IR 05000170/2008201

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IR 05000170-08-201, on 01/07/2008 - 01/10/2008, for Armed Forces Radiobiology Research Institute
ML080240044
Person / Time
Site: Armed Forces Radiobiology Research Institute
Issue date: 01/28/2008
From: Johnny H. Eads
NRC/NRR/ADRO/DPR/RTRBB
To: Lillis-Hearne P K
US Dept of the Navy, National Naval Medical Ctr
Voth M, NRR/ADRA/DPR/PRT, 415-1210
References
IR-08-201
Download: ML080240044 (25)
v • d • e


Text

January 28, 2008

Colonel Patricia L illis-Hearne, Director Armed Forces Radiobiology Research Institute National Naval Medical Center 8901 Wisconsin Avenue Bethesda, MD 20889-5603

SUBJECT: NRC ROUTINE, ANNOUNCED INSPECTION REPORT NO. 50-170/2008-201

Dear Colonel Lillis-Hearne:

This letter refers to the inspection conducted on January 7-10, 2008, at your Research Reactor Facility. 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 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 with NRC requirements was identified.

However, one inspector follow-up item from a previous inspection was discussed but left open to be revisited in a future inspection. No response to this letter is required.

In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter and its enclosure 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.

Should you have any questions concerning this inspection, please contact Marcus H. Voth at 301-415-1210.

Sincerely,/RA/

Johnny Eads, Branch Chief Research and Test Reactors Branch B Division of Policy and Rulemaking Office of Nuclear Reactor Regulation

Docket No. 50-170 License No. R-84

Enclosure:

NRC Inspection Report No. 50-170/2008-201 cc w/enclosure: See next page Armed Forces Radiobiology Research Docket No. 50-170

cc:

Director, Maryland Office of Planning 301 West Preston Street Baltimore, MD 21201

Montgomery County Executive 101 Monroe Street, 2 nd Floor Rockville, MD 20850 Mr. Stephen I. Miller Reactor Facility Director Armed Force Radiobiology Research Institute 8901 Wisconsin Avenue Bethesda, MD 20889-5603

Environmental Program M anager III Radiological Health Program Air & Radiation Management Adm.

Maryland Dept of the Environment 1800 Washington Blvd.,Suite 750 Baltimore, MD 21230-1724

Rich McLean, Manager Nuclear Programs Maryland Department of Natural Resources Tawes B-3 Annapolis, MD 21401

Director Air & Radiation Management Adm.

Maryland Dept of the Environment 1800 Washington Blvd., Suite 710 Baltimore, MD 21230

Test, Research, and Training Reactor Newsletter University of Florida 202 Nuclear Sciences Center Gainesville, FL 32611

January 28, 2008 Colonel Patricia L illis-Hearne, Director Armed Forces Radiobiology Research Institute National Naval Medical Center 8901 Wisconsin Avenue Bethesda, MD 20889-5603

SUBJECT: NRC ROUTINE, ANNOUNCED INSPECTION REPORT NO. 50-170/2008-201

Dear Colonel Lillis-Hearne:

This letter refers to the inspection conducted on January 7-10, 2008, at your Research Reactor Facility. 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 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 with NRC requirements was identified.

However, one inspector follow-up item from a previous inspection was discussed but left open to be revisited in a future inspection. No response to this letter is required.

In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter and its enclosure 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.

Should you have any questions concerning this inspection, please contact Marcus H. Voth at 301-415-1210.

Sincerely,/RA/ Johnny Eads, Branch Chief Research and Test Reactors Branch B Division of Policy and Rulemaking Office of Nuclear Reactor Regulation Docket No. 50-170 License No. R-84

Enclosure:

NRC Inspection Report No. 50-170/2008-201 cc w/enclosure: See next page DISTRIBUTION

PUBLIC RTR r/f AAdams RidsNrrDrpPrtb RidsOgcMailCenter BDavis (cover letter only, O5-A4)

ADAMS ACCESSION NO.:ML080240044 *Concurrence via telephone TEMPLATE #: NRR-106 OFFICE PRT:RI PRT:LA PRT:BC NAME MVoth mv EBarnhill*

