IR 05000134/2004201
| ML041690121 | |
| Person / Time | |
|---|---|
| Site: | 05000134 |
| Issue date: | 06/30/2004 |
| From: | Madden P Division of Regulatory Improvement Programs |
| To: | Laflamme S Worcester Polytechnic Institute |
| dragoun T, NRR/DRIP/RNRP, 610-337-5373 | |
| References | |
| 50-134/2004-201 | |
| Download: ML041690121 (14) | |
Text
June 30, 2004
SUBJECT:
NRC INSPECTION REPORT NO. 50-134/2004-201
Dear Mr. LaFlamme:
June 30, 2004
SUBJECT:
NRC INSPECTION REPORT NO. 50-134/2004-201
Dear Mr. LaFlamme:
This letter refers to the inspection conducted on April 19-22, 2004 at the Worcester Polytechnic Institute Leslie C. Wilbur Nuclear 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 concerns or noncompliance with NRC requirements were identified.
No response to this letter is required.
In accordance with 10 CFR 2.390 of the NRCs "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 NRCs 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 Mr. Thomas Dragoun in King of Prussia, PA at 610-337-5373.
Sincerely,
/RA/
Patrick M. Madden, Section Chief Research and Test Reactors Section New, Research and Test Reactors Program Division of Regulatory Improvement Programs Office of Nuclear Reactor Regulation Docket No. 50-134 License No. R-61 Enclosures: NRC Inspection Report No. 50-134/2004-201 cc w/encl: Please see next page Distribution PUBLIC RNRP/R&TR r/f AAdams CBassett JLyons MMendonca PDoyle TDragoun WEresian FGillespie SHolmes DHughes EHylton PIsaac PMadden KWitt PYoung BDavis (cover letter only)(O5-A4)
NRR enforcement coordinator (Only IRs with NOVs, O10-H14)
ACCESSION NO.: ML041690121 TEMPLATE #: NRR-106 OFFICE R&TR:RI R&TR:LA R&TR:SC NAME TDragoun EHylton PMadden DATE 6/ 8 /2004 6/ 18 /2004 6/ 18 /2004 C = COVER E = COVER & ENCLOSURE N = NO COPY OFFICIAL RECORD COPY U.S. NUCLEAR REGULATORY COMMISSION OFFICE -OF NUCLEAR REACTOR REGULATION
Docket No:
50-134 License No:
R-61 Report No:
50-134/2004-201 Licensee:
Worcester Polytechnic Institute Facility:
Leslie C. Wilbur Nuclear Reactor Facility Location:
Worcester, Massachusetts Dates:
April 19 - 22, 2004 Inspector:
Thomas F. Dragoun Approved by:
Patrick M. Madden, Section Chief Research and Test Reactors Section New, Research and Test Reactors Program Division of Regulatory Improvement Programs Office of Nuclear Reactor Regulation
EXECUTIVE SUMMARY Worchester Polytechnic Institute Leslie C. Wilbur Nuclear Reactor Facility NRC Inspection Report No. 50-134/2004-201 This routine, announced inspection included onsite review of selected aspects of the organization and staffing, operations logs and records, procedures, operator requalification program, surveillance and limiting conditions for operations, health physics program, committees and audit program, and emergency preparedness program since the last NRC inspection.
The licensees programs were acceptably directed toward the protection of public health and safety, and in compliance with NRC requirements.
Organization and Staffing
The organization and staffing were consistent with Technical Specification requirements.
Operations Logs and Records
Records were kept in accordance with the regulatory requirements.
Procedures
The procedural control and implementation program satisfied Technical Specification requirements.
Operator Requalification
Operator requalification was conducted as required by the Requalification Program.
Surveillance and Limiting Conditions for Operations
The reactor was operated within the Limiting Conditions for Operations specified in the Technical Specifications.
Health Physics
The radiation protection program satisfied NRC requirements.
Committees and Audits
The review and audit program satisfied Technical Specification requirements.
The NRC approved Emergency Plan was acceptably implemented.
