IR 05000020/1997202

Insp Rept 50-020/97-202 on 971118-21.No Violations Noted. Major Areas Inspected:Organization & Operations & Maint Activities,Procedures & Documentation,Review & Audit & Design Change Functions & Emergency Preparedness

ML20198N080
Person / Time
Site:	MIT Nuclear Research Reactor
Issue date:	01/09/1998
From:	Weiss S NRC (Affiliation Not Assigned)
To:
Shared Package
ML20198N078	List: IR 05000020/1997202 ML20198N073
References
50-020-97-202, 50-20-97-202, NUDOCS 9801200248
Download: ML20198N080 (6)

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U. S. NUCLEAR REGULATORY COMMISSION Docket No: 50-20

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' License No: R 37

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Report No: 50-20/97202 Ucensee: Massachusetts institute of Techriology -

Facility: MIT Research Reactor _

Location: 138 Albany Street Cambridge, Massa husetts Dates:' November 18-21,1997

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Inspector: Thomas F. Dragoun, Reactor inspector Approved by: Seymour H. Weiss, Director ,

Non Power Reactors and Decommissioning Project Directorate

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._ Modifications to support insta:lation of the fission converter were properly planned and

coordinated. Improvements in operating procedures and safety system drawings were

. notable. Implemontation of the revised Emergency Plan was well underway.

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Flaport Details Summsr/ of Plant Status The reactor was operated continuously at full power. The staff indicated that MIT management had accepted a DOE grant to continue BNCT trials and approved reector operations for another four years, reticensing of the reactor, installation of a fission conysrter, and taplacement of the cooling tower with a larger capacity unit. Removal of a helium system that supported the magnetics laboratory was underway. Preparations were completed for relocation of the reactor makeup water tank to make room for the fission cor verter. A full size wooden mockup of the fission converter had been f abricated and placed in the reactor containment building. A new frisker with a large area cas-flow detector was installed at the containment building exit. This device has increased beta-gamma sensitivity and the capability of detecting alpha particle Organization and Operations and Maintenance Activ! ties inspection '. scope (Inspection Procedure 39745)

The inspector reviewed:

• organization and staffing, e the annual report, e shift staffing, ar d

• logs and significant problem Observations and Findings The inspector observed the weekly coordination meeting between the reactor superintendents, the RRPO, and Assistant RRFO. The operations sc;1edule, reactor tour schedule, major maintenance, and modification work were reviewed to ensure acceptable pre job review and provisions for technician coverage by the radiation protection department. Tt.e discussion included elements of the upcoming major outage for disassembly and removal of the thermal column. Close cooperation was demonstrate During an inspection in 1996, a significant loss of supervisory staff was noted. No further lossec have occurred. Staff performance and ;norale appeared to be very high as demonstrated by the niany accomplishments listed in the annual report and interviews by the inspecto A significant effort was noted to dig;tize (scan) the reactor safety system P&lD, make updates with CAD software, and print drawings for staff use. To accomplish this, a new computer and large plotter were purchased and sccnning equipment was borrowed. The senior operator in charge of the project stated that piping systems were walked down to verify the update .

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The crew schedule for reactor operations on weekends and back shifts were fully manned. The superintendent indicated that obtaining volunteers for these shifts and holidays was not difficult due to incentives and high moral The number of spurious scrams caused by glitches in the nuclear instrumentation channels was below previous levels but still notable. Replacernent Ni channel hardware (Gamma Metrics) was on site but installation had been delayed. Th. Director stated that additional engineering assistance would be sought for this projec Conclusions Staffing requirements in TS 7.0 were satisfied. Operatior.el and maintenanct. activities were well coordinated and ensured consistency with regul. story requirement Procedures and Documentation Inspection ScoLa (Inspection Procedure 42745!

