ML20134N237

Notice of Violation from Insp on 850708-16

ML20134N237
Person / Time
Site:	Neely Research Reactor
Issue date:	08/21/1985
From:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20134N231	List: IR 05000160/1985002 ML20134N230 ML20134N237 ML20134N240
References
50-160-85-02, 50-160-85-2, NUDOCS 8509050047
Download: ML20134N237 (2)

Text

. .

. ~

ENCLOSURE 1 NOTICE OF VIOLATION Georgia Institute of Technology Docket No. 50-160 Research Reactor (GTRR) License No. R-97 The following violations were identified during an inspection conducted on July 8-16. 1985. The Severity Levels were assigned in accordance with the NRC Enforcement Policy (10 CFR Part 2, Appendix C).

1. Technical Specification (TS) 6.4.b. , requires that " written procedures shall be provided and utilized for the following . . . (7) Surveillance and testing requirements." This specification implies adequate procedures.

Contrary to the above, the following procedural problems were identified:

Procedure 2006, " Weekly Reactor Shutdown Checklist," does not require verification that the D2 0 level is actually <12 inches at the "D 20 Low Level" alarm point per TS 3.2.a, Table 3.1. This is an example of an inadequate procedure.

Procedure 7203, "ECCS - Monthly Surveillance," requires the operator to open valve 8 to drain reactor water level until a low level alarm is received. In actuality, the operators state that they open the valve and drain until they hear the Reactor Isolation Valves close. This is a failure to follow the procedure.

Procedure 7202, " Control Rod Drop Time," specifically requires a Hewlett Packard Universal Counter be set up and used to perform the timing. Because of component failure, May and June 1985 surveillances were completed _using an oscilloscope for this timing; however, no temporary change was made to the procedure. This is a failure to follow procedure.

This is a Severity Level IV violation (Supplement I).

2. Technical Specification 4.2.a references Table 4.1 and jointly requires the licensee to " Calibrate Semi-Annually (the) Reactor D 20 Level channels."

Contrary to the above, Licensee Procedure 7241, "LI-ul Check," designed to l meet this criteria, has been scheduled and performed on an annual basis  !

since 1978.

This is a Severity Level IV violation (Supplement I).

h5000

, Georgia Institute of Technology Docket No. 50-160 Research Reactor (GTRR) 2 License No. R-97

3. Technical Specification 6.5.b.6 requires the licensee to ". .

. retain [ ]

at the facility for life of the facility . .

. (6). Updated, corrected, and as-built facility drawings."

Contrary to the above, the inspector found numerous errors in the updated facility flow diagrams, including components that appear on drawings but are not actually installed in the facility, and piping system interconnec-tions that are not consistent with the drawings.

This is a Severity Level IV violation (Supplement I).

4. 10 CFR 50.54.1-1 requires that "...the licensee shall have in effect an operator requalification program which shall, as a minimum, meet the

requirements of Appendix A of Part 55 of this chapter," and that "...the licensee shall not... make a change.in an approved operator requalification program..." The licensee's NRC approved requalification program requires that_if an individual scores less than 80 percent in an area, he will receive. formal retraining- in that area.

Contrary to the above, a licensed operator failed a portion of his 1984 requalification' exam and a retraining program was not initiated for him as required by the licensee's August 5, 1984.NRC approved program.

This is a Severity Level IV violation (Supplement I).

5. Technical Specification . 6.2.c requires that "The [ Nuclear Safeguards]

Committee shall meet quarterly and as circumstances warrant."

Contrary to the above, after meeting on February 4, 1985, the licensee failed to meet again until June 13, 1985.

This is a Severity Level V violation (Supplement I).

Pursuant to 10 CFR 2.201, you are required to submit to this office within 30 days of the date of this Notice, a written statement or explanation in reply, including: (1) admission or denial of the alleged violations; (2) the reasons for the violations if admitted; (3) the corrective steps which have been taken and the results achieved; (4) corrective steps which will be .taken to avoid further violations; and (5) the date when full compliance will be achieved.

Security or safeguards information should be submitted as an enclosure to facilitate withholding _it from public disclosure as required by 10 CFR 2.790(d) or 10 CFR 73.21.

Date: AUG 211985

_-