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| | issue date = 11/04/2013 | | | issue date = 11/04/2013 |
| | title = IR 05000315-13-407; 05000316-13-407; 09/16/2013 - 09/20/2013, Donald C. Cook Nuclear Power Plant, Units 1 and 2; Routine Security Baseline Inspection (Public) | | | title = IR 05000315-13-407; 05000316-13-407; 09/16/2013 - 09/20/2013, Donald C. Cook Nuclear Power Plant, Units 1 and 2; Routine Security Baseline Inspection (Public) |
| | author name = Skokowski R A | | | author name = Skokowski R |
| | author affiliation = NRC/RGN-III/DRS/PSB | | | author affiliation = NRC/RGN-III/DRS/PSB |
| | addressee name = Weber L | | | addressee name = Weber L |
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| =Text= | | =Text= |
| {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION REGION III 2443 WARRENVILLE ROAD, SUITE 210 LISLE, IL 60532-4352 November 4, 2013 | | {{#Wiki_filter:UNITED STATES ember 4, 2013 |
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| EA-12-005
| | ==SUBJECT:== |
| | DONALD C. COOK NUCLEAR POWER PLANT, UNITS 1 AND 2, NRC INSPECTION REPORT 05000315/2013407; 05000316/2013407 |
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| Mr. Larry Weber Senior Vice President and Chief Nuclear Officer Indiana Michigan Power Company | | ==Dear Mr. Weber:== |
| | On September 20, 2013, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at your Donald C. Cook Nuclear Power Plant, Units 1 and 2. The inspection covered one or more of the key attributes of the security cornerstone of the NRCs Reactor Oversight Process. The enclosed inspection report documents the inspection results, which were discussed on September 20, 2013, with Mr. S. Partin and other members of your staff. |
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| Nuclear Generation Group One Cook Place
| | The inspection examined activities conducted under your license as they relate to security and compliance with the Commissions rules and regulations and with the conditions of your license. |
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| Bridgman, MI 49106
| | The inspector reviewed selected procedures and records, observed activities, and interviewed personnel. |
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| SUBJECT: DONALD C. COOK NUCLEAR POWER PLANT, UNITS 1 AND 2, NRC INSPECTION REPORT 05000315/2013407; 05000316/2013407
| | No findings were identified during this inspection. |
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| ==Dear Mr. Weber:==
| | In accordance with Title 10 of the Code of Federal Regulations (10 CFR) 2.390, Public Inspections, Exemptions, Request for Withholding, of the NRC's "Rules of Practice," a copy of this letter will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records System (PARS) component of NRC's Agencywide Documents Access and Management System (ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room). |
| On September 20, 2013, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at your Donald C. Cook Nuclear Power Plant, Units 1 and 2. The inspection covered one or more of the key attributes of the security cornerstone of the NRC's Reactor Oversight Process. The enclosed inspection report documents the inspection results, which were discussed on September 20, 2013, with Mr. S. Partin and other members of your staff. The inspection examined activities conducted under your license as they relate to security and compliance with the Commission's rules and regulations and with the conditions of your license. The inspector reviewed selected procedures and records, observed activities, and interviewed personnel. No findings were identified during this inspection. In accordance with Title 10 of the Code of Federal Regulations (10 CFR) 2.390, "Public Inspections, Exemptions, Request for Withholding,"
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| of the NRC's "Rules of Practice," a copy of this letter will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records System (PARS) component of NRC's Agencywide Documents Access and Management System (ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room). However, the material enclosed herewith contains Security-Related Information in accordance with 10 CFR 2.390(d)(1) and its disclosure to unauthorized individuals could present a security vulnerability. Therefore, the material in the enclosure will not be made available electronically for public inspection in the NRC Public Document Room or from the PARS component of NRC's ADAMS. Enclosure 1 contains Sensitive Unclassified Non-Safeguards Information. When separated from Enclosure 1, this transmittal document is decontrolled. If you choose to provide a response and Security-Related Information is necessary to provide an acceptable response, please mark your entire response "Security-Related Information - Withhold from public disclosure under 10 CFR 2.390" in accordance with 10 CFR 2.390(d)(1) | |
| and follow the instructions for withholding in 10 CFR 2.390 (b)(1). In accordance with 10 CFR 2.390(b)(1)(ii), the NRC is waiving the a ffidavit requirements for your response. Should you have any questions concerning this inspection, we will be pleased to discuss them with you.
