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[[Issue date::July 19, 2011]] | [[Issue date::July 19, 2011]] | ||
Dr. Paul Facility Director Dow Chemical Company 1602 Building Midland, MI 48674 | Dr. Paul J. O' Connor Facility Director Dow Chemical Company 1602 Building Midland, MI 48674 | ||
SUBJECT: DOW CHEMICAL COMPANY- NRC INSPECTION REPORT NO. 50-264/2011-201 | SUBJECT: DOW CHEMICAL COMPANY- NRC INSPECTION REPORT NO. 50-264/2011-201 | ||
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===Enclosure:=== | ===Enclosure:=== | ||
As stated cc w/encl: See next page July 19, 2011 Dr. Paul | As stated cc w/encl: See next page July 19, 2011 Dr. Paul J. O' Connor Facility Director Dow Chemical Company 1602 Building Midland, MI 48674 | ||
SUBJECT: DOW CHEMICAL COMPANY- NRC INSPECTION REPORT NO. 50-264/2011-201 | |||
==Dear Dr. O' Connor:== | |||
The U.S. Nuclear Regulatory Commission (NRC) conducted an inspection on June 27-30, 2011, at your DOW TRIGA Research Reactor (Inspection Report No. 50-264/2011-201). 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 (PARS) component of NRC's 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 Jack Donohue at 301-452-1950 or electronic mail at Jack.Donohue@nrc.gov. | |||
Sincerely,/RA/ Johnny H. Eads, Jr., Chief Research and Test Reactors Oversight Branch Division of Policy and Rulemaking Office of Nuclear Reactor Regulation Docket No. 50-264 License No. R-108 | |||
===Enclosure:=== | |||
As stated cc w/encl: See next page DISTRIBUTION: PUBLIC PRTB/rf RidsNrrDprPrta RidsOgcMailCenter JDonohue, NRR GWertz, NRR RidsNrrDprPrtb BDavis (Ltr only O13-E19) | |||
GLappert, NRR Accession Number: ML111950101 TEMPLATE #: NRC-002 OFFICE PROB:RI PRPB:LA PROB:BC NAME JDonohue GLappert JEads DATE 7/12/11 7/13/11 7/19/11 OFFICIAL RECORD COPY U. S. NUCLEAR REGULATORY COMMISSION OFFICE OF NUCLEAR REACTOR REGULATION Docket No: 50-264 License No: R-108 Report No: 50-264/2011-201 Licensee: The Dow Chemical Company Facility: TRIGA Research Reactor Location: Midland, Michigan Dates: June 27 - 30, 2011 Inspector: Jack Donohue Accompaniment: Taylor Lichatz, Project Manager Approved by: Johnny H. Eads, Jr., Chief Research and Test Reactors Oversight Branch Division of Policy and Rulemaking Office of Nuclear Reactor Regulation EXECUTIVE SUMMARY The Dow Chemical Company TRIGA Research Reactor Inspection Report No. 50-264/2011-201 The primary focus of this routine, announced inspection was the onsite review of selected aspects of the Dow Chemical Company (the licensee's) Class II research reactor facility safety programs including surveillance and limiting conditions for operation; experiments; health physics; design changes; committees, audits and reviews; emergency planning; maintenance logs and records; fuel handling logs and records and transportation activities. The licensee's programs were acceptably directed toward the protection of public health and safety, and in compliance with U.S. Nuclear Regulatory Commission (NRC) requirements. Surveillance and Limiting Conditions for Operations Surveillance was observed to be performed in accordance with requirements as stated in the Technical Specifications. Experiments No new experiments were requested but procedures existed to review them pursuant to Technical Specification requirements should one be requested. Health Physics * Surveys were being completed and documented as required * Postings met regulatory requirements * Personnel dosimetry was being worn and recorded doses were within the NRC's regulatory limits * Radiation monitoring equipment was being maintained and calibrated as required * The Radiation Protection Program satisfied regulatory requirements * The radiation protection training program was being administered as required * Environmental monitoring satisfied license and regulatory requirements. Design Changes No changes, tests, or experiments subject to Title 10 of the Code of Federal Regulations (10 CFR) Section 50.59 reporting were performed. | |||
Committees, Audits and Reviews The Committee on Reactor Operations provided the oversight required by the Technical Specifications. Emergency Planning The emergency preparedness program was conducted in accordance with the Emergency Plan. Maintenance Logs and Records The licensee maintained records documenting principal maintenance activities. Fuel Handling Logs and Records Fuel handling and inspection activities were completed and documented as required by Technical Specification and facility procedures. Transportation of Radioactive Materials * The program for shipping radioactive material satisfied regulatory requirements. | |||
REPORT DETAILS Summary of Facility Status Dow Chemical Company's (the Licensee's) 300 kilowatt Training Research Isotope Production General Atomics (TRIGA) Mark I research reactor has been operated in support of experiments, reactor operator training, and periodic equipment surveillances. During the inspection, the reactor was operated in support of on-going work. | |||
1. Surveillance and Limiting Conditions for Operation a. Inspection Scope (IP 69001 and IP 92701) The inspector reviewed the following to ensure that the surveillance requirements and limiting conditions for operation (LCOs) specified in Technical Specification Section 4.0 were met: Dow Nuclear Research Reactor Procedure (DNRRP) No. 4.1.1, "Daily Prestart Checkout," Revision 11, dated November 2006 DNRRP No. 4.1.2, "Daily Startup/Shutdown (checklist)," Revision 11, dated November 2006 DNRRP No. 4.1.2, "Daily Checklist," Revision 11, dated December 2009 DNRRP No. 4.1.3, "Monthly Checklist," Revision 11, dated November 2006 DNRRP No. 4.1.4, "Semi-Annual Checklist," Revision 11, date November 2006 DNRRP No. 4.1.5, "Annual Checkout," Revision 11, dated November 2006 DNRRP No. 4.1.2.1, "Thermal Calibration," Revision 11, dated November 2006 DNRRP No. 4.2.2, "Area Monitor Calibration," Revision 11, dated September 2006 DNRRP No. 4.2.3, "Water Radioactivity Monitor Calibration," Revision 11, dated November 2006 DNRRP No. 4.2.4, "Continuous Air Monitor Calibration," dated Revision 11, dated November 2006 DNRRP No. 4.2.5, "Control Rod Calibration," dated June 6, 2008 DNRRP No. 4.4.1, "Procedure for the Control Rod Removal and Inspection," Revision 11, dated November 2006 DNRRP No. 4.4.2, "Rod Drop Time," Revision 0, dated November 11, 2006 Completed "Water Radioactivity Monitor Calibration" forms, dated from August 6, 2009 to January 14, 2011 Completed "Area Monitor Calibration" forms, dated from July 15, 2010 to January 13, 2011 Completed "Continuous Air Monitor Calibration" forms, dated from January 15, 2010 to January 14, 2011 Completed "Daily Checklist" forms, dated from January 2009 to present Completed "Thermal Calibration" forms, dated January 10, 2010, January 12, 2010 and January 14, 2011 Completed "Annual Checkout" forms, for 2010 and 2011 Completed "Semi-Annual Checklist" forms, dated January 21, 2009, August 11, 2009, January 21, 2010, August 2, 2010 and January 14, 2011 Completed "Monthly Checklist" forms, dated from January 2009 to present DOW TRIGA Research Reactor Annual Report - 2010, dated March 7, 2011 DOW TRIGA Research Reactor Annual Report - 20109, dated January 25, 2010 b. Observations and Findings The inspector noted that daily, monthly, semiannual, and annual channel checks, tests, and/or calibrations for TS-required surveillance were completed as required. The LCO verifications were completed on schedule and in accordance with licensee procedures. All of the recorded results were within the TS and procedurally prescribed parameters. The records and logs were noted to be complete and were being maintained as required. The procedures for the surveillances provided clear and concise direction and control of reactor operational tests and surveillances. The inspector observed the licensee complete the startup checkout form for TS required items on June 28, 2011. All of the items on the startup checkout form were carried out appropriately and the personnel conducting the tests did so in a safe and knowledgeable manner. The inspector verified that all of the checks conducted were in compliance with TS required values and parameters. c. Conclusion The licensee's program for completing surveillance inspections and LCO confirmations satisfied TS and licensee administrative controls. 2. Experiments a. Inspection Scope (IP 69001) To ensure that the requirements of TS Sections 3.7 and 6.4 were being met concerning experimental programs, the inspector reviewed selected aspects and/or portions of: Experimental administrative controls and precautions Approved reactor experiments documentation Review and approval process for experiments Reactor Operations Committee (ROC) meeting minutes, dated June 23, 2011, March 23, 2011, January 3, 2011, September 22, 2010 and July 14, 2010. Reactor Logbooks Nos. 107 to 111, covering operations from December 11, 2009 to present DNRRP No. 3, "Administrative Procedures," dated September 2006 DNRRP No 3.3,"Rules Governing Experiments, Storage and Handling of, and Accountability for Nuclear and Radioactive Material," dated September 2006 DNRRP No 3.3.1,"Classes of Experiments," dated September 2006 DNRRP No 3.3.5,"Authorization for Operation of the Reactor," dated September 2006 DNRRP No. 3.4, "Procedural and Administrative Limitations," dated July 2008 DNRRP No. 3.5, "Reactor Operations Log Book," dated September 2006 DNRRP No. 4.6.2a, "Samples in the Lazy Susan - Placement and Retrieval," Revision 11, dated November 2006 TRIGA Activation Request Form, Version 7, dated January 1997 Completed "TRIGA Activation Request Form" forms, dated from November 2009 to present Completed Approval Sheet for Special Experiments, "Annual Fuel Inspection," for 2010 and 2011 b. Observations and Findings One of the many uses for the Dow TRIGA Research Reactor (DTRR) is the irradiation of various materials. The most frequently used experimental facilities are the pneumatic tube irradiation facility and the lazy susan. Samples that have been irradiated at DTRR include various materials that are produced or utilized at Dow Chemical Company. All experiments conducted are in accordance with approved authorization requests. The Facility Director (FD) or Reactor Supervisor (RS) reviews and approves all routine samples to be irradiated in accordance with the TS limitations for each sample to be irradiated in the core. No new routine experiments had been initiated, reviewed, or approved since the previous inspection at the facility. One special experiment was approved to conduct the annual fuel inspections with a new camera device. This special inspection must obtain ROC approval prior to performance. All new and special experiments are reviewed and approved by the ROC. The inspector confirmed that all of the experiments conducted were in accordance with TS limits and procedural requirements. c. Conclusion No new experiments were requested. Procedures existed to review them pursuant to TS requirements should one be requested. 3. Health Physics a. Inspection Scope (IP 69001) The inspector reviewed the following to verify compliance with 10 CFR Part 19, 10 CFR Part 20, and the applicable TS requirements: * radiological signs and posting in various areas of the facility * area and personnel dosimetry results for 2010 and 2011 * facility and equipment during tours * radiation protection training records * maintenance and calibration of radiation monitoring equipment, including the water radioactivity monitor, area radiation monitor, and the continuous air monitor * organization and staffing * radiological signs and posting * facility monthly, annual, and other periodic contamination and area radiation surveys from January 2009 to January 2011 * monthly pool water Tritium analyses from October 2006 to November 2007 * TRIGA Reactor 2006 Annual Audit, dated January 28, 2011 * Radiation Safety Committee Meeting Minutes, dated January 2009 thru present * The Dow Chemical Company Radiation Protection Program Audit - Michigan Operations, dated January 10, 2010 * Procedure entitled, "Personnel and Area Survey Procedures Using a Geiger-Mueller (GM) Survey Meter," dated May 11, 2004 * Procedure entitled, "Wipe Testing Procedures - Loose Isotopes," dated May 11, 2004 * DNRRP No. 3.3.3, "Handling, Storage, and Disposal of Radioactive Material," dated September 2006 * DNRRP No. 4.2.2, "Area Monitor Calibration," dated November 2006 * DNRRP No. 4.2.3, "Water Radioactivity Monitor Calibration," dated November 2006 * DNRRP No. 4.2.4, "Continuous Air Monitor Calibration," dated November 2006 * DNRRP No. 4.7.1, "Wipe Tests and Radiation Surveys," dated November 2006 * DNRRP No. 4.7.2, "Procedure for the Disposal of Waste Generated in the Neutron Activation Analysis Group," dated June 2008 * Standard IH-477 - Radiation Protection Program, "Control of Ionizing Radiation Hazards," revised May 22, 2007 * Fate of Radioactive Effluents from the Michigan Operations Buildings, undated b. Observations and Findings (1) Surveys The inspector reviewed monthly radiation and contamination surveys of the reactor building, which were conducted by the facility staff. The results were documented on the appropriate forms, evaluated as required and corrective actions taken when readings or results exceeded set action levels. The number and location of survey points was adequate to characterize the radiological conditions. The licensee investigates any readings above background levels. The inspector verified that the Radiation Safety Officer (RSO) reviews all of the survey records. One elevated reading was discovered this year during the annual audit wipe test and decontaminated as necessary. The inspector verified that the licensee implemented corrective action to reduce the levels of contamination. The RSO also conducts an annual independent contamination survey of the facility and has verified that all of the readings are as expected. (2) Postings and Notices The inspector reviewed the postings required by 10 CFR Part 19 at the entrances to various controlled areas including the Reactor Bay, and radioactive material storage areas. The postings were acceptable and indicated the radiation and contamination hazards present. The facility's radioactive material storage areas were found to be properly posted. No unmarked radioactive material was found in the facility. (3) Dosimetry The licensee used a National Voluntary Laboratory Accreditation Program-accredited vendor to process personnel dosimetry. Through direct observation, the inspector determined that dosimetry was used in an acceptable manner by facility personnel. For visitors to the facility, radiation exposures are recorded through the permanent staff at the facility. Records indicate that no abnormal readings were obtained. | |||
An examination of the records for the inspection period showed that all exposures were well within NRC limits and within licensee action levels. All of the staff and researchers associated with the facility wear Optically Stimulated Luminescense Dosimeter (OSLD) badges and minimal doses were recorded for 2010 through present. The licensee indicated that 2010 exposures were 70 millirem (mrem) whole body and 100 mrem extremities. The licensee formally investigates any dosimetry readings that indicate a quarterly exposure above 125 millirem (mrem) for whole body. The as low as reasonably achievable (ALARA) goal specified in the radiation safety procedures is to keep exposures to less than 10% of the applicable NRC requirements and the licensee consistently meets this goal. (4) Radiation Monitoring Equipment The calibration verification of portable survey meters and friskers was completed by a contracted company. The fixed area radiation detectors were calibrated at the facility by the DTRR staff using a Cs-137 source. The calibration records of portable survey meters, friskers, fixed radiation detectors, and air monitoring equipment in use at the facility were reviewed. Calibration frequency met the requirements established in TS 4.4 while records were being maintained as required. The inspector verified that proper precautions are always used to maintain doses ALARA while conducting the calibrations. The inspector reviewed the licensee's tracking system for ensuring the instrument calibrations are completed on time and found it to be useful. (5) Radiation Protection Program The licensee's Radiation Protection Program (RPP) was established through the procedures. The RPP provides guidance for