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{{Adams | |||
| number = ML20137K919 | |||
| issue date = 11/15/1985 | |||
| title = Insp Rept 50-482/85-36 on 850930-1004.No Violation or Deviation Noted.Major Areas Inspected:Corporate & Onsite Organizations & Mgt Controls,Staffing & Staff Qualifications & Chemistry/Radiochemistry Program | |||
| author name = Murray B, Nicholas J, Wise R | |||
| author affiliation = NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) | |||
| addressee name = | |||
| addressee affiliation = | |||
| docket = 05000482 | |||
| license number = | |||
| contact person = | |||
| document report number = 50-482-85-36, NUDOCS 8512030316 | |||
| package number = ML20137K899 | |||
| document type = INSPECTION REPORT, NRC-GENERATED, INSPECTION REPORT, UTILITY, TEXT-INSPECTION & AUDIT & I&E CIRCULARS | |||
| page count = 18 | |||
}} | |||
See also: [[see also::IR 05000930/2010004]] | |||
=Text= | |||
{{#Wiki_filter:_ | |||
. ,. | |||
APPENDIX | |||
U.S. NUCLEAR REGULATORY COMMISSION | |||
REGION IV | |||
NRC Inspection Report: STN 50-482/85-36 | |||
Docket: STN 50-482 License: NPF-42 | |||
Licensee: Kansas Gas and Electric Company (KG&E) | |||
P. O. Box 208 | |||
Wichita, Kansas 67201 | |||
Facility Name: Wolf Creek Generating Station (WCGS) | |||
Inspection At: WCGS Site, Burlington, Kansas ., | |||
Inspection Conducted: September 30-October 4, 1985 | |||
Inspectors: | |||
J.,flairNicholas,\SeniorRadiation | |||
Rf/rfff | |||
Date ' | |||
Mpecialist, Facilities Radiological | |||
Protection Section | |||
0. A WulAa | |||
Rpjfsell Wise, Radi'ation Specialist, | |||
uhkr | |||
Date | |||
UFacilities Radiological Protection | |||
Section | |||
Approved: 40 OA'N[ | |||
BlaineMurray, Chief,/ Facilities | |||
////f/8f | |||
Ddte ' | |||
Radiological Protection Section | |||
Inspection Summary ' | |||
Inspection Conducted September 30-October 4, 1985 (Report STN 50-482/85-36) | |||
Areas Inspected: Routine, announced inspection of the licensee's | |||
chemistry / radiochemistry program including review of corporate and onsite | |||
organizations and management controls, staffing and staff qualifications, | |||
training program, chemistry / radiochemistry program, quality assurance (QA) | |||
program of chemistry / radiochemistry activities, facilities and equipment, | |||
0512030316 851115 | |||
PDH ADOCK 05000432 | |||
G PDN | |||
r , | |||
' | |||
c , | |||
' | |||
2 | |||
postaccident sampling system (PASS), quality control of analytical | |||
measurements, and whole body counting system confirmatory measurements. | |||
The inspection involved 84 inspector-hours onsite and eight inspector-hours | |||
offsite by two NRC inspectors. | |||
Results: Within the areas inspected, no violations or deviations were | |||
identified. | |||
. | |||
~ | |||
r ;. | |||
o .' | |||
3 | |||
Details | |||
1. Persons Contacted | |||
*F. T. Rhodes, Plant Manager | |||
*G. D. Boyer, Superintendent, Technical Support | |||
*L. F. Breshears, Health. Physics Supervisor | |||
*H. Chernoff, Licensing Engineer | |||
0. A. Dominques, QA Technician | |||
K. R. Ellison, Regulatory, Quality, and Administration | |||
J. D. Hartley, Chemistry Technician | |||
J. D. Hawthorne, Secondary Chemistry Supervisor | |||
*S. A. Henry, Primary Chemistry Supervisor | |||
*C. J. Hoch, QA Technician | |||
R. L. Hoyt, Emergency Planning Administrator | |||
*J. A. Ives, Site Health Physicist | |||
*R. L. Logsdon, Site Chemist | |||
*A. S. Mah, Superintendent :f Training | |||
*W. C. Manwaring, Instrume.t-s and Controls (I&C) | |||
J. A. Moore, Chemistry Technician | |||
*T. S. Morrill, Radiochemist | |||
*M. M. Nichols, Superintendent of Plant Support | |||
C. L. Palmer, Radwaste Chemistry Supervisor | |||
*C. E. Parry, Superintendent of Quality Systems Engineering | |||
C. G. Patrick, Superintendent of Quality Evaluations | |||
*G. J. Pendergrass, Licensing Engineer | |||
*K. R. Peterson, Lead Licensing Engineering | |||
C. C. Reekte, QA Auditor | |||
B. D. Reischman, Senior Engineer (Nuclear Chemist), Nuclear Services | |||
*C. Rise, Health Physics Operations Supervisor | |||
H. Stubby, Chemistry Training Instruc+or | |||
C. A. Swartzendrubec, Manager of Radiological Services | |||
P. E. Turner, Manager of Nuclear Training | |||
*D. Walsh, Maintenance Services Supervisor | |||
*R. W. Wollum, I&C Coordinator | |||
*J. A. Zell, Superintendent of Operations | |||
*M. G. Williams, Superintendent of Regulatory, Quality, and Administration | |||
Others | |||
*B. L. Bartlett, NRC Resident Inspector | |||
*J. E. Cummins, Senior NRC Resident Inspector | |||
* Denotes those present during the exit briefing on October 4, 1985. . | |||
_ -. . -. --- | |||
-- | |||
. | |||
4 | |||
2. Chemistry / Radiochemistry Organization and Management Controls | |||
The NRC inspectors reviewed the licensee's corporate and onsite | |||
organizations and staffing regarding chemistry / radiochemistry activities | |||
to determine compliance with commitments in Chapter 13, " Conduct of | |||
Operations," in the Final Safety Analysis Report (FSAR) and requirements | |||
in Section 6.2, " Organization," in the Technical Specifications (TS) and | |||
WCGS administrative procedures. The NRC inspectors verified that the | |||
organizational structures of the corporate radiological services section | |||
, | |||
l | |||
and the onsite chemistry / radiochemistry section (C/RS) were as defined in | |||
the FSAR, TS, and WCGS administrative procedures. The NRC inspectors | |||
reviewed the corporate and WCGS management control procedures and position | |||
descriptions for the assignment of responsibilities for the management and | |||
implementation of the WCGS chemistry / radiochemistry program. The NRC | |||
inspectors verified that the administrative control responsibilities | |||
specified by the WCGS procedures were being implemented. | |||
The NRC inspectors reviewed the staffing of the corporate radiological | |||
services nuclear chemistry section and the onsite C/RS and noted that the | |||
corporate nuclear chemistry section was fully staffed and the two staff | |||
members were the same as reported in previous NRC inspection reports. | |||
t | |||
Since the previous NRC inspection in April 1985, the onsite C/RS had lost. | |||
its secondary chemistry supervisor and one chemistry technician. The | |||
secondary chemistry supervisor position had been filled by one of the | |||
senior chemistry technicians leaving 14 chemistry technician positions | |||
- | |||
filled and two vacancies. The site chemist was actively recruiting to | |||
fill the staff vacancies. | |||
No violations or deviations were identified. | |||
3. Chemistry / Radiochemistry Personnel Qualifications | |||
The NRC inspectors reviewed the qualifications of tha corporate | |||
radiological services nuclear chemistry personnel and onsite C/RS | |||
personnel to determine compliance with commitments in Cnapter 13 " Conduct | |||
of Operations," in the FSAR and requirements in Section 6.3, " Unit Staff | |||
Qualifications," in the TS. | |||
! | |||
The NRC inspectors reviewed the resumes for each of the corporate nuclear | |||
chemistry technical support personnel and verified that they met the | |||
I required qualifications specified in the FSAR and position descriptions. | |||
l Based on the review of the onsite C/RS staff resumes, the NRC inspectors | |||
determined that the site chemist, radiochemist, and the three laboratory | |||
supervisors met the ANSI /ANS 3.1-1978 qualifications as committed to in | |||
the FSAR and TS. Eight of fourteen chemistry technician positions were | |||
filled with personnel who satisfied the ANSI /ANS 3.1-1978 qualifications. | |||
The C/RS has eight shift qualified technicians, three technicians who | |||
should be shift qualified by December 1985, and three newly hired | |||
i | |||
, | |||
l | |||
l | |||
t | |||
L | |||
. | |||
. | |||
5 | |||
technicians who were presently in qualification training. The NRC | |||
inspectors determined that the C/RS shift rotation was composed of ANSI | |||