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| Sincerely,
| | However, the material enclosed herewith contains Security-Related Information in accordance with 10 CFR 2.390(d)(1) and its disclosure to unauthorized individuals could present a security vulnerability. Therefore, the material in the enclosure will not be made available electronically for public inspection in the NRC Public Document Room or from the PARS component of NRCs ADAMS. |
| /RA/ By John B. Giessner Acting For/
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| Richard A. Skokowski, Chief
| | Enclosure 1 contains Sensitive Unclassified Non-Safeguards Information. When separated from Enclosure 1, this transmittal document is decontrolled. If you choose to provide a response and Security-Related Information is necessary to provide an acceptable response, please mark your entire response Security-Related Information Withhold from public disclosure under 10 CFR 2.390 in accordance with 10 CFR 2.390(d)(1) |
| | and follow the instructions for withholding in 10 CFR 2.390 (b)(1). In accordance with 10 CFR 2.390(b)(1)(ii), the NRC is waiving the affidavit requirements for your response. |
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| Plant Support Branch
| | Should you have any questions concerning this inspection, we will be pleased to discuss them with you. |
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| Division of Reactor Safety Docket Nos. 50-315; 50-316 License Nos. DPR-58; DPR-74 | | Sincerely, |
| | | /RA/ By John B. Giessner Acting For/ |
| Nonpublic Enclosure 1: Inspection Report 05000315/2013407; 05000316/2013407 w/Attachment 1: Supplemental Information (Nonpublic) | | Richard A. Skokowski, Chief Plant Support Branch Division of Reactor Safety Docket Nos. 50-315; 50-316 License Nos. DPR-58; DPR-74 Nonpublic Enclosure 1: Inspection Report 05000315/2013407; 05000316/2013407 w/Attachment 1: Supplemental Information (Nonpublic) |
| Public Enclosure 2: Inspection Report 05000315/2013407; 05000316/2013407 w/Attachment 2: Supplemental Information (Public) | | Public Enclosure 2: Inspection Report 05000315/2013407; 05000316/2013407 w/Attachment 2: Supplemental Information (Public) |
| cc w/Enclosure 1: S. Coker, NSIR/DSO/DDSO/ST R. Albert, NSIR T. Dimitriadis, RI | | cc w/Enclosure 1: S. Coker, NSIR/DSO/DDSO/ST R. Albert, NSIR T. Dimitriadis, RI B. Desai, RII M. Haire, RIV K. Yale, State Liaison Officer, State of Michigan cc w/o Enclosure 1: Distribution via ListServTM cc w/Enclosure 2: Distribution via ListServ' U. S. NUCLEAR REGULATORY COMMISSION |
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| B. Desai, RII M. Haire, RIV K. Yale, State Liaison Officer, State of Michigan cc w/o Enclosure 1: Distribution via ListServTM cc w/Enclosure 2: Distribution via ListServŽ | |
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| Enclosure 2 U. S. NUCLEAR REGULATORY COMMISSION
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| ==REGION III== | | ==REGION III== |
| Docket Nos: 05000315; 05000316 License Nos: DPR-58; DPR-74 | | Docket Nos: 05000315; 05000316 License Nos: DPR-58; DPR-74 Report No: 05000315/2013407; 05000316/2013407 Licensee: Indiana Michigan Power Company Facility: Donald C. Cook Nuclear Power Plant, Units 1 and 2 Location: Bridgman, Michigan Dates: September 16 through September 20, 2013 Inspector: J. Maynen, Senior Physical Security Inspector Approved by: R. Skokowski, Chief Plant Support Branch Division of Reactor Safety Enclosure 2 |
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| Report No: 05000315/2013407; 05000316/2013407
| | =SUMMARY OF FINDINGS= |
| | | IR 05000315/2013407; 05000316/2013407; 09/16/2013 - 09/20/2013, Donald C. Cook Nuclear |
| Licensee: Indiana Michigan Power Company Facility: Donald C. Cook Nuclear Power Plant, Units 1 and 2
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| Location: Bridgman, Michigan Dates: September 16 through September 20, 2013
| | Power Plant, Units 1 and 2; Routine Security Baseline Inspection. |
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| Inspector: J. Maynen, Senior Physical Security Inspector Approved by: R. Skokowski, Chief Plant Support Branch
| | This report covers a one week period of announced routine baseline inspection on security. |
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| Division of Reactor Safety 1 Enclosure 2
| | The inspection was conducted by one Region III physical security inspector. No findings were identified. The NRCs program for overseeing the safe operation of commercial nuclear power reactors is described in NUREG-1649, Reactor Oversight Process. |
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| =SUMMARY OF FINDINGS=
| | A. Inspector-Identified and Self-Revealed Findings |
| IR 05000315/2013407; 05000316/2013407; 09/16/2013 - 09/20/2013, Donald C. Cook Nuclear Power Plant, Units 1 and 2; Routine Security Baseline Inspection. This report covers a one week period of announced routine baseline inspection on security. The inspection was conducted by one Region III physical security inspector. No findings were identified. The NRC's program for overseeing t he safe operation of commercial nuclear power reactors is described in NUREG-1649, "Reactor Oversight Process." A. Inspector-Identified and Self-Revealed Findings