keeping doses ALARA and is consistent with the guidance in 10 CFR Part 20. The inspector verified that the RPP was being reviewed annually as required by 10 CFR 20.1101(c). No issues related to the RPP were identified in the review of the program. The RSO reviews the overall implementation of the radiation protection program at the DTRR. The RPP requires that all personnel who work with radioactive materials receive training in radiation protection, policies, procedures, requirements, and the facilities prior to having unescorted access at the facility. The RSO is responsible for conducting the training and all of the training is typically conducted both on a computer and with practical applications. A test is administered at the end of the training to verify that the individuals understood the material presented. The training covered the topics required to be taught in 10 CFR Part 19 and the review of training materials and tests indicated that the staff were instructed on the appropriate subjects. (6) Facility Tour The inspector toured the reactor facility, counting laboratories and accompanying facilities. Control of radioactive material and control of access to radiation and high radiation areas were observed to be acceptable. The postings and signs for these areas were appropriate. | |||
Licensee personnel followed the indicated precautions for access to controlled areas. (7) Environmental Monitoring Several OSLDs were placed around the inside walls of the reactor facility and minimal doses were recorded. Records show that there was minimal radiation exposure to the environment from the reactor during the previous year. There was no liquid effluent discharged from the reactor facility. The licensee indicated that gaseous effluents from the reactor facility were less than 1 mrem/year. c. Conclusion The inspector determined that: (1) surveys were being completed and documented as required, (2) postings met regulatory requirements, (3) personnel dosimetry was being worn and recorded doses were within the NRC's regulatory limits, (4) radiation monitoring equipment was being maintained and calibrated as required, (5) the RPP satisfied regulatory requirements, 6) the radiation protection training program was being administered as required, and 7) environmental monitoring satisfied license and regulatory requirements. | |||
4. Design Changes a. Inspection Scope (IP 69001) The inspector reviewed the following materials to verify compliance with regulatory requirements. In order to verify that any modifications to the facility were consistent with 10 CFR 50.59, the inspector reviewed selected aspects of: Facility design changes and records Facility configuration and associated records ROC meeting minutes, dated June 23, 2011, March 23, 2011, January 3, 2011, September 22, 2010 and July 14, 2010. DNRRP No. 3, "Administrative Procedures," dated July 2008 DNRRP No. 3.2.2, "Reactor Operations Committee - DOW TRIGA Reactor," dated September 2006 DNRRP No. 3.4, "Procedural and Administrative Limitations," dated September 2006 DNRRP No. 4.5.3, "Maintenance," dated November 2006 DOW TRIGA Research Reactor Annual Report - dated January 25, 2010 b. Observations and Findings Through review of applicable records and interviews with licensee personnel, the inspector determined that there have not been any significant changes at the facility in the previous two years. c. Conclusion Based on the records reviewed, the inspector determined that the licensee's design change program was generally being implemented as required. 5. Committees, Audits, and Reviews The inspector reviewed the following to ensure that the audits and reviews stipulated in TS Section 6.2 were being completed by the ROC. a. Inspection Scope (IP 69001) Safety review records and audit reports since June 2001 Responses to the review and audit reports ROC meeting minutes, dated June 23, 2011, March 23, 2011, January 3, 2011, September 22, 2010 and July 14, 2010. Peer Review of the Dow TRIGA Research Reactor, dated November 17, 2010 DNRRP No. 3, "Administrative Procedures," dated September 2006 DNRRP No. 3.2.2, "Reactor Operations Committee - DOW TRIGA Reactor," dated, September 2006 DNRRP No 3.3, "Rules Governing Experiments, Storage and Handling of and Accountability for Nuclear and Radioactive Material," dated September 2006 DNRRP No. 3.4, "Procedural and Administrative Limitations," dated July 2008 b. Observations and Findings The ROC is defined in the TSs and the inspector verified that the committee is following all aspects of the requirements. The ROC had quarterly meetings as required by TS 6.2.1.c and a quorum was present as required. Review of the minutes indicated the ROC provided guidance, direction and oversight, and ensured suitable use of the reactor. The minutes provided an acceptable record of ROC review functions and of their safety oversight of reactor operations. Audits of the items required by TS 6.2.3 were completed by individuals appointed by members of the ROC. Minor issues that were not safety related were noted in the audit reports and meeting minutes and the inspector observed that any safety related items were properly controlled. A Peer Review Audit was additionally performed as requested by DNRRP. The inspector noted that the safety reviews and audits, and the associated findings, were acceptably detailed. The licensee immediately responded to all audit findings and ensured that the corrective actions were properly completed. c. Conclusion Review and oversight functions required by the TSs were acceptably completed by the ROC. 6. Emergency Planning a. Inspection Scope (IP 69001) The inspector reviewed the implementation of selected portions of the emergency preparedness program including: DTRR Emergency Plan (E-Plan), dated June 22, 2011 EP Drill for 2011, dated May 20, 2011 Procedure entitled, "1602 Building Radiation Emergency," revised July 27, 2007 Procedure entitled, " Emergency Procedures" dated February 2004 Emergency response facilities, supplies, equipment, and instrumentation Monthly Inventories of Emergency Equipment Memorandum of Agreement, State Office of Emergency Management, County of Midland Michigan, dated October 20, 2010 b. Observations and Findings The inspector reviewed the revised E-Plan in use at the DTRR and verified that the E-Plan was being properly implemented at the facility. The inspector reviewed the emergency facilities, instrumentation, and equipment and verified that the emergency response equipment, in general, was as described in the E-Plan. | |||
Through direct observation, records review, and interviews with emergency organization personnel, the inspector determined that they were capable to respond, and knowledgeable of the proper actions to take in case of an emergency. The facility staff is responsible for responding to an emergency during all hours and making assessments and corrective as well as protective actions. The responsibility and authority for directing and coordinating emergency response activities are assigned to the FD/RS, acting as the emergency director. All facility personnel receive annual emergency response training. The inspector verified that the licensee has continually reviewed the E-Plan and conducted an inventory of the emergency response equipment. Emergency drills had been conducted annually as required by the E-Plan. The drill for 2011 was both practical exercises and tested the notification and response of emergency personnel. Critiques were written and discussed following the drills to document any problems identified during the exercises. The action items that resulted were incorporated as part of the lesson learned policy. The inspector visited the 1100 building, which is the Dow Emergency Services and Security Center on June 28, 2011. While at the center, the inspector talked to the Emergency Services and Security Delivery Specialist about the supplies and equipment at the Support Center that would be available in case of an emergency. The coordinator stated that designated individuals on the emergency services teams had radiation training and if additional support is needed, other support staff can respond. The inspector interviewed dispatch personnel and observed response actions to several tested Reactor Building alarms. | |||