and shift qualified personnel. | |||
No violations or deviations were identified. | |||
4. Chemistry / Radiochemistry Training Program | |||
The NRC inspectors. reviewed the licensee's chemistry / radiochemistry | |||
training program to determine compliance with commitments in Chapter 13.2, | |||
" Training," in the FSAR, and requirements in Section 6.4, " Training," in | |||
the TS, 10 CFR Part 19.12, and WCGS administrative procedures. | |||
The NRC inspectors reviewed the training program for C/RS personnel with | |||
the nuclear training manager and the C/RS training coordinator. The | |||
nuclear training department had added to its staff an instructor with | |||
expertise in nuclear power plant chemistry / radiochemistry. The NRC | |||
inspectors inspected the new training facilities and training chemistry | |||
laboratory. | |||
. | |||
The NRC inspectors reviewed the nuclear training department procedures | |||
which had been completed and approved and determined that several WCGS | |||
administrative procedures were still being used to direct nuclear training | |||
department activities until all training department procedures have been | |||
completed. The licensee's program for qualification and training of WCGS | |||
chemistry staff is described in WCGS Procedure ADM-04-004, " Chemistry | |||
Group Training Program," Rev. 6, August 15, 1985. The NRC inspectors | |||
reviewed the licensee's program and found it being implemented in | |||
accordance with the above procedure. | |||
The NRC inspectors reviewed the licensee's task analysis for C/RS | |||
personnel which was in progress. | |||
The nuclear training department had developed a health physics / chemistry | |||
technician course in cooperation with local universities. The NRC | |||
inspectors reviewed the course lecture outline and study materials. | |||
The NRC inspectors reviewed the C/RS individual staff training records and | |||
qualification cards and found that training was being completed and | |||
documented as per procedure. | |||
No violations or deviations were identified. | |||
5. Chemistry / Radiochemistry Program | |||
The NRC inspectors reviewed the licensee's chemistry / radiochemistry | |||
program to determine compliance with commitments in Chapter 5, " Reactor | |||
Coolant System and Connected Systems;" Chapter 9, " Auxillary Systems;" and | |||
- - | |||
* . | |||
6 | |||
Chapter 11. " Radioactive Waste Management;" and requirements in | |||
Section 3/4.4.7, " Chemistry," in the TS and C/RS procedures. | |||
The NRC inspectors' review of the chemistry / radiochemistry program found | |||
that the licensee had completed and approved all identified administrative | |||
procedures, surveillance procedures, chemical control procedures, | |||
instrument calibration and performance check procedures, sampling | |||
procedures, and analytical procedures. A review of selected procedures, | |||
logs, and analytical data indicated that the C/RS had established | |||
sufficient administrative and analytical procedures to meet the | |||
requirements of the FSAR and TS. | |||
The NRC inspectors verified that the secondary chemistry laboratory | |||
instruments and the primary chemistry laboratory instruments had been | |||
calibrated according to procedures and a quality control program had been | |||
implemented. | |||
The NRC inspectors reviewed the status of the chemical and reagent | |||
inventory program and found the C/RS staff implementing the program in the | |||
laboratories according to procedure. | |||
No violations or deviations were identified. | |||
6. Quality Assurance Program | |||
The NRC inspectors reviewed the licensee's QA organization and | |||
audit / surveillance program regarding chemistry / radiochemistry activities | |||
to determine compliance with commitments in Chapter 17, " Quality Assur- | |||
ance," in the FSAR, requirements in Section 6.5.2.8, " Audits," in the TS, | |||
and QA manual procedures. | |||
The NRC inspectors. reviewed the QA department organization, selected QA | |||
audit and surveillance procedures, audit plans for 1985 and 1986, QA | |||
auditor qualificatibns, and audit and surveillance reports. Audit and | |||
surveillance reports generated from QA activities during 1984 and 1985 in | |||
the areas of chemistry and radiochemistry, chemistry personnel | |||
qualifications, chemistry instrument calibration and quality control, and | |||
system chemical control were reviewed for scope to ensure thoroughness of | |||
program evaluation and timely follow-up of identified deficiencies. The | |||
NRC inspectors found that the audit plans and checklists generated from a | |||
list of essential elements and attributes dealing with | |||
chemistry / radiochemistry activities were comprehensive and that the | |||
responses and corrective actions to QA findings were timely. It was noted | |||
that the chemistry / radiochemistry audits were being performed by an audit | |||
team which included a lead auditor qualified to the requirements of | |||
ANSI /ASME N45.2.23-1978 and a qualified technical specialist knowledgeable | |||
! in chemistry / radiochemistry activities at a nuclear power facility. | |||
No violations or deviations were identified, | |||
f | |||
I | |||
- . | |||
7 | |||
7. Facilities and Equipment | |||
. | |||
The NRC inspectors inspected the secondary chemistry laboratory and | |||
sampling area, primary chemistry laboratory and sampling area, | |||
radiochemistry counting room, postaccident sampling area, and radwaste | |||
laboratory and sampling area. The laboratories were equipped with the | |||
necessary chemicals, reagents, standards, labware, and analytical | |||
instrumentation to perform the required analytical procedures. At the | |||
time of the inspection, it was noted that three of the four high purity | |||
germanium (HPG) detectors connected to the Nuclear Data gamma spectroscopy | |||
system and located in the radwaste laboratory and radiochemistry counting | |||
room were temporarily out-of-service for electronic malfunctions. | |||
The NRC inspectors noticed during the inspection that every process | |||
instrument located on the secondary chemistry instrument panel (RM-171) | |||
was not operational. These process instruments included the sodium | |||
analyzers, dissolved oxygen analyzers, conductivity meters, pH cells, and | |||
associated recorders. The NRC inspectors discussed their concerns with | |||
this instrument problem with the licensee and it was emphasized at the | |||
exit briefing that this panel and associated instruments be kept in | |||
current calibration and routine operation to maintain current status of | |||
secondary chemical parameters and provide documentation of secondary | |||
chemistry trends. The licensee acknowledged the NRC inspectors' concerns | |||
with the inoperable instrumentation and stated that the instruments would | |||
be checked and repaired prior to November 8, 1985, subject to availability | |||
of needed parts. | |||
No violations or deviations were identified. | |||
8. Postaccident Sampling 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.d, | |||
"Postaccident Sampling," in the TS. | |||
The NRC inspectors inspected the areas in the plant where the PAS! | |||
hardware is installed. The NRC. inspectors verified that the equipment and | |||
associated procedures satisfied the requirements of NUREG-0737, | |||
Item II.B.3, and TS for representative sampling and analysis of reactor | |||
coolant and containment atmosphere following a reactor incident. The | |||
licensee had completed operator training as part of shift qualification | |||
training for chemistry technicians and had established an instrument | |||
calibration and maintenance program in compliance with TS requirements. | |||
The NRC inspectors reviewed the in-line instrument calibration and quality | |||
control records. The licensee demonstrated PASS operability by collecting | |||
a sample of reactor coolant and performing required analyses including | |||
, -- | |||
- . | |||
8 | |||
