IR 05000005/1999201
| ML20206A524 | |
| Person / Time | |
|---|---|
| Site: | Pennsylvania State University |
| Issue date: | 04/22/1999 |
| From: | NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20206A517 | List: |
| References | |
| 50-005-99-201, 50-5-99-201, NUDOCS 9904280195 | |
| Download: ML20206A524 (10) | |
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U. S. NUCLEAR REGULATORY COMMISSION
- Docket No: 50-005 License No: R-2 Report No: 50-005/1999201 i
L'censee:
i Pennsylvania State University l l
Facility: Penn State Breazeate Reactor Location: University Park, Pennsylvania l
Dates: March 22 26,'1999
- Inspector
- Thomas F. Dragoun l
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' Approved by: Ledyard B. Marsh,~ Director l Events Assessment, Generic Communications and Non-Power Reactors Branch Division of Regulatory improvement Programs-Office of Nuclear Reactor Regulation (
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EXECUTIVE SUMMARY This routine, announced inspection included onsite review of selected aspects of the operations program, organizational structure and functions, radiation protection program, I
. operator requalification program, design changer surveillance program, safeguards program, physical security program, efforts to identify and address year 2000 computer problems, and corrective actions for reportable occurrences since the last NRC inspectio .
The licensee's programs were acceptably directed toward the protection of public health r wt safety, and in compliance with NRC requirements. Records continue to be maintained ic a complete, orderly and easily retrievable manner. The new reactor director has introduced a more vigorous approach to safety issues and attention to detail that has resulted in an increase in the problems identified and resolved by the license l i
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Report Details Summary of Plant Status During the inspection the reactor was operated periodically to support experiments and operator requalification training. A truckload of concrete was poured into forms to be used as shielding during modification of a neutron radiography cell. A detailed training session for reactor operators was held to review a new procedure to electrically power down the control room. This included a tour of electrical distribution panel . ORGANIZATIONAL STRUCTURE AND FUNCTIONS (69001)
! Scope The inspector reviewed:
- organization and staffing i e qualifications (
- management responsibilities, and I e administrative controls
) Observations and Findinas j The organizational management structure and staffing had significantly changed since the last inspection. A new Manager of Radiation Protection, Reactor Director, and Vice President for Research were appointed. The Health Physics Office was ,
merged with the Department of Environmental Health and Safety. The Nuclear l Engineering Department was merged with the Mechanical Engineering Departmen The chairman of this new department oversees the reactor program. Amendment 32 to the Technical Specifications (TS), issued in March 1998, incorporated many administrative changes, including the reorganization. Qualifications of the staff met l TS requirements specified in section 6.1.1. Review of records verified that l management responsibilities were administered as required by TS and applicable procedure The licensed reactor operations staff has been stable with 11 licensed operator The staffing level appears acceptable to support the reactor programs. Several senior reactor operators were promoted to supervisory positions. Meetings with the operating staff held twice weekly appeared to tvovide an effective forum for information exchange between management anu the staff. The staff appeared to be enthusiastic and competent. The new Reactor Director introduced a more rigorous approach to safety issues and attention to detail. This change resulted in an increase in the number of reportable events forwarded to the NRC and discussed in section 6.0 of this repor .
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2- Conclusions The organizational functions satisfied NRC requirement . RADIATION PROTECTION (69001) Scone The inspector reviewed:
- RP Department staffing I e routine radiation surveys e maintenance and calibration of portable instruments e laboratory analysis of samples e personnel dosimetry e control of effluents !
e environmental monitoring I e notices to workers e restricted area postings
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- radiation worker training l e solid waste processing e ALARA program o audits, and e oversight b. Observations and Findinas The Manager of Radiation Protection was promoted and his previous position as I Associate Health Physicist was filled by a new hire. Both HP Specialists in the l department were replaced along with some of the support personnel. Staffing is acceptable with all key positions fiDd by qualified personnel. However, the majority of the staff is new. In addition, after the reorganization of university departments, all levels of management with responsibility for oversight of the RP program were also new. The inspector noted some lack of familiarity with research reactor programs during interviews with the staff. In response, upper management stated that peer reviews and assistance with program development may be sought. Additionally, selected staff may visit other research reactor f acilities to gain insight into other programs. The Reactor Director stated that he and the reactor operators staff also share in the responsibility and support for the radiation protection progra The scope and frequency of routine radiation surveys by the RP specialists were accepteble. The reactor staff also conducts independent surveys with separate instrumentation.
