IR 05000020/1996002

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Insp Rept 50-020/96-02 on 960916-20.No Violations Noted. Major Areas Inspected:Emphasis on Maint & Training After Departure of Staff Members Resulted in Improved Program Performance
ML20129D245
Person / Time
Site: MIT Nuclear Research Reactor
Issue date: 10/16/1996
From: Dragoun T, White S
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
Shared Package
ML20129D237 List:
References
50-020-96-02, 50-20-96-2, NUDOCS 9610240242
Download: ML20129D245 (7)


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U. S. NUCLEAR REGULATORY COMMISSION i

REGION I I Docket No: 50-20 i License No: R-37  !

Report No: 50-20/96-02 Licensee: Massachusetts institute of Technology i Facility: MIT Research Reactor Location: 138 Albany Street Cambridge, Massachusetts ,

Dates: September 16-20,1996 Inspector: Thomas F. Dragoun, Project Scientist Approved by: John R. White, Chief, Radiation Safety Branch Division of Reactor Safety 9610240242 961005 PDR ADOCK 05000020 0 PM _

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EXECUTIVE SUMMARY i i

Massachusetts Institute of Technology Report No. 'A-20/96-02 .

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Emphasis on maintenance and training after the departure of several staff members has  !

resulted in improved program performanc !

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Report Details Summarv of Plant Status The reactor was operated continuously at full power during the week except for Tuesday night swing shift. At that time, a shutdown occurred for troubleshooting and repairs after No.6 shim blade magnet current pegged high. Orientation tours for physics students were conducte Conduct of Operations 01.1 Oraanization and Operations and Maintenance Activities Inspection Scope (Insoection Procedure 39745)

The inspector reviewed:

  • organization and staffing, e administrative controls, and
  • the console log and the job workbook Observations and Findinas Since the last inspection in July 1995, three senior supervisors and the lead j c'ectronics technician departed. All positions were refilled quickly. In addition, the Nuclear Reactor Laboratory Director (Prof. Harling) announced he would retire at the end of September 1996. The Reactor Operations Director will act in this position '

until it is filled interviews and observations by the inspector indicated that the new appointees were well qualified and motivated, in particular, the electronics maintenance function was assigned to a senior reactor operator who corrected long standing equipment problems that lead to violations of the TS last year. One additional operator was assigned to help reduce the repair backlog. The electronics shop was cleared of clutter and additional benchtop instruments ordere Use of a published weekly operations schedule and a daily " white board" schedule updated in grease-pencil demonstrated good planning and work coordinatio Logs were clear and descriptive. Data records indicated that the facility was operated within parameters specified in the TS. Equipment malfunctions and abnormalities were clearly identified and copied to the job workbook for action. The I Assistant Superintendent of Operations reviews and initials each page of the console lo Good safety-consciousness was involved in the decision to quickly shutdown the reactor after shim blade #6 magnet current pegged high. Good teamwork was demonstrated during the trouble-shooting and repair, which took about three hour The reactor was returned to full power before the erd of the shif I i

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2 Conclusions Staffing requirements in TS 7.0 were satisfied. Record keeping was goo Electronics maintenance has improved.

O2 Operational Status of Facilities and Equipment

O2.1 Surveillance

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Insoection Scope (Inspection Procedure 61745)

The inspector reviewed:

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e limiting conditions of operation, and e observed performance of a surveillance i Observations and Findinas j Surveillances were found to be complete in accordance with monthly schedules

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contained in procedure PM 7.3.1. Picoammeter channel #3, which had not passed the loss-of-signal scram test during the last NRC inspection, has been repaired.

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Equipment malfunctions or abnormalities found during surveillances were well

documented and followed-up by the Operations Superintendent until resolved.

I o Cone:lusions The safety equipment surveillances required by TS section 4.0 are completed as i require O3 Operations Procedures and Documentation J Insoection Scoce (Insocction Procedure 42745)

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The inspector reviewed:

l e operating procedures and updates, and e adherence to procedures Observations and Findinas

Documented safety reviews, as specified in 10 CFR 50.59, were completed for i each change to the operating procedures. The formalized approval process for
changes was followed in all cases. Records and interviews indicated that changes were reviewed by all reactor operators. Proper use of procedures was noted during a reactor shutdown and conduct of a surveillanc ,

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In a September 25,1995 letter responding to inspection 95-02, the licensee stated ;

that written guidance to operators for dealing with equipment malfunctions was written but not used because the equipment was repaired. This was verified by the ;

inspector. Inspector Follow item 95-02-01 is close c. Conclusions Use of facility procedures, and changes thereto, satisfied TS 7.8 requirement Operator Training and Qualification

a. inspection Scoce (Insoection Procedure 41745)

The inspector reviewed:

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  • active license status,
  • training records,
  • records of reactivity manipulations e medical examinations, and
  • written examinations b. Observations and Findinas

