IR 05000284/2012201
| ML12249A062 | |
| Person / Time | |
|---|---|
| Site: | Idaho State University |
| Issue date: | 09/13/2012 |
| From: | Gregory Bowman Research and Test Reactors Branch B |
| To: | Kunze J Idaho State University |
| Lichatz, Taylor 301-415-7128 | |
| References | |
| IR-12-201 | |
| Download: ML12249A062 (20) | |
Text
September 13, 2012
SUBJECT:
IDAHO STATE UNIVERSITY - NRC INSPECTION REPORT NO.
50-284/2012-201
Dear Dr. Kunze:
On August 20-22, 2012, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at the Idaho State University AGN-201M Research Reactor Facility. The enclosed report documents the inspection results, which were discussed on August 22, 2012, with you, members of your staff, and members of the Reactor Safety Committee.
The inspection examined activities conducted under your license as they relate to safety and compliance with the Commissions rules and regulations and with the conditions of your license.
The inspector reviewed selected procedures and records, observed activities, and interviewed personnel. Based on the results of this inspection, no findings of significance were identified.
In accordance with Title 10 of the Code of Federal Regulations, Section 2.390 Exemptions, inspections, requests for withholding a copy of this letter, its enclosure, and your response (if any) will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records component of NRCs Agencywide Documents Access and Management System (ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).
Should you have any questions concerning this inspection, please contact Taylor Lichatz at 301-415-7128 or by electronic mail at Taylor.Lichatz@nrc.gov.
Sincerely,
/PIsaac for RA/
Gregory T. Bowman, Chief Research and Test Reactors Oversight Branch Division of Policy and Rulemaking Office of Nuclear Reactor Regulation Docket No. 50-284 License No. R-110
Enclosure: NRC Inspection Report No. 50-284/2012-201
cc w/encl: See next page
NRC-002 OFFICE PROB:RI*
PROB:LA PROB:BC NAME TLichatz GLappert GBowman DATE 9/6/2012 9/6/2012 9/13/2012
Idaho State University
Docket No. 50-284
cc:
Idaho State University ATTN: Adam Mallicoat Reactor Supervisor Campus Box 8060 Pocatello, ID 83209-8060
Idaho State University ATTN: Dr. George Imel, Dean College of Science and Engineering Campus Box 8060 Pocatello, ID 83209-8060
Idaho State University ATTN: Dr. Peter Farina Radiation Safety Officer Physics Department Box 8106 Pocatello, ID 83209-8106
Director Idaho Dept. of Environmental Quality 1410 North Hilton Boise, ID 83606
Test, Research and Training Reactor Newsletter 202 Nuclear Sciences Center University of Florida Gainesville, FL 32611
U. S. NUCLEAR REGULATORY COMMISSION OFFICE OF NUCLEAR REACTOR REGULATION
Docket No:
50-284
License No:
R-110
Report No:
50-284/2012-201
Licensee:
Idaho State University
Facility:
AGN-201M Reactor Facility
Location:
Pocatello, Idaho
Dates:
August 20-22, 2012
Inspector:
Taylor Lichatz
Approved by:
Gregory T. Bowman, Chief Research and Test Reactors Oversight Branch Division of Policy and Rulemaking Office of Nuclear Reactor Regulation
EXECUTIVE SUMMARY
Idaho State University AGN-201M Research Reactor Facility NRC Inspection Report No.: 50-284/2012-201
The primary focus of this routine, announced inspection included onsite review of selected aspects of Idaho State University (the licensees) Class II research reactor safety program including: procedures, experiments, health physics, design changes, committees, audits and reviews, and transportation of radioactive materials since the last U.S. Nuclear Regulatory Commission (NRC) inspection of these areas. The licensees programs were acceptably directed toward the protection of public health and safety and in compliance with NRC requirements.
Procedures
- Facility procedural review, revision, control, and implementation satisfied technical specification (TS) requirements.
Experiments
- Experiments were being reviewed in accordance with procedures and standard practice.