The inspector also visited the Dow Medical Center. The inspector talked to the Medical Physician and staff and discussed decontamination techniques used on medically injured personnel. The staff was very helpful and knowledgeable on the requirements and their responsibilities. The inspector observed that there appeared to be a good working relationship between the licensee and the Emergency Services and Security Center and the Medical Center which was capable to handle a variety of events that could happen at the DTRR. | |||
c. Conclusion The emergency preparedness program was conducted in accordance with the requirements stipulated in the E-Plan. 7. Maintenance Logs and Records a. Inspection Scope (IP 69001 To verify that the licensee was complying with the applicable regulations, the inspector reviewed selected aspects of: DTRR Maintenance Forms, dated from 2009 to present DNRRP No. 3, "Administrative Procedures," dated September 2006 DNRRP No. 4.5.3, "Maintenance," date June 16, 2008 Completed "Dow TRIGA Research Reactor Maintenance" forms, from 2010 to present b. Observations and Findings The inspector reviewed the maintenance records related to 2009, 2010 and 2011 scheduled and unscheduled preventive and corrective maintenance activities. Routine/preventive maintenance was controlled and documented on reactor maintenance forms, which are maintained in a binder. All maintenance of reactor systems was reviewed by the FD/RS or the alternate RS. Implementation of changes to equipment, systems, tests, or experiments are generally done by the staff at the facility. After all maintenance items are completed, system operational checks are performed to ensure the affected systems function before returning them to service. During a facility tour, the inspector noted that the equipment in the Control Room and the Reactor Room was operational. c. Conclusion Maintenance logs, records, and performance satisfied TS and procedure requirements. 8. Fuel Handling Logs and Records a. Inspection Scope (IP 69001) To verify that TS and procedural requirements were being met, the inspector reviewed selected aspects of: Reactor Logbooks Nos.107 to 111 covering operations from 2009 to present DNRRP No. 3.4, "Procedural and Administrative Limitations," dated July 2008 DNRRP No. 3.5, "Reactor Operations Log Book," Revision 0, dated September 2006 DNRRP No. 4.3.2, "Movement of Fuel - General Requirements," Revision 0,dated July 2, 2008 DNRRP No. 4.3.3, "Movement of Fuel - Approach to Criticality," Revision 0, dated July 2, 2008 DNRRP No. 4.3.4, "Procedure for the Performance of the Annual Fuel Inventory," Revision 0, dated July 2, 2008 DNRRP No. 4.4.1, "Procedure for the Control Rod Removal and Inspection," Revision 11, dated November 2006 DNRRP No. 4.5.3, "Maintenance," Revision 1, dated June 16, 2008 Fuel handling equipment and instrumentation Fuel movement and inspection records dated January 10, 2011 and January 30, 2010 b. Observations and Findings The inspector determined that the licensee was maintaining the required records of the various fuel movements that had been completed and verified that the movements were conducted and recorded in compliance with procedure. All fuel movements were noted in the Operating Logbook as well as in the Fuel Element Location and Inventory Logbook. The fuel element inspections generally included all of the fuel elements every four years and inspection of the control rods on an annual frequency, which is more frequent then the TS requirements. | |||
Inspections of the fuel elements and control rods showed consistency with accepted values and did not indicate any deterioration of cladding. Data recorded for fuel handling was clear and cross-referenced in the operations logs and the core map. Log entries clearly identified, as required by procedure, that a minimum of two persons were present when fuel was being moved. The inspector determined that the procedures and the controls specified (ROC approval) for these operations were acceptable. c. Conclusion Fuel handling and control rod inspection activities were completed and documented as required by TS and facility procedures. 9. Inspection of Transportation Activities a. Inspection Scope (IP 86740) To verify compliance with regulatory and procedural requirements for transferring or shipping licensed radioactive material, the inspector reviewed the following: * Selected records of various types of radioactive material shipments * Dow Radiation Protection Manual b. Observations and Findings Through records review and discussions with licensee personnel, the inspector determined that the licensee had not shipped any radioactive material since the previous inspection in this area under the reactor license. Transfer of radioactive material to other Dow facilities was under the Broad Scope License (21-00265-06) with guidance from the Radiation Safety Committee, the RSO and the Dow Radiation Protection Manual. | |||
c. Conclusion No radioactive material shipments had been made under the auspices of the reactor license during the past year. | |||
10. Exit Interview The inspector presented the inspection results to licensee management at the conclusion of the inspection on June 30, 2011. The inspector described the areas inspected and discussed in detail the inspection observations. No dissenting comments were received from the licensee. The licensee acknowledged the findings presented and did not identify as proprietary any of the material provided to or reviewed by the inspector during the inspection. | |||
PARTIAL LIST OF PERSONS CONTACTED Licensee B. Haskins SRO - Assistant Reactor Supervisor K. Kisser Dispatcher - Emergency Services W. Konze Chairman, Reactor Operations Committee and Director Analytical Sciences - Core R&D M. Lee Medical Physician and Medical Center Director J. Morris Emergency Services and Security Specialist P. O'Connor Facility Director J. Seeburger Emergency Services and Security Operation Leader J. Weldy Radiation Safety Officer S. Yusuf Reactor Supervisor INSPECTION PROCEDURES USED IP 69001 CLASS II NON-POWER REACTORS ITEMS OPENED, CLOSED, AND DISCUSSED Opened: None Closed: None Discussed: None LIST OF ACRONYMS USED 10 CFR Title 10 of the Code of Federal Regulations ADAMS Agencywide Documents Access and Management System ALARA As Low As Reasonably Achievable DNRRP Dow Nuclear Research Reactor Procedure DTRR Dow TRIGA Research Reactor FD/RS Facility Director/Reactor Supervisor IP Inspection Procedure MREM Millirem NRC U.S. Nuclear Regulatory Commission OSLD Optically Stimulated Luminescence Dosimeter ROC Reactor Operations Committee RPP Radiation Protection Program RS Reactor Supervisor RSO Radiation Safety Officer TRIGA Training Research Isotope Production General Atomics TS Technical Specification Dow Chemical Company Docket No. 50-264 cc: Office of the Mayor 333 West Ellsworth Midland, MI 48640 Office of the Governor Room 1 - Capitol Building Lansing, MI 48913 Alex Pollock Chair, Radiation Safety Committee 2030/410 Dow Center Midland, MI 48674 Dr. Sandeep Dhingra, Chair Reactor Operations Committee The Dow Chemical Company 1897 Building Midland, MI 48667 Test, Research, and Training Reactor Newsletter University of Florida 202 Nuclear Sciences Center Gainesville, FL 32611 | |||
}} | }} | ||
Revision as of 08:31, 22 February 2018
| ML111950101 | |
| Person / Time | |
|---|---|
| Site: | Dow Chemical Company |
| Issue date: | 07/19/2011 |
| From: | Johnny H. Eads Research and Test Reactors Branch B |
| To: | O'Connor P J Dow Chemical Co |
| DONOHUE J, NRC/NRR/DPR/PROB 415-3163 | |
| References | |
| IR-11-201 | |
| Download: ML111950101 (20) | |
Text
July 19, 2011
Dr. Paul J. O' Connor Facility Director Dow Chemical Company 1602 Building Midland, MI 48674
SUBJECT: DOW CHEMICAL COMPANY- NRC INSPECTION REPORT NO. 50-264/2011-201
Dear Dr. O' Connor:
The U.S. Nuclear Regulatory Commission (NRC) conducted an inspection on June 27-30, 2011, at your DOW TRIGA Research Reactor (Inspection Report No. 50-264/2011-201). 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 (PARS) component of NRC's 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 Jack Donohue at 301-452-1950 or electronic mail at Jack.Donohue@nrc.gov.
