|
|
| (10 intermediate revisions by the same user not shown) |
| Line 2: |
Line 2: |
| | number = ML13189A232 | | | number = ML13189A232 |
| | issue date = 07/15/2013 | | | issue date = 07/15/2013 |
| | title = Donald C. Cook Nuclear Plant, Unit 1, Summary of Conference Telephone Call Regarding the 2013 Steam Generator Tube Inspections | | | title = Summary of Conference Telephone Call Regarding the 2013 Steam Generator Tube Inspections |
| | author name = Wengert T J | | | author name = Wengert T |
| | author affiliation = NRC/NRR/DORL/LPLIII-1 | | | author affiliation = NRC/NRR/DORL/LPLIII-1 |
| | addressee name = Weber L J | | | addressee name = Weber L |
| | addressee affiliation = Indiana Michigan Power Co | | | addressee affiliation = Indiana Michigan Power Co |
| | docket = 05000315 | | | docket = 05000315 |
| | license number = DPR-058 | | | license number = DPR-058 |
| | contact person = Wengert T J | | | contact person = Wengert T |
| | case reference number = TAC MF0875 | | | case reference number = TAC MF0875 |
| | package number = ML13189A226 | | | package number = ML13189A226 |
| Line 15: |
Line 15: |
| | page count = 5 | | | page count = 5 |
| | project = TAC:MF0875 | | | project = TAC:MF0875 |
| | | stage = Other |
| }} | | }} |
|
| |
|
| =Text= | | =Text= |
| {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555*0001 July 15, 2013 Mr. Lawrence Senior Vice President and Chief Nuclear Officer Indiana Michigan Power Company Nuclear Generation Group One Cook Place Bridgman, MI 49106 | | {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555*0001 July 15, 2013 Mr. Lawrence J. Weber Senior Vice President and Chief Nuclear Officer Indiana Michigan Power Company Nuclear Generation Group One Cook Place Bridgman, MI 49106 |
|
| |
|
| SUBJECT: DONALD C. COOK NUCLEAR PLANT, UNIT 1 -SUMMARY OF CONFERENCE TELEPHONE CALL REGARDING THE 2013 STEAM GENERATOR TUBE INSPECTIONS (TAC NO. MF0875) | | ==SUBJECT:== |
| | DONALD C. COOK NUCLEAR PLANT, UNIT 1 - |
| | |
| | ==SUMMARY== |
| | OF CONFERENCE TELEPHONE CALL REGARDING THE 2013 STEAM GENERATOR TUBE INSPECTIONS (TAC NO. MF0875) |
|
| |
|
| ==Dear Mr. Weber:== | | ==Dear Mr. Weber:== |
| On April 12, 2013, the U.S. Nuclear Regulatory Commission (NRC) staff participated in a conference call with Indiana Michigan Power Gompany (I&M) representatives regarding the ongoing steam generator (SG) tube inspection activities conducted during the 2012 outage at the Donald C. Cook Nuclear Plant, Unit 1. The NRC follows the results of the industry's SG inspections in order*to maintain an awareness of the condition of the SGs and the types of tube degradation mechanisms that are active. The enclosed documentation of the telephone call is provided to I&M for information. The information provided by I&M in support of the discussion (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 13189A222) is available to the public. Based on the information provided during the conference call, the NRC staff did not identify any issues that warranted additional follow-up action at this time. If there are any questions, please contact me at 301-415-4037.
| |
|
| |
|
| Sincerely,Thomas J. Weng , Senior Project Manager Plant Licensing Branch 111-1 Division of Operating Reactor licensing Office of Nuclear Reactor Regulation Docket No. 50-315 | | On April 12, 2013, the U.S. Nuclear Regulatory Commission (NRC) staff participated in a conference call with Indiana Michigan Power Gompany (I&M) representatives regarding the ongoing steam generator (SG) tube inspection activities conducted during the 2012 outage at the Donald C. Cook Nuclear Plant, Unit 1. The NRC follows the results of the industry's SG inspections in order*to maintain an awareness of the condition of the SGs and the types of tube degradation mechanisms that are active. |
| | The enclosed documentation of the telephone call is provided to I&M for information. The information provided by I&M in support of the discussion (Agencywide Documents Access and Management System (ADAMS) Accession No. ML13189A222) is available to the public. Based on the information provided during the conference call, the NRC staff did not identify any issues that warranted additional follow-up action at this time. If there are any questions, please contact me at 301-415-4037. |
| | Sincerely, Thomas J. Weng , Senior Project Manager Plant Licensing Branch 111-1 Division of Operating Reactor licensing Office of Nuclear Reactor Regulation Docket No. 50-315 |
| | |
| | ==Enclosure:== |
| | |
| | Conference Call Summary cc w/encl: Distribution via ListServ |
| | |
| | ==SUMMARY== |
| | OF CONFERENCE CALL WITH INDIANA MICHIGAN POWER COMPANY REGARDING THE SPRING 2013 STEAM GENERATOR TUBE INSPECTION RESULTS DONALD C. COOK NUCLEAR PLANT, UNIT 1 DOCKET NUMBER 50-315 On April 12, 2013, the Nuclear Regulatory Commission (NRC) staff participated in a conference call with Indiana Michigan Power Company (the licensee) representatives regarding ongoing steam generator (SG) tube inspection activities at Donald C. Cook Nuclear Plant (CNP), Unit 1. |
| | In support of the conference call, the licensee provided a document summarizing some of the inspection results. This document is located in the NRC's Agencywide Documents Access and Management System (ADAMS) at Accession No. ML13189A222. |
| | CNP Unit 1 has four model 51 R recirculating SGs designed and fabricated by Babcock and Wilcox International. Each SG has 3,496 thermally treated, Alloy 690 tubes that have an outside diameter of 0.875 inches, and a nominal wall thickness of 0.049 inches. The tubes are |
| | . supported by Type 410 stainless steel, lattice-grid tube supports, and flat fan bars. The tubes were hydraulically expanded at each end for the full depth of the tubesheet. |
