IR 05000297/2013201
| ML13038A005 | |
| Person / Time | |
|---|---|
| Site: | North Carolina State University |
| Issue date: | 02/07/2013 |
| From: | Gregory Bowman Research and Test Reactors Branch B |
| To: | Hawari A North Carolina State University |
| Eads, Johnny 919-219-9128 | |
| References | |
| IR-13-201 | |
| Download: ML13038A005 (16) | |
Text
February 7, 2013
SUBJECT:
NORTH CAROLINA STATE UNIVERSITY - NRC ANNOUNCED ROUTINE INSPECTION REPORT NO. 50-297/2013-201
Dear Dr. Hawari:
February 7, 2013
SUBJECT:
NORTH CAROLINA STATE UNIVERSITY - NRC ANNOUNCED ROUTINE INSPECTION REPORT NO. 50-297/2013-201
Dear Dr. Hawari:
The U.S. Nuclear Regulatory Commission (NRC) conducted an inspection on January 7-10, 2013, at your North Carolina State University (Inspection Report No. 50-297/2013-201). The inspection included a review of activities authorized for your facility. The enclosed report presents the results of that inspection. Areas examined during the inspection are identified in the enclosed report. Within these areas, the inspection consisted of selective examinations of procedures and representative records, interviews with personnel, and observations of activities in progress.
Based on the results of this inspection, no safety concern or noncompliance of requirements was 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, and requests for withholding a copy of this letter and its enclosure will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records component of NRCs document system (Agencywide Document Access and Management System (ADAMS)). ADAMS is accessible from the NRC Web site at (the Public Electronic Reading Room) http://www.nrc.gov/reading-rm/adams.html.
Should you have any questions concerning this inspection, please contact Johnny Eads at 919-219-9128 or electronic mail at Johnny.eads@nrc.gov
Sincerely,
/RA by P. Isaac for/
Gregory T. Bowman, Chief Research and Test Reactors Oversight Branch Division of Policy and Rulemaking Office of Nuclear Reactor Regulation Docket No. 50-297 License No. R-120 Enclosure: As stated cc w/encl: See next page
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Accession Number: ML13038A005 TEMPLATE #: NRC-002 OFFICE PROB:RI PRPB:LA PROB:BC NAME JEads
GLappert GBowman, PJI for DATE 2/4/13 2/7/2013 2/7/2013 Official Record Copy
North Carolina State University Docket No.: 50-297
cc:
Office of Intergovernmental Relations 116 West Jones Street Raleigh, NC 27603
Dr. Yousry Azmy, Head Nuclear Engineering Department North Carolina State University P.O. Box 7909 Raleigh, NC 27695-7909
Section Chief Department of Environment and Natural Resources Division of Environmental Health Radiation Protection Section 3825 Barrett Drive Raleigh, NC 27609-7221
Dr. Louis Martin-Vega Dean of Engineering North Carolina State University 113 Page Hall Box 7901 - NCSU Raleigh, NC 27695-7901
Test, Research, and Training Reactor Newsletter University of Florida 202 Nuclear Sciences Center Gainesville, FL 32611
Andrew Cook Manager, Engineering and Operations Department of Nuclear Engineering North Carolina State University P. O. Box 7909 Raleigh, NC 27695-7909
U. S. NUCLEAR REGULATORY COMMISSION
OFFICE OF NUCLEAR REACTOR REGULATION
Docket No:
50-297
License No:
R-120
Report No:
50-297/2013-201
Licensee:
North Carolina State University
Facility:
PULSTAR Nuclear Reactor Facility
Location:
Raleigh, NC
Dates:
January 7 to 10, 2013
Inspector:
Accompanied by:
Jan Rataj, Foreign Assignee
Approved by:
Gregory T. Bowman, Chief Research and Test Reactors Oversight Branch Division of Policy and Rulemaking Office of Nuclear Reactor Regulation
EXECUTIVE SUMMARY
North Carolina State University PULSTAR Reactor Facility NRC Inspection Report No. 50-297/2013-201
The primary focus of this routine, announced inspection was the onsite review of selected aspects of the North Carolina State University Class II research reactor facility safety programs including procedures; requalification training; surveillance and limiting conditions for operation (LCO); design changes; committees, audits and reviews; emergency planning; maintenance logs and records; and fuel handling logs and records. The licensees programs were acceptably directed toward the protection of public health and safety, and were in compliance with U.S.
Nuclear Regulatory Commission (NRC) requirements
Procedures
- Facility procedural review, revision, and implementation satisfied Technical Specification requirements.
Requalification Training
- Operator requalification was conducted as required by the Requalification Program and Title 10 of the Code of Federal Regulations (10 CFR) Part 55.
Surveillance and LCO
- LCO and surveillances required by Technical Specification were being properly implemented.