JEads jhe

DATE 1/24/08 1/24/08 1/28/08

OFFICIAL RECORD COPY U. S. NUCLEAR REGULATORY COMMISSION OFFICE OF NUCLEAR REACTOR REGULATION

Docket No: 50-170

License No: R-84

Report No: 50-170/2008-201

Licensee: Armed Forces Radiobiology Research Institute

Facility: AFRRI Reactor Facility

Location: Bethesda, MD

Dates: January 7-10, 2008

Inspector: Marcus H. Voth, Lead Patrick J. Isaac

Approved by: Johnny H. Eads, Branch Chief Research and Test Reactors Branch B Division of Policy and Rulemaking Office of Nuclear Reactor Regulation

EXECUTIVE SUMMARY

Armed Forces Radiobiology Research Institute AFRRI Research Reactor Facility NRC Inspection Report No. 50-170/2008-201

The primary focus of this routine, announced inspection was the onsite review of selected aspects of the Armed Forces Radiobiology Research Institute Class II research reactor facility safety programs including organization and staffing; operations logs and records; procedures; requalification training; surveillance and limiting conditions for operation; exper iments; design changes; committees, audits and reviews; emergency planning; maintenance logs and records; fuel handling logs and records; and follow-up on previously identified items since the last NRC inspection of these areas. 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 licensee's organization and staffing was in compliance with the requirements specified in the Technical Specifications.
  • The Inspector Follow-up Item regarding the Radiation Protection Officer was left open pending the next inspection of the health physics program.

Operations Logs and Records

Procedure s * The inspector found that appropriate procedures were in effect, being followed, and being updated as necessary.

Requalification Training

  • Operator requalification was up-to-date and was being performed as required by the AFRRI Reactor Operator Requalification Program.

Surveillance and Limiting Conditions for Operation

  • The system for tracking and completing surveillance checks and verifying compliance with limiting conditions for operation was well maintained.
  • Maintenance records, performance, and reviews satisfied Technical Specification and procedure requirements.

Experiments

  • Conduct and control of experiments met the requirements of regulations, the AFRRI Technical Specifications, and the applicable facility procedures.

2 Design Changes

  • No new changes, tests, or experiments subject to 10 CFR Part 50.59 reporting were performed since the previous inspection.

Committees, Audits and Reviews

  • The Reactor and Radiation Facilities Safety Subcommittee provided the oversight required by the Technical Specifications.

Emergency Planning

  • The emergency preparedness program was conducted in accordance with the Emergency Plan. * The emergency drill observed by the inspector demonstrated the licensee's effective implementation of the emergency program.

Maintenance Logs and Records

  • This topic was inspected and reported above as a subset of surveillance activities.

Fuel Handling Logs and Records

  • Fuel handling and inspection activities were completed and documented as required by Technical Specifications and facility procedures.

REPORT DETAILS

Summary of Facility Status

The Armed Forces Radiobiology Research Institute (AFRRI) one megawatt Training Research Isotope Production General Atomics (TRIGA) Mark II research reactor located on the campus of the National Naval Medical Center (NNMC) operated in support of the Institute's mission of research, experiments, education, reacto r operator traini ng and periodic equipment surveillance immediately prior to the inspection. During the inspection the reactor was maintained in a shutdown status as a precaution because of repair activities on the roof over the reactor bay.

1. Organization and Staffing a. Inspection Scope (Inspection Procedures (IP) 69001 and 92701)

The inspector reviewed the following regarding the licensee's organization and staffing to ensure that the requirements of Section 6.1, Organization, of the AFRRI Technical Specifications (TS), Amendment No. 24 to License No. R-84, dated September 18, 2001, were being met:

  • organizational structure
  • management responsibilities
  • staffing requirements for safe operation of the re search reactor facility
  • 2006 Annual Operating Report, submitted March 29, 2007
  • Reactor Logbook Number 129, November 2, 2006 to October 31, 2007
  • Reactor Logbook Number 130, November 2, 2007 to present
  • AFRRI Emergency Telephone Directory, November 2007

b. Observations and Findings In October of 2007 three per sons assigned to AFRRI on military rotations received NRC Senior Reactor Operator (SRO) licenses, bringing to five the number of licensed operators. The Reactor Supervisor and Reactor Facility Director who are civilian staff also hold SRO licenses. One additional civilian staff member was scheduled to take an SRO exam in January. The inspector and licensee discussed the consequences of simultaneous military rotations on staffing and also the depth of coverage for contingencies in senior reactor staff positions.

