IR 05000223/1997201

Insp Rept 50-223/97-201 on 970513-16.No Violations Noted. Major Areas Inspected:Licensee Organization,Operations & Maint Activities

ML20141G113
Person / Time
Site:	University of Lowell
Issue date:	06/26/1997
From:	NRC (Affiliation Not Assigned)
To:
Shared Package
ML20141G110	List: IR 05000223/1997201 ML20141G106
References
50-223-97-201, NUDOCS 9707030305
Download: ML20141G113 (9)

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U.S. NUCLEAR REGULATORY COMISSION Docket No: 50-223 License No: R-125 Report No: 50-223/97201 Licensee: University of Massachusetts Facility: Lowell University Research Reactor Location: 1 University Avenue Lowell, Massachusetts Dates: May 13-16, 1997 Inspector: Thomas F. Dragoun, Project Scientist Approved by: Marvin M. Mendonca, Acting Director Non-Power Reactors and Decommissioning Project Directorate EXECUTIVE SUMMARY R(actor operations were conducted in a manner consistent with regulatory requirements and licensee commitment Corrective actions regarding failure of containment isolation valve mechanisms and position indications were acceptable. The redesignated health physics technician position is filled by permanent staf PDR ADOCK 05000223 G PDR

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Report Details Summary of Plant Status The reactor was operated periodically for experiments. Neutron dosimeters were irradiated with a collimated beam from the thermal column. Electronic components and medical equipment were irradiated with the Co-60 sourc Upgraded nuclear instrumentation channels were being tested prior to installatio Conduct of Operations 01.1 Oraanization and Operations and Maintenance Activities Inspection Scope (Inspection Procedure 39745)

The inspector reviewed: l

e organization and staffing,

e administrative controls, and e the console log i Observations and Findinas l Current staffing consists of 8 licensed operators and 6 student i

trainees. The staff appears motivated and enthusiasti i l Dissolution of the Nuclear Engineering Department has not affected l the quality or number of trainees. The staffing level is able to support increased utilization of the facility, equipment repairs, and proposed project In a June 3,1996 letter, the licensee stated that the health j physics technician position will be changed to a full-time staff -

position. The inspector confirmed that this new permanent position  !

is filled with an experienced and qualified individual. Inspector follow up item 96-02-02 is close The console log was neat, legible, and recorded required  ;

information. " Critical Hourly Readings" are taken on all measuring channels. Important systems are visually inspected using a checklist every four hours dfsring operation. Conduct of i surveillances and reactivity manipulations for operator requalification were clearly noted in the lo These are notable practice In a January 21, 1997 letter, the licensee reported failure of containment isolation valves "D" and "E" to close. These large l

disk-and-seal blast valves are spring loaded to close and open by an air-operated piston and pushrod' acting on the disk center. The failures resulted from stripped threads at the piston to pushrod join Earlier detection of the failure was masked by a history of ;

faulty valve position indication '

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2 r Short term corrective actions completed include temporary thread repairs, operating procedure changes, operator training, and repair ,

and adjustment of the valve position indicating switches. Long term

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repair options are under review with the valve manufacture Licensee actions regarding this matter are acceptabl , Conclusioni  :

Staffing requirements in TS 6.1 were_ satisfied. Operating records required by.TS 6.7 were well kept and available for review. Actions relative to the failure of containment isolation valves were acceptabl .2 Experiments i

j Inspection Scope (Inspection Procedure 69745)

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The inspector reviewed; e potential hazards identification, e control of irradiated items, and e radiation controls i Observations and Findinas

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Experimenters and staff demonstrated a good understanding of hazards associated with experiments. Administrative controls and communications with the control room was good. Access to the high radiation area created by a beam from the thermal column port was controlled by physical barriers and a reactor operator trainee serving as watchma fonclusions Experiments were conducted in accordance with regulatory requirement Operational Status of Facilities and Equipment 02.1 Surveillance Inspection Scope (Inspection Procedure 61745)

i The inspector reviewed:

!' e surveillance procedures, e surveillance data, and

[ e limiting conditions of operation

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j b. Observations and Findinas '

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Surveillances were found to be completed in accordance with a l monthly schedule and results were within equipment specification Data folders are labeled with the appropriate TS section oumber l allowing easy retrieval. Surveillance procedures were clear, I descriptive, and employed generally accepted testing techniques or

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manufacturers recommendations. Procedures and data sheets specify

! the acceptance range for each entry. Data sheets also cross

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reference the. appropriate console log entry (volume and pace) for additional information. Data was complete and demonstrated equipment operabilit The inspector noted some data sheets were not readily available in the appropriate folder. The Reactor Supervisor and CR0 indicated that data filing was behind schedule but would be corrected soon, c. Conclusions The safety equipr.ent surveillances required by TS section 4.0 are completed as required.

l 03 Operations Procedures and Documentation l Inspection Scope (Inspection Procedure 42745)

The inspector reviewed:

e operating procedures and updates, and e adherence to procedures

b. Observations and Findinas Procedures required by TS 6.3 were available, clear, and concis Changes were approved by the Reactor Safety Subcommittee as required. Operators properly used procedures and demonstrated awareness of changes and reasons for the change.