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| ===Cornerstone: Security=== | | ===Cornerstone: Security=== |
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| No findings were identified. | | No findings were identified. |
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| ===B. Licensee-Identified Violations=== | | ===Licensee-Identified Violations=== |
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| None. | | None. |
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| 2
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| =REPORT DETAILS= | | =REPORT DETAILS= |
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| ==4OA5 Other Activities== | | ==4OA5 Other Activities== |
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| ===.1 Inspection of Confirmatory Order EA-12-005 On June 28, 2012, the NRC issued Confirmatory Order EA-12-005 (Order) to the licensee.=== | | ===.1 Inspection of Confirmatory Order EA-12-005=== |
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| | On June 28, 2012, the NRC issued Confirmatory Order EA-12-005 (Order) to the licensee. |
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| | The elements of the agreement between the U.S. Nuclear Regulatory Commission (NRC)and the licensee consisted of the following three specific actions: |
| | Section V, Item 1. |
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| | Within 90 days of the effective date of the Order, develop a lessons-learned presentation and within 180 days of the effective date of the Order, present these lessons-learned to first line supervisors and above. |
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| | Section V, Item 2. |
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| | Within 365 days of the effective date of the Order, develop and present the facts and lessons learned at an industry FFD forum and a broader industry forum. |
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| | Section V, Item 3. |
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| | Notify the NRC Regional Administrator, Region III, within 30 days of the completion of all actions described in the Order. |
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| | A lessons-learned presentation was developed on August 1, 2012, and the site supervisors and managers were briefed on the issue at the site leadership meeting held on October 3, 2012. The licensee made arrangements to ensure that supervisors and managers who did not attend the meeting received the briefing prior to resuming supervisory duties. |
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| | On June 5, 2013, the Site Vice President presented the facts and lessons learned to a broad industry forum, including industry FFD management and senior management personnel, at the annual USA/STARS Annual Conference. |
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| | On June 20, 2013, the NRC Regional Administrator, Region III, was notified of the completion of the actions required by the Order. |
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| | The inspectors independently verified the actions completed by the licensee as required by Section V of Confirmatory Order EA-12-005. |
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| The elements of the agreement between the U.S. Nuclear Regulatory Commission (NRC) and the licensee consisted of the following three specific actions: Section V, Item 1. Within 90 days of the effective date of the Order, develop a lessons-learned presentation and within 180 days of the effective date of the Order, present these lessons-learned to first line supervisors and above. Section V, Item 2. Within 365 days of the effective date of the Order, develop and present the facts and lessons learned at an industry FFD forum and a broader industry forum. Section V, Item 3. Notify the NRC Regional Administrator, Region III, within 30 days of the completion of all actions described in the Order. A lessons-learned presentation was developed on August 1, 2012, and the site supervisors and managers were briefed on the issue at the site leadership meeting held on October 3, 2012. The licensee made arrangements to ensure that supervisors and managers who did not attend the meeting received the briefing prior to resuming supervisory duties. On June 5, 2013, the Site Vice President presented the facts and lessons learned to a broad industry forum, including industry FFD management and senior management personnel, at the annual USA/STARS Annual Conference. On June 20, 2013, the NRC Regional Administrator, Region III, was notified of the completion of the actions required by the Order. The inspectors independently verified the actions completed by the licensee as required by Section V of Confirmatory Order EA-12-005.
