ML20140E914
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| ML20140E914 | |
| Person / Time | |
|---|---|
| Site: | River Bend  |
| Issue date: | 03/06/1986 |
| From: | Murray B, Nicholas J, Wise R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20140E887 | List: |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-2.B.3, TASK-TM 50-458-86-05, 50-458-86-5, NUDOCS 8603280233 | |
| Download: ML20140E914 (18) | |
See also: IR 05000458/1986005
Text
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APPENDIX B
U. S. NUCLEAR REGULATORY COMMISSION
REGION IV
NRC Inspection Report: 50-458/86-05 License: NPF-47
Docket: 50-458
Licensee: Gulf States Utilities (GSU)
P. O. Box 2951
Beaumont, Texas 77704
Facility Name: River Bend Station (RBS)
Inspection At: River Bend Station, St. Francisville, Louisiana
Inspection Conducted: January 27-31, 1986
Inspectors: /IAk. /Ait2//
J. Blair Nicholas, Radiation Specialist, Dtte
& Facilities Radiological Protection Sect on
0fdin19Mbvuxb/
R'ussell Wise, 'Radiatiori Specialist, Facilit !es
5 6/B6
0' ate'
d. Radiological Protection Section
Approved: OfqJMlA{[/// M/[[
BlaineMurray,~ Chief,facilitiesRadiological D' ate
Protection Section
Inspection Summary
Inspection Conducted January 27-31, 1986 (Report 50-458/86-05')
Areas Inspected: Routine, announced inspection of the licensee's water chemistry
and radiochemistry programs including: review of organization and management
control, staffing and staff qualifications, training program, facilities and
equipment, NUREG-0737, Item II.B.3, postaccident sampling system (PASS), quality
assurance (QA) program of chemistry / radiochemistry activities, quality control
of analytical measurements, radiochemistry and whole body counting system
confirmatory measurements. The inspection involved 78 inspector-hours onsite by
two NRC inspectors.
Results: Within the areas inspected, one violation was identified (see paragraph 6).
Two previously identified open items were closed.
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DETAILS
1. Persons Contacted
GSU
*W. J. Cahill, Senior Vice President , RBS Nuclear Group
*J. C. Deddens, Vice President, RBS Nuclear Group-
*T. F. Plunkett, Plant Manager
*T. D. Burnett, Plant Chemist'
*S. V. Desai, Chemical Engineer
~*J. W. Evans, Stenographer
*K. J. Giadrosich, Operations - QA
*D. P.. Gipson, Assistant Plant Manager - Operations
*R. E. Horn, Nuclear Training Representative
*R. J. King, Lkensing Engineer
*W. J. Lambert, Systems Engineer
*G. D. Lipham, Chemistry Foreman
A. _S. Maryman, Nuclear Chemistry Technician
R. L. McCann, Nuclear Chemistry Tectnician
*J. H. McQuirter, Licensing Engineer
*C. .L. Nash, Chemistry Supervisor
, D. M. Ross, Radiological Health Specialist
R. J. Shah, QA Engineer
*J.- E. Somerindyke, Corporate Security
J. E. Spivey,-QA Engineer
*P. F. Tomlinson, Director, Quality Services
W. K. Woodcox, Chemistry Foreman
Others
*D. D. Chamberlain, NRC Senior Resident Inspector
W. B. Jones, NRC Resident Inspector-
* Denotes those present-during the exit briefing on January.3.1, 1986.
The NRC inspectors also interviewed several'other RBS employees during the
inspection.
2. , Licensee ~ Action on Previous-Inspection Findings
.
(Closed) Open Item (458/8422-05): Postaccident Sampling System _- This item
involved the lack of. PASS operation verification by collecting reactor
water and contair. ment atmosphere samples, performing required analyses, and
completing training of nuclear chemistry technicians.on PASS. The NRC j
senior resident inspector witnessed a demonstration of the licensee's :
ability to provide representative reactor water samples using the manual
grab PASS on November 10, 1985. The NRC inspector during this inspection- .l
also witnessed a similar demonstration and verified that the' licensee's
PASS and associated procedures satisfy the requirements of NUREG-C737,
Item II.B.3. The licensee had completed technician training on.the PASS '
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for 10 nuclear chemistry technicians. The li'censee's methods, analytical
sensitivities, and analytical results of chemistry parameters are
consistent with PASS requirements. This item is considered closed.
