IR 05000252/1998202
| ML20155G672 | |
| Person / Time | |
|---|---|
| Site: | University of New Mexico |
| Issue date: | 10/30/1998 |
| From: | NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20155G669 | List: |
| References | |
| 50-252-98-202, NUDOCS 9811090146 | |
| Download: ML20155G672 (19) | |
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U. S. NUCLEAR REGULATORY COMMISSION l
i Docket No: 50 252 l j
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License No: R 102 Report No: 50-252/98 202 l
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l Licensee: University of New Mexico I
Facility: AGN-201M Reactor !
Location: Albuquerque, New Mexico ,
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Dates October 5 8,1998 -
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inspector: Craig Bassett, Senior Non-Power Reactor Inspector Approved by: Seymour H. Weiss, Director Non-Power Reactors and Decommissioning Project Directorate Division of Reactor Program Ma,agement Office of Nuclear Reactor Regulation
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9911090146 991030 C PDR ADOCK 05000252 :
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EXECUTIVE SUMMARY l
l This routine, announced inspection included onsite review of various aspects of the I licensee's programs concerning the conduct of operations and emergency preparedness as they relate to the licensee's five watt Class Il research reactor. The licensee's programs were directed toward the protection of public health and safety and were in compliance with WC requirements. No safety concerns or violations of regulatory requirements were identifie Conduct of Ooerations e Staffing, reporting, and record keeping met requirements specified in Technical Specifications (TS) Chapter * Review and oversight functions required by TS 6.4 were acceptably completed by the Reactor Safety Advisory Committee. No 10 CFR 50.59 changes had been implemented since the last NRC operations inspection, e The Requalification Program was being completed as required and records were being maintained. The operators were maintaining their licenses in an active statu Medical examinations were being completed as require e Facility procedures and document reviews satisfied TS 6.4 and 6.6 requirement e The licensee's reactor fuel was not required to be inspected annually but was generally handled once during the academic year for the " Approach io CMality" student experimen e The program for surveillance and LCO confirmations was being implemented in accordance with TS requirements, o Experiments were being conducted in accordance with properly reviewed and approved procedures and were satisfactorily documented in the operations lo Emeraencv Preoaredness e The licensee's Emergency Plan was found to be acceptable by the NRC in 1985 and no major revisions had beer, made. The licensee is currently revising the Plan and
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will submit the revision once it is reviewed and approved as require * The Emergency Plan and implementing Procedures were being revised and were
- adequate to implement the provisions of the Plan. An inspector Follow-up Item was
- identified because of apparent discrepancies between the AGN Operations Manual and the Emergency Plan concerning conditions requiring the evacuation of the Nuclear Engineering Laboratory.
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2 j e Emergency responders were know!edgeable of proper actions to take in case of an emergency but an Inspector Follow up Item was identified for failure to maintain !
first aid supplies in the storage cabinets as require I e The Letters of Agreement with offsite agencies maintained by the licensee were being updated. The letters indicated that support would be available in case of an emergency. Communications with these support agencies were being tested j periodically as require )
l l e Annual drills were being held as required. The licensee took credit for an actual j
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event in 1998 in lieu of a simulated dnll. A critique identifying lessons learned was I written following the event. This was determined to be acceptable.
I e Emergen::y preparedness training was being completed as part of the reactor l l operators' requalification program.
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[ Reoort Details l
Summarv of Plant Status Although the licensee's non-power reactor (NPR) was not operated during this inspection, a review of the applicable records indicated that the reactor continued to be operated at various power levels up to the maximum authorized level of five watts for physics experiments and to support researc Conduct of Operations
a. NPR Oraanization. Ooerations, and Maintenance Activities (Insoection Procedure flP1 69001)
1) Insoection Scoce .
l To verify staffing, reporting, and record keeping requirements specified in . '
Technical Specifications (TS) 6.1,6.9, and 6.10 were being met, the inspector reviewed:
e organization and staffing for the facility, e administrative controls, e the reactor console logs, and e the annual report ) ' Observations and Findinos The licensee's current operational organization structure and assignment of responsibilities were consistent with that specified in the TS 6.1.