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| {{a|4OA6}} | | {{a|4OA6}} |
| ==4OA6 Management Meetings== | | ==4OA6 Management Meetings== |
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| ===.1 Exit Meeting The inspector presented the inspection results to Mr. S. Partin and other members of licensee management at the conclusion of the inspection on September 20, 2013.=== | | ===.1 Exit Meeting=== |
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| | The inspector presented the inspection results to Mr. S. Partin and other members of licensee management at the conclusion of the inspection on September 20, 2013. |
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| The inspector asked the licensee whether any materials examined during the inspection should be considered proprietary. No proprietary information was identified. | | The inspector asked the licensee whether any materials examined during the inspection should be considered proprietary. No proprietary information was identified. |
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| ATTACHMENT 2: | | ATTACHMENT 2: |
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| =SUPPLEMENTAL INFORMATION= | | =SUPPLEMENTAL INFORMATION= |
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| ==KEY POINTS OF CONTACT== | | ==KEY POINTS OF CONTACT== |
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| Licensee | | Licensee |
| : [[contact::S. Partin]], Plant Manager | | : [[contact::S. Partin]], Plant Manager |
| : [[contact::C. Hutchinson]], Director, Nuclear Site Services | | : [[contact::C. Hutchinson]], Director, Nuclear Site Services |
| : [[contact::J. Carter]], Security | | : [[contact::J. Carter]], Security |
| : [[contact::K. Henderson]], Regulatory Affairs | | : [[contact::K. Henderson]], Regulatory Affairs |
| Nuclear Regulatory Commission | | Nuclear Regulatory Commission |
| : [[contact::J. Ellegood]], Senior Resident Inspector | | : [[contact::J. Ellegood]], Senior Resident Inspector |
| : [[contact::P. LaFlamme]], Resident Inspector | | : [[contact::P. LaFlamme]], Resident Inspector |
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| ==LIST OF ITEMS OPENED, CLOSED, AND DISCUSSED== | | ==LIST OF ITEMS OPENED, CLOSED, AND DISCUSSED== |
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| ===Opened, Closed, and Discussed=== | | ===Opened, Closed, and Discussed=== |
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| None | | None |
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| ==LIST OF DOCUMENTS REVIEWED== | | ==LIST OF DOCUMENTS REVIEWED== |
| The following is a list of documents reviewed during the inspection.
| |
| : Inclusion on this list does not imply that the NRC inspector reviewed the documents in their entirety but rather that selected sections or portions of the documents were evaluated as part of the overall inspection effort.
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| : Inclusion of a document on this list does not imply NRC acceptance of the document, or any part of it, unless this is stated in the body of the inspection report.
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| ==4OA5 Other Activities==
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| : Confirmatory Order
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| : EA-12-005; dated June 28, 2012
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| : Letter from J. Gebbie to C. Casto; Donald C. Cook Nuclear Plant, Units 1 and 2;
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| : Response to Confirmatory Order
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| : EA-12-005; dated June 20, 2013
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| : AR 2012-8093; Confirmatory Order Issued to I&M by NRC, regarding 10 CFR 26
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| ==LIST OF ACRONYMS==
| |
| : [[USED]] [[]]
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| : [[ADAMS]] [[Agencywide Documents and Access Management System]]
| |
| : [[CFR]] [[Code of Federal Regulations]]
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| DRS Division of Reactor Safety
| |
| NRC U.S. Nuclear Regulatory Commission L. Weber -2-
| |
| If you choose to provide a response and Security-Related Information is necessary to provide an acceptable response, please mark your entire response "Security-Related Information - Withhold from public disclosure under
| |
| : [[10 CFR]] [[2.390" in accordance with 10]]
| |
| : [[CFR]] [[2.390(d)(1) and follow the instructions for withholding in]]
| |
| : [[10 CFR]] [[2.390 (b)(1). In accordance with 10]]
| |
| CFR 2.390(b)(1)(ii), the NRC is waiving the affidavit requirements for your response.
| |
|
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| Should you have any questions concerning this inspection, we will be pleased to discuss them with you.
