ML062330308

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NRC Inspection Report No. 50-05/2006-201
ML062330308
Person / Time
Site: Pennsylvania State University
Issue date: 08/24/2006
From: Johnny Eads
NRC/NRR/ADRA/DPR/PRTB
To: Pell E
Pennsylvania State Univ, University Park, PA
Bassett C, NRR/DRIP/REXB, 404-562-4899
References
IR-06-201
Download: ML062330308 (11)
v • d • e


Text

August 24, 2006 Dr. Eva J. Pell Vice President for Research Dean of the Graduate School The Pennsylvania State University 304 Old Main University Park, PA 16802-1504

SUBJECT:

NRC INSPECTION REPORT NO.50-05/2006-201

Dear Dr. Pell:

This refers to the inspection conducted on April 3 - 7, 2006, at the Pennsylvania State University Breazeale Research Reactor. 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 noncompliance of NRC requirements or safety concerns was identified. 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 available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of NRC's document system (ADAMS). ADAMS is accessible from the NRC Web site at (the Public Electronic Reading Room) http://www.nrc.gov/reading-rm/adams.html.

Should you have any questions concerning this inspection, please contact Dan Hughes at NRC headquarters at 301-415-1631.

Sincerely,

/RA/

Johnny Eads, Branch Chief Research and Test Reactors Branch B Division of Policy and Rulemaking Office of Nuclear Reactor Regulation Docket No. 50-05 License No. R-2

Enclosure:

NRC Inspection Report No. 50-05/2006-201 cc w/enclosure: See next page

Pennsylvania State University cc:

Mr. Eric J. Boeldt, Manager of Radiation Protection The Pennsylvania State University 304 Old Main University Park, PA 16802-1504 Dr. C. Frederick Sears, Director The Pennsylvania State University Breazeale Nuclear Reactor University Park, PA 16802-1504 Mr. William P. Dornsife, Director Bureau of Radiation Protection Department of Environmental Protection 13th Floor, Rachel Carson State Office Bldg.

P.O. Box 8469 Harrisburg, PA 17105-8469 Test, Research and Training Reactor Newsletter University of Florida 202 Nuclear Sciences Center Gainesville, FL 32611

August 24, 2006 Dr. Eva J. Pell Vice President for Research Dean of the Graduate School The Pennsylvania State University 304 Old Main University Park, PA 16802-1504

SUBJECT:

NRC INSPECTION REPORT NO.50-05/2006-201

Dear Dr. Pell:

This refers to the inspection conducted on April 3 - 7, 2006, at the Pennsylvania State University Breazeale Research Reactor. 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 noncompliance of NRC requirements or safety concerns was identified. 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 available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of NRC's document system (ADAMS). ADAMS is accessible from the NRC Web site at (the Public Electronic Reading Room) http://www.nrc.gov/reading-rm/adams.html.

Should you have any questions concerning this inspection, please contact Dan Hughes at NRC headquarters at 301-415-1631.

Sincerely,

/RA/

Johnny Eads, Branch Chief Research and Test Reactors Branch B Division of Policy and Rulemaking Office of Nuclear Reactor Regulation Docket No. 50-05 License No. R-2

Enclosure:

NRC Inspection Report No. 50-05/2006-201 cc w/enclosure: See next page Distribution PUBLIC PRTBr/f AAdams CBassett PIsaac MMendonca PDoyle TDragoun DHughes EHylton BDavis (cover letter only)(O5-A4)

NRR enforcement coordinator (Only IRs with NOVs, O10-H14)

ACCESSION NO.: ML062330308 TEMPLATE #: NRR-106 OFFICE PRTB:RI PRTB:PM PRTB:LA PRTB:SC NAME GBassett:tls DHughes EHylton JEads DATE / /2006 / /2006 08/22 /2006 08/24/2006 OFFICIAL RECORD COPY

U. S. NUCLEAR REGULATORY COMMISSION Docket No: 50-005 License No: R-2 Report No: 50-05/2006-201 Licensee: Pennsylvania State University Facility: Breazeale Research Reactor Location: University Park, Pennsylvania Dates: April 3 - 7, 2006 Inspector: Thomas F. Dragoun Approved by: Johnny Eads, Branch Chief Research and Test Reactors Branch B Division of Policy and Rulemaking Office of Nuclear Reactor Regulation

EXECUTIVE

SUMMARY

The focus of this routine, announced inspection was the on-site review of selected aspects of the licensees Class II non-power research reactor operation including: procedures, requalification program, surveillance and limiting conditions for operation, experiments, health physics program, and oversight by the Safeguards Committee.

The licensee's programs were acceptably directed toward the protection of public health and safety, and in compliance with NRC requirements.

Procedures

! The procedural control and implementation program satisfied Technical Specification requirements.