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The results of an NRC initiallicensing exams conducted the previous week were not available. However, early indications were that all candidates passed, demonstrating the effectiveness of the training progra Requalification status and medical evaluations were up to date for all staff. A new committee was created to oversee requalification progress, a function previously assigned to a single supervisor, when it was determined that the workload was excessive for one perso Several student operators were on staff and in training. This increased personnel resource provides a better opportunity for the perminent staff to upgrade programs and perform maintenance. Mentors were assigned to each trainee to assure proper focus and understanding of the nature and requirements of reactor operation c. Conclusions The requalification program satisfied the requirements in TS 7.4,10 CFR 55 and Appendix 13.C of the SA '

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07 Quality Assurance in Operations 07.1 Review and Audit and Desian Chanae Functions a. insoection Scoce (Inspection Procedure 40745)

The inspector reviewed:

  • MIT Reactor Safeguards Committee membership and minutes of meeting, e Annual independent audit and quarterly administrative audits, and e Peer audit b. Observations and Findinas in a letter forwarding inspection report 95-02, the NRC stated that the complexity of factors contributing to the operation of the reactor with one shim blade partially inserted indicated the need for a peer review of programs. On August 19-20,1996, two directors frotn other research reactor facilities conducted a peer review. A draft report concluded that corrective actions were appropriate for the 1995 equipment failures and provided five additional recommendations. The licensee's resolution of the finalized recommendations will be reviewed in a future inspectio In a related matter, after the 1995 event, the licensee stated that a safety analysis of operating with one blade partially inserted would be completed. The inspector reviewed a student doctoral thesis presented by the licensee that contained safety ,

analysis. However, only fully withdrawn blades were analyzed by this effort. This )

matter remains ope All required audits were completed on time and provided good insight for the I programs reviewe c. Conclusions Review and oversight functions required by TS 7.0 and licensee commitments were l satisfactorily complete P1 Conduct of EP Activities  !

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a. Scoce (Insoection Procedure 82745)

The inspector reviewed:

e changes to the emergency plan, e changes to implementing procedures, e facilities, equipment, and supplies, e exercises and drills, and e trainin j

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' Observations and Findinas The emergency plan and implementing procedures were revised to be more user friendly and provide operator aids. A review of the changes by the inspector indicated that appropriate guidance was followed. Implementation of the revision '

will occur after MITSRC approval, expected during the next scheduled meeting in October 1996.

The inspector accompanied a SRO and a trainee during the monthly inventory of emergency self contained breathing apparatus. The operational check technique used was effective and the number of units available exceeded the minimum i specified in the emergency plan. However, a review of records indicated that

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rnedical evaluations prior to respirator use and initial fit testing were not done since 1994. The RRPO stated that the MIT Industrial Hygiene Department provides these

services, and committed that arrangements would be made to assure that the j required qualifications and subsequent record update would be completed by October 30,1996. This matter will be reviewed in a future inspection (Inspector l

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Follow Item 96-02-01).

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Records of the annual drill and training were satisfactor Conclusions The emergency plan was acceptably implemented, l

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V. Manaaement Meetina X Exit Meeting Summary (Inspection Procedure 30703)  !

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The inspector presented the inspection results to members of licensee management at the conclusion of the inspection on September 20,1996. The licensee acknowledged the l findings presente l PARTIAL LIST OF PERSONS CONTACTED i

Licensee ,

l J. Bernard, Director of Reactor Operations l T. Date, Assistant Reactor Radiation Protection Officer '

E. Lau, Assistant Operations Superintendent j F. McWilliams, Reactor Radiation Protection Officer (RRPO)

J T. Newton, Assistant Operations Superintendent j i

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i 6 INSPECTION PROCEDURES USED  ;

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! IP 30703: ENTRANCE AND EXIT INTERVIEWS i

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

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MAINTENANCE ACTIVITIES

! l l lP 40745: CLASS l NON-POWER REACTOR REVIEW AND AUDIT AND DESIGN

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CHANGE FUNCTIONS j i >

l iP 41745: CLASS I NON-POWER REACTOR OPERATOR LICENSES, REQUALIFICATION, l AND MEDICAL ACTIVITIES i 1

! IP 42745: CLASS I NON-POWER REACTOR PROCEDURES i

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IP 61745: CLASS I NON-POWER REACTOR SURVElLLANCE i

IP 82745: CLASS I NON-POWER REACTOR EMERGENCY PREPAREDNESS .'

ITEMS OPENED, CLOSED, AND DISCUSSED ,

Ooened 50-20/96-02-01 IFl Annual medical evaluation of respirator users and ,

initial fit testing to be brought up to date by I October 30,1996, i

Closed  ;

50-20/95-02-01 IFl Written guidance to be provided to reactor operator for dealing with equipment malfunctions until repairs :

can be mad ;

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LIST OF ACRONYMS USED CFR Code of Federal Regulations IFl Inspector Follow item .

MITRSC MIT Reactor Safeguards Committee  !

NRC Nuclear Regulatory Commission RRPO Reactor Radiation Protection Officer SAR Safety Analysis Report SRO Senior reactor operator TS Technical Specifications

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