Design Changes
- Changes at the facility were acceptably reviewed in accordance with 10 CFR 50.59 and applicable licensee administrative controls.
Committees, Audits, and Reviews
- The Radiation Safety Committee and Reactor Safety and Audit Committee provided the oversight required by the Technical Specifications.
Emergency Planning
- The emergency preparedness program was conducted in accordance with the Emergency Plan and implementing procedures.
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Maintenance Logs and Records
- Maintenance was performed and logs and records maintained consistent with Technical Specification and licensee procedure requirements.
Fuel Handling Logs and Records
- Fuel handling logs or activities satisfied the Technical Specification requirements and facility procedural requirements.
REPORT DETAILS
Summary of Facility Status
The North Carolina State University (NCSU, the licensee) Nuclear Reactor Program (NRP)
PULSTAR research reactor continued to be operated in support of graduate and undergraduate research and laboratory instruction, service irradiations, reactor operator training, and periodic surveillance. During the inspection, the reactor was operated in support of ongoing work and research.
1.
Procedures
a.
Inspection Scope (IP 69001-02.03)
The inspector reviewed the following to ensure that the requirements of technical specification (TS) Section 6.4, Operating Procedures (OP), were being met:
- PULSTAR Operations Manual, specifically procedures:
NRP-OP-101, Reactor Startup and Shutdown, Rev. 7, dated October 18, 2010 NRP-OP-103, Reactor Operations, Rev. 2, dated May 1, 2009 NRP-OP-104, Reactor Experiments, Rev. 3, dated January 10, 2010 NRP-OP-105, Response to SCRAMS, Alarms and Abnormal Conditions, Rev. 5, dated November 14, 2011 NRP-OP-301, Reactor Fuel Handling, Rev. 1, dated October 15, 2012
- Special Procedure (SP) Manual, specifically procedures:
SP 2.1, Review and Approval of Documents, Rev. 8, dated September 15, 2008 SP 2.6, Operator Requalification Program, Rev. 6, dated January 19, 1995
- PULSTAR Emergency Procedures (EP), specifically procedures:
EP-1, Emergency Plan Activation, Response, and Actions, Rev.
18, dated September 28, 2011 EP-4, Emergency Classification, dated October 13, 2008
- PULSTAR Nuclear Reactor Emergency Plan, dated September 19, 2008
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Observations and Findings
The inspector observed that the licensee maintained written procedures covering the areas specified in TS Section 6.4. A systematic approach was being used to update and reissue procedures. New procedures and major changes were reviewed and approved by the Reactor Safety and Audit Committee (RSAC) and the Radiation Safety Committee (RSC) in accordance with a written procedure on document control. Minor changes did not require committee approval but were reviewed by the committees; the reviews and approvals were documented in the minutes of the respective committee meetings.
b.
Conclusion
The licensee was maintaining and implementing written procedures in accordance with TS requirements.
2.
Requalification Training
a.
Inspection Scope (Inspection Procedure (IP) 69001-02.04)
The inspector reviewed the following to verify that the requirements of 10 CFR Part 55, Operators Licenses, and the licensees Operator Requalification Program were being met:
- Requalification Written Examination administered December 19, 2011
Special Procedure 2.6, PULSTAR Operator Requalification Program, dated January 19, 1995
Individual requalification training records, 2011 - 2012
b.
Observations and Findings
The licensees reactor operator staff consisted of six NRC licensed Senior Reactor Operators (SRO), all held by full time staff members, and four Reactor Operators (RO).
The licensees requalification program included the regulatory requirement for an annual operating test and a biennial written examination. The inspectors verified that both examinations were administered at the specified frequency and that the level of difficulty was comparable to that of NRC-administered examinations.
The inspector reviewed the content of the written and oral examinations used for the 2011 - 2012 requalification cycle and found them adequate. The inspector selected six licensed SROs and one licensed ROs and reviewed their training and medical records in detail. The inspector reviewed documentation indicating that all operators had performed the required number of reactor manipulations at the frequency specified in the requalification program.
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It was noted that there we no operator requalification lectures conducted in 2012.
The PULSTAR Operator Requalification Program, Section 5.4 allows an exception to the requirement to attend operator requalification lectures if written exam scores exceeded 80 percent. Since examination scores for all operators exceeded 80 percent, the lectures were not conducted.
c.
Conclusion
Operator requalification was conducted as required by the Requalification Program and NRC regulations.
3.
Surveillance and Limiting Conditions for Operation
a.
Inspection Scope (IP 69001-02.05)
The inspector reviewed the following to determine if the LCO specified in TS Section 3.0 was being effectively implemented and if the periodic surveillance tests on safety systems were being performed in accordance with TS Section 4.0:
- Procedure NRP-OP-101, Reactor Startup and Shutdown, Appendix A, Startup Checklist, Rev. 7, dated October 18, 2010
Procedure SP-2.5, PULSTAR Reactor Surveillance, Rev. 1, dated February 1, 1989
PULSTAR Surveillance and Maintenance File
PULSTAR 2012 Surveillance Master Schedule
NCSU PULSTAR Reactor Logbook #8 dated February 29, 2012, to present
b.
