IR 05000348/1979013

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IE Insp Rept 50-348/79-13 on 790327-30.No Noncompliance Noted.Major Areas Inspected:Refueling Activities
ML19270G816
Person / Time
Site: Farley Southern Nuclear icon.png
Issue date: 04/12/1979
From: Martin R, Vogtlowell R
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML19270G813 List:
References
50-348-79-13, NUDOCS 7906200359
Download: ML19270G816 (4)


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Report No. 50-348/79-13 Licensee: Alabama Power Company 600 North 18th Street Birmingham, Alabama 35202 Facility Name: Farley 1 Docket No. 50-348/79-13 License No. NPF-2 Inspection at Farley ite near Ashford, Alabama 4 it II Inspector:

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Date Signed R. J'. Vo.t-Low f//M Approved by: ~

KSS 1 Dat'e Signed R. D. Martin, Section Chi

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SUMMARY Inspection on March 27-30, 1979 Areas Inspected This routine, unannounced inspection involved 27 inspector-hours onsite in the area of refueling activities.

Results

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In the area inspected, no apparent items of noncompliance or deviations were identified. One unresolved item was identified relative to the annual requirement for performance of a crack detecting inspection of the main polar crane hook (79-13-01).

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DETAILS 1.

Persons Contacted Licensee Employees W. G. Hairston, Plant Manager

  • J. Woodard, Assistant Plant Manager
  • K. W. McCracken, Technical Superintendent
  • W. Shipman, Maintenance Superintendent D. Morey, Maintenance Supervisor C. Nesbitt, Chemical and Health Physics Supervisor
  • R.

D. Hill, Plant QA Engineer L. Emfinger, Document Control Supervisor R. Marlow, Reactor Engineer W. MacDonald, Plant Engineer

  • Attended exit interview.

2.

Exit Interview The inspection scope and findings were summarized on March 30, 1979 with those persons indicated in Paragraph 1 above.

3.

Licensee Action on Previous Inspection Findings Not inspecteds 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 paragraph 6.

5.

Refueling Activities a.

Refueling Reference Documents:

The following reference documents relating to the Cycle I to Cycle II refueling outage were reviewed by the inspector:

" Reload Safety Evaluation - J. M. Farley Nuclear Plant - Unit 1 -

Cycle II" - issued by the Westinghouse Nuclear Fuel Division in December 1978.

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" Westinghouse Reload Safety evaluation Methodology" -WCAP 9273, March 1978.

b.

Refueling Procedures The following plant procedures were reviewed by the inspector:

FNP-1-STP-41.1 Source Range Functional Check Channel N-31 (32).

(Including a review by the inspector of the data sheets associated with the execution of this procedure on 3/26-27/79).

FNP-1-STP-18.1 Containment Purge and Exhaust Isolation Test (Including a review of the data sheets associated with execution of this test on 3/25/79).

FNP-0-MP-11.1 Reactor Polar Crane Monthly Check (Including a review of the data sheets associated with the execution of this procedure on 3/10/79).

FNP-0-MP-11.2 Reactor Polar Crane Six Month Check (Including a review of the data sheet associated with the execution of this procedure on 3/10/79).

FNP-0-MP-11.3 Reactor Polar Crane Annual Check (For additional information see paragraph 6 of this report).

FNP-1-STP-36.0 Manipulator Crane Cutoff and Load Test (Including a review of the data sheets associated with the execution of this procedure on 3/25/79).

FP-ALA-R1 Refueling Procedure-The inspector reviewed the Official Test Copy of the Refueling Procedure which was kept in the Shift Supervisor's office in the main control room.

In particular, sections 9.2.12 and 9.2.13 relating to the refueling equipment checkout and operational demonstration were examined to ascertain signoff of the various procedural steps, as appropriate.

At the request of the inspector, the licensee initiated procedure change TCN-1G on 3/29/79 to include the contents of Technical Specifications paragraph 6.2.2.e under the specific responsi-bilities of the Alabama Power Ccmpany senior reactor operator (SRO) licensed Refueling Shift Supervisor.

Within the areas inspected no items of noncompliance or deviations were identified.

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-3-6.

Crack Detection Inspection of the Containment Polar Crane Hook During the review of FNP-0-MP-11.3, the inspector noted the requirement in paragraph 5.27 of the procedure for annual " magnetic particle or other suitable crack detecting inspection on the main hoist sister hook, and auxiliary hook".

The inspector requested documentary evidence of the hook inspection since at that time the crane had already been used for refueling activities which bv the requirements of paragraph 3.1 of FNP-0-MP-11.3 entailed prior performance of said hook inspection.

At the conclusion of the exit interview, the licensee indicated that they believed the hook inspection had indeed been performed but that they had so far been unsuccessful in contacting the individual from the

" Crane Inspection and Certification Bureau" whose responsibility, they felt, included a crack detection inspection of the book during his September 1978 crane inspection. The licensee agreed to notify the inspector once definitive information became available.

This matter remains unresolved (50-348/79-13-01).

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