Health Physics
- Surveys were being completed and the results documented acceptably.
- Postings met the regulatory requirements.
- Personnel dosimetry was being worn as required and doses were well within NRC regulatory limits.
- Radiation monitoring equipment was being maintained and calibrated as required.
- Acceptable radiation protection training was being provided to staff members.
- The Radiation Protection and As Low As Reasonably Achievable Programs were being acceptably implemented.
- Effluent monitoring satisfied license and NRC regulatory requirements.
- Releases were within the specified NRC regulatory and TS limits.
Design Changes
- Based on the records reviewed, the inspector determined that the licensee's design change program was being implemented as required.
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Committees, Audits and Reviews
- The review and audit program was being conducted acceptably by the Reactor Safety Committee.
Transportation of Radioactive Materials
- No radioactive material had been shipped from the reactor facility under the reactor license during the past several years.
Follow-up
- The facility was generally resolving the follow-up items from previous inspections.
REPORT DETAILS
Summary of Plant Status
The Idaho State University (ISU, the licensee) Aerojet General Nucleonics-201M (AGN-201M)
Research Reactor Facility, licensed to operate at a maximum steady-state thermal power of 5 Watts, continued to be operated in support of operator training, surveillance, experiments, and laboratory work. During the inspection the reactor was not operational.
1.
Procedures
a.
Inspection Scope (IP 69001)
The inspector reviewed selected aspects of the following to verify that the licensee was complying with the requirements of technical specification (TS)
Sections 6.5 and 6.6:
- Selected forms and checklists
ISU AGN-201M Reactor Facility Master Log
Selected maintenance and surveillance procedures
Selected Operations Procedures and Radiation Protection Procedures
ISU AGN-201M General Rules, Rev. 4, dated September 19, 1994
TS for ISU AGN-201M Reactor, Amendment No. 7, approval dated February 23, 2011
AGN-201 Operating Procedure (OP) #1, Rev. 3, dated April 26, 1994
AGN-201 OP #2, Rev. 3, dated April 26, 1994
AGN-201 Experimental Procedure (EP) #12, Reactivity Oscillators for the AGN-201, Rev. 1, dated April 16, 2012
Form ROL-101 Rev. 3, April 26, 1994
Reactor Power as a function of Channel No. 3 Detector Current, dated May 9, 2012
List of Authorized Operators, October 26, 2009, last updated June 5, 2012
b.
Observations and Findings
The licensees procedures were found to be acceptable for current facility operations and the current staffing level. The inspector determined that the various facility procedures were being updated as needed and that substantive revisions to procedures, checklists, and forms were presented to the Reactor Safety Committee (RSC) for review and approval as required by TS. The inspector noted that there have been no new operating and surveillance procedures developed in the past few years. However, one new experimental procedure had been developed: "Reactivity Oscillators for the AGN-201." It was properly reviewed and approved by the RSC.
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During the inspection, the inspector noted that the licensee had not yet made the necessary changes in OP #1 to reflect the Glory Tube Irradiations that they previously committed to. The licensee informed the inspector that they discuss Glory Tube Irradiations in their operator training, but it is not reflected in any written documents. Therefore, Inspector Follow-Up Item (IFI) 50-284/2010-202-02 (NRC Report 50-284/2010-202, ADAMS Accession No. ML102290226) will remain open as well as IFI 50-284/2011-201-02 (discussed in NRC Report 50-284/2011-201, Agencywide Documents Access & Management System (ADAMS) Accession No. ML112350812 and NRC Report 50-284/2010-201, ADAMS Accession No. ML100321367).
c.
Conclusion
Procedural review, revision, control, and implementation satisfied TS requirements.
2.
Experiments
a.
Inspection Scope (IP 69001)
The inspector reviewed selected aspects of the following in order to verify that experiments were being conducted within approved guidelines:
- AGN-201 Operations Logs from January 2010 to Present
ISU AGN-201M Reactor Facility Master Log
ISU AGN-201 EP #12, Reactivity Oscillators for the AGN-201, Rev. 1, dated April 16, 2012
"Summary of 10 CFR 50.59 Analysis of Use of 'Pile Oscillator' in the AGN-201 Reactor," approval dated May 5, 2010
b.