Observations and Findings
Surveillances were completed on schedule and in accordance with licensee procedures. The protocols and techniques were effective in verifying the performance of the safety equipment. All the recorded results were within the TS and procedurally prescribed parameters. The records and logs were complete and were being maintained as required. Checks and calibrations were completed as required by TS.
c.
Conclusion
The limiting conditions for operation and surveillances required by TS were being properly implemented.
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4.
Design Changes
a.
Inspection Scope (IP 69001-02.08)
In order to verify that any modifications to the facility were consistent with 10 CFR 50.59, the inspector reviewed selected aspects of:
- SP 2.1, Review and Approval of Documents, dated September 15, 2008
PULSTAR Annual Operating Report for 2011, dated March 29, 2012
b.
Observations and Findings
Through review of applicable records and interviews with licensee personnel, the inspector determined that no changes requiring prior NRC approval had been initiated and/or completed at the facility since the last NRC operations inspection.
The inspector review records for Modification # 0728, Secondary Pump Trip. A secondary pump trip was installed in the secondary start/stop circuit to prevent inadvertent cool down of the reactor pool. Two alarm setpoints were programmed into the Reactor Temperature Recorder. Upon decreasing pool water temperature, the first setpoint causes an abnormal pool temperature alarm to annunciate on the Control Console to alert the reactor and allow time for appropriate actions to be taken. If the reactor operator fails to take action, the second setpoint will cause a trip of the secondary pump. The operation of the secondary pump is described in Final Safety Analysis Report (FSAR) Sections 4.2.2 and 4.2.5. The operation of the secondary pump is also discussed in the accident analysis in FSAR Section 13.2.1.5, Heat Exchanger Pressure Boundary Breach.
The licensee completed a 10 CFR 50.59 screening on September 16, 2011 and concluded that a full 10 CFR 50.59 safety evaluation need not be completed.
Based on a review of the modification and the discussion of the secondary pump functions contained in the FSAR, further NRC review of this conclusion is needed. As a result Unresolved Item (URI 50-297/2013-201-01) has been initiated and this issue will be reviewed in a future reactor inspection.
No additional issues were identified in area of design changes.
c.
Conclusion
Records indicated that changes at the facility were acceptably reviewed in accordance with 10 CFR 50.59 and applicable licensee administrative controls.
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5.
Committees, Audits, and Reviews
a.
Inspection Scope (IP 69001-02.09)
The inspector reviewed the following to ensure that the audits and reviews stipulated in TS Section 6.2 were being completed:
- RSC Membership, dated September 26, 2012
RSAC Membership, dated September 27, 2012
RSAC Minutes of meetings held February 8, 2012, April 4, 2012, May 30, 2012, and October 3, 2012
RSC Minutes of meetings held December 1, 2011 and March 23, 2012
2011 RSAC Audit Summary dated May 30, 2012
b.
Observations and Findings
The composition of the RSC and RSAC were as specified in the TS. A review of records indicated that both committees met at the prescribed frequency and provided the oversight and reviews of the reactor programs as required by the TS.
c.
Conclusion
The TSC and RSAC provided the oversight required by the TS.
6.
Emergency Planning
a.
Inspection Scope (IP 69001-02.10)
The inspector reviewed the emergency preparedness program and its implementation through the following:
- PULSTAR Nuclear Reactor Emergency Plan, Rev. 9, dated September 19, 2008
Emergency Procedure 1, Emergency Plan Activation, Response and Actions, Rev. 18, dated September 28, 2011
Emergency Procedure 2, Off-Site Notification, Rev. 17, dated September 28, 2011
Emergency Procedure 4, Emergency Classification, Rev. 6, dated October 13, 2008
Emergency Procedure 6, Training, Rev. 6, dated July 19, 2006
Emergency Procedure 7, Drills, Rev. 6, dated March 22, 2001
Emergency Procedure 9, Emergency Locker Inventory, Rev 6, dated February 25, 2009
Training Records of Emergency Support Groups
PULSTAR Nuclear Reactor, Emergency Drill Scenario, dated June 7, 2012
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PULSTAR Nuclear Reactor Drill Summary and Critique, dated June 14, 2012
Letter of Agreement with City of Raleigh Fire Department, dated February 2, 2011
Letter of Agreement with State of North Carolina Division of Emergency Management, dated February 1, 2011
Letter of Agreement with Wake County Emergency Management, dated January 5, 2013
Letter of Agreement with Rex Healthcare Hospital, dated January 7, 2013
Emergency Locker Inventory, dated November 27, 2012
b.
