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Category:Congressional Correspondence
MONTHYEARML15287A0162015-10-13013 October 2015 10-13-15 Ack Ltr to Senator Debbie Stabenow - Palisades ML15173A2872015-06-22022 June 2015 06-22-15 Acknowledge Ltr to Senator Stabenow - Palisades ML13183A2262013-07-0303 July 2013 G20130462/LTR-13-0528 - Letter to Senator Debbie Stabenow, from: R. W. Borchardt, Constituent Concerns Regarding Repairs at Palisades ML13169A2322013-06-18018 June 2013 G20130462/LTR-13-0528-Ticket - Senator Debbie Stabenow Ltr. Constituent Concerns Regarding Repairs at Palisades ML13169A2292013-06-18018 June 2013 G20130462/LTR-13-0528 - Senator Debbie Stabenow Ltr. Constituent Concerns Regarding Repairs at Palisades ML12198A1712012-08-22022 August 2012 Enclosuresponse to Information Requests from Rep. E. J. Markey Letter of June 22, 2012 ML12198A1732012-08-15015 August 2012 Attachment to Enclosuexecutive Summary ML12191A4022012-08-15015 August 2012 G20120453/LTR-12-0298/EDATS: SECY-2012-0330 - Letter to Rep. Edward J. Markey from Chairman Macfarlane Shutdown of Palisades Nuclear Power Plant - Leak in Water Storage Tank ML12166A4562012-08-15015 August 2012 G20120377/LTR-12-0221/SECY-2012-0279 - Letter to Senator Debbie Stabenow from Chairman Macfarlane Re Safety Issues with Palisades Nuclear Power Plant ML12178A4462012-06-22022 June 2012 G20120453/LTR-12-0298/EDATS: SECY-2012-0330 - Ltr. Rep. Edward J. Markey Re Shutdown of Palisades Nuclear Power Plant - Leak in Water Storage Tank ML12157A0842012-05-17017 May 2012 G20120377/LTR-12-0221/EDATS: SECY-2012-0279 - Ltr. Senator Debbie Stabenow Safety Issues with Palisades Nuclear Power Plant ML11336A3712011-12-0101 December 2011 G20110839/LTR-11-0638/EDATS: SECY-2011-0639 - Ltr. Rep. Edward J. Markey Recent Results of Nuclear Regulatory Commission Investigation of Palisades Shutdown (Due to Congress: 1/6/12) CY-92-223, G20110523/LTR-11-0411/EDATS: SECY-2011-0411 - Ltr. from Rep. E.J. Markey to Chairman Jaczko NRC Safety Requirements for Reactors Granted Construction Permits Prior to 19712011-07-14014 July 2011 G20110523/LTR-11-0411/EDATS: SECY-2011-0411 - Ltr. from Rep. E.J. Markey to Chairman Jaczko NRC Safety Requirements for Reactors Granted Construction Permits Prior to 1971 ML0704401972007-03-0202 March 2007 G20070094/LTR-07-0097 - Ltr. Representative John Kline, Incident at the Monticello Nuclear Generating Plant and Its Applicability to the Prairie Island Nuclear Generation Plant ML0535301372005-04-26026 April 2005 Letter from Congressman Fred Upton to Chairman Nils Diaz Pertaining to Palisades Nuclear Power Plant ML18347A7471979-06-15015 June 1979 Replacement of the Steam Generator 2015-06-22
[Table view] Category:Letter
MONTHYEARML24022A1172024-01-23023 January 2024 Acceptance of Requested Licensing Action Amendment Request to Revise Renewed Facility Operating License and Permanently Defueled Technical Specifications to Support Resumption of Power Operations ML24012A2422024-01-16016 January 2024 Acceptance of Requested Licensing Action License Transfer Request ML23236A0042023-12-27027 December 2023 Issuance of Amendment 274 Re Changes to Perm Defueled Emergency Plan and Perm Defueled Emergency Action Level Scheme ML23355A1242023-12-26026 December 2023 Withdrawal of an Amendment Request Re License Amendment Request to Revise License Condition to Eliminate Cyber Security Plan Requirements ML23192A0772023-12-26026 December 2023 Letter Exemption from the Requirements of 10 CFR 140.11(a)(4) Concerning Offsite Primary and Secondary Liability Insurance ML23191A5222023-12-22022 December 2023 Exemption Letter from the Requirements of 10 CFR 50.54(W)(1) Concerning Onsite Property Damage Insurance (EPID - L-2022-LLE-0032) ML23263A9772023-12-22022 December 2023 Exemption from Certain Emergency Planning Requirements and Related Safety Evaluation ML23354A2602023-12-21021 December 2023 Reference Simulator Inspection Request for Information L-23-019, Proof of Financial Protection 10 CFR 140.152023-12-18018 December 2023 Proof of Financial Protection 10 CFR 140.15 PNP 2023-030, License