l l A review of the reactor console logs showed that they were being maintained as
! required and problems, if any, were being documented. The annual reports summarized the required information and were issued at the frequency specified in the TS ) Conclusions Staffing, reporting, and record keeping met the requirements specified in TS Chapter b. NPR Review. Audit. and Design Change Functions (IP 69001)
1) Inscection Scoce in order to verify that the licensee had established and conducted reviews and audits as required and to determine whether modifications to the facility were consistent with 10 CFR 50.59 and the TS, the inspector reviewed:
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e Reactor Safety Advisory Committee meeting minutes,
- audits and reviews, and e engineering changes under 10 CFR 50.59, 2) Observations and Findinas Minutes of the Reactor Safety Advisory Committee (RSAC) showed that the committee met at the required frequency and that a quorum was present. The topics considered during the meetings were appropriate and as stipulated in TS 6.4. The RSAC and/or persons from other institutions conducted audits and reviews as required and the results were reviewed. Problems noted during audits were discussed and recommendations for improvement were made. The licensee implemented the improvement The inspector noted that a former member of the RSAC had recently retired and left the committee. The resume of the individual who replaced the former member was reviewed. The individual was well qualified to serve on the RSA Through review of applicable records and interviews with licensee personnel, the
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inspector determined that no engineering changes had been initiated or completed since the last NRC operations inspectio ) Conclusions Review and oversight functions required by TS 6.4 were acceptably completed by the RSAC. No 10 CFR 50.59 changes had been carried out since the last NRC operations inspectio c. NPR Ooerator Licenses. Reaualification. and Medical Activities (IP 69001)
, 1) Insoection Scoce To determine that operator requalification activities and training were conducted as required and that medical requirements were met, the inspector reviewed:
e active licenso status, e logs and records of reactivity manipulations and maintenance, o written examinations, e training records, and a medical examination records, 2) Observations and Findings The licensee currently has three qualified senior reactor operators (SROs) and one reactor operator (RO). It was noted that, although no reactor operator licenses had expired, one person would be required to renew his license next year. The licensee was aware of thi l
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4 3 l A review of the training records indicated that training had been conducted in l
the areas outlined in the licensee's " Operator and Senior Operator Requalification i Program for the University of New Mexico." Written and operational l examinations were also being administered as required. it was noted that the licensee was tracking and documenting hours to ensure that the operators met the requirements stipulated in 10 CFR 55.53(e) pertaining to maintaining operating licenses in an active status. In order to comply with the requirement for actively performing the functions of an operator or senior operator for a minimum of four hours per calendar quarter, the licensee included time spent in reactor console / reactivity manipulations, supervisory functions, and performing maintenance. This was consistent with the duties defined for SROs in TS 6.1.1 Operators were receiving the required medical examinations at the frequency ,
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3) Conclusions t
The Requalification Program was being completed as required and records were being maintained. The operators were maintaining their licenses in an active status. Medical examinations were being completed as require d. NPR Procedures (IP 69001)
1) Insoection Scone To determine whether facility procedures met TS requirements, the inspector reviewed:
- operating procedures, e administrative procedures, and a procedural reviews and update ) Observations and Findinas Operating procedures were acceptable for the facility and the current staffing level. Documents were being reviewed as requirei and updated as needed. It was noted that the Operations and Maintenance Procedures were last revised in January 1997. No operations were conducted during this inspection but adherence to procedure was determined from a review of logs and other record ) .Canclusions Facility procedures and document reviews satisfied TS 6.4 and requirement .. - ..- _- . - - -- .- . -- ..
