ML17346A683

Donald C. Cook Nuclear Plant Unit 2, Supplemental Information Regarding the Reactor Vessel Internals Aging Management Program

ML17346A683
Person / Time
Site:	Cook
Issue date:	12/08/2017
From:	Lies Q S Indiana Michigan Power Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
Shared Package
ML17346A656	List: AEP-NRC-2017-52, Enclosure 3: Donald C. Cook Nuclear Plant Unit 2, Application for Withholding Proprietary Supplemental Information Regarding the Reactor Vessel Internals Aging Management Program from Public Disclosure ML17346A683
References
AEP-NRC-2017-52
Download: ML17346A683 (4)

Text

s INOIANA MICHIGAN POWER A unit of American Electric Power December 8, 2017 Docket Nos.: 50-316 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Donald C. Cook Nuclear Plant Unit 2 Indiana Michigan Power Cook Nuclear Plant One Cook Place Bridgman, Ml 49106 lndianaMichiganPower.com AEP-NRC-2017-52 10 CFR 50.4 Supplemental Information Regarding the Reactor Vessel Internals Aging Management Program

References:

1. Letter from J. P. Gebbie, Indiana Michigan Power Company (l&M), to U.S. Nuclear Regulatory Commission (NRC); "Donald C. Cook Nuclear Plant Units 1 and 2, Transmittal of Reactor Vessel Internals Aging Management Program," dated October 1, 2012, Agencywide Documents Access and Management System (ADAMS) Accession No. ML 12284A320.

2. Letter from K. Hsueh, NRC to A Demma, Electric Power Research Institute, "Final Safety Evaluation of WCAP-17096-NP, Revision 2, 'Reactor Internals Acceptance Criteria Methodology and Data Requirements' (TAC No. ME4200)," dated May 3, 2016, ADAMS Accession No. ML 16061A187.

3. Letter from D. J. Wrona, NRC to J. P. Gebbie, l&M, "Donald C. Cook-Nuclear Plant, Units 1 and 2 :..:... Staff Assessment Regarding Program Plan for Aging Management for Reactor Vessel Internals (CAC Nos. MF0050 and MF0051 )," dated September 8, 2016, ADAMS Accession No. ML 16063A434.

This letter provides Supplemental Information for the Donald C. Cook Nuclear Plant (CNP) Unit 2, pertaining to the CNP Reactor Vessel Internals Aging Management Program. By Reference 1, Indiana Michigan Power Company (l&M) transmitted the CNP Reactor Vessel Internals Aging Management Program which implemented guidance from the Electric Power Research Institute provided in MRP-227-A, "Materials Reliability Program: Pressurized Water Reactor Internals Inspection and Evaluation Guidelines" (MRP-227-A).

By Reference 2, the U.S. Nuclear Regulatory Commission (NRC) transmitted a Final Safety Evaluation of WCAP-17096-NP, Revision 2, "Reactor Internals Acceptance Criteria Methodology and Data Requirements." Section 4 of Reference 2 requires licensees to submit plant-specific and/or generic

• analyses to the NRC within one (1) year after any inspection that detects relevant conditions as defined in MRP-227-A.

By Reference 3, the NRC transmitted a Final Safety Evaluation of the CNP Reactor Vessel Internals Aging Management Program which approved the program. PROPRIETARY INFORMATION Enclosure 2 to this letter contains proprietary information.

__ Withhold from public disclosure under 1 O CFR 2.390. Upon removal of Enclosure 2, this Letter is decontrolled.

U. S. Nuclear Regulatory Commission Page 2 AEP-NRC-2017-52 During the VT-3 inspection performed at CNP during the Unit 2 Cycle 23 refueling outage, five (5) degraded baffle-edge bolts were identified.

The baffle-edge bolts are identified in Reference 2 as a Condition 3 Group 1 RVI component; therefore, the plant specific failure modes and effects analysis (FMEA) must be submitted to the NRC within one (1) year after any inspection that detects relevant conditions as defined in MRP-227-A.