| | Information provided by the licensee is summarized below: |
| | * At the time of the call the licensee indicated that it was approximately 75 percent complete with SG tube inspections and that the results of the inspections are consistent with their expectations (projections). The maximum wear depth expected during this inspection is 33 percent through wall. At the time of the call the maximum depth detected was 32 percent through wall. The licensee stated that 1200 new indications were projected, but only 450 had been detected at the time of the call. |
| | * The licensee indicated that the average through wall wear growth for SGs 11, 12, 13, and 14 are 2.7, 3.0,2.8, and 1.76 percent, respectively. The standard deviation ranged from 1.18 to 1.62 percent. |
| | * The extent of the X-probe inspections at the top of the tubesheet (ITS) is from the tube end to the first support. The tubes inspected included all tubes around the periphery of the tube bundle and all tubes adjacent to the divider lane. This is the first outage that the X-probe is being used at CNPUnit 1. |
| | o There are approximately 20 tubes per SG that have wear scars greater than 20 percent though wall. |
| | * The licensee indicated that there was a typographical error on page 2 of their notes. |
| | The "Lattice Grid Significant Indications" is not at the "fan bar" but rather at "lattice grid 4." |
| | Enclosure |
| | |
| | -2 |
| | * The licensee indicated that it performed SG channel head inspections. In particular, the tubesheet, divider plate, and cladding were inspected and nothing abnormal was reported. |
| | * During the last SG inspection outage, 100 percent of the tubes were inspected. There was an unexpected increase in the number of indications of wear. The root cause for the large number of wear indications was that the SGs are operating close to a resonant condition. The original SGs were originally designed to operate at a primary pressure of 2235 pounds per square inch (psi) and a temperature of 574°F. To extend the life of the original SGs, plant primary pressure and temperature were reduced (prior to the replacement in 2000) to 2085 psi and 556°F, respectively. To address the increase in the number of wear indications, the licensee plans to restore primary pressure and temperature to their original values of 2235 psi and 574°F during the next refueling outage. This should result in secondary side pressure increasing from 650 psi to 800 psi which should move the SG out of the resonant condition. After one cycle of operating at the increased reactor coolant system pressure and temperature, the licensee currently plans another SG tube inspection outage to confirm the adequacy of their corrective actions. |
| | * The licensee plans to inspect 100 percent of the tubes during the next refueling outage. |
| | * Foreign object search and retrieval was currently ongoing in SG 11. Three objects had been identified. Two were retrieved, and attempts to retrieve the third object were scheduled for later in the day. |
| | * Additional inspections of the foreign object in SG 13 will be performed to determine the nature of the object and to attempt to retrieve it. |
| | * The licensee indicated that if a foreign object cannot be removed, they will perform an engineering evaluation and will most likely stabilize and plug the tubes surrounding the part. . |
| | * Only 75 pounds of sludge were removed during sludge lancing operations in the prior outage, and this was after 3 cycles of operation. Prior deposit mapping indicated about 800 pounds of deposits are in the SGs. |
| | The following abbreviations are used in the document provided by the licensee: |
| | CL = cold leg |
| | = |
| | ECT eddy current test |
| | = |
| | EPRI Electric Power Research Institute |
| | = |
| | FO foreign object |
| | = |
| | FOSAR foreign object search and retrieval |
| | = |
| | HL hot leg |
| | = |
| | MFP main feedwater pump NEI =Nuclear Energy Institute |
| | = |
| | PLP possible loose part |
| | = |
| | SI special interest |
| | |
| | - 3 SSI :: secondary side inspection* |
| | ITS:: top of tubesheet TW:: through wall The NRC staff did not identify any issues that required follow-up action at this time; however, the staff asked.to be notified in the event that any unusual conditions were detected during the remainder of the outage or if a tube fails an in-situ pressure test. |
| | |
| | July 15, 2013 Mr. Lawrence J. Weber Senior Vice President and Chief Nuclear Officer Indiana Michigan Power Company Nuclear Generation Group One Cook Place Bridgman, MI 49106 |
|
| |
|
| ===Enclosure:=== | | ==SUBJECT:== |
| Conference Call Summary cc w/encl: Distribution via ListServ SUMMARY OF CONFERENCE CALL WITH INDIANA MICHIGAN POWER COMPANY REGARDING THE SPRING 2013 STEAM GENERATOR TUBE INSPECTION RESULTS DONALD C. COOK NUCLEAR PLANT, UNIT 1 DOCKET NUMBER 50-315 On April 12, 2013, the Nuclear Regulatory Commission (NRC) staff participated in a conference call with Indiana Michigan Power Company (the licensee) representatives regarding ongoing steam generator (SG) tube inspection activities at Donald C. Cook Nuclear Plant (CNP), Unit 1. In support of the conference call, the licensee provided a document summarizing some of the inspection results. This document is located in the NRC's Agencywide Documents Access and Management System (ADAMS) at Accession No. ML 13189A222. CNP Unit 1 has four model 51 R recirculating SGs designed and fabricated by Babcock and Wilcox International. Each SG has 3,496 thermally treated, Alloy 690 tubes that have an outside diameter of 0.875 inches, and a nominal wall thickness of 0.049 inches. The tubes are . supported by Type 410 stainless steel, lattice-grid tube supports, and flat fan bars. The tubes were