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1) Insoection Scoce in order to verify adherence to fuel handling and inspection requirements, the inspector reviewed:
e fuel handling procedures, and e applicable logs and record ) Observations and Findinas
The inspector determined that, except for the well established " Approach to Criticality" project (experiment), reactor fuel had not been handled in the period since the last inspection. Acceptable radiological controls were established for the experiment and were implemented as require ). Conclusions The licensee's reactor fuel was not required to be inspected annually but was generally handled once during the academic year for the "Approcch to Criticality" student experiment, f. NPR Surveillance (IP 69001)
1) Insoection Scone To determine that surveillances and Limiting Conditions for Operations verifications were being completed as required by TS 4.0, the inspector reviewed:
e surveillance and maintenante procedures, e selected surveillance data and records, and e Limiting Conditions for Operation ) Observations and Findinas The inspector noted that selected daily and other periodic checks, tests, verifications, and/or calibrations for TS-required surveillances and Limiting Conditions for Operations (LCO) were completed as required. The surveillances and LCO verifications reviewed were completed on schedule as required and in l
accordance with licensee procedures. All the recorded results were within the
! TS and procedural prescribed parameters. The records and logs reviewed were
! accurate, complete, and being maintained as required.
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3) . Conclusions The program for surveillance and LCO confirmations was being carried out in accordance with T3 requirements, g. NPR Exoeriments (IP 69001)
1) Insoection Scone ~ ,
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In order to' verify that experiments were being conducted within approved
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guideli.nes, the inspector reviewed:
e experiment review and approval by the RSAC, e potential hazards identification, and e control of irradiated item ]
I 2) Observations and Findinas The ipspector noted that all the experiments conducted were well-established l procedures that had been in place for many years. No new experiments had been' initiated, reviewed, or approved since the last inspection. The experiments were conducted under the cognizance of the Chief Reactor Supervisor as required. The results of the experiments were documented in the reactor operations log boo ) faQrlusions Experiments were being conducted in accordance with properly reviewed and approved procedures and were satisfactorily documented in the operations lo . ' Emergency Preparedness a. - Changes to the Emergency Plan (IP 69001)
1) laspection Secoe To determine compliance with the requirements of 10 CFR 50.54(q) and the licensee's Emergency Plan, the inspector reviewed:
e the Emergency Plan and implementing Procedures, e RSAC meeting minutes,
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2) Observations and Findinga The licensee submitted a revised Emergency Plan (E-Plan) to the NRC on March 11,1985. The NRC reviewed the changes and found that they were acceptable to implement the requirements of 10 CFR Part 50, Appendix E. No substantial changes have been made since then. The inspector did note that the E-Plan was last reviewed by the RSAC on April 28,1998, and that some changes and improvements had been suggested. Therefore, the plan is currently being revised and will be submitted to the NRC upon completion of the revision and upon approval by the RSAC and the Reactor Administrato ) Conclusions l The licensee's Emergency Plan was found to be acceptable by the NRC in 1985 and no major revisions had been made. The licensee is currently revising the Plan and will submit the revision once it is reviewed and approved as require b. Emeraencv Plan and lmolementino Procedures (IP 69001)
, 1) Insoection Scooe l
l In order to verify the adequacy of the licensee's Emergency Plan and j Implementing Procedures, the inspector reviewed: ,
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- the Emergency Plan, l e RSAC meeting minutes, and e recent suggestions for revisions and update ) Observations and Findinas As noted above, the RSAC had recently reviewed the E Plan and had made suggestions for improvement. During this inspection and review of the E-Plan, the inspector noted that the implementing Procedures were basically included in the Plan itself. The procedures appeared to be acceptable to implement the provisions stipulated in the E-Plan.
l During the review of the E-Plan, the inspector noted that an evacuation of the l
Nuclear Engineering (NE) Laboratory is called for under certain conditions. The AGN Operations Manual also specified certain conditions requiring evacuation of the NE Lab but those conditions did not correspond to the ones listed in the E-Pla The licensee was informed that the apparent discrepancies between the AGN Operations Manual and the E Plan concerning the conditions requiring evacuation of the NE Lab would be considered by the NRC as an inspector Follow-up item (IFI) and the resolution of the apparent problem would be verified during a future inspection (IFl 50 252/98 202-01).