The inspector determined from the reactor console logbook that minimum staffing and on-call requirements were in compliance with TS Section 6.1.3.2, Operations.

Inspector Follow-up Item (IFI) 50-170/2007-201-01 was discussed in depth; "Define a chain of command from the Radiation Protection Officer (RPO) to the AFRRI Director (Licensee) consistent with Technical Specification 6.1." At issue during the previous inspection was a proposal by the AFRRI parent organization, the Uniformed Services University of the Health Sc iences (USUHS), t hat the RPO responsibilities defined in the AFRRI TS be delegated to the USUHS RPO. This would have eliminated the direct reporting of the AFRRI RPO to the AFRRI Director (the Licensee) required by TS Section 6.1.1, [Organization] Structure. Significant staffing changes had occurred since the previous inspection. First, a decision was made to create a civilian RP O position on the AFRRI staff; an interim RPO was appointed until the permanent RPO could be recruited.

Second, two key members of the RPO staff were replaced as a result of the untimely death of the person responsible for radiation protection training and re-training and the retirement of the person performing personnel dosimetry, facility radiation surveys and environmental monitoring. Third, an experienced health physics expert was assigned to oversee new personnel and the radiation protection program during the transition. The inspector left IFI 50-170/2007-201-01 open pending a thorough review of the overall health physics program effectiveness during the next inspection.

c. Conclusions The licensee's organization and staffing was in compliance with the requirements specified in the Technical Specifications. The Inspector Follow-up Item regarding the Radiation Protection Officer was left open pending the next inspection of the health physics program.

2. Operations Logs and Records a. Inspection Scope (IP 69001)

The inspector reviewed selected aspects of the following to verify compliance with TS Section 6.3 and applicable procedure requirements for operation:

  • staffing for reactor operations
  • AFRRI Malfunction Log, pages 113-114
  • Reactor Logbook Number 130, November 02, 2007 to present
  • Reactor Logbook Number 129, November 02, 2006 to October 31, 2007
  • AFRRI Operational Procedure 8, Reactor Operations, Rev. dated May 1, 1998
  • AFRRI Operational Procedure 8, TAB A, Logbook Entry Checklist, Rev. dated February 26, 2001
  • AFRRI Operational Procedure 8, TAB B, Daily Operational Startup Checklist, November 22, 2006
  • AFRRI Operational Procedure 8, TAB B1, Daily Safety Checklist, AFRRI Form 61b (R), November 22, 2006
  • AFRRI Operational Procedure 8, TAB D, K-Excess, January 16, 1992
  • AFRRI Operational Procedure 8, TAB E, Steady State Operations, November 24, 1997 * AFRRI Operational Procedure 8, TAB F1, Square Wave Operation, (Subcritical), April 29, 1998
  • AFRRI Operational Procedure 8, TAB F2, Square Wave Operation, (Critical), November 24, 1997
  • AFRRI Operational Procedure 8, TAB G1, Pulse Operation (Critical), March 16, 1998
  • AFRRI Operational Procedure 8, TAB G2 Pulse Operation (Subcritical), March 16, 1998 * AFRRI Operational Procedure 8, TAB H, Weekly Operational Instrument Checklist, AFRRI Form 66 (R), November 22, 2006
  • AFRRI Operational Procedure 8, TAB I, Daily Operational Shutdown Checklist, AFRRI Form 62 (R), November 22, 2006
  • AFRRI Operational Procedure 9, Reactor Room Safety, November 22, 2006 b. Observations and Findings The operating logs and records were well maintained and provided a clear indication of operational activities, changes in reactivity, and maintenance actions or malfunctions that had occurred. The logs and records indicated that shift staffing, including on-call personnel, was as required by TS 6.1.3.2. Logs and records also showed that operational conditions and parameters were consistent with license and TS requirements and that TS operational limits had not been exceeded. Information on the operational status of the facility was recorded in log books and on checklists as required by procedure. Scrams and other malfunctions were identified in the logs and records, reported, and their cause(s) resolved before the resumption of operations under the authorization of the Reactor Facility Director.

c. Conclusions The operations program was acceptable, well documented, and in compliance with Technical Specification Section 6.1 requirements.