(Closed) Open Item (458/8422-06): Facilities, Equipment, and Supplies --
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This item involved the completion of construction, testing, calibration'of
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process instrumentation, and the routine.~use of the' chemistry sample panels
and-associated process instrumentation. The NRC inspectors inspected the -
various chemistry sampling areas including the reactor water sample panel,
turbine. plant sample panel, condensate demineralizer sample panel, makeup
water sample panel, radwaste sample panel, and fuel building. sample panel.
The NRC inspectors determined that all the sampling panels had been tested
and calibrations had been performed on associated process instrumentation
in accordance with RBS procedures and that all sampling areas were in
j reutine operation. This item is considered closed. 4 3. Inspector Observations
The following are observations the NRC inspectors discussed with the
licensee during the inspection and at the exit' interview on January 31,
1986. These observations are neither violations nor unresolved items.
These items were recommcnded for licensee consideration for program
improvement, but they have no' specific regulatory requirement. The
licensee stated the items would be reviewed.
o Confirmatory Measurements - The percent agreement between the licensee
and NRC were below the expected values for these kinds of measurements
(see paragraph 12.b).
4. Chemistry / Radiochemistry Organization and Managemer.t Controls
The NRC inspectors reviewed the licensee's organization and staffing of the
chemistry / radiochemistry section (C/RS) to determine compliance with
commitments in Chapter 13 of the Final Safety Analysis Report (FSAR) and
the requirements in Section 6.2.of the Technical Specifications (TS) and
in RBS procedures.
The NRC inspectors verified that the organizational structure of the C/RS
was as defined in the FSAR, TS, and RBS procedures. The NRC inspectors
reviewed the RBS management control procedures and position descriptions
for the assignment of. responsibilities for the management and implementa-
tion of the RBS. chemistry / radiochemistry program. The NRC inspectors
verified that the administrative control responsibilities specified by the
RBS procedures were being implemented.
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The NRC inspectors reviewed the staffing of the_C/RS and noted that since
the previous NRC chemistry / radiochemistry inspection in June 1985, the C/RS
had lost its lead chemist and~one' chemistry foreman. The chemistry foreman
position had been filled by one of the plant chemists and the vacated' plant
chemist position had been filled by one of the senior nuclear chemistry
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technicians leaving 15 nuclear chemistry technician positions filled and
one vacancy. At the time of the inspection, the lead chemist position was
temporarily filled with a qualified contractor. The chemistry supervisor
was recruiting to fill the staff vacancies.
No violations or deviations were identified.
5. Chemistry / Radiochemistry' Personnel Qualifications
The NRC inspectors reviewed the qualifications of the C/RS personnel to
determine compliance with commitments in Chapter 13 of the FSAR and the
requirements in Section 6.3 of the TS and in RBS procedures.
The NRC inspectors reviewed the resumes of each of .he C/RS personnel and
verified that they met the required qualifications specified in the FSAR,
TS, RBS procedures, and position descriptions. The NRC inspectors
determined that the licensee had an' adequate staff to meet shift staffing
. requirements.
No violations or deviations were identified.
6. Chemistry / Radiochemistry Training Program
The NRC inspectors reviewed the licensee's chemistry / radiochemistry
training program to determine complianca with commitments in Chapter 13.2
of the FSAR and the requirements in Section 6.4 of the TS, 10 CFR
Part 19.12, and in RBS procedures.
The NRC inspectors reviewed the licensee's program for training and
qualification of RBS C/RS personnel as described in the nuclear training
department procedures and in RBS Chemistry Section Procedure.
The.NRC inspectors reviewed the C/RS individual staff training matrix
records and determined that nine chemistry technicians had completed all
matrix training requirements and six chemistry technicians were in the
process of completing the general RBS systems training and PASS hands-on
analysis training.
No violations or deviations were identified.
7. Chemistry / Radiochemistry Program
The NRC inspectors reviewed the licensee's chemistry / radiochemistry program
to determine compliance with commitments in Chapters 5, 9, and 11 of the
FSAR and the requirements in Section 3/4.4.4 of the TS.and in C/RS procedures.
The NRC inspectors' review of the chemistry / radiochemistry program found
that the licensee nad completed and approved all identified administrative
procedures, surveillance procedures, chemical control procedures, instrument
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calibration and performance check procedures, sampling procedures, and
analytical procedures. A review of selected procedures, logs, and analyt-
ical data indicated that the C/RS had established sufficient administrative
a1d analytical procedures to meet the requirements of the FSAR and TS.