gamma isotopic, pH, boron, and conductivity. The licensee also collected | |||
a sample of containment atmosphere and performed a gamma isotopic | |||
analysis. The licensee demonstrated to the NRC inspectors the use of the | |||
manual local control panel for obtaining an undiluted grab sample for | |||
analyses. The NRC inspectors noted that the reactor coolant system | |||
hydrogen analyzer was out-of-service for repair and the dissolved oxygen | |||
analyzer was due for cell reconditioning. The NRC inspectors verified | |||
that work orders had been issued to maintain these instruments and place | |||
them back in service. The NRC inspectors determined that the licensee's | |||
procedures, analytical sensitivities, and analytical results of chemistry | |||
parameters were consistent with PASS requirements. ' | |||
l | |||
No violations or deviations were identified. | |||
9. | |||
' | |||
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 | |||
Section 6.8, " Procedures and Programs," in the TS. | |||
The NRC inspectors examined the licensee's radiochemistry counting room | |||
instrument calibration and quality control procedures, counting instrument | |||
calibration data and performance check data, and other documentation of | |||
instrument performance. Data for the period January through | |||
September 1985 were reviewed. | |||
No violations or deviations were identified. | |||
h 10. -Analytical Measurements | |||
, | |||
a. Confirmatory Measurements | |||
Confirmatory measurements were performed on the following samples and | |||
standards in the Region IV mobile laboratory at the WCGS site during | |||
the inspection: | |||
1. NRC Particulate Filter Standard (SRS-17818-109) | |||
2. Containment Atmosphere Charcoal Cartridge | |||
3. Liquid Radwaste Effluent (Waste Tank TH8078) | |||
4. Reactor Coolant System Gas | |||
5. Reactor Coolant System Degassed Liquid | |||
Reactor Coolant System Iodines | |||
' | |||
6. | |||
L | |||
_ -. | |||
- | |||
. | |||
9 | |||
* | |||
7. Ccc.tainment Atmosphere (1 Liter Gas Marinelli) | |||
. | |||
8. Containment Atmosphere (30 cc gas bulb) | |||
9. NRC Face Loaded Scott Charcoal Cartridge (SRS-17817-109) | |||
, | |||
10. NRC Tritum Sample | |||
. | |||
The confirmatory measurements counting arrangements are essentially | |||
, the same as those discussed in NRC Inspection Report 50-482/84-40. | |||
Attachment 1 contains the criteria used to compare results. | |||
' | |||
b. Results | |||
The licensee maintains three HPG detectors in the radiochemistry | |||
counting room and two HPG detectors in the radwaste laboratory. All- | |||
five detectors are used for routine isotopic analysis of radioactive | |||
samples to demonstrate compliance with TS and regulatory | |||
requirements. At the time of the inspection the two HPG detectors in | |||
the radwaste laboratory and one HPG detector in the radiochemistry | |||
counting room were out-of service. The two in-service HPG detectors | |||
were cross-checked on selected count!ag geometries. The HPG detector | |||
labeled (1) is maintained by the C/RS and the HPG detector labeled | |||
(2) is maintained by the health physics section. The analytical | |||
results from the two detectors were compared with the NRC results, as | |||
well as with each other. The licensee performed the tritium sample | |||
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 94 percent agreement with the NRC analysis | |||
results based on 58 agreement results out of 62 nuclides identified | |||
and compared. The licensee's tritium result on the NRC tritium | |||
sample was in agreement with the NRC analysis result. The licensee's | |||
results cross-checked with 100 percent agreement between the two HPG | |||
detectors for all counting geometries compared. | |||
Confirmatory measurements were performed by the licensee on a liquid | |||
unknown sample prepared by Radiological Environmental Sciences | |||
Laboratory using known nuclide concentrations of sosp, soSr, tritium, | |||
and gamma emitting nuclides. The licensee analyzed the sample and | |||
reported the results as requested. The licensee's analytical results | |||
were compared to the known sample activities and t he results of the | |||
comparisons are presented in Attachment 2, sample 11. The licensee's | |||
results were in 100 percent agreement with the certified activities | |||
in the sample. | |||
No violations or deviations were identified. | |||
i | |||
, , . - - --e - , _ _ , - - - - _ . . , .- . _ . - - , _ _ _ _ _ - | |||
. _ _ _. . _ _ . | |||
'O , | |||
i | |||
10 | |||
l | |||
11. Whole Body Counting System | |||
l The NRC inspectors reviewed the licensee's whole body counting system to | |||
I | |||
determine compliance with 10 CFR Part 20.103. | |||
l | |||
l | |||
The NRC inspectors reviewed the health physics procedures which provide | |||
guidance in the operation, calibration, and quality control of the whole | |||
body counting system. The licensee's calibration program and QA program | |||
l for the whole body counting system were reviewed. The licensee | |||
i | |||
! | |||
participates in a cross-check program on a qudrterly basis with a | |||
commercial vendor who supplies unknown activities in the phantom | |||
; configuration used by the licensee. | |||
The NRC inspectors supplied the 1icensee with a whole body counting | |||
phantom to perform confirmatory measurements in their chair style whole | |||
! body counting system. The counting arrangements were essentially the same | |||
as those discussed in NRC Inspection Report 50-482/84-40. The results of | |||
the body positioning test and the comparison of the analytical results of , | |||
the confirmatory measurements against the standard activities are | |||
tabluated in Attachment 3. | |||
The results of the body burden activity measurements were approximately | |||
the same as experienced during the tests performed during the NRC | |||
inspection conducted in October 1984. In general, the licensee's results | |||
were approximately 50 percent lower than the certified activities of the | |||
NRC standards. | |||
No violations or deviations were identified. | |||
12. Exit Briefing | |||
Tne NRC inspectors met with the NRC resident inspectors and licensee | |||
representatives identified in paragraph 1 of this report at the conclusion | |||
of the inspection on October 4, 1985. The NRC inspectors summarized the | |||
scope of the inspection and discussed the inspection findings including | |||
the results of the confirmatory measurements performed on various | |||
intercomparison samples and the whole body counting system. The licensee | |||
committed to repair the secondary chemistry process instrumentation on | |||
panel RM-171 by November 8, 1985, subject to availability of needed parts | |||
and have all the instruments calibrated and operational. | |||
i | |||
- .,- . -. . - - . - - _. _ _ - , - - .-- -. . _ _ - - . - .. _- - | |||
1 | |||
; * . | |||
; | |||
L ATTACHMENT 1 i | |||
! | |||
, | |||
triteria for Comparing Analytical Measurements . ! | |||
l The following are the criteria used in comparing the results of capability l | |||
i 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 ifmits vary in relationship to .the comparison | |||
1 | |||
1 | |||
of the resolution. | |||
} - | |||
i'' NRC VALUE | |||
i Resolution = NRC UNCERTAINTY l | |||
\ ' | |||
! | |||
4 | |||
Ratio = LICENSEE VALUE l | |||
: 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. | |||
i | |||
4 | |||
I | |||
4 | |||
q RESOLUTION AGREEMENT RATIO I | |||
- i | |||
<4 0.4 - 2.5 ; | |||
' | |||
' | |||
4-7 0.5 - 2.0 | |||
! 8 - 15 0.6 - 1.66 ' | |||
16 - 50 0.75 - 1.33 | |||
i 51 - 200 0.80 - 1.25 ' | |||
j. >200 0.85 - 1.18 | |||
> | |||
{ The above criteria are applied to the following analyses: | |||
: (1) Gamma Spectrometry. | |||
- | |||
; | |||
} (2) Tritium analyses of 11guld samples, | |||
q (3) Iodine on absorbers. | |||
l | |||
3 (4) noSr and 'OSr determinations. | |||
1 | |||
l | |||
; (5) Gross Beta where samples are counted on the same date using the same l | |||
