ML20091A955

Responds to NRC Re Violations Noted in IE Insp Rept 50-160/84-01.Corrective Actions:Procedure 7202 Revised to Incorporate Instrument Setup Instructions & Procedure 4000 Revised to Include Containment Bldg Test Steps

ML20091A955
Person / Time
Site:	Neely Research Reactor
Issue date:	04/26/1984
From:	Karam R Neely Research Reactor, ATLANTA, GA
To:	Verrelli D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML20091A948	List: ML20091A955 ML20091A957 ML20091A991
References
NUDOCS 8405300138
Download: ML20091A955 (2)

Text

e Georgia Institute of Technology R"" SCHOOL OF NUCLEAR ENGINEERING AND HEALTH PHYSICS ATLANTA, GECAGIA 30332 .

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NEELY NUCLEAR AESEARCH (404)894-3600 CENTEA April 26, 1984 U.S. Nuclear Regulatory Commission, Region II ATrN: Mr. David M. Verrelli, Chief Project Branch 1 101 Marietta Street, N.W.

Atlanta, Georgia 30303

Subject:

Inspection Report 50-160/84-01 Gentlemen:

This letter is our response to the referenced inspection report of the Georgia tech Research Reactor on March 13-15, 1984.

Item Inadequate procedures 7202 " Control Rod Drop Time" and 4000, " Containment Building Pressure Test."

Note: The inspection report incorrectly identified the Control Rod Drop Time procedure as Nq. 7207 It is actually No. 7202.

The initial draf t of procedure 7202 omitted the detailed instrument set-up instructions to avoid reference to a specific instrument of a specific trade label (in this case a Hewlett Packard Universal Timer, Model 53258) . We have revised Procedure 7202 (copy enclosed) so that it now incorporates those instructions.

Our experience in performing the complicated steps involved in the Containment Building pressure test led us to make occasional pen and ink changes to the procedure in an effort to take into account many small details. Because of oversight, these changes were not incorporated into a revised, printed procedure. Procedure No. 4000 has now been revised (copy enclosed) to include these changes. Both procedures 7202 and 4000 will be reviewed by the Nuclear Safeguards Committee at their next scheduled meeting.

8405300138 840509 PDR ADOCK 05000160 PDR 0

A Unit of the University System t ; Georgia An Equal Education and Employment opportunity Institutx>n

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Item Nuclear Safeguards Committee Meeting frequency and distribution of minutes Prior to this inspection, our interpretation of the meeting requirements for the Nuclear Safcguards Committee was that there must be a minimum of four meetings a year, one in each calendar quarter.

The Cormlittee acknowledges the interpretation of the inspector. Further meetings of the Safeguard Committee will be scheduled in accordance with Technical Specifications requirement. Written records of such meetings will be distributed to all Committee members and to the President of Georgia Tech. The failure to send minutes of the Nuclear Safeguards Committee to the President was an inadvertent error.

The official distribution list for the Committee has been changed and includes the President.

Report Detail 10a Console Logbook All licensed reactor personnel have been requested (copy enclosed) to initial their logbook entries regardless of the reactor status.

Report Detail 12 AGN 201 Facility On April 16, 1984, the AGN-201 reactor vessel was opened and inspected by R.S. Kirkland, R.M. Boyd and L.D. McDow^11. The water was at normal level and a sample subsequently analyzed at the Nuclear Research Center did not show any radioactivity.

I hope that you will find our answers to the questions raised in the referenced report satisfactory. If you should need additional clarification or information, please do not hesitate to call.

Sincerely yours,

. a 9t&J.

R.A. Karam Interim Director Nuclear Research Center RAK/jlr

Enclosures:

Procedure 7202, Rev. dated 4/25/84 Procedure 4000, Rev. dated 4/19/84 Memo to McDowell, Davis, Downs and llendricks dated 4/26/84 pc: Members, Nuclear Safeguards Committee