ML20234D442
| ML20234D442 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 06/26/1987 |
| From: | Baer R, Murray B, Scott H NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20234D368 | List: |
| References | |
| RTR-REGGD-01.008, RTR-REGGD-1.008 50-482-87-12, IEIN-79-07, IEIN-79-7, IEIN-82-18, IEIN-82-43, IEIN-83-05, IEIN-83-25, IEIN-83-5, IEIN-83-59, IEIN-83-73, IEIN-84-24, IEIN-84-56, IEIN-84-61, IEIN-84-91, IEIN-85-048, IEIN-85-088, IEIN-85-48, IEIN-85-88, IEIN-86-022, IEIN-86-032, IEIN-86-22, IEIN-86-32, NUDOCS 8707070209 | |
| Download: ML20234D442 (8) | |
See also: IR 05000482/1987012
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APPENDIX C
U.S. NUCLEAR REGULATORY COMMISSION
REGION IV
NRC Inspection Report:
50-482/87-12
License:
Docket: 50-482
Licensee: Wolf Creek Nuclear Operations Corporation (WCNOC)
P. O. Box 411
Burlington, Kansas
66839
Facility Name: Wolf Creek Generating Station (WCGS)
Inspection At: WCGS Site, Burlington, Kansas
Inspection Conducted: May 18-22, 1987
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Inspectors:
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R. E.' Bier, Radiation
etialist, Facilities
Date
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Radiological Protect' n Section
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H. L. S'cott, Radiati,p Specialist, Facilities
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Radiological Proteta. ion Section
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Approved:
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B. Murr'ay, C6ief, Fac'
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Protection Section
Inspection Summary
Inspection Conducted May 18-22, 1987 (Report 50-482/87-12)
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Areas Inspected:
Routine, unannounced inspection of the radiation protection
program including:
organization and management controls; external occupational
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exposure control and personal dosimetry; internal exposure control and
assessment; control of radioactive materials and contamination, surveys, and
monitoring; facilities and equipment; and the licensee's actions concerning
certain NRC Inspection and Enforcement Information Notices (IEIN).
Results: Within the areas inspected, one violation and one deviation were
identified (violation, radiation protection manager qualifications,
paragraph 5; and deviation, airborne radioactivity monitors, paragraph 6).
8707070209 870630
ADOCK 05000482
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DETAILS
1.
Persons Contacted
- F. T. Rhodes, Vice President, Nuclear Operations
- G. D. Boyer, Plant Manager
- L. F. Breshears, Health Physics (HP) Supervisor
- H. M. Davis, HP Supervisor
D. M. Dullum, Engineer, Nuclear Operations Support (NOS)
- A. A. Freitag, Manager, Nuclear Plant Engineering
- C. J. Hoch, Quality Assurance (QA) Technician
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E. C. Holman, HP Technician
J. M. Isom, HP Technician
- C
Kesinger, Training Program Coordinator (HP)
- W. H. Ketchum, Radiological Services Lead Engineer
L. M. Kline, HP Technician
- W. M. Lindsay, Supervisor, Quality Systems
- 0. L. Maynard, Manager, Licensing
- G. A. McClelland, QA Auditor
C. M. Medenciy, HP Supervisor
M. H. Megehee, Compliance Engineer
- T.
S. Morrill, Site Health Physicist
J. R. Myer, Senior Engineer NOS
- M. M. Nichols, Superintendent, Plant Support
L. W. Nilges, HP Technician
- D. K. Parks, Training Coordinator
- G. J. Pendergrass, Licensing Engineer
L. T. Rice, HP Technician
- W. J. Rudolph II, Manager, QA
W. L. Selbe, Lead Engineer NOS
R. M. Stambaugh, Supervisor, Audits, QA
- K. M. Thrall, Radiological Services Senior Engineer
- M. G. Williams, Superintendent, Regulatory, Quality and_ Administration
N.R_C
- B. L. Bartlett, NRC Resident Inspector
J. E. Cummins, NRC Senior Resident Inspector
- Denotes those individuals present during the exit interview conducted on
May 22, 1987.
The NRC inspectors also interviewed several other licensee employees
including administrative, HP, and chemistry personnel.
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2.
Inspector Observations
The following are observations the NRC inspectors discussed with the
licensee during the exit interview on May 22, 1987. These observations
are not violations, deviations, unresolved items, or open items.
These
observations were identified for licensee consideration for program
improvement, but the observations have no specific regulatory requirement.
The licensee stated that these items would be considered.
Radiation Survey Instrumentation - The NRC inspectors noted that a large
number of the portable radiation monitoring instrumentation were not
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available to support plant operation.
This equipment was either out-of
service because the calibration had expired or was in need of repair.
Emergency Locker Equipment - Radiological monitoring equipment contained
in emergency kits are not removed and exchanged when their calibration
expires prior to the next scheduled inventory.
3.
Program Areas Inspected
The following program areas were inspected.
Unless otherwise noted, the
inspection was completed and revealed no violations, deviations,
unresolved items, or open items.
Notations after a specific inspection
item are used to identify the following:
I = item not inspected or only
partially inspected; V = violation; D = deviation; U = unresolved item;
and 0 = open item.
Procedure
Inspection Requirements
83722
Organization and Management Controls (Radiation Protection)
02.01 - Organization
02.02 - Staffing
02.03 - Radiation Protection Manager - V (see paragraph 5)
02.04 - Identification and Correction of Program
Weaknesses - I
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02.05 - Audits and Appraisal
83524
External Occupational Exposure Control
and Personal Dosimetry
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02.01 - Physical Controls
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02.02 - Administrative Controls
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02.03 - Personal Dosimetry
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83724
External Occupational Exposure Control
and Personal Dosimetry
02.01 - Audits and Appraisal
02.02 - Program Changes
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02.03 - Planning and Preparation for Outages
02.04 - Personal Dosimetry
02.05 - Administrative Controls
02.06 - Records, Reports, and Notifications
83525
Internal Exposure Control and Assessment
02.01 - Administrative Controls
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02.02 - Engineering Controls - I
02.03 - Respiratory Protection Equipment - I
02.04 - Air Sampling - I
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02.05 - Bioassay - I
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83725
Internal Exposure Control and Assessment
02.01 - Audits and Appraisals
02.02 - Program Changes
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02.03 - Planning and Preparation for Outages - I
02.04 - Assessing Intakes of Radioactive Materials - I
02.05 - Engineering Administrative Controls - I
02.06 - Respiratory Protection Equipment - 1
02.07 - Records, Reports, and Notifications
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83526
Control of Radioactive Materials and Contamination,
Surveys, and Monitoring
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02.01 - Area and Airborne Radiation Monitors - D (see
paragraph 6)
02.02 - Portable Survey, Sampling, and Contamination
Monitoring Instruments
02.03 - Protective Clothing and Equipment
02.04 - Radioactive Material and Contamination Control
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02.05 - In-Plant Surveys and Monitoring
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83726
Control of Radioactive Materials andContamination,
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Surveys, and Monitoring
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02.01 - Audits and Appraisals
02.02 - Program Changes
02.03 - Surveys and Monitoring
02.04 - Radioactive Materials and Contamination Controls
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83527
Facilities and Equipment
02.01 - Facilities
02.02 - Equipment
83727
Facilities and Equipment
02.01 - Facility Changes
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4.
Review of NRC Inspection and Enforcement Information Notices
The NRC inspectors reviewed the licensee's program for reviewing and
tracking information contained in certain IEINs.
The licensee's nuclear
operations support group tracks IEINs and other information in accordance
with Procedure KGP-1311, " Industrial Technical Information Program."
The licensee's responses to the following IEIN's were reviewed:
79-07
79-09
80-22
81-26
82-18
82-31
82-36
82-42
82-43
82-44
82-49
82-51
83-05
83-10
83-14
83-21
83-25
83-33
83-49
83-52
83-59
83-64
83-67
83-68
83-73
83-81
84-15
84-19
84-24
84-34
84-40
84-50
84-56
84-57
84-59
84-60
84-61
84-72
84-75
84-82
84-91
85-06
85-42
85-46
85-48
85-52
85-60
85-87
85-88
85-92
86-18
86-20
86-22
86-23
86-24
86-30
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86-32
86-41
86-42
86-43
86-44
86-46
86-76
86-90
86-103
86-107
87-03
87-07
The licensee's actions were generally considered acceptable. The NRC
inspectors discussed with licensee representatives that some IEINs involve
incidents which could involve more than one work group within the
licensee's organization.
However, procedures have not been established
for these types of incidents.
No violations or deviations were identified.
5.
Radiation Protection Manager Qualifications
The NRC inspectors reviewed the qualifications of the individual recently
assigned to the position of Site Health Physicist.
Technical Specification 6.3.1 states "each member of the unit staff shall
mee't or exceed the minimum qualifications of ANSI /ANS 3.1-1978, except for
the Site Health Physicist who shall meet or exceed the qualifications of
Regulatory Guide 1.8, September 1975 for a Radiation Protection Manager."
Regulatory Guide 1.8, September 1975 states, in part, the Radiation
Protection Manager (RPM) should be an experienced professional in applied
radiation protection at nuclear facilities dealing with radiation
protection problems and programs similar to those at nuclear power
stations. The RPM should have a Bachelor's Degree or the equivalent in a
science or engineering subject, including some formal training in
Rad 4ation Protection. The RPM should have at least 5 years of-
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professional experience in applied radiation protection and at least.3
years of this professional experience should be in applied radiation
protection work in a nuclear facility dealing with radiological problems
similar to those encountered in nuclear power stations, preferably in an
actual nuclear power station.