Sincerely,/RA/ Johnny H. Eads, Jr., Chief Research and Test Reactors Oversight Branch Division of Policy and Rulemaking Office of Nuclear Reactor Regulation Docket No. 50-264 License No. R-108
Enclosure:
As stated cc w/encl: See next page July 19, 2011 Dr. Paul J. O' Connor Facility Director Dow Chemical Company 1602 Building Midland, MI 48674
SUBJECT: DOW CHEMICAL COMPANY- NRC INSPECTION REPORT NO. 50-264/2011-201
Dear Dr. O' Connor:
The U.S. Nuclear Regulatory Commission (NRC) conducted an inspection on June 27-30, 2011, at your DOW TRIGA Research Reactor (Inspection Report No. 50-264/2011-201). 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 (PARS) component of NRC's 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 Jack Donohue at 301-452-1950 or electronic mail at Jack.Donohue@nrc.gov.
Sincerely,/RA/ Johnny H. Eads, Jr., Chief Research and Test Reactors Oversight Branch Division of Policy and Rulemaking Office of Nuclear Reactor Regulation Docket No. 50-264 License No. R-108
Enclosure:
As stated cc w/encl: See next page DISTRIBUTION: PUBLIC PRTB/rf RidsNrrDprPrta RidsOgcMailCenter JDonohue, NRR GWertz, NRR RidsNrrDprPrtb BDavis (Ltr only O13-E19)
GLappert, NRR Accession Number: ML111950101 TEMPLATE #: NRC-002 OFFICE PROB:RI PRPB:LA PROB:BC NAME JDonohue GLappert JEads DATE 7/12/11 7/13/11 7/19/11 OFFICIAL RECORD COPY U. S. NUCLEAR REGULATORY COMMISSION OFFICE OF NUCLEAR REACTOR REGULATION Docket No: 50-264 License No: R-108 Report No: 50-264/2011-201 Licensee: The Dow Chemical Company Facility: TRIGA Research Reactor Location: Midland, Michigan Dates: June 27 - 30, 2011 Inspector: Jack Donohue Accompaniment: Taylor Lichatz, Project Manager Approved by: Johnny H. Eads, Jr., Chief Research and Test Reactors Oversight Branch Division of Policy and Rulemaking Office of Nuclear Reactor Regulation EXECUTIVE SUMMARY The Dow Chemical Company TRIGA Research Reactor Inspection Report No. 50-264/2011-201 The primary focus of this routine, announced inspection was the onsite review of selected aspects of the Dow Chemical Company (the licensee's) Class II research reactor facility safety programs including surveillance and limiting conditions for operation; experiments; health physics; design changes; committees, audits and reviews; emergency planning; maintenance logs and records; fuel handling logs and records and transportation activities. The licensee's programs were acceptably directed toward the protection of public health and safety, and in compliance with U.S. Nuclear Regulatory Commission (NRC) requirements. Surveillance and Limiting Conditions for Operations Surveillance was observed to be performed in accordance with requirements as stated in the Technical Specifications. Experiments No new experiments were requested but procedures existed to review them pursuant to Technical Specification requirements should one be requested. Health Physics * Surveys were being completed and documented as required * Postings met regulatory requirements * Personnel dosimetry was being worn and recorded doses were within the NRC's regulatory limits * Radiation monitoring equipment was being maintained and calibrated as required * The Radiation Protection Program satisfied regulatory requirements * The radiation protection training program was being administered as required * Environmental monitoring satisfied license and regulatory requirements. Design Changes No changes, tests, or experiments subject to Title 10 of the Code of Federal Regulations (10 CFR) Section 50.59 reporting were performed.
Committees, Audits and Reviews The Committee on Reactor Operations provided the oversight required by the Technical Specifications. Emergency Planning The emergency preparedness program was conducted in accordance with the Emergency Plan. Maintenance Logs and Records The licensee maintained records documenting principal maintenance activities. Fuel Handling Logs and Records Fuel handling and inspection activities were completed and documented as required by Technical Specification and facility procedures. Transportation of Radioactive Materials * The program for shipping radioactive material satisfied regulatory requirements.
REPORT DETAILS Summary of Facility Status Dow Chemical Company's (the Licensee's) 300 kilowatt Training Research Isotope Production General Atomics (TRIGA) Mark I research reactor has been operated in support of experiments, reactor operator training, and periodic equipment surveillances. During the inspection, the reactor was operated in support of on-going work.