Observations and Findings
During the inspection the inspector noted that there have been no new experiments created since the last inspection and there have been no changes to the current experiments. Therefore, the inspector reviewed the safety analysis for the pile oscillator device, the written experimental procedure for the pile oscillator device, and the relevant operations logs. The review process for the experiment was in accordance with the requirements of Title 10 of the Code of Federal Regulations (10 CFR) Section 50.59. The review identified potential hazards, experiment constraints, accounts for irradiated material, and determination of reactivity worth for the experiments. The operations logs appropriately record experiments performed.
c.
Conclusion
Experiments were being reviewed in accordance with licensee procedures and standard practice.
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3.
Health Physics
a.
Inspection Scope (IP 69001)
The inspector reviewed the following to verify compliance with 10 CFR Parts 19 and 20, and TS Sections 3.4, 4.2.3, 4.4c, 5.4, 6.6, and 6.7.2:
Radiological signs and postings
ISU AGN-201M Reactor Facility Master Log
Personnel dosimetry records for 2010 to present
ISU Radiation Safety Policy Manual, Rev. 8, dated August 17, 2009
Contamination and radiation survey records for reactor from 2010 to present
Records documenting the maintenance and calibration of radiation monitoring equipment from 2010 to present
Records of selected airborne releases
Records documenting the maintenance and calibration of radiation monitoring equipment from 2010 to present
Annual Operating Report for the Idaho State University AGN-201M Reactor, License No. R-110; Docket No. 50-284, for calendar year 2010, dated October 29, 2011
Annual Operating Report for the Idaho State University AGN-201M Reactor, License No. R-110; Docket No. 50-284, for calendar year 2011 dated July 20, 2012
AGN-201 Operations Logs from January 5, 2010 to Present documenting Pre-Start checks, surveys, and reactor operations
TS for ISU AGN-201M Reactor, Amendment No. 7, approval dated February 23, 2011
ISU AGN-201M General Rules, Rev. 4, dated September 19, 1994
AGN-201 OP #1, Rev. 3, dated April 26, 1994
AGN-201 OP #2, Rev. 3, dated April 26, 1994
ISU AGN-201M Visitor Log and Register for Organized Groups and Tours
ISU AGN-201M Experimental Plan No. 8, Health Physics Survey, Rev. 1, dated May 3, 1979
ISU Technical Safety Office (TSO) Radiation Procedures Manual (RPM)
Procedure Number TSO-08-02-Rev 2, Dosimetry, approval dated September 1, 2009
The inspector toured the licensee's facility, observed the use of dosimetry and radiation monitoring equipment, and interviewed licensee personnel.
b.
Observations and Findings
(1)
Surveys
Various periodic and Prestart-Up contamination and radiation surveys were completed by reactor staff and TSO personnel. Through records reviews and interviews with reactor and TSO staff members, the inspector
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determined that the contamination and radiation surveys were performed as required by TS Section 4.4.c and Radiation Safety procedures. The inspector verified that results were evaluated and corrective actions taken and documented as required when contamination levels exceeded the established limits. Radiation survey results were used to verify the location of radiation and high radiation areas and ensure 10 CFR 20.1902 postings were accurate.
(2)
Postings and Notices
During tours of the facility, the inspector observed caution signs and postings in place and controls established for the controlled areas were acceptable for the hazards involving radiation, high radiation, and contamination and were posted as required by 10 CFR Part 20, Subpart J. Through observations of and interviews with licensee staff, the inspector confirmed that personnel complied with the signs, postings, and controls. The facilitys radioactive material storage areas were noted to be generally properly posted. No unmarked radioactive material was detected in the facility.
