IR 05000027/2016201
| ML16214A368 | |
| Person / Time | |
|---|---|
| Site: | Washington State University |
| Issue date: | 08/11/2016 |
| From: | Anthony Mendiola Research and Test Reactors Oversight Branch |
| To: | Keane C Washington State Univ |
| Morlang G | |
| References | |
| IR 2016201 | |
| Download: ML16214A368 (17) | |
Text
ust 11, 2016
SUBJECT:
WASHINGTON STATE UNIVERSITY - NUCLEAR REGULATORY COMMISSION ROUTINE INSPECTION REPORT NO. 50-027/2016-201
Dear Dr. Keane:
From July 19-21, 2016, the U.S. Nuclear Regulatory Commission (NRC, the Commission)
completed an inspection at your Washington State University Training, Research, Isotope
Production, General, Atomics research reactor located in the Nuclear Radiation Center. The
enclosed report documents the inspection results, which were discussed on July 21, 2016, with
Dr. Donald Wall, Director of the Nuclear Radiation Center, and members of your staff.
The inspection examined activities conducted under your license as they relate to safety and compliance with the Commission's rules and regulations and with the conditions of your license.
The inspector reviewed selected procedures and records, observed activities, and interviewed
personnel. Based on the results of this inspection, no findings of significance were identified.
No response to this letter is required.
In accordance with Title 10 of the Code of Federal Regulations , Section 2.390, "Public inspections, exemptions, requests for withholding," a copy of this letter, its enclosure, and your
response (if any) will be available electronically for public inspection in the NRC Public
Document Room or from the NRC's document system (Agencywide Documents Access and Management 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, please contact Gary Morlang at 301-415-4092 or by electronic mail at Gary.Morlang@nrc.gov.
Sincerely,
/RA/
Anthony J. Mendiola, Chief Research and Test Reactors Oversight Branch
Division of Policy and Rulemaking
Office of Nuclear Reactor Regulation
Docket No.50-027
License No. R-076
Enclosure:
As stated
cc: w/enclosure: See next page Washington State University Docket No. 50-27
cc:
Director Division of Radiation Protection
Department of Health
7171 Cleanwater Lane, Bldg #5
P.O. Box 47827
Olympia, WA 98504-7827
Mr. David Clark, Director
Washington State University
Radiation Safety Office
P.O. Box 641302
Pullman, WA 99164-1302
Dr. Ken Nash Chair
Washington State University
Reactor Safeguards Committee
Nuclear Radiation Center
P.O. Box 641300
Pullman, WA 99164-1300
Mr. Corey Hines, Reactor Supervisor
Washington State University
Nuclear Radiation Center
P.O. Box 641300
Pullman, WA 99164-1300 Test, Research and Training Reactor Newsletter
P.O. Box 118300
University of Florida
Gainesville, FL 32611-8300 Dr. Donald Wall, Director Washington State University
Nuclear Radiation Center
50 Roundtop Drive
Pullman, WA 99164-1300
ML16214A368; *concurred via e-mail NRC-002 OFFICE NRR/DPR/PROB NRR/DPR/PROB/LA* NRR/DPR/PROB/BC NAME GMorlang NParker AMendiola DATE 08/10/16 08/9/16 08/11/16
U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF NUCLEAR REACTOR REGULATION
Docket No.50-027
License No. R-76
Report No. 50-027/2016-201
Licensee: Washington State University
Facility: Nuclear Radiation Center
Location: Pullman, WA
Dates: July 19-21, 2016
Inspector: Gary Morlang
Approved by: Anthony J. Mendiola, Chief Research and Test Reactors Oversight Branch
Division of Policy and Rulemaking
Office of Nuclear Reactor Regulation EXECUTIVE SUMMARY Washington State University Nuclear Radiation Center NRC Inspection Report No. 50-027/2016-201
The primary focus of this routine, announced inspection was the onsite review of selected
aspects of the Washington State University (the licensee's) 1000 Kilowatt Class II research
reactor safety program including: (1) organizational structure and staffing; (2) operator
requalification program; (3) procedures; (4) radiation protection program; (5) effluent
environmental monitoring; (6) design change function; and (7) transportation of radioactive
materials since the last U.S. Nuclear Regulatory Commission (NRC) inspection of these areas.