hydraulically expanded at each end for the full depth of the tubesheet. Information provided by the licensee is summarized below: At the time of the call the licensee indicated that it was approximately 75 percent complete with SG tube inspections and that the results of the inspections are consistent with their expectations (projections). The maximum wear depth expected during this inspection is 33 percent through wall. At the time of the call the maximum depth detected was 32 percent through wall. The licensee stated that 1200 new indications were projected, but only 450 had been detected at the time of the call. The licensee indicated that the average through wall wear growth for SGs 11, 12, 13, and 14 are 2.7, 3.0,2.8, and 1.76 percent, respectively. The standard deviation ranged from 1.18 to 1.62 percent. The extent of the X-probe inspections at the top of the tubesheet (ITS) is from the tube end to the first support. The tubes inspected included all tubes around the periphery of the tube bundle and all tubes adjacent to the divider lane. This is the first outage that the X-probe is being used at CNPUnit 1. There are approximately 20 tubes per SG that have wear scars greater than 20 percent though wall. The licensee indicated that there was a typographical error on page 2 of their notes. The "Lattice Grid Significant Indications" is not at the "fan bar" but rather at "lattice grid 4." Enclosure
| | DONALD C. COOK NUCLEAR PLANT, UNIT 1 - |
| -2 The licensee indicated that it performed SG channel head inspections. In particular, the tubesheet, divider plate, and cladding were inspected and nothing abnormal was reported. During the last SG inspection outage, 100 percent of the tubes were inspected. There was an unexpected increase in the number of indications of wear. The root cause for the large number of wear indications was that the SGs are operating close to a resonant condition. The original SGs were originally designed to operate at a primary pressure of 2235 pounds per square inch (psi) and a temperature of 574°F. To extend the life of the original SGs, plant primary pressure and temperature were reduced (prior to the replacement in 2000) to 2085 psi and 556°F, respectively. To address the increase in the number of wear indications, the licensee plans to restore primary pressure and temperature to their original values of 2235 psi and 574°F during the next refueling outage. This should result in secondary side pressure increasing from 650 psi to 800 psi which should move the SG out of the resonant condition. After one cycle of operating at the increased reactor coolant system pressure and temperature, the licensee currently plans another SG tube inspection outage to confirm the adequacy of their corrective actions. The licensee plans to inspect 100 percent of the tubes during the next refueling outage. Foreign object search and retrieval was currently ongoing in SG 11. Three objects had been identified. Two were retrieved, and attempts to retrieve the third object were scheduled for later in the day. Additional inspections of the foreign object in SG 13 will be performed to determine the nature of the object and to attempt to retrieve it. The licensee indicated that if a foreign object cannot be removed, they will perform an engineering evaluation and will most likely stabilize and plug the tubes surrounding the part. . Only 75 pounds of sludge were removed during sludge lancing operations in the prior outage, and this was after 3 cycles of operation. Prior deposit mapping indicated about 800 pounds of deposits are in the SGs. The following abbreviations are used in the document provided by the licensee: CL = cold leg ECT =eddy current test EPRI =Electric Power Research Institute FO =foreign object FOSAR =foreign object search and retrieval HL =hot leg MFP =main feedwater pump NEI =Nuclear Energy Institute PLP =possible loose part SI =special interest
| |
| -SSI :: secondary side inspection* ITS:: top of tubesheet TW:: through wall The NRC staff did not identify any issues that required follow-up action at this time; however, the staff asked.to be notified in the event that any unusual conditions were detected during the remainder of the outage or if a tube fails an in-situ pressure test.
| |
|
| |
|
| July 15, 2013 Mr. Lawrence Senior Vice President and Chief Nuclear Officer Indiana Michigan Power Company Nuclear Generation Group One Cook Place Bridgman, MI 49106 DONALD C. COOK NUCLEAR PLANT, UNIT 1 -SUMMARY OF CONFERENCE TELEPHONE CALL REGARDING THE 2013 STEAM GENERATOR TUBE INSPECTIONS (TAC NO. MF0875)
| | ==SUMMARY== |
| | OF CONFERENCE TELEPHONE CALL REGARDING THE 2013 STEAM GENERATOR TUBE INSPECTIONS (TAC NO. MF0875) |
|
| |
|
| ==Dear Mr. Weber:== | | ==Dear Mr. Weber:== |
| On April 12, 2013, the U.S. Nuclear Regulatory Commission (NRC) staff participated in a conference cal.1 with Indiana Michigan Power Company (I&M) representatives regarding the ongoing steam generator (SG) tube inspection activities conducted during the 2012 outage at the Donald C. Cook Nuclear Plant, Unit 1. The NRC follows the results of the industry's SG inspections in order to maintain an awareness of the condition of the SGs and the types of tube degradation mechanisms that are active. The enclosed documentation of the telephone call is provided to I&M for information. The information provided by I&M in support of the discussion (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 13189A222) is available to the public. Based on the information provided during the conference call, the NRC staff did not identify any issues that warranted additional follow-up action at this time. If there are any questions, please contact* me at 301-415-4037.
| |
|
| |
|