The NRC inspectors reviewed the calibration and qua'ity control program
for the secondary chemistry laboratory instruments and primary chemistry
laboratory instruments. Laboratory instrument calibration and performance
check data and other documentation of instrument performance were reviewed.
During the review of instrument calibration data, it was noted that the
licensee'had not documented any calibrations performeo on the Fisher
Model 1200 gas chromatograph when performing hydrogen analysis of the
offgas hydrogen recombiner effluent. The rnalysis. procedure COP-0425,
" Determination of H2and 0 Gas
2 Concentration - Gas Chromatography Method,"
Revision 1, July 25, 1985, requires in paragraph 8.3 that calibration
standard data be recorded on the appropriate chemistry log. The fraquency
of calibration .'or the gas chromatograph, prior to each use, and appropriate
chemistry log, 50ul.1.7.4, are specified in CSP-121, "Chcmistry Laboratory
Instrument Surveillance," Revision 1, December-22, 1985. The NRC inspectors
determined on January 29, 1986, that the gas chromatograph had been used to
perform 57 hydrogen analyses of the offgas hydrogen recombiner effluent,
while the offgas explosive gas monitoring system was inoperable, during the
period January 14-26, 1986. A review of the TS surveillance report form
for procedure N P-0100, " Chemical / Radiochemical Technical Specifications
Surveillances," Revision 1, December 20, 1985, completed during the above
specified period showed that the offgas hydrogen recombiner effluent had
been sampled and analyzed every 4 hours for hydrogen concentration .to
satisfy Technical Specification Table 3.3.7.11-1, Action 123, without the
required gas chromatograph calibration data being documented. Technical
Specification 6.10.2.d requires that records be retained for at least 5
years of surveillance activities, inspections, and calibrations required
by the TS. The licensee's failure to maintain calibration records of the
gas chromatograph while performing a TS required surveillance is considered
an apparent violation of TS 6.10.2.d. (458/8605-01).
8. Facilities and-Equipment
The NRC inspectors inspected the facilities and equipment / supplies used by
the C/RS staff. The following facilities were inspected: cold laboratory,
radiochemistry laboratory, radiochemistry counting room, various chemistry
sampling panels, and PASS sample preparation area. The licensee had
completed construction in all the areas inspected. The laboratories were
equipped with the necessary chemicals, reagents, standards, labware, and
analytical instrumentation to perform the required analytical procedures.
The installation of the. various chemistry sampling panels was completed and
the associated process instrumentation had been tested and' calibrated and
was routinely operational. The PASS sample preparation area adjacent to
the radiochemistry laboratory was equipped ano functional.
No violations or deviations were identified.
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'9. Postaccident.Samplina System
The NRC . inspectors reviewed the licensee's PASS to determine compliance
with the requirements of NUREG-0737, Item II.B.3, and Section 6.8.4.c
of the TS.
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The NRC inspectors inspected the area.in the plant where the PASS hardware
had been installed. The NRC inspectors verified _that the equipment and
associated procedures satisfied the requirements of NUREG-0737, Item II.B.3,
and the TS for representative sampling and analysis of reactor water and
containment atmosphere follcwing a reactor incident. The licensee had
completed PASS operator training for 10 C/RS technicians as part of their
shift qualification. Five remaining C/RS technicians'will receive PASS
operator training as soon as current PASS operating procedure revisions are
approved. The NRC inspectors witnessed the initial monthly chemistry
surveillance of PASS in accordance with Chemistry Section Procedure,
CSP-0150, " Chemistry Surveillance of the Post-Accident Sampling System
(PASS)," Revision 1, January 2, 1986. The licensee demonstrated PASS
operability by collecting a simulated sample of reactor water using
demineralized flush water due to the status of the plant at 10 percent
power and plant operations having many systems isolated to assist in
diagnosing plant operating problems.. The licensee also collected a sample
from the containment building. The licensee prepared these samples for.the
required analyses in accordance with approved procedures. -However, due to
the nature of these samples, analyses were not performed during this
inspection. As discussed in NRC Inspection Report 50-458/85-77, the PASS
had been demonstrated operable on November 10, 1985, by the taking of two
liquid samples from the jet pump header.