The licensee's safety program was acceptably directed toward the protection of public health
and safety. No violations or deviations were identified.
Organizational Structure and Staffing
Organizational structure and staff responsibilities were consistent with Technical Specification (TS) Section 6 requirements.
Operator Requalification Program
Operator requalification was conducted as required by the Reactor Requalification Plan.
A medical examination for each reactor operator with an active license was being completed every two years as required.
Procedures
Facility procedural review, revision, control, and implementation satisfied TS requirements.
Radiation Protection Program
Surveys were being completed and documented acceptably to permit evaluation of the radiation hazards present.
Postings met the regulatory requirements specified in Title 10 of the Code of Federal Regulations (10 CFR) Part 19, "Notices, Instructions and Reports to Workers: Inspection and Investigations," and 10 CFR Part 20, "Standards for Protection Against Radiation."
Personnel dosimetry was being worn as required and doses were well within the licensee's procedural action levels and NRC's regulatory limits.
Radiation monitoring equipment was being maintained and calibrated as required.
Acceptable radiation protection training was being provided to staff personnel.
The Radiation Protection Program being implemented by the licensee satisfied regulatory requirements.
- 2 - Effluent and Environmental Monitoring
Effluent monitoring satisfied licensee and regulatory requirements.
Releases were within the specified regulatory and TSs limits.
Design Change Functions
The latest changes completed by the licensee were reviewed using the criteria specified in 10 CFR 50.59, "Changes, tests and experiments," determined to be acceptable, and
approved by the Reactor Safeguards Committee.
Transportation of Radioactive Materials
Shipments of radioactive materials were being made in accordance with the requirements of Department of Transportation regulations as required by Title 49 of the Code of Federal Regulations 71.5(a).
Enclosure REPORT DETAILS Summary of Plant Status Washington State University (WSU, the licensee) continued to operate the 1000 Kilowatt
Training, Research, Isotope Production, General, Atomics (TRIGA) research and test reactor in
support of irradiation work for various experiments and organizations, operator training, and
surveillance. During the inspection, the reactor was started up, operated, and shut down as
required and in accordance with applicable procedures to support these ongoing activities.
1. Organizational Structure and Staffing a. Inspection Scope (Inspection Procedure [IP] 69001)
The inspector reviewed the following regarding the licensee's organization and staff levels to ensure that the requirements of TS Sections 6.1-6.3, dated September 30, 2011, were being met:
Console logs for 2015, and to date in 2016 Management responsibilities WSU Nuclear Radiation Center organizational structure and staffing Annual Report for WSU Nuclear Radiation Center TRIGA Reactor for the Reporting Period of July 1, 2014 to June 30, 2015, dated August 7, 2015 Annual Report for WSU Nuclear Radiation Center TRIGA Reactor for the Reporting Period of July 1, 2013 to June 30, 2014, dated August 21, 2014 WSU Nuclear Radiation Center Administrative Procedure Number (No.) 1, "Responsibilities and Authority of Reactor Operating Staff," (not dated) WSU Nuclear Radiation Center Operations Log Sheets for 2015 and 2016 to date b. Observations and Findings The inspector noted that the WSU Nuclear Radiation Center organizational structure and the responsibilities of the reactor staff had not changed since the
last inspection.
As required by TS Section 6.2 a Senior Reactor Operator (SRO) or Reactor Operator (RO) must be present in the control room during reactor operations. If
the SRO on duty is also the RO on duty then a second person must be available
at the facility. The licensee documented this by individual log entries.
c. Conclusion The organizational structure and functions were consistent with the requirements specified in TS Section 6.1.