! Conclusions Use of facility procedures, and changes thereto, satisfied TS 7.8 requirements.

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05 Operater Troining and Qualification l a. Inspection Scope (Inspection Procedure 41745)

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The inspector reviewed: ,

l l l e active license status, e training records, e records of reactivity manipulations-  ;

e medical examinations, and '

e written examinations i I

b. Observations and Findinas  !

There were no expired licenses among the roster of active operator j

The biennial requalification written exams use a full NRC initial -

! qualification exam. It is administered and corrected by the Reactor Supervisor. This ensures all required technical areas are tested.

Generalized staff training and individual specific training to t

correct weaknesses is determined by the CR0 and RS. The CR0 also publishes a required reading list of procedure and TS changes and audits completio Records of training, console manipulations, medical evaluations, and written exams were current for each operato c. Conclusions j

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The requalification program is conducted in accordance with the NRC

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approved program.

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07 Quality Assurance in Operations t

07.1 Review and Audit and Desian Chance Functions i

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a. Insoection Scope (Inspection Procedure 40745) i i

The inspector reviewed: )

e Reactor Safety Subcommittee membership and minutes of meeting, e Subcommittee written charter, e interview with the Subcommittee chairman, and e a recent security audi !

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5 Observations and Findinas Records indicated that the Subcommittee met at the required frequency and reviewed reactor operations. In a February 1997

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meeting, the committee accepted the finding of no URSQ from the 10 CFR 50.59 review of the replacement nuclear instrumentation channels on site for testing. The scientific diversity and proficiencies of the membership satisfied TS requirements. The Subcommittee charter was. reissued by the current Chancellor in October 1994. Elements of the charter reflect TS oversight requirements. The chairman ,

expressed satisfaction with the functioning of the Subcommitte The CR0 conducted a thorough and detailed audit of security '

practices. Corrective action for reported weaknesses was underwa Conclusions Review and audit functions" required by TS 6.2 were acceptably complete P1 Conduct of EP Activities

' ' Scope (Inspection Procedure 82745)

The inspector reviewed:

e facilities, equipment, and' supplies, e exercises and drills, and e trainin Observations and Findinas_

l A revised Emergency Preparedness Plan was submitted to the NRC in September 1994 and implemented in January'1995. Local facilities, equipment and supplies were as required in the plan. Improved communication is anticipated after receipt of donated radios. .A merger of hospitals resulted in a change in location of the emergency room, which is also nearby. The recent drill tested the i~

response of this new location. The drill was well planned, well conducted, and identified a few area for improvement. The speed and professionalism of the EMT response received favorable comment Training required by Section 10.1 of the Plan was complete except -

for some members of the campus police. Agreements with off-site l

, support agencies were in effect but due for the biennial updat Conclusions i The emergency plan was acceptably implemented.

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X Exit Meetitig Summary (Inspection Procedure 30703)

l- The inspector presented the inspection results to members of licensee l management at the conclusion of the inspection on September 20, 1996.

l The licensee acknowledged the findings presented.

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PARTIAL LIST OF PERSONS CONTACTED Licensee

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l * L. Bettenhausen, Reactor Supervisor

' * W. Church, Radiation Safety Officer G. Kegel, Director, Radiation Laboratory D. Medich, Chief Reactor Operator

• Denotes those present at the exit meetin INSPECTION PROCEDURES USED IP 30703: ENTRANCE AND EXIT INTERVIEWS I

IP 39745: CLASS I NON-POWER REACTORS ORGANIZATION AND OPERATIONS AND MAINTENANCE ACTIVITIES

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IP 40745: CLASS I NON-POWER REACTOR REVIEW AND AUDIT AND DESIGN CHANGE l FUNCTIONS l

l IP 41745: CLASS I NON-POWER REACTOR OPERATOR LICENSES, REQUALIFICATION AND MEDICAL ACTIVITIES IP 42745: CLASS I NON-POWER REACTOR PROCEDURES IP 61745: CLASS I NON-POWER REACTOR SURVEILLANCE IP 69745: CLASS I NON-POWER REACTOR EXPERIMENTS IP 82745: CLASS I NON-POWER REACTOR EMERGENCY PREPAREDNESS ITEMS OPENED, CLOSED, AND DISCUSSED Opened none Closed

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50-233/96-02-02 IFI Fill permanent HP technician position

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l LIST OF ACRONYMS USED CFR Code of Federal Regulations CR0 Chief Reactor Operator

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EMT Emergency Medical Technician

- EP Emergency preparedness IFI Inspector Follow Item IP Inspection Procedure NRC Nuclear Regulatory Commission RS Reactor Supervisor SAR Safety Analysis Report

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SR0 Senior reac?:r operator TS Technical Specifications l URSQ UnReviewed Safety Question )

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