IR 05000225/2009201
ML092710278 | |
Person / Time | |
---|---|
Site: | Rensselaer Polytechnic Institute |
Issue date: | 09/30/2009 |
From: | Blount T Division of Policy and Rulemaking |
To: | Geuther J Rensselaer Polytechnic Institute |
DONOHUE J, NRC/NRR/DPR/PRTB 415-3163 | |
References | |
IR-09-201 | |
Download: ML092710278 (17) | |
Text
ber 30, 2009
SUBJECT:
RENSSELAER POLYTECHNIC INSTITUTE - NRC ROUTINE INSPECTION REPORT NO. 50-225/2009-201 AND NOTICE OF VIOLATION
Dear Dr. Geuther:
This letter refers to the inspection conducted on August 31 - September 2, 2009, at your Rensselaer Polytechnic Institute (RPI) Reactor Critical Facility. The enclosed report documents the inspection results, which were discussed on September 2, 2009, with you, your staff and members of the Nuclear Safety Review Board (NSRB). The inspection included a review of activities authorized for your facility.
This inspection was an examination of activities conducted under your license as they relate to safety and compliance with the Commissions rules and regulations and with the conditions of your license. Within these areas, the inspection consisted of selected examination of procedures and representative records, observations of activities, and interviews with personnel.
Based on the results of this inspection, the U.S. Nuclear Regulatory Commission (NRC) has determined that a Severity Level IV violation of NRC requirements has occurred. The violation was evaluated in accordance with the NRC Enforcement Policy included on the NRCs Web site at www.nrc.gov; select What We Do, Enforcement, then Enforcement Policy. The violation is cited in the enclosed Notice of Violation (Notice) and the circumstances surrounding it are described in detail in the subject inspection report.
The NRC has concluded that information regarding the reason for the violation, the corrective actions planned and taken to correct the violation and prevent recurrence is already adequately addressed on the docket in Inspection Report No. 50-225/2009-201. Therefore, you are not required to respond to this letter unless the description herein does not accurately reflect your corrective actions or your position. In that case, or if you choose to provide additional information, you should follow the instructions specified in the enclosed Notice. In accordance with 10 CFR 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 NRC=s document system (Agencywide Document Access 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 Jack Donohue at 301-415-3163 or by electronic mail at Jack.Donohue@nrc.gov.
Sincerely,
/RA/
Thomas B. Blount, Deputy Director Division of Policy and Rulemaking Office of Nuclear Reactor Regulation Docket No. 50-225 License No. CX-22 Enclosures: 1. NRC Inspection Report No. 50-225/2009-201 2. Notice of Violation cc w/ encls: See next page
Rensselaer Polytechnic Institute Docket No. 50-225 cc:
Mayor of the City of Schenectady Schenectady, NY 12305 Barbara Youngberg Radiation Section Chief New York State Department of Environmental Conservation 625 Broadway Albany, NY 12233-7255 Dr. Tim Wei 2052 JEC Rensselaer Polytechnic Institute 110 8th Street Troy, NY 12181 Director, Bureau of Environmental Radiation Protection New York State Department of Health 547 River Street, Room 530 Troy, NY 12180-2216 Test, Research and Training Reactor Newsletter Director of Nuclear Facilities University of Florida 202 Nuclear Science Center Gainesville, FL 32611-8300 In accordance with 10 CFR 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 NRC=s document system (Agencywide Document Access 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 Jack Donohue at 301-415-3163 or by electronic mail at Jack.Donohue@nrc.gov.
Sincerely,
/RA/
Thomas B. Blount, Deputy Director Division of Policy and Rulemaking Office of Nuclear Reactor Regulation Docket No. 50-225 License No. CX-22 Enclosures: 1. NRC Inspection Report No. 50-225/2009-201 2. Notice of Violation cc w/ encls: See next page DISTRIBUTION:
PUBLIC PRTB/rf RidsNrrDprPrta RidsNrrDprPrtb WKennedy, NRR RidsOgcMailCenter MCompton, NRR(cover letter only, O13-E19)
GLappert, NRR ADAMS ACCESSION NO.: ML092710278 TEMPLATE #: NRC-002 OFFICE PRT:RI PRT:LA PRT:BC DPR:DD NAME JDonohue jjd GLappert gl JEads jhe TBlount tb DATE 9/29/09 9/29/09 9/30/09 9/30/09 OFFICIAL RECORD COPY
NOTICE OF VIOLATION Rensselar Polytechnic Institute Docket No. 50-225 Reactor Critical Facility License No. CX-22 During an NRC inspection conducted on August 31 - September 2, 2009, a violation (VIO) of NRC requirements was identified. In accordance with the NRC Enforcement Policy, the violation is listed below:
Rensselaer Polytechnic Institute Critical Facility License, CX-22, stipulates in Technical Specification (TS) 4.3 that The criticality detection system, area gamma monitor and the mobile particulate air monitor shall be checked daily if the reactor is operated, tested monthly and calibrated semi-annually.