- 2 - 2. Operator Requalification Program a. Inspection Scope (IP 69001)
The inspector reviewed the following in order to determine that operator training
and requalification activities were conducted as required and that medical
requirements were met:
- Biennial written examination records for 2014 through 2015
- Operator medical examination records from 2014 to the present
- Operator license status and effective dates of current operator licenses
- WSUNRC Reactor Staff Requalification Program, latest revision, dated May 15, 2010
- Active duty status and Annual Reactor Operating Test results noted and maintained in the Operator Requalification Schedule forms (A.3)
- Logs and records of reactivity manipulations maintained in the Quarterly RO/SRO Activity Report (O.14) No tebook and documented on forms entitled, "Quarterly Operational Hours for Reactor Operators and Senior Reactor
Operators" b. Observations and Findings At the time of the inspection, there were 3 licensed SROs and 9 licensed ROs
working at the facility. The inspector noted that all the licenses of the operators
were current.
A review of the logs and records showed that the training and requalification
program was being followed and that biennial written examinations had been
completed as required. An annual operating test had been conducted for each
operator by the Assistant Facility Director as required by the program. It was
also verified that each operator had completed the required number of hours of
reactor operations and reactivity manipulations.
The inspector reviewed records documenting the completion of physical
examinations for selected operators. It was noted that licensed operators were
receiving biennial medical examinations as required.
c. Conclusion
The requalification and training program was current and being acceptably
maintained. Medical examinations for each operator were being completed
biennially as required.
3. Procedures a. Inspection Scope (IP 69001)
The inspector reviewed selected aspects of the following to verify that the licensee was complying with the requirements of TS Section 6.8:
- 3 - Required Reading Notebook (O.15) Selected administrative and standard operating procedures Related logs and records documenting procedure implementation Records documenting procedure changes and temporary changes Administrative controls as outlined in WSU Nuclear Radiation Center Administrative Procedure No. 2, "Approval, Revision, and Review of Standard
Operating Procedures," (not dated)
b. Observations and Findings Procedures were available for those tasks and activities specified in the TS.
Records showed that procedures for potential malfunctions (e.g., radioactive
releases, contaminations, and reactor equipment problems) had been developed
and were being implemented as required. If procedure changes were needed, they were reviewed and approved by the Reactor Safeguards Committee as
required. The Standard Operating Procedures were reviewed biennially as
required by TS Section 6.8. It was noted that all the operating procedures at the
facility had been revised and updated to more fully reflect current operational
activities
Training of personnel on procedures and the applicable changes was
acceptable. The licensee maintained a notebook entitled, "Required Reading,"
that was used to keep staff members of current issues at the facility including
changes to procedures. The inspector verified that licensee personnel were
reading the material in the notebook and signing off to document that they had
completed their required review. The inspector also verified that, once the newly
revised procedures were approved by the Reactor Safeguards Committee, all
operations staff members would be required to read them and sign off signifying
that they had completed the task and understood the changes made.
Through observation of reactor operations, the inspector also verified that
personnel conducted TS activities in accordance with applicable procedures.
c. Conclusion Procedural review, revision, control, and implementation satisfied TS requirements.
4. Radiation Protection Program a. Inspection Scope (IP 69001)
The inspector reviewed the following to verify compliance with 10 CFR Part 19,
"Notices, Instructions and Reports to Workers: Inspection and Investigations,"
and 10 CFR Part 20, "Standards for Protection Against Radiation,"
TS Sections 3.5, 4.5, and procedural requirements:
Preventative Maintenance Checklists for 2015 and to date in 2016 Radiation Monitor Calibration Schedule Forms for 2015 and to date in 2016
- 4 - Nuclear Radiation Center dosimetry records for 2015 through April 2016 Radiation and contamination survey records for 2015 through the present Calibration and periodic check records for radiation monitoring instruments documented on the applicable forms Various WSU Nuclear Radiation Center Standard Operating Procedures (SOPs) including: No. 16, "Standard Procedure for Health Physics Surveys,"
No. 6, "Standard Procedure for Maintenance of the Area Radiation Monitors,"
and No. 18, "Standard Procedure for Portable Survey Instrumentation
Calibration" WSU Nuclear Radiation Center Administrative Procedure, "Radiation Protection Program," latest revision dated March 20, 2012, which outlined the
program and also contained and explained the As Low As Reasonably
Achievable (ALARA) Policy for the facility WSU Radiation Protection Program Manual which contained and outlined the Campus practices and ALARA Policy b. Observations and Findings
(1) Surveys
The inspector reviewed selected weekly general area radiation and
contamination surveys and semiannual neut ron surveys of the Pool Room, the Beam Room, and other associated laboratories and support areas from
2015 to the present. The surveys had been completed by licensee personnel
as required by WSU Nuclear Radiation Center Standard Operating Procedure
No. 16. The results were documented on the appropriate forms and
evaluated as required, and corrective actions were taken when readings or
results exceeded set action levels.
(2) Postings and Notices
The inspector reviewed the postings at the entrances to various controlled
areas including the Control Room, t he Pool Room, the Beam Room, and various laboratories in the Nuclear Radiation Center. The postings were
acceptable and typically indicated the radiation and/or contamination hazards
present. Other postings also showed the industrial hygiene hazards present
in the areas. The facility's radioactive material storage areas were noted to
be properly posted. No unmarked radioactive material was detected in the
facility. Copies of current notices to workers required by 10 CFR Part 19
were posted on various bulletin boards throughout the facility including in the
stairway leading to the Control Room, in the Reactor Shop area, and in the
Conference Room as well.
(3) Dosimetry
The inspector determined that the licensee was provided optically stimulated
luminescent (OSL) dosimeters for whole body monitoring of beta and gamma
radiation exposure (with an additional component to measure neutron
- 5 - radiation). The licensee was also provided thermoluminescent dosimeter (TLD) finger rings for extremity monito ring. The dosimetry was supplied by the campus Radiation Safety Office and processed by a National Voluntary
Laboratory Accreditation Program accredited vendor (Landauer).
An examination of the OSL and TLD results indicating radiological exposures
at the facility for the past two years showed that the highest occupational
doses, as well as doses to the public, were within 10 CFR Part 20 limitations.
The inspector verified that NRC Form-5 reports had been completed and
provided to each employee who had rece ived exposure at the facility during 2015 and 2016.
(4) Radiation Monitoring Equipment
The records of selected meters, detectors, and air monitoring equipment in
use at the facility were reviewed. The inspector noted that the calibration of
portable survey meters, friskers, and fi xed radiation detectors was typically completed by a contractor (Ludlum Measurements, Inc.). The inspector
verified that calibrations were completed and that appropriate calibration
records were being maintained by the licensee as required. Calibration
frequency met the requirements established in the applicable manuals.
(5) Radiation Protection Training
The inspector reviewed documentation of the radiation protection training
given to new employees by the WSU Radiation Safety Office entitled, "Radiation Safety Training Course." The course was offered online to provide
greater access to all personnel. The content of the course given, along with
various additional modules, was found to be acceptable and the training
program satisfied the requirements in 10 CFR 19.12, "Instruction to workers."
Through a review of selected training records, the inspector verified that
newly hired licensee personnel had received the training as required. Annual
refresher training was also being provided to the staff who had been at the
facility for over a year.
(6) ALARA Policy
The ALARA Policy was also outlined and established in the WSU Nuclear
Radiation Center Administrative Procedure, "Radiation Protection Program,"
as well as in the campus, "WSU Radiation Protection Program Manual." The
ALARA program provided guidance for keeping doses as low as reasonably
achievable and was consistent with the guidance in 10 CFR Part 20.
(7) Radiation Protection Program
The licensee's Radiation Protection Program was established in the WSU
Nuclear Radiation Center Administrative Procedure of the same name with
the latest revision dated March 20, 2012. The campus program was outlined
- 6 - and explained in a WSU campus document entitled, "WSU Radiation
Protection Program Manual." The inspector noted that the licensee's
program outlined personal dose limits; surveys, monitoring, and records; reports and audits; as well as the ALARA program. It also required that all
personnel receive training in radiation protection, policies, procedures, requirements, and facilities prior to entering a radiation area or working with
radioactive material. The program was being reviewed annually as required.