j reference nuclide. | |||
;i | |||
[ | |||
i i | |||
4 : | |||
l ! | |||
i ! | |||
4 | |||
* | |||
!, | |||
! | |||
! | |||
; | |||
i | |||
- . . _ _ _ . _ _ - . | |||
- . | |||
ATTACHMENT 2 | |||
Confirmatory Measurements Results | |||
1. NRC Particluate Filter Standard (SRS-17818-109) | |||
(Standardized 11:00 CDT, July 1,1985) | |||
WCGS WCGS Results NRC Results WCGS/NRC Comparision- | |||
Nuclide Det. (uci/ Sample) (uCi/ Sample) Ratio Decision | |||
, | |||
57Co (1) 1.6610.02E-02 1.9210.01E-02 0.87 Agreement | |||
(2) 1.7910.03E-02 0.94 Agreement | |||
SOCo (1) 4.5210.06E-02 4.7410.04E-02 0.96 Agreement | |||
(2) 4.8110.08E-02 1.02 Agreement ( | |||
ssY (1) 1.0910.13E-01 1.1010.01E-01 0.99 Agreement ! | |||
(2) 1.1310.02E-01 1.03 Agreement ' | |||
108Cd (1) 1.0410.01E+00 1.3110.01E+00 0.80 Disagreement | |||
(2) 1.1310.01E+00 0.86 Agreement | |||
118Sn (1) 6.5210.07E-02 7.1010.04E-02 0.92 Agreement | |||
(2) 7.3510.09E-02 1.04 Agreement | |||
137Cs (1) 4.1810.05E-02 3.6110.02E-02 1.16 Agreement | |||
(2) 4.4610.06E-02 1.24 Agreement ' | |||
! | |||
taoCe (1) 3.0910.03E-02 3.3910.02E-02 0.91 Agreement | |||
(2) 3.4010.04E-02 1.00 Agreement | |||
20sHg (1) 5.7210.08E-02 6.1910.05E-02 .0.92 Agreement | |||
(2) 6.2710.12E-02 1.01 Agreement | |||
t | |||
2. Containment Atmosphere Charcoal Cartridge | |||
(Sampled 12:00 CDT, October 2, 1985) , | |||
WCGS WCGS Results NRC Results WCGS/NRC Comparision | |||
Nuclide Det. (uCi/ Sample) (uCi/ Sample) Ratio Decision | |||
1811 . (1) 5.1210.18E-03 5.5810.06E-03 0.92 Agreement l | |||
tas! (1) 1.3510.17E-03 1.5310.0SE-03 0.88 A0reement ; | |||
I | |||
l i | |||
: | |||
4 | |||
i | |||
L | |||
i | |||
_ _ _ _ . _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ . . _ _ . | |||
. - . - _ - _ _ . _ _ | |||
, | |||
. - , , | |||
~2- | |||
! | |||
3. Liquid Radwaste Effluent (Waste Tank TH8078) | |||
(Sampled 16:45 CDT, September 30, 1985) | |||
l | |||
l WCGS WCGS Results NRC Results WCGS/NRC Comparision | |||
l Nuclide Oe t. (uC1/ml) (uCf/ml) Ratio Decision | |||
stCr (1) 2.9710.44E-06 2.9910.39E-06 0.99 Agreement | |||
< | |||
54Mn (1) 1.3910.31E-07 Not Identified -- | |||
No Comparison 1 | |||
i ssCo (1) 6.6810.19E-06 6.5110.13E-06 1.03 Agreement . | |||
88Fe (1) 4.2910.86E-07 5.2910.63E-07 0.81 Agreement | |||
osZr (1) 3.1410.81E-07 2.4410.66E-07 1.29 Agreement | |||
1811 (1) 4.4610.71E-07 5.7310.50E-07 0.78 Agreement | |||
1831 (1) 6.0710.79E-07 6.0710.52E-07 1.00 Agreement | |||
140La (1) 7.0111.05E-07 8.6410.64E-07 0.81 Agreement | |||
187W (1) 2.0710.30E-07 2.0710.20E-07 1.00 Agreement | |||
E! No nuclide identification was made by the NRC. Nuclide activity | |||
was less than 10 percent of the isotopic value for liquid as | |||
stated in 10 CFR Part 20, Appendix B, Table II; therefore, no ' | |||
comparison was made. | |||
t | |||
4. Reactor Coolant System Gas | |||
(Sampled 16:55 CDT, October 1, 1985) | |||
WCGS WCGS Results NRC Results WCGS/NRC Comparision , | |||
Nuclide Det. (uCf/cc) (uCi/cc) Ratio Decision | |||
41Ar (1) 4.0710.04E-02 1# -- | |||
No Comparison | |||
"S"Kr (1) 1.4410.05E-03 1.2710.02E-03 1.13 Agreement | |||
a7Kr (1) 2.9410.14E-03 2.4010.09E-03 1.23 Agreement ! | |||
anKr (1) 3.8810.17E-03 3.2510.07E-03 1.19 Agreement | |||
l | |||
ssXe (1) 3.7410.12E-03 3.5510.05E-03 1.05 Agreement | |||
186*Xe (1) 4.0310.35E-03 2/ -- | |||
No Comparison | |||
: | |||
F | |||
t | |||
. _ _ _ _ _ _ | |||
:s * . | |||
-3- | |||
135Xe (1) 6.7210.08E-03 5.8410.04E-03 1.15 Agreement | |||
188Xe (1) 7.58E-03 2/ -- | |||
No Comparsion | |||
1 Isotopic peak was present in the spectial data; however, the | |||
gas efficiency calibration used for the analysis did not | |||
include efficiencies for gamma energies greater than 514 kev. | |||
Therefore, no NRC analysis was made and no comparison. | |||
Isotopic activity had decayed to below the lower level of | |||
detectability at the time of sample analysis. | |||
5. Resctor Coolant System Degassed Liquid | |||
(Sampled 15:14 COT, October 1, 1985) | |||
WCGS WCGS Results NRC Results WCGS/NRC Comparision | |||
Nuclide Det. (uct/ml) (uCi/ml) Ratio Decision | |||
24Na (1) 1.8110.05E-03 1.9110.03E-03 0.94 Agreement | |||
naCo (1) 5.6710.42E-04 4.9310.23E-04 1.15 Agreement | |||
anRb (1) 5.7810.43E-03 2.2210.27E-02 0.26 Disagreement | |||
80Rb (1) 5.6110.27E-03 1/ -- | |||
No Comparison | |||
'8Nb (1) 2.7510.33E-04 1.4410.19E-04 1.91 Disagreement | |||
"7Nb (1) 9.78E-05 8.9112.56E-05 1.10 Agreement | |||
388Cs (1) 1.1010.02E-02 1.2610.02E-02 0.87 Agreement | |||
188Ba (1) 1.2410.23E-03 1.6810.16E-03 0.74 Agreement | |||
187W (1) 4.52E-04 9.7911.05E-04 0.46 Disagreement | |||
1 Primary line for nuclide identification was not present; | |||
therefore, no nuclide identification and no comparison. | |||
6. Reactor Coolant System lodine Analysis | |||
"(Sampled 16:14 CDI, October 1,198b) | |||
WCGS WCGS Results NRC Results WCGS/NRC Comparision | |||
Nuclide Det. (uci/ml) (ucf/ml) Ratio DecIsfon | |||
tan! (1) 2.4710.24E-04 2,4810.15E 04 1.00 Agreement | |||
_ _ _ _ _ _ _ _ _ _ _ - _ _ _ - _ - - _ _ _ . - | |||
.- - - . _ -. .. .. | |||
. | |||
-a | |||
l | |||
! . | |||
-4- l | |||
; | |||
I | |||
1s21 (1) 5.1410.07E-03 4.6610.05E-03 1.10 Agreement | |||
1881 (1) , | |||
3.0110.04E-03 2.7510.02E-03 1.09 Agreement | |||
184I (1) 1.0710.02E-02 1.1410.02E-02 0.94 Agreement | |||
185I (1) 5.64 0.15E-03 6.3910.11E-03 0.88 Agreement | |||
7. Containment Atmosphere (1 Liter Gas Marinelli) | |||
(Sampled 10:25 CDT, October 2,1985) | |||
WCGS WCGS Results NRC Results 'WCGS/NRC Comparision | |||
Nuclide Det. (uct/ Sample) (uCf/ Sample) Ratio Decision | |||
41Ar (1) 1.8710.12E-06 1! -- | |||
No Comparison | |||
(2) 1.6010.13E-06 | |||
183Xe (1) 9.8110.15E-06 9.7310.19E-06 1.01 Agreement | |||
(2) 9.6510.19E-06 0.99 Agreement | |||
tasXe (1) 9.8511.42E-08 8.94tl.95E-08 1.10 Agreement | |||
(2) 9.41tl.64E-08 1.05 Agreement | |||
1 Isotopic peak was present in the spectral data; however, the | |||
gas efficiency calibration used for the analysis did not include | |||
efficiencies for gamma energies greater than 514 kev. Therefore, | |||
no NRC analysis was made and no comparison. | |||
8. Containment Atmosphere (30cc gas bulb) | |||
(Sampled 10:18 COT, October 2,1985) | |||
WCGS WCGS Results NRC Results WCGS/NRC Comparision | |||
Nuclide Det. (uCi/cc) (uC1/cc) Ratio Decision ; | |||
183Xe (1) 4.1810.61E-06 4.31tl.01E-06 0.97 Agreement | |||
, | |||
' | |||
9. NRC Face Loaded Scott Charcoal Cartridge Standard (SRS-17817-109) " | |||
(Standardized 11:00 COT, July 1,1985) | |||
WCGS WCGS Results NRC Results II WCGS/NRC Comparision | |||
Nuclide De t ._ (uct/ Sample) (uci/ Sample) Ratio Decision | |||
87C0 (2) 1.6410.03E-02 1.95E-02 0.84 Agreement | |||
soCo (2) 4.9910.08E-02 4.99E-02 1.00 Agreement | |||
w | |||
r . | |||
. . , | |||
i | |||
-5- | |||
1 | |||
asY (2) 1.2010.02E-01 1.18E-01 1.02 Agreement | |||
108Cd (2) 9.5510.09E-01 1.26E+00 0.76 Agreement | |||
218Sn (2) 7.2610.11E-02 7.42E-02 0.98 Agreement | |||
137Cs (2) 4.5710.07E-02 4.75E-02 0.96 Agreement | |||
188Ce (2) 3.2110.05E-02 3.54E-02 0.91 Agreement | |||
20sHg (2) 6.6510.13E-02 7.08E-02 0.94 Agreement | |||
1! | |||
' | |||
! NRC results were taken from the standard certification | |||
supplied to the Region IV office by the commercial vendor | |||
and traceable to the National Bureau of Standards. | |||
10. NRC Tritium Sample | |||
(Sampled 16:31 CDT, October 1, 1985) | |||
WCGS Results NRC Results WCGS/NRC Comparision | |||
Nuclide (uC1/ Sample) (uCi/ Sample) Ratio _ Decision | |||
, | |||
8H 2.96E-01 2.90E-01 1.02 Agreement | |||
11. RESL Unknown Liquid Sample | |||
(Standarized 12:00 MSi, January 11, 1985) | |||
WCGS Results NRC Results 1 WCGS/NRC Comparision | |||
Nuclide (uCi/ml) (uCi/ml) Ratio Decision | |||
8H 6.8910.39E-05 6.5410.13E-05 1.05 Agreement | |||
soSr 3.1210.09E-04 2.7510.08E-04 1.13 Agreement | |||
80Sr 2.2810.19E-05 3.0310.12E-05 0.75 Agreement | |||
is7Cs 1.3810.06E-05 1.3610.03E-05 1.01 Agreement | |||
60Co 1.2610.07E-05 1.2210.02E-05 1.03 Agreement | |||
1 NRC results were taken from the standard certification | |||