1. Surveillance and Limiting Conditions for Operation a. Inspection Scope (IP 69001 and IP 92701) The inspector reviewed the following to ensure that the surveillance requirements and limiting conditions for operation (LCOs) specified in Technical Specification Section 4.0 were met: Dow Nuclear Research Reactor Procedure (DNRRP) No. 4.1.1, "Daily Prestart Checkout," Revision 11, dated November 2006 DNRRP No. 4.1.2, "Daily Startup/Shutdown (checklist)," Revision 11, dated November 2006 DNRRP No. 4.1.2, "Daily Checklist," Revision 11, dated December 2009 DNRRP No. 4.1.3, "Monthly Checklist," Revision 11, dated November 2006 DNRRP No. 4.1.4, "Semi-Annual Checklist," Revision 11, date November 2006 DNRRP No. 4.1.5, "Annual Checkout," Revision 11, dated November 2006 DNRRP No. 4.1.2.1, "Thermal Calibration," Revision 11, dated November 2006 DNRRP No. 4.2.2, "Area Monitor Calibration," Revision 11, dated September 2006 DNRRP No. 4.2.3, "Water Radioactivity Monitor Calibration," Revision 11, dated November 2006 DNRRP No. 4.2.4, "Continuous Air Monitor Calibration," dated Revision 11, dated November 2006 DNRRP No. 4.2.5, "Control Rod Calibration," dated June 6, 2008 DNRRP No. 4.4.1, "Procedure for the Control Rod Removal and Inspection," Revision 11, dated November 2006 DNRRP No. 4.4.2, "Rod Drop Time," Revision 0, dated November 11, 2006 Completed "Water Radioactivity Monitor Calibration" forms, dated from August 6, 2009 to January 14, 2011 Completed "Area Monitor Calibration" forms, dated from July 15, 2010 to January 13, 2011 Completed "Continuous Air Monitor Calibration" forms, dated from January 15, 2010 to January 14, 2011 Completed "Daily Checklist" forms, dated from January 2009 to present Completed "Thermal Calibration" forms, dated January 10, 2010, January 12, 2010 and January 14, 2011 Completed "Annual Checkout" forms, for 2010 and 2011 Completed "Semi-Annual Checklist" forms, dated January 21, 2009, August 11, 2009, January 21, 2010, August 2, 2010 and January 14, 2011 Completed "Monthly Checklist" forms, dated from January 2009 to present DOW TRIGA Research Reactor Annual Report - 2010, dated March 7, 2011 DOW TRIGA Research Reactor Annual Report - 20109, dated January 25, 2010 b. Observations and Findings The inspector noted that daily, monthly, semiannual, and annual channel checks, tests, and/or calibrations for TS-required surveillance were completed as required. The LCO verifications were completed on schedule and in accordance with licensee procedures. All of the recorded results were within the TS and procedurally prescribed parameters. The records and logs were noted to be complete and were being maintained as required. The procedures for the surveillances provided clear and concise direction and control of reactor operational tests and surveillances. The inspector observed the licensee complete the startup checkout form for TS required items on June 28, 2011. All of the items on the startup checkout form were carried out appropriately and the personnel conducting the tests did so in a safe and knowledgeable manner. The inspector verified that all of the checks conducted were in compliance with TS required values and parameters. c. Conclusion The licensee's program for completing surveillance inspections and LCO confirmations satisfied TS and licensee administrative controls. 2. Experiments a. Inspection Scope (IP 69001) To ensure that the requirements of TS Sections 3.7 and 6.4 were being met concerning experimental programs, the inspector reviewed selected aspects and/or portions of: Experimental administrative controls and precautions Approved reactor experiments documentation Review and approval process for experiments Reactor Operations Committee (ROC) meeting minutes, dated June 23, 2011, March 23, 2011, January 3, 2011, September 22, 2010 and July 14, 2010. Reactor Logbooks Nos. 107 to 111, covering operations from December 11, 2009 to present DNRRP No. 3, "Administrative Procedures," dated September 2006 DNRRP No 3.3,"Rules Governing Experiments, Storage and Handling of, and Accountability for Nuclear and Radioactive Material," dated September 2006 DNRRP No 3.3.1,"Classes of Experiments," dated September 2006 DNRRP No 3.3.5,"Authorization for Operation of the Reactor," dated September 2006 DNRRP No. 3.4, "Procedural and Administrative Limitations," dated July 2008 DNRRP No. 3.5, "Reactor Operations Log Book," dated September 2006 DNRRP No. 4.6.2a, "Samples in the Lazy Susan - Placement and Retrieval," Revision 11, dated November 2006 TRIGA Activation Request Form, Version 7, dated January 1997 Completed "TRIGA Activation Request Form" forms, dated from November 2009 to present Completed Approval Sheet for Special Experiments, "Annual Fuel Inspection," for 2010 and 2011 b. Observations and Findings One of the many uses for the Dow TRIGA Research Reactor (DTRR) is the irradiation of various materials. The most frequently used experimental facilities are the pneumatic tube irradiation facility and the lazy susan. Samples that have been irradiated at DTRR include various materials that are produced or utilized at Dow Chemical Company. All experiments conducted are in accordance with approved authorization requests. The Facility Director (FD) or Reactor Supervisor (RS) reviews and approves all routine samples to be irradiated in accordance with the TS limitations for each sample to be irradiated in the core. No new routine experiments had been initiated, reviewed, or approved since the previous inspection at the facility. One special experiment was approved to conduct the annual fuel inspections with a new camera device. This special inspection must obtain ROC approval prior to performance. All new and special experiments are reviewed and approved by the ROC. The inspector confirmed that all of the experiments conducted were in accordance with TS limits and procedural requirements. c. Conclusion No new experiments were requested. Procedures existed to review them pursuant to TS requirements should one be requested. 3. Health Physics a. Inspection Scope (IP 69001) The inspector reviewed the following to verify compliance with 10 CFR Part 19, 10 CFR Part 20, and the applicable TS requirements: * radiological signs and posting in various areas of the facility * area and personnel dosimetry results for 2010 and 2011 * facility and equipment during tours * radiation protection training records * maintenance and calibration of radiation monitoring equipment, including the water radioactivity monitor, area radiation monitor, and the continuous air monitor * organization and staffing * radiological signs and posting * facility monthly, annual, and other periodic contamination and area radiation surveys from January 2009 to January 2011 * monthly pool water Tritium analyses from October 2006 to November 2007 * TRIGA Reactor 2006 Annual Audit, dated January 28, 2011 * Radiation Safety Committee Meeting Minutes, dated January 2009 thru present * The Dow Chemical Company Radiation Protection Program Audit - Michigan Operations, dated January 10, 2010 * Procedure entitled, "Personnel and Area Survey Procedures Using a Geiger-Mueller (GM) Survey Meter," dated May 11, 2004 * Procedure entitled, "Wipe Testing Procedures - Loose Isotopes," dated May 11, 2004 * DNRRP No. 3.3.3, "Handling, Storage, and Disposal of Radioactive Material," dated September 2006 * DNRRP No. 4.2.2, "Area Monitor Calibration," dated November 2006 * DNRRP No. 4.2.3, "Water Radioactivity Monitor Calibration," dated November 2006 * DNRRP No. 4.2.4, "Continuous Air Monitor Calibration," dated November 2006 * DNRRP No. 4.7.1, "Wipe Tests and Radiation Surveys," dated November 2006 * DNRRP No. 4.7.2, "Procedure for the Disposal of Waste Generated in the Neutron Activation Analysis Group," dated June 2008 * Standard IH-477 - Radiation Protection Program, "Control of Ionizing Radiation Hazards," revised May 22, 2007 * Fate of Radioactive Effluents from the Michigan Operations Buildings, undated b. Observations and Findings (1) Surveys The inspector reviewed monthly radiation and contamination surveys of the reactor building, which were conducted by the facility staff. The results were documented on the appropriate forms, evaluated as required and corrective actions taken when readings or results exceeded set action levels. The number and location of survey points was adequate to characterize the radiological conditions. The licensee investigates any readings above background levels. The inspector verified that the Radiation Safety Officer (RSO) reviews all of the survey records. One elevated reading was discovered this year during the annual audit wipe test and decontaminated as necessary. The inspector verified that the licensee implemented corrective action to reduce the levels of contamination. The RSO also conducts an annual independent contamination survey of the facility and has verified that all of the readings are as expected. (2) Postings and Notices The inspector reviewed the postings required by 10 CFR Part 19 at the entrances to various controlled areas including the Reactor Bay, and radioactive material storage areas. The postings were acceptable and indicated the radiation and contamination hazards present. The facility's radioactive material storage areas were found to be properly posted. No unmarked radioactive material was found in the facility. (3) Dosimetry The licensee used a National Voluntary Laboratory Accreditation Program-accredited vendor to process personnel dosimetry. Through direct observation, the inspector determined that dosimetry was used in an acceptable manner by facility personnel. For visitors to the facility, radiation exposures are recorded through the permanent staff at the facility. Records indicate that no abnormal readings were obtained.