, i The licensee analyzed the first sample for pH, dissolved oxygen, dissolved
- hydrogen, boron, conductivity, and radionuclides'within 3 hours from the
i time the decision was made to take the samples as required by NUREG-0737. i
The NRC inspectors determined that the licensee's procedures, analytical
sensitivities, and analytical results of chemi_stry parameters were
! consistent with PASS requirements.
No violations or deviations were identified.
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10. Quality Assurance Program
The NRC inspectors revi sed the licensee's QA audit / surveillance program
regarding chemistry /radicciemistry activities to determine compliance
with commitments in Chapter 17 of the FSAR and the requirements in
Section 6.5.3.8 of the-TS and related RBS QA procedures.
The NRC inspectors reviewed the QA department organization, selected QA
audit and surveillance procedures, audit schedule for 1986, QA audits
l qualifications, and audit and surveillance reports. The licensee completed
an audit of the chemistry / radiochemistry program on June 6,1985, which was-
reviewed in NRC Inspection Report (458/85-47). The NRC inspectors noted
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that the next chemistry / radiochemistry program audit is scheduled for
May 1986. . Reports generated from surveillances performed during 1985 in
the areas of chemistry / radiochemistry TS surveillance requirements were
reviewed for scope to ensure thoroughness of program evaluation. The NRC
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inspectors found the QA surveillance program adequate and responses and
corrective actions to surveillance findings timely.
No violations'or deviations were identified.
11. Quality Control of Radiological Analytical Measurements
The NRC inspectors inspected the radiochemistry counting room and reviewed
the licensee's program for calibration and quality control of radiological
analytical measurements to determine compliance with the requirements in
Sections 6.8 and 6.10 of the TS.
The NRC inspectors reviewed the licensee's records, for the period July
through December 1985, involving instrument surveillance procedures',
instrument calibration and quality control procedures, counting instrument
calibration and performance check data, and other documentation of
instrument ~ performance.
No violations or deviations were identified.
12. Analytical Measurements
a. Confirmatory Measurements
Confirmatory measurements were performed on the following standards
and samples in the NRC Region IV mobile laboratory at'RBS during the
inspection:
(1) NRC Face Loaded Scott Charcoal Cartridge Standard
(SRS-17817-109)
(2) NRC Particulate Filter Standard (SRS-17818-109)
(3) Simulated Liquid Radwaste (1 Liter Marinelli Beaker)
(4) Reactor Coolant System Liquid (1 Liter Poly Bottle)
(5) Reactor Coolant System Tritium Sample
The confirmatory measurements test consisted of comparing measurements
made by the licensee and the N'lC mobile laboratory. The NRC's mobile
laboratory measurements are referenced to the National Bureau of
Standards (NBS) by laboratory intercomparisons. Confirmatory measure-
ments 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 I contains the criteria used
to compare results.
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b. Results
The licensee maintains four germanium-lithium ~ detectors in the
radiochemistry counting room. At the time of the inspection, two of
.the detectors were out-of-service due to electronic malfunctions. All
four detectors.are used for routine isotopic analysis of radioactive
samples to demonstrate compliance with TS and regulatory requirements.
The analytical results from the two detectors were compared with the
NRC results, as well as with each other. The licensee performed the
tritium analysis on their liquid scintillation counting system. The
individual sample analyses and comparison of analytical results of the
confirmatory measurements are tabulated in Attachment 2.
The licensee's gamma isotopic results from the listed samples in
Attachment 2 showed 82 percent agreement with the NRC analysis results
based on 61 agreement results out of 74.nuclides identified and
compared. The 82 percent agreement results between the licensee and
NRC are below the value that would be expected for an effective radio-
chemistry program. The normally expected agreement would be greater
than 90 percent. The comparative measurements'results were discussed
with the licensee during the exit interview on January 31, 1986. The
licensee stated that their radiochemistry program.would be reviewed in
an attempt to improve their measurement capabilities. The licensee's
tritium result on the reactor coolant system sample was in agreement
with the NRC analysis result.
Confirmatory measurements were performed by the licensee on a liquid
unknown samp?e prepared by the Radiological Environmental Sciences
Laboratory (RESL) in Idaho Falls, Idaho using known nuclide concen-
trations of 893p, 903p, 3g, 137Cs, and 50Co. The licensee's analytical
results were compared to the known sample activities and the results
of the comparisons are presented in Attachment 2, sample 6. The
licensee's results were in 100 percent agreement with the certified
activities for 3H, 187Cs, and 60Co in the sample. The analytical
results for 895r and 90Sr were not available from the licensee's
contractor laboratory at the time of the inspection.