Report Details Summary of Plant Status During the inspection the reactor was not operated.
1.
Organization and Staffing a.
Inspection Scope (Inspection Procedure (IP) 69001)
The inspector reviewed selected aspects of:
organization and staffing
qualifications b.
Observations and Findings The non-Technical Specification required position of Director of Nuclear Engineering Programs was canceled by the institute's administration. Some duties of the position, such as grant applications and communications with Department of Energy (DOE),
were transferred to the Director of the Nuclear Reactor Facility. The Directors immediate supervisor, the Mechanical Department Head, had changed since the last NRC inspection. There was no apparent impact on the reactor operations program from these organization changes.
There were four licensed Senior Reactor Operators (SROs) on staff. Two will graduate this year but two replacements are in training. One of the trainees is the campus Assistant Radiation Safety Officer (ARSO) who will become a permanent operator. This change is to enhance the operational capability of the reactor.
c.
Conclusions The organization and staffing were consistent with Technical Specification requirements.
2.
Operation Logs and Records a.
Inspection Scope (IP 69001)
The inspector reviewed the following to ensure that selected records were maintained as required by TS Section 5.6, 5.8, and 10 CFR 20 Subpart L:
Licensee Annual Reports dated March 28, 2003 and March 29, 2004
Console logs for the period December 8, 2000 through April 14, 2004
Personnel radiation exposure data for years 2001 and 2002
Maintenance Log for the period January 23, 2002 to March 2, 2004
Personnel dosimetry reports for 2001, 2002, and 2003
Radiation survey quarterly results recorded on Form #17 for 2001, 2002, and 2003
Annual audit of the radiation protection program dated January 26, 2004
-2-b.
Observations and Findings Annual reports contained the data required to be recorded by the TS. Console log entries were highly detailed and descriptive and provided an indication of operational activities. Logs and records also showed that operational conditions and parameters were consistent with license and TS requirements. Shift staffing requirements are found in TS Section 2.2, thus making staffing a Limiting Condition for Operations (LCO). This situation is unique among research reactors. Compliance with this LCO was documented in the console log. All logs and records were clear, well organized, and readily retrievable.
c.
Conclusions Records were kept in accordance with the regulatory requirements.
3.
Procedures a.
Inspection Scope (IP 69001)
The inspector audited the following to ensure that the requirements of TS Section 5.5 were being met concerning written procedures:
Procedure OP-01, Check-out and Operation, revision 3, dated October 2001 Completed checklists associated with this procedure from March 31, 2003 to March 25, 2004
Procedure OP-02, Routine Experiments and Samples Irradiation Procedure revision 0, dated April 1998
Procedure OP-03, Fuel Unloading Procedure revision 2, dated July 2001
Procedure OP-04, Standard Core Configuration Reload with Fuel Loading Sequence Guide revision 2, dated July 2001
Procedure SP-01, Regulating Blade Worth and Excess Reactivity Measurement revision 1, April 1998
Procedure SP-02, Power Level Calibration revision 1, dated April 1998
Procedure SP-03, Rod Drop-Time Measurement revision 1, dated April 1998
Procedure SP-04, Rod Withdrawal-Time Measurement revision 1, dated April 1998
Procedure SP-05, Minimum Shutdown Margin Measurement revision 1, dated April 1998
Procedure AP-01, Director Responsibilities revision 0, dated April 1998
Procedure 99-SSG-2, Sample Irradiation in SS Guide Tube dated December 15, 1999
Procedure MP-1, Demineralizer Regeneration no revision, dated April 1996
Procedure MP-2, Procedure for Replacing Resin in Ion Exchange Column no revision, dated November 1983
Procedure MP-3, Control Blade and Drive Inspection Procedure no revision, dated October 1992
Procedure MP-4, U-V Sterilizer and Cartridge Filter Maintenance Procedure no revision, dated June 1992
Procedure MP-5, Diatomaceous Earth (DE) Filter System Procedure no revision, dated July 1992
-3-b.