(8) Facility Tours
The inspector toured the Control R oom, Pool Room, Beam Room, and selected support laboratories and offices. Control of radioactive material and
control of access to radiation and high radiation areas were acceptable. As
noted earlier, the postings and signs for these areas were appropriate.
c. Conclusion The inspector determined that the Radiation Protection Program being
implemented by the licensee satisfied regulatory requirements because:
(1) surveys were being completed and documented acceptably; (2) postings met
regulatory requirements; (3) personnel dosimetry was being worn as required
and doses were well within the NRC's regulatory limits; (4) radiation monitoring
equipment was being maintained and calibrated as required; and (5) acceptable
radiation protection training was being provided to facility personnel.
5. Effluent and Environmental Monitoring a. Inspection Scope (IP 69001)
The inspector reviewed the following to verify compliance with the requirements of 10 CFR Part 20 and TS Sections 3.5, 4.5 and 6.10:
Continuous Air Monitor System Maintenance Log Equipment Maintenance Record for the Argon Monitoring System Preventative Maintenance Checklists for 2015 and to date in 2016 Continuous Air Monitor Channel Test forms for 2015 and to date in 2016 Exhaust Gas Monitor Channel Test forms for 2015 and to date in 2016 WSU Monthly Console Auxiliary Equipment Maintenance Checklists and WSU Monthly Reactor Auxiliary Equipment Maintenance Checklists for 2015
and to date in 2016 Annual Report for WSU Nuclear Radiation Center TRIGA Reactor for the Reporting Period of July 1, 2014 to June 30, 2015, dated August 7, 2015 Annual Report for WSU Nuclear Radiation Center TRIGA Reactor for the Reporting Period of July 1, 2013 to June 30, 2014, dated August 21, 2014 Airborne release records documented in the Average Monthly Concentration of Argon-41 Released section of the Reactor Operations Summary Log for
the period from 2015 to the present
- 7 - Liquid release records documented in the Reactor Operations Summary Log and calculated on the appropriate forms in the Liquid Waste Tank Release
Data Log for the period from 2015 to the present b. Observation and Findings The inspector reviewed the calibration records of the area radiation monitoring
system, the exhaust gas or stack moni toring system, and the continuous air monitoring system. These systems had been calibrated annually according to procedure. The monthly set-point verification, alarm check, and operability
records for the monitoring equipment were also reviewed. Corrective actions, including recalibration, were completed if the set-point values were exceeded.
The inspector also reviewed the records documenting liquid and airborne releases
to the environment for the past two years. The inspector determined that gaseous
release activity continued to be calculated as required by procedure and the
results were adequately documented. The releases were determined to be within
the 10 CFR Part 20 Appendix B concentrations and TS limits. To demonstrate
compliance with the annual dose constraints of 10 CFR 20.1101, "Radiation
protection programs," paragraph (d), the licensee used the COMPLY computer
code. The highest calculated dose that could be received by a member of the
public as a result of gaseous emissions from reactor operations was determined
to be 4.9 E-4 millirem per year (mr/yr)
for the period from July 2013 through June 2014 and 2.4 E-4 mr/yr for the period from July 2014 through June 2015. These
doses were well below the 10 mr/yr limit stipulated in 10 CFR 20.1101(d).
The activity of liquid waste to be discharged from the facility was calculated as
required and releases were approved by the Reactor Supervisor or a SRO after
analysis indicated that they met regulatory requirements for discharge into the
sanitary sewer. Through observation of the facility, the inspector did not identify
any new potential release paths.
On-site and off-site environmental gamma radiation monitoring was conducted
using TLDs in accordance with the applicable procedures. The data indicated that
there were no measurable doses above any regulatory limits. These results and
those outlined above were acceptably reported in the WSU Reactor Operations
Annual Reports for 2013-2014 and 2014-2015.
From a review of the various environmental monitoring records and documents, the inspector determined that the licensee was complying with all the
requirements specified in TS Sections 3.5 and 4.5.
c. Conclusion Effluent monitoring satisfied license and regulatory requirements and releases
were within the specified regulatory and TS limits. The licensee was complying
with all the requirements specified in TS Sections 3.5 and 4.5.