No violations or deviations were identified.
13. Whole Body Counting System
The NRC inspectors reviewed the licensee's " standup" whole body counting
system (WBCS) to determine compliance with 10 CFR Part 20.103. The
licensee maintains a shadow shield bed type WBCS also.
The NRC inspectors reviewed the licensee's program for operation,. calibration,
and quality control of the " standup" WBCS and found it adequate. The
licensee had calibrated the " standup" WBCS using sources of common nuclides
found in nuclear power facilities which represented vari.ous percentages of
maximum permissible organ burdens. The licensee's sources were traceable
to the NBS and were.used in a masonite phantom supplied by the vendor-of
the WBCS.
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The NRC inspectors supplied the licensee with a whole body counting
phantom to perform confirmatory measurements in.' the " standup" WBCS. The
phantom and counting arrangements were described in NRC Inspection
Report 50-458/85-17. The phantom was-stood. upright on a support in the
WBCS during the measurements. The results of the body positioning ~ test
and the. comparison of the analytical results of the confirmatory measurecents-
against the standard activities are tabulated in Attachment 3.
The licensee analyzed the nuclide~ activities riositioned in the NRC phantom
a to simulate inhalation as " mock f odine"~ in the thyroid and soCo in the
lungs. The NRC inspectors checked the licensee's accuracy of body positioning
in the " standup" WBCS and found the reproducibility of measurements
satisfactory. The results of the body burden activity measurements taken
resulted in several observations regarding the " standup" WBCS. These
observations include the following:
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a. The licensee's results for 5 percent through two organ burdens of
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6oCo in 'the right lung ranged from 14 percent higher to 25 percent
lower than the certified activities of the NRC standards with increasing
organ burdens. (See Tests (4)-(8)). These results are more accurate
than the results of similar previous tests performed on the licensee's
shadow shield style WBCS. (See NRC Inspection Report 50-458/85-17).
b. The licensee's results~for 5 percent through two organ burdens of
133Ba as " mock iodine" in the thyroid were nonconservative and were
approximately 40 percent low 3r than the certified activities of the
NRC standards. (See Tests (9)-(13)). These results are more
consistent and overall more accurate than the results of similar
previous tests performed on the licensee's shadow shield style
WBCS which showed results ranging from 40 percent lower to 300
percent higher than the certified activities over the same organ
! -burden range. (See NRC Inspection Report 50-458/85-17).
c. The licensee was able to analyze most accurately a 5 percent organ
burden of 233Ba as " mock iodine" in the thyroid in the presence of a
5 percent organ t,urden of 80Co in the lungs. (See Test (17)). The
other combinations of activity concentrations tested of " mock iodine"
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in the thyroid and 80Co in lungs gave results indicating the thyro'<i
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. activity approximately 50 percent lower than the certified activi
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values. (See Tests (14), (15), (16), and (18)).
The licensee was informed of the analytical results of the confirmatory
measurements.
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No violations or deviations were identified.
14. . Exit Briefina
The NRC inspectors met with the NRC senior resident inspector and the
licensee representatives identified in paragraph 1 at the conclusion of the-
- inspection on January 31, 1986. The lead NRC inspector summarized the
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scope of the inspection, discussed the inspection findings,.and presented
the results of the confirmatory measurements.
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ATTACHMENT 1.
Criteria ^for Comparing 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 UNCERTAINTY
Ratio = LICENSEE VALUE
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
<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
The above criteria are applied to the following analyses:
(1) Gamma Spectrometry.
(2) Tritium analyses of liquid samples.
(3) Iodine on adsorbers.
(4) 895r and 995r determinations.
(5) Gross Beta where samples are counted on the same date using the same'
reference nuclide.