Contrary to the above, the mobile particulate air monitor has not been calibrated semi-annually as required.
This has been determined to be a Severity Level IV violation (Supplement I).
The NRC has concluded that information regarding the reason for the violation; the corrective action planned and taken to correct the violation and prevent recurrence and the date when full compliance will be achieved is already adequately addressed on the docket in Inspection Report No. 50-225/2009-201. However, you are required to submit a written statement or explanation pursuant to 10 CFR 2.201 if the description therein does not accurately reflect your corrective actions or your position. In that case, or if you choose to respond, clearly mark your response as a "Reply to a Notice of Violation," include the VIO number, and send it to the U.S. Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington, DC 20555-0001 with a copy to the Director, Office of Nuclear Reactor Regulation within 30 days of the date of the letter transmitting this Notice of Violation (Notice).
If you choose to respond, your response will be made available electronically for public inspection in the NRC Public Document Room or from the NRC=s document system (ADAMS),
accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html. Therefore, to the extent possible, the response should not include any personal privacy, proprietary, or safeguards information so that it can be made available to the Public without redaction.
In accordance with 10 CFR 19.11, you may be required to post this Notice within two working days.
Dated this 30th day of September 2009
U. S. NUCLEAR REGULATORY COMMISSION OFFICE OF NUCLEAR REACTOR REGULATION Docket No: 50-225 License No: CX-22 Report No: 50-225/2009-201 Licensee: Rensselaer Polytechnic Institute Facility: Reactor Critical Facility Location: Schenectady, NY Dates: August 31-September 2, 2009 Inspector: Jack Donohue Approved by: Johnny H. Eads, Chief Research and Test Reactors Branch B Division of Policy and Rulemaking Office of Nuclear Reactor Regulation
EXECUTIVE SUMMARY Rensselaer Polytechnic Institute Reactor Critical Facility NRC Inspection Report No. 50-225/2009-201 The primary focus of this routine, announced, operations inspection was the on-site review of selected aspects of the Rensselaer Polytechnic Institutes (the licensees) research reactor safety program. This included a review of: organization and staffing, operations logs and records, research procedures, operator requalification, surveillance and limiting conditions for operations, experiments, design changes, committee, audits and reviews, maintenance logs and records, and fuel handling. The licensee's programs were acceptably directed toward the protection of public health and safety, and in compliance with NRC requirements.
Organization and Staffing The organization and staffing were consistent with Technical Specification (TS)
requirements.
Operations Logs and Records Operational activities were consistent with applicable TS and procedural requirements.
Procedures Procedural control and implementation satisfied TS requirements.
Operator Requalification The Reactor Operator Requalification Program was implemented satisfactorily, the program was up-to-date, and plan requirements were met.
Surveillance and Limiting Conditions for Operations The licensee's program for completing surveillance inspections and Limiting Conditions for Operation confirmations satisfied TS and licensee administrative controls except for TS 4.3. See Violation No. 50-225/2009-201-01.
Experiments The approval and control of experiments met TS and applicable regulatory requirements.
-2-Design Changes The licensee's design change program was being implemented as required.
Committees, Audits and Reviews Nuclear Safety Review Board review and audit functions required by the TS were being acceptably implemented.
Maintenance Logs and Records Maintenance logs, records, and performance satisfied TS and procedure requirements.
Fuel Handling Fuel handling activities were completed and documented as required by TS and facility procedures.
REPORT DETAILS Summary of Facility Status The Rensselaer Polytechnic Institute (RPI, the licensee) Reactor Critical Facility (RCF) Class II research reactor, licensed to operate at a maximum steady-state thermal power of 100 Watts, continued to be operated in support of academic instruction, operator training, surveillance, and research. During the inspection the reactor was not operated.
