IR 05000607/1998201
| ML20236V431 | |
| Person / Time | |
|---|---|
| Site: | University of California-Davis |
| Issue date: | 07/30/1998 |
| From: | NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20236V420 | List: |
| References | |
| 50-607-98-201, NUDOCS 9808030182 | |
| Download: ML20236V431 (17) | |
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U. S. NUCLEAR REGULATORY COMMISSION OFFICE OF NUCLEAR REACTOR REGULATION l
Docket No: 50-607
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Report No: 50- 607/98-201
1 Licensee: United States Air Force j i
l Facility: McClellan Nuclear Radiation Center Location: McClellan Air Force Base Sacramento, California
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Dates: June 15-19,1998 inspector: Stephen W. Holmes, Reactor inspector Approved by: Seymour H. Weiss, Director Non-Power Reactors and Decommissioning Project Directorate Division of Reactor Program Management Office of Nuclear Reactor Regulation-i'
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I-l 9808030182 980730 F PDR ADOCK 05000607 G PDR %
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EXECUTIVE SUMMARY This evaluation consisted of the review of selected conditions and records, observation of the physical plant, ongoing operations, surveys, and surveillance, and related discussions with facility personnel. Additionally, the reactor critical operations, silicon ingot irradiations, several surveillance, multiple operator shift changes and routine health physics surveys were observed. The evaluation was conducted following the guidance of the Nuclear Regulatory Commission (NRC) Inspection Manual and proposed facility license, Technical Specifications (TS), plans and program The reactor was being maintained and operated as required by the applicable requirement Control and supervision of the large staff and the reactor's 24-hour operations was i
comprehensive. The computerized preventive maintenance system tracked reactor
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surveillance, and scheduled maintenance and non-routine maintenance / repairs in a timely,
- accurate manner. Reactor design changes were complete and technically sound with extensive Nuclear Safety Committee involvement.
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Report Details Summary of Plant Statut
[ Reactor operations were continuing with three shifts 24-hours a day. Activities included l silicon doping irradiations, operator training, and proposed Technical Specification (TS)
' inspections and surveillance. No safety concerns were note Operations 01 Conduct of Operations 01.1 Reactor Staffino Scoce (Inscection Procedure 39745)
The reactor staff qualifications, operations logs and records, and selected events were reviewed. Also, shift turnovers for all three shifts were observe Observations and Findinos Operators consisted of the Reactor Director (RD), the Operations Supervisor (OS), and in excess of fifteen Senior Reactor Operators (SRO) and Reactor Operators (RO). The reactor staff satisfied the training and experience required by the TS. Operation logs and records confirmed that shift staffing met the duty and on-call personnel requirements, Conclusions The research reactor operations staffing satisfied TS requirement .2 Control and Performance of Experiments Scoce (Insoection Procedure 69005J Approved reactor experiments, and associated reactor logs, documentation, data, and Nuclear Safety Committee (NSC) minutes were reviewed. Two experimental-related activities were observed. Discussions with dacility staff were also conducted on experimental control, Observations and Findinos l
Each experiment had been pre-screened / reviewed and approved by the l Experimental Review Board or was referred to the NSC as required. Review of i the experiment procedures and reactor 109 books, interviews with staff, and observation verified that experiments were constrained as required by the TS y and experiment authorization. The experiments were also installed, performed, l and removed as outlined in the experiment authorization and procedures. The
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NSC review of experiments ensured evaluation for unreviewed safety questions or TS change Observation of a silicon ingot " flip" and the central facility reactivity worth measurement experiment confirmed that experiments conformed to TS and pertinent requirements. There were safety constraints for the identified hazard Reactivity assessments were performed when required for handling of experiment Conclusions Control and performance of experiments met TS and applicabic requirement .3 Reactor Ooetalions Scope (Insoection Procedure 39745)
Reactor operations logs, fuel logs, and periodic checkout, start-up and shutdown checklists were reviewed. Start-up, steady state power operation, several surveillance, and a shutdown were observe Observations and Findings k Reactor cperations were carried out following written procedures and T I information on operational status was recorded in log books and checklists as required by procedures and TS. Use of maintenance and repair logs satisfied pertinent requirements. Significant problems and events noted in the operations log were reported and quickly resolved as required by TS and administrative procedures, _ Conclusions Operational activities were consistent with applicable requirement .4 Fuel Handlina Scope (InsoectionProcedure 607451 Reactor operations and fuel logs, and periodic checkout, start-up and shutdown checklists were reviewed. The post refueling rod worth measurements, power calibration, and reactor startup checks were observe Observations and Findinos