| |
| Sincerely, /RA/ By John B. Giessner Acting For/ Richard Skokowski, Chief
| |
| Plant Support Branch Division of Reactor Safety
| |
|
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| Docket Nos. 50-315; 50-316 License Nos. DPR-58; DPR-74
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|
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| Nonpublic Enclosure 1: Inspection Report 05000315/2013407; 05000316/2013407 w/Attachment 1: Supplemental Information (Nonpublic)
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| Public Enclosure 2: Inspection Report 05000315/2013407; 05000316/2013407 w/Attachment 2: Supplemental Information (Public)
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| cc w/Enclosure 1:
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| : [[S.]] [[Coker,]]
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| : [[NSIR]] [[/DSO/DDSO/ST]]
| |
| : [[R.]] [[Albert,]]
| |
| : [[NSIR]] [[]]
| |
| : [[T.]] [[Dimitriadis,]]
| |
| : [[RI]] [[]]
| |
| : [[B.]] [[Desai,]]
| |
| : [[RII]] [[]]
| |
| : [[M.]] [[Haire,]]
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| RIV
| |
| K. Yale, State Liaison Officer, State of Michigan
| |
| cc w/o Enclosure 1: Distribution via ListServTM cc w/Enclosure 2: Distribution via ListServŽ
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|
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| DISTRIBUTION w/Enclosure 2: Daniel Rich
| |
| RidsNrrDorlLpl3-1 Resource
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| RidsNrrPMDCCook Resource RidsNrrDirsIrib Resource Cynthia Pederson
| |
| Anne Boland
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| Steven Orth
| |
|
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|
| Allan Barker
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| Carole Ariano Linda Linn
| |
| : [[DRPIII]] [[]]
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| DRSIII
| |
| Patricia Buckley Tammy Tomczak ROPreports.Resource@nrc.gov
| |
| : [[DOCUME]] [[NT NAME:]]
| |
| : [[DCC]] [[2013407]]
| |
| : [[DRS]] [[]]
| |
| : [[OUO]] [[Cover Letter.docx Publicly Available Non-Publicly Available Sensitive Non-Sensitive To receive a copy of this document, indicate in the concurrence box "C" = Copy without attach/encl "E" = Copy with attach/encl "N" = No copy]]
| |
| : [[OFFICE]] [[]]
| |
| : [[RIII]] [[]]
| |
| : [[RIII]] [[]]
| |
| : [[RIII]] [[]]
| |
| : [[RIII]] [[]]
| |
| : [[NAME]] [[]]
| |
| : [[JM]] [[aynen:cs GHansen for DFunk SOrth JGiessner for RSkokowski]]
| |
| : [[DATE]] [[10/30/13 10/31/13 11/04/13 11/04/13]]
| |
| : [[OFFICI]] [[AL]]
| |
| : [[RECORD]] [[]]
| |
| : [[COPY]] [[]]
| |
| }} | | }} |
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IR 05000315/20203012020-10-19019 October 2020
NRC Initial License Examination Report 05000315/2020301; 05000316/2020301
IR 05000315/20200112020-09-17017 September 2020
Information Request to Support Upcoming Temporary Instruction 2515/194 Inspection; Inspection Report 05000315/2020011; 05000316/2020011
IR 05000315/20200052020-09-0101 September 2020
Updated Inspection Plan for Donald C. Cook Nuclear Plant, Units 1 and 2 (Report 05000315/2020005 and 05000316/2020005)
IR 05000315/20200022020-08-10010 August 2020
Integrated Inspection Report 05000315/2020002 and 05000316/2020002
2024-01-31
[Table view]
Category:Letter
MONTHYEARIR 05000315/20230042024-01-31031 January 2024
Integrated Inspection Report 05000315/2023004 and 05000316/2023004
ML24004A1582024-01-19019 January 2024
Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0039 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting))
AEP-NRC-2024-01, Emergency Plan Revision 482024-01-0808 January 2024
Emergency Plan Revision 48
AEP-NRC-2023-56, Report Per Technical Specification 5.6.6 for Inoperability of Unit 1 Post Accident Monitoring Reactor Coolant (Loop 3 Cold Leg) Wide Range Temperature Recorder Thermal Sensor2023-12-20020 December 2023
Report Per Technical Specification 5.6.6 for Inoperability of Unit 1 Post Accident Monitoring Reactor Coolant (Loop 3 Cold Leg) Wide Range Temperature Recorder Thermal Sensor
ML23352A3502023-12-19019 December 2023
Dc. Cook Nuclear Power Plant, Units 1 Biennial Licensed Operator Requalification Program Inspection and Request for Information
ML23338A2642023-12-0505 December 2023
Confirmation of Initial License Examination
AEP-NRC-2023-45, Unit 2 - Schedular Exemption for Enhanced Weapons, Firearms, Background Checks, and Security Event Notifications Implementation2023-11-16016 November 2023
