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ATTACHMENT 2

Chemistry Confirmatory Measurements Results

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RBS Results NRC Results RBS/NRC Comparison

l Chemical Parameter (ppb) (ppb) Ratio Decision

Nickel 146.214.6 153.014.0 0.9610.04 Agreement

Iron 157.619.6 147.014.2 1.0710.07 Agreement

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i Chromium 145.212.1 -143.018.0 1.0210.06 Agreement

Copper 140.712.3 14516.0 0.9710.04 Agreement

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L Silica 20.610.3 21.811.4 0.9510.06 Agreement

Chloride 11.9810.16 12.0511.55 0.9910.13 Agreement

i Sulfate 11.8410.37 10.0010.45 1.1810.06 Disgreement

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NOTE: All licensee analyses were run at least in triplicate. The analyses

were repeat analyses of one dilution and the uncertainty is an estimate of the

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instrument precision.

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ATTACHMENT 3

Criteria For Comparing Analytical Measurements

This attachment provides criteria for comparing results of capability tests.

In these. criteria the judgement limits are based on the uncertainty of the

ratio of the licensee's value to the NRC value. The following steps are

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(1) the ratio'of the licensee's value to the NRC value is computed

Licensee Value

(ratio = NRC Value );

(2) the uncertainty of the ratio is propagated.1

If the absolute value of one minus the ratio is less than or equal to twice the

ratio uncertainty, the results are in agreement. (ll-ratiol 5 2 uncertainty)

Z= X, then Sz2 = Sx2+ 2

V F F- 2

(From: Bevington, P.R., Data Reduction and Error Analysis fer the Physical

Sciences, McGraw-Hill, New York, 1969)

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' ATTACHMENT 4

, RADIOLOGICAL CONFIRMATORY' MEASUREMENTS RESULTS

1. - ' Reactor Coolant Liquid-(1 Liter Marinelli Beaker)

'(Sampled 08:40, CST, February .10, 1987)

RBS Results. NRC' Results'- RBS/NRC -. Comparison

Nuclide (uCi/ml) (uCi/ml) Ratioi . Decision

24Na 6.48810.385 E-4. 6.41110.118E-4 1.01 . Agreement

5.85710.'353 E-4 0.91 Agreement

6.-15610.368 E-4 0.96 Agreement

s Cr. 1.18710.098 E-3- 1.22010.068E-3 0.97 Agreement

Not Identified

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1.13810.089 E-3 0.93' Agreement

99Mo 5.425i0.380 E-4 5.03910.329 E-4 1.08 Agreement

5.00610.386 E-4 0.99 Agreement

5.13510.360 E-4 1.02 Agreement

tosRh 6.15810.507 E-4 6.32610.353 E-4 0.97 Agreement

5.97910,526 E-4 0.95 Agreement-

5.94010.467 E-4 0.94 Agreement

'122Sb 6.99110.071 E-5 7.37510.536 E-5 0.95 Agreement

6.22910.069 E-5 0.84 Agreement-

5.02110.069 E-5 0.68 Agreement

187W 1.44510.139 E-4 1.48010.238 E-4 0.98 Agreement

1.24510.015 E-4 0.84 Agreement

-1.33010.131 E-4 0.90 Agreement

98"Tc ,3.69710.292 E-3 4.25010.018 E-3 0.87 Agreement

'3.42910.269 E-3

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0.81 Disagreement.

3.55810.283 E-3 0.84 Disagreement

13&I 2.27110.063 E-5 3.25710.666 E-5 0.70 . Agreement

2.19510.068 E-5 0.67 Agreement

1.98710.058 E-5 0.61 Agreement

132I 4.51610.170 E-4 4.65710.127 E-4 0.97 Agreement

4.34410.157 E-4 0.93 Agreement

4.63710.167 E-4 0.94 Agreement

133I 2.87810.188 E-4 2.94910.058 E-4 0.98 Agreement

2.72810.184 E-4 0.93 Agreement

2.85910.184 E-4 0.97 Agreement

1341 1.02610.036 E-3 1.05010.038 E-3 0.98 Agreement

9.82210.302 E-4 0.94 Agreement

9.64310.386 E-4 0.92 Agreement

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135I '5.72610.202 E-4 6.27310.224 E-4 0.91 Agreement

5.21910.200 E-4 0.83 Agreement

5.54310.201 E-4 0.88 Agreement

2. Off Gas Sample (15 cc Off Gas Vial)

(Sampled 10:29, CST, February 11,1987)

