ML20210N789

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Ro:On 990802,licensed RSO Was Not Readily Available During Operation of Reactor IAW TS 6.1.5.Caused by SRO on Duty Leaving Site Boundary & Not Informing RO in Reactor Cr. Licensee Will Initiate Two Administrative Procedure Changes
ML20210N789
Person / Time
Site: University of Lowell
Issue date: 08/03/1999
From: Bobek L
MASSACHUSETTS, UNIV. OF, LOWELL, MA (FORMERLY LOWELL
To: Dragoun T
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
References
NUDOCS 9908110215
Download: ML20210N789 (2)


Text

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1 Leo Bobek

-- University ofMassachusetts Lowell

  • ReactorSupervisor One University Avenue I ' \ l \' I v - t l ) <'f PinanskiHall107A Lowell, Massachusetts 01834 qs~8 \. ts> >n3, tel. 978-934-3363

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LOWett RADIATION LABORATORY August 03,1999

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USNRC Document Control Desk Washington, D.C. 20555 And Mr. Thomas Dragoun USNRC RGN-I DRS 475 AllendaleRoad King of Prussia, PA 19406-1415 Re: Facility Docket Number 50-223, Facility License Number R-125

Dear Mr. Dragoun:

This letter is being submitted as required under the University of Massachusetts Research Reactor (UMLRR) Technical Specifications, Section 6.6 for reporting Unusual Events within 30 days.

For approximately 35 minutes on August 2,1999, the UMLRR was out of compliance with UMLRR Technical Specification 6.1.5. This specification requires that a licensed senior reactor operator (SRO) be readily available on call whenever the reactor is in operation.

DESCRIPTION On August 2,1999, UMLRR staffinitiated a routine surveillance procedure for reactivity calibration of the reactor control blades. Reactor operation for the surveillance began at 9:01 a.m.

To determine control blade reactivity, the surveillance requires repeated measurements of reactor period as a function of blade position and is performed at a sufficiently low power to minimize l

temperature etTects. The measurements proceeded throughout the day. At approximately 4:15 i

p.m., the senior reactor operator on duty left the site boundary having not informed the reactor l operator (RO) in the reactor control room. At that time, there were two licensed reactor operators l

f in the facility. At approximately 4:45 p.m., the reactor operator ca; led the SRO's office telephone extension to check when the SRO would be leaving for the day. When there was no answer at the extension, the second RO made a cursory inspection of the reactor containment building and adjacent office building to determine if the SRO on duty or another SRO was present. Having not g found either, the RO reported this to the control room RO who then commenced immediate reactor shutdown at 4:51 p.m.

CORRECTIVE ACTION

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While thcie was no safety significance associated with this unusual event, this variance in the '

performance specifications for personnel requirements under the UMLRR technical specifications reverls a weakness in administrative controls designed to limit such unusual events.

< 1 r A ll A 9908110215 990803 PDR ADOCK 05000223 g PDR

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4 T. Dragoun ,USNRC August 3,1999 Page 2 of 2 As a result, the following corrective action will be implemented. in addition to supplemental training on technical specification administrative requirements and the necessary adherence to licensed responsibilities, the UMLRR will initiate two administrative procedural changes. One change will require the SRO on duty to be equipped with a personal electronic communications device. This change will increase assurance that the SRO is aware of on duty status and will be readily available on call in accordance with the administrative requirements of the technical specifications. A second change will require the SRO to record an estimated operations shutdown time and the communications call number on the pre-operational instruction form currently in use.

For further information or questions concerning this matter, please contact me at the above telephone numi>er.

Sincerely, L M. Bobek, f

.c Reactor Supervisor Cc: UML Reactor Safety Subcommittee Mr. Ronald Tooker, Chief Reactor Operator

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