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-3-A standard collimated irradiator (Sheppard) with a variable distance range is used to calibrate portable meters. The inspector noted that a closed circuit TV system is used to observe the meter readings when the radiation source is exposed. This is a 1 good ALARA practice. In addition, meters are calibrated at three points per scale with separate verification of full scale readings. Distance is measured with a high accuracy digital readout dev ce. These techniques exceed recommendation l l
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The HP Manager indicated that an annual review of the radiation protection program content and implementation as required by 10 CFR 20.1101 was completed in October 1998. However, the report of findings was still in draft. The inspector '
requested a copy of the final report. This was forwarded to the inspector by licensee letter dated April 5,1999. This matter is close The counting laboratory consists of a liquid scintillation counter and a three inch sodium iodide gamma detector attached to a multichannel analyzer. A review of j
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records indicated that daily background counts and calibrated standard counts were j done and reviewed by the laboratory specialist. However, the quality verification of j the system operability did not use standard technique. The RP Manager stated that I this matter would be reviewe I
_ Conclusions The radiation protection program satisfied NRC requirement l 3. DESIGN CONTROL (69001) i a. Scone l The inspector reviewed; e facility design changes and records !
e f acility configuration b. Observations and Findinas Data from instrumented 12 weight-% fuel replacing 8 weight-% fuel in the core "B" (inner) ring indicated higher than anticipated operating temperatures. This reduced the safety margin. Administrative limits on maximum power and pulsing were invoked and the Safety Analysis Report was revised. Computer modeling was used to determine optimum fuel loading, predict excess reactivity, and determine the l conservative locations for instrumented elements. Records indicate that the fuel was
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shuffled in a controlled and documented manner using a special procedure. The instrumented (temperature sensor) elements were tested in several locations, an anomaly was detected and determined to be caused by an overpowered elemen The instrumented elements were finally placed in conservative locations. Excess reactivity and shutdown margin were measured and found to be within TS specifications for the new core configuration called " Core Load #50."
c. Conclusions The design change was technically sound and satisfied NRC requiremrot . OPERATOR REQUAllFICATION (69001)
a. Scope The inspector reviewed e requalification records e training aids a written exams b. Observations and Findinas A revised operator requalification plan was approved by the NRC in June 1997. The plan has been implemented by licensee procedure AP-3, Revision 1, also dated June 1997. The list of records specified in section J of this procedure were maintained and documented the completion of program requirement Output from the digital console has been ported to the LAN so that the console display can be projected onto a large screen in a classroom for training and demonstrations. An SRO has been designated as the training specialist. She has made extcasive use of training experts on the university staff to guide development of training materials. Technical experts from the university staff are recruited to provide lectures. Test results are analyzed and staff observations are used to determine training need ]
c. Conclusions The operator requalification program was effectively implemente I
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-5- SURVEILLANCE (69001) The inspector reviewed
- surveillance results e surveillance procedures Observations and Findinas Surveillance verifications were completed on schedule and in accordance with licensee procedures. All the recorded results were within the TS and procedurally prescribed 1 parameters. The records and logs reviewed were complete, orderly, and easily f retrievable. The flexibility for fuelinspections permitted by TS Amendment 32 will not be implemented until the next biennial cycl Conclusions The surveillance program satisfied Technical Specification requirement . ABNORMAL OCCURRENCES i Scone The inspector reviewed the completed root cause analysis and corrective actions for the following occurrences reported to the NRC in accordance with TS 6.5.2 since the last inspection:
- August 1998, unplanned release of tritiated Reactor Pool Water e February 1998, reactor console unattended for a brief period
- October 1997, hardware pulse interlock misadjusted
- September 1997, misinterpretation of rod withdrawalinterlock bypass