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Procedures for refueling, fuel shuffling, and TS required inspections / surveillance were extensive and detailed, ensuring controlled operations. Fuel movement, inspection, log keeping, and reccrding followed the facility's procedures. Data recorded for fuel movement was clear and cross referenced in ,oel and I
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operations logs. Radiological controls and pncedures conformed to health physics (HP) ALARA principle Observation of the post refueling rod worth measurements, power calibration and reactor st.srtup checks confirmed that TS limits and facility procedural requirements were met before normal operations were resumed after fuel movement, Conclusions Fuel handling activities and documentation were as required by TS and facility procedures. No safety concerns were identifie O2 Operational Status of Facilities and Equipment Scone finsoection Procedure 39745)
l The evaluation observed reactor equipment and the physical facilit ! k Observations and Frdinos )
Equipment was access ble with no extraneous clutter. All required equipment and facilities observed vtere operationa Conclusions Reactor and support facilities were operational as require Operations Procedures and Documentation 1 Scoce (Insoection Procedure 42745) I I
Operating procedures and updates, reactor operating records and logs, NSC l'
minutes were reviewed. Observations included the use of precedures during operation Observations and Findinas Written procedures required by the TS were available and used by the facility staff. Adherence to the procedures was acceptable. Procedures were routinely updated as needed. The reactor facility procedures had been reviewed and approved by the NSC as required by T Records of power level, operating periods, unusual events, calibration and maintenance procedures, installed experiments, and start-up and snutdown checks were being kept. The facility'.e loge sind records were clear, concise, and legible. The annual reactor operating reports, logs, and records acceptably L-_--__--___--------------_
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documented reactor operations activities. Reactor operations and testing were documented as required by the TS.
l Scrams were identified in the logs and records, and were reported and resolved as required before the resumption of operations under the authorization of a l SR , Conclusions Facility operational procedures satisfied TS requirements. Reactor operating records and logs were being maintained as required by TS. Significant problems l
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and events identified in the logs and records were reported and resolved as require Operator Training and Qualification Program Scoce (Insoection Procedure 690031 The requalification program records, training records, SRO/RO operational hours were reviewe QhatrXations and Findinas All operators and senior operators were participating in the ongoing training as required by the proposed requalification plan. Lectures were conducted and training given for abnormal and emergency procedures as required. The lecture
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outline for the reactor operator requalification program included appropriate j subject material and a comprehensive written examination. Training records
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contained the documentation required by the requalification program. Biennial medicel exams had been completed as require Operator hours were tracked to ensure that performance requirements were met.
! Checklists were used for tracking requalification requirements and ensuring that the plan elements were accomplished.
! Conclusions l The reactor operator requalification training program was being conducted and documented following the requalification plan requirements. Reactor operator requalification training records were being acceptably maintained. TS requirements were met.
l 06 Organization and Administration Scooe (Insoection Procedure 39745)
The organization, staffing and administrative controls were reviewe .
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5 Observations and Findinas As an Air Force facility, the reactor licensee is the Commanding General, McClellan Air Force Base. Direct control is delegated to the Facility Director who reports back to the Commander for all nuclear safety and licensing issue The Commander is advised by the NS Conclusions Organizational and administrative controls were consistent with TS and other applicable requirements and commitment Quality Assurance in Operations Scoce (Insoection Procedure 40745)
The NSC minutes, annual reviews, audits, and reviews of changes, tests and experiments were reviewed. The June 17,1998, NSC meeting was observe Observations and Findinas NSC membership satisfied TS requirements and the Committee's procedural rules. The NSC had meetings as required. Review of the minutes showed that the NSC provided guidance, direction, safety oversight, and ensured suitable use of the reactor. The committee's reviews of the console upgrade, the silicon flipping tool and cans, central facility modification and reactivity worth experiment approval were comprehensive and demonstrated that the NSC was actively performing its dutie Required audits of reactor facility activities and reviews of procedures, equipment changes, proposed tests or experiments, had been performed and documente )
l Conclusions The NSC meeting frequency satisfied TS requirements. Audits were conducted 1 as required. The NSC carried out its safety duties as obligated by pertinent requirements, TS, and administrative criteria.