Copies of current notices to workers were posted in various areas in the facility. Radiological signs were typically posted at the entrances to controlled areas. Other postings characterized the industrial hygiene hazards that were present in the areas. During one facility tour, the inspector noted that various copies of NRC Form-3, Notice to Employees, were posted at the facility as required by 10 CFR Part 19.11, were the current version. With the current version of NRC Form 3 posted, notices, caution signs, postings, and controls for radiation areas were as required in 10 CFR Parts 19 and 20.
(3)
Dosimetry
The licensee was provided dosimetry by the ISU TSO. The TSO used a National Voluntary Laboratory Accreditation Program accredited vendor, Landauer, to process the whole body optically stimulated thermoluminescent (OSL) dosimeters supplied to facility personnel.
Through direct observation, the inspector determined that dosimetry was acceptably used by facility personnel. Through an examination of the OSL dosimeter results since 1st quarter 2010, indicating exposure to radiation at the facility, it was determined that the doses were well within the 10 CFR Part 20 limits.
(4)
Radiation Monitoring Equipment
Examination of selected survey meters indicated that the instruments had the acceptable up-to-date calibration sticker attached. The instrument calibration records indicated the calibration of portable survey meters was typically completed by TSO personnel. On occasion, survey meters were
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sent to a contractor for calibration. Calibration frequency met the specified TS requirements and records were maintained as required.
Area radiation monitors were also being calibrated as required.
(5)
Radiation Protection Program
The licensees Radiation Protection Program was established in the Idaho State University Radiation Safety Policy Manual, Revision 8, with approval by the Radiation Safety Committee dated August 17, 2009. The program included requirements that all personnel who worked with radioactive materials receive training in radiation protection, policies, procedures, requirements, and facilities. Completion of this training was verified by each persons supervisor and by TSO personnel. The program appeared to be acceptable and was being reviewed annually as required by the Radiation Safety Officer.
(6)
As Low As Reasonably Achievable (ALARA) Program
The ALARA Program was outlined and established in Radiation Safety Policy Manual Section 3.1. The ALARA program provided guidance for keeping doses as low as reasonably achievable and was consistent with the guidance in 10 CFR Part 20.
(7)
Radiation Protection Training
The inspector reviewed the radiation worker (or rad worker) training given to reactor staff members, to those who were not on staff but who were authorized to use the experimental facilities of the reactor, and to student assistants working at the facility on a part-time basis. The inspector verified that rad worker training was given upon initial employment and refresher training was required annually thereafter. The documents of the training provided to licensee staff members indicated that all current staff members had received the required training. The inspector determined that the personnel training program satisfied requirements in 10 CFR 19.12.
(8)
Facility Tours
The inspector toured the Reactor Room, adjacent laboratories, and support areas. Control of radioactive material and control of access to radiation areas was acceptable.
(9)
Effluent and Environmental Monitoring
The inspector reviewed the records documenting airborne releases to the environment for the past two years. The inspector determined that gaseous releases continued to be calculated as required by licensee procedure and were adequately documented. The releases were
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determined to be within the annual dose constraints of 10 CFR 20.1101(d), 10 CFR Part 20, Appendix B concentrations, and TS limits.
The inspector confirmed that there had been no liquid or solid waste radioactive releases from the reactor facility during the past two years.
Through observation of the facility, the inspector found no new potential release paths.
On-site gamma radiation monitoring was completed using various thermoluminescent dosimeters (TLDs) placed around the facility in accordance with the applicable procedures. The data indicated that there were no measurable doses to the public above any NRC regulatory limits.
c.
Conclusion
The inspector determined that the Radiation Protection and ALARA Programs satisfied NRC regulatory requirements. Surveys were being completed and documented acceptably. Postings met NRC regulatory requirements. Personnel dosimetry was being worn as required and doses were well within the NRCs regulatory limits. Radiation monitoring equipment was being maintained and calibrated as required. Acceptable radiation protection training was being provided. Effluent monitoring satisfied license and NRC regulatory requirements, and releases were within the specified NRC regulatory and TS limits.
4.
Design Changes
a.