3. Procedures

a. Inspection Scope (IP 69001)

The inspector reviewed the following to ensure that the requirements of TS Section 6.3, Operating Procedures, were being met concerning written procedures:

  • Procedures for the AFRRI Reactor Facility, two volumes
  • AFRRI Administrative Procedure A3, Facility Modifications, February 26, 2001
  • AFRRI Administrative Procedure A5, Evaluation and Reporting of Defects, March 4, 1994 * AFRRI Operational Procedure 0, Writing and Modifying Procedures, February 11, 1999 * AFRRI Operational Procedure 8, Tab B - Daily Operational Startup Checklist, November 22, 2006
  • AFRRI Operational Procedure 8, Tab B1 - Daily Safety Checklist, November 22, 2006
  • AFRRI Operational Procedure 8, Tab H - Weekly Operational Instrument Checklist, November 22, 2006
  • AFRRI Operational Procedure 8, Tab I - Daily Operational Shutdown Checklist, November 22, 2006 b. Observations and Findings The inspector reviewed the licensee's written procedures and revisions to procedures.

The Procedures Manual was organized to address the specific categories of procedures identified in TS Section 6.3, Procedures. The inspector reviewed a procedure addressing the reporting of defects as required by 10 CFR Part 21 and also a procedure for creating, controlling, and revising procedures.

Changes to procedures were infrequent but when necessary, found to be properly implemented. Specifically, the inspector reviewed procedure changes made necessary by an upgrade of instrumentation. A cover sheet on each procedure documented review by the Reactor Facility Direct or, the Reactor and Radiation Facility Safety Committee or Subcommittee (RRFSC or RRFSS), and each licensed reactor operator on the staff at the time the procedure modification was implemented.

c. Conclusions The inspector found that appropriate procedures were in effect, being followed, and being updated as necessary.

4. Requalification Training a. Inspection Scope (IP 69001)

To verify that the licensee was complying with the requirements of the operator requalification program, the inspectors reviewed selected aspects of:

  • Reactor Operator Requalification Program for the Armed Forces Radiobiology Research Institute TRIGA Reactor Facility, revised June 27, 2001
  • the effective dates of current operator licenses
  • operator training records maintained on ARequalification Program Checklist

@ forms in individual folders for each operator

  • operator physical examination records for the past two years
  • operator competence evaluation and written examination records
  • operator active duty status noted on AQuarterly SRO/RO Operating Requirements

@ forms located in the training folders

  • current requalification cycle graded written examination in individual folder for each operator * current requalification cycle operating test evaluation in individual folder for each operator b. Observations and Findings There were five NRC licensed SROs on staff at the facility and one per son in training. The Requalification Program was maintained up-to-date and SRO licenses were current.

A review of the logs and records showed that training was being conducted in accordance with the licensee

=s NRC-approved requalification and training program. Requalification program data such as attendance at training sessions and completion of examinations was documented as required. Records of quarterly reactor operations, reactivity manipulations, other operations activities, and Reactor Supervisor activities were being maintained. Records indicating the completion of the annual operations tests and supervisory observations were also maintained. Biennial written examinations were being completed and documented as required as well. The inspectors also noted that operators were receiving the required biennial medical examinations.

c. Conclusions Operator requalification was up-to-date and was being performed as required by the AFRRI Reactor Operator Requalification Program. 5. Surveillance and Limiting Conditions for Operation a. Inspection Scope (IP 69001)

The inspectors reviewed selected aspects of:

  • AFRRI Malfunction Log, pages 113-114
  • Reactor Logbook Number 130, November 02, 2007 to present
  • Reactor Logbook Number 129, November 02, 2006 to October 31, 2007
  • Annual Shutdown Maintenance Checklist conducted for 2006 and 2007
  • surveillance activities and equipment maintenance documented in the TRIGA Tracker System including Monthly Reports and Annual Maintenance Reports for