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11. Maintenance M1 Conduct of Maintenance M1.1 Surveillance and Limitina Conditions for Ooeration Scoce (Insoection Procedure 31745)
Selected surveillance recoras, data sheets and records of tests, procedures, reactor logs, checklists, and periodic reports were reviewed. Reactor operations and several surveillance were observe Observations and Findinas Daily and other periodic checks, tests, and verifications for TS required limiting conditions for operations (LCO) were completed as required. Surveillance and LCO verifications were completed on schedule as required by TS and applicable procedures. All were within prescribed TS and procedure parameters and in close agreement with the previous surveillance result The computerized preventive maintenance system (PMS) was used to track surveillance, checks, and inspections. This included the date last performed, date presently completed, information on where documented and by whom, overdue status, trends, full system historical records, etc. This provided clear and concise control of the reactor operational tests and surveillance. Use at the facility was comprehensive and timel Conclusions The facility's program for surveillance, LCO confirmations, and inspections satisfied TS requirements. The use of the in-depth PMS ensured that surveillance activities were completed in a most timely manner and provided extensive information of equipment condition and status for use by the facilit M2 Maintenance and Material Condition of Facilities and Equipment Scoce (Insoection Procedure 39745)
The maintenance and reactor logs, NSC rninutes, and repair records were reviewed. Facility and equipment were observed during surveys, operations, and accompanied tours, Observations and Findig'Is
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Routine / preventative maintenance was controlled and documented in the PMS and/or operations log. Unscheduled maintenance or repairs were reviewed to decide if they required a safety review evaluation (e.g.,10 CFR 50.59).
Verifications and operational systems checks were performed to ensure system
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operability before return to service. Trends were identified and problems resolved as required, Conclusions Maintenance logs, records, performance, and reviews satisfied TS and procedure requirement j M8 Miscellaneous Maintenance issues j 1 Scooe (Insoection Procedure) {
The records pertaining to the year 2000 (Y2K) concerns were reviewe Observations and Findinas The current console upgrade included Y2K compliance in its specifications. The facility was covered under the Air Force Y2K program. The staff stated that Y2K concerns were being addressed to ensure facility would not be adversely 1 impacte l ( Conclusions Y2K concerns were being addresse Ill. Enaineerina E1 Conduct of Engineering, Design Changes ,
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The procedures, logs, records, and NSC files were reviewed. The change l packages for the console upgrade, silicon flipping tool and cans, central facility
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modification, and a number of completed changes were reviewed. The proposed FSAR, and TS and basis were also reviewe b. : Observations and Findinas Changes were rigorously controlled requiring a facility staff review, a committee l review, and were recorded and stored in individual change binders. Questions
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from the committee and replies from the reactor and HP staffs were documented and incorporated into the modification package The packages for the console upgrade, silicon flipping tool and cans, central facility modification, and a number of other projects were reviewed. The ,
evaluations were far-reaching with supporting documentation and informatio !
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NSC involvement was also comprehensive. Post installation verification testing of the systems was thorough. Procedure and drawing changes were included and were consistent with the observation Conclusions Design changes were reviewed, approved, carried out, tested, and controlled as required by TS, procedures, and pertinent requirement IV. Plant Suonort R1 Radiological Protection and Chemistry Controls R1.1 Radiation Protection Postinas Scoce (Insoection Procedure 83743)
Radiological signs and postings were observed during accompanied tours and routine radiation surveys were reviewe Observations and Findinos Postings were acceptable for the hazards involve Conclusions Radiological postings satisfied applicable requirement R1.2 Gaseous and Liauid Effluent Monitorina and Release Scoce (Insoection Procedure 69004) l Annual reports, release records, counting and analysis results were reviewe ,
) Observations and Findings I Gaseous releases were calculated from integrated power using the CAP 88-PC j Code authorized in the facility FSAR. Liquid was minimal and was analyzed prior to disposal to ensure limits were met. Releases were acceptably documented and well within the annual dose constraint of 10 CFR 20.1101(d) and the Appendix B concentration limits.