Inspection Scope (IP 69001)
The inspector reviewed the following to verify compliance with the requirements
of 10 CFR 50.59:
- Summary Review of 10 CFR 50.59 Analysis of the use of "Pile Oscillator" in the AGN-201 Reactor, Approval dated March 5, 2010
Annual Operating Report for the Idaho State University AGN-201M Reactor, License No. R-110; Docket No. 50-284, for calendar year 2010, dated October 29, 2011
Annual Operating Report for the Idaho State University AGN-201M Reactor, License No. R-110; Docket No. 50-284, for calendar year 2011 dated July 20, 2012
Reactor Safety Committee meeting minutes since February 2010
b.
Observations and Findings
The facility has made one design change to the facility since the last inspection; the addition of a pile oscillator device mounted outside of the reactor tank. The oscillator is intended to measure small amounts of radioactivity via small fluctuations between 1 and 5 cycles per second. The inspector reviewed the screening analysis required under the stipulations of 10 CFR 50.59 to ensure that
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the design changes do not alter the safety functions as described by the facility Final Safety Analyses Report (FSAR). The screening process and administrative process that the facility uses to review and approve changes in accordance with 10 CFR 50.59 is acceptable.
The inspector also discussed with the licensee their intentions to add a newer solid state reactor console. Several years ago the licensee performed a 10 CFR 50.59 screening analysis on the upgrade and submitted their intentions to the NRC. However, the inspector informed the licensee that the previous 10 CFR 50.59 analysis that had been performed is now outdated and that NRC regulations have changed. Since the console upgrades have not been completed, there are several additional changes that the licensee plans to make, and are expected to continue, the licensee agreed to perform another 10 CFR Part 50.59 analysis on the solid state reactor console using their current process.
In order to track this progress, the inspector opened an Inspector Follow-Up Item (IFI) 50-284/2012-201-01.
c.
Conclusion
Based on the records reviewed, the inspector determined that the licensee's design change program was being implemented as required.
5.
Committees, Audits and Reviews
a.
Inspection Scope (IP 69001)
To verify that the licensee had established and conducted reviews and audits as required in TS Section 6.4 and to verify that modifications to the facility were being reviewed in accordance with the stipulations in 10 CFR 50.59 and approved as required by TS Section 6.5, the inspector reviewed:
- ISU AGN-201M Reactor Facility Master Log since January 2010
Completed audits and reviews since February 2010
Annual Operating Report for the Idaho State University AGN-201M Reactor, License No. R-110; Docket No. 50-284, for calendar year 2010, dated October 29, 2011
Annual Operating Report for the Idaho State University AGN-201M Reactor, License No. R-110; Docket No. 50-284, for calendar year 2011 dated July 20, 201
Reactor Safety Committee meeting minutes since February 2010
TS for ISU AGN-201M Reactor, Amendment No. 7, approval dated February 23, 2011
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b.
Observations and Findings
The inspector reviewed the RSC meeting minutes from February 2010 to the present. These meeting minutes showed, as required by TS Section 6.4.1, the committee met at least once per calendar year and that a quorum was present.
The topics considered during the meetings were appropriate and as stipulated in TS Section 6.1.8. Through review of the RSC minutes the inspector confirmed that the RSC reviewed proposed changes in the license, audit reports, and any reported violations as required by TS Section 6.4.2.
The inspector noted that members of the safety committee had completed audits of various aspects of the reactor facility operations, programs, and procedures as required by TS Section 6.4.3. The audits were structured so that the various aspects of the licensee's operations and safety programs and plans were reviewed annually. The inspector noted that the audit findings were acceptable and that the licensee responded and took corrective actions as needed, which included completion of TS activities. During several instances, the audits revealed that the licensee did not always complete TS surveillances within the specified interval. Since the inspector did not review surveillances during this inspection, the inspector opened IFI 50-284/2012-201-02 in order to track the timely completion of TS surveillances.
c.
Conclusion
The review and audit program was being conducted acceptably by the RSC.
6.
Transportation
a.