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-ATTACHMENT 2
Confirmatory Measurements:Results
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1. NRC Face Lo'ded
a Scott Charcoal Cartridge Standard (SRS-17817-109)
(Standardized 11:00 CST, July 1,1985)
RBS RBS Results- NRC-Results. RBS/NRC. Comparison
- Nuclide Det. -(uCi/ sample) (uCi/ sample) Ratio Decision
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57Co- (1) =1.8210.08E-02 1.8910.01E-02 0.96' Agreement
(2) 2.0110.09E-02 '1.06 Agreement
60Co #1) 4.74 0.16E-02 4.8710.02E-02 0.97 Agreement
;
(2) ~5.02 0.17E-02 1.03 Agreement
asY (1) 1.0810.04E-01 1.1410.01E-01 0.95 Agreement
j (2) 1.1510.05E-01 1.01 ' Agreement
109Cd- (1) 1.1710.09E+00 1.1910.003E+0 0.98 Ngreement'
7 (2) 1.2610.10E+00 1.06 . Agreement ! , 11aSn (1) 6.8210.39E-02 7.3810.04E-02 0.92 Agreement 1 (2) 7.5810.43E-02 1.03 Agreement
'137Cs (1) 4.4010.24E-02 4.4410.02E-02 0.99 Agreement
(2) 4.8210.27E-02 1.09 Agreement
139Ce (1). 3.1210.21E-02 3.5310.02E-02 0.88 Agreement '
,
(2) 3.4710.23E-02 0.98 Agreement
zosHg (1) 6.9510.59E-02 7.2110.11E-02 0.96 Agreement
(2) 7.6110.64E-02
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1.05 Agreement
l 2. .NRC Particulate Filter Standard (SRS-17818-109)
- (Standardized 11
- 00 CST, July 1, -1985)
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RBS RBS Results NRC Results RBS/NRC Comparison
j- Nuclide Det. (uCi/ sample) (uCi/ sample) . Ratio Decision !
57Co (1) 3.8010.08E-02 1.9510.01E-02 0.92 Agreement
(2) 1.6210.07E-02 0.83 Agreement
80Co (1) 4.'6810.16E-02 4.6410.02E-02 1. 01' ' Agreement
- (2) 4.5210.16E-02 0.97 Agreement
asY (1) 1. 0810. 04E-01 1.0710.01E-01' 1~. 01 Agreement
.(2) 1.0410.04E-01 0.98 Agreement
- 109Cd (1) 1.1210.09E+00 1.32 0.003E+0 0.85 Agreement
(2) 1.0310.08E+00 0.78 Disagreement
113Sn (1) 7.0210.40E-02 6.8810.04E-02- 1.02 Agreement.
j .(2) 6.4810.37E-02 0.94 Agreement
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137Cs (1) 4.4310.24E-02 4.1110.02E-02 1.08 Agreement
(2) 4.19 0.23E-02 1.02 Agreement
139Ce (1) 3.0510.20E-02 3.34 0.01E-02 0.91 Agreement
(2) 2.81 0.19E-02 0.84 Disagreement
203Hg (1) 6.6110.56E-02 5.9510.08E-02 1.11 Agreement
(2) 6.0210.52E-02 1.01 Agreement
3. Simulated Liquid Radwaste (1 Liter Marinelli Beaker)
(Sampled 14:30 CST, January 28,.1986)
RBS RBS Results NRC Results RBS/NRC Comparison
Nuclide Det. (uCi/ml) (uCi/ml) Ratio Decision
24Na (1) 4.74 0.24E-05 4.4810.05E-05 1.06 Agreement
(2) 4.63 0.23E-05 1.03 Agreement
51Cr (1). 1.4310.28E-05 1.5310.27E-05 0.94 Agreement
(2)- 1.9310.34E-05 1.27 Agreement
54Mn (1) 7.2610.42E-06 7.1810.22E-06 1.01 Agreement
(2) 7.03i0.43E-06 0.98 Agreement
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56Mn (1) 1.4010.06E.04 1.2510.03E-04 1.13 Agreement
(2) 1.3510.06E-04 1.09 Agreement
ssCo (1) 2.5410.22E-06 3.7810.19E-06 -
No Comparison 1/
(2) 2.3810.23E-06 -
No Comparison I/
64Cu (1) 2.6910.15E-03 2.7710.06E-03 0.97 Agreement
(2) 2.65 0.15E-03 0.96 Agreement
97Nb (1) Not Identified 2/ 2.01 0.02E-04 -
Disagreement
(2) NotIdentified]/ Disagreement
99"Tc (1) Not Identif ed 2/ 2.1510.04E-05 -
Disagreement
(2) NotIdentified2/ -
Disagreement
99Mo (1) 1.3710.08E-05 8.20il.01E-06 1.67 Disagreement
(2) 1.48i0.09E-05 1.80 Disagreement
122Sb (1) 9.8110.71E-06 7.3310.21E-06 1.34 ,Disaoreement
(2) 8.5310.68E-06 1.16 Agreement
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132I (1) 3.0810.13E-05 2.7610.07E-05 1.12 Agreement
(2) 2.8310.18E-05 1.03 Agreement
133I (1)- Not Identified 3/ 2.9310.20E-06 -
Disagreement
(2) 1.9310.26E-07 0.07 Disagreement
1851 (1) 1.9710.75E-06 2.0910.76E-06 0.94 Agreement
(2) 2.6010.77E-06 1.24 Agreement
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187W (1) 2.9010.62E-06 2.0610.87E-06 -
No Comparison 1/
(2) 3.39 0.59E-06 -
No Comparison 1/
j
]/ Nuclide concentration' determined by the NRC was less than 10 percent
of the isotopic value stated in 10 CFR Part 20, Appendix B, Table-II;
therefore, no comparison was made.