- May 1997. missed surveillance on pool water conductivity
- December 1996, fuel temperature safety char.nel inoperative Observations and Findinos In each case, the required actions were complete and acceptable, These matters are close c.- Conclusions Technical Specification requirements regarding Reportable Occurrences were satisfie u
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.7 6- YEAR 2000 PREPARATIONS Scooe The inspector reviewed licensee action relative to the elements of a questionnaire developed by the NRC staff to assess potential Y2K computer problem Observations and Findinas A university-wide program to identify and correct Y2K problems is in place. There is an Internet web page maintained by the university that provides assistance with Y2K issues. The Research Engineer / Supervisor /SRO from the reactor staff was assigned responsibility for Y2K efforts at the reactor facility. A test program provided by the digital control console manufacturer (AECL) determined that the historical trending computer (computer Z) was not Y2K compliant. A temporary solution to roll-back of the system clock by a predetermined number of years will be dry run in May. If successful, this solution will remain in place until the vendor is able to provide a software fix and incorporate additional features requested by the facility. Management indicated that deadlines for completing this upgrade are still under negotiation with the vendor. Other systems related to radiation safety and security were tested or certified by the respective vendors and records maintained by the responsible superviso l Conclusions l
No threat to health or safety was identified as a result of Ye 2000 computer issue . MATERIAL CONTROL AND ACCOUNTABILITY !85102) 1 i Scope j The inspector reviewed:
i o assignment of responsibility for special nuclear material l
- procedures e accountability records and reports - Observations and Findinas The licensee was maintaining a system of controls that provided the quantity identity, and current location of all special nuclear material (SNM) within the facility. The inspector verified selected portions of the latest annualinventory by piece count. The possession and use of SNM was limited to the locations and purposes authorized under the license. The material control and accountability forms (DOE /NRC Forms 741 and 742)
were prepared and transmitted as required.
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-7- Conclusions
- Special Nuclear Materials were acceptably controlled and inventorie . SECURITY '81431)- Scope
- The inspector reviewed selected aspects of:
e- physical protection equipment e security systems, equipment and instrumentations
- e implementation of the Physical Protection Plan i Observations and Findinas
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Physical' protection systems (barriers and alarms), equipment and instrumentation were as required by the Physical Protection Plan. Periodic equipment operability checks were completed and recorded as required. Access control was as require Implementing procedures were consistent with the Physical Protection Plan. The formality of key control has improved since the last inspection. The annual security I plan review was noteworthy in terms of depth of the review and the value of the conclusions and recommendations provided to facility managemen Conclusions Security activities and systems satisfied Physical Protection Plan requirement . Exit Meetina Summarv The inspector presented the inspection results to members of licensee management _ ,
at the conclusion of the inspection on March 26,1999. The licensee acknowledged {
the findings presente ]
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PARTIAL' LIST OF PERSONS CONTACTED i
Licensee W. Anderson, Assistant VP for Physical Plant
- A. Baratta, Chairman, Mechanical and Nuclear Engineering Department E. Boeldt, Manager, Radiation Protection I
- M. Bryan, Research Engineer / Supervisor RSEC L. Burton, Associate Dean, Engineering M. Claver, Director, Environmental Health and Safety-C. Davison, Research and Education Specialist / Supervisor RSEC T. Flinchbaugh, Manager, Operations and Training RSEC D. Hughes, Manager, Engineering RSEC M. Morlang, Reactor Engineer / Supervisor RSEC F. Sears, Director, Radiation Science & Engineering Center INSPECTION PROCEDURES USED 1 IP 69001 CLASS 11 NON-POWER REACTORS IP 81431 FlXED SITE PHYSICAL PROTECTION OF SNM OF LOW STRATEGIC SIGNIFICANCE IP 85102 MATERIAL CONTROL AND ACCOUNTING )
ITEMS OPENED, CLOSED, AND DISCUSSED OPENED: None CLOSED: None LIST OF ACRONYMS USED ALARA As Low As Reasonably Achievable j CFR Code of Federal Regulations l NRC Nuclear Regulatory Commission RP- Radiation Protection SNM special nuclear material TS _ Technical Specifications Y2K . year 2000
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