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3) Conclusions
The Emergency Plan and implementing Procedures were being revised and were !
l adequate to implement the provisions of the Plan. An Inspector Follow-up Item )
l was identified because of apparent discrepancies between the AGN Operations- l l Manual and the Emergency Plan conceming conditions requiring the evacuation l
of the Nuclear Engineering Laboratory.
l l c. Emeroencv Preoaredness Proaram imolementation (IP 69001) l l 'l 1) Insoection Scopa l To determine the adequacy of the licensee's Emergency Preparedness Program implementation, the inspector reviewed:
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- equipment, l e instrumentation, j e supplies on hand, and e emergency response personnel trainin ) Observations and Findinas The facilities and equipment set aside for emergency response were generally being maintained as required. However, the inspector noted that not all the supplies listed in E-Plan were in the cabinets or storage locations that had been set aside for this purpose. Specifically, no first aid supplies were located in the l storage cabinets, no calibrated portable survey instrument which could detect alpha radiation was present, and no self-reading personnel dosimeters were available for use. The Inspector interviewed the acting Radiation Protection l Officer for the university and noted that, in response to an emergency, the campus health physics personnel would bring two trunks / suit cases with the The trunks contained various survey instruments, including one that would detect alpha radiation. The trunks also contained self-reading personnel dosimeters that could be used by facility personnel. However, no first aid supplies were maintained in the health physics emergency response trunk The licensee was informed that the lack of the required first aid supplies would be noted by the NRC as an IFl and the acquisition of the supplies would be verified during a future inspection (IFl 50 252/98 202-02).
Through records review and interviews with licensee personnel, emergency responders were determined to be knowledgeable of the proper actions to take
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l 3) Conclusions l
Emergency responders were knowledgeable of proper actions to take in case of
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an emergency but an Inspector Follow-up Item was identified for failure to maintain first aid supplies in the storage cabinets as require . Offsite Sunoort (IP 69001)
1) ' Insoection Scone To verify the adequacy of the offsite support that would be provided to the licensee in case of an emergency, the inspector reviewed:
e the Emergency Plan, o Letters of Agreement, and
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e communications capabilitie )' Observations and Findinas Although Letters of Agreement were on file indicating that various local agencies were available to respond in case of an emergency, it was noted that the letters were dated 1995. The licensee was in the process of obtaining updated letters from the various agencies during the week of the Inspection. The inspector noted that an agreement had been established with the University of New Mexico (UNM) Hospital in case a contaminated injured person required medical treatmen Through a review of the applicable records, the inspector determined that communications with support agencies had been tested on a periodic basis as
! required. However, upon checking with the UNM Police, the inspector noted-that the dispatcher for the police did not have a current Notification Roster for persons to callin case of an emergency involving the research reactor. The dispatcher made a copy of the current roster that the inspector had and placed
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the current copy in the dispatcher's log book for future reference. The licensee l was informed about this problem. Licensee personnelindicated that steps would l
be taken to ensure that a current roster is forwarded to the UNM Police whenever it is update ) Conclusions The Letters of Agreement with offsite agencies maintained by the licensee were being updated. The letters indicated that support would.be available in case of l an emergency. Communications with these support agencies were being tested periodically as required.
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e. Emeroency Preoaredness Exercises and Drills (IP 69001)
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1) Insoection Scagg To determine that the licensee was conducting the exercises and drills as specified in the Emergency Plan, the inspector reviewed:
e the critiques of drill performance by emergency responders, and a the documentation of recent drill ) Observations and Findinas The inspector noted that drills had baen conducted annually as required by the Emergency Plan. Critiquer were generally written following the drills to discuss the positive and negative aspects of the exercise and to outline possible solutions to any problems idtotified. It was noted that no drill was held in 1998 but credit for completion c the annual drill was taken for an actual event. The event involved a water leak in the Cobalt-60 Cell located in the same Nuclear Engineering (NE) Laboratory as the research reactor. Because of the event, the licensee exercised various portions of the Emergency Plan even though the reactor facility was not involved. The licensee wrote a critique of the event and of the lessons learned. This was determined to be acceptable by the inspecto ) Conclusions Annual drills were being held as required. The licensee took credit for an actual event in 1998 in lieu of a simulated drill. A critique identifying lessons learned was written following the event. This was determined to be acceptable.