1. Organization and Staffing a. Inspection Scope (Inspection Procedure (IP) 69001-02.01)
The inspector reviewed the following regarding the licensee's organization and staffing to ensure that the requirements of Section 6.1 of the Technical Specifications (TS), Amendment No. 11 to License No. CX-22 dated September 7, 2004, were being met:
- Organizational structure
- Staffing requirements for safe operation of the research reactor facility
- Annual Report for the RPI-RCF for the Year 2007, February 29, 2008
- Standard Operating Procedures
- Reactor Critical Facility (RCF) Logbook entries from April 30, 2008 to present b. Observations and Findings Through discussions with licensee representatives, the inspector determined that the management structure met TS requirements. The RCF staff consisted of three part-time RPI employees, each holding an NRC Senior Reactor Operator (SRO) license, and three additional SROs; two being current RPI graduate students and the third being a recent RPI graduate working at the Knolls Atomic Power Laboratory but volunteering services and maintaining an SRO license.
The RCF Director, J.Geuther reports to the Head of the Mechanical, Aerospace and Nuclear Engineering (MANE) Department. Reporting to the RCF Director were Adjunct Professor T. Trumbull and Operations Supervisor J. Berry. The MANE Department Head T. Wei reports to D. Rosowsky, Dean of Engineering.
Through review of the reactor logbook the inspector verified that the individuals staffing for the reactor were clearly designated and met the TS requirements.
c. Conclusions The licensee's organization and staffing were in compliance with the requirements specified in the TS.
-2-2. Operations Logs and Records a. Inspection Scope (IP 69001-02.02)
The inspector reviewed selected parts of the following reactor operations records to verify that the requirements of TS Section 6.6 were being met:
- RCF Procedure, Pre-Startup Procedure, Revision (Rev.) 6.3, dated January 2009
- RCF Procedure, Pre-Startup Checklist, Version 2.3, dated July 2008
- RCF Procedure, Pre-Startup Checklist, Version 2.1, dated September 2006
- RCF Logbook entries from April 30, 2008 to present
- Completed Pre-start Checklists, October 2008 to present
- Completed Reactor Secured Checklists, October 2008 to present b. Observations and Findings The inspector found that records were comprehensive and complete indicating that the operations were conducted in accordance with written procedures that were properly reviewed and approved.
The procedures were electronically available for use at the control panel for use during reactor operations and maintenance of the reactor. The inspector determined the logs reflect accurate accounts of reactor operations and maintenance.
c. Conclusions Operational activities were consistent with applicable TS and procedural requirements.
3. Procedures a. Inspection Scope (IP 69001)
The inspector audited the following to ensure that the requirements of TS Section 6.2 were being met concerning written procedures:
- List of current versions of approved procedures and written procedures
- RCF Procedure: Operating Procedures, Version 2.1, dated September 2006
- RCF Procedure: Pre-Startup Procedure, Version 6.3, dated January 2009
-3-b. Observations and Findings The inspector determined that written procedures were available for the activities delineated in TS Section 6.2 and were approved by the Nuclear Safety Review Board (NSRB) before they were implemented. The clarity and detail in the procedures were acceptable. Temporary changes to the procedures that do not change their original intent could be authorized by the Operations Supervisor and were required to be subsequently reviewed by the NSRB. RCF staff members conducted TS activities in accordance with applicable procedures.
c. Conclusions Procedural control and implementation satisfied TS requirements.
4. Requalification Training a. Inspection Scope (IP 69001-02.04)
The inspector reviewed the following to verify that the requirements of Title 10 of the Code of Federal Regulations (10 CFR) 50.55, Operators Licenses, were being met:
- Medical File for SROs
- RCF Logbook entries from April 30, 2008 to present b. Observations and Findings The licensees requalification program is in accordance with TS 6.1.4 and ANSI/ANS-15.4-1977, Section 4-6, American National Standard for Selection and Training of Personnel for Research Reactors. The inspector verified through review of records that RPI personnel holding SRO licenses undergo continuous training for oral checkouts, an annual operating test and a biennial written examination. The inspector reviewed records indicating that SROs performed requalification activities in accordance with the program. Additionally, the inspector reviewed medical records of all SROs and found them complete and satisfactory.
c. Conclusions Operator requalification was conducted as required by the licensees Requalification Program.
5. Surveillance and Limiting Conditions for Operation a. Inspection Scope (IP 69001-02.05)
The inspector reviewed the following to verify compliance with TS Section 3.0, Limiting Conditions for Operation, and to determine if the periodic surveillance
-4-tests on safety systems were performed as stipulated in TS Section 4.0, Surveillance Requirements:
- RCF Surveillance Procedures Version 3.0, dated February 2006
- RCF Procedure, Pre-Startup Procedure, Rev. 6.3, dated July 2008
- RCF Procedure, Pre-Startup Checklist, Version 2.3, dated July 2008
- RCF Procedure, Secured Checklist, Version 2.1, dated September 2006
- RCF Logbook entries from April 30, 2008 to present
- Completed Pre-start Checklists, October 2008 to present
- Completed Reactor Secured Checklists, October 2008 to present
- Gold foil activation for power calibration performed on August 6, 2008, per SOP Section C, Version 3, dated February, 2006 b. Observations and Findings The inspector selected a sample of the TS limiting conditions for operation to verify implementation. In general, the licensee demonstrated a method of compliance built into SOPs and documenting completion in reactor logbooks or on supplementary forms.
Surveillances were completed on schedule and in accordance with licensee procedures for those items on the audit list. The protocols and techniques were effective in verifying acceptable performance of the safety equipment checked.
The recorded results reviewed 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 with one noted exception, (VIO 50-225/2009-001-01) the mobile particulate air monitor is required to be calibrated semi-annually. The detector has not been calibrated for five years. It appears that the operations staff at the time agreed that this was not a useful evolution, but did not request a revision to the TS or justify why they did not agree with the basis for the semi-annual calibration provided in the TS.
The pre-start procedures at the facility requires the operator to test the area monitors and the mobile particulate air monitor instrument by holding a test source next to the detector and verifying the instrument responds as expected.
This satisfies the TS definition of the test and therefore as long as the reactor is operated at least monthly both the daily check and the monthly test are completed by this start-up procedure. The operator would sign the logbook to document the entire startup procedure. The signature in the logbook is the only documentation that the steps of the startup procedure, including the radiation detection system were performed.
Following identification of the violation, a plan was implemented by the licensee to satisfy the TS requirement and improve documentation of the checks. The corrective actions are as follows:
- The periodic surveillance summary sheet will be updated to include monthly tests of the radiation monitoring system. This item will be
-5-checked off each month after the pre-start procedure is completed for the first time each month.
- The existing calibration procedure for the mobile air particulate detector (APD) will be implemented immediately to satisfy the TS requirement to inspect the APD. This procedure will be executed semi-annually until such time as a revision to the TS removing the equipment is authorized.
It should be noted that following the inspection, the inspector was notified by the licensee that the plan was executed and the facility was now in compliance with the TS requirements.
c. Conclusions Operations were found to be in compliance with the limiting conditions for operation and surveillance requirements as stated in the TS except Section 4.3, Radiation Monitoring. The semi-annual calibrations of the mobile particulate air monitoring instrument were not recently performed and have been determined to be a Severity Level IV violation, failure to comply with the Action Statement for a TS (Supplement I).
6. Experiments a. Inspection Scope (IP 69001)
The inspector reviewed selected aspects of the following to verify compliance with TS Section 3.4:
- Experimental program requirements
- Experimental administrative controls and precautions
- RCF Logbook entries from April 30, 2008 to present
- Critical Benchmark Experiment Procedure Using Borobond', dated August 25, 2009 b. Observations and Findings There was one new experiment approved during the interval since the last inspection. Most of the utilization consisted of classroom training and performing previously approved experiments.
At the time of the inspection, preparatory work was in progress for a new experiment that had been recently approved by the NSRB. The purpose of the experiment is to perform reactivity measurements of ceramic material.
c. Conclusions The approval and control of experiments met TS and applicable regulatory requirements.
-6-7. Design Changes a. Inspection Scope (IP 69001)
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 for the past two years
- RCF Logbook entries from April 30, 2008 to present
- RCF Procedures b. Observations and Findings Through review of applicable records and interviews with licensee personnel, the inspector determined that no significant changes had been completed at the facility since the last inspection. The inspector verified that administrative controls were in place that required the appropriate review and approval of all changes prior to implementation and previous changes had been performed in accordance with regulatory requirements.
c. Conclusions Based on the records reviewed, the inspector determined that the licensee's design change program was being implemented as required.