Requalification Training

! Operator requalification was conducted as required by the Requalification Program.

Surveillance and Limiting Conditions for Operations

! The records review indicated that the surveillance program was conducted in accordance with Technical Specification requirements.

Experiments

! Experiments were conducted within the constraints established by the Technical Specifications.

Health Physics

! The Radiation Protection Program being implemented by the licensee satisfied regulatory requirements.

Committees, Audits, and Reviews

! The Reactor Safeguards Committee provided the oversight required by the Technical Specifications.

Report Details Summary of Plant Status The Director provided a detailed tour of the facility for the benefit of the incoming NRC inspector. The reactor was started and shutdown several times for experiments, training, and service work. The inspector observed the 8 oclock daily coordination meeting for all staff.

1. PROCEDURES
a. Inspection Scope (Inspection Procedure (IP) 69001)

The inspector reviewed the following to determine if procedures were maintained as required by Technical Specification 6.3 Operating Procedures, NRC requirements in Title 10 of the Code of Federal Regulations, and licensee administrative requirements:

  • Use of Change Record for Procedures checklist to review changes made to following procedures:

- AOP-3, Loss of Cobalt-60 Pool Water Revision 3 reviewed on August 20, 2003

- CCP-9, Transient Rod Drive and Air Supply Revision 4 reviewed on January 16, 2006

- SOP-2, Daily Checkout Procedure Revision 17 reviewed on January 24, 2006

  • Procedures conducted for compliance with Technical Specifications as follows:

- CCP-1 Control Rod Speed and Scram Time Checks Revision 5 dated December 10, 2004 satisfies requirements in TS Sections 4.2.2, 3.13, 3.21, 3.22, and 3.26.

- CCP-8 Calibration of Air Monitors Revision 8 dated February 13, 2006 satisfies TS section 3.6.1 and 4.6.1.

- CCP-18 Review of Procedures Revision 4 dated October 17, 2005 satisfies the administration requirement for a biennial review of procedures.

  • Observed a reactor startup using procedure SOP-1, Reactor Operating Procedure Revision 13
  • Procedures AP-1 Revision 2, AP-6 Revision 3, and AP-8 Revision 5 were compared to verify that the benefits from a consistent format was also applied to non-technical procedures
b. Observations and Findings The inspector noted that all procedures at the facility have the same format and content and provide comprehensive guidance. These factors contribute to proper implementation by the staff. Procedures were readily available when requested by the inspector. The inspector was often able to find procedures and

other documentation unassisted due to the highly structured filling system. All procedures required by the TS were available.

c. Conclusions The procedural control and implementation program satisfied Technical Specification requirements.
2. REQUALIFICATION TRAINING
a. Inspection Scope (IP 69001)

The inspector reviewed selected records to determine if the Requalification Program approved by the NRC on July 9, 1997, and requirements in 10 CFR 55.59 were implemented. The review included:

  • operator license status
  • operator training records
  • operator physical examination records
  • operator examination records
  • operator active duty status
b. Observations and Findings There were no changes to this program since the last NRC inspection. The inspector reviewed the records of the physical exams, annual evaluations, biennial written exams, and reactivity manipulations for four of the operators. All were up-to-date with the requirements of the program.
c. Conclusions Operator requalification was conducted as required by the Requalification Program.
3. SURVEILLANCE
a. Inspection Scope (IP 69001)

The inspector reviewed the following regarding conduct of surveillance on safety systems as specified by TS 4.0:

  • Procedure SOP-2, Daily Checkout Procedure Revision 11, effective January 19, 2004
  • Procedure CCP-7, Wide Range Channel Electronic Checks Revision 2
  • Procedure CCP-14, Power Range Channel Electronic Checks Revision 2
  • Procedure CCP-9, Transient Rod Drive and Air Supply Revision 4
b. Observations and Findings The data records were well maintained and showed that surveillance requirements specified in TS were completed on schedule and in accordance with licensee procedures. All the recorded results were within the TS and procedurally prescribed parameters.
c. Conclusions The records review indicated that the surveillance program was conducted in accordance with Technical Specification requirements.
4. EXPERIMENTS
a. Inspection Scope (IP 69001)

The inspector reviewed the following to confirm that experiments were conducted in accordance with TS 3.7, Limitations of Experiments and TS 6.4, Review and Approval of Experiments:

  • Procedure SOP 9, Pneumatic Transfer System Operation Revision 3, dated October 7, 2005
  • Procedure SOP 5, Experiment Evaluation and Authorization Revision 4
  • Procedure SOP-7, Qualification of Reactor Pool Reactor Operating Positions Revision 4
  • Memorandum from the Radiation Safety Officer and the Associate Director for Operations dated October 17, 2005 authorizing certain personnel to use of the rabbit system
b. Observations and Findings The inspector observed the experimental samples placed in-core and the process for relocating the reactor core for certain experiments. These activities were conducted in accordance with the applicable procedure. Operation of the pneumatic transfer system (rabbit system) was described in detail by the licensee.
c. Conclusions Experiments were conducted within the constraints established by the TS.
5. HEALTH PHYSICS The inspector reviewed the following to verify compliance with 10 CFR Part 20 and TS Section 6 requirements and procedural requirements:
  • Administrative Procedure AP-18, Radiation Protection Program Revision 2, effective January 13, 2004
  • Annual Operating Report for Fiscal Year 2004 - 2005 dated
  • December 15, 2005
  • NRC Materials License Number 37 - 00185 - 04, Docket 030 - 00952, expires September 30, 2008
  • Policy Rules and Procedures for the use of Radioactive Material at the Pennsylvania State University, Spring 2001
  • Radiation survey maps, Radioactive Material Survey for all levels in the reactor building required to be completed weekly. Data for 2006
  • Quarterly radiation surveys. Data for 2004 and 2005
  • Personnel exposure records for 2005
  • Control of solid, liquid, and gaseous radioactive waste
  • Organization and staffing of the radiation protection function of the Environmental Health and Safety program
b. Observations and Findings The reactor radiation protection program had not changed since the last inspection and remains a subset of the campus program with oversight provided by the University Isotopes Committee (UIC). The program was documented and its status was reviewed annually by the RSO as required by 10 CFR 20.1101.

Training of new radiation workers and experimenters was a multi-step process.

The initial training consisted of a self-paced computerized program available on the Universities web site. The next step includes a practical demonstration of the protective devices and techniques. A 40-question exam covering the general radiation protection concepts was administered and successful candidates were referred to the reactor staff or Principal Investigator for the detailed training associated with the particular apparatus. The content of this training satisfied the requirements in 10 CFR 19.12.

Caution signs and postings were as required by 10 CFR 20, Subpart J. Routine radiological surveys were completed on a weekly, monthly, and quarterly basis in accordance with program requirements. Equipment used for these activities were maintained, calibrated and used acceptably. The survey reports were particularly well detailed and provided a thorough record and description of the radiological status of the area, including the condition of posted warning signs, presence of radwaste, condition of survey meters stationed in the area, and abnormal radiation levels.

Personnel dosimetry records indicated doses were well below NRC limits and, with one exception, were below the licensees administrative limit of 10% of the NRC limit (500 mrem per year). The RSO stated that efforts to reduce the individuals dose are continuing.

The calculation of the concentration of radioactivity in liquid waste are completed by the RSO. If the liquid was determined to meet the criteria for discharge to the

sewer, the RSO notifies the reactor staff. The liquid may be discharged to the sewer or processed through an evaporator.

c. Conclusions The radiation protection program acceptably satisfied NRC requirements.
6. COMMITTEES, AUDITS, AND REVIEWS
a. Inspection Scope (IP 69001)

The inspector reviewed the following to ensure that the audits and reviews stipulated in TS Section 6.2 were completed:

  • Reactor Safeguards Committee (RSC) composition.
  • Committee meeting minutes for January 17, 2006; April 12, October 11, and January 18, 2005
b. Observations and Findings The meeting minutes showed that the safeguards committee met as required by the TS with a quorum present. The committee composition was as specified in the TS. Five members were from the science and engineering fields and one member was a health physicist. The issues and oversight provided by the committee were in accordance with the review function with effective follow up of decisions.
c. Conclusions Audits were conducted by the RSC according to the requirements specified in the TS.
7. EXIT INTERVIEW The inspector presented the inspection results to members of licensee management at the conclusion of the inspection on April 7, 2006. The licensee acknowledged the findings presented.

PARTIAL LIST OF PERSONS CONTACTED Licensee E. Boeldt, Manager, Radiation Protection M. Bryan, Research Engineer L. Burton, Dean of Engineering M. Claver, Director, Environmental Health and Safety T. Flinchbaugh, Associate Director for Operations M. Linsley, EHS Program Manager T. Litzinger, Chair, Safeguards Committee M. Morlang, Reactor Engineer/Supervisor RSEC E. Pell, Vice President for Research and Dean of the Graduate School F. Sears, Director, Radiation Science & Engineering Center INSPECTION PROCEDURES USED IP 69001 CLASS II NON-POWER REACTORS ITEMS OPENED, CLOSED, AND DISCUSSED OPENED: None CLOSED: None LIST OF ACRONYMS USED CFR Code of Federal Regulations IP Inspection Procedure NRC Nuclear Regulatory Commission RP Radiation Protection RSC Penn State Reactor Safeguards Committee RSO Radiation Safety Officer TS Technical Specifications

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