IR 05000193/1988003

Insp Rept 50-193/88-03 on 880826.No Emergency Preparedness Violations Identified.Major Areas Inspected:Emergency Preparedness

ML20154S375
Person / Time
Site:	Rhode Island Atomic Energy Commission
Issue date:	09/27/1988
From:	Amato C, Lazarus W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
Shared Package
ML20154S360	List: IR 05000193/1988003 ML20154S357
References
50-193-88-03, 50-193-88-3, NUDOCS 8810050056
Download: ML20154S375 (4)

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U.S. NUCLEAR REGULATORY COMMISSION

REGION I

Report N /88-03 Docket N License N R-95 Licensee: Rhode Island Atomic Energy Commission 2 Facility: Nuclear Science Center Location: Narr_ajansett Bay Campu_s, Rhode_ Island University of Rhode~ Island

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harragansett, Rhode lsland Inspection Conducted: August 26, 1988 Inspector: __ WW C. G4Kmato(Amergency PrepWedness 9/date Spccialist, EPS, FRSTB, DRSS

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Approved by: xW #?!PT f date La: rus, Chief, Emergen.y Preparedness Section, FRSSB, DRSS j Inspection Summary: Inspection on August 26, 1983 (Report _No. 50-193/88-03]

l Areas Inspected: Routine, announced, safety inspection in the area of i

emergency preparednes Results: No errergency preparedness violations were identified. Nine unresolved items were identified, two in emergency preparedness and seven in non-emergency preparedness area t e

G810050056 880928 DR ADOCK0500g3

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. t DETAILS i 1.0 Persons Contacted l The following personnel attended the entrance and exit meetin .

A. DiMeglio, Director l M. Doyle Assistant Director  !

D. Johnson, Health Physicist l

2.0 The Facility 2.1 The Rhode Island Atomic Energy Commission Nuclear Science Centers i Reactor is a 2 K4 open pool reactor fueled with highly enriched I uranium and housed within a a concrete building. While it is located on the Narragansett Bay Campus of the University of Rhode Island, it '

is not a component of the University, it does not support academic programs and is dedicated to research. The Licensee is an agency of the State Government of Rhode Island. The reactor operates on a one shift per per day basi The staff numbers 12; this number includes clerical and custodial members. The Health Physicist serves the University and gives about half time to reactor activitie The Assistant Director is a licensed Senior Reactor Operator and a Health '

Physicis Irradiation facilities include two beam tubes, a thermal column, and a pneumatic, sample dispatch system called a rabbi .0 The Emergency Plan and Procedure 3.1 The Emergency Plan and Implementing Procedures were un-dated April, 1987. They are well written and meet the guidance of Regulatory Guide 2.6 and ANSI 15.16. Each of the items in the Regulatory Guide

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is addressvd. Seven Implementing Procedures have been developed; Table 1.1 of Procedure 1 is a detailed Emergency Event Classification Matrix which encompasses both events and symptoms. Both operating and after operation hour conditions are considered. A detailed i decontamination procedure protocol is included as is a Security Pla Section 8.5 of the plan describes emergency notifications but does not specify the time sequence or priorit The Licensee agreed to review and correct this ite (50-193/88-13-01) l 4.0 Emergency Facilities and Equipment 4.1 Emergency facilities and equipment when checked by the inspector were found to be in accordance with the Plan description. However, the following items were noted which require correction by the License __

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a.) The emergency phone list in the control room wa andated and not readily visible. The Licensee agreed to up-oete the list, place it under quarterly surveillance and within a transparent envelope secured in a position clearly visible to the operato Additional copies of the list would be distributed on an as need basis, b.) The emergency equipment locker is located in the assembly area which is adjacent to the Campus Security office in the Horn building. The locker, marked "radioactive materials", was located in a non-controlled area and it did not contain radioactive materials. The Licensee undertook immediate corrective action, c.) The battery operated air sampler was not maintained on battery charge t.nd did not function. There was no proximate AC outlet to which the battery could be connected. The Licensee will arrange to run an AC line to this cabine These items will be subject to a future inspectio (50-193/88-03-02)

5.0 Plan Review 5.1 The reactor Utili:ation Committee is a reactor safety committee which meets annually. The last meeting took place November 23, 198 The Ccmmittee reviewed the Plan and Procedures and reported favorably. Per Section 10.4 of the Plan, the Director also reviews the Plan and Procedure .0 Training 6.1 Training is conducted in accordance with Section 10 of the Pla Training includes exercises and exercise critique. Six exercises have been held since 1936. Formal documentation of training is in order, 7.0 Off-Site Activities Letters of Agreement are in place. Fire, Police, ambulance and hospital support arrangements are in plac .0 Licensee Response to Emeroency Appraisal Items S.1 The NRC identified fif teen items during a 1984 Emergency Appraisal, The Licensee responded to these positively in letter to the Director, Division of Radiation Safety and Sr.feguards, NRC Region 1 dated February 7,1935. Based on a review and follow up of this letter, the inspector concluded that with the exception of item 50-193/34-02-07, the licensee's actions have closed all items except item 07 which remains open pending review of data demonstrating sampling is isokinetic in region of laminar flo _ _ _ _ _ _ _ _ _ _ _ _ _

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l 9.0 Non-Emergency Preparedness Observations During a tour of the facility the following items were observe I l

9.1 There is evidence of rain seepage into the containment (which is  ;

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operated at negative pressure.) This may be indicative of l unacceptable containment leakag (50-193/88-03-03)  !

9.2 A wooden plank had been placed across the top of the pool in front  ;

of the reactor. Operators walk out on the plank to manipulate fue !

This is apparently an on going practice and is done to facilitate  ;

fuel manipulation but may be indicative of a need to modify j hardware or procedure (50-193/88-03-04). '

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! 9.3 The reactor bridge railing facing the pool is not in plac i (50-193/88-03-05)

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9.4 An electrical element within the reactor control console over-heated  !

and smoked on the night of August 25, 198S. There may have been an '

unwanted, small upward displacement of a control blade adding reactivit Discussion with operators indicated that this may have happened on more than one occasion. (50-193/8S-03-06)  !

l 9.5 Both personnel containment doors are allowed to be simultaneously [

open during reactor operation. A Licensee staff trember indicated -

that this was acceptable as long as another person was presen !

! (50-193/S3-03-07) l

! i 9.6 One Senior Reactor Operator License posted was dated 1985. The i i inspector was told the individual had been eaamined in 1935 and t i passed but this license had not been received from this NR '

(50-193/83-03-03)

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l 9.7 Another operator left the employ of the RI AEC but apparently [

neither he nor the employer advised the NRC of this to allow >

l cancellation of this license. (50-193/SS-03-09) i t

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These items are unresolved and will be further evaluated in an upcoming inspection.

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10.0 Exit Meeting

! 10.1 The inspector met with the personnel identified in Section 1 of this

) of this report and advised them no violations were identified.

, The unresolved itens were not noted. At no time during the course

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of this inspection, did the inspector give the Licensee written material.

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