ML16308A113

Summary of October 27, 2016, Public Meeting with Indiana Michigan Power Company Regarding the Donald C. Cook Nuclear Plant, Units 1 and 2 (CAC Nos. MF7114 and MF7115)

ML16308A113
Person / Time
Site:	Cook
Issue date:	11/16/2016
From:	Dietrich A W Plant Licensing Branch III
To:	Indiana Michigan Power Co
Dietrich A, NRR/DORL/LPLIII-1, 415-2846
References
CAC MF7114, CAC MF7115
Download: ML16308A113 (13)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 November 16, 2016 LICENSEE: Indiana Michigan Power Company, LLC FACILITY: Donald C. Cook Nuclear Plant, Units 1 and 2 SUBJECT: SUMMARY OF OCTOBER 27, 2016, PUBLIC MEETING WITH INDIANA MICHIGAN POWER COMPANY REGARDING THE DONALD C. COOK NUCLEAR PLANT, UNITS 1 AND 2 (CAC NOS. MF7114 AND MF7115) On October 27, 2016, a Category I public meeting was held between the U.S. Nuclear Regulatory Commission (NRC) and representatives of Indiana Michigan Power Company (l&M, the licensee) at NRC Headquarters, One White Flint North, 11555 Rockville Pike, Rockville, Maryland. This meeting was open to members of the public. The meeting notice and agenda, dated October 21, 2016, are available in the Agencywide Documents Access and Management System (ADAMS) at Accession No. ML 16295A375. A list of attendees is provided as Enclosure 1. The licensee's presentation is provided as Enclosure 2. Purpose The purpose of the meeting was to discuss the license amendment request (LAR) dated November 19, 2015, for the Donald C. Cook Nuclear Plant, Units 1 and 2 (ADAMS Accession No. ML 15328A469). The proposed amendment is consistent with the NRG-approved Technical Specifications Task Force (TSTF) Traveler, TSTF-425, Revision 3, "Relocate Surveillance Frequencies to Licensee Control -RITSTF Initiative Sb." The proposed change would relocate surveillance frequencies to a licensee-controlled program, the Surveillance Frequency Control Program. The meeting focused on a recent upgrade to the licensee's probabilistic risk assessment (PRA), which was performed in support of the LAR. Background During the meeting, the NRC staff presented a background of the LAR review thus far. A summary of the background follows. The NRC staff's review of the licensee's LAR to adopt TSTF-425 has included two requests for additional information (RAls) related to PRA. The NRC staff issued the first RAI by letter dated May 11, 2016 (ADAMS Accession No. ML 16127 A079). In the first RAI, the NRC requested that the licensee explain the disposition of certain facts and observations (F&Os) for pre-initiator human failure events. The licensee responded by letter dated June 16, 2016 (ADAMS Accession No. ML 16173A256). In the June 16, 2016, letter, the licensee stated that it had performed a new pre-initiator Human Reliability Analysis (HRA) to resolve the F&O. The NRC staff issued the second RAI by letter dated August 1, 2016 (ADAMS Accession No. ML 16211A015). In the August 1, 2016, letter, the NRC stated that if the new analysis constituted a PRA upgrade, the licensee would need to perform a focused scope peer review and provide the F&Os to the NRC, along with their dispositions and impact on the LAR. The