Amendment Request to Revise Renewed Facility Operating License and Permanently Defueled Technical Specifications to Support Resumption of Power Operations2023-12-14014 December 2023 License Amendment Request to Revise Renewed Facility Operating License and Permanently Defueled Technical Specifications to Support Resumption of Power Operations PNP 2023-035, Withdrawal of License Amendment Request - Revise License Condition to Eliminate Cyber Security Plan Requirements2023-12-12012 December 2023 Withdrawal of License Amendment Request - Revise License Condition to Eliminate Cyber Security Plan Requirements PNP 2023-028, Application for Order Consenting to Transfer of Control of License and Approving Conforming License Amendments2023-12-0606 December 2023 Application for Order Consenting to Transfer of Control of License and Approving Conforming License Amendments L-23-012, Master Decommissioning Trust Agreement Changes for Indian Point Nuclear Generating Units 1, 2 and 3, Pilgrim Nuclear Power Station, Palisades Nuclear Plant and the Non-Qualified Trust for Big Rock Point2023-11-13013 November 2023 Master Decommissioning Trust Agreement Changes for Indian Point Nuclear Generating Units 1, 2 and 3, Pilgrim Nuclear Power Station, Palisades Nuclear Plant and the Non-Qualified Trust for Big Rock Point ML23291A4402023-11-0303 November 2023 Acceptance of Requested Licensing Action Request for Exemption from 10 CFR 50.82(a)(2) to Support Reauthorization of Power Operations IR 05000255/20230032023-10-0404 October 2023 NRC Inspection Report No. 05000255/2023003(DRSS)-Holtec Decommissioning International, LLC, Palisades Nuclear Plant ML23275A0012023-10-0202 October 2023 Request for Withholding Information from Public Disclosure for Palisades Nuclear Plant PNP 2023-025, Request for Exemption from Certain Termination of License Requirements of 10 CFR 50.822023-09-28028 September 2023 Request for Exemption from Certain Termination of License Requirements of 10 CFR 50.82 PNP 2023-026, Pre-Submittal Meeting Presentation - Palisades Nuclear Plant License Transfer Application to Support Resumption of Power Operations2023-09-28028 September 2023 Pre-Submittal Meeting Presentation - Palisades Nuclear Plant License Transfer Application to Support Resumption of Power Operations PNP 2023-023, Special Report High Range Noble Gas Monitor Inoperable2023-08-0909 August 2023 Special Report High Range Noble Gas Monitor Inoperable ML23215A2302023-08-0303 August 2023 Notice of Organization Change - Chief Nuclear Officer IR 05000255/20230022023-07-19019 July 2023 NRC Inspection Report 05000255/2023002 DRSS-Holtec Decommissioning International, LLC, Palisades Nuclear Plant ML23087A0362023-05-0202 May 2023 PSDAR Review Letter ML23117A2172023-05-0101 May 2023 Safety Evaluation for Quality Assurance Program Manual Reduction in Commitment PNP 2023-018, 2022 Annual Non-Radiological Environmental Operating Report2023-04-25025 April 2023 2022 Annual Non-Radiological Environmental Operating Report L-23-004, HDI Annual Occupational Radiation Exposure Data Reports - 20222023-04-24024 April 2023 HDI Annual Occupational Radiation Exposure Data Reports - 2022 PNP 2023-007, and Big Rock Point, 2022 Annual Radioactive Effluent Release and Waste Disposal Reports2023-04-19019 April 2023 and Big Rock Point, 2022 Annual Radioactive Effluent Release and Waste Disposal Reports PNP 2023-008, 2022 Radiological Environmental Operating Report2023-04-18018 April 2023 2022 Radiological Environmental Operating Report L-23-003, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations2023-03-31031 March 2023 Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations PNP 2023-002, 6 to Updated Final Safety Analysis Report2023-03-31031 March 2023 6 to Updated Final Safety Analysis Report ML23088A0382023-03-29029 March 2023 Stations 1, 2, & 3, Palisades Nuclear Plant, and Big Rock Point - Nuclear Onsite Property Damage Insurance PNP 2023-006, Report of Changes to Security Plan, Revision 202023-03-29029 March 2023 Report of Changes to Security Plan, Revision 20 PNP 2023-012, Presentation on