~
l
'2/ Nuclide was not identified by the . licensee because it was not included
in the isotope library used for the analysis.
4
3/ Isotopic peak was present 'n the: spectral data;-however, the licensee's
peak confidence level for peak identification had been established so
as not to allow analysis.of nuclides at sensitivity levels equal to 10
l
percent of the isotopic values stated in 10 CFR Part 20, Appendix B, ,
t Table II, Column 2.
4. Reactor Coolant System Liquid (1 Liter Poly Bottle)
(Sampled 16:30 CST, January 28, 1986)
RBS RBS Results NRC Results RBS/NRC Comparison
Nuclide Det. (uCi/ml) -(uCi/ml) - Ratio Decision
24Na (1) 1.8010.10E-04 1.6710.03E-04 1.08 Agreement
(2) 1.7610.10E-04 1.05- Agreement
51Cr (1) 7.4711.68E-05 5.8210.78E-05 1.28 Agreement
<
-(2) 8.84 1.57E-05 1.52 Agreement
s4Mn (1) 2.2710.18E-05 1.8610.06E-05 1.22 Agreement
(2) 2.1410.17E-05 -1.16 Agreement
56M7 (1) 3.3910.56E-04 3.1310.41E-04 1.08 Agreement
(2) 3.6010.60E-04 1.15 Agreement
58C0 (1) 9.28tl.13E-06 9.2610.50E-06 1.00 Agreement
(2) 1.1510.12E-05 1.25' Agreement
64Cu (1) 1.0610.08E-02 8.4910.32E-03 1.25 Agreement
(2) 1.0610.09E-02 1. 2r Agreement
89Mo (1) 4.2010.29E-05 3.1210.34E-05 1.35 Agreement
(2) 3.7410.26E-05 1.20 Agreement
1225b (1) 5.0510.39E-05 2.0410.07E-05 2.48 Disagreement'
(2) 3.6310.31E-05 1.78- Disagreement
4
187W (1) 1.7610.44E-05 9.5812.04E-06 1.83 Agreement
(2) 1.5910.71E-05 1.66 Agreement
i
e
F*
*
l . * <
. .
4
5. Reactor Coolant System Tritium Sample
(Sampled 14:00 CST, January 27, 1986)
RBS Result N.'tC Result RBS/NRC Comparison
Nuclide (uCi/ml) (uCi/ml) Ratio Decision
3H 8.5610.31E-05 11.1010.59E-05 0.77 Agreement
6. RESL Unknown Liquid Sample
(Standardized 12:00 MST, January 11, 1985)
RBS Results NRC Results RBS/NRC. Comparison
Nuclide- (uCi/ml) (uCi/ml) Ratio Decision
3H 4.9610.49E-05 4.5610.09E-05 1.08 Agreement
88Sr 2/ -
No. Comparison
8 Sr 2/ -
No Comparison
137Cs 7.62il.03E-06 9.5010.19E-06 0.80 Agreement
6 Co 6.5010.88E-06 8.4910.17E-06 0.76 Agreement
1/ NRC results were taken from the st.andard certification supplied to the
Region IV office as prepared by RESL and traceable to the National
Bureau of Standards.
2/ Analytical results were not available from the licensee's contractor
at the time of the report.
.
_ - .. -_ _ . . _ _ . . . .
. .,
ATTACHMENT 3
I " Standup" Whole Body Counting System Confirmatory' Measurements ! 4
1. Positioning Verification Test
NRC Whole Body Phantom With 5 Percent Lung Burden Standard
Tests (1), (2), and'(3) .