- 8 - 6. Design Change Function a. Inspection Scope (IP 69001)
The inspector reviewed the following to verify compliance with 10 CFR 50.59,
"Changes, tests and experiments," regarding design change control:
Console Logs for 2015 and 2016 to present
- Safety review and audit records for the past two years Reactor Safeguards Committee meeting minutes for 2015 to the present Annual Report for Washington State University Nuclear Radiation Center TRIGA Reactor for the Reporting Period of July 1, 2014 to June 30, 2015, dated August 7, 2015 Annual Report for WSU Nuclear Radiation Center TRIGA Reactor for the Reporting Period of July 1, 2013 to June 30, 2014, dated August 21, 2014 Reactor Safeguards Committee Facility Records Quarterly Audits for 2015 to the present documenting reviews of operations records, summary records, and administrative records WSU Nuclear Radiation Center Administrative Procedure No. 3, "Approval and Review of Facility Modifications and Special Tests or Experiments,"
(not dated)
b. Observations and Findings The inspector reviewed the records and observed the changes that had been
made at the facility from 2014 to the present. Prior to implementing substantive
changes, the licensee was required to submit them to the Reactor Safeguards
Committee where they were reviewed and, if determined to be acceptable, approved by the committee. The inspector noted that the facility modification
procedure was followed and an evaluation was completed as required. The
licensee considered the criteria included in 10 CFR 50.59 and concluded that the
changes were acceptable under the regulations. None of the changes
constituted a safety question or required a change to the TS.
c. Conclusion The latest changes completed by the licensee were reviewed using the criteria specified in 10 CFR 50.59, determined to be acceptable, and approved by the Reactor Safeguards Committee.
7. Transportation of Radioactive Materials a. Inspection Scope (IP 86740)
The inspector reviewed the following to verify compliance with procedural
requirements for transferring licensed material:
Records of radioactive material shipments for January 2015 and to the present
- 9 - Training records of the individuals who were designated as "shippers" at the facility Various records of the recipients' licenses to possess the radioactive material which the licensee had shipped to them WSU Nuclear Radiation Center SOP, No. 19, "Standard Procedure for Off-Site Shipment of Radioactive Material," No. 32, "Standard Procedure for
Use, Receipt, and Transfer of Radioactive Material" b. Observations and Findings Through records review and discussions with licensee personnel, the inspector
determined that the licensee had shipped various types of radioactive material
since the previous inspection in this area. The records indicated that the
radioisotope types and quantities were calculated and dose rates measured as
required. All radioactive material shipment records reviewed by the inspector
had been completed in accordance with Department of Transportation (DOT) and
NRC requirements.
The inspector noted that two staff members had received the required training for
shipping radioactive material and/or "Dangerous Goods." The most recent
training was completed on February 19, 2015. The inspector also determined
that the licensee maintained copies of the recipients' licenses to possess
radioactive material as required and that the licenses were verified to be current
prior to initiating a shipment.
c. Conclusion Shipments of radioactive material were being made in accordance with the
requirements of DOT regulations as required by Title 49 of the Code of Federal Regulations 71.5(a).
8. Exit Interview The inspection scope and results were summarized on July 21, 2016, with members of
licensee management. The inspector described the areas inspected and discussed in
detail the inspection findings. No dissenting comments were received from the licensee.
PARTIAL LIST OF PERSONS CONTACTED Licensee Personnel
C. Hines Associate Director D. Wall Director, Nuclear Radiation Center K. Restis Senior Reactor Operator H. Bennet Reactor Operator S. King Reactor Operator T, Vole Reactor Operator
INSPECTION PROCEDURES USED IP 69001 Class II Research and Test Reactors IP 86740 Inspection of Transportation Activities
ITEMS OPENED, CLOSED, AND DISCUSSED Opened None
Closed None PARTIAL LIST OF ACRONYMS USED 10 CFR Title 10 of the Code of Federal Regulations ALARA As Low As Reasonably Achievable DOT Department of Transportation No. Number NRC Nuclear Regulatory Commission
OSL Optically Stimulated Luminescent RO Reactor Operator SOP Standard Operating Procedure SRO Senior Reactor Operator TLD Thermoluminescent dosimeter TS Technical Specification WSU Washington State University