RBS Results NRC Results RBS/NRC Comparison

Nuclide (uCi/cc) (uCi/cc) Ratio Decision

41Ar 7.14512.444 E-5 5.74411.283 E-5 1.24 Agreement

7.61812.384 E-5 1.33 Agreement

8.48812.521 E-5 1.48 Agreement

85"Kr 1.69710.171 E-4 1.67410.066 E-4 1.01 Agreement

1.50910.202 E-4 0.90 Agreement

1.66110.159 E-4 0.99 Agreement

87Kr 9.83010.912 E-4 1.15310.034 E-3 0.85 Agreement

9.52510.912 E-4 0.83 Agreement

9.98110.946 E-4 0.87 Agreement

88Kr 6.38510.613 E-4 6.03910.333 E-4 1.06 Agreement

7.23310.846 E-4 1.20 Agreement

5.75310.542 E-4 0.95 Agreement

185"Xe 3.57410.468 E-3 2.92610.090 E-3 1.22 Agreement

3.36710.337 E-3 1.15 Agreement

3.34710.643.E-3 1.14 Agreement

135Xe 5.19810.461 E-4 5.27310.122 E-4 0.99 Agreement

4.47310.433 E-4 0.85 Agreement

4.86010.428 E-4 0.92 Agreeement

138Xe 1.54210.104 E-2 1.25010.049 E-2 1.23 Agreement

1.38310.059 E-2 1.11 Agreement

1.33310.155 E-2 1.07 Agreement

3. Particulate Filter Standard (21478-109)

(Standardized 09:00, CST, February 9, 1987)

RBS Results NRC Results RBS/NRC Comparison

Nuclide (uCi/ Sample) (uCi/ Sample) Ratio Decision

109Cd 1.19810.101 E+0 1.11210.003 E+0 1.08 Agreement

1.24510.105 E+0 1.12 Agreement

1.16210.098 E+0 1.04 Agreement

57Co 2.86110.124 E-2 2.58510.010 E-2 1.11 Agreement

2.99410.128 E-2 1.16 Agreement

2.77710.119 E-2 1.07 Agreement

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189Ce 1.83910.122 E-2 1.74010.010 E-2 1.06 Agreement

1.92210.128.E-2 1.10 Agreement

1.84410.123 E-2 1.06 Agreement

203Hg 1.32110.104 E-2 1.38210.012 E-2 0.96 Agreement

1.35910.107 E-2 0.98 Agreement

1.30410.103 E-2 0.94 Agreement

118Sn 3.08110.165 E-2 2.90010.021 E-2 1.06 Agreement

3.21510.170 E-2 1.11 Agreement

2.98510.162 E-2 1.03 Agreement

137Cs 5.12210.252 E-2 4.63510.030 E-2 1.11 Agreement

5.13310.253 E-2 1.11 Agreement

5.03510.248 E-2 1.09 Agreement

88 y 3.91010.152 E-2 3.71610.030 E-2 1.05 Agreement

3.97510.155 E-2 1.07 Agreement

3.88510.152 E-2 1.05 Agreement

GoCo 3.11510.107 E-2 2.94210.029 E-2 1.06 Agreement

3.20610.111 E-2 1.09 Agreement

.3.16210.110 E-2 1.07 Agreement

4. Charcoal Cartridge Standard (21420-109)

l (Standardized 09:00, CST, February 9, 1987)

RBS Results NRC Results RBS/NRC Comparison

Nuclide (uCi/ Sample) (uCi/ Sample) Ratio Decision

109Cd 1.19710.101 E+0 1.16310.003 E+0 1.03 Agreement

1.26010.106 E+0 1.08 Agreement

1.19210.101 E+0 1.03 Agreement

57C0 2.80510.123 E-2 2.63010.011 E-2 1.07 2 Agreement

3.05310.131 E-2 1.16 Agreement

2.84710.124 E-2 1.08 Agreement

139Ce 1.87510.125 E-2 1.78110.011 E-2 1.05 Agreement .

