2CAN069901, Forwards Probabilistic Operational Assessment of ANO-2 SG Tubing for Cycle 14. Replacement of SGs Planned for Next Refueling Outage (2R14) Scheduled for Fall of 2000
| ML20195D176 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 06/02/1999 |
| From: | Vandergrift J ENTERGY OPERATIONS, INC. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20195D181 | List: |
| References | |
| 2CAN069901, 2CAN69901, NUDOCS 9906090095 | |
| Download: ML20195D176 (2) | |
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O Ent:rgy oper:tions,Inc.
.1448 3A 333 Redvine, AR 72801 Tel 501858-5000 June 2,1999 2CAN069901 U. S. Nuclear Regulatory Commission Dee Control Desk Mail Station OPI-17 Washington, DC 20555
Subject:
Arkansas Nuclear One - Unit 2 Docket No. 50-368 LicenseNo NPF-6 Operational Assessment of Steam Generator Tub'mg for Cycle 14 Gentlemen:
Entergy Operations has completed its operational assessment of steam generator tubing for the 14* operational cycle at Arkansas Nuclear One, Unit 2 (ANO-2).
The attached assessment, which utilizes criteria from both NEI 97-06, " Steam Generator Program Guidelines," and draA NRC regulatory guide DG-1074, " Steam Generator Tube Integrity,"
concludes that adequate margin exists to safely run ANO-2 until the planned midcycle I
inspection cunently scheduled for November 1999. The operational assessment for the first half of Cycle 14 is similar to those that have been performed and presented to the NRC for the last several cycles ofoperation. The prinwy diffe' rence in this assessment is the use of revised probability of detection (POD) curves based upon a site-speciSc performance demonstration program. The POD curve used to represent the last inspection also accounts for changes made in the disposition of bobbin coil indications at the eggerate supports. Also included in the assessment is consideration of the slightly elevated hot leg temperature being utilized for this cycle of operation. These changes further refine the probabilistic techniques previously utilized to provide a higher confidence in the final results.
i Cycle 14 is the last cycle of operation with the existing ANO-2 steam generators.
i Rghemment of the steam generators is planned for the next refueling outage (2R14) scheduled for the fall of 2000. Following the midcycle inspection, consistent with NEI 97-06, a condition monitoring assessment will be performed to verify the validity of the previous operational assessment. Any irregularities identified will be addressed in the subsequent operational assessment, t
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- U. S. NRC June 2,1999 2CAN069901 Page 2 We would be pleased to meet with the NRC staff to discuss the methodology, results, and implications of the assessment. Should you have questions concerning this submittal, please contact me.
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JDV/jd attachment cc:
Mr. Ellis W. Merschoff Regional Administrator U. S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-8064 NRC Senior Resident Inspector Arkansas Nuclear One P.O. Box 310 LW AR 72847 Mr. Chris Nolan NRR Project Manager Region IV/ANO-2 U. S. Nuclear Regulatory Commission NRR Mail Stop 13-D-18 One White Flint North 11555 Rockville Pike l
Rockville, MD 20852 l
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