Unit 2 - Schedular Exemption for Enhanced Weapons, Firearms, Background Checks, and Security Event Notifications Implementation
IR 05000315/20234042023-11-0606 November 2023
Cyber Security Inspection Report 05000315/2023404 and 05000316/2023404
ML23310A1152023-11-0606 November 2023
Notification of the NRC Baseline Inspection and Request for Information, Inspection Report 05000316/2024002
IR 05000315/20234032023-09-19019 September 2023
Security Baseline Inspection Report 05000315/2023403 and 05000316/2023403
IR 05000315/20230112023-08-31031 August 2023
Functional Engineering Inspection - Commercial Grade Dedication Report 05000315/2023011 and 05000316/2023011
ML23242A1832023-08-30030 August 2023
Notification of NRC Baseline Inspection and Request for Information; Inspection Report05000315/2023004
AEP-NRC-2023-40, Annual Report of Loss-of-Coolant Accident Evaluation Model Changes2023-08-29029 August 2023
Annual Report of Loss-of-Coolant Accident Evaluation Model Changes
IR 05000315/20234022023-08-11011 August 2023
Security Baseline Inspection Report 05000315/2023402 and 05000316/2023402
AEP-NRC-2023-34, Supplement to Request for Approval of Change Regarding Neutron Flux Instrumentation2023-08-0202 August 2023
Supplement to Request for Approval of Change Regarding Neutron Flux Instrumentation
IR 05000315/20230022023-07-24024 July 2023
Integrated Inspection Report 05000315/2023002 and 05000316/2023002
ML23178A2422023-06-28028 June 2023
Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch III
IR 05000315/20230122023-06-22022 June 2023
Biennial Problem Identification and Resolution Inspection Report 05000315/2023012 and 05000316/2023012
IR 05000315/20235012023-06-21021 June 2023
Emergency Preparedness Biennial Exercise Inspection Report 05000315/2023501 and 05000316/2023501
AEP-NRC-2023-29, Core Operating Limits Report2023-06-19019 June 2023
Core Operating Limits Report
ML23159A0192023-06-13013 June 2023
Information Meeting with a Question and Answer Session to Discuss NRC 2022 End-Of-Cycle Plant Performance Assessment of Donald C. Cook Nuclear Plant, Units 1 and 2
AEP-NRC-2023-32, Response to NRC Regulatory Issue Summary 2023-1 Preparation and Scheduling of Operator Licensing Examinations2023-06-0606 June 2023
Response to NRC Regulatory Issue Summary 2023-1 Preparation and Scheduling of Operator Licensing Examinations
AEP-NRC-2023-33, Renewable Operating Permit2023-06-0505 June 2023
Renewable Operating Permit
AEP-NRC-2023-30, Follow-Up Notification of Ph Non-Compliance for Turbine Room Sump2023-06-0101 June 2023
Follow-Up Notification of Ph Non-Compliance for Turbine Room Sump
AEP-NRC-2023-27, Annual Radiological Environmental Operating Report2023-05-15015 May 2023
Annual Radiological Environmental Operating Report
ML23131A3282023-05-11011 May 2023
D.C. Cook Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection 05000315/2023404 and 05000316/2023404
IR 05000315/20230012023-05-0303 May 2023
Integrated Inspection Report 05000315/2023001 and 05000316/2023001
AEP-NRC-2023-19, Annual Radioactive Effluent Release Report2023-04-30030 April 2023
Annual Radioactive Effluent Release Report
ML23117A0062023-04-27027 April 2023
Review of the Spring 2022 Steam Generator Tube Inspections Report
ML23114A1142023-04-25025 April 2023
Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection
AEP-NRC-2023-23, Annual Report of Individual Monitoring for 20222023-04-24024 April 2023
Annual Report of Individual Monitoring for 2022
AEP-NRC-2023-24, Notification of Ph Non-Compliance for Turbine Room Sump2023-04-12012 April 2023
Notification of Ph Non-Compliance for Turbine Room Sump
AEP-NRC-2023-20, Annual Report of Property Insurance2023-04-0303 April 2023
Annual Report of Property Insurance
AEP-NRC-2023-15, Decommissioning Funding Status Report2023-03-28028 March 2023
Decommissioning Funding Status Report
ML23076A0212023-03-20020 March 2023
Request for Information for NRC Commercial Grade Dedication Inspection; Inspection Report 05000315/2023011; 05000316/2023011
IR 05000315/20234012023-03-16016 March 2023
Security Baseline Inspection Report 05000315/2023401 and 05000316/2023401
ML23066A1882023-03-0707 March 2023
Information Request to Support Upcoming Problem Identification and Resolution (Pi&R) Inspection at Donald C. Cook Nuclear Plant
IR 05000315/20220062023-03-0101 March 2023
Annual Assessment Letter for Donald C. Cook Nuclear Plant, Units 1 and 2 (Report 05000315/2022006 and 05000316/2022006)
IR 05000315/20220042023-02-0101 February 2023
Integrated Inspection Report 05000315/2022004 and 05000316/2022004 and Exercise of Enforcement Discretion