2006 and 2007

  • AFRRI Operational Procedure 8, Tab B, Daily Operational Startup Checklist, November 22, 2006
  • AFRRI Operational Procedure 8, Tab B1 Daily Safety Checklist, November 22, 2006
  • AFRRI Operational Procedure 8, Tab H, Weekly Operational Instrument Checklist, November 22, 2006 b. Observations and Findings (1) Maintenance Logs Routine and preventive maintenance were well controlled and documented in the TRIGA Tracking system through the Monthly TRIGA Tracker Report consistent with the TS and licensee procedures. Verifications and operational systems checks were performed to ensure system operability before return to service. Use of maintenance and malfunction logs satisfied procedural requirements. In June 2007, the Pulse Data Recorder failed to collect data in the subcritical pulse mode. The malfunction was noted in the operations log and also reported in the malfunction log. Pulsing operations were suspended until the problem was fixed and the recorder returned to service.

(2) Surveillance Activities

Daily, weekly, monthly, quarterly, semiannual, and other periodic checks, tests, and verifications for TS required Limiting Conditions for Operation (LCOs) were being

completed as required. All surveillance and LCO verifications reviewed were completed on schedule as required by TS 4.0, Surveillance Requirements, and in accordance with licensee procedures. A computer-based system, the TRIGA Tracker system, was used to track completion of the various required surveillance and LCO verifica tions. C hecklists for surveillance activities were completed and filed to document the date those activities were completed and by whom. These checklists and associated forms provided acceptable documentation of the results and proper control of reactor operational tests and surveillance. The Annual Shutdown Maintenance Checklist documented all of the annual TS surveillanc e requirements. c. Conclusions The system for tracking and completing surveillance checks and verifying compliance with limiting conditions for operation was well maintained. Maintenance records, performance, and reviews satisfied TS and procedure requirements.

6. Experiments a. Inspection Scope (IP 69001)

To verify compliance with the licensee's procedures, TS Sections 3.6, Limitations on Experiments, TS Section 6.4, Review and Approval of Experiments, and 10 CFR 50.59, the inspector reviewed selected aspects of:

  • Reactor Utilization Reques t Logbook, 1995 to present
  • Routine Reactor Authorization, No. 1 through 5, dated July 2000
  • 2006 Annual Operating Report, submitted March 29, 2007
  • Reactor Logbook Number 129, November 2, 2006 to October 31, 2007
  • Reactor Logbook Number 130, November 2, 2007 to present
  • AFRRI Operational Procedure 1 - Conduct of Experiments, March 4, 1996

b. Observations and Findings Six experiments consisting of multiple samples per experiment were performed during 2007. These were all performed under existing authorizations; no new authorizations were approved during the year. Written procedures existed for the conduct of experiments and for the review and approval process for new experiments.

c. Conclusions Conduct and control of experiments met the requirements of regulations, the AFRRI Technical Specifications, and the applicable facility procedures.

7. Design Changes a. Inspection Scope (IP 69001)

To verify compliance with the licensee's procedures, TS Section 6.2.4, Review Function, and 10 CFR 50.59, the inspector reviewed selected aspects of:

  • Minutes of the Reactor and Radiation Facilities Safety Subcommittee Meeting of June 26, 2007, with meeting handouts
  • Facility Modification Wor ksheet 1, 10 CFR 50.59 Analysis, Replacement of Area Radiation Monitor System, November 6, 2006
  • AFRRI Administrative Procedure A3, Facility Modifications, February 26, 2001
  • AFRRI Operational Procedure 8, Tab B - Daily Operational Startup Checklist, November 22, 2006
  • AFRRI Operational Procedure 8, Tab B1 - Daily Safety Checklist, November 22, 2006
  • AFRRI Operational Procedure 8, Tab H - Weekly Operational Instrument Checklist, November 22, 2006 * AFRRI Operational Procedure 8, Tab I - Daily Operational Shutdown Checklist, November 22, 2006 b. Observations and Findings

The licensee reported that since the previous inspection there were no changes made which constituted a change r eportable pur suant to 10 CFR Part 50.59. One facility change since the previous inspection, replacement of obsolete technology area radiation monitors with state-of-the-art devices, was evaluated per facility procedures and determined not to reach the threshold for 50.59 reporting. The inspector concurred with this finding and verified that minor procedural changes were made pursuant to findings of the design change review process.

c. Conclusions No new changes, tests, or experiments subject to 10 CFR Part 50.59 reporting were performed since the previous inspection.