Inspection Scope (IP 86740)
The inspector reviewed the following to verify compliance with NRC regulatory and licensee procedural requirements for shipping or transferring licensed material:
Annual Operating Report for the Idaho State University AGN-201M Reactor, License No. R-110; Docket No. 50-284, for calendar year 2010, dated October 29, 2011
Annual Operating Report for the Idaho State University AGN-201M Reactor, License No. R-110; Docket No. 50-284, for calendar year 2011, dated July 20, 2012
AGN-201 Operations Log, Form ROL-101, Rev. 3, dated April 26, 1994, for the period from January 5, 2010, to the present documenting Pre-Start checks, surveys, and reactor operations
b.
Observations and Findings
Through records review and discussions with licensee personnel, the inspector determined that the licensee had not shipped any radioactive material from the
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facility under the reactor license in recent years. It was noted that radioactive material produced in the reactor was either transferred to the campus broadscope license (ISU Type A Broadscope Radioactive Materials License 11-27380-01) and shipped under the auspices of that license, or transferred to other authorized users on campus, or maintained at the reactor facility for use in laboratories in accordance with procedure.
c.
Conclusion
No radioactive material had been shipped from the reactor facility under the reactor license during the past several years.
7.
Follow-up on Previously Identified Issue
a.
Inspection Scope (IP 92701)
The inspector followed up on the Unresolved Item (URI) 50-284/2010-202-01 to follow-up on the termination of the two operator licenses that were in non-compliance with 10 CFR 55.53(h) and IFI 50-284/2011-201-04 to follow-up on the licensees requalification program. The inspector also reviewed and discussed with the licensee the following IFIs: IFI 50-284/2010-202-01 and IFI 50-284/2010-202-03, and the IFI 50-284/2011-202-01.
b.
Observations and Findings
URI 50-284/2011-201-03
The inspector followed-up on the URI 50-284/2011-201-03 (NRC Report 50-284/2011-201, ADAMS Accession No. ML112350812) regarding the termination of two operator licenses who were in non-compliance with 10 CFR 55.53(h). The two SROs failed to complete the requalification program. Through reviews of licensee documents, the inspector made note that the licenses had been terminated. Therefore, the inspector closed URI 50-284/2011-201-03.
IFI 50-284/2011-201-04
The inspector followed-up on the IFI 50-284/2011-201-04 (NRC Report 50-284/2011-201, ADAMS # ML112350812) to verify the licensee's commitment of having their qualification check-lists up-to-date. The inspector noted that the checklists are used as an aid for their requalification program tracking and were instituted by the facility as a result of Non-Cited Violation (NCV) 50-284/2007-201-01 (NRC Report 50-284/2007-201). The inspector reviewed the requalification checklists, RSC audits, and interviewed the licensee on the progress with their requalification program. As the licensee and licensee personnel are still updating and improving their program, IFI 50-284/2011-201-04 will remain open.
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IFI 50-284/2010-202-01
The inspector followed up on the IFI 50-284/2010-202-01 (NRC Report 50-284/2010-202, ADAMS Accession No. ML102290226) to verify the licensee's commitment to update the Control Rod reactivity rod worth curves and adequately perform the surveillance. The inspector reviewed the licensees records, logs, and facility audits and determined that the control rod reactivity rod worth curves were adequately being maintained. Therefore, the inspector closed IFI 50-284/2010-202-01.
IFI 50-284/2010-202-03
The inspector followed up on the IFI 50-284/2010-202-03 (NRC Report 50-284/2010-202, ADAMS Accession No. ML102290226) to verify the licensee's commitment to update the table of values "Reactor Power Level as a Function of Channel No. 3 Detector Current" and adequately perform the power calibration surveillance. The inspector reviewed the licensees records, logs, and facility audits and observed that the table of values Reactor Power Level as a Function of Channel No. 3 Detector Current was appropriately updated. Therefore, the inspector closed IFI 50-284/2010-202-03.