An examination of the records for the inspection period showed that all exposures were well within NRC limits and within licensee action levels. All of the staff and researchers associated with the facility wear Optically Stimulated Luminescense Dosimeter (OSLD) badges and minimal doses were recorded for 2010 through present. The licensee indicated that 2010 exposures were 70 millirem (mrem) whole body and 100 mrem extremities. The licensee formally investigates any dosimetry readings that indicate a quarterly exposure above 125 millirem (mrem) for whole body. The as low as reasonably achievable (ALARA) goal specified in the radiation safety procedures is to keep exposures to less than 10% of the applicable NRC requirements and the licensee consistently meets this goal. (4) Radiation Monitoring Equipment The calibration verification of portable survey meters and friskers was completed by a contracted company. The fixed area radiation detectors were calibrated at the facility by the DTRR staff using a Cs-137 source. The calibration records of portable survey meters, friskers, fixed radiation detectors, and air monitoring equipment in use at the facility were reviewed. Calibration frequency met the requirements established in TS 4.4 while records were being maintained as required. The inspector verified that proper precautions are always used to maintain doses ALARA while conducting the calibrations. The inspector reviewed the licensee's tracking system for ensuring the instrument calibrations are completed on time and found it to be useful. (5) Radiation Protection Program The licensee's Radiation Protection Program (RPP) was established through the procedures. The RPP provides guidance for keeping doses ALARA and is consistent with the guidance in 10 CFR Part 20. The inspector verified that the RPP was being reviewed annually as required by 10 CFR 20.1101(c). No issues related to the RPP were identified in the review of the program. The RSO reviews the overall implementation of the radiation protection program at the DTRR. The RPP requires that all personnel who work with radioactive materials receive training in radiation protection, policies, procedures, requirements, and the facilities prior to having unescorted access at the facility. The RSO is responsible for conducting the training and all of the training is typically conducted both on a computer and with practical applications. A test is administered at the end of the training to verify that the individuals understood the material presented. The training covered the topics required to be taught in 10 CFR Part 19 and the review of training materials and tests indicated that the staff were instructed on the appropriate subjects. (6) Facility Tour The inspector toured the reactor facility, counting laboratories and accompanying facilities. Control of radioactive material and control of access to radiation and high radiation areas were observed to be acceptable. The postings and signs for these areas were appropriate.
Licensee personnel followed the indicated precautions for access to controlled areas. (7) Environmental Monitoring Several OSLDs were placed around the inside walls of the reactor facility and minimal doses were recorded. Records show that there was minimal radiation exposure to the environment from the reactor during the previous year. There was no liquid effluent discharged from the reactor facility. The licensee indicated that gaseous effluents from the reactor facility were less than 1 mrem/year. c. Conclusion The inspector determined that: (1) surveys were being completed and documented as required, (2) postings met regulatory requirements, (3) personnel dosimetry was being worn and recorded doses were within the NRC's regulatory limits, (4) radiation monitoring equipment was being maintained and calibrated as required, (5) the RPP satisfied regulatory requirements, 6) the radiation protection training program was being administered as required, and 7) environmental monitoring satisfied license and regulatory requirements.
4. Design Changes a. Inspection Scope (IP 69001) The inspector reviewed the following materials to verify compliance with regulatory requirements. In order to verify that any modifications to the facility were consistent with 10 CFR 50.59, the inspector reviewed selected aspects of: Facility design changes and records Facility configuration and associated records ROC meeting minutes, dated June 23, 2011, March 23, 2011, January 3, 2011, September 22, 2010 and July 14, 2010. DNRRP No. 3, "Administrative Procedures," dated July 2008 DNRRP No. 3.2.2, "Reactor Operations Committee - DOW TRIGA Reactor," dated September 2006 DNRRP No. 3.4, "Procedural and Administrative Limitations," dated September 2006 DNRRP No. 4.5.3, "Maintenance," dated November 2006 DOW TRIGA Research Reactor Annual Report - dated January 25, 2010 b. Observations and Findings Through review of applicable records and interviews with licensee personnel, the inspector determined that there have not been any significant changes at the facility in the previous two years. c. Conclusion Based on the records reviewed, the inspector determined that the licensee's design change program was generally being implemented as required. 5. Committees, Audits, and Reviews The inspector reviewed the following to ensure that the audits and reviews stipulated in TS Section 6.2 were being completed by the ROC. a. Inspection Scope (IP 69001) Safety review records and audit reports since June 2001 Responses to the review and audit reports ROC meeting minutes, dated June 23, 2011, March 23, 2011, January 3, 2011, September 22, 2010 and July 14, 2010. Peer Review of the Dow TRIGA Research Reactor, dated November 17, 2010 DNRRP No. 3, "Administrative Procedures," dated September 2006 DNRRP No. 3.2.2, "Reactor Operations Committee - DOW TRIGA Reactor," dated, September 2006 DNRRP No 3.3, "Rules Governing Experiments, Storage and Handling of and Accountability for Nuclear and Radioactive Material," dated September 2006 DNRRP No. 3.4, "Procedural and Administrative Limitations," dated July 2008 b. Observations and Findings The ROC is defined in the TSs and the inspector verified that the committee is following all aspects of the requirements. The ROC had quarterly meetings as required by TS 6.2.1.c and a quorum was present as required. Review of the minutes indicated the ROC provided guidance, direction and oversight, and ensured suitable use of the reactor. The minutes provided an acceptable record of ROC review functions and of their safety oversight of reactor operations. Audits of the items required by TS 6.2.3 were completed by individuals appointed by members of the ROC. Minor issues that were not safety related were noted in the audit reports and meeting minutes and the inspector observed that any safety related items were properly controlled. A Peer Review Audit was additionally performed as requested by DNRRP. The inspector noted that the safety reviews and audits, and the associated findings, were acceptably detailed. The licensee immediately responded to all audit findings and ensured that the corrective actions were properly completed. c. Conclusion Review and oversight functions required by the TSs were acceptably completed by the ROC. 6. Emergency Planning a. Inspection Scope (IP 69001) The inspector reviewed the implementation of selected portions of the emergency preparedness program including: DTRR Emergency Plan (E-Plan), dated June 22, 2011 EP Drill for 2011, dated May 20, 2011 Procedure entitled, "1602 Building Radiation Emergency," revised July 27, 2007 Procedure entitled, " Emergency Procedures" dated February 2004 Emergency response facilities, supplies, equipment, and instrumentation Monthly Inventories of Emergency Equipment Memorandum of Agreement, State Office of Emergency Management, County of Midland Michigan, dated October 20, 2010 b. Observations and Findings The inspector reviewed the revised E-Plan in use at the DTRR and verified that the E-Plan was being properly implemented at the facility. The inspector reviewed the emergency facilities, instrumentation, and equipment and verified that the emergency response equipment, in general, was as described in the E-Plan.