Observations and Findings The inspector determined that written procedures were available for the activities delineated in TS Section 5.5 and were approved by the Radiation, Health, and Safeguards Committee (RHSC) before they were implemented. The clarity and detail in the procedures was acceptable.
c.
Conclusions The procedural control and implementation program satisfied Technical Specification requirements.
4.
Operator Requalification a.
Inspection Scope (IP 69001)
The inspector reviewed the following to verify compliance with the requirements in 10 CFR 55 and Appendix F to the Safety Analysis Report dated September 25, 1979:
operator active license status
training
operator physical examination records
reactivity manipulation records
written examination results b.
Observations and Findings There are four licensed operators and all licenses are current. The requirement for a procedures change review, physical examination, written examination, reactivity manipulations, operational evaluation, and semiannual review of the emergency response plan were completed in a manner consistent with the Requalification Program requirements.
c.
Conclusions Operator requalification was conducted as required by the Requalification Program.
5.
Surveillance and Limiting Conditions for Operation a.
Inspection Scope (IP 69001)
The inspector reviewed the following to ensure that the surveillance requirements and limiting conditions for operations (LCO) specified in TS Sections 2.0 and 3.0 were met:
Console log. Data for December 8, 2000 to April 14, 2004
Maintenance log. Data for January 23, 2002 to March 2, 2004 b.
Observations and Findings Within the limited scope of this review, the inspector determined that surveillance, test and LCO verifications and calibrations were completed on schedule and in accordance with licensee procedures, checklists, or equipment manufacturers recommendations.
-4-c.
Conclusions The reactor was operated within the Limiting Conditions for Operations specified in the TS.
6.
Health Physics a.
Inspection Scope (IP 69001)
The inspector reviewed the following to verify compliance with 10 CFR Part 19 and Part 20 and TS Sections 3.3 and 5.5:
Worcester Polytechnic Institute RHSC Radiation Regulations Memorandum October 1995
Health Physics Procedure 01, Area Monitors and Pool Level Monitor Calibration revision 1, dated July 1996
Health Physics Procedure 03, Survey Instrument Calibration revision 4, dated July 1996
Health Physics Procedure 04, Campus Wipe Test revision 2, dated July 1996
Health Physics Procedure 06, Activities and Releases revision 2, dated July 1996
Health Physics Procedure 07, Pool Water and Hold-up Tank Water Analysis revision 1, dated July 1996
Health Physics Procedure 08, RSO Quarterly Report revision 1, dated July 1996
Health Physics Procedure 10, Radiation Surveys revision 1, dated July 1996.
Semiannual results for 2001, 2002, 2003
Health Physics Procedure 17, Personnel and Area Monitoring revision 0, dated October 1993
Health Physics Procedure 20, RSO Monthly Reactor Facility Inspection revision 1, dated October 1993
Personnel annual dosimetry results for 2001, 2002, and 2003
RSO annual audit dated January 26, 2004
Radiation Worker training material WPI Isotope Training Notes version dated February 11, 2004 b.
Observations and Findings The Health Physics (HP) program for the reactor includes the campus byproduct license. No major changes to the policies or procedures were required after the State (Massachusetts) became an NRC agreement State. The State is authorized regulate the byproduct licenses.
During tours of the facilities the inspector determined that the controls, warning signs and postings were acceptable for the radiological conditions reported during the routine radiation surveys. The only controlled areas at the facility are the walkway adjacent to the reactor pool and a basement closet used for storage of radioactive training sources. Dosimetry results showed that personnel doses were well below the NRC annual limit. The area radiation monitors and portable survey meters were maintained and calibrated as required. A documented annual review was conducted as required by 10 CFR 20.1101. The radiation worker training program satisfied the requirements in 10 CFR 19.12.
-5-c.
Conclusions The radiation protection program satisfied NRC requirements.
7.
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 5.2 and 10 CFR 50.59 were being completed by the RHSC:
RHSC membership
RHSC minutes of meeting for meetings held February 7, April 30, June 6, and October 29, 2001, January 28, April 30, August 1, November 25, 2002, and January 30, April 30, July 30, and October 29, 2003 b.