-2 -licensee responded to the second RAI by letter dated September 9, 2016 (ADAMS Accession No. ML 16258A145). In the September 9, 2016, letter, the licensee stated that the new initiator analysis does constitute a PRA upgrade, and that a focused-scope peer review would be scheduled for the fourth quarter of 2016. On October 11, 2016, the licensee submitted an emergency LAR (ADAMS Accession No. ML 16287A615) that was unrelated to the TSTF-425 review, but that included discussion about the HRA focused scope peer review that had been recently performed. The NRC staff reviewed the information that was submitted and issued an RAI on October 13, 2016, related to the scope of review and applicability of Supporting Requirements from the PRA Standard (ADAMS Accession No. ML 16291A011). The licensee then determined that it did not need the emergency amendment, and the LAR was withdrawn by letter dated October 13, 2016 (ADAMS Accession No. ML 16291A496), before an RAI response was submitted to the NRC. On October 21, 2016, a telephone conference was held to inform the licensee that the NRC staff was prepared to deny the TSTF-425 LAR, as submitted. The basis for denial was that the LAR lacked an analysis that was necessary for the NRC staff's review. Specifically, the licensee incorporated a new method into its PRA model without performing a focused scope peer review and providing the F&Os and impact assessments to the NRC. Additionally, the licensee did not fully respond to the NRC RAI dated August 1, 2016, rather the response only contained a promise for future information. On the October 21, 2016, phone call, the NRC staff offered the licensee the opportunity to withdraw the TSTF-425 LAR, or to request a public meeting for further discussion of the issues. The licensee requested a public meeting. Technical Discussion During the meeting, the licensee presented information regarding the status of the focused scope peer review on HRA pre-initiators. The presentation given by the licensee is included as Enclosure 2 of this meeting summary. The licensee stated that it had completed a focused scope peer review of its pre-initiator HRA. The licensee provided a table of the high level requirements (HLRs) from the PRA standard, ASME/ANS RA-Sa-2009, "Standard for Level 1/Large Early Release Frequency Probabilistic Risk Assessment for Nuclear Power Plant Applications," along with the result of the focused scope peer review for each applicable HLR. The licensee stated that the documentation for the focused scope peer review was finalized on October 11, 2016, and that a full response to the August 1, 2016, RAI could be provided by November 4, 2016. The licensee stated that it would provide a copy of the complete focused scope peer review report with the RAI response. The NRC staff asked the licensee if the focused scope peer review had been influenced by the F&Os from the previously performed peer review. The licensee stated that the focused scope peer review was complete and independent, and had not been biased by the previous review. The NRC staff requested that the licensee's RAI response include an explanation for any HLRs that had not been evaluated as part of the focused scope peer review. The NRC staff stated that, following the meeting, a determination would be made whether or not to continue with the denial of the LAR. No regulatory decisions were made during the meeting.

-3 -Public Participation Members of the public were in attendance via telephone, but had no comments. Public Meeting Feedback forms were not received. Please direct any inquiries to me at 301-415-2846, or Allison.Dietrich@nrc.gov. Docket Nos. 50-315 and 50-316 Enclosure: 1. List of Attendees 2. Licensee Presentation cc w/encl: Distribution via Listserv Sincerely, :ifl Allison W. Dietrich, Project Manager Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation LIST OF ATTENDEES OCTOBER 27. 2016, PUBLIC MEETING WITH l&M. LLC REGARDING LICENSE AMENDMENT REQUEST TO RELOCATE SURVEILLANCE FREQUENCIES TO LICENSEE CONTROL Name Eric Benner David Wrona Allison Dietrich CJ Fong Jonathan Evans Leslie Fields Mihaela Biro John Ellegood* Garill Coles* Steve Short* Michael Scarpello James Heyeck Helen Kish* DONALD C. COOK NUCLEAR PLANT, UNITS 1 AND 2 CAC NOS. MF7114 AND MF7115 Organization U.S. Nuclear Regulatory Commission (NRC) NRC NRC NRC NRC NRC NRC NRC Pacific Northwest National Laboratory (PNNL) PNNL Indiana Michigan Power Company (l&M) l&M l&M Danielle Burgoyne* l&M Brandon Irvin Jensen Huqhes Eric Thornsbury Jensen Hughes Victoria Anderson* Nuclear Enerav Institute *Participated by phone Enclosure 1 Enclosure 2 Licensee Presentation 0 An Overview of the D.C. Cook Focused Scope Peer Review -HRA Pre-Initiators '-"' INOIANA iiilMICHIGAN ,.,,,,.,,. October 27, 2016 NRC Headquarters -Rockville, MD Presented by Brandon Irvin -D.C. Cook PRA Team Eric Thornsbury -D.C. Cook PRA Team Michael Scarpello -D.C. Cook Regulatory Affairs Manager James Heyeck -D.C. Cook PRA Engineer D.C. Cook Nuclear Power Plant A unit of American Elsctric Power

