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MONTHYEARML1036400462011-01-0505 January 2011 Summary of Conference Call with Palisades Nuclear Plant Regarding the Fall 2010 Steam Generator Inspections Project stage: Other 2011-01-05
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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
[Table view] Category:Conference/Symposium/Workshop Paper
MONTHYEARML15294A2922015-10-27027 October 2015 Summary of Conference Call with Palisades Nuclear Plant Regarding the Fall 2015 Steam Generator Inspections ML1101106472011-01-13013 January 2011 December 16, 2010, Summary of Telephone Conference Call Held Between the U.S. Nuclear Regulatory Commission and Entergy Operations, Inc. Regarding Progress on National Fire Protection Association (NFPA) Standard 805 Transition Activities ML1036400462011-01-0505 January 2011 Summary of Conference Call with Palisades Nuclear Plant Regarding the Fall 2010 Steam Generator Inspections ML0919504132009-07-24024 July 2009 Summary of Telephone Conference Call Between the U.S. Nuclear Regulatory Commission and Entergy Operations, Inc. Regarding Progress on National Fire Protection Association (NFPA) Standard 805 Transition Activities ML0910607622009-05-0707 May 2009 04/07/09 Summary of Conference Call with Palisades Nuclear Plant Regarding the Spring 2009 Steam Generator Inspections 2015-10-27
[Table view] Category:Meeting Summary
MONTHYEARML24016A0052024-01-23023 January 2024 Summary of Meeting with Holtec Decommissioning International, LLC, Regarding Power Operations Technical Specifications ML23303A2132023-11-0101 November 2023 Summary of Meeting with Holtec Decommissioning International, LLC Regarding Plan to Submit a License Transfer Request as Part of a Regulatory Path for Potentially Requesting Reauthorization of Power Operations at Palisades Nuclear Plant ML23263A0012023-09-27027 September 2023 Summary of August 29, 2023, Meeting with Holtec Decommissioning International, LLC Regarding Plan to Submit an Exemption Request as Part of a Regulatory Path for Potentially Requesting Reauthorization of Power Operations at Palisades Nuclea ML23171B1222023-06-22022 June 2023 Summary of Meeting with Holtec Decommissioning International, LLC Regarding Regulatory Path for Potentially Requesting Reauthorization of Power Operations at Palisades Nuclear Plant ML23107A1212023-04-20020 April 2023 Summary of Meeting with Holtec Decommissioning International, Llc Regarding Regulatory Path for Potentially Requesting Reauthorization of Power Operations at Palisades Nuclear Plant ML22292A2612022-10-31031 October 2022 PSDAR Meeting Summary ML22132A0892022-05-12012 May 2022 Summary of the April 26, 2022, Public Outreach to Discuss the NRC 2021 End-of-Cycle Plant Performance Assessment of Palisades Nuclear Plant ML21200A2262021-07-19019 July 2021 Summary of the July 1, 2021, Public Outreach to Discuss the NRC 2020 End-of-Cycle Plant Performance Assessment of Palisades Nuclear Plant ML21145A0482021-06-0202 June 2021 Summary of May 12, 2021, Teleconference with Entergy Nuclear Operations, Inc. to Discuss Potential License Amendment Request Related to Permanently Defueled Technical Specifications for Palisades Nuclear Plant ML21012A0382021-01-14014 January 2021 December 8, 2020, Summary of Public Teleconference with Entergy Nuclear Operations Inc. Regarding Pre-submittal of a License Transfer Application to Holtec International for Palisades Nuclear Plant ML20309A2372020-11-0606 November 2020 Summary of Public Teleconference with Entergy Nuclear Operations, Inc. to Discuss Future Request for One-Time Exemption from Certain Requirements of 10 CFR 50, Appendix E, Section Iv.F. at Palisades Nuclear Plant (EPID L-2020-LRM-0091 ML20304A1442020-11-0202 November 2020 Summary of September 21, 2020, Public Teleconference with Entergy Nuclear Operations Inc. Regarding a Proposed Alternative for Repair of Reactor Vessel Head Penetrations for Palisades Nuclear Plant ML20280A6972020-10-13013 October 2020 20200910 NRC Mid Outage Q and a for Phone Call for Palisades 1R27-Entergy Responses ML20280A6962020-10-13013 October 2020 20200912 NRC Mid Outage Q and a for Phone Call for Palisades 1R27 (Revised) ML20280A6952020-10-13013 October 2020 Letter - Palisades Nuclear Plant- Summary of September 11, 2020, Conference Call with Entergy Nuclear Operations Inc. Regarding the Fall 2020 Steam Generator Tube Inspections at Palisades Nuclear Plant EPID L-2020-LRO-0051 ML20231A2202020-08-17017 August 2020 Summary of Public Webinar to Discuss the NRC 2019 End-Of-Cycle Plant Performance Assessment of the Palisades Nuclear Plant ML19296D0632019-11-0101 November 2019 August 2019 Palisades NEIMA 108 Public Meeting Summary ML19136A2552019-05-16016 May 2019 Summary of the Public Outreach/Open House to Discuss the NRC 2018 End-of-Cycle Plant Performance Assessment of the Palisades Nuclear Plant ML18351A2382018-12-18018 December 2018 Summary of Public Teleconference Call with Entergy Nuclear Operations. Inc., Regarding Emergent Alternative Request for Repair of Central Rod Drive Nozzles at Palisades Nuclear Plant ML18340A0072018-12-0606 December 2018 Summary of Call with Entergy Nuclear Operations, Inc. - Verbal Authorization of Request for Alternative for the Repair of Reactor Vessel Closure Head Penetrations ML18268A2802018-09-26026 September 2018 Summary of Public Teleconference Call with Entergy Nuclear Operations, Inc. Regarding Upcoming License Amendment Request to Relocate Surveillance Frequencies to Licensee Control ML18107A4972018-04-27027 April 2018 April 10, