ML060600168
ML060600168 | |
Person / Time | |
---|---|
Site: | South Texas |
Issue date: | 02/27/2006 |
From: | Shannon M Plant Support Branch Region IV |
To: | Sheppard J South Texas |
References | |
-RFPFR IR-06-008 | |
Download: ML060600168 (20) | |
See also: IR 05000498/2006008
Text
February 27, 2006
James J. Sheppard, President and
Chief Executive Officer
STP Nuclear Operating Company
P.O. Box 289
Wadsworth, Texas 77483
SUBJECT: SOUTH TEXAS PROJECT ELECTRIC GENERATING STATION - NRC
RADIATION SAFETY TEAM INSPECTION REPORT 05000498/2006008;
Dear Mr. Sheppard:
On January 26, 2006, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection
at your South Texas Project Electric Generating Station, Units 1 and 2, facility The enclosed
Radiation Safety Team inspection report documents the inspection findings which were
discussed with Mr. Gary Parkey, Executive Vice President of Generation and General Plant
Manager, and other members of your staff.
The inspection examined activities conducted under your license as they relate to safety and
compliance with the Commissions rules and regulations and with the conditions of your license.
The team reviewed selected procedures and records, observed activities, and interviewed
personnel. Specifically, the team evaluated the inspection areas within the Radiation Protection
Strategic Performance Area that are scheduled for review every two years. These areas are:
- Radiation Monitoring Instrumentation
- Radioactive Gaseous and Liquid Effluent Treatment and Monitoring Systems
- Radioactive Material Processing and Transportation
- Radiological Environmental Monitoring Program and Radioactive Material Control
Program
This inspection report documents one self-revealing, non-cited violation of very low safety
significance (Green). Additionally, one licensee-identified violation, which was also determined
to be of very low safety significance, is listed in Section 4OA7 of this report. If you contest
these non-cited violations or their significance, you should provide a response within 30 days of
the date of this inspection report, with the basis for your denial, to the U.S. Nuclear Regulatory
Commission, ATTN: Document Control Desk, Washington DC 20555-0001; with copies to the
Regional Administrator, U.S. Nuclear Regulatory Commission Region IV, 611 Ryan Plaza Drive,
Suite 400, Arlington, Texas 76011-4005; the Director, Office of Enforcement, U.S. Nuclear
Regulatory Commission, Washington DC 20555-001; and the NRC Resident Inspector at the
South Texas, Units 1 and 2, facility.
STP Nuclear Operating Company -2-
In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter, its
enclosure, and your response (if any) will be made available electronically for public inspection
in the NRC Public Document Room or from the Publicly Available Records (PARS) component
of NRCs document system (ADAMS). ADAMS is accessible from the NRC Web site at
http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).
Should you have any questions concerning this inspection, we will be pleased to discuss them
with you.
Sincerely,
//RA//
Michael P. Shannon, Chief
Plant Support Branch
Division of Reactor Safety
Dockets: 50-498
50-499
Licenses: NPF-76
Enclosure:
NRC Inspection Report 05000498/2006008; 05000499/2006008
w/Attachment: Supplemental Information
cc w/enclosure:
E. D. Halpin
Vice President, Oversight
STP Nuclear Operating Company
P.O. Box 289
Wadsworth, TX 77483
S. M. Head, Manager, Licensing
STP Nuclear Operating Company
P.O. Box 289, Mail Code: N5014
Wadsworth, TX 77483
C. Kirksey/C. M. Canady
City of Austin
Electric Utility Department
721 Barton Springs Road
Austin, TX 78704
J. J. Nesrsta/R. K. Temple
City Public Service Board
P.O. Box 1771
San Antonio, TX 78296
STP Nuclear Operating Company -3-
Jack A. Fusco/Michael A. Reed
12301 Kurland Drive
Houston, TX 77034
Jon C. Wood
Cox Smith Matthews
112 E. Pecan, Suite 1800
San Antonio, TX 78205
A. H. Gutterman, Esq.
1111 Pennsylvania Avenue NW
Washington, DC 20004
Records Center
700 Galleria Parkway
Atlanta, GA 30339-3064
Director, Division of Compliance & Inspection
Bureau of Radiation Control
Texas Department of State Health Services
1100 West 49th Street
Austin, TX 78756
Brian Almon
Public Utility Commission
William B. Travis Building
P.O. Box 13326
1701 North Congress Avenue
Austin, TX 78701-3326
Environmental and Natural
Resources Policy Director
P.O. Box 12428
Austin, TX 78711-3189
Judge, Matagorda County
Matagorda County Courthouse
1700 Seventh Street
Bay City, TX 77414
Terry Parks, Chief Inspector
Texas Department of Licensing
and Regulation
Boiler Program
P.O. Box 12157
Austin, TX 78711
STP Nuclear Operating Company -4-
Susan M. Jablonski
Office of Permitting, Remediation and Registration
Texas Commission on Environmental Quality
MC-122, P.O. Box 13087
Austin, TX 78711-3087
Ted Enos
4200 South Hulen
Suite 630
Fort Worth, TX 76109
STP Nuclear Operating Company -5-
Electronic distribution by RIV:
Regional Administrator (BSM1)
DRP Director (ATH)
DRS Director (DDC)
DRS Deputy Director (RJC1)
Senior Resident Inspector (JXC2)
Branch Chief, DRP/A (CEJ1)
Senior Project Engineer, DRP/A (TRF)
Team Leader, DRP/TSS (RLN1)
RITS Coordinator (KEG)
Only inspection reports to the following:
T. Bloomer, OEDO RIV Coordinator (TEB)
ROPreports
Sunsi Review Completed: Yes ADAMS: Yes G No Initials: mps
Publicly Available G Non-Publicly Available G Sensitive Non-Sensitive
R:\_STP\2006\STP2006-08RP-Team-LC2.wpd
RIV:DRS/PSB PSB PSB PSB C:PSB
LCCarsonII GLGuerra LTRicketson BDBaca DLStearns
/RA/ /RA/ /RA/ /RA/ /RA/
02/ 23 /06 02/ 27 /06 02/ 23 /06 02/ 22 /06 02/ 27 /06
C:PSB C:DRP/A C:PSB
MPShannon CEJohnson MPShannon
/RA/ /RA/ /RA/
02/ 27 /06 02/ 27 /06 02/ 27 /06
OFFICIAL RECORD COPY T=Telephone E=E-mail F=Fax
ENCLOSURE
U.S. NUCLEAR REGULATORY COMMISSION
REGION IV
Dockets: 50-498, 50-499
Licenses: NPF-76
Report No: 05000498/2006008
Licensee: STP Nuclear Operating Company
Facility: South Texas Project Electric Generating Station, Units 1 and 2
Location: FM 521 - 8 miles west of Wadsworth
Wadsworth, Texas 77483
Dates: January 23 - 26, 2006
Inspectors: L. C. Carson II, Senior Health Physicist - Team Leader
B. D. Baca, Health Physicist
G. L. Guerra, Health Physicist
L. T. Ricketson, P.E., Senior Health Physicist
D. L. Stearns, Health Physicist
Approved By: Michael P. Shannon, Chief, Plant Support Branch
Division of Reactor Safety
-1- Enclosure
SUMMARY OF FINDINGS
IR 05000498/2006008, 05000499/2006008; January 23-26 2006; South Texas Project Electric
Generating Station; Radiation Monitoring Instrumentation and Protective Equipment;
Radioactive Gaseous and Liquid Effluent Treatment and Monitoring Systems; and Radiological
Environmental Monitoring Program and Radioactive Material Control Program
The report covered a one week period of inspection on site by a team of five region-based
health physics inspectors. Based upon the results of the inspection, the team reviewed one
self-revealing violation of very low safety significance (Green). The significance of most
findings is indicated by their color (Green, White, Yellow, Red) using IMC 0609, Significance
Determination Process, (SDP). Findings for which the SDP does not apply may be Green or
be assigned a severity level after NRC management review. The NRC's program for
overseeing the safe operation of commercial nuclear power reactors is described in
NUREG-1649, Reactor Oversight Process, Revision 3, dated July 2000.
A. NRC-Identified and Self-Revealing Findings
Cornerstone: Public Radiation Safety (PS)
- Green. The team reviewed two examples of a self-revealing non-cited violation of
Technical Specification 6.8.1, resulting from the licensees failure to prevent radioactive
material from being unconditionally released from a radiologically controlled area. The
first example involved a radiation detection instrument with fixed radioactive
contamination. The second example involved a contaminated lifting sling that was used
to remove equipment and containers from the containment building. In both examples,
the radioactive material was identified after it was removed from a radiologically
controlled area but before it left the protected area. Corrective actions for the first
example involved counseling the responsible individual. Corrective actions for the
second example are still being evaluated. Both examples were entered into the
licensees corrective action program as Condition Reports 04-4266 and 05-14345.
This finding is greater than minor because it was associated with a Public Radiation
Safety cornerstone attribute (material release) and it affected the associated
cornerstone objective in that the failure to control radioactive material decreases the
licensees assurance that the public will not receive unnecessary dose. Using the Public
Radiation Safety Significance Determination Process, the team determined that the
finding had very low safety significance because: (1) the finding was a radioactive
material control finding, (2) it was not a transportation finding, (3) it did not result in
public dose greater than 0.005 rem, and (4) radioactive material was not released from
the protected area more than five times. Additionally, this finding had cross-cutting
aspects associated with human performance. In the first example, a radiation protection
technician failed to maintain direct supervision of the contaminated instrument. In the
second example, the procedural guidance allowed the licensee to use only portable GM
instruments on large items despite the loss of detection sensitivity.
-2- Enclosure
Licensee Identified Violations
One violation of very low safety significance, which was identified by the licensee, has
been reviewed by the team. Corrective actions taken or planned by the licensee have
been entered into the licensees corrective action program. This violation and corrective
action is listed in Section 4OA7 of this report.
-3- Enclosure
Report Details
2. RADIATION SAFETY
Cornerstone: Occupational Radiation Safety [OS]
2OS3 Radiation Monitoring Instrumentation and Protective Equipment (71121.03)
a. Inspection Scope
This area was inspected to determine the accuracy and operability of radiation
monitoring instruments that are used for the protection of occupational workers and the
adequacy of the program to provide self-contained breathing apparatus (SCBA) to
workers. The team used the requirements in 10 CFR Part 20 and the licensees
procedures required by technical specifications as criteria for determining compliance.
The team interviewed licensee personnel and reviewed:
- Calibration of area radiation monitors associated with transient high and very
high radiation areas and post-accident monitors used for remote emergency
assessment
- Calibration of portable radiation detection instrumentation, electronic alarming
dosimetry, and continuous air monitors used for job coverage
- Calibration of whole body counting equipment and radiation detection
instruments utilized for personnel and material release from the radiologically
controlled area
- Licensee Event Reports, audits and self-assessments
- Corrective action program reports since the last inspection
- Licensee action in cases of repetitive deficiencies or significant individual
deficiencies
- Calibration expiration and source response check currency on radiation detection
instruments staged for use
- The licensees capability for refilling and transporting SCBA air bottles to and
from the control room and operations support center during emergency
conditions, status of SCBA staged and ready for use in the plant and associated
surveillance records, and personnel qualification and training
- Qualification documentation for onsite personnel designated to perform
maintenance on the vendor-designated vital components, and the vital
component maintenance records for SCBA units.
The inspector completed 9 of the required 9 samples.
-4- Enclosure
b. Findings
No findings of significance were identified.
2PS1 Radioactive Gaseous And Liquid Effluent Treatment And Monitoring Systems
(71122.01)
a. Inspection Scope
This area was inspected to ensure that the gaseous and liquid effluent processing
systems are maintained so that radiological releases are properly mitigated, monitored,
and evaluated with respect to public exposure. The team used the requirements in
10 CFR Part 20, 10 CFR Part 50 Appendices A and I, the Offsite Dose Calculation
Manual, and the licensees procedures required by technical specifications as criteria for
determining compliance. The team interviewed licensee personnel and reviewed:
- The most current radiological effluent release reports, changes to radiation
monitor setpoint calculation methodology, anomalous sampling results, effluent
radiological occurrence performance indicator incidents, self-assessments,
audits, and licensee event reports
- Gaseous and liquid release system component configurations
- Routine processing, sample collection, sample analysis, and release of
radioactive liquid and gaseous effluent; and Radioactive liquid and gaseous
effluent release permits and dose projections to members of the public
- Abnormal releases
- Changes made by the licensee to the Offsite Dose Calculation Manual, the liquid
or gaseous radioactive waste system design, procedures, or operation since the
last inspection
- Monthly, quarterly, and annual dose calculations
- Surveillance test results involving air cleaning systems and stack or vent flow
rates
- Instrument calibrations of discharge effluent radiation monitors and flow
measurement devices, effluent monitoring system modifications, effluent
radiation monitor alarm setpoint values, and counting room instrumentation
calibration and quality control
- Interlaboratory comparison program results
- Licensee event reports, special reports, audits, self-assessments and corrective
action reports performed since the last inspection
The inspector completed 10 of the required 10 samples.
-5- Enclosure
b. Findings
No findings of significance were identified.
2PS2 Radioactive Material Processing and Transportation (71122.02)
a. Inspection Scope
This area was inspected to verify that the licensees radioactive material processing and
transportation program complies with the requirements of 10 CFR Parts 20, 61, and 71
and Department of Transportation regulations contained in 49 CFR Parts 171-180. The
team interviewed licensee personnel and reviewed:
- The radioactive waste system description, recent radiological effluent release
reports, and the scope of the licensees audit program
- Liquid and solid radioactive waste processing systems configurations, the status
and control of any radioactive waste process equipment that is not operational or
is abandoned in place, changes made to the radioactive waste processing
systems since the last inspection, and current processes for transferring
radioactive waste resin and sludge discharges
- Radio-chemical sample analysis results for radioactive waste streams and use of
scaling factors and calculations to account for difficult-to-measure radionuclides
- Shipping records for non-excepted package shipments
- Licensee event reports, special reports, audits, state agency reports,
self-assessments and corrective action reports performed since the last
inspection
Either because the conditions did not exist or an event had not occurred, no
opportunities were available to review the following items:
- Shipment packaging, surveying, labeling, marking, placarding, vehicle checking,
driver instructing, and disposal manifesting
The inspector completed 6 of the required 6 samples.
2PS3 Radiological Environmental Monitoring Program (REMP) And Radioactive Material
Control Program (71122.03)
a. Inspection Scope
This area was inspected to ensure that the REMP verifies the impact of radioactive
effluent releases to the environment and sufficiently validates the integrity of the
radioactive gaseous and liquid effluent release program; and that the licensees surveys
and controls are adequate to prevent the inadvertent release of licensed materials into
the public domain. The team used the requirements in 10 CFR Part 20, Appendix I of
10 CFR Part 50, the Offsite Dose Calculation Manual, and the licensees procedures
-6- Enclosure
required by technical specifications as criteria for determining compliance. The team
interviewed licensee personnel and reviewed
- Annual environmental monitoring reports and licensee event reports
- Selected air sampling and thermoluminescence dosimeter monitoring stations
- Collection and preparation of environmental samples
- Operability, calibration, and maintenance of meteorological instruments
- Each event documented in the Annual Environmental Monitoring Report which
involved a missed sample, inoperable sampler, lost thermoluminescence
dosimeter, or anomalous measurement
- Significant changes made by the licensee to the Offsite Dose Calculation Manual
as the result of changes to the land census or sampler station modifications
since the last inspection
- Calibration and maintenance records for air samplers, composite water
samplers, and environmental sample radiation measurement instrumentation,
quality control program, interlaboratory comparison program results, and vendor
audits
- Locations where the licensee monitors potentially contaminated material leaving
the radiological controlled area [or controlled access area] and the methods used
for control, survey, and release from these areas
- Type of radiation monitoring instrumentation used to monitor items released,
survey and release criteria of potentially contaminated material, radiation
detection sensitivities, procedural guidance, and material release records
- Licensee event reports, special reports, audits, self-assessments and corrective
action reports performed since the last inspection
The inspector completed 10 of the required 10 samples.
b. Findings
Introduction. The team reviewed two examples of a Green, self-revealing non-cited
violation of Technical Specification 6.8.1, resulting from the licensees failure to prevent
radioactive material from being unconditionally released from the radiologically
controlled area.
Description. On March 31, 2004, a radiation protection technician observed a radiation
detection instrument outside a radiologically controlled area behind the Unit 2 equipment
hatch lay down area. Upon further examination, the radiation protection technician
noted a Radioactive Material label on the instrument. This alerted the radiation
protection technician to the fact that radioactive material had been unconditionally
released from a radiologically controlled area. Surveys of the instrument indicated no
loose radioactive contamination, but did identify 3.7 to 3.9 nanocuries of fixed
-7- Enclosure
radioactive contamination. The licensee concluded that another radiation protection
technician assigned to frisk items in the area left the instrument unattended and failed to
return it to the radiologically controlled area at the end of the work shift.
On October 29, 2005, an individual carrying a lifting sling from the maintenance
operations facility caused a contamination monitor in the east gatehouse to alarm.
Radiation protection personnel responded to the alarm and determined the sling was
contaminated with radioactive material (approximately 149 nanocuries). The licensee
concluded that the radioactive material originated from equipment and containers rigged
out of the reactor containment building during outages. Prior to being released from the
containment building, the all items were surveyed using portable Geiger-Muller (GM)
friskers. However, the portable GM friskers were not capable of detecting the all
quantities of radioactive material present on the items. Even though it was not in the
containment building, the lifting sling captured and concentrated small amounts of
radioactive material in the webbing. The lifting sling was also surveyed with portable
GM friskers and again the radioactive material was not detected. A more sensitive
measurement device, such as a tool monitor with scintillation detectors was not required
by the licensees procedure to supplement the portable GM friskers and therefore was
not used.
In both of these examples, although the radioactive material was allowed outside
radiologically controlled areas, it was not removed from the licensees protected area.
Analysis. NRC regulations provide no minimum level of licensed radioactive material
that can be disposed of in a manner other than as radioactive waste or transferred to a
licensed recipient, with one exception in 10 CFR 20.2005.
In the first example, the licensee intended the instrument with fixed radioactive
contamination be conditionally released from the radiologically controlled area under
the control of a radiation protection technician. However, when the radiation protection
technician using the instrument failed to maintain oversight of it, it was then
unconditionally released. The failure of the radiation protection technician to control
radioactive material outside the radiologically controlled area was a performance
deficiency.
In the second example, the licensee failed to detect the radioactive material present in
the lifting sling before it was released from the radiological controlled area. Information Notice No. 85-92, Surveys of Waste Before Disposal from Nuclear Reactor Facilities,
and Health Physics Position 073 provide guidance applicable to situations in which small
amounts of radioactive material are accumulated. The guidance states that, In order to
preclude the unintentional release of radioactive material, a good monitoring program
likely would include careful surveys using equipment and techniques for detecting very
low levels of radioactivity. Surveys conducted with portable survey instruments using
pancake GM probes are generally more appropriate for small items and small areas
because of the loss of detection sensitivity created by moving the probe and the
difficulties in completely scanning large areas. This does not preclude the use of such
instruments for larger items and areas, if supplemented by other survey equipment or
techniques. The accumulation of small amounts of contamination that escaped
pancake probe detection may be detected using detectors sensitive to gamma radiation,
such as by using a sensitive scintillation detector in a low-background area. The
licensee did not supplement its surveys made with portable pancake GM probes with
-8- Enclosure
surveys made with a sensitive scintillation detector. Therefore, the accumulated
radioactive material was not discovered until an individual attempted to take the lifting
sling from the protected area and entered a more sensitive radiation detection device
located outside the radiologically controlled area. The failure to confine radioactive
material to the radiologically controlled area is a performance deficiency.
This finding is greater than minor because it was associated with a Public Radiation
Safety cornerstone attribute (material release) and it affected the associated
cornerstone objective in that the failure to control radioactive material decreases the
licensees assurance that the public will not receive unnecessary dose. Using the Public
Radiation Safety Significance Determination Process, the team determined that the
finding had very low safety significance because: (1) the finding was a radioactive
material control finding, (2) it was not a transportation finding, (3) it did not result in
public dose greater than 0.005 rem, and (4) radioactive material was not released from
the protected area more than five times. Additionally, this finding had cross-cutting
aspects associated with human performance. In the first example, a radiation protection
technician failed to maintain direct supervision of the contaminated instrument. In the
second example, the procedural guidance allowed the licensee to use only portable GM
instruments on large items despite the loss of detection sensitivity.
Enforcement. Technical Specification 6.8.1.a requires written procedures to be
established, implemented, and maintained covering the applicable procedures
recommended in Appendix A of Regulatory Guide 1.33, Revision 2, February 1978.
Section 7 of Appendix B includes, Procedures for Control of Radioactivity (For limiting
materials released to environment and limiting personnel exposure). Procedure
0PGP03-ZR-0053, Radioactive Material Control Program, Revision 11, addresses this
requirement and states in Section 7.5.2, Items and materials which contain licensed
radioactivity, as determined by Radiation Protection procedures, SHALL NOT be
unconditionally released from the radiologically controlled area. The licensee violated
this requirement when it allowed the contaminated survey instrument and lifting sling to
be unconditionally released from the radiologically controlled area.
Because the failure to confine radioactive material to the radiologically controlled area
was determined to be of very low safety significance and the examples were entered
into the licensees corrective action program as Condition Reports 04-4266 and
05-14345, this violation is being treated as a non-cited violation, consistent with
Section VI.A of the NRC Enforcement Policy: NCV 05000498/2006008-01;
05000499/2006008-01 - Failure to confine radioactive material to the radiologically
controlled area.
4. OTHER ACTIVITIES
4OA2 Problem Identification and Resolution
Annual Sample Review
a. Inspection Scope
The team evaluated the effectiveness of the licensees problem identification and
resolution process with respect to the following inspection areas:
-9- Enclosure
- Radiation Monitoring Instrumentation (Section 2OS3)
- Radioactive Gaseous and Liquid Effluent Treatment and Monitoring Systems
(Section 2PS1)
- Radioactive Material Processing and Transportation (Section 2PS2)
- Radiological Environmental Monitoring Program and Radioactive Material
Control Program (Section 2PS3)
b. Findings and Observations
No findings of significance were identified.
4OA6 Management Meetings
Exit Meeting Summary
On January 26, 2006, the team presented the inspection results to Mr. G. Parkey,
Executive Vice President of Generation and General Plant Manager, and other
members of his staff who acknowledged the findings. The team confirmed that
proprietary information was not provided or examined during the inspection.
4OA7 Licensee-Identified Violations
The following violation of very low safety significance (Green) was identified by the
licensee and is a violation of NRC requirements which meet the criteria of Section VI of
NUREG-1600, NRC Enforcement Policy, for being dispositioned as an NCV.
Department of Transportation Regulation 49 CFR 172.504(a) requires exclusive use
shipments of low specific activity material to be placarded with a RADIOACTIVE
placard on each side and each end of the vehicle. The licensee violated this
requirement on October 20, 2004, when a shipment of low specific activity material was
shipped to a processor in Tennessee via an exclusive use vehicle without the required
placards. During a review of the documentation and regulations the next morning, the
licensee identified the error, contacted the vehicle driver and instructed him to display
the correct placards on the vehicle. This violation is of very low safety significance
because the issue is a violation of transportation requirements, did not exceed radiation
limits, did not result in a breach of the package during transit, did not involve the
requirements of the Certificate of Compliance, was not a nonconformance with low level
burial ground requirements, and was not a failure to make notifications or to provide
emergency information. This event was documented in the licensees corrective action
program as CR-04-14179.
-10- Enclosure
ATTACHMENT
SUPPLEMENTAL INFORMATION
KEY POINTS OF CONTACT
Licensee personnel
R. Aguilera, Radiological Engineering Supervisor, Health Physics
A. Barnett, Engineer, System Engineering
D. Bryant, Supervisor, Chemistry Performance
W. Bullard, Manager, Radiation Protection
W. Curry, Senior Metrology Laboratory Technician, Metrology Laboratory
L. Earls, Consulting Engineer, Radiation Protection
E. Hardcastle, Laboratory Analyst, Health Physics
S. Head, Manager, Licensing
J. Houston, Senior Radwaste Specialist, Radiation Protection
R. Jones, Staff Lead Metrology Specialist, Metrology and Radiological Laboratories
G. Parkey, Executive Vice President of Generation and General Plant Manager
A. Passafuma, Radiological Environment Monitoring Program Technician, Health Physics
T. Riccio, Engineer, Instrumentation/Monitoring Systems
R. Savage, Senior Staff Specialist, Licensing
J. Sepulveda, Supervisor, Radiation Protection
D. Sherwood, Radiological Services Supervisor, Health Physics
J. Sheppard, President and Chief Executive Officer
D. Scoggins, Supervisor, Metrology Laboratory
M. Tomek, Radiation Protection Supervisor
G. Williams, REMP / Dosimetry Health Physicist, Radiation Protection
NRC
J. Cruz, Senior Resident Inspector
LIST OF ITEMS OPENED, CLOSED, AND DISCUSSED
Opened and Closed During this Inspection
50-499/2006008-01 NCV Failure to confine radioactive material to a radiologically controlled
area. (Section 2PS3)
Previous Items Closed
NONE
Previous Items Discussed
NONE
A-1 Attachment
LIST OF DOCUMENTS REVIEWED
Section 2OS3: Radiation Monitoring Instrumentation and Protective Equipment
Audits and Self Assessments
CR 04-08739 Instrument Setpoints for Contamination Control
CR 04-11611 2004 Thermo Electron Users Group Meeting for Radiation Protection
Instrumentation and Dosimetry Assessment
CR 05-06702 Electronic Personal Dosimetry Failures during 1RE12
National Voluntary Laboratory Accreditation Program Assessment
Calibration Forms and Work Authorization Numbers
EQ ID: 400-00041-013, 400-00041-072, 400-00044-015, 400-00044-022, 400-00044-024,
400-00044-026, 400-00061-013, 400-00061-021, 400-00061-026, 400-00061-029,
400-00097-002, 400-00097-011, 400-00097-015, 400-00097-023, 400-00097-042,
400-00099-005, 400-00099-008, 400-00099-009, 400-00099-012, 400-00099-023,
400-00124-121
Work Authorization Numbers: 206549, 212970, 213495, 227239, 249372, 249373, 252362,
256798, 263831, 267729
Whole Body Counter System: Subject ID 999-98-1009 and 999-99-1009 for August 2005
Condition Records
04-10246, 04-12930, 04-13152, 04-13491, 04-14041, 04-14948, 04-16047, 04-16053,
04-16437, 05-00546, 05-02559, 05-03331, 05-04640, 05-04937, 05-06052, 05-06702,
05-07734, 05-08467, 05-09024, 05-09025, 05-09074, 05-09965, 05-10519, 05-11210
Procedures
0PGP03-ZA-0076 Accident Monitoring Instrumentation Maintenance, Revision 3
0PGP03-ZA-0078 Administration of the Radiation Monitoring System, Revision 8
0PGP03-ZA-0128 Medical Examination, Revision 5
0PGP03-ZC-0001 Radiological Instrumentation Control, Revision 8
0PGP03-ZR-0048 Personnel Dosimetry Program, Revision 12
0PGP03-ZR-0050 Radiation Protection Program, Revision 8
0PGP03-ZR-0051 Radiological Access and Work Controls, Revision 21
0PRP04-ZR-0004 Release of Materials From Radiologically Controlled Areas, Revision 13
0PRP02-ZR-0006 TLD Issue and Collection, Revision 7
0PGP03-ZR-0054 Respiratory Protection Program, Revision 12
0PRP06-ZR-0002 Respiratory Protection Equipment Issue and Return, Revision 16
0PRP06-ZR-0005 Maintenance, Inspection, and Storage of Respiratory Protection
Equipment Revision 10
0PRP06-ZR-0008 Air Quality Evaluation for Compressors or Pressurized Gas Cylinders,
Revision 3
0PRP02-ZR-0007 Evaluation of Intakes, Revision 9
0PRP02-ZR-0010 Personnel Exposure Investigation, Revision 7
0PRP02-ZR-0011 Calibration of WBC System, Revision 3
0PRP07-ZR-0011 Radiological Work ALARA Reviews, Revision 7
0PTP04-ZC-0013 Calibration of Air Samplers/Sampling Pumps, Revision 11
A-2 Attachment
0PTP04-ZC-0002 Calibration of the Eberline 6112 (Series) Teledetector and Fag
Kugelfischer Fh40f (Series) Radiameter, Revision 4
0PTP04-ZC-0018 Calibration of Self Reading Dosimeters, Revision 2
0PTP04-ZC-0022 Calibration of Area Alarm Monitors / Underwater Meters, Revision 8
0PTP04-ZC-0036 Calibration of the Eberline AMS-4 Air Monitoring System, Revision 5
0PTP04-ZC-0043 Calibration of Radiological Meters and Ion Chambers, Revision 12
0PTP04-ZC-0044 Calibration of Counting Instruments, Revision 7
0PTP04-ZC-0047 Calibration of the Siemens Electronic Personal Dosemeter, Revision 5
0PTP04-ZC-0049 Calibration of Geiger Counters and Micro R/Hr Meters, Revision 1
Conduct of Operations for Radiation Protection, Chapter 9, Revision 6
Miscellaneous
2003 and 2004 Radioactive Effluent Release Reports
Licensee Event Report 2005-06
Positive Whole Body Count Logs
South Texas Project - System Health Report, 4th Quarter 2005, Radiation Monitoring (RA)
Walkdown Checklist for Area Monitors
Whole Body Counter Radioactive Source Certificate
Listing of SCBA Certified and Qualified Personnel
Air Quality Records for breathing air compressors
General Employee Training - 003: Respiratory Protection
Section 2PS1: Radioactive Gaseous and Liquid Effluent Treatment and Monitoring
Systems
Documents Reviewed
Procedures
0POP02-WL-0005 Waste Monitor Tank Operations, Revision 14
0POP02-WL-0100 Liquid Waste Release, Revision 11
0PCP09-ZR-0004 Determination of Radionuclides by Gamma Spectroscopy, Revision 17
0PCP09-ZR-0017 Liquid Permit Generation, Revision 13
0PCP07-ZS-0010 Waste Monitor Tank Sampling, Revision 2
0PSP05-RA-8010A Unit Vent Particulate and Iodine Effluent Monitor Calibration, Revision 5
0PSP05-RA-8010B MAB Unit Vent Wide Range Gas Monitor Calibration, Revision 6
0PSP05-RA-8038, Liquid Waste Processing System No.1 Monitor Calibration, Revision 8
0PSP05-WL-4078, Plant Liquid Waste Discharge Flow Calibration, Revision 3
0PSP07-WL-LDP1, Liquid Effluent Permit, Revision 11
0PSP11-HF-0001, FHB Exhaust Filter Airflow Capacity Test, Revision 8
0PSP11-ZH-0008, CRE and FHB HVAC In-Place HEPA Filter Leak Test, Revision 13
0PSP11-ZH-0009, EAB and FHB HVAC In-Place Adsorbent Leak Test, Revision 19
Condition Reports
04-10578, 04-13075. 04-13150, 04-13339, 04-14566, 04-14663, 04-10678, 04-11655,
04-11733, 04-15311, 04-15880, 04-16389, 05-01197, 05-03214, 05-05001, 05-05037,
05-05215, 05-05218, 05-06218, 05-06294, 05-06295, 05-06880, 05-07956, 05-08027,
05-010417, 05-11164, 05-12157, 05-14769, 05-15266, 05-15431, 05-15946, 06-00940,
06-01271
A-3 Attachment
Audits and Surveillance
Chemistry and Offsite Dose Calculation Manual June 2004 to June 2005 Annual Evaluation
Quality Audit 04-08(OD), Offsite Dose Calculation Manual
Quality Monitoring Reports
MN-05-0-6647 MN-05-1-6701 MN-05-0-7835 MN-05-0-9263
MN-05-0-11447 MN-05-0-11538
Monitor Calibrations and Surveillance
Unit Vent Radiation Monitors Source Check (31784799)
Unit Vent Radiation Monitors Source Check (31900981)
Unit Vent Radiation Monitors Source Check (31910718)
Unit Vent Particulate and Iodine Effluent Monitor Calibration (31855854)
Unit Vent Particulate and Iodine Effluent Monitor Calibration (31855891)
MAB Unit Vent Wide Range Gas Monitor Calibration (31780321)
Plant Liquid Waste Discharge Flow Calibration (31757618)
Liquid Waste Processing System No. 1 Monitor Calibration (31885865)
Other Documents
4th Quarter Measurement Assurance Program Sample Results 2004
2nd Quarter Measurement Assurance Program Sample Results 2005
3rd Quarter Measurement Assurance Program Sample Results 2006
System Health Report - Radwaste Systems, 4th quarter 2005
Release permits with liquid effluent monitor inoperable: 2WLDP845 and 2WLDP846
Section 2PS2: Radioactive Material Processing and Transportation
Corrective Action Documents (Condition Reports)
04-14179
05-09411
05-13645
05-14669
05-16331
Procedures
0POP03-ZA-0017 Radioactive Waste Process Control Program, Revision 5
0POP02-WS-0002 High Integrity Container (HIC) Dewatering, Revision 9
0PRP03-ZR-0001 Determination of Radioactive Material Curie Content, Revision 8
0PRP03-ZR-0002 Radioactive Waste Shipments, Revision 17
0PRP03-ZR-0009 10CFR61 Sampling and Analysis Program, Revision 6
0PRP03-ZR-0011 Shipment of Radioactive Material, Revision 12
A-4 Attachment
Records
Waste Shipments of Type A, Type B, and LSA Materials.
Section 2PS3: Radiological Environmental Monitoring Program and Radioactive Material
Control Program
Corrective Action Documents (Condition Reports)
04-04266, 05-30040, 05-03164, 05-03214, 05-04898, 05-14065, 05-14345
Audits and Self-Assessments
Self-Assessment/Benchmarking Report - RETS/REMP Workshop 2005
Audit Frequency Extension - Radiological Environmental Monitoring Program (File No.: Q54)
Procedures
0PGP03-ZR-0039, Radiological Environmental Monitoring Program, Revision 12
0PGP03-ZR-0053, Radioactive Material Control Program, Revision 11
0PRP04-ZR-0004, Release of Materials From Radiologically Controlled Areas, Revision 13
0PRP10-ZL-0023, REMP Interlaboratory Comparison Program, Revision 10
0PRP10-ZA-0003, Operation and Calibration of the Radiological Laboratorys Gamma Counting
Systems, Revision 12
0PRP10-ZU-0001, REMP Sample Collection, Revision 5
0PRP10-ZU-0007, Environmental TLD Monitoring, Revision 10
0PSP05-EM-0001, Primary Meteorological System Calibration (60 Meter Tower)
0PSP05-EM-0002, Secondary Meteorological System Calibration (10 Meter Tower)
Standing Orders
No. 27 Maintenance Calibration of SAM Series Small Article Monitors, Revision 1
No. 30 Maintenance Calibration of Eberline PM-7 Portal Monitors, Revision 0
No. 31 Maintenance Calibration of Eberline PCM-1C Personnel Contamination Monitors,
Revision 0
Miscellaneous
2004 Environmental Operating Report
Offsite Dose Calculation Manual, Revision 12
A-5 Attachment