! Conclusions Gaseous and liquid effluent monitoring and releases satisfied applicable requirements.
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R1.3 Radiation Protection Survevs Scoce (Insoection Procedure 83743)
Procedures and survey records were reviewed, and routine health physics surveys were observe Observations and Findinas Monthly and other periodic contamination and radiation surveys including pool water analyses were done by HP staffs as required by TS and procedure Results were evaluated and corrective actions taken and documented when readings /results exceeded set action level Survey results verified that contamination in the facility was infrequent and both identified contamination and radiation levels were well below NRC and facility limit HP surveys required for specific reactor operations such as exposure door openings, silicon ingot handling, etc. were performed as required and documented as neede Conclusions Surveys were performed and documented as required. TS and pertinent requirements were me R1.4 Personnel Dosimetrv Scoce (Insoection Procedure 83743)
Dosimetry records and procedures were reviewe Observations and Findinas The facility used Brook AFB, a National Voluntary Laboratory Accreditation Program-accredited program to process personnel thermoluminescent dosimetr An examination of records for the past year showed that all exposures were within NRC limits. Records were reviewed by the RSO. ALARA and declared pregnancy programs were in effec Conclusions f
Doses were in conformance with facility and 10 CFR Part 20 limits. The )
dosimetry program was conducted in accordance with 10 CFR 20.1501, j 10 CFR 20.1502, and facility procedure j
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R2 Status of Radiation Protection and Control (RP&C) Facilities and Equipment Scone (Insoection Procedure 83743)
The inventory, calibration, and periodic checks of portable radiation survey and laboratory instruments were reviewed, Observations and Findinas Calibrated instruments were available. Instruments used to perform radiation surveys were calibrated in-house and through the Air Force system with radioactive sources traceable to national standards. Calibration frequencies and procedures followed manufactures or Air Force standards and satisfied TS requirement The calibration of the GeLi multi-channel analyzer, liquid scintillation and gas flow proportional counters followed the manufacturers' recommendations and used calibration sources in the same geometry as the actual samples analyze Allinstruments checked were in calibration. Calibration records were in orde l Conclusions l I
RP&C equipment was being maintained according to industry and equipment I manufacturer standards. Calibrations satisfied TS requirement R3 RP&C Procedures and Documentation Scoce (Insoection Procedure 83743)
The Radiation Protection Program (RPP) documentation and various HP procedures were reviewe Observations and Findinas HP procedures were available for those tasks and items required by the TS, applicable requirements and facility directives. Changes were reviewed and approved as required. Coordination between reactor and HP staffs on procedures affecting each other was acceptabl The RPP was formally documented and had been audited by the NSC as required.
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The RPP satisfied the requirements of 10 CFR 20.1101. Oversight and review were provided by the NSC and the reactor and HP staffs as required by TS and facility procedures. HP procedures met TS.
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R RP&C Organization and Administration Scone (Insoection Procedure 83743)
The RPP documentation was reviewe Observations and Findinas The Reactor Safety Health Physic Supervisor is responsible for the RPP to include procedum approval, development and implementation of the program, ALARA reviews and technical oversight Day to day s@eduling is done by O Coordination of HP activities between the HP and reactor staffs was acceptabl Conclusion HP staffing and RPP documentation met TS, pertinent requirements, and facility j commitment {
R8 Radioactive Material Transfer / Disposal Scoce (Inst.ection Procedure 86740)
The transfer documentation, and shipping and disposal records were reviewe I
- Observations and Findinas Production o, radioactive waste at the facility was minimal. All transfers were recorded on the applicable forms. Transfer documentation was kept on file as require t Material transferred to other authorized persons was documented, and was in accordance with appropriate requirement Conclusions Radioactive material was transferred and disposed of in accordance with facility procedures, TS, and 10 CFR 20 requirement I P1 Conduct of Emergency Preparedness Activities and Staff Training Scone (Insoection Procedure 82745)
The emegency plan (EP) procedures, and training and drill records for the reactor l were reviewe l l
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12 Observations and FindMi The facility drills were incorporated into the McClellan Air Force Base-wide system and were canducted periodically as required. The exercises were conducted according to, and fulfilled, the requirements stipulated in the EP. Key croergency response personnel demonstrated that they could respond to emergencies as required. Offsite response by security, law enforcement, and other responders were acceptable for the scenario involved, involvement of offsite personnel was comprehensive and well coordinated, items ideritified by individual critiques were addressed, evaluated, and then incorporated when appropriat Training records verified that acceptable training had been provided to in-house staf Conclusions The EP was effectively carried out as required. EP drills and training were acceptably being conducte P2 Status of EP Facilities, Equipment, and Resources Scoco (Insoection Prncedure 82745) I The inventory records were reviewed, and EP facilities, equipment and supplies were compared to program requirement Observations and Findina_ s Equipment and supplies were as required by the EP and inventory record Support facilities and commta.ications were also as spw;cified by FP requirement Conclusions EP facilities, equipment, and resources satisfied the plan requirement P3 EP Procedures and. Documentation Scone (Insoection Procedure 82745)
EP documents and implementing procedures were reviewed.