The NRC inspectors reviewed the personal resume and discussed work
assignments with the individual designated as the Site Health Physicist.
The NRC inspectors concluded that the individual had accumulated
experience which totaled approximately 3 years in applied radiation
protection and the equivalent of a bachelors degree.
The failure to designate an individual as the Site Health Physicist that
meets or exceeds the requirements of Regulatory Guide 1.8, September 1975
is considered an apparent violation of Technical Specification 6.3.1.
(482/8712-01)
6.
Airborne Radioactivity Monitoring
The NRC inspectors reviewed the licensee's airborne monitoring program to
determine agreement with Sections 12.3.4.2.2.2.9 and 12.5.2 1 of the USAR.
The USAR states that work areas will be monitored using portable
continuous airborne monitors (CAMS) as a primary method, with grab
sampling as a backup to the CAMS.
In addition, the licensee stated in
their April 22, 1986, letter in response to deviation (482/8542-01) that
CAMS would be utilized to sample the following locations:
1974' Auxiliary Building
2000' Auxiliary Building (north end)
2000' Auxiliary Building (south end)
1976' Radwaste Building
2047' Fuel Building
The NRC inspectors determined on May 20, 1987, the licensee did not have
CAMS sampling:
(1) the 2000-foot level in the auxiliary building (north
end), (2) the 1976-foot level in the radwaste building, and (3) the
2047-foot level in the fuel building.
The failure to implement the
specified airborne monitoring program is considered a deviation from -
commitments made to the NRC.
(482/8712-02)
7.
personnel Dosimetry
The NRC inspectors reviewed the licensee's personnel dosimetry program.
The licensee's primary, in-house, system is a Panasonic Thermoluminescent
Dosimeter (TLD) system. The licensee uses four TLD elements, two
(elements 1 and 2) are lithium borate and two (elements 3 and 4) calicum
sulfate in a type VD802 dosimeter. The filtration over the four elements
of the dosimeter is as follows:
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Element
Filtration (milligrams per square
Number
centimeter)
1
23 (mylar)
2
300 (plastic)
3
300 (plastic)
4
1000(plastic, lead)
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The licensee's quality assurance / quality control program includes the use
of spiked quality control badges which are read with each tray containing
50 badges.
Each month, approximately 15 spiked badges are also processed
which have been exposed to beta and gamma radiations, neutron radiation,
or gamma radiation. The radioactive sources used to spike these badges
are strontium-90, cesium-137, and moderated californium-252.
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The licensee had a contractor conduct a neutron and photon dose and energy
spectral measurement inside the reactor containment during 50 percent and
100 percent power operation.
It was concluded that the remmeter and
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albedo TLDs used were energy dependent in that they yield a higher
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response per unit flux at lower neutron energies (less than 10 key) than
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at higher energies. The overresponse for the remmeter was approximately
2.5 and the overresponse to the albedo TLD was typically a factor of 6 at
100 percent power and 17 at 50 percent power.
No violations or deviations were identified.
8.
Skin Contamination / Hot Particles
The inspector reviewed the licensee's prograrr for documenting skin and
clothing contamination and the operation of laundry facilities including
monitoring of protective clothing.
Procedures HPH 03-014 " Personnel
Decontamination," Revision 1, December 23, 1985, and HP 03-005 " Laundry
Facility Operation," Revision 0, November 16, 1984, have been implemented
to address the above areas.
The NRC inspectors discussed with licensee representatives the information
discussed in IEIN 86-23, " Excessive Skin Exposure Due to Contamination with
Hot Particles." The licensee utilizes friskers at the step-off pad leaving
contaminated areas and a personnel contamination monitor when exiting the
radiologically controlled area.
Protective clothing is monitored for
fixed contamination and clothing having fixed contamination greater than
0.5 mr/hr is segregated.
The NRC inspectors noted in procedure HPH 03-014
that the licensee does not routinely provide for a determination of skin
dose from contamination unless personnel contamination is greater than
100 counts per minute above background for longer than one hour nor are
there any directions for the removal and identification of the contamination
if it is a small area (particle).
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The licensee stated that they plan to review and upgrade
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procedure HPH 03-014 to ensure the information in IEIN is adequately
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addressed.
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No violations or deviations were identified.
9.
Exit Interview
The NRC inspectors met with the personnel identified in paragraph 1 at the
conclusion of the inspection on May 22, 1987.
The NRC inspectors
summarized the scope and findings of the inspection.
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