1CAN069804, Submits Results of Pilot Plant Application Study Performed at Unit 1 for NRC Review.Submittal Provides Pilot Application Based on ASME Code Case N-560.Calculations NSD-024 & EPRI-116-310 & Rept SIR-98-055,encl

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Submits Results of Pilot Plant Application Study Performed at Unit 1 for NRC Review.Submittal Provides Pilot Application Based on ASME Code Case N-560.Calculations NSD-024 & EPRI-116-310 & Rept SIR-98-055,encl
ML20248J873
Person / Time
Site: Arkansas Nuclear Entergy icon.png
Issue date: 06/03/1998
From: James D
ENTERGY OPERATIONS, INC.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20248J876 List:
References
1CAN069804, 1CAN69804, NUDOCS 9806090341
Download: ML20248J873 (3)


Text

?

l y Entergy operations,Inc. '

y 1448 SA 333 ResdMie, AR 72801 Tel501858 5000 June 3,1998 1CAN069804 U. S.' Nuclear Regulatoy Commission Document Control Desk '

Mail Station OPI-17 Washington, DC 20555

Subject:

Arkansas Nuclear One - Unit 1 Docket No. 50-313 License No. DPR-51 1 Risk Informed Inservice Inspection Pilot Plant Submittal

(

Gentlemen As indicated in a letter from the Nuclear Energy Institute to the NRC dated August 29, 1997, entitled " Risk Informed Inservice Inspection Industry Submittals," Entergy Operations is submitting the results'of the pilot plant application study performed at Arkansas Nuclear One, Unit 1 (ANO-1), for NRC review. ANO-1 is the only risk informed inservice inspection (ISI) pilot plant proposed which utilizes a Babcock and Wilcox design.

This submittal provides a pilot application based on ASME Code Case N-560. The y application provides for an alternative to the 1992 Edition of the ASME Section XI j inspection requirements for Class 1, Category B-J piping welds (excluding socket welds) contained in Table IWB-2500-1. In general, the risk analysis was performed consistent with the requirements of Code Case N-560. However, as is the nature of a pilot plant application, some' methodology ==k==*s were implemented during the course of the evaluation. The enhancements are diam ==A in the attached documents I

The following documents support the ANO-1 risk informed ISI application for the reactor coolant, makeup and purification, and decay heat removal systems:

e Calculation No. NSD-024, " Consequence Evaluation for ANO-1," Rev. O, prepared by Duke Fapaaaring and Services (formerly Yankee Atomic) b e Calculation No. EPRI-116-310, " Degradation Mechanisms Evaluation for ANO-1,"  !

Rev. O, prepared by Structural Integrity Associates i hD T 9806090341 990603 i PDR ADOCK 05000313 O PDR 3

U. S. NRC June 3,1998 1CAN069804 Page 2 e

Report No. SIR-98-055, " Risk Evaluation and Element Selection in Support of ASME Code Case N-560 for Arkansas Nuclear One - Unit 1," Rev. O, prepared by Structural Integrity Associates These documents (attached) support the conclusion that the proposed alternative provides an acceptable level of quality and safety as required by 10CFR50.55a(aX3Xi).

Entergy Operations requests prompt review of this alternative. Approval is requested prior to July 1999, to allow sufficient time for Entergy Operations to revise the ANO-1 ISI program to implement the risk informed approach for the fifteenth refueling outage, scheduled for the fall of1999.

Should you have any questions, please contact me.

Very trul ours ScM' A

Dale E. J es Acting Director, Nuclear Safety DEJ/jjd attachments cc: Mr. Ellis W. Merschoff Regional Administrator U. S. Nuclear Regulatory Commission RegionIV 611 Ryan Plaza Drive, Suite 400 Arlington TX 76011-8064 s

NRC Senior Resident Inspector Arkansas Nuclear One P.O. Box 310 London, AR 72847 Mr. William D. Reckley NRR Project Manager Region IV/ANO-1 & 2 U. S. Nuclear Regulatory Commission NRR Mail Stop 13-H-3 One White Flint North 11555 Rockville Pike Rockville, MD 20852

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