2.02710.135 E-2 1.14 Agreement

1.86110.124 E-2 , 1.05 Agreement

20aHg 1.35910.109 E-2 1.30710.011 E-2 1.04 Agreement

1.35610.107 E-2 1.04 Agreement

1.29810.103 E-2 0.99 Agreement

113Sn 3.12310.169 E-2 2.97610.021 E-2 1.05 Agreement

3.29810.175 E-2 1.11 Agreement

3.04010.165 E-2 1.02 Agreement

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137Cs 5.11710.252 E-2 4.81310.029 E-2 1.06 Agreement

5.35510.264 E-2 1.11 Agreement

5.05210.250 E-2 1.05 Agreement

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3.95610.155 E-2 3.83910.030 E-2 1.03 Agreement

4.19410.164 E-2 1.09 Agreement

3.89310.153 E-2 1.01 Agreement

80Co 3.23310.112 E-2 3.15410.029 E-2 1.03 Agreement

3.37110.117 E-2 1.07 Agreement

3.23810.113 E-2 1.03 Agreement

5. Liquid Waste Sample (1 liter Marinelli)

(Sample 07:50, CST, February 11, 1987)

RBS Results NRC Results RBS/NRC Comparison

Nuclide (uCi/ml) (uCi/ml) Ratio Decision

24Na 5.85610.814 E-7 5.06510.573 E-7 1.16 Agreement

5.13610.781 E-7 1.01 Agreement

5.49410.813 E-7 1.08 Agreement

stCr 2.04410.523 E-6 2.33110.584 E-6 0.88 Agreement

2.09910.569 E-6 0.90 Agreement

1.56810.499 E-6 0.67 Agreement

54Mn 1.87610.090 E-5 1.85110.025 E-5 1.01 Agreement

1.75010.085 E-5 0.95 Agreement

1.83610.088 E-5 0.99 Agreement

58C0 2.21610.107 E-5 2.17610.025 E-5 1.02 Agreement

2.07610.101 E-5 0.95 Agreement

2.14810.105 E-5 0.99 Agreement

80Co 1.87210.074 E-5 1.81610.027 E-5 1.03 Agreement

1.81110.072 E-5 1.00 Agreement

1.78010.071 E-5 0.98 Agreement

85Zn 2.95510.298 E-6 2.67310.238 E-6 1.11 Agreement

2.40910.282 E-6 0.90 Agreement

2.66810.291 E-6 1.00 Agreement

80*Tc 9.86010.908 E-7 8.42010.539 E-7 1.17 Agreement

8.72110.830 E-7 1.04 Agreement

1.00510.096 E-6 1.19 Agreement

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6. Tritium San >1e

(Sampled Fe)ruary 11,1987)

RSS Results NRC Results R8S/NRC Comparison l

Nuclide (uci/c) (uci/a) Ratio Decision

8H 5.0010.11 E-4 5.6710.58 E-4 0.88 Agreement

7. RESL Liquid Sample  ;

(Standardized 12:00, MST, January 11,1986) ,

RBS Results NRC Results RBS/NRC Comparison l

Nuclide (uCi/ml) (uCf/ml) Ratio Decision  ;

soSr 1.310.1 E-04 1.4010.04 E-04 0.93 Agreement

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00Sr 1.510.1 E-05 1.3310.05 E-05 1.13 Agreement _

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55Fe 6.310.2 E-04 8.2610.17 E-05 7.63 Disagreement

aH 1.0010.03 E-04 1.1110.02 E-04 0.90 Agreement  ;

137Cs 2.3010.15 E-05 2.1910.07 E-05 1.05 Agreement  ;

soCo 2.0910.10 E-05 1.9510.04 E-05 1.07 Agreement

54Mn 1.4710.10 E-05 1.3510.03 E-05 1.09 Agreement l'

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ATTACHMENT 5

.

Criteria for Comparina Analytical Measurements

The following are the criteria used in comparing the results of capability

tests and verification measurements. The criteria are based on an empirical

relationship established through prior experience and this program's analytical

requirements.

In these criteria, the judgement limits vary in relation to the comparison of

the resolution.

NRC VALUE

Resolution = _

NRC UNCERTAlhiY

LICENSEE VALUE

Ratio =

NRC VALUE

Comparisons are made by first determining the resolution and then reading

across the same line to the corresponding ratio. The following table shows the

acceptance values.

!

RESOLUTION AGREEMENT RATIO

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!

<4 0.4 - 2.5

4-7 0.5 - 2.0

8 - 15 0.6 - 1,66 .

,

16 - 50 0.75 - 1.33

51 - 200 0.80 - 1.25

>200 0.85 - 1.18

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The above__ criteria are applied to the following analyses:

(1) Gamma Spectrometry.

(2) Tritium analyses of Ilquid samples. ,

(3) Iodine on adsorbers.

(4) av5r and '0Sr determinations.

(5) Gross Beta where samples are counted on the same date using the same

reference nucilde.

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