| Sincerely,IRAJ Thomas J. Wengert, Senior Project Manager Plant Licensing Branch 111-1 Division of Operating Reactor licensing Office of Nuclear Reactor Regulation Docket No. 50-315 | | On April 12, 2013, the U.S. Nuclear Regulatory Commission (NRC) staff participated in a conference cal.1 with Indiana Michigan Power Company (I&M) representatives regarding the ongoing steam generator (SG) tube inspection activities conducted during the 2012 outage at the Donald C. Cook Nuclear Plant, Unit 1. The NRC follows the results of the industry's SG inspections in order to maintain an awareness of the condition of the SGs and the types of tube degradation mechanisms that are active. |
| | The enclosed documentation of the telephone call is provided to I&M for information. The information provided by I&M in support of the discussion (Agencywide Documents Access and Management System (ADAMS) Accession No. ML13189A222) is available to the public. Based on the information provided during the conference call, the NRC staff did not identify any issues that warranted additional follow-up action at this time. If there are any questions, please contact* |
| | me at 301-415-4037. |
| | Sincerely, IRAJ Thomas J. Wengert, Senior Project Manager Plant Licensing Branch 111-1 Division of Operating Reactor licensing Office of Nuclear Reactor Regulation Docket No. 50-315 |
| | |
| | ==Enclosure:== |
|
| |
|
| ===Enclosure:===
| | Conference Call Summary cc w/encl: Distribution via ListServ DISTRIBUTION: |
| Conference Call Summary cc w/encl: Distribution via ListServ DISTRIBUTION: PUBLIC LPL3-1 R/F RidsNrrPMPrairielsland Resource RidsNrrDorl Resource RidsNrrDeEsgb Resource JGiessner, Rill RidsNrrDorlLpL3-1 Resource RidsNrrLABTully Resource .1 Ellegood, Rill RidsAcrsAcnw_MailCTR Resource KKarwoski, NRR AObodoako, NRR OHills, Rill TBilik, Rill ADAMS Package Accession No.: ML 13189A226 ADAMS Accession No.: ML13189A232 Slides Accession No.: ML"8 memo dated 5122113 NRR-106 FICE NRRlLPL3-1/PM IESGB/BC NRR/LPL3-1/BC ME lWen ert RCarlson TE 07111/13 07/15/13}} | | PUBLIC LPL3-1 R/F RidsNrrDorlLpL3-1 Resource KKarwoski, NRR RidsNrrPMPrairielsland Resource RidsNrrLABTully Resource AObodoako, NRR RidsNrrDorl Resource .1 Ellegood, Rill OHills, Rill RidsNrrDeEsgb Resource RidsAcrsAcnw_MailCTR Resource TBilik, Rill JGiessner, Rill ADAMS Package Accession No.: ML13189A226 ADAMS Accession No.: ML13189A232 Slides Accession No.: ML13189A222 "8 memo dated 5122113 NRR-106 FICE NRRlLPL3-1/PM NRR/LPL3 IESGB/BC NRR/LPL3-1/BC ME lWen ert RCarlson TE 07111/13 07/15/13}} |
Similar Documents at Cook |
|---|
Category:Letter
MONTHYEARIR 05000315/20240032024-10-31031 October 2024
Integrated Inspection Report 05000315/2024003 05000316/2024003 07200072/2024001 and Exercise of Enforcement Discretion
AEP-NRC-2024-77, U2C28 Steam Generator Tube Inspection Report2024-10-21021 October 2024
U2C28 Steam Generator Tube Inspection Report
AEP-NRC-2024-80, Independent Spent Fuel Storage Installation Registration of Dry Spent Fuel Storage Cask2024-10-15015 October 2024
Independent Spent Fuel Storage Installation Registration of Dry Spent Fuel Storage Cask
AEP-NRC-2024-79, Unit 2, Independent Spent Fuel Storage Installation - Registration of Dry Spent Storage Cask2024-09-26026 September 2024
Unit 2, Independent Spent Fuel Storage Installation - Registration of Dry Spent Storage Cask
AEP-NRC-2024-78, Reply to a Notice of Violation: EA-24-0472024-09-23023 September 2024
Reply to a Notice of Violation: EA-24-047
05000316/LER-2024-002-01, Manual Reactor Trip Following Rapid Downpower for Steam Leak2024-09-12012 September 2024
Manual Reactor Trip Following Rapid Downpower for Steam Leak
IR 05000315/20244022024-09-10010 September 2024
Security Baseline Inspection Report 05000315/2024402 and 05000316/2024402, Independent Spent Fuel Storage Installation Security Inspection Report 07200072/2024401
AEP-NRC-2024-69, Core Operating Limits Report2024-09-0909 September 2024
Core Operating Limits Report
IR 05000315/20243012024-09-0505 September 2024
NRC Initial License Examination Report 05000315/2024301 and 05000316/2024301
ML24225A0022024-09-0303 September 2024
Issuance of Amendment Nos. 363 and 344 Revising Technical Specifications Section 3.8.1, AC Sources-Operating, for a One-Time Extension of a Completion Time
IR 05000315/20240112024-08-30030 August 2024
NRC Inspection Report 05000315/2024011 and 05000316/2024011 and Notice of Violation
AEP-NRC-2024-76, Unit 2 - Supplement to License Amendment Request for One-Time Extension of Completion Time for Inoperable AC Source - Operating2024-08-28028 August 2024
Unit 2 - Supplement to License Amendment Request for One-Time Extension of Completion Time for Inoperable AC Source - Operating
AEP-NRC-2024-51, Annual Report of Loss-Of-Coolant Accident Evaluation Model Changes2024-08-28028 August 2024
Annual Report of Loss-Of-Coolant Accident Evaluation Model Changes
05000316/LER-2024-003, Plant Shutdown Required by Technical Specifications Due to Reactor Coolant System Identified Leakage2024-08-22022 August 2024
Plant Shutdown Required by Technical Specifications Due to Reactor Coolant System Identified Leakage
IR 05000315/20240052024-08-21021 August 2024
Updated Inspection Plan for Donald C. Cook Nuclear Plant, Units 1 and 2 (Report 05000315/2024005 and 05000316/2024005)
AEP-NRC-2024-61, Unit 2 - Response to Request for Additional Information for Neutron Flux Instrumentation License Amendment Request2024-08-15015 August 2024
Unit 2 - Response to Request for Additional Information for Neutron Flux Instrumentation License Amendment Request
ML24221A2702024-08-0808 August 2024
Unit 2 Independent Spent Fuel Storage Installation - Registration of Dry Spent Fuel Storage Cask
AEP-NRC-2024-62, Unit 2, Independent Spent Fuel Storage Installation, Registration of Dry Spent Fuel Storage Cask2024-08-0707 August 2024