8. Committees, Audits, and Reviews a. Inspection Scope (IP 69001)
The inspector reviewed the following to ensure that the audits and reviews stipulated in TS Section 6.1.5 and 10 CFR 50.59 were being completed by the NSRB:
- [Quarterly] RCF Checks, dated November 5, 2008 to July 22, 2009
-7-b. Observations and Findings The TS for the RPI RCF required semiannual meetings of the NSRB. The inspector reviewed the minutes for the last two years and found them compliant with the TS requirements. The TS requires an annual assessment of reactor operations. This assessment of reactor operations was conducted by the RSO on reactor equipment; criticality detectors, area monitors particulate activity detectors, portable detectors and event contact lists Additionally, the audit covered surveillance items, rod timing, moderator dump time, instrument channel calibration, reactor parameters, radiation detectors, contamination inspection and material reports and provide advice to the Facility Director. The RSO proceeded to briefly stipulate the NSRB composition, a brief set of rules, and descriptions of the review and audit functions. The review function included new tests and experiments of a significant difference, reportable occurrences and TS changes.
The inspector noted that the SRO performed quarterly reviews at the RCF. The inspector in discussion with the NSRB chair indicated the NSRB had awareness as to the state of reactor operations and their commitment to provide oversight as required in its operations.
c. Conclusions NSRB review and audit functions required by the TS were being acceptably implemented and documented.
9. Maintenance Logs and Records a. Inspection Scope (IP 69001-02.11)
The inspector reviewed the following selected maintenance logs and records to verify compliance with the requirements of regulations and TS Sections 6.2.7, 6.5.1.d, and 6.6.1.a:
- RCF Logbook entries from April 30, 2008 to present
- Annual Report for the RPI-RCF for the Year 2007, dated February 29, 2008 b. Observations and Findings The inspector reviewed selected portions of the reactor logbooks governing the interval of time since the previous inspection. Major maintenance activities were found documented there with detail commensurate with the safety significance of the activity.
During log review, the inspector reviewed bank worth measurements, integral rod worth, ceramic material testing, power calibrations, temperature measurement, gold foil activation and rod drop testing. The logs were complete, well written and comprehensive.
-8-c. Conclusions Maintenance performed along with logs and records of maintenance activities met TS requirements.
10. Fuel Handling Logs and Records a. Inspection Scope (IP 69001-02.12)
The inspector reviewed the following to verify compliance with requirements of TS Sections 5.6 and 6.2.2:
- RCF Logbook entries from April 30, 2008 to present
- RCF Procedure, Operating Procedure Section C, Fuel Handling, Version 2.1, dated September 2006 b. Observations and Findings The inspector reviewed a core configuration change on August 13, 2008. Fuel was moved in accordance with an approved written procedure and recorded in the reactor logbook. The inspector noted that no fuel movement operation was performed during the last calendar year.
c. Conclusions Fuel handling activities were completed and documented as required by TS and facility procedures.
11. Exit Interview The inspection scope and results were summarized on September 2, 2009, with the Facility Director and NSRB. The inspector discussed the findings for each area reviewed. The licensee acknowledged the findings and did not identify as proprietary any of the material provided to or reviewed by the inspector during the inspection and the results of the inspection are subject to management review.
PARTIAL LIST OF PERSONS CONTACTED Licensee J. Berry Operations Supervisor P.Caracappa Radiation Safety Officer Reactor Critical Facility Director M.Podowski Chair Nuclear Safety Review Board T.Trumbull Adjunct Professor of Nuclear Engineering INSPECTION PROCEDURES USED IP 69001 Class II Non-Power Reactors ITEMS OPENED, CLOSED, AND DISCUSSED Opened VIO 50-225/2009-201-01 A Severity Level IV VIO for the failure to perform semi-annual calibrations of the mobile particulate air monitor per TS Section 4.3 Closed None LIST OF ACRONYMS USED ADAMS Agencywide Document Access and Management System ANSI/ANS American National Standards Institute/American Nuclear Society CFR Code of Federal Regulations IFI Inspector Follow-up Item IP Inspection Procedure NIMS National Incident Management System NSRB Nuclear Safety Review Board NRC Nuclear Regulatory Commission RCF Reactor Critical Facility Rev. Revision RPI Rensselaer Polytechnic Institute RSO Radiation Safety Officer SOP Standard Operating Procedure SRO Senior Reactor Operator TS Technical Specification VIO Violation