supplied to the Region IV office as prepared by RESL | |||
and traceable to the National Bureau of Standards. , | |||
..- | |||
E | |||
[.s . | |||
} | |||
l | |||
k | |||
L | |||
ATTACHMENT 3 | |||
Whole Body Countina System Confirmatory Measurements | |||
1. Positioning Verification Test | |||
' | |||
NRC Whole Body Phantom With 5 Percent Lung Burden Standard | |||
' Tests (1), (2), and (3) | |||
WCGS Result WCGS Result WCGS Result Standard | |||
Nuclide Test (1) Test (2) Test (3) Average Deviation | |||
60Co 0.274 0.292 0.310 0.292 0.018 | |||
2. Analytical Measurements | |||
a. Luna Test | |||
NRC Whole Body Phantom With Various Lung Organ | |||
Burden Activities of Cobalt-60 | |||
WCGS Results NRC Results* WCGS/NRC | |||
Test No. % MP08 (uC1) (uC1) Ratio | |||
4 5% 0.307 0.500 0.61 | |||
5 10% 0.572 1.000 0.57 | |||
6 50% 2.488 5.000 0.50 | |||
7 100% 4.584 10.000 0.46 | |||
8 200% 9.040 20.000 0.45 | |||
b. Thyroid Test | |||
NRC Whole Body Phantom With Various Thyroid Oraan | |||
Burden Activities of Barium-133 as Mock Iodine-131 | |||
WCGS Results NRC Results* WCGS/NRC | |||
Test No. % MPOB (uci) (uCl) Ratio | |||
9 5% 0.016 0.036 0.44 | |||
10 10% 0.033 0.070 0.47 | |||
_. | |||
_ . | |||
o .. .. | |||
-2- | |||
11L 50% 0.168 0.350 0.48 | |||
12 100% 0.363 0.700 0.52 | |||
13 200% 0.686 1.400 0.49 | |||
c. Luna and Thyroid Scan | |||
NRC Whole Body Phantom With Various Combinations of Luna | |||
and Thyroid Organ Burden Activities of Cobalt-60 in the | |||
Lunas and Barium-133 as Mock Iodine-131 in the Thyroid | |||
WCGS Results NRC Results* WCGS/NRC | |||
Test No. Nuclide % MP0B (uCI) (uC1) Ratio | |||
14 133Ba 200% 0.709 1.400 0.51 | |||
60Co 10% 0.517 1.000 0.52 r | |||
15 183Ba 100% 0.335 0.700 0.48 l | |||
SoCo 10% 0.507 1.000 0.51 ' | |||
I | |||
16 183Ba 100% 0.332 0.700 0.47 ' | |||
60Co 5% 0.263 0.500 0.53 | |||
17 188Ba 5% 0.018 0.036 0.50 , | |||
ooCo 5% 0.263 0.500 0.53 | |||
d. Luna ' Text (mixed isotopic standards) | |||
NRC Whole Body Phantom With Various Luna Organ , | |||
, | |||
Burden Activities of Cesium-137 and Cobalt-60 ' | |||
WCGS Results NRC Results* WCGS/NRC | |||
Test No. Nuclide % MPOB (uC1) (uC1) Ratio , | |||
3 | |||
18 837Cs 5% 0.825 1.570 0.53 | |||
80Co 5% 0.201 0.502 0.40 | |||
19 187Cs 10% 1.677 3.130 0.53 | |||
80Co 10% 0.457 1.000 0.46 | |||
20 137Cs 50% 7.51 15.70 0.48 | |||
80Co 50% 2.03 5.02 0.40 | |||
* | |||
NRC values were taken from the standard certificates | |||
supplied with the standards as prepared by a commercial | |||
vendor and verified by the NRC's reference laboratory. | |||
RESL, in Idaho Falls, Idaho, | |||
t | |||
l | |||
._ | |||
}} |
Revision as of 14:11, 22 July 2020
ML20137K919 | |
Person / Time | |
---|---|
Site: | Wolf Creek ![]() |
Issue date: | 11/15/1985 |
From: | Murray B, Nicholas J, Wise R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
To: | |
Shared Package | |
ML20137K899 | List: |
References | |
50-482-85-36, NUDOCS 8512030316 | |
Download: ML20137K919 (18) | |
See also: IR 05000930/2010004
Text
_
. ,.
APPENDIX
U.S. NUCLEAR REGULATORY COMMISSION
REGION IV
NRC Inspection Report: STN 50-482/85-36
Docket: STN 50-482 License: NPF-42
Licensee: Kansas Gas and Electric Company (KG&E)
P. O. Box 208
Wichita, Kansas 67201
Facility Name: Wolf Creek Generating Station (WCGS)
Inspection At: WCGS Site, Burlington, Kansas .,
Inspection Conducted: September 30-October 4, 1985
Inspectors:
J.,flairNicholas,\SeniorRadiation
Rf/rfff
Date '
Mpecialist, Facilities Radiological
Protection Section
0. A WulAa
Rpjfsell Wise, Radi'ation Specialist,
uhkr
Date
UFacilities Radiological Protection
Section
Approved: 40 OA'N[
BlaineMurray, Chief,/ Facilities
////f/8f
Ddte '
Radiological Protection Section
Inspection Summary '
Inspection Conducted September 30-October 4, 1985 (Report STN 50-482/85-36)
Areas Inspected: Routine, announced inspection of the licensee's
chemistry / radiochemistry program including review of corporate and onsite
organizations and management controls, staffing and staff qualifications,
training program, chemistry / radiochemistry program, quality assurance (QA)
program of chemistry / radiochemistry activities, facilities and equipment,
0512030316 851115
PDH ADOCK 05000432
G PDN
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2
postaccident sampling system (PASS), quality control of analytical
measurements, and whole body counting system confirmatory measurements.
The inspection involved 84 inspector-hours onsite and eight inspector-hours
offsite by two NRC inspectors.
Results: Within the areas inspected, no violations or deviations were
identified.
.
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Details
1. Persons Contacted
- F. T. Rhodes, Plant Manager
- G. D. Boyer, Superintendent, Technical Support
- L. F. Breshears, Health. Physics Supervisor
- H. Chernoff, Licensing Engineer
0. A. Dominques, QA Technician
K. R. Ellison, Regulatory, Quality, and Administration
J. D. Hartley, Chemistry Technician
J. D. Hawthorne, Secondary Chemistry Supervisor
- S. A. Henry, Primary Chemistry Supervisor
- C. J. Hoch, QA Technician
R. L. Hoyt, Emergency Planning Administrator
- J. A. Ives, Site Health Physicist
- R. L. Logsdon, Site Chemist
- A. S. Mah, Superintendent :f Training
- W. C. Manwaring, Instrume.t-s and Controls (I&C)
J. A. Moore, Chemistry Technician
- T. S. Morrill, Radiochemist
- M. M. Nichols, Superintendent of Plant Support
C. L. Palmer, Radwaste Chemistry Supervisor
- C. E. Parry, Superintendent of Quality Systems Engineering
C. G. Patrick, Superintendent of Quality Evaluations
- G. J. Pendergrass, Licensing Engineer
- K. R. Peterson, Lead Licensing Engineering
C. C. Reekte, QA Auditor
B. D. Reischman, Senior Engineer (Nuclear Chemist), Nuclear Services
- C. Rise, Health Physics Operations Supervisor
H. Stubby, Chemistry Training Instruc+or
C. A. Swartzendrubec, Manager of Radiological Services
P. E. Turner, Manager of Nuclear Training
- D. Walsh, Maintenance Services Supervisor
- R. W. Wollum, I&C Coordinator
- J. A. Zell, Superintendent of Operations
- M. G. Williams, Superintendent of Regulatory, Quality, and Administration
Others
- B. L. Bartlett, NRC Resident Inspector
- J. E. Cummins, Senior NRC Resident Inspector
- Denotes those present during the exit briefing on October 4, 1985. .
_ -. . -. ---
--
.
4
2. Chemistry / Radiochemistry Organization and Management Controls
The NRC inspectors reviewed the licensee's corporate and onsite
organizations and staffing regarding chemistry / radiochemistry activities
to determine compliance with commitments in Chapter 13, " Conduct of
Operations," in the Final Safety Analysis Report (FSAR) and requirements
in Section 6.2, " Organization," in the Technical Specifications (TS) and
WCGS administrative procedures. The NRC inspectors verified that the
organizational structures of the corporate radiological services section
,
l
and the onsite chemistry / radiochemistry section (C/RS) were as defined in
the FSAR, TS, and WCGS administrative procedures. The NRC inspectors
reviewed the corporate and WCGS management control procedures and position
descriptions for the assignment of responsibilities for the management and
implementation of the WCGS chemistry / radiochemistry program. The NRC
inspectors verified that the administrative control responsibilities
specified by the WCGS procedures were being implemented.
The NRC inspectors reviewed the staffing of the corporate radiological
services nuclear chemistry section and the onsite C/RS and noted that the
corporate nuclear chemistry section was fully staffed and the two staff
members were the same as reported in previous NRC inspection reports.
t
Since the previous NRC inspection in April 1985, the onsite C/RS had lost.
its secondary chemistry supervisor and one chemistry technician. The
secondary chemistry supervisor position had been filled by one of the
senior chemistry technicians leaving 14 chemistry technician positions
-
filled and two vacancies. The site chemist was actively recruiting to
fill the staff vacancies.
No violations or deviations were identified.
