ML20005F877

Responds to Violations Identified in Insp Rept 50-160/89-02. Corrective Actions:Procedure 4000 Revised & Being Reviewed Against Stds ANS 7.60 & Procedure 7247 Drafted to Cover Area & Is Undergoing Review

ML20005F877
Person / Time
Site:	Neely Research Reactor
Issue date:	01/06/1990
From:	Karam R Neely Research Reactor, ATLANTA, GA
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9001170346
Download: ML20005F877 (3)

Text

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I f '., Georgia institute of Technology i 1

i b NEELY NUCLEAR RESEAACH CENTER i

, t 900 ATLANTIC OAfVE i ATLANTA GEORGIA 30332-0425 ,

January 6, 1990  ;

l U. S. Nuclear Regulatory Commission l Washington, D. C. 20555  :

ATTENTION: DOCUMENT CONTROL DESK j SUBJECT Georgia Institute of Technology j License No. R-97, Docket No. 50-160  ;

REPLY TO A NOTICE OF VIOLATION, INSPECTION i REPORT NO. 50-160/89-02  ;

Gentlemen:  ;

Pursuant to 10 CFR 2.201, please find attached a response to violations identified in USNRC' Inspection Report No. 50-160/89-02, i

The deadline for receipt of this response was - extended to January 12, 1990, -in a telephone conversation between Mr. Ed

• McAlpine and Dr. Betty Revsin.  ;

If you have further questions,'please call me at (404) 894- -

3600.  ;

Sincerely, oe. . w -

L R. A.'Karam, Director >

Neely Nuclear Research Centar ,

' cc Mr. S. Ebneter, Regional Administrator U. S. Nuclear Regulatory Commission  ;

101 Marietta Street, N. W. .

Atlanta, GA 30323 i

900127o346 9oolo6 NI '

[*DR ADOCK 05000160 't I PDC Telsus 542507 GTRIOOAATL Fax: 404 894-3120(Venty 404 8944951)

A Unit of the University System of Georgia An t qual Educaten and Employment omwtonity inshtution ' !

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ATTACHMENT 1 GEORGIA INSTITUTE OF TECHNOLOGY REPLY TO A NOTICE OF VIOIATION INSPECTION REPORT NO. 50-160/89-02 VIOLATION 50-160/89-02-01. SEVERITY LEVEL IV fSUPPLEMENT 1)

Technical Specification 6.4.b.7 requires that surveillance and testing of safety related systems be conducted in accordance with procedures which have been appropriately reviewed and approved.

Further, the licensee's Safety Analysis Report, Section 7.7.2 states that the containment building integrated leak-rate test shall be conducted in accordance with the American Nuclear Standard 1ANS) 7.60, Leakage-Rate Testing of Containment Structures.

Contrary to the above, the containment building leak-rate test was not conducted in accordance with ANS 7.60 with regard to leakage test data analysis _and the conduct of the supplemental test for verifying the accuracy of the leakage test results.

REPLY

1. Admission or denial of the violation:

The Georgia Institute of Technology agrees with the violation as stated.

2. Reason for the violation:

Procedure 4000, Containment Building Pressure Test, approved by the Nuclear Safeguard Committee on 1/30/86 was deficient in that the procedure did not provide adequate guidance to the_ operator in the area of data handling and treatment.

3. Corrective steps that have been taken and results achieved:

Procedure 4000 has been revised and is currently being reviewed against Standard ANS 7.60 and other requirements

4. Corrective steps which will be taken to avoid further violations:

It is anticipated that an adequate procedure which meets the requirements of ANS 7.60 will, when completed, ensure that further violations in this area do not occur.

5. Date when full compliance will be achieved:

Full compliance will be achieved as of March 31, 1990.

,o e a

T VIOLATION S0-160/89-02-02, SEVERITY LEVEL IV fSUPPLEMENT I)

Technical Specification 3.1.d requires that any shim blade not full inserted be withdrawn sufficiently to assure a negative rate trip when released into the core. Technical Specification 6.4.b(1) requires that written procedures shall be provided and utilized for normal startup and operation of the reactor and of all systems and components involving the nuclear safety of the system.

Contrary to the above, the licensee had not provided procedures to assure that shim rods were always withdrawn to at least five degrees, which the licensee had determined experimentally to be the minimal withdrawal to assure a negative rate trip.

1 REPLY

1. Admission or denial of the violation:

The Georgia Institute of Technology agrees with the violation as stated.

2. Reason for the violation:

The Staff of the Neely Nuclear Research Center has been ,

involved in upgrading operating procedures on many fronts: Health Physics, Operations, Emergency Response, Environmental, Security, etc. Consequently, the procedure to assure that shim safety blades were always withdrawn to at least 5 degrees was overlooked.

3. Corrective steps which have been taken and the results achieved:

Procedure 7247 has been drafted to cover this area and is currently undergoing review.

4. Corrective steps which will be taken to avoid further violations:

The corrective action directed toward development of an adequate procedure which implements Technical Specification requiremento will, when completed, ensure that further violations in this area will not occur.

5. Date when full compliance will be achieved:

Full compliance will be achieved as of March 31, 1990.

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