The inspector reviewed:

e operatin0 procedure updates, and e administrative control of procedures, Observations and Findings Since the last inspection,32 operating procedures were updated, the reactor systems manual was revised and reissued, and software for estimating reactivity of xenon af ter shutdown and calculation of critical blade position for reactor startup were revise Safety reviews for selected updates indicated that the review includ 'J an assessment required by 10 CFR 50.59. and impact on the operator requalification program, t.ecurity plan, and emergency plan. Drafts of revisions indicated broad-based participation by the operating staff during the revision process. Alllicensed personnel also initiated 3 checkoff list after reviewing the final procedure and its safety revie Conc!usions Changes to procedures satisfied requirements in TS 7.8 and 10 CFR 50.5 Review and Audit and Design Change Functio s

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i 3 inspection Scope (Inspection Procedure 40745)

The inspector reviewed:

• Annual independent audit, and

• Quarterly administrative audit Observations and Findings The annualindependent audit did not report any weaknesses and found commendable improvements in several creas. Quarterly administrative audits were completed on schedule by the Quality Assurance supervisor. The audit reports were thorough and detailed. Audit findings were reviewed and initiated by the reactor operators, Cor.clusions Rev!ew and oversight functions required by TS 7.0 were acceptably complete Emergeracy Preparedness Scope (Inspection Procedure 82745)

The inspector reviewed implementatio.. of the revised emergency plan, including:

e training, e facilities, equipment, and supplies, and e exercises and drill Observations and Findings A revised Emergency Plan was issued on April 30,1997. Records indicated that training and 16 sting of reactor operators was complete. Non-liceased employees and experimenters were briefed by the RRPO. Supervisors of the Campus Police and Cambridge Department of Emergency Planning were briefod on the changes and arrangements made for training their staff Capabilities of the Emergency Support Center, as described in section 4.8.1 of the Plan, were verified by the inspector. Remote monitoring and sciam capability from the utility room, as described in section 4.8.2.4, were also verifie The medical drill, radiological emergency exercise, and building evacuation drill each have a separate written procedure for conuuct of the drill. Records indicated that the drills were conducted at the required frequency, scenarios were realistic, critiques were effective and were reviewed by the reactor operator ____- _ __- - _ _ _ _

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Building evacuation lights and horns (speakers) were found at the locations designated in the Plan. Lockers containing emergency equipment wers inventoried and restocked quarterly as required. Supplies appeared to be as required. Three new SCBA complete replacement units were delivered during this inspection. The NIOSH certification of these units was verified, Conclusions The revised emergency plan was effectively implemente Fuel Movement Scope (Inspection Procedure 60745)

The inspector reviewed:

o control of fuelloading, and e conformance with TS limit Observations ano Findings Control of fuelloading and shuMiing of the reactor core for the most recent configuration ( #131 ) was reviewed. Need for refueling was decided by the Assistant Operations Superintendent based on a requirement to override peak xenon effects, particularly during boron capture therapy trials. Another consideration was the TS lin. <

on element burnup since elements are flipped and rotated to achieve maximum burnu The proposed refueling plan required concurrence from both Superintendents and a SRO and demonstrated a comprehensive quality assurance practice. The same personnel later verity the final configuration. Diagrams and instructions for the fuel movement were clear. Calculations of excess reactivity and shutdown margin were performed and verified. Requirements in TS 3.9 and 3.11 were satisfie Conclusions Administrative control of fuelloading was acceptabl X1. Exit Meeting Summary (Inspection Procedure 30703)

The inspector presented the inspection results to members of licensee managamant at the conclusion of the inspection on November 21,1997. The "censee acknowledged the findings presente !

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PARTIAL LIST OF PERSONS CONTACTED J. Bernard, Director of Reactor Operations

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

T. Newton, Assistant Operations Superinter. dent S. Tucker, Quality Assurance Supervisor INSPECTION PROCEDURES USED IP 30703: ENTRANCE AND EXIT INTEiNIEWS IP 39745: CLASS i NON-POWER REACTORS ORGANIZATION AND OPERATIONS AND MAINTENANCE ACTIVITIES IP 40745: CLASS I NON POWER REACTOR REVIEW AND AUDIT AND DESIGN OHANGE FUNCTIONS IP 42745: CLASS I NON-POWER REACTOR PROCEDURES IP 60745: CLASS I NON-POWER REACTOR FUEL MOVEMENT IP 82745: CLASS I NON-POWER REACTOR EMERGENCY PREPAREDNESS ITEMS OPENED, CLOSED, AND DISCUSSED Opened none

. Closed none LIST OF ACRONYMS USED BNCT- Boron neutron capture therapy CFR Code of Federal Regulation NIOSH National Institute of Occupational Safety and Health NRC Nuclear Regulatory Commission RRPO Reactor Radiation Protection Officer SCBA 'Self contained breathing apparatus SRO Senior reactor onerator TS . Technical Specifications

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