The one (1) year period is considered to begin on the date the plant begins power operation upon startup from the refueling outage during which the degradation was discovered.

Unit 2 Cycle 23 began on January 1, 2017. Enclosure 1 to this letter is an Affirmation Statement.

Enclosure 2 to this letter provides Section 3.6 of WCAP-18131-P Revision 1 which contains the plant specific FMEA for CNP as directed by Section 4*.3 of Reference

2. Enclosure 2 includes introductory pages and Section 3.6 (Pages 3-52 through 3-72) of WCAP 18131-P, Revision 1, "Background and Technical Basis Supporting Engineering Flaw Acceptance Criteria for D. C. Cook Unit 2 Reactor Vessel Internals MRP-227-A Primary and Expansion Components." Enclosure 3 provides an application for withholding proprietary information from public _disclosure.

The subject document was prepared and classified as Westinghouse Proprietary Information from Public Disclosure CAW-17-4671, accompanying Affidavit, Proprietary Information Notice, and Copyright Notice. As Item 1 contains information proprietary to Westinghouse Electric Company LLC ("Westinghouse"), it is supported by an Affidavit signed by Westinghouse, the owner of the information.

The Affidavit sets forth the basis on which the information may be withheld from public disclosure by the Nuclear Regulatory Commission

("Commission")

and addresses with specificity the considerations listed in paragraph (b)(4) of Section 2.390 of the Commission's regulations.

Accordingly, it is respectfully requested that the information which is proprietary to Westinghouse*

be withheld from public disclosure in accordance with 10 CFR Section 2.390 of the Commission's regulations.

Correspondence with respect to the copyright or proprietary aspects of the item listed above or the supporting Westinghouse Affidavit should reference CAW-17-4671 and should be addressed to James A. Gresham, Manager, Regulatory Compliance, Westinghouse Electric Company, 1000 Westinghouse Drive, Building 2 Suite 259, Cranberry Township, Pennsylvania 16066. There are no new regulatory commitments made in this letter. Should you have any questions, please contact Mr. Michael K. Scarpello, Regulato-ry Affairs Manager, at (269) 466-2649.

0~A,G Cane Lies Site Vice President DB/mll PROPRIETARY INFORMATION Enclosure 2 to this letter contains proprietary information.

• Withhold from public disclosure under 1 O CFR 2.390. Upon removal of Enclosure 2; this Letter is decontrolled.

U. S. Nuclear Regulatory Commission Page 3

Enclosures:

1. Affirmation AEP-NRC-2017-52

2. Westinghouse WCAP-1813~-P, Revision 1, "Background and Technical Basis Supporting Engineering Flaw Acceptance Criteria for D. C. Cook Unit 2 Reactor Vessel Internals MRP-227-A Primary and Expansion Components," Section 3.6 3. CAW-17-4671, "Application for Withholding Proprietary Information from Public Disclosure" c: R. J. Ancona, MPSC MDEQ -RMD/RPS NRG Resident Inspector C. D. Pederson, NRG Region Ill J. K. Rankin, NRG Washington DC A. J. Williamson -AEP Ft. Wayne, w/o enclosures PROPRIETARY INFORMATION Enclosure 2 to this letter contains proprietary information.

Withhold from public disclosure under 10 CFR 2.390. Upon removal of Enclosure 2, this Letter is decontrolled.

Enclosure 1 to AEP-NRC-2017-52 AFFIRMATION I, Q. Shane Lies, being duly sworn, state that I am the Site Vice President of Indiana Michigan Power Company (l&M), that I am authorized to sign and file this request with the U. S. Nuclear Regulatory Commission on behalf of l&M, and that the statements made and the matters set forth herein pertaining to l&M are true and correct to the best of my knowledge, information, and belief. Indiana Michigan Power Company 1~A-~ ~nelies Site Vice President SWORN TO AND SUBSCRIBED BEFORE ME THIS °6 DAY OF L)!CeM ber , 2017 My Commission Expires Ol/'2.L I 20\~