1CAN051403, Unit 1, Reactor Vessel Internals Aging Management Program Plan

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Unit 1, Reactor Vessel Internals Aging Management Program Plan
ML14141A554
Person / Time
Site: Arkansas Nuclear Entergy icon.png
Issue date: 05/20/2014
From: Pyle S
Entergy Operations
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
1CAN051403, TAC ME0680
Download: ML14141A554 (2)


Text

Entergy Entergy Operations, Inc.

1448 S.R. 333 Russellville, AR 72802 Tel 479-858-4704 Stephenie L. Pyle Manager, Regulatory Assurance Arkansas Nuclear One 1CAN051403 May 20, 2014 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk 11555 Rockville Pike Rockville, MD 20852

SUBJECT:

Reactor Vessel Internals Aging Management Program Plan Arkansas Nuclear One - Unit 1 Docket No. 50-313 License No. DPR-51

REFERENCES:

1. Entergy letter dated January 31, 2000, "License Renewal Application,"

(1CAN010003) (ML003679667)

2. Materials Reliability Program: Pressurized Water Reactor Internals Inspection and Evaluation Guidelines (MRP-227-A) December 2011
3. NRC letter from Robert A. Nelson (NRC) to Neil Wilmshurst (EPRI) dated December 16, 2011, "Revision 1 to the Final Safety Evaluation of EPRI Report, Materials Reliability Program Report 1016596 (MRP-227),

Revision 0, "Pressurized Water Reactor (PWR) Internals Inspection and Evaluation Guidelines" (TAC No. ME0680)

Dear Sir or Madam:

By letter dated January 31, 2000 (Reference 1), Entergy Operations, Inc. (Entergy) submitted a License Renewal Application (LRA) for Arkansas Nuclear One, Unit 1 (ANO-1). In the LRA, Entergy made the following commitment related to reactor vessel internals aging management:

New Site Activity - Involves a new inspection program beginning after May 20, 2014, and continuing through year 60. Inspections may include volumetric examination of a sample of baffle bolts and visual examination of the reactor vessel internals. A report defining the inspection program will be provided to the NRC prior to May 20, 2014.

The purpose of this transmittal is to provide the ANO-1 Reactor Vessel Internals Aging Management Program Plan for review and approval. The program plan is attached.

1 CAN051403 Page 2 of 2 This plan identifies the internals components that must be included for aging management review and identifies the augmented inspection plan for the ANO-1 reactor vessel internals.

This plan implements the EPRI Materials Reliability Program: Pressurized Water Reactor Internals Inspection and Evaluation Guidelines (MRP-227-A) (Reference 2). This program was developed so that the aging effects of the reactor vessel internal components are adequately managed and provide reasonable assurance that the internals components will continue to perform their intended function through the period of extended operation.

Reference 3 provides Revision 1 of the Final Safety Evaluation of MRP-227A. As part of that evaluation, a number of action items and conditions were specified. Documented in Section 5 of the attached program plan is how ANO-1 conforms to those action items and conditions.

ANO-1 enters the period of extended operation on May 20, 2014.

This letter contains several new regulatory commitments. These commitments are listed in .

If you have any questions or require additional information, please contact me.

Sincerely, SLP/rwc

Attachment:

1. PWR Internals Aging Management Program Plan for Arkansas Nuclear One, Unit 1
2. List of Commitments cc: Mr. Marc L. Dapas Regional Administrator U. S. Nuclear Regulatory Commission, Region IV 1600 East Lamar Boulevard Arlington, TX 76011-4511 NRC Senior Resident Inspector Arkansas Nuclear One P.O. Box 310 London, AR 72847 U. S. Nuclear Regulatory Commission Attn: Mr. Peter Bamford MS O-8B3 One White Flint North 11555 Rockville Pike Rockville, MD 20852