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b, Observations and Findinas The procedures were current, approved and were readily availablegfor use by response personnel. They acceptably addressed classification, notification, and protective actions required during an emergency to protect the health and safety I
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of the public. Implementing procedures were consistent with the EP requirements. Emergency phone list and on-calllists were also readily available I and up-to-dat Conclusions EP procedures and documentation were as required by EP and pertinent requirement S1 Conduct of Security and Safeguards Activities Scone (Insoection Procedure 81401)
The security plan, security logs, reports, and security related response documents were reviewed. The facility was observe {
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l The reactor building was secured with only those persons authorized by the plan having access to the facility. Base police provided security as required by the plan. In accordance with applicable requirements, security checks were performed and tracked. Corrective actions were taken when require Test / verification of the security systems was performed as require Conclusions Conduct of security and safeguard activities satisfied the pla S2 Status of Security Facilities, Equipment, and, Procedure Supoe (Insoection Procedure 81404)
The security plan, security logs and reports were reviewed. Security related equipment and facilities were observed, Obse vations and Fir.dinas The safeguards system was as described in the security plan. The system provided detection and assessment of unauthorized access. The system also provided for detection of removal of special nuclear material from the facilit The alarms, devices, and procedures al lowed the base police to detect and respond to unauthorized activities. Response rosters were current and posted as required.
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Security facilities, equipment, and procedures satisfied plan requirements.
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V. Management Meetings X1 Exit Meeting Summa y The evaluation results were presented to members of facility management at the conclusion of the evaluation on June 18,1998. Facility personnel acknowledged the findings presente PARTIAL LIST OF PERSONS CONTACTED License 2
'W. Richards Reactor Director
'C Hydel Nuclear Operations and Maintenance Supervisor
'R. Crusby Chief, maintenance and Service Division, McClellen AFB J. Ching Supervisory Health Physicist T. Fitt Security Manager A. Weeks Training Coordinator H. Egbert Reactor Operator W. Bauer Experiment Coordinator A. Brinkley Supervisory Reactor Engineer Nuclear Regulatory Commissian
' Eresian Project Manager
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l lNSPECTION PROCEDURE (IP) USED {
39745 I Class l Non-Power Reactors Organization and Operations and Maintenance l Activities 40745 l Class i Non-Power Reactor Review and Audit and Design Change Functions 42745 Class l Non-Power Reactor Procedures 60745 Class I Non-Power Reactor Fuel Movement )
61745 Class I Non-Power Reactor Surveillance !
69003 Class I Non-Po'ver Reactor Operator Licenses, Requalification, and Medical Activities
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60904 Class i Non-Power Reactor Effluent and Environmental Monitoring 60905 Class l Non-Power Reactor Experiments l 81401 Plans, Procedures, and Reviews !
82745 Class i Non-Power Reactor Emergency Prepare ars; 83743 Class I Non-Power Reactors Radiation Protection i 86740 inspection of Transportation Activities l
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ITEMS OPENED, CLOSED, AND DISCUSSED Doened NONE Closed NONE PARTIAL LIST OF ACRONYMS USED HP Health Physics EP Emergency Plan FSAR Final Safety Analysis Report LCO Limiting Conditions for Operations NRC Nuclear Regulatory Commission OS Operations Supervisor RC Reactor Committee RO Reactor Operator SRO Senior Reactor Operator TS Technical Specifications
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