Regulatory Path to Reauthorize Power Operations2023-03-16016 March 2023 Presentation on Regulatory Path to Reauthorize Power Operations ML23038A0982023-03-15015 March 2023 Request for Withholding Information from Public Disclosure ML23095A0642023-03-14014 March 2023 American Nuclear Insurers, Notice of Cancellation Rescinded PNP 2023-001, Regulatory Path to Reauthorize Power Operations2023-03-13013 March 2023 Regulatory Path to Reauthorize Power Operations PNP 2023-004, Report of Changes to Palisades Nuclear Plant Technical Specification Bases2023-03-0808 March 2023 Report of Changes to Palisades Nuclear Plant Technical Specification Bases PNP 2023-005, Response to Palisades Nuclear Plant - Request for Additional Information Related to the Post-Shutdown Decommissioning Activities Report2023-03-0101 March 2023 Response to Palisades Nuclear Plant - Request for Additional Information Related to the Post-Shutdown Decommissioning Activities Report ML22361A1022023-02-24024 February 2023 Reactor Decommissioning Branch Project Management Changes for Some Decommissioning Facilities and Establishment of Backup Project Manager for All Decommissioning Facilities ML23052A1092023-02-17017 February 2023 FEMA Letter to NRC, Proposed Commission Paper Language for Palisades Nuclear Plant Emergency Plan Decommissioning Exemption Request ML23032A3992023-02-0101 February 2023 Regulatory Path to Reauthorize Power Operations IR 05000255/20220032022-12-28028 December 2022 NRC Inspection Report No. 05000255/2022003(DRSS); 07200007/2022001 (Drss) Holtec Decommissioning International, LLC, Palisades Nuclear Plant L-22-042, Oyster, Pilgrim, Indian Point, Palisades and Big Rock Point - Proof of Financial Protection 10 CFR 140.152022-12-14014 December 2022 Oyster, Pilgrim, Indian Point, Palisades and Big Rock Point - Proof of Financial Protection 10 CFR 140.15 PNP 2022-037, Report of Changes to Security Plan, Revision 192022-12-14014 December 2022 Report of Changes to Security Plan, Revision 19 ML22321A2852022-11-17017 November 2022 LLC Master Decommissioning Trust Agreement for Palisades Nuclear Plant IR 05000255/20224012022-11-0909 November 2022 Decommissioning Palisades Nuclear Plant - Decommissioning Security Inspection Report 05000255/2022401 PNP 2022-036, Response to Request for Additional Information Regarding License Amendment Request for Proposed Permanently Defueled Emergency Plan and Permanently Defueled Emergency Action Level Scheme2022-11-0808 November 2022 Response to Request for Additional Information Regarding License Amendment Request for Proposed Permanently Defueled Emergency Plan and Permanently Defueled Emergency Action Level Scheme PNP 2022-035, International - Notification of Commitment Cancellations for Remaining Activities Related to Beyond-Design-Basis Seismic Hazard Reevaluations2022-11-0202 November 2022 International - Notification of Commitment Cancellations for Remaining Activities Related to Beyond-Design-Basis Seismic Hazard Reevaluations PNP 2022-024, Request for Exemption from 10 CFR 140.11(a)(4) Concerning Primary and Secondary Liability Insurance2022-10-26026 October 2022 Request for Exemption from 10 CFR 140.11(a)(4) Concerning Primary and Secondary Liability Insurance PNP 2022-026, Request for Exemption from 10 CFR 50.54(w)(1) Concerning Onsite Property Damage Insurance2022-10-26026 October 2022 Request for Exemption from 10 CFR 50.54(w)(1) Concerning Onsite Property Damage Insurance ML22292A2572022-10-25025 October 2022 Permanently Defueled Emergency Plan License Amendment RAI Letter 2024-01-23
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August 15, 2012 The Honorable Debbie Stabenow United States Senate Washington, DC 20510
Dear Senator Stabenow:
On behalf of the U.S. Nuclear Regulatory Commission, (NRC), I am responding to your letter of May 17, 2012, regarding the Palisades Nuclear Plant. You requested an explanation of the issues at the plant that resulted in it being downgraded in the NRC Reactor Oversight Process Action Matrix as well as information regarding actions the NRC has taken to address those issues.
In the fourth quarter of 2011, Palisades was moved to the Degraded Cornerstone Column of the NRC Action Matrix as a result of several incidents that occurred in the preceding months. The Action Matrix translates individual plant performance into corresponding NRC oversight action based on licensee performance in seven cornerstones of safety and security.
The decline in licensee performance at Palisades included two inspection findings of low to moderate safety significance (White) and one finding of substantial safety significance (Yellow).
The NRC will be conducting additional oversight that will include inspections to evaluate the licensees progress in resolving these findings. The NRC will also review the results of an independent assessment of the safety culture at Palisades and corrective actions that are underway.
The first incident at Palisades involved its safety-related auxiliary feedwater (AFW) system. At Palisades, the AFW system is used to supply water to the secondary side of the steam generators for reactor cooling when normal feedwater sources are unavailable. It can be used during normal plant operations and accident scenarios. The AFW system consists of three pumps; two are electric motor-driven and one is steam-turbine-driven. The system will shut down a pump if the turbine exceeds an operating limit. On May 10, 2011, the turbine-driven AFW pump tripped during routine testing. Subsequent examination of the pump revealed the presence of grease on a component called a knife-edge. This grease caused the lever to slip which shut down the pump.
Further investigation by the NRC and licensee revealed that, during maintenance on October 29, 2010, a worker incorrectly greased the knife-edge on the pump trip mechanism.
The procedure used during this process required greasing some components, but not this specific component. The worker who performed the work did annotate the procedure to include the words knife-edge in the text after he lubricated the knife-edge. The annotation was not reviewed and assessed by the supervisor as required by site procedures to determine if a
change to procedure was necessary. Based on the information provided by the licensee and the NRC inspectors examination of the trip mechanism following the pump trip, the NRC concluded that the grease played a significant role in the turbine-driven AFW pump trip. After removal of the grease, the licensee tested the pump, which performed satisfactorily, and returned the pump to service.
The licensees failure to follow procedures for greasing of components on the turbine-driven auxiliary feedwater pump constituted a failure to follow NRC requirements, resulting in a finding of low to medium safety significance (White). The NRC resident inspectors observed troubleshooting activities and testing of the pump, and verified that the licensee had taken appropriate measures to ensure proper operation of the turbine-driven AFW pump.
The second incident at Palisades involved the service water system. The plants service water system includes three motor driven pumps, which are used to provide cooling water for safety-related equipment, such as component cooling water, containment air coolers, diesel generators, and control room coolers, during both normal operations and accident conditions.
Under normal operating conditions, two pumps are in service at all times; however, the plants technical specifications require all three pumps to be operable.
On August 9, 2011, one of the three service water pumps failed. The other two pumps continued to operate and provide the required service water flow needed for then-current plant conditions. Subsequent investigation of the failed pump determined that a shaft coupling had failed. Within a pump, a coupling is used to connect two shaft ends together, which allows the two shafts to rotate together.
As part of its post-incident restoration of the system, the licensee used spare couplings that had been purchased earlier, following a September 2009 failure of the same pump. On August 12, 2011, the licensee replaced all the pump couplings and two portions of the pump shaft and, after a successful test of the pump, returned the pump to service. The NRC resident inspectors observed portions of the work performed to restore the pump to service.