Observations and Findings The composition and meeting frequency of the RHSC satisfied the TS requirements.
The minutes of meeting demonstrated that the RHSC provided exceptionally thorough and detailed reviews and oversight of every aspect of reactor operations. For example, each semi-annual radiation survey report was completed by the HP technician and reviewed and approved for presentation to the RHSC by the RSO. The survey data was then reviewed by entire RHSC committee membership during each April and October quarterly meetings. If determined to be acceptable, the RHSC Chairman and the Reactor Director sign the data sheet and it becomes part of the permanent file required by 10 CFR Part 20. The inspector confirmed this action was taken by the committee during the October and April meetings held during 2001, 2002, and 2003.
There were no equipment changes since the last NRC inspection. Procedure changes were minor.
c.
Conclusions The review and audit program satisfied Technical Specification requirements.
8.
Emergency Planning a.
Scope (IP 69001)
The inspector reviewed selected aspects of:
the Emergency Plan
Letters of Agreement with support agencies
Critiques of biannual emergency drills held January 30 and July 30, 2003, January 28 and August 1, 2002, and February 7 and July 23, 2001
-6-b.
Observations and Findings A change to the Emergency Plan was approved by the NRC on May 16, 2002. The revised plan was found to be adequately implemented including the change to the calibration frequency of radiation detecting equipment described in Section 10 of the Plan. The Plan was audited and reviewed annually as required. Agreements with Worcester Police and Fire Departments, University of Massachusetts Medical School and University of Massachusetts Lowell Radiation Laboratory (outside response organizations) were all dated November 2002 and included in the plan.
Emergency drills had been conducted as required by the Emergency Plan. Critiques were held following the drills to discuss the strengths and weaknesses identified during the exercise and to develop possible solutions to any problems identified. The results of these critiques were documented and filed.
c.
Conclusions The NRC approved Emergency Plan was being properly implemented.
9.
Follow-up on Previously Identified Issues a.
Inspection Scope The inspector reviewed the actions taken by the licensee following identification of two Inspector Follow-up Items during a previous inspection in December 1, 2000 and documented in NRC Inspection Report No. 50-134/2000-201.
b.
Observations and Findings (1)
IFI 50-134/2000-201-01 - Follow-up on the biennial physical examination of the two student operators were due but were not scheduled.
During NRC Inspection 50-134/2000-201 the inspector determined that the biennial physical examination of the two student operators were due but were not scheduled. To prevent a recurrence, the Facility Director developed a status matrix listing all requalification requirements and due dates in a computer spreadsheet. The data was updated weekly, printed out, and posted. The RHSC also reviews the data during the quarterly meetings. Licensees corrective action regarding this matter was complete and satisfactory. Inspector Follow-up Item 50-134/2000-201-01 is closed.
c.
Conclusions The licensee had taken action to resolve previously identified issues involving two Inspector Follow-up items. These items were closed.
10. Exit Meeting The inspector presented the inspection results to licensee management at the conclusion of the inspection on April 22, 2004. The licensee acknowledged the findings presented.
PARTIAL LIST OF PERSONS CONTACTED S. LaFlamme, Nuclear Reactor Facility Director D. Adams, Radiation Safety Officer R. Steele, Assistant Radiation Safety Officer D. Messier, Chairman, Radiation, Health, and Safeguards Committee INSPECTION PROCEDURES USED IP 69001 CLASS II NON-POWER REACTORS IP 85102 MATERIAL CONTROL AND ACCOUNTING - REACTORS ITEMS OPENED, CLOSED, AND DISCUSSED Opened None Closed 50-134/2000-201-01 IFI Complete biennial physical exam of operators 50-134/2000-201-02 IFI Revise radiation survey report form LIST OF ACRONYMS USED CFR Code of Federal Regulations IFI Inspector Follow-up Item IP Inspection Procedure NRC Nuclear Regulatory Commission RHSC Radiation, Health, and Safeguards Committee RSO Radiation Safety Officer SNM Special Nuclear Material TS Technical Specifications