3. Chemistry / Radiochemistry Personnel Qualifications
The NRC inspectors reviewed the qualifications of tha corporate
radiological services nuclear chemistry personnel and onsite C/RS
personnel to determine compliance with commitments in Cnapter 13 " Conduct
of Operations," in the FSAR and requirements in Section 6.3, " Unit Staff
Qualifications," in the TS.
!
The NRC inspectors reviewed the resumes for each of the corporate nuclear
chemistry technical support personnel and verified that they met the
I required qualifications specified in the FSAR and position descriptions.
l Based on the review of the onsite C/RS staff resumes, the NRC inspectors
determined that the site chemist, radiochemist, and the three laboratory
supervisors met the ANSI /ANS 3.1-1978 qualifications as committed to in
the FSAR and TS. Eight of fourteen chemistry technician positions were
filled with personnel who satisfied the ANSI /ANS 3.1-1978 qualifications.
The C/RS has eight shift qualified technicians, three technicians who
should be shift qualified by December 1985, and three newly hired
i
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l
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t
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.
.
5
technicians who were presently in qualification training. The NRC
inspectors determined that the C/RS shift rotation was composed of ANSI
and shift qualified personnel.
No violations or deviations were identified.
4. Chemistry / Radiochemistry Training Program
The NRC inspectors. reviewed the licensee's chemistry / radiochemistry
training program to determine compliance with commitments in Chapter 13.2,
" Training," in the FSAR, and requirements in Section 6.4, " Training," in
the TS, 10 CFR Part 19.12, and WCGS administrative procedures.
The NRC inspectors reviewed the training program for C/RS personnel with
the nuclear training manager and the C/RS training coordinator. The
nuclear training department had added to its staff an instructor with
expertise in nuclear power plant chemistry / radiochemistry. The NRC
inspectors inspected the new training facilities and training chemistry
laboratory.
.
The NRC inspectors reviewed the nuclear training department procedures
which had been completed and approved and determined that several WCGS
administrative procedures were still being used to direct nuclear training
department activities until all training department procedures have been
completed. The licensee's program for qualification and training of WCGS
chemistry staff is described in WCGS Procedure ADM-04-004, " Chemistry
Group Training Program," Rev. 6, August 15, 1985. The NRC inspectors
reviewed the licensee's program and found it being implemented in
accordance with the above procedure.
The NRC inspectors reviewed the licensee's task analysis for C/RS
personnel which was in progress.
The nuclear training department had developed a health physics / chemistry
technician course in cooperation with local universities. The NRC
inspectors reviewed the course lecture outline and study materials.
The NRC inspectors reviewed the C/RS individual staff training records and
qualification cards and found that training was being completed and
documented as per procedure.
No violations or deviations were identified.
5. Chemistry / Radiochemistry Program
The NRC inspectors reviewed the licensee's chemistry / radiochemistry
program to determine compliance with commitments in Chapter 5, " Reactor
Coolant System and Connected Systems;" Chapter 9, " Auxillary Systems;" and
- -
- .
6
Chapter 11. " Radioactive Waste Management;" and requirements in
Section 3/4.4.7, " Chemistry," in the TS and C/RS procedures.
The NRC inspectors' review of the chemistry / radiochemistry program found
that the licensee had completed and approved all identified administrative
procedures, surveillance procedures, chemical control procedures,
instrument calibration and performance check procedures, sampling
procedures, and analytical procedures. A review of selected procedures,
logs, and analytical data indicated that the C/RS had established
sufficient administrative and analytical procedures to meet the
requirements of the FSAR and TS.
The NRC inspectors verified that the secondary chemistry laboratory
instruments and the primary chemistry laboratory instruments had been
calibrated according to procedures and a quality control program had been
implemented.
The NRC inspectors reviewed the status of the chemical and reagent
inventory program and found the C/RS staff implementing the program in the
laboratories according to procedure.
No violations or deviations were identified.
6. Quality Assurance Program
The NRC inspectors reviewed the licensee's QA organization and
audit / surveillance program regarding chemistry / radiochemistry activities
to determine compliance with commitments in Chapter 17, " Quality Assur-
ance," in the FSAR, requirements in Section 6.5.2.8, " Audits," in the TS,
and QA manual procedures.
The NRC inspectors. reviewed the QA department organization, selected QA
audit and surveillance procedures, audit plans for 1985 and 1986, QA
auditor qualificatibns, and audit and surveillance reports. Audit and
surveillance reports generated from QA activities during 1984 and 1985 in
the areas of chemistry and radiochemistry, chemistry personnel
qualifications, chemistry instrument calibration and quality control, and
system chemical control were reviewed for scope to ensure thoroughness of
program evaluation and timely follow-up of identified deficiencies. The
NRC inspectors found that the audit plans and checklists generated from a
list of essential elements and attributes dealing with
chemistry / radiochemistry activities were comprehensive and that the
responses and corrective actions to QA findings were timely. It was noted
that the chemistry / radiochemistry audits were being performed by an audit
team which included a lead auditor qualified to the requirements of
ANSI /ASME N45.2.23-1978 and a qualified technical specialist knowledgeable
! in chemistry / radiochemistry activities at a nuclear power facility.
No violations or deviations were identified,
f
I
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7
7. Facilities and Equipment
.
The NRC inspectors inspected the secondary chemistry laboratory and
sampling area, primary chemistry laboratory and sampling area,
radiochemistry counting room, postaccident sampling area, and radwaste
laboratory and sampling area. The laboratories were equipped with the
necessary chemicals, reagents, standards, labware, and analytical
instrumentation to perform the required analytical procedures. At the
time of the inspection, it was noted that three of the four high purity
germanium (HPG) detectors connected to the Nuclear Data gamma spectroscopy
system and located in the radwaste laboratory and radiochemistry counting
room were temporarily out-of-service for electronic malfunctions.
The NRC inspectors noticed during the inspection that every process
instrument located on the secondary chemistry instrument panel (RM-171)
was not operational. These process instruments included the sodium
analyzers, dissolved oxygen analyzers, conductivity meters, pH cells, and
associated recorders. The NRC inspectors discussed their concerns with
this instrument problem with the licensee and it was emphasized at the
exit briefing that this panel and associated instruments be kept in
current calibration and routine operation to maintain current status of
secondary chemical parameters and provide documentation of secondary
chemistry trends. The licensee acknowledged the NRC inspectors' concerns
with the inoperable instrumentation and stated that the instruments would
be checked and repaired prior to November 8, 1985, subject to availability
of needed parts.
No violations or deviations were identified.
8. Postaccident Sampling 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.d,
"Postaccident Sampling," in the TS.
The NRC inspectors inspected the areas in the plant where the PAS!
hardware is installed. The NRC. inspectors verified that the equipment and
associated procedures satisfied the requirements of NUREG-0737,
Item II.B.3, and TS for representative sampling and analysis of reactor
coolant and containment atmosphere following a reactor incident. The
licensee had completed operator training as part of shift qualification
training for chemistry technicians and had established an instrument
calibration and maintenance program in compliance with TS requirements.
The NRC inspectors reviewed the in-line instrument calibration and quality
control records. The licensee demonstrated PASS operability by collecting
a sample of reactor coolant and performing required analyses including
, --
- .
8
gamma isotopic, pH, boron, and conductivity. The licensee also collected
a sample of containment atmosphere and performed a gamma isotopic
analysis. The licensee demonstrated to the NRC inspectors the use of the
manual local control panel for obtaining an undiluted grab sample for
analyses. The NRC inspectors noted that the reactor coolant system
hydrogen analyzer was out-of-service for repair and the dissolved oxygen
analyzer was due for cell reconditioning. The NRC inspectors verified
that work orders had been issued to maintain these instruments and place
them back in service. The NRC inspectors determined that the licensee's
procedures, analytical sensitivities, and analytical results of chemistry
parameters were consistent with PASS requirements. '
l
No violations or deviations were identified.
9.
'
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
Section 6.8, " Procedures and Programs," in the TS.
The NRC inspectors examined the licensee's radiochemistry counting room
instrument calibration and quality control procedures, counting instrument
calibration data and performance check data, and other documentation of
instrument performance. Data for the period January through
September 1985 were reviewed.
No violations or deviations were identified.
h 10. -Analytical Measurements
,
a. Confirmatory Measurements
Confirmatory measurements were performed on the following samples and
standards in the Region IV mobile laboratory at the WCGS site during
the inspection:
1. NRC Particulate Filter Standard (SRS-17818-109)
2. Containment Atmosphere Charcoal Cartridge
3. Liquid Radwaste Effluent (Waste Tank TH8078)
4. Reactor Coolant System Gas
5. Reactor Coolant System Degassed Liquid
Reactor Coolant System Iodines
'
6.
L
_ -.
-
.
9
7. Ccc.tainment Atmosphere (1 Liter Gas Marinelli)
.
8. Containment Atmosphere (30 cc gas bulb)
9. NRC Face Loaded Scott Charcoal Cartridge (SRS-17817-109)
,
10. NRC Tritum Sample
.