~
i
RBS Result' RBS' Result RBS Result -Standard
j Nuclide Test (1) Test (2) Test (3) Average Deviation ! 60Co 0.636 0.629 '0.627 0.631 0.005 i
2. Analytical Measurements-
a. -Lung Test
NRC Whole Body Phantom With Various Lung Organ Burden Activities of
,
Cobalt-60
'
RBS Results NRC Results* RBS/NRC-
Test No. % MP0B (uCi) (uCi) Ratio
4 5% 0.568 0.500 1.14
5 10% 1.204 1.000 1.20
6 50% 4.780 5.000 0.96
j 7 100% 8.972 10.000; 0.90
8 200% 15.016 20.000 0.75
b. Thyroid Test
NRC Whole Body Phantom With Various Thyroid Organ Burden Activities of
Barium-133 as Mock Iodine-131
RBS Results NRC Results* RBS/NRC
-
Test No. % MP08 (uCi) (uCi) Ratio
'
9 5% 0.022 0.036 0.61
10 10% 6.042 0.070 0.60
11 50% 0.210 0.350 0.60
- 12 100% 0.354 0.700 0.50
1 13. 200% 0.760 1.400 0.54 1 !
l t
_ . . _._ . . . _ . _ . __ ._. - _ __ _ . . _
. .
2
c. Lung and Thyroid Scan
NRC Whole Body Phantom With Various Combinations of Lung and Thyroid
Organ Burden Activities of Cobalt-60 in the Lungs and Barium-133
as Mock Iodine-131 in the Thyroid
RBS Results NRC Results* RBS/NRC
Test No. Nuclide % MP08 (uCi) -(uCi) Ratio
14 133Ba 200% 0.763 1.400 0.'55
GoCO 10% 1.116 1.000 1.12
15 133Ba 100% 0.375 0.700 0.54
60C0 10% 1.130 1.000 1.13
16 133Ba 100% 0.370 0.700 0.53
60Co 5% 0.564 -0.500 1.13
17 133Ba 5% 0.031 0.036 0.86
SOCo 5% 0.588 0.500 1.18
18 133Ba 200% 0.629 1.400 0.45
60Co 200% 14.806 20.000 0.74
*
NRC values were taken from the standard certificates supplied
with the standat-ds as prepared by a commercial vendor and
verified by the NRC's laboratory, RESL, in Idaho Falls, Idaho,
s
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ATTACitMEtiT B ",
*
OPEN ACTI0fl ITEMS LIST
Date: c/n /r; Type Code: A= Allegation M= Miscellaneous
B= Bulletin 0=0 pen Item
Docket flo: so ver C= Circular R=Part 21 Report
(8) D= Deviation T= Temporary Instructions
E=50.55(e) U= Unresolved Item
L=LER V= Violation
floto - Max characters allowed for each entry shown in (1)
1 2 3- 4 5 6 7 8
Type I tera Report .
Responsible Update /Closecut Status
Item flo. Paragraph Section Module Description Report Code
(1) (8) (6) (4) (7) (186) (30) (1)
Y f?or-oi & -r K r 14725~ X. .'/~ <a. k T.a -..J Ca1:b'<wI. %
of A Crs Cho hy,y L
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Updatsd: mbar 5,1985 f[ffff
R3 port Resp. . .
Update /Close .
' Jyp3 I tts No. Pa rac ra ph. Sect. Module .ebcriptien Ettpo rt gbg . . .
0- 8414-004 6.8 T-RP GASEOUS RADWASTE SYSTEM 0 .
T-RP EFFLUENT RELEASE PROCEDURES 0
0 8414-005 7
8414-006 8 T-RP SOLID RADWASTE SYSTEM 0
0
T-RP RADIATION MONITORING SYSTEMS 0
0 8414-007 9
PROCESS AND EFFLUENT MONITORS
T-RP AIR CLEANING FILTER SYSTEMS 0 1
0- 841'4-008 10
0 8422-0'5 8 T-RP 84525 POSTACCIDENT SAMPLING SYSTEM ( 85-17 )( 85-47 ) ($.or) .A'C-
O' 8422-006 9 T-RP. 84525 FACILITIES, EQUIPMENT, & SUPPLIES ( 85-17 )( 85-47 )(g4.os) D d-
T-RP ~ NUREG-0737, ITEM lil.A.2 0
0 8505-001 13
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