AEP-NRC-2023-11, Form OAR-1, Owner'S Activity Report2023-01-31031 January 2023
Form OAR-1, Owner'S Activity Report
IR 05000315/20230102023-01-31031 January 2023
Phase 4 Post-Approval License Renewal Inspection Report 05000315/2023010 and 05000316/2023010
AEP-NRC-2023-02, Request for Approval of Change Regarding Neutron Flux Instrumentation2023-01-26026 January 2023
Request for Approval of Change Regarding Neutron Flux Instrumentation
ML22363A5622023-01-0404 January 2023
Relief Request ISIR-5-06 Related to ASME Code Case N-729-6 Supplemental Examination Requirements of Reactor Vessel Closure Head Penetration Nozzles
AEP-NRC-2022-66, Report Per Technical Specification 5.6.6 for Inoperability of Unit 2 Post Accident Monitoring Neutron Flux Monitoring2022-12-15015 December 2022
Report Per Technical Specification 5.6.6 for Inoperability of Unit 2 Post Accident Monitoring Neutron Flux Monitoring
AEP-NRC-2022-46, Notification of Deviation from Electric Power Research Institute (EPRI) Materials Reliability Program 2019-008, Interim Guidance for NEI 03-08 Needed Requirements for Us PWR Plants for Management of Thermal Fatigue in2022-12-12012 December 2022
Notification of Deviation from Electric Power Research Institute (EPRI) Materials Reliability Program 2019-008, Interim Guidance for NEI 03-08 Needed Requirements for Us PWR Plants for Management of Thermal Fatigue in
ML22340A1392022-11-30030 November 2022
Submittal of Revision 31 to Updated Final Safety Analysis Report and 10CFR50.71(e) Updated and Related Site Change Reports
IR 05000315/20220112022-11-0404 November 2022
Design Basis Assurance Inspection (Teams) Inspection Report 05000315/2022011 and 05000316/2022011
IR 05000315/20220032022-10-28028 October 2022
Integrated Inspection Report 05000315/2022003 and 05000316/2022003
AEP-NRC-2022-58, U1C31 Steam Generator Tube Inspection Report2022-10-24024 October 2022
U1C31 Steam Generator Tube Inspection Report
AEP-NRC-2022-61, Request for Relief Related to American Society of Mechanical Engineers (ASME) Code Case N-729-6 Supplemental Examination Requirements, ISIR-5-062022-10-24024 October 2022
Request for Relief Related to American Society of Mechanical Engineers (ASME) Code Case N-729-6 Supplemental Examination Requirements, ISIR-5-06
2024-01-08
[Table view] |
Text
UNITED STATES ember 4, 2013
SUBJECT:
DONALD C. COOK NUCLEAR POWER PLANT, UNITS 1 AND 2, NRC INSPECTION REPORT 05000315/2013407; 05000316/2013407
Dear Mr. Weber:
On September 20, 2013, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at your Donald C. Cook Nuclear Power Plant, Units 1 and 2. The inspection covered one or more of the key attributes of the security cornerstone of the NRCs Reactor Oversight Process. The enclosed inspection report documents the inspection results, which were discussed on September 20, 2013, with Mr. S. Partin and other members of your staff.
The inspection examined activities conducted under your license as they relate to security and compliance with the Commissions rules and regulations and with the conditions of your license.
The inspector reviewed selected procedures and records, observed activities, and interviewed personnel.
No findings were identified during this inspection.
In accordance with Title 10 of the Code of Federal Regulations (10 CFR) 2.390, Public Inspections, Exemptions, Request for Withholding, of the NRC's "Rules of Practice," a copy of this letter will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records System (PARS) component of NRC's Agencywide Documents Access and Management System (ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).
However, the material enclosed herewith contains Security-Related Information in accordance with 10 CFR 2.390(d)(1) and its disclosure to unauthorized individuals could present a security vulnerability. Therefore, the material in the enclosure will not be made available electronically for public inspection in the NRC Public Document Room or from the PARS component of NRCs ADAMS.
Enclosure 1 contains Sensitive Unclassified Non-Safeguards Information. When separated from Enclosure 1, this transmittal document is decontrolled. If you choose to provide a response and Security-Related Information is necessary to provide an acceptable response, please mark your entire response Security-Related Information Withhold from public disclosure under 10 CFR 2.390 in accordance with 10 CFR 2.390(d)(1)
and follow the instructions for withholding in 10 CFR 2.390 (b)(1). In accordance with 10 CFR 2.390(b)(1)(ii), the NRC is waiving the affidavit requirements for your response.