The confirmatory measurements counting arrangements are essentially
, the same as those discussed in NRC Inspection Report 50-482/84-40.
Attachment 1 contains the criteria used to compare results.
'
b. Results
The licensee maintains three HPG detectors in the radiochemistry
counting room and two HPG detectors in the radwaste laboratory. All-
five detectors are used for routine isotopic analysis of radioactive
samples to demonstrate compliance with TS and regulatory
requirements. At the time of the inspection the two HPG detectors in
the radwaste laboratory and one HPG detector in the radiochemistry
counting room were out-of service. The two in-service HPG detectors
were cross-checked on selected count!ag geometries. The HPG detector
labeled (1) is maintained by the C/RS and the HPG detector labeled
(2) is maintained by the health physics section. The analytical
results from the two detectors were compared with the NRC results, as
well as with each other. The licensee performed the tritium sample
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 94 percent agreement with the NRC analysis
results based on 58 agreement results out of 62 nuclides identified
and compared. The licensee's tritium result on the NRC tritium
sample was in agreement with the NRC analysis result. The licensee's
results cross-checked with 100 percent agreement between the two HPG
detectors for all counting geometries compared.
Confirmatory measurements were performed by the licensee on a liquid
unknown sample prepared by Radiological Environmental Sciences
Laboratory using known nuclide concentrations of sosp, soSr, tritium,
and gamma emitting nuclides. The licensee analyzed the sample and
reported the results as requested. The licensee's analytical results
were compared to the known sample activities and t he results of the
comparisons are presented in Attachment 2, sample 11. The licensee's
results were in 100 percent agreement with the certified activities
in the sample.
No violations or deviations were identified.
i
, , . - - --e - , _ _ , - - - - _ . . , .- . _ . - - , _ _ _ _ _ -
. _ _ _. . _ _ .
'O ,
i
10
l
11. Whole Body Counting System
l The NRC inspectors reviewed the licensee's whole body counting system to
I
determine compliance with 10 CFR Part 20.103.
l
l
The NRC inspectors reviewed the health physics procedures which provide
guidance in the operation, calibration, and quality control of the whole
body counting system. The licensee's calibration program and QA program
l for the whole body counting system were reviewed. The licensee
i
!
participates in a cross-check program on a qudrterly basis with a
commercial vendor who supplies unknown activities in the phantom
- configuration used by the licensee.
The NRC inspectors supplied the 1icensee with a whole body counting
phantom to perform confirmatory measurements in their chair style whole
! body counting system. The counting arrangements were essentially the same
as those discussed in NRC Inspection Report 50-482/84-40. The results of
the body positioning test and the comparison of the analytical results of ,
the confirmatory measurements against the standard activities are
tabluated in Attachment 3.
The results of the body burden activity measurements were approximately
the same as experienced during the tests performed during the NRC
inspection conducted in October 1984. In general, the licensee's results
were approximately 50 percent lower than the certified activities of the
NRC standards.
No violations or deviations were identified.
12. Exit Briefing
Tne NRC inspectors met with the NRC resident inspectors and licensee
representatives identified in paragraph 1 of this report at the conclusion
of the inspection on October 4, 1985. The NRC inspectors summarized the
scope of the inspection and discussed the inspection findings including
the results of the confirmatory measurements performed on various
intercomparison samples and the whole body counting system. The licensee
committed to repair the secondary chemistry process instrumentation on
panel RM-171 by November 8, 1985, subject to availability of needed parts
and have all the instruments calibrated and operational.
i
- .,- . -. . - - . - - _. _ _ - , - - .-- -. . _ _ - - . - .. _- -
1
- * .
L ATTACHMENT 1 i
!
,
triteria for Comparing Analytical Measurements . !
l The following are the criteria used in comparing the results of capability l
i 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 ifmits vary in relationship to .the comparison
1
1
of the resolution.
} -
i NRC VALUE
i Resolution = NRC UNCERTAINTY l
\ '
!
4
Ratio = LICENSEE VALUE l
- 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.
i
4
I
4
q RESOLUTION AGREEMENT RATIO I
- i
<4 0.4 - 2.5 ;
'
'
4-7 0.5 - 2.0
! 8 - 15 0.6 - 1.66 '
16 - 50 0.75 - 1.33
i 51 - 200 0.80 - 1.25 '
j. >200 0.85 - 1.18
>
{ The above criteria are applied to the following analyses:
- (1) Gamma Spectrometry.
-
} (2) Tritium analyses of 11guld samples,
q (3) Iodine on absorbers.
l
3 (4) noSr and 'OSr determinations.
1
l
- (5) Gross Beta where samples are counted on the same date using the same l
j reference nuclide.
- i
[
i i
4 :
l !
i !
4
!,
!
!
i
- . . _ _ _ . _ _ - .
- .
ATTACHMENT 2
Confirmatory Measurements Results
1. NRC Particluate Filter Standard (SRS-17818-109)
(Standardized 11:00 CDT, July 1,1985)
WCGS WCGS Results NRC Results WCGS/NRC Comparision-
Nuclide Det. (uci/ Sample) (uCi/ Sample) Ratio Decision
,
57Co (1) 1.6610.02E-02 1.9210.01E-02 0.87 Agreement
(2) 1.7910.03E-02 0.94 Agreement
SOCo (1) 4.5210.06E-02 4.7410.04E-02 0.96 Agreement
(2) 4.8110.08E-02 1.02 Agreement (
ssY (1) 1.0910.13E-01 1.1010.01E-01 0.99 Agreement !
(2) 1.1310.02E-01 1.03 Agreement '
108Cd (1) 1.0410.01E+00 1.3110.01E+00 0.80 Disagreement
(2) 1.1310.01E+00 0.86 Agreement
118Sn (1) 6.5210.07E-02 7.1010.04E-02 0.92 Agreement
(2) 7.3510.09E-02 1.04 Agreement
137Cs (1) 4.1810.05E-02 3.6110.02E-02 1.16 Agreement
(2) 4.4610.06E-02 1.24 Agreement '
!
taoCe (1) 3.0910.03E-02 3.3910.02E-02 0.91 Agreement
(2) 3.4010.04E-02 1.00 Agreement
20sHg (1) 5.7210.08E-02 6.1910.05E-02 .0.92 Agreement
(2) 6.2710.12E-02 1.01 Agreement
t
2. Containment Atmosphere Charcoal Cartridge
(Sampled 12:00 CDT, October 2, 1985) ,
WCGS WCGS Results NRC Results WCGS/NRC Comparision
Nuclide Det. (uCi/ Sample) (uCi/ Sample) Ratio Decision
1811 . (1) 5.1210.18E-03 5.5810.06E-03 0.92 Agreement l
tas! (1) 1.3510.17E-03 1.5310.0SE-03 0.88 A0reement ;
I
l i
4
i
L
i
_ _ _ _ . _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ . . _ _ .
. - . - _ - _ _ . _ _
,
. - , ,
~2-
!
3. Liquid Radwaste Effluent (Waste Tank TH8078)
(Sampled 16:45 CDT, September 30, 1985)
l
l WCGS WCGS Results NRC Results WCGS/NRC Comparision
l Nuclide Oe t. (uC1/ml) (uCf/ml) Ratio Decision
stCr (1) 2.9710.44E-06 2.9910.39E-06 0.99 Agreement
<
54Mn (1) 1.3910.31E-07 Not Identified --
No Comparison 1
i ssCo (1) 6.6810.19E-06 6.5110.13E-06 1.03 Agreement .
88Fe (1) 4.2910.86E-07 5.2910.63E-07 0.81 Agreement
osZr (1) 3.1410.81E-07 2.4410.66E-07 1.29 Agreement
1811 (1) 4.4610.71E-07 5.7310.50E-07 0.78 Agreement
1831 (1) 6.0710.79E-07 6.0710.52E-07 1.00 Agreement
140La (1) 7.0111.05E-07 8.6410.64E-07 0.81 Agreement
187W (1) 2.0710.30E-07 2.0710.20E-07 1.00 Agreement
E! No nuclide identification was made by the NRC. Nuclide activity
was less than 10 percent of the isotopic value for liquid as
stated in 10 CFR Part 20, Appendix B, Table II; therefore, no '
comparison was made.
t
4. Reactor Coolant System Gas
(Sampled 16:55 CDT, October 1, 1985)
WCGS WCGS Results NRC Results WCGS/NRC Comparision ,
Nuclide Det. (uCf/cc) (uCi/cc) Ratio Decision
41Ar (1) 4.0710.04E-02 1# --
No Comparison
"S"Kr (1) 1.4410.05E-03 1.2710.02E-03 1.13 Agreement
a7Kr (1) 2.9410.14E-03 2.4010.09E-03 1.23 Agreement !
anKr (1) 3.8810.17E-03 3.2510.07E-03 1.19 Agreement
l
ssXe (1) 3.7410.12E-03 3.5510.05E-03 1.05 Agreement
186*Xe (1) 4.0310.35E-03 2/ --
No Comparison
F
t
. _ _ _ _ _ _
- s * .