'-"' .lllDIAIU& liiMMICHHMN ,,.,,,. *. TSTF-425 License Amendment Request *A License Amendment request submitted in late 2015 for adoption of Risk Informed Initiative Sb/ TSTF-425

• RAls received related to Pre-Initiators 0 RAl-PRA-1 -Noted F&Os received on pre-initiators from 2015 PRA Peer Review and questioned the intent to disposition these F&Os with PRA Sensitivities 0 RAl-PRA-1-0 I -Focus of RAI shifted to understanding if the "new analysis" was considered as a "PRA Upgrade" D.C. Cook Nuclear Power Plant A nnit of American Electric Power iliilil.MICHIMN l'fJl'lm** Focused Scope Follow-On Peer Review *A review of NEI 05-04 and guidance provided directly from the PRA Standard RA-Sa-2009 was performed to determine the appropriate scope and level of review required. 0 As a result, the scope of the review was limited to Cook Pre-Initiator Methods against HLRs HR-A, HR-Band HR-C 0 SRs HR-A I through HR-C3 reviewed D.C. Cook Nuclear Power Plant A unit of American Elttctric Power

... MICHIGAN ,...,. *. Focused Scope Follow-On Peer Review

• A Focused Scope Peer Review was performed and completed in October 2016 based on the identification of an upgrade. ° Changes made to Identification, Screening, and Definition methodology used in PRA for initiators. 0 No change made to the method of quantification or documentation. D.C. Cook Nuclear Power Plant A unit of American Electric Pawer High Level Requirement Overview HLR-HR-B .. C HLR-HR-D HLR-HR-1 Screening of Pre-Initiators impact of Pre-4(\ltiators Assessment and Quantification of Pre-Initiators Documentation Required Review Review Not Upgraded (I) NdtUpgraded (2) Focused Scope Peer Review Complete -SRs Met at CC-II SR.s. Met N/A NIA. (I) Pre-initiator quantification methodologies (TH ERP and ASEP) were not changed (2) No changes made to the documentation approach as a result of changing identification and screening lllDIAllA iiiil MICHIGAN IOtllfS** A unit of American Electric Power D.C. Cook Nuclear Power Plant

""'INOIANA ... MICHIGAN Finalizing the RAI Responses

• Pre-Initiator Focused Scope PRA Peer Review was completed and final documentation approved on October I I th 2016.

• Final RAI responses agreed to be provided by mid November can be provided as early as November 4th. D.C. Cook Nuclear Power Plant A anit of American Electric Power

,. INDIAllll ... MICHIGAN l'Olllfl** What will we provide

• A copy of the complete Focused Scope PRA Peer Review report

• Dispositioning of a finding received 0 Single Finding received related to documentation and verification of process used for screening however the SR was graded as Met Cat II D.C. Cook Nuclear Power Plant A llnit of American Electric Power

-3 -Public Participation Members of the public were in attendance via telephone, but had no comments. Public Meeting Feedback forms were not received. Please direct any inquiries to me at 301-415-2846, or Allison. Dietrich@nrc.gov. Docket Nos. 50-315 and 50-316 Enclosure: 1. List of Attendees 2. Licensee Presentation cc w/encl: Distribution via Listserv DISTRIBUTION: PUBLIC LPL3-1 Reading RidsAcrsAcnw_MailCTR Resource RidsNrrDorlLpl3-1 Resource RidsOpaMail Resource PMNS Resource LFields, NRR ADAMS Accession No.: ML 16308A113 OFFICE DORULPL3-1 /PM DORULPL3-1/LA NAME A Dietrich SRohrer DATE 11/3/16 11/3/16 Sincerely, IRA/ Allison W. Dietrich, Project Manager Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation RidsNrrLASRohrer Resource RidsRgn3mailCenter Resource RidsNrrPmDCCook Resource RidsNrrDorl Resource RidsNrrDraApla Resource JEvans, NRR DRNAPLA/BC DORULPL3-1/BC DORULPL3-1 /PM SRosenberg DWrona A Dietrich 11/14/16 11/15/16 11/16/16 OFFICIAL RECORD COPY