On August 15, 2011, the NRC sent a team of experts to review the circumstances surrounding the pumps failure and its relation to the 2009 failure of the same pump. The NRC inspection team reviewed the results of an independent metallurgical analysis on the failed coupling. The analysis showed that the reason for the failure of the coupling was inter-granular stress corrosion cracking (IGSCC). IGSCC is a type of metallurgical failure that can cause metal to develop a crack under certain conditions. This crack can propagate until the material fails. The failure of the coupling in 2011 was determined to be a repeat of the failure that occurred in September 2009, when another coupling in the same pump failed due to IGSCC.
The NRC inspection team determined during its review of the 2011 event that the licensees 2009 root cause evaluation only focused on one material property and did not consider the susceptibility of the couplings to IGSCC. In addition, this root cause evaluation did not address the adequacy of the couplings material for the environment to which it was subjected. Since not all critical factors were investigated, the corrective actions taken in 2009 were inadequate to prevent IGSCC from recurring.
The NRC conducted an evaluation of the licensees performance and determined that the failure to prevent recurrence of significant conditions adverse to quality and the failure to completely consider the properties of the coupling material, a material susceptible to IGSCC, constituted a failure to follow NRC requirements. This finding was determined to be of low to moderate safety significance (White). The service water pump couplings have been replaced with new couplings made from a different type of steel, which is not as susceptible to this type of corrosion, and the NRC has verified that the new couplings are in compliance with our requirements.
The third incident at Palisades involved maintenance work on a safety-related direct current electrical bus. The plant experienced an automatic reactor shutdown on September 25, 2011, when a worker was performing maintenance activities on an electrical panel. A small metal piece located inside the electrical panel came into contact with another metal piece resulting in a series of electrical problems that caused the loss of half of the control room indicators and activation of certain safety systems not warranted by actual plant conditions.
This made the automatic shutdown more challenging for the operators to handle and increased the risk of a more significant event occurring. However, a second electrical bus remained available and operators maintained the plant in a safe shutdown condition.
In response to this incident, the NRC sent a Special Inspection Team (SIT) to further investigate the circumstances surrounding the maintenance work activities that led to the reactor shutdown, and the plants response to the shutdown. During its review of the event, the SIT found several procedural deficiencies related to the work instructions. The SIT concluded that the work packages used by the licensee were not appropriate for the circumstances and were not written in accordance with plant procedures. This is contrary to NRC regulations, which require that activities affecting quality be prescribed by documented instructions or procedures of a type appropriate to the circumstances, and that the activities be accomplished in accordance with the procedures. This inspection finding has been determined to be of substantial safety significance (Yellow).
As part of the corrective actions for this event, the licensee replaced the damaged bus connectors and breakers. Compensatory measures are in place that raise the trip set point for the shunt trip breaker to improve coordination between the breaker and the downstream fuses, one of the deficiencies found by the SIT. The NRC resident inspectors and the SIT reviewed the compensatory measures and found them adequate. In addition to the previously discussed Yellow finding, the SIT also identified several performance deficiencies that were determined to be of very low safety significance (Green).
Going forward, the NRC will perform two supplemental inspections, in addition to routine baseline inspections, to review the long-term corrective actions the licensee has taken, and determine the effectiveness of those actions to fix the issues that led to the two White findings and one Yellow finding in 2011. In addition, the NRC will evaluate the sites safety culture, which the NRC defines as the core values and behaviors resulting from a collective commitment by leaders and individuals to emphasize safety over competing goals to ensure protection of people and the environment. We expect the licensee to address these issues and we will carefully review their actions. The first supplemental inspection of the AFW pump was conducted in June 2012. We will schedule an inspection of the service water pump coupling failure and the electrical breaker issues after the licensee completes work to address these issues.
Please be assured that the NRC is closely overseeing the Palisades Nuclear Plant and ensuring that the plant continues to operate safely. The NRC expects the licensee to fully address the identified shortcomings and we will take whatever actions are necessary to assure continued safe operation of the facility. If you need additional information, please contact me or Rebecca Schmidt, Director of the Office of Congressional Affairs, at (301) 415-1776.
Sincerely,
/RA/
Allison M. Macfarlane