Unit 2, Independent Spent Fuel Storage Installation, Registration of Dry Spent Fuel Storage Cask
ML24256A1482024-08-0202 August 2024
2024 Post Examination Submittal Letter
AEP-NRC-2024-47, Form OAR-1, Owners Activity Report2024-07-30030 July 2024
Form OAR-1, Owners Activity Report
ML24183A0162024-07-25025 July 2024
Review of Reactor Vessel Material Surveillance Program Capsule W Technical Report
ML24169A2142024-07-25025 July 2024
Issuance of Amendment No. 362 Regarding Change to Technical Specification 3.4.12, Low Temperature Overpressure Protection System
IR 05000315/20240022024-07-24024 July 2024
Integrated Inspection Report 05000315/2024002 and 05000316/2024002
05000316/LER-2024-002, Manual Reactor Trip Following Rapid Downpower for Steam Leak2024-07-15015 July 2024
Manual Reactor Trip Following Rapid Downpower for Steam Leak
ML24197A1262024-07-15015 July 2024
Unit 2 - Request for Additional Information (RAI) for License Amendment Request for One-Time Extension of Completion Time for Inoperable AC Source - Operating
ML24191A0692024-07-0909 July 2024
Operator Licensing Examination Approval - Donald C. Cook Nuclear Power Plant, July 2024
AEP-NRC-2024-56, Unit 2, Independent Spent Fuel Storage Installation, Registration of Dry Spent Fuel Storage Cask2024-07-0808 July 2024
Unit 2, Independent Spent Fuel Storage Installation, Registration of Dry Spent Fuel Storage Cask
AEP-NRC-2024-48, Response to Request for Additional Information (RAI) for License Amendment Request for One-Time Extension of Completion Time for Inoperable AC Source - Operating2024-07-0202 July 2024
Response to Request for Additional Information (RAI) for License Amendment Request for One-Time Extension of Completion Time for Inoperable AC Source - Operating
ML24176A1012024-06-21021 June 2024
57143-EN 57143 - Paragon Energy Solutions - Update 1 (Final) - 10CFR Part 21 Final Notification: P21-05242024-FN, Rev. 0
AEP-NRC-2024-45, Report Per Technical Specification 5.6.6 for Inoperability of Post Accident Monitoring Neutron Flux Monitoring2024-06-13013 June 2024
Report Per Technical Specification 5.6.6 for Inoperability of Post Accident Monitoring Neutron Flux Monitoring
ML24163A0132024-06-12012 June 2024
Request for Information for the NRC Age-Related Degradation Inspection: Inspection Report 05000315/2024012 and 05000316/2024012
ML24159A2522024-05-30030 May 2024
10 CFR 50.71(e) Update and Related Site Change Reports
AEP-NRC-2024-23, Core Operating Limits Report2024-05-23023 May 2024
Core Operating Limits Report
05000316/LER-2024-001, Reactor Trip Due to Main Turbine Trip from a High-High Thrust Bearing Position Trip2024-05-20020 May 2024
Reactor Trip Due to Main Turbine Trip from a High-High Thrust Bearing Position Trip
ML24141A2162024-05-20020 May 2024
—Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection
AEP-NRC-2024-40, Unit 2 - Supplement to License Amendment Request for One-Time Extension of Completion Time for Inoperable AC Source - Operating2024-05-16016 May 2024
Unit 2 - Supplement to License Amendment Request for One-Time Extension of Completion Time for Inoperable AC Source - Operating
AEP-NRC-2024-41, Annual Radiological Environmental Operating Report2024-05-15015 May 2024
Annual Radiological Environmental Operating Report
AEP-NRC-2024-07, Unit 2 - Transmittal of Report of Changes to the Emergency Plan2024-05-14014 May 2024
Unit 2 - Transmittal of Report of Changes to the Emergency Plan
AEP-NRC-2024-26, Transmittal of Donald C. Cook Nuclear Plant, Emergency Plan Revision 492024-05-14014 May 2024
Transmittal of Donald C. Cook Nuclear Plant, Emergency Plan Revision 49
IR 05000315/20240012024-05-14014 May 2024
Integrated Inspection Report 05000315/2024001 and 05000316/2024001
IR 05000315/20244012024-05-14014 May 2024
– Security Baseline Inspection Report 05000315/2024401 and 05000316/2024401
AEP-NRC-2024-24, Form OAR-1, Owners Activity Report2024-05-0707 May 2024
Form OAR-1, Owners Activity Report
ML24115A2152024-05-0707 May 2024
LTR: CNP Non-Acceptance with Opportunity TS 3-8-1
ML24256A1472024-05-0606 May 2024
DC Cook 2024 NRC Examination Submittal Letter: Submittal
ML24116A0002024-05-0202 May 2024
– Regulatory Audit in Support of Review of the Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors
AEP-NRC-2024-35, Response to NRC Regulatory Issue Summary 2024-01 Preparation and Scheduling of Operator Licensing Examinations2024-04-30030 April 2024
Response to NRC Regulatory Issue Summary 2024-01 Preparation and Scheduling of Operator Licensing Examinations
AEP-NRC-2024-28, 2023 Annual Radioactive Effluent Release Report2024-04-29029 April 2024
2023 Annual Radioactive Effluent Release Report
AEP-NRC-2024-31, Annual Report of Individual Monitoring2024-04-24024 April 2024
Annual Report of Individual Monitoring
AEP-NRC-2024-02, Unit 2 License Amendment Request for One-Time Extension of Completion Time for Inoperable AC Source - Operating2024-04-0303 April 2024
Unit 2 License Amendment Request for One-Time Extension of Completion Time for Inoperable AC Source - Operating
AEP-NRC-2024-29, (CNP) Unit 2 - Request for Relief Related to American Society of Mechanical Engineers (ASME) Code Case N-729-6 Supplemental Examination Requirements, ISIR-5-072024-04-0303 April 2024
(CNP) Unit 2 - Request for Relief Related to American Society of Mechanical Engineers (ASME) Code Case N-729-6 Supplemental Examination Requirements, ISIR-5-07
2024-09-09
[Table view]
Category:Meeting Summary
MONTHYEARML24183A2292024-07-0101 July 2024
Summary of Public Outreach to Discuss the NRC 2023 End-Of-Cycle Plant Performance Assessment of Donald C. Cook Nuclear Plant, Units 1 and 2
ML24103A1872024-04-16016 April 2024
Summary of Meeting with Indiana Michigan Power Co., Regarding Surveillance Capsule Program for DC Cook Nuclear Plant, Unit 2