IFI 50-284/2011-201-01
The inspector followed-up on the IFI 50-284/2011-201-01 (NRC Report 50-284/2011-201, ADAMS # ML112350812) to confirm that no issues would result from the Reactor Administrator (RA) and Radiation Safety Officer (RSO) roles being performed by the same individual. From approximately April 2011 to approximately January 2012, when the new RSO was hired, Dr. Kunze, the RA, performed the roles of RA and RSO. There are no TS requirements which preclude D from performing the dual role. The inspector also interviewed the licensee and discussed the issue with other NRC personal. It was determined that both positions were satisfactorily performed and that no issues resulted. Therefore, the inspector closed IFI 50-284/2011-201-01.
c.
Conclusion
The following IFIs are considered closed: IFI 50-284/2010-202-01, IFI 50-284/2010-202-03, and IFI 50-284/2011-201-01. It was determined that a violation did not result from URI 50-284/2011-201-03 and is considered closed.
The IFI 50-284/2011-201-04 will remain open.
8.
Exit Meeting Summary
The inspection scope and results were summarized on August 22, 2012, with licensee
representatives. The inspector discussed the findings for each area reviewed.
PARTIAL LIST OF PERSONS CONTACTED
Licensee
A. Mallicoat
Reactor Supervisor G. Imel
Dean, College of Science and Engineering Reactor Administrator, Nuclear Engineering Department
Other Personnel
R. Acha
Health Physicist, TSO, ISU P. Farina
Radiation Safety Officer and Director, TSO, ISU F. Just
Chair, Reactor Safety Committee
INSPECTION PROCEDURES USED
Class II Research and Test Reactors IP 86740
Inspection of Transportation Activities
ITEMS OPENED, CLOSED, AND DISCUSSED
OPENED:
IFI 50-284/2012-201-01 Follow-up on the licensee's commitment of performing a new 10 CFR 50.59 review of the proposed digital reactor console.
IFI 50-284/2012-201-02 Follow-up on the licensee's completion of surveillances.
CLOSED:
IFI 50-284/2010-202-01 Follow-up on the licensee's commitment to update the Control Rod reactivity rod worth curves and adequately perform the surveillance.
IFI 50-284/2010-202-03 Follow-up on the licensee's commitment to update the table of values "Reactor Power Level as a Function of Channel No. 3 Detector Current" and adequately perform the power calibration surveillance.
IFI 50-284/2011-201-01 Follow-up on any issues resulting from the RA and RSO roles being performed by the same individual.
URI 50-284/2011-201-03 Follow-up to potential violation of 10 CFR 55.53(h) for failure to complete a requalification program for two licensed SROs.
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DISCUSSED
IFI 50-284/2010-202-02 Follow-up to the licensee's commitments made to revise and properly review and approve Operating Procedure #1.
IFI 50-284/2011-201-02 Follow-up on previous issues discussed from the non-routine inspection (Inspection Report No. 50-284/2010-201) and commitments made to revise and properly review and approve Operating Procedure #1.
IFI 50-284/2011-201-04 Follow-up to the licensee's commitment of having their qualification check-lists up-to-date; the checklists are used as an aid for their requalification program tracking and were instituted by the facility as a result of Non-Cited Violation NCV 50-284/2007-201-01 (NRC Report 50-284/2007-201).
LIST OF ACRONYMS USED
10 CFR Title 10 of the Code of Federal Regulations ADAMS Agencywide Documents Access and Management System AGN-201M Aerojet General Nucleonics-201M ALARA As Low As Reasonably Achievable FSAR Final Safety Analysis Report IFI Inspection Follow-up Item IP Inspection Procedure ISU Idaho State University NRC U.S. Nuclear Regulatory Commission NCV Non-cited Violation OP Operating Procedure OSL Optically Stimulated Thermoluminescent RA Reactor Administrator Rev.
Revision RPM Radiation Procedures Manual RO Reactor Operator RSP Radiation Safety Procedure RSC Reactor Safety Committee RSO Radiation Safety Officer SRO Senior Reactor Operator TLD Thermoluminescent Dosimeter TS Technical Specification TSO Technical Safety Office URI Unresolved Item