8. Committees, Audits, and Reviews a. Inspection Scope (IP 69001)

The inspector reviewed the following to verify compliance with the requirements of TS Section 6.2, Review and Audit - The Reactor and Radiation Facility Safety Committee:

  • Minutes of the Reactor and Radiation Facilities Safety Subcommittee Meeting of June 26, 2007, with meeting handouts
  • Draft Minutes of the Reac tor and Radiation Facilities Safety Subcommittee Meeting of December 13, 2007, with meeting handouts
  • Facility Modification Wor ksheet 1, 10 CFR 50.59 Analysis, Replacement of Area Radiation Monitor System, November 6, 2006
  • AFRRI Emergency Drill Final Report, November 15, 2006
  • AFRRI Reactor Facility Audit Report, January 8-9, 2007, with cover letter from auditor W. Vernetson to RRFSS Chairman, C. Lissner, October 2, 2007
  • 2007 AFRRI Reactor Facility Audi t, S. Osborne, De cember 12, 2007 b. Observations and Findings The licensee's safety oversight was performed by its Radiation Safety Committee (RSC)

which was comprised of key managers who were members of two subcommittees, the Radioisotope and X-ray Safety Subcommittee (RXSS) and the Reactor and Radiation Facility Safety Subcommittee (RRFSS). TS Section 6.2, Review and Audit, defined a review and audit committee named the Reactor and Radiation Facility Safety Committee (RRFSC). The latter did not exist by that name. Instead, the RRFSS performed the functions ascribed to the RRFSC in TS Section 6.2, Review and Audit.

The inspector verified that the RRFSS composition, meeting quorums, and meeting frequency were all in accordance with TS Section 6.2, Review and Audit. Records of meeting proceedings were well-organized and included complete sets of materials distributed at meetings. The inspector verified that review functions prescribed in TS Section 6.2.4, Review Function, were all reviewed by the committee. The inspector also verified that the audit function required by TS Section 6.2.5, Audit Function, was conducted and that the audit reports were reviewed by the RRFSS.

c. Conclusions The Reactor and Radiation Facilities Safety Subcommittee provi ded the ov ersight required by the Technical Specifications.

9. Emergency Planning a. Inspection Scope (IP 69001)

The inspector reviewed the implementation of selected portions of the emergency preparedness program including:

  • AFRRI Emergency Drill conducted on January 17, 2008
  • AFRRI Emergency Drill Final Report, November 15, 2006
  • AFRRI and AFRRI Reactor Emergency Response Guidebook, Controlled Copy Number 55, April 1996
  • AFRRI Emergency Telephone Directory, November 2007
  • Decontamination of Personnel and Equipment, M. Hildebrand, no date
  • Training Files for Emergency Command Post and Emergency Response Team Personnel for 2007
  • DOD-AFRRI Inter-service Support Agreement, D. Hinkes, February 17, 2000 b. Observations and Findings The inspector reviewed the Emergency Plan of record, implementing procedures for the

plan, the report of the previous emergency drill, the status of recommended follow-up actions from the previous drill, reference documents for use in responding to emergency situations, the agreement document for services committed to AFRRI by the National Naval Medical Center (NMMC) in the event of an emergency, and training records for individuals assigned duties in the event of an emergency. Documents and documented actions were found to meet regulatory requirements and licensee commitments. While some documents were noted to be over ten years old and subject to being obsolescent, no specific examples of significance were identified. A licensee representative stated that a periodic review and update were under consideration.

