1CAN069201, Forwards Rev 0 to SIR-92-037, ASME Code Case N-481, Evaluation of Arkansas Nuclear One Unit 1 Reactor Coolant Pumps. Rept Provides Results of VT-2 Exam & ASME Code Case N-481 Evaluation

Forwards Rev 0 to SIR-92-037, ASME Code Case N-481, Evaluation of Arkansas Nuclear One Unit 1 Reactor Coolant Pumps. Rept Provides Results of VT-2 Exam & ASME Code Case N-481 Evaluation

ML20097G081
Person / Time
Site:	Arkansas Nuclear
Issue date:	06/12/1992
From:	James Fisicaro ENTERGY OPERATIONS, INC.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20097G083	List: 1CAN069201, Forwards Rev 0 to SIR-92-037, ASME Code Case N-481, Evaluation of Arkansas Nuclear One Unit 1 Reactor Coolant Pumps. Rept Provides Results of VT-2 Exam & ASME Code Case N-481 Evaluation ML20097G085
References
1CAN069201, 1CAN69201, NUDOCS 9206160279
Download: ML20097G081 (3)

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.ec_c Ent :rgy .

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Operations June 12, 1992 1CAN069201 U. S. Nuclear Regulatory Commission Document Control Desk Mail Station P1-137 l Washington, DC 20555 j

Subject:

Arkansas Nuclear One - Unit I /

Docket No. 50-313 License No. DPR-51 '

Summary Report of the Code case N-481 Evaluation for All Four RCPs and Visual Inspection Results of the "D" Reactor l Coolant pump Gentlemen:

During the recently completed Arkansas Nuclear One, Unit 1 (ANO-1) refueling outage (1R10), the "D" reactor coolant pump (RCP) was disassembled. This disassembly was to inspect the RCP for damage due to potential mot.or thrust bearing failure and was not a planned outage evolution.

In letter dated March 26, 1992 (ICAN039211), information was submitted to the NRC to revise an Entergy operations commitment to perform single-wall radiography of the pump casing and instead conduct RCP casing structural integrity examinations and evaluations using the methodology contained in ASME Code Case N-481. In the March 26, 1992, letter Entergy Operations committed to submit a report. of the Code Case evaluation.

During a March 30, 1992, telephone conference call, the NRC requested the results of the VT-1 and VT-3 examination of the "D" RCP. Also requested was a comparative analysis between the Code Case postulated flaw evaluation and the "A" and "B" RCP previous fracture mechanics and stress analysis evaluations. This information was submitted to the NRC in our letter dated April 13, 1992 (ICAN049202).

The Code Case also requires that a VT-2 visual examination of tne exterior of all pumps be perfarmed during a hydrostatic pressure test.

Entergy Operations committed to perform this examination prior to returning ANO-1 to power operations.

The purpose of this submittal is to provide the results of the VT-2 examination and the ASME Code Case N-481 evaluation.

9206160279 920612 PDR P

ADOCK 05000313 PDR 1[ i i l

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. U. S. NRC June 12, 1992 '

page 2 4 l

Results of the VT-2 Examination ,

I A VT-2 examinat fon of the exterior surface of all four RCPs ("A", "B", l "C", and "D") was performed prior to returning the unit to power operations. No leaks waro identified during the examinations.

• Codo Caso N-481_ Evaluation i Attached in the summary report of the ovaluation for all four ANO-1 RCPn por the requirements of ASME Codo Case N-481. This report discusses the  :

results of previous examinations,-the background of the code caso, and  ;

the associated fracture mechanica evaluations. Based on these '

evaluations, it was concluded that the ANO-1 RCp pump casings satisfy the  !

safety.and serviceability requirements of the code case.

As stated in our lettor_ dated March 26, 1992 (ICANO39211), Entergy Operations changed its augmented inservice inspection commitment of performing single-wall radiography of RCP casing wolds in the event any t pump is completely disassembled for maintenance, repair or examination.

Our-present commitment is to c.onduct RCP caning structural integrity examinations and evaluations using the methodology contained in Code Case N-481. This letter completos our actions- regarding the structural ,

integrity examinations and evaluations.

Using the methodology contained in Code Case N-481 in lieu of single-wall radiography, Entergy Operations bolinves that the intent of the augmented innervice inspnction plan described in the NRC April 25, 1989, Safety Evaluation has been mot. Entergy Operations will continun to perform the remaining-portions of the augmonted plan described in the April 25, 1989, Safety Evaluation. Entergy. Operations Intends to apply this codo case to other RCP inspections for the remaining portion of the sncond 10-year inservice inspection interval for ANO-1.

Eight >pages of the report contain information that was previously submitted to the NRC as proprietary under letter dated October 27, 1988 (ICAN108805).- These eight pages have been noted as proprietary in the attached report and they will be submitted under a separate cover letter.

Should you have any questions regarding this issue, pleaso contact me.

Very truly yours, 42mv h5L4"*

James J. Fisicato Director, bicensing i

I JJF/RWC/s]f 1 Attachment i

1 i

i' l U. S. NRC ,

• • ' June 12, 1992 Page 3 cc Mr. Robert Martin U. S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive Suite 400 Arlington, TX 76011-8064 NRC Senior Resident inspector Arkansas Nuclear One - ANO-1 & 2

-Number 1. Nuclear Plant Road Russellville, AR 72801 Mr. Thomas W. Alexion NRR Project Manager, Region IV/ANO-1 U. S. Nuclear Regulatory Commission NRR Hail Stop 13-H-3 One White Flint North 11555 Rockville Pike Rockville, Maryland 20852

'Hs.! Sher! Peterson NRR Project Manager, Region IV/ANO-2 U. S. Nuclear Regulatory Commission

.NRR Mail Stop 13-H-3 One White Flint North 11555 Rockville Pike-Rockville, Maryland 20852 1

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