Through direct observation, records review, and interviews with emergency organization personnel, the inspector determined that they were capable to respond, and knowledgeable of the proper actions to take in case of an emergency. The facility staff is responsible for responding to an emergency during all hours and making assessments and corrective as well as protective actions. The responsibility and authority for directing and coordinating emergency response activities are assigned to the FD/RS, acting as the emergency director. All facility personnel receive annual emergency response training. The inspector verified that the licensee has continually reviewed the E-Plan and conducted an inventory of the emergency response equipment. Emergency drills had been conducted annually as required by the E-Plan. The drill for 2011 was both practical exercises and tested the notification and response of emergency personnel. Critiques were written and discussed following the drills to document any problems identified during the exercises. The action items that resulted were incorporated as part of the lesson learned policy. The inspector visited the 1100 building, which is the Dow Emergency Services and Security Center on June 28, 2011. While at the center, the inspector talked to the Emergency Services and Security Delivery Specialist about the supplies and equipment at the Support Center that would be available in case of an emergency. The coordinator stated that designated individuals on the emergency services teams had radiation training and if additional support is needed, other support staff can respond. The inspector interviewed dispatch personnel and observed response actions to several tested Reactor Building alarms.
The inspector also visited the Dow Medical Center. The inspector talked to the Medical Physician and staff and discussed decontamination techniques used on medically injured personnel. The staff was very helpful and knowledgeable on the requirements and their responsibilities. The inspector observed that there appeared to be a good working relationship between the licensee and the Emergency Services and Security Center and the Medical Center which was capable to handle a variety of events that could happen at the DTRR.
c. Conclusion The emergency preparedness program was conducted in accordance with the requirements stipulated in the E-Plan. 7. Maintenance Logs and Records a. Inspection Scope (IP 69001 To verify that the licensee was complying with the applicable regulations, the inspector reviewed selected aspects of: DTRR Maintenance Forms, dated from 2009 to present DNRRP No. 3, "Administrative Procedures," dated September 2006 DNRRP No. 4.5.3, "Maintenance," date June 16, 2008 Completed "Dow TRIGA Research Reactor Maintenance" forms, from 2010 to present b. Observations and Findings The inspector reviewed the maintenance records related to 2009, 2010 and 2011 scheduled and unscheduled preventive and corrective maintenance activities. Routine/preventive maintenance was controlled and documented on reactor maintenance forms, which are maintained in a binder. All maintenance of reactor systems was reviewed by the FD/RS or the alternate RS. Implementation of changes to equipment, systems, tests, or experiments are generally done by the staff at the facility. After all maintenance items are completed, system operational checks are performed to ensure the affected systems function before returning them to service. During a facility tour, the inspector noted that the equipment in the Control Room and the Reactor Room was operational. c. Conclusion Maintenance logs, records, and performance satisfied TS and procedure requirements. 8. Fuel Handling Logs and Records a. Inspection Scope (IP 69001) To verify that TS and procedural requirements were being met, the inspector reviewed selected aspects of: Reactor Logbooks Nos.107 to 111 covering operations from 2009 to present DNRRP No. 3.4, "Procedural and Administrative Limitations," dated July 2008 DNRRP No. 3.5, "Reactor Operations Log Book," Revision 0, dated September 2006 DNRRP No. 4.3.2, "Movement of Fuel - General Requirements," Revision 0,dated July 2, 2008 DNRRP No. 4.3.3, "Movement of Fuel - Approach to Criticality," Revision 0, dated July 2, 2008 DNRRP No. 4.3.4, "Procedure for the Performance of the Annual Fuel Inventory," Revision 0, dated July 2, 2008 DNRRP No. 4.4.1, "Procedure for the Control Rod Removal and Inspection," Revision 11, dated November 2006 DNRRP No. 4.5.3, "Maintenance," Revision 1, dated June 16, 2008 Fuel handling equipment and instrumentation Fuel movement and inspection records dated January 10, 2011 and January 30, 2010 b. Observations and Findings The inspector determined that the licensee was maintaining the required records of the various fuel movements that had been completed and verified that the movements were conducted and recorded in compliance with procedure. All fuel movements were noted in the Operating Logbook as well as in the Fuel Element Location and Inventory Logbook. The fuel element inspections generally included all of the fuel elements every four years and inspection of the control rods on an annual frequency, which is more frequent then the TS requirements.
Inspections of the fuel elements and control rods showed consistency with accepted values and did not indicate any deterioration of cladding. Data recorded for fuel handling was clear and cross-referenced in the operations logs and the core map. Log entries clearly identified, as required by procedure, that a minimum of two persons were present when fuel was being moved. The inspector determined that the procedures and the controls specified (ROC approval) for these operations were acceptable. c. Conclusion Fuel handling and control rod inspection activities were completed and documented as required by TS and facility procedures. 9. Inspection of Transportation Activities a. Inspection Scope (IP 86740) To verify compliance with regulatory and procedural requirements for transferring or shipping licensed radioactive material, the inspector reviewed the following: * Selected records of various types of radioactive material shipments * Dow Radiation Protection Manual b. Observations and Findings Through records review and discussions with licensee personnel, the inspector determined that the licensee had not shipped any radioactive material since the previous inspection in this area under the reactor license. Transfer of radioactive material to other Dow facilities was under the Broad Scope License (21-00265-06) with guidance from the Radiation Safety Committee, the RSO and the Dow Radiation Protection Manual.
c. Conclusion No radioactive material shipments had been made under the auspices of the reactor license during the past year.
10. Exit Interview The inspector presented the inspection results to licensee management at the conclusion of the inspection on June 30, 2011. The inspector described the areas inspected and discussed in detail the inspection observations. No dissenting comments were received from the licensee. The licensee acknowledged the findings presented and did not identify as proprietary any of the material provided to or reviewed by the inspector during the inspection.
PARTIAL LIST OF PERSONS CONTACTED Licensee B. Haskins SRO - Assistant Reactor Supervisor K. Kisser Dispatcher - Emergency Services W. Konze Chairman, Reactor Operations Committee and Director Analytical Sciences - Core R&D M. Lee Medical Physician and Medical Center Director J. Morris Emergency Services and Security Specialist P. O'Connor Facility Director J. Seeburger Emergency Services and Security Operation Leader J. Weldy Radiation Safety Officer S. Yusuf Reactor Supervisor INSPECTION PROCEDURES USED IP 69001 CLASS II NON-POWER REACTORS ITEMS OPENED, CLOSED, AND DISCUSSED Opened: None Closed: None Discussed: None LIST OF ACRONYMS USED 10 CFR Title 10 of the Code of Federal Regulations ADAMS Agencywide Documents Access and Management System ALARA As Low As Reasonably Achievable DNRRP Dow Nuclear Research Reactor Procedure DTRR Dow TRIGA Research Reactor FD/RS Facility Director/Reactor Supervisor IP Inspection Procedure MREM Millirem NRC U.S. Nuclear Regulatory Commission OSLD Optically Stimulated Luminescence Dosimeter ROC Reactor Operations Committee RPP Radiation Protection Program RS Reactor Supervisor RSO Radiation Safety Officer TRIGA Training Research Isotope Production General Atomics TS Technical Specification Dow Chemical Company Docket No. 50-264 cc: Office of the Mayor 333 West Ellsworth Midland, MI 48640 Office of the Governor Room 1 - Capitol Building Lansing, MI 48913 Alex Pollock Chair, Radiation Safety Committee 2030/410 Dow Center Midland, MI 48674 Dr. Sandeep Dhingra, Chair Reactor Operations Committee The Dow Chemical Company 1897 Building Midland, MI 48667 Test, Research, and Training Reactor Newsletter University of Florida 202 Nuclear Sciences Center Gainesville, FL 32611