1CAN100903, Supplemental to Response to Request for Information Regarding Steam Generator Tube Integrity During Break in Upper Hot Leg Piping

From kanterella
(Redirected from ML093010329)
Jump to navigation Jump to search

Supplemental to Response to Request for Information Regarding Steam Generator Tube Integrity During Break in Upper Hot Leg Piping
ML093010329
Person / Time
Site: Arkansas Nuclear Entergy icon.png
Issue date: 10/26/2009
From: Walsh K
Entergy Operations
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
1CAN100903, TAC MD7178
Download: ML093010329 (4)
v • d • e


Text

1CAN100903 October 26, 2009 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555

SUBJECT:

Supplemental to Response to Request for Information Regarding Steam Generator Tube Integrity During Break in Upper Hot Leg Piping Arkansas Nuclear One, Unit 1 Docket No. 50-313 License No. DPR-51

REFERENCES:

1.

NRC letter dated July 31, 2009, Arkansas Nuclear One, Unit No. 1 -

Individual Plant Actions Re: Pressurized-Water Reactor Owners Group Topical Report BAW-2374, Revision 2, Risk-Informed Steam Generator Tube Thermal Loads due to Breaks in Reactor Coolant System Upper Hot Let Large-Bore Piping (1CNA070901) (TAC No.

MD7178)

2.

Entergy letter dated August 14, 2008, Response to Request for Additional Information Regarding Technical Specification Changes and Analyses Relating to Use of Alternate Source Term (1CAN080801) (TAC No. MD7178)

3.

Entergy letter dated August 31, 2009, Response to Request for Information Regarding Steam Generator Tube Integrity During Break in Upper Hot Leg Piping (1CAN080902)

Dear Sir or Madam:

By letter dated August 31, 2009 (Reference 3), Entergy Operations, Inc. (Entergy) provided information to the NRC relating to once-through Steam Generator (SG) tube loads under conditions resulting from postulated breaks in reactor coolant system (RCS) upper hot leg large-bore piping. As a result of further telecommunications with the NRC, Entergy is proposing a commitment to validate the Arkansas Nuclear One, Unit 1 (ANO-1) SG tube loads under the aforementioned conditions. This validation will be completed no later than April 1, 2010.

There is one new commitment included in Attachment to this letter.

Entergy Operations, Inc.

1448 S.R. 333 Russellville, AR 72802 Tel 479-858-3110 Kevin T. Walsh Vice President, Operations Arkansas Nuclear One

1CAN100903 Page 2 of 2 If you have any questions or require additional information, please contact David Bice at 479-858-5338.

I declare under penalty of perjury that the foregoing is true and correct. Executed on October 26, 2009.

Sincerely, Original signed by Kevin T. Walsh KTW/dbb

Attachment:

List of Regulatory Commitments cc:

Mr. Elmo Collins Regional Administrator U. S. Nuclear Regulatory Commission Region IV 612 E. Lamar Blvd., Suite 400 Arlington, TX 76011-4125 NRC Senior Resident Inspector Arkansas Nuclear One P.O. Box 310 London, AR 72847 U. S. Nuclear Regulatory Commission Attn: Mr. Alan B. Wang MS O-7 D1 One White Flint North 11555 Rockville Pike Rockville, MD 20852 U. S. Nuclear Regulatory Commission Attn: Mr. Kaly Kalyanam MS O-8 B1 One White Flint North 11555 Rockville Pike Rockville, MD 20852 Mr. Bernard R. Bevill Arkansas Department of Health Radiation Control Section 4815 West Markham Street Slot #30 Little Rock, AR 72205

Attachment to 1CAN100903 List of Regulatory Commitments

Attachment to 1CAN100903 Page 1 of 1 LIST OF REGULATORY COMMITMENTS The following table identifies those actions committed to by Entergy Operations, Inc. (Entergy) in this document. Any other statements in this submittal are provided for information purposes and are not considered to be regulatory commitments.

COMMITMENT TYPE (Check one)

SCHEDULED COMPLETION DATE ONE-TIME ACTION CONTINUING COMPLIANCE Entergy will verify that the Steam Generators are designed to withstand the loading associated with the worst-case large break Loss of Coolant Accident (LBLOCA) and that tube integrity will be maintained for this LBLOCA as verified through implementation of Technical Specification 5.5.9, Steam Generator (SG)

Program. The results of the verification shall be provided to the NRC within 30 days thereafter.

9 April 1, 2010

Retrieved from "https://kanterella.com/w/index.php?title=1CAN100903,_Supplemental_to_Response_to_Request_for_Information_Regarding_Steam_Generator_Tube_Integrity_During_Break_in_Upper_Hot_Leg_Piping&oldid=5308780"