Letter Sequence RAI |
|---|
EPID:L-2017-LRO-0068, Donald C. Cook Nuclear Plant Unit 2, Supplemental Information Regarding the Reactor Vessel Internals Aging Management Program (Approved, Closed) |
|
MONTHYEARML17346A6832017-12-0808 December 2017
Donald C. Cook Nuclear Plant Unit 2, Supplemental Information Regarding the Reactor Vessel Internals Aging Management Program
Project stage: Request
ML18043A0092018-02-0909 February 2018
NRR E-mail Capture - DC Cook, Unit 2 - Request for Additional Information Regarding Reactor Vessel Internals Again Management Program
Project stage: RAI
ML18092A0842018-03-28028 March 2018
Donald C. Cook Nuclear Plant Unit 2, Response to Request for Additional Information Regarding Supplemental Information Regarding the Reactor Vessel Internals Aging Management Program
Project stage: Request
ML18145A1862018-06-0505 June 2018
Review of Supplemental Information Regarding the Reactor Vessel Internals Aging Management Program
Project stage: Approval
2018-02-09
[Table View] |
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[Table view]
Category:Request for Additional Information (RAI)
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2023-12-19
[Table view] |
Text
NRR-DMPSPEm Resource From: Rankin, Jennivine Sent: Friday, February 09, 2018 10:36 AM To: 'Helen L Levendosky'; 'Danielle M Burgoyne'
Subject:
DC Cook, Unit 2 - Request for Additional Information Regarding Reactor Vessel Internals Again Management Program (EPID L-2017-LRO-0068)
Attachments: Final RAI.docx Mrs. Levendosky, By letter dated December 8, 2017 (Agencywide Documents Access and Management System Accession No. ML17346A683), Indiana Michigan Power Company (the licensee) submitted supplemental information to the U.S. Nuclear Regulatory Commission (NRC) regarding the reactor vessel internals aging management program. Specifically, the submittal focuses on 5 degraded baffle-edge bolts identified during the Donald C.
Cook Nuclear Plant, Unit 2 cycle 23 refueling outage.
The NRC staff has reviewed the information provided and determined that additional information is required in order to complete its review. A draft request for additional information (RAI) was transmitted on January 30, 2018, and a clarification call was held on February 9, 2018. As agreed upon, please submit your response to the RAI by March 30, 2018. If you wish to alter the date of your response, please contact me at (301) 415-1530.
Please treat this e-mail as formal transmittal of the RAIs.
- Thanks, Jennie Jennie Rankin, Project Manager Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation 1
Hearing Identifier: NRR_DMPS Email Number: 154 Mail Envelope Properties (DM2PR09MB042964C7950FD97686293A4998F20)
Subject:
DC Cook, Unit 2 - Request for Additional Information Regarding Reactor Vessel Internals Again Management Program (EPID L-2017-LRO-0068)
Sent Date: 2/9/2018 10:35:47 AM Received Date: 2/9/2018 10:35:48 AM From: Rankin, Jennivine Created By: Jennivine.Rankin@nrc.gov Recipients:
"'Helen L Levendosky'" <hllevendosky@aep.com>
Tracking Status: None
"'Danielle M Burgoyne'" <dmburgoyne@aep.com>
Tracking Status: None Post Office: DM2PR09MB0429.namprd09.prod.outlook.com Files Size Date & Time MESSAGE 1128 2/9/2018 10:35:48 AM Final RAI.docx 27155 Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date:
Recipients Received:
REQUEST FOR ADDITIONAL INFORMATION REGARDING SUPPLEMENTAL INFORMATION REGARDING THE REACTOR VESSEL INTERNALS AGING MANAGEMENT PROGRAM DONALD C. COOK NUCLEAR PLANT, UNIT NO. 2 DOCKET NO. 50-316 EPID L-2017-LRO-0068 By letter dated December 8, 2017 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML17346A683), Indiana Michigan Power Company (the licensee) submitted supplemental information to the U.S. Nuclear Regulatory Commission (NRC) regarding the reactor vessel internals aging management program. Specifically, the submittal focuses on 5 degraded baffle-edge bolts identified during the Donald C. Cook Nuclear Plant (CNP), Unit 2 cycle 23 refueling outage.
RAI-1
Condition 3 of the NRC staffs final safety evaluation (SE) of WCAP-17096-NP-A, Revision 2, Reactor Internals Acceptance Criteria, Methodology and Data Requirements (ADAMS Accession No. ML16061A187) requires licensees to submit to the NRC the plant specific failure modes and effects analysis (FMEA) within one year after the inspection that detects relevant conditions. In Enclosure 2 of the December 8, 2017, submittal, the licensee provided a proprietary FMEA of the baffle-edge bolts for CNP, Unit 2. Specifically, the licensee provided sections relevant to baffle-edge bolts from 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.
The methodology and analysis section for baffle-edge bolts as described in WCAP-17096-NP-A (ADAMS Accession No. ML16279A320) states, in part, [o]bservation of relevant conditions in the baffle edge bolts or locking bars would require a FMEA on the observed condition.
The NRC staff notes that the information provided in the December 8, 2017, submittal describes the process for baffle-edge bolt FMEA and the generic results of the FMEA, but does not take into account the specific observed condition of the baffle-edge bolts at CNP, Unit No. 2 as described in WCAP-17096-NP-A. Please provide the results of the baffle-edge bolt FMEA considering the as-found condition at CNP, Unit No. 2.
