IR 05000160/1980003

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IE Insp Rept 50-160/80-03 on 800826-28.No Noncompliance Noted.Major Areas Inspected:Nuclear Safeguards Committee Log & Record Review,Surveillance & Procedures
ML19340C245
Person / Time
Site: Neely Research Reactor
Issue date: 09/23/1980
From: Dance H, Julian C, Skinner P
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML19340C243 List:
References
50-160-80-03, 50-160-80-3, NUDOCS 8011140316
Download: ML19340C245 (4)


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'o UNITED STATES

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T,f, NUCLEAR REGULATORY COMMISSION

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REGION 11

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101 MARIETTA si., N.W.. sulTE 3100 J

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Report No. 50-160/80-03 Licensee: Georgia Institute of Technology

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i 225 North Avenue Atlanta, GA 30332 Facility Name: Gecrgia Institute of Technology Research Reactor (GTRR)

Docket No. 50-160 l

License No. R-97 Inspectors:

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C. Julian V

Date Signed L $% TOM AYb d P. Skiftner Date Signed Approved by:

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H.' C. Dance, Mection Chief, RONS Branch Date Signed SUMMARY Inspection on August 26-28, 1980 Areas Inspected This routine, unannounced inspection involved 52 inspector-hours on site in the areas of Nuclear Safeguards Committee activities, log and record review, surveil-lance, experiments, procedures and a facility tour.

Results Of the 5 areas inspected, no items of noncompliance or deviations were identified.

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DETAILS 1.

Persons Contacted Licensee Employees

  • L Veever, Director Nuclear Engineering
  • J.

Russell, Director Nuclear Research Center

  • R. S. Kirkland, Associate Director Nuclear Research Center, Reactor Supervisor
  • R. Boyd, Radiological Safety Officer L. D. McDowell, Reactor Shif t Supervisor

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S. Millspau, Health Physics Technician Other licer.see employees contacted included various technical and operatione personnel.

NRC

  • ll. Dance, RONS Section :hief
  • Attended exit. iden.e4 2.

Exit Interview

The inspection scope and findings were dk4sarized on August 28, 1980 with those persons indicated in Paragraph 1 above. Each unresolved item was i

discussed in some detail as described in the following paragraphs. The licensee representatives committed to resolve the items discussed.

3.

Licensee Action on Previous Inspection Findings a.

Closed:

Infraction (80-01-08) Failure to perform primary coolant pH measurement weekly. The inspector reviewed surveillance records and logs to determine if this requirement is being met and found no dis-crepancies in this area.

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Closed: Deficiency (80-01-12) Failure to make a timely submittal of an annual report covering the previous years operation.

The latest annual report was submitted on February 28, 1980.

4.

Unresolved Items Unresolved items are matters about which more information is required to determine whether they are acceptable or may involve noncompliance or deviations.

New unresolved items identified during this inspection are discussed in paragraphs 5 and 6.

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Surveillance Technical Specifications 6.4.b(7) requires written procedures be approved by the Nuclear Safeguards Committee (NSC) prior to being effective. The inspector reviewed the surveillance program and found that adequate proce-dures exist for surveillance testing in all areas with the exception of rod drop testing.

The rod drop procedure consists primarily of instructions as to how to set up the electronic timers and does not contain a step by step sequence for plant conditions and manipulations. Surveillance procedures are presently contained on index cards which do not reflect the review and approval of the NSC. The inspector stated that these procedures should be more formalized, detailed, and complete to meet the intent of the Technical Specifications.

i Subsequent to the inspection, on September 24, 1980 in a phone conversation between C. Julian and R. Kirkland, the licensee agreed to review and revise as necessary each surveillance procedure prior to its next use.

This is an unresolved item (160/80-03-01).

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Nuclear Safeguards Committee Reviews Technical Specification 6.6.C requires all " abnormal occurr nces" be reviewed e

by the Nuclear Safeguards Committee (NSC). The inspect.sr reviewed the NSC meeting minutes and past Licensee Event Reports (LE!.O and found LER-3 had not yet been reviewed by the NSC.

In addition, of the reactor operations audits that have been completed during 1980, as directed by the NSC, no documentation was available that indicates subsequent review by the NSC and action taken as a result of the audit findings.

This item (160/80-03-02) is an unresolved item pending further review during a future i.wpection.

7.

Facility Tour The inspectors toned the facility with the Reactor Supervisor and observed a reactor startup and reactor operations.

The Re.v cor Supervisor stated that since February 1980 the reactor has been opecated in Mode 1, i.e., at thermal powers less than or equal to one mega-vatt.

This restriction has been imposed by the licensee to meet Technical Specification 3.7.a which requires the D 0 Energency Coolant System to be

operable for operation above one megawatt.

The Emergency Core Coolant System was declared inoperable due to erratic flow indications observed during surveillance testing.

The licensee presently believes that the erra ic flow problem is not caused by a failure of the manual isolation valve as previously thought but rather is due to permanent deformation in the diaphragms of the parallel automatic

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ECCS initiation valves. The licensee stated that the two diaphragms had been replaced and that testing would continue to determine ECCS operability.

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During a plant tour the inspector observed that the old ECCS valve diaphragms h4d been left on a work bench in a passage way of the lower level of the containment. At the inspectors request, a contamination survey was made and the diaphragms and work bench were found to have low level contamination.

The licensee promptly corrected the situation. The inspector stated at the exit interview that -lthough this matter is not an item of noncompliance, the circumstances of this situation cause concern over the adequacy of the contamination control measures in force.

No deviations or items of noncompliance were identified in this area.

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Log and Record Review The inspector reviewed the operating log for the period March 3 through June 4, 1980. The unscheduled shutdown reports from March 3 through July 23, 1980 were examined.

No deviations or items of noncompliance were identified in this area.