ML24031A5872024-02-0202 February 2024
Summary of Meeting with Indiana Michigan Power Company Regarding Neutron Flux Instrumentation for Donald C. Cook Nuclear Plant, Unit Nos. 1 and 2
ML23215A1662023-08-17017 August 2023
Summary of July 31, 2023, Meeting with Indiana Michigan Power Company Regarding Operating Power Sources for Donald C. Cook Nuclear Plant, Unit Nos. 1 and 2
ML23199A2402023-07-19019 July 2023
Summary of the July 13, 2023, Public Outreach to Discuss the NRC 2022 End-of-Cycle Plant Performance Assessment of Donald C. Cook Nuclear Plant, Units 1 and 2
ML22355A6022023-01-0303 January 2023
Summary of December 14, 2022, with Indiana Michigan Power Company to Discuss Potential Changes to the Emergency Plan for Donald C. Cook Nuclear Plant, Unit Nos. 1 and 2
ML22318A1992022-11-21021 November 2022
Summary of November 7, 2022, Meeting with Indiana Michigan Power Company Regarding Neutron Flux Instrumentation for Donald C. Cook Nuclear Plant, Unit Nos. 1 and 2
ML22154A5342022-06-0909 June 2022
Summary of the June 1, 2022, Public Outreach to Discuss the NRC 2021 End-Of-Cycle Plant Performance Assessment of Donald C. Cook Nuclear Plant
ML22011A2732022-01-13013 January 2022
Summary of Meeting with Indiana Michigan Power Company to Discuss Planned Final Response to Generic Letter 2004-02 for Donald C. Cook Nuclear Plant, Unit Nos. 1 and 2
ML21349B3092022-01-0303 January 2022
Summary of Meeting with Indiana Michigan Power Company to Discuss Potential Changes to the Quality Assurance Program for Donald C. Cook Nuclear Plant, Units 1 and 2
ML21202A1072021-07-23023 July 2021
Summary of July 20, 2021, with Indiana Michigan Power Company to Discuss Potential Changes to the Emergency Plan for Donald C. Cook Nuclear Plant, Unit Nos. 1 and 2
ML21196A5182021-07-15015 July 2021
July 8, 2021, Summary of Public Webinar to Discuss the NRC 2020 End-Of-Cycle Plant Performance Assessment of the Donald C. Cook Nuclear Plant
ML21082A0052021-03-24024 March 2021
Summary of March 19, 2021, with Indiana Michigan Power Company Regarding Containment Water Level Channels for Donald C. Cook Nuclear Plant, Unit Nos. 1 and 2
ML20349A0152020-12-17017 December 2020
Summary of November 30, 2020, Teleconference with Indiana Michigan Power Company Regarding a Planned License Amendment Request to Extend the Containment Integrated Leak Rate Testing Interval for Donald C. Cook Nuclear Plant, Unit No. 2
ML20282A2712020-10-14014 October 2020
Summary of October 2, 2020, Teleconference with Indiana Michigan Power Company Regarding Donald C. Cook Nuclear Plant, Unit No. 1
ML20248H4752020-09-10010 September 2020
Summary of August 6, 2020, Teleconference with Indian Michigan Power Company Related to Steam Generator Eddy Current Testing License Amendment Request
ML20209A6032020-07-27027 July 2020
Summary of the July 21, 2020, Public Webinar to Discuss the NRC 2019 End-of-Cycle Plant Performance Assessment of the Donald C. Cook Nuclear Plant, Units 1 and 2
ML20133K1282020-05-21021 May 2020
Summary of May 4, 2020, Teleconference with Indiana Michigan Power Company Regarding Donald C. Cook Nuclear Plant, Unit Nos. 1 and 2
ML20121A0692020-05-0404 May 2020
Summary of Teleconference with Indiana Michigan Power Company Regarding Donald C. Cook Nuclear Plant, Unit Nos. 1 and 2
ML20041C9492020-02-13013 February 2020
Summary of February 6, 2020, Teleconference with Indiana Michigan Power Company Regarding Donald C. Cook Nuclear Plant, Unit Nos. 1 and 2
ML19350A0552019-12-30030 December 2019
Summary of 12/12/2019 Meeting with Indiana Michigan Power Company, License Amendment Request for D.C. Cook Nuclear Plant, Units 1 and 2 to Delete Surveillance Requirement Related to Diesel Generator Load Test Resistor Banks
ML19212A5652019-07-30030 July 2019
Summary of Public Open House to Discuss NRC Activities and the 2018 End-Of-Cycle Performance Assessment of Donald C. Cook Nuclear Generating Plant, Units 1 and 2
ML19141A0622019-06-0606 June 2019
Summary of November 19, 2018, Meeting with Indiana Michigan Power Company Regarding Donald C. Cook Nuclear Plant, Unit Nos. 1 and 2
ML19099A3262019-04-16016 April 2019
Summary of Meeting with Indiana Michigan Power Company Regarding Donald C. Cook Nuclear Plant, Unit Nos. 1 and 2
ML19067A0482019-03-12012 March 2019
Summary of Public Teleconference with Indiana Michigan Power Co. (I&M) Review of LAR for Approval of Leak-Before-Break Methodology for Reactor Coolant System Small Diameter Piping (EPID-2019-LLA-0054)
ML18334A0402018-12-13013 December 2018
Summary of Meeting with Indian Michigan Power Company Regarding Donald C. Cook Nuclear Plant, Unit No. 1
ML18109A0692018-04-26026 April 2018
Summary of April 10, 2018, Meeting with Indiana Michigan Power Company Regarding Donald C. Cook Nuclear Plant, Unit Nos. 1 and 2
ML18052B0542018-02-26026 February 2018
Summary of February 15, 2018, Meeting with Indian Michigan Power Company Donald C. Cook Nuclear Plant, Unit Nos. 1 and 2 (EPID L-2018-LRM-0008
ML18018B1382018-01-22022 January 2018
Summary of Meeting with Indiana Michigan Power Company Regarding Donald C. Cook Nuclear Plant, Unit No. 1
ML17265A4922017-10-0404 October 2017
Summary of Meeting with Indiana Michigan Power Company Regarding Donald C. Cook Nuclear Plant, Unit Nos. 1 and 2 2
ML17235B1232017-08-23023 August 2017
Summary of the July 27, 2017, Open House to Discuss the 2016 End-of-Cycle Plant Performance Assessment of Donald C. Cook Nuclear Plant
ML17082A0762017-03-27027 March 2017
Summary of March 20, 2017, Meeting with Indiana Michigan Power Company Regarding Donald C. Cook Nuclear Plant, Unit Nos. 1 and 2
ML16308A1132016-11-16016 November 2016
Summary of October 27, 2016, Public Meeting with Indiana Michigan Power Company Regarding the Donald C. Cook Nuclear Plant, Units 1 and 2