-3-
135Xe (1) 6.7210.08E-03 5.8410.04E-03 1.15 Agreement
188Xe (1) 7.58E-03 2/ --
No Comparsion
1 Isotopic peak was present in the spectial data; however, the
gas efficiency calibration used for the analysis did not
include efficiencies for gamma energies greater than 514 kev.
Therefore, no NRC analysis was made and no comparison.
Isotopic activity had decayed to below the lower level of
detectability at the time of sample analysis.
5. Resctor Coolant System Degassed Liquid
(Sampled 15:14 COT, October 1, 1985)
WCGS WCGS Results NRC Results WCGS/NRC Comparision
Nuclide Det. (uct/ml) (uCi/ml) Ratio Decision
24Na (1) 1.8110.05E-03 1.9110.03E-03 0.94 Agreement
naCo (1) 5.6710.42E-04 4.9310.23E-04 1.15 Agreement
anRb (1) 5.7810.43E-03 2.2210.27E-02 0.26 Disagreement
80Rb (1) 5.6110.27E-03 1/ --
No Comparison
'8Nb (1) 2.7510.33E-04 1.4410.19E-04 1.91 Disagreement
"7Nb (1) 9.78E-05 8.9112.56E-05 1.10 Agreement
388Cs (1) 1.1010.02E-02 1.2610.02E-02 0.87 Agreement
188Ba (1) 1.2410.23E-03 1.6810.16E-03 0.74 Agreement
187W (1) 4.52E-04 9.7911.05E-04 0.46 Disagreement
1 Primary line for nuclide identification was not present;
therefore, no nuclide identification and no comparison.
6. Reactor Coolant System lodine Analysis
"(Sampled 16:14 CDI, October 1,198b)
WCGS WCGS Results NRC Results WCGS/NRC Comparision
Nuclide Det. (uci/ml) (ucf/ml) Ratio DecIsfon
tan! (1) 2.4710.24E-04 2,4810.15E 04 1.00 Agreement
_ _ _ _ _ _ _ _ _ _ _ - _ _ _ - _ - - _ _ _ . -
.- - - . _ -. .. ..
.
-a
l
! .
-4- l
I
1s21 (1) 5.1410.07E-03 4.6610.05E-03 1.10 Agreement
1881 (1) ,
3.0110.04E-03 2.7510.02E-03 1.09 Agreement
184I (1) 1.0710.02E-02 1.1410.02E-02 0.94 Agreement
185I (1) 5.64 0.15E-03 6.3910.11E-03 0.88 Agreement
7. Containment Atmosphere (1 Liter Gas Marinelli)
(Sampled 10:25 CDT, October 2,1985)
WCGS WCGS Results NRC Results 'WCGS/NRC Comparision
Nuclide Det. (uct/ Sample) (uCf/ Sample) Ratio Decision
41Ar (1) 1.8710.12E-06 1! --
No Comparison
(2) 1.6010.13E-06
183Xe (1) 9.8110.15E-06 9.7310.19E-06 1.01 Agreement
(2) 9.6510.19E-06 0.99 Agreement
tasXe (1) 9.8511.42E-08 8.94tl.95E-08 1.10 Agreement
(2) 9.41tl.64E-08 1.05 Agreement
1 Isotopic peak was present in the spectral data; however, the
gas efficiency calibration used for the analysis did not include
efficiencies for gamma energies greater than 514 kev. Therefore,
no NRC analysis was made and no comparison.
8. Containment Atmosphere (30cc gas bulb)
(Sampled 10:18 COT, October 2,1985)
WCGS WCGS Results NRC Results WCGS/NRC Comparision
Nuclide Det. (uCi/cc) (uC1/cc) Ratio Decision ;
183Xe (1) 4.1810.61E-06 4.31tl.01E-06 0.97 Agreement
,
'
9. NRC Face Loaded Scott Charcoal Cartridge Standard (SRS-17817-109) "
(Standardized 11:00 COT, July 1,1985)
WCGS WCGS Results NRC Results II WCGS/NRC Comparision
Nuclide De t ._ (uct/ Sample) (uci/ Sample) Ratio Decision
87C0 (2) 1.6410.03E-02 1.95E-02 0.84 Agreement
soCo (2) 4.9910.08E-02 4.99E-02 1.00 Agreement
w
r .
. . ,
i
-5-
1
asY (2) 1.2010.02E-01 1.18E-01 1.02 Agreement
108Cd (2) 9.5510.09E-01 1.26E+00 0.76 Agreement
218Sn (2) 7.2610.11E-02 7.42E-02 0.98 Agreement
137Cs (2) 4.5710.07E-02 4.75E-02 0.96 Agreement
188Ce (2) 3.2110.05E-02 3.54E-02 0.91 Agreement
20sHg (2) 6.6510.13E-02 7.08E-02 0.94 Agreement
1!
'
! NRC results were taken from the standard certification
supplied to the Region IV office by the commercial vendor
and traceable to the National Bureau of Standards.
10. NRC Tritium Sample
(Sampled 16:31 CDT, October 1, 1985)
WCGS Results NRC Results WCGS/NRC Comparision
Nuclide (uC1/ Sample) (uCi/ Sample) Ratio _ Decision
,
8H 2.96E-01 2.90E-01 1.02 Agreement
11. RESL Unknown Liquid Sample
(Standarized 12:00 MSi, January 11, 1985)
WCGS Results NRC Results 1 WCGS/NRC Comparision
Nuclide (uCi/ml) (uCi/ml) Ratio Decision
8H 6.8910.39E-05 6.5410.13E-05 1.05 Agreement
soSr 3.1210.09E-04 2.7510.08E-04 1.13 Agreement
80Sr 2.2810.19E-05 3.0310.12E-05 0.75 Agreement
is7Cs 1.3810.06E-05 1.3610.03E-05 1.01 Agreement
60Co 1.2610.07E-05 1.2210.02E-05 1.03 Agreement
1 NRC results were taken from the standard certification
supplied to the Region IV office as prepared by RESL
and traceable to the National Bureau of Standards. ,
..-
E
[.s .
}
l
k
L
ATTACHMENT 3
Whole Body Countina System Confirmatory Measurements
1. Positioning Verification Test
'
NRC Whole Body Phantom With 5 Percent Lung Burden Standard
' Tests (1), (2), and (3)
WCGS Result WCGS Result WCGS Result Standard
Nuclide Test (1) Test (2) Test (3) Average Deviation
60Co 0.274 0.292 0.310 0.292 0.018
2. Analytical Measurements
a. Luna Test
NRC Whole Body Phantom With Various Lung Organ
Burden Activities of Cobalt-60
WCGS Results NRC Results* WCGS/NRC
Test No. % MP08 (uC1) (uC1) Ratio
4 5% 0.307 0.500 0.61
5 10% 0.572 1.000 0.57
6 50% 2.488 5.000 0.50
7 100% 4.584 10.000 0.46
8 200% 9.040 20.000 0.45
b. Thyroid Test
NRC Whole Body Phantom With Various Thyroid Oraan
Burden Activities of Barium-133 as Mock Iodine-131
WCGS Results NRC Results* WCGS/NRC
Test No. % MPOB (uci) (uCl) Ratio
9 5% 0.016 0.036 0.44
10 10% 0.033 0.070 0.47
_.
_ .
o .. ..
-2-
11L 50% 0.168 0.350 0.48
12 100% 0.363 0.700 0.52
13 200% 0.686 1.400 0.49
c. Luna and Thyroid Scan
NRC Whole Body Phantom With Various Combinations of Luna
and Thyroid Organ Burden Activities of Cobalt-60 in the
Lunas and Barium-133 as Mock Iodine-131 in the Thyroid
WCGS Results NRC Results* WCGS/NRC
Test No. Nuclide % MP0B (uCI) (uC1) Ratio
14 133Ba 200% 0.709 1.400 0.51
60Co 10% 0.517 1.000 0.52 r
15 183Ba 100% 0.335 0.700 0.48 l
SoCo 10% 0.507 1.000 0.51 '
I
16 183Ba 100% 0.332 0.700 0.47 '
60Co 5% 0.263 0.500 0.53
17 188Ba 5% 0.018 0.036 0.50 ,
ooCo 5% 0.263 0.500 0.53
d. Luna ' Text (mixed isotopic standards)
NRC Whole Body Phantom With Various Luna Organ ,
,
Burden Activities of Cesium-137 and Cobalt-60 '
WCGS Results NRC Results* WCGS/NRC
Test No. Nuclide % MPOB (uC1) (uC1) Ratio ,
3
18 837Cs 5% 0.825 1.570 0.53
80Co 5% 0.201 0.502 0.40
19 187Cs 10% 1.677 3.130 0.53
80Co 10% 0.457 1.000 0.46
20 137Cs 50% 7.51 15.70 0.48
80Co 50% 2.03 5.02 0.40
NRC values were taken from the standard certificates
supplied with the standards as prepared by a commercial
vendor and verified by the NRC's reference laboratory.
t
l
._