Should you have any questions concerning this inspection, we will be pleased to discuss them with you.
Sincerely,
/RA/ By John B. Giessner Acting For/
Richard A. Skokowski, Chief Plant Support Branch Division of Reactor Safety Docket Nos. 50-315; 50-316 License Nos. DPR-58; DPR-74 Nonpublic Enclosure 1: Inspection Report 05000315/2013407; 05000316/2013407 w/Attachment 1: Supplemental Information (Nonpublic)
Public Enclosure 2: Inspection Report 05000315/2013407; 05000316/2013407 w/Attachment 2: Supplemental Information (Public)
cc w/Enclosure 1: S. Coker, NSIR/DSO/DDSO/ST R. Albert, NSIR T. Dimitriadis, RI B. Desai, RII M. Haire, RIV K. Yale, State Liaison Officer, State of Michigan cc w/o Enclosure 1: Distribution via ListServTM cc w/Enclosure 2: Distribution via ListServ' U. S. NUCLEAR REGULATORY COMMISSION
REGION III
Docket Nos: 05000315; 05000316 License Nos: DPR-58; DPR-74 Report No: 05000315/2013407; 05000316/2013407 Licensee: Indiana Michigan Power Company Facility: Donald C. Cook Nuclear Power Plant, Units 1 and 2 Location: Bridgman, Michigan Dates: September 16 through September 20, 2013 Inspector: J. Maynen, Senior Physical Security Inspector Approved by: R. Skokowski, Chief Plant Support Branch Division of Reactor Safety Enclosure 2
SUMMARY OF FINDINGS
IR 05000315/2013407; 05000316/2013407; 09/16/2013 - 09/20/2013, Donald C. Cook Nuclear
Power Plant, Units 1 and 2; Routine Security Baseline Inspection.
This report covers a one week period of announced routine baseline inspection on security.
The inspection was conducted by one Region III physical security inspector. No findings were identified. The NRCs program for overseeing the safe operation of commercial nuclear power reactors is described in NUREG-1649, Reactor Oversight Process.
A. Inspector-Identified and Self-Revealed Findings
Cornerstone: Security
No findings were identified.
Licensee-Identified Violations
None.
REPORT DETAILS
OTHER ACTIVITIES
4OA5 Other Activities
.1 Inspection of Confirmatory Order EA-12-005
On June 28, 2012, the NRC issued Confirmatory Order EA-12-005 (Order) to the licensee.
The elements of the agreement between the U.S. Nuclear Regulatory Commission (NRC)and the licensee consisted of the following three specific actions:
Section V, Item 1.
Within 90 days of the effective date of the Order, develop a lessons-learned presentation and within 180 days of the effective date of the Order, present these lessons-learned to first line supervisors and above.
Section V, Item 2.
Within 365 days of the effective date of the Order, develop and present the facts and lessons learned at an industry FFD forum and a broader industry forum.
Section V, Item 3.
Notify the NRC Regional Administrator, Region III, within 30 days of the completion of all actions described in the Order.
A lessons-learned presentation was developed on August 1, 2012, and the site supervisors and managers were briefed on the issue at the site leadership meeting held on October 3, 2012. The licensee made arrangements to ensure that supervisors and managers who did not attend the meeting received the briefing prior to resuming supervisory duties.
On June 5, 2013, the Site Vice President presented the facts and lessons learned to a broad industry forum, including industry FFD management and senior management personnel, at the annual USA/STARS Annual Conference.
On June 20, 2013, the NRC Regional Administrator, Region III, was notified of the completion of the actions required by the Order.
The inspectors independently verified the actions completed by the licensee as required by Section V of Confirmatory Order EA-12-005.
4OA6 Management Meetings
.1 Exit Meeting
The inspector presented the inspection results to Mr. S. Partin and other members of licensee management at the conclusion of the inspection on September 20, 2013.
The inspector asked the licensee whether any materials examined during the inspection should be considered proprietary. No proprietary information was identified.
ATTACHMENT 2:
SUPPLEMENTAL INFORMATION
KEY POINTS OF CONTACT
Licensee
- S. Partin, Plant Manager
- C. Hutchinson, Director, Nuclear Site Services
- J. Carter, Security
- K. Henderson, Regulatory Affairs
Nuclear Regulatory Commission
- J. Ellegood, Senior Resident Inspector
- P. LaFlamme, Resident Inspector
LIST OF ITEMS OPENED, CLOSED, AND DISCUSSED
Opened, Closed, and Discussed
None
LIST OF DOCUMENTS REVIEWED