Observations and Findings
The inspector reviewed the licensees emergency preparedness program as defined in the above-referenced emergency plan and implementing procedures.
The inspector also reviewed documentation related to an annual drill conducted June 7, 2012, the critique of the drill and lessons learned.
The inspector found that letters of agreement with support agencies were available and current.
EP 6, Training, specifies that training for support agency personnel be offered every two years. Training records indicated that it was offered annually on multiple days to accommodate shift workers schedules.
EP 9, Emergency Locker Inventory, specified the inventory for emergency supply cabinets at various locations, calling for a quarterly inventory of each locker and also an inventory after each use. The inspector checked the inventory of the lobby locker in the Burlington Laboratory and verified that the inventory was performed on the designated frequency, that the specified items were in the cabinets and that the radios were operable.
The inspector review the Notification of Unusual Event declared and submitted to the NRC as required on August 23, 2011 for the magnitude 5.8 earthquake near Mineral, Virginia and felt in Raleigh, North Carolina. The results of the facility walkdown confirmed that no damage was sustained at the facility. The required emergency notifications were completed in accordance with the facility emergency response plan.
c.
Conclusion
The emergency preparedness program was conducted in accordance with the Emergency Plan and implementing procedures.
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7.
Maintenance Logs and Records
a.
Inspection Scope (IP 69001-02.11)
The inspector reviewed the following selected maintenance and reactor operations records to ensure that the requirements of TS Sections 6.8 "Retention of Records" were being met:
- PULSTAR Maintenance Log and History Report
PULSTAR Unscheduled Scram and Shutdown Log
PULSTAR Reactor Logbook, Logbook #8 dated February 29, 2012 to present
b.
Observations and Findings
The inspector reviewed the maintenance records related to scheduled and unscheduled preventive and corrective maintenance activities that had occurred during the inspection period. The inspector reviewed maintenance records and interviewed personnel regarding maintenance completed on the rod drive for Safety Rod #2 on October 31, 2012 and the shock absorber replacement for the Regulating Rod.
Routine and preventive maintenance was controlled and documented in the appropriate logs. These documents indicated that all maintenance activities were in accordance with the requirements in licensee administrative controls.
The inspector verified that all maintenance was conducted in accordance with the requirements of TS Section 4.0, and system operational checks were performed before returning them to service.
c.
Conclusion
Maintenance was performed and logs and records maintained consistent with TS and licensee procedure requirements.
8.
Fuel Handling Logs and Records
a.
Inspection Scope (IP 69001-02.12)
The inspector reviewed the following records to verify implementation of the requirements of TS Section 4.1:
- Procedure NRP-OP-301, Reactor Fuel Handling, Rev. 1, dated October 15, 2012, Appendix A, Confirmations of fuel movement and Appendix B, Fuel Movements Schedule on September 17, 2012, December 21, 2012, and January 2, 2013
Core Map Records of Fuel Element Locations
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b.
Observations and Findings
The inspector found the procedures used for fuel handling provide for the safe handling of fuel elements. The data sheets and the Core Map Records adequately documented the location of fuel elements at all times.
c.
Conclusion
Fuel movements were performed safely in accordance with TS requirements and licensee procedural requirements.
9.
Exit Interview
The inspector presented the inspection results to licensee management at the conclusion of the inspection on January 10, 2013. The inspector described the areas inspected and discussed in detail the inspection observations. The licensee acknowledged the findings presented and did not identify as proprietary and of the material provided to or reviewed by the inspector during the inspection.
PARTIAL LIST OF PERSONS CONTACTED
Licensee
A. Cook
Manager, Nuclear Reactor Program and Reactor Operations Manager Director, Nuclear Reactor Program K. Kincaid
Chief of Reactor Maintenance G. Wicks
Reactor Health Physicist
INSPECTION PROCEDURES USED
IP 69001 Class II Research and Test Reactors
ITEMS OPENED, CLOSED, AND DISCUSSED
Opened
50-297/2013-201-01 URI Safety Evaluation for Modification 0728, Secondary Pump Trip on
Low Reactor Pool Temperature
Closed
None
Discussed
None
PARTIAL LIST OF ACRONYMS USED
10 CFR Title 10 of the Code of Federal Regulations ADAMS Agencywide Document Access and Management System EP
Emergency Procedure IP
Inspection Procedure LCO
Limiting conditions for operation NCSU North Carolina State University NRC
U.S. Nuclear Regulatory Commission NRF
Nuclear Reactor Facility NRP
Nuclear Reactor Program OP
Operating Procedure PARS Publicly Available Records Rev.
Revision RO
Reactor Operator RSAC Reactor Safety and Auditing Committee RSC
Radiation Safety Committee SP
Special Procedure SRO
Senior Reactor Operator TS
Technical Specifications