The inspector verified that inventories of emergency supplies were maintained per procedure and that radiation monitoring devices designated for emergency use were available, functional, and within their calibration period. The inspector met with representatives of the NNMC Fire Department and the NNMC Police Department and

determined that their capabilities were in accordance with commitments.

On January 17, 2008, a week after completion of the inspection, the inspector

participated as an observer in the annual emergency drill and witnessed the effective integration of the above cited re sources in a successful drill.

c. Conclusions The emergency preparedness program was conducted in accordance with the Emergency Plan. The emergency drill observed by the inspector demonstrated the licensee's effective implementation of the emergency program.

10. Maintenance Logs and Records Since the licensee treated maintenance as a subset of the surveillance record keeping and tracking system the two areas were inspected together and reported as such in Section 5 of this inspection report.

11. Fuel Handling Logs and Records a. Inspection Scope (IP 69001)

The inspector reviewed the following to verify compliance with TS Section 6.3.f,

[Procedures] Reactor core loading and unloading:

  • AFRRI Fuel Element Record File
  • Fuel Inventory Sheet, October 1, 2007
  • AFRRI Operational Procedure 7, Reactor Core Loading and Unloading, May 15, 1991 * Reactor Logbook Number 129, November 2, 2006 to October 31, 2007
  • Reactor Logbook Number 130, November 2, 2007 to present
  • Control Room Reactor Fuel Inventory Map b. Observations and Find In the reactor logbook, the inspector noted reactor fuel element movements for the periodic surveillance measurements and inspection of the reactor fuel. For a random sample of five elements, the inspector verified that fuel moves and measurements were accurately recorded in each of the various records referenced above. A written and properly approved procedure was used in the conduct of the fuel moves.

c. Conclusions Fuel handling and inspection activities were completed and documented as required by Technical Specifications and facility procedures.

12. Exit Interview The inspection scope and results were summarized during an exit meeting on January 10, 2008, with members of licensee management. The inspector described the areas inspected and discussed significant inspection observations. No dissenting comments were received from the licensee.

PARTIAL LIST OF PERSONS CONTACTED

Licensee K. Baldwin, SFC, Senior Reactor Operator M. Belson, CPT, Senior Reactor Operator K. Connor, HM2, Radiation Health Technician P. Lillis-Hearne, COL, Director, AFRRI C. Lissner, Deputy Scientific Director J. Mercier, COL, Director, Military Medical Operations S. Miller, Reactor Facility Director M. Palmer, SFC, Environmental Health and Safety, AFRRI Division, Technical Supervisor T. Pellmar, Scientific Director H. Spence, Reactor Operations Supervisor W. D. Tomlinson, Senior Reactor Operator Trainee

Other Personnel

J. Caicedo, Operations Chief, National Naval Medical Center Police Department P. Fluerant, Chief, National Naval Medical Center Police Department W. Holzberger, Asst Chief, National Naval Medical Center Fire Department J. Pommerville, Asst VP for Environmental Health and Safety, USUHS L. Reagan, Command Investigator, National Naval Medical Center Police Department D. Zelonis, Inspector, National Naval Medical Center Fire Department

INSPECTION PROCEDURES USED

IP 69001 Class II Research and Test Reactors IP 92701 Follow-up

ITEMS OPENED, CLOSED, AND DISCUSSED

Opened None

Closed None

Discussed 50-170/2007-201-01 IFI Define a chain of command from the Radiation Protection Officer to the AFRRI Director (Licensee) consistent with Technical specification 6.1 (See discussion in Section 1 of this report.)

2 PARTIAL LIST OF ACRONYMS USED

ADAMS Agencywide Document Access and Management System AFRRI Armed Forces Radiobiology Research Institute FR Code of Federal Regulations IFI Inspector Follow-up Item IP Inspection Procedure LCO Limiting Condition for Operation NNMC National Naval Medical Center NRC Nuclear Regulatory Commission RPO Radiation Protection Officer RRFSC Reactor and Radiation Facility Safety Committee RRFSS Reactor and Radiation Facility Safety Subcommittee RSC Radiation Safety Committee SRO Senior Reactor Operator TS Technical Specifications TRIGA Training Research Isotope Production General Atomics USUHS Uniformed Services University of the Health Sciences

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