ML16244A7062016-08-30030 August 2016
Summary of the August 22, 2016, Donald C. Cook Public Meeting
ML16193A5912016-07-15015 July 2016
Summary of Meeting with Indiana Michigan Power Company Regarding Donald C. Cook Nuclear Plant, Units 1 and 2
ML15271A0462015-10-0505 October 2015
Summary of Public Meeting with Indiana Michigan Power Company Regarding Donald C. Cook Nuclear Plant, Units 1 and 2
ML15237A3362015-09-0202 September 2015
Summary of August 24, 2015, Telephone Call to Provide Verbal Authorization of Relief Request ISIR-4-06, Alternate Repair of Socket Weld
ML15107A0982015-04-24024 April 2015
April 14, 2015, Summary of Meeting with Indiana Michigan Power Company Regarding Donald C. Cook Nuclear Plant, Units 1 and 2
ML14311A3182014-11-14014 November 2014
Summary of Conference Call with Donald C. Cook Nuclear Plant, Unit 1 Regarding the Fall 2014 Steam Generator Inspections
ML14231A0752014-08-27027 August 2014
Summary of the August 8, 2014, Pre-Application Meeting with American Electric Power Company to Discuss a Future License Amendment Request for Alternative Source Term and TSTF-490
ML14209A9422014-07-30030 July 2014
July 9, 2014, Summary of Category 1, Public Meeting with Indiana Michigan Power Company to Discuss Seismic Hazard Reevaluations Associated with Implementation of Japan Lessons-Learned Near-Term Task Force Recommendation 2.1
ML14199A0802014-07-18018 July 2014
Summary of July 8, 2014 Donald C. Cook Public Annual Assessment Meeting
ML14023A3872014-01-30030 January 2014
Summary of Joint Steering Committee Meeting to Discuss Activities Related to Lessons-Learned from the Fukushima Dai-Ichi Nuclear Power Plant Event
ML13210A2272013-08-0202 August 2013
6/26/13, Summary of Pre-Application Meeting to Discuss Pending License Amendment Request to Modify the CNP Unit 1 Normal Operating Pressure and Temperature
ML13189A2322013-07-15015 July 2013
Summary of Conference Telephone Call Regarding the 2013 Steam Generator Tube Inspections
ML13154A4062013-06-0303 June 2013
5/30/2013 - Summary of the D.C. Cook Public Meeting
ML12159A4022012-06-0707 June 2012
May 31, 2012 Summary of Public Meeting to Discuss the 2011 Annual Assessment Results for D.C. Cook
ML1133307782011-11-29029 November 2011
Record of Discussion by Phone on 10/5/11 Regarding Steam Generator Inspection
ML11129A2422011-06-0808 June 2011
Summary of Meeting with Indiana Michigan Power Company to Discuss Issues Related to a Future Submittal Using NFPA 805
ML0931305572009-11-0909 November 2009
Summary of Public Meeting with Staff from the D.C. Cook Nuclear Power Plant Regarding the September 2008 Unit 1 Turbine Vibration Event
2024-07-01
[Table view]
Category:Conference/Symposium/Workshop Paper
MONTHYEARML13189A2322013-07-15015 July 2013
Summary of Conference Telephone Call Regarding the 2013 Steam Generator Tube Inspections
ML1133307782011-11-29029 November 2011
Record of Discussion by Phone on 10/5/11 Regarding Steam Generator Inspection
2013-07-15
[Table view] |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555*0001 July 15, 2013 Mr. Lawrence J. Weber Senior Vice President and Chief Nuclear Officer Indiana Michigan Power Company Nuclear Generation Group One Cook Place Bridgman, MI 49106
SUBJECT:
DONALD C. COOK NUCLEAR PLANT, UNIT 1 -
SUMMARY
OF CONFERENCE TELEPHONE CALL REGARDING THE 2013 STEAM GENERATOR TUBE INSPECTIONS (TAC NO. MF0875)
Dear Mr. Weber:
On April 12, 2013, the U.S. Nuclear Regulatory Commission (NRC) staff participated in a conference call with Indiana Michigan Power Gompany (I&M) representatives regarding the ongoing steam generator (SG) tube inspection activities conducted during the 2012 outage at the Donald C. Cook Nuclear Plant, Unit 1. The NRC follows the results of the industry's SG inspections in order*to maintain an awareness of the condition of the SGs and the types of tube degradation mechanisms that are active.
The enclosed documentation of the telephone call is provided to I&M for information. The information provided by I&M in support of the discussion (Agencywide Documents Access and Management System (ADAMS) Accession No. ML13189A222) is available to the public. Based on the information provided during the conference call, the NRC staff did not identify any issues that warranted additional follow-up action at this time. If there are any questions, please contact me at 301-415-4037.
Sincerely, Thomas J. Weng , Senior Project Manager Plant Licensing Branch 111-1 Division of Operating Reactor licensing Office of Nuclear Reactor Regulation Docket No. 50-315
Enclosure:
Conference Call Summary cc w/encl: Distribution via ListServ
SUMMARY
OF CONFERENCE CALL WITH INDIANA MICHIGAN POWER COMPANY REGARDING THE SPRING 2013 STEAM GENERATOR TUBE INSPECTION RESULTS DONALD C. COOK NUCLEAR PLANT, UNIT 1 DOCKET NUMBER 50-315 On April 12, 2013, the Nuclear Regulatory Commission (NRC) staff participated in a conference call with Indiana Michigan Power Company (the licensee) representatives regarding ongoing steam generator (SG) tube inspection activities at Donald C. Cook Nuclear Plant (CNP), Unit 1.
In support of the conference call, the licensee provided a document summarizing some of the inspection results. This document is located in the NRC's Agencywide Documents Access and Management System (ADAMS) at Accession No. ML13189A222.
CNP Unit 1 has four model 51 R recirculating SGs designed and fabricated by Babcock and Wilcox International. Each SG has 3,496 thermally treated, Alloy 690 tubes that have an outside diameter of 0.875 inches, and a nominal wall thickness of 0.049 inches. The tubes are
. supported by Type 410 stainless steel, lattice-grid tube supports, and flat fan bars. The tubes were hydraulically expanded at each end for the full depth of the tubesheet.