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f. Emeraencv Preoaredness Trainina (lP 69001)
1) Insoection Scoce in order to verify the adequacy of the licensee's emergency training, the inspector reviewed:
e the Emergency Plan, and e training records, 2) Observations and Findinas in the area of Emergency Preparedness and Response, training was reportedly being completed as part of the reactor operators' requalification program. A review of the requalificatien program indicated that the training was completed as require , -
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3) Conclusions Emergency preparedness training was being completed as part of the reactor operators' requalification progra l 3. Follow-up on Previously identified Violations a. Inspection Scope The inspector followed up on three violations that had been identified during a previous inspection and documented in inspection Report No. 50-252/97-201. The inspector raviewed the licensee's response, evaluation, and corrective actions, as applicable, to the problems or issues note b. Observations and Findings 1) VIO 50-252/97-201-01 (Closed): Failure to Monitor Operator Proficienc The inspector verified that the licensee had established a program for tracking operator requalification actions. Forms used to record this data had been changed to document the hours spent by each individual as a reactor operator, as a supervisor and in performing maintenance. Records reflected that all operators have maintained an active license since the problem was identifie ) VIO 50-252/97-201-02 (Closed): Failure to Measure Rod Scram Time The inspector verified that the licensee had taken corrective actions. The licensee developed a set-up that could be used to measure the rod scram time An infrared emitter / receiver connected to e digital acquisition was used, along with a computer, to measure the scram times. The results indicated that the scram times were well within the limit specified in the T ) VIO 50-252/97-201-03 (Closed): Failure to Control Access to the Nuclear Engineering Laborator The inspector verified that the licensee changed the combination to the lock on the NE Lab door every semester. Then, people not formerly on the access lir .
are required to sign the correct form and are given the new code to allow them to open the locked door to the NE Lab. People no longer needing access to the facility are dropped from the access lis c. Conclusions Three violations identified during previous a NRC inspection wer.. closed duririg this
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4. Exit interview The inspection scope and results were summarized on October 9,1998, with licensee
- representatives. 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 inspectio !
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PARTIAL LIST OF PERSONS CONTACTED
l Licensee -
R. Becker, Interim Radiation Protection Officer (RPO) l R. Busch, Chief Reactor Supervisor J. Cecchi, Chair, Chemical and Nuclear Engineering Department K. Carpenter, Reactor Supervisor G. Cooper, Reactor Supervisor N. Roderick, Reactor Administrator INSPECTION PROCEDURES USED IP 69001: Class ll Non-Power Reactors ITEMS OPENED, CLOSED, AND DISCUSSED Ooened 50-252/98-202-01. IFl Follow-up on the resolution of the apparent discrepancies between the AGN Operations Manual and the E-Plan I concerning the conditions requiring evacuation of the NE La l 50-252/98 202-02 IFl Follow-up on the lack of the required first aid supplies in the NE l
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Lab and the acquisition of the supplie l Closed 50-252/97-201 01 VIO Failure to Monitor Operator Proficienc :
50-252/97-201 02 VIO Failure to Measure Rod Scram Time /97-201-03 VIO Failure to Control Access to the NE Laborator LIST OF ACRONYMS USED l
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AGN Aerojet General Nuclear l CFR Code of Federal Regulations l IFl Inspector Foiiow-up Item j lP Inspection Procedure '
LCO Limiting Condition for Operations NE Nuclear Engineering NPR Non-Power Reactor 4 NRC Nuclear Regulatory Commission l
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I- RO Reactor operator RPO . Radiation Protection Officer RSAC- Reactor Safety Advisory Committee l SRO Senior reactor operator L
TS Technical Specificationt '
.TRT Test, Research, and Training Reactor VIO Violation .,
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INSPECTION FOLLOW-UP SYSTEM (IFS)
SPEED CLOSEOUT / UPDATE FORM 5 0 -
0 2 5 2 RESPONSIBLE INDIVIDUAL: - C. Bassett DOCKET _ REVIEWED BY: S. Weiss NUMBERS
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FACILITY: University of New Mexico ,
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CLOSEOUT /
AFFECTED UNITS ITEM INSPECTION ITEM UPDATE INSPECTION ITEM (1/2/3) TYPE l NUMBER REPORT N END DATE STATUS ,
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UNITS ITEM UPDATE INSPECTION ITEM (1/2/3) TYPE EA NUMBER NOV ID NUMBER REPORT N END DATE STATUS VIO - -
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