Information provided by the licensee is summarized below:
- At the time of the call the licensee indicated that it was approximately 75 percent complete with SG tube inspections and that the results of the inspections are consistent with their expectations (projections). The maximum wear depth expected during this inspection is 33 percent through wall. At the time of the call the maximum depth detected was 32 percent through wall. The licensee stated that 1200 new indications were projected, but only 450 had been detected at the time of the call.
- The licensee indicated that the average through wall wear growth for SGs 11, 12, 13, and 14 are 2.7, 3.0,2.8, and 1.76 percent, respectively. The standard deviation ranged from 1.18 to 1.62 percent.
- The extent of the X-probe inspections at the top of the tubesheet (ITS) is from the tube end to the first support. The tubes inspected included all tubes around the periphery of the tube bundle and all tubes adjacent to the divider lane. This is the first outage that the X-probe is being used at CNPUnit 1.
o There are approximately 20 tubes per SG that have wear scars greater than 20 percent though wall.
- The licensee indicated that there was a typographical error on page 2 of their notes.
The "Lattice Grid Significant Indications" is not at the "fan bar" but rather at "lattice grid 4."
Enclosure
-2
- The licensee indicated that it performed SG channel head inspections. In particular, the tubesheet, divider plate, and cladding were inspected and nothing abnormal was reported.
- During the last SG inspection outage, 100 percent of the tubes were inspected. There was an unexpected increase in the number of indications of wear. The root cause for the large number of wear indications was that the SGs are operating close to a resonant condition. The original SGs were originally designed to operate at a primary pressure of 2235 pounds per square inch (psi) and a temperature of 574°F. To extend the life of the original SGs, plant primary pressure and temperature were reduced (prior to the replacement in 2000) to 2085 psi and 556°F, respectively. To address the increase in the number of wear indications, the licensee plans to restore primary pressure and temperature to their original values of 2235 psi and 574°F during the next refueling outage. This should result in secondary side pressure increasing from 650 psi to 800 psi which should move the SG out of the resonant condition. After one cycle of operating at the increased reactor coolant system pressure and temperature, the licensee currently plans another SG tube inspection outage to confirm the adequacy of their corrective actions.
- The licensee plans to inspect 100 percent of the tubes during the next refueling outage.
- Foreign object search and retrieval was currently ongoing in SG 11. Three objects had been identified. Two were retrieved, and attempts to retrieve the third object were scheduled for later in the day.
- Additional inspections of the foreign object in SG 13 will be performed to determine the nature of the object and to attempt to retrieve it.
- The licensee indicated that if a foreign object cannot be removed, they will perform an engineering evaluation and will most likely stabilize and plug the tubes surrounding the part. .
- Only 75 pounds of sludge were removed during sludge lancing operations in the prior outage, and this was after 3 cycles of operation. Prior deposit mapping indicated about 800 pounds of deposits are in the SGs.
The following abbreviations are used in the document provided by the licensee:
CL = cold leg
=
ECT eddy current test
=
EPRI Electric Power Research Institute
=
FO foreign object
=
FOSAR foreign object search and retrieval
=
HL hot leg
=
MFP main feedwater pump NEI =Nuclear Energy Institute
=
PLP possible loose part
=
SI special interest
- 3 SSI :: secondary side inspection*
ITS:: top of tubesheet TW:: through wall The NRC staff did not identify any issues that required follow-up action at this time; however, the staff asked.to be notified in the event that any unusual conditions were detected during the remainder of the outage or if a tube fails an in-situ pressure test.
July 15, 2013 Mr. Lawrence J. Weber Senior Vice President and Chief Nuclear Officer Indiana Michigan Power Company Nuclear Generation Group One Cook Place Bridgman, MI 49106
SUBJECT:
DONALD C. COOK NUCLEAR PLANT, UNIT 1 -
SUMMARY
OF CONFERENCE TELEPHONE CALL REGARDING THE 2013 STEAM GENERATOR TUBE INSPECTIONS (TAC NO. MF0875)
Dear Mr. Weber:
On April 12, 2013, the U.S. Nuclear Regulatory Commission (NRC) staff participated in a conference cal.1 with Indiana Michigan Power Company (I&M) representatives regarding the ongoing steam generator (SG) tube inspection activities conducted during the 2012 outage at the Donald C. Cook Nuclear Plant, Unit 1. The NRC follows the results of the industry's SG inspections in order to maintain an awareness of the condition of the SGs and the types of tube degradation mechanisms that are active.
The enclosed documentation of the telephone call is provided to I&M for information. The information provided by I&M in support of the discussion (Agencywide Documents Access and Management System (ADAMS) Accession No. ML13189A222) is available to the public. Based on the information provided during the conference call, the NRC staff did not identify any issues that warranted additional follow-up action at this time. If there are any questions, please contact*
me at 301-415-4037.
Sincerely, IRAJ Thomas J. Wengert, Senior Project Manager Plant Licensing Branch 111-1 Division of Operating Reactor licensing Office of Nuclear Reactor Regulation Docket No. 50-315
Enclosure:
Conference Call Summary cc w/encl: Distribution via ListServ DISTRIBUTION:
PUBLIC LPL3-1 R/F RidsNrrDorlLpL3-1 Resource KKarwoski, NRR RidsNrrPMPrairielsland Resource RidsNrrLABTully Resource AObodoako, NRR RidsNrrDorl Resource .1 Ellegood, Rill OHills, Rill RidsNrrDeEsgb Resource RidsAcrsAcnw_MailCTR Resource TBilik, Rill JGiessner, Rill ADAMS Package Accession No.: ML13189A226 ADAMS Accession No.: ML13189A232 Slides Accession No.: ML13189A222 "8 memo dated 5122113 NRR-106 FICE NRRlLPL3-1/PM NRR/LPL3 IESGB/BC NRR/LPL3-1/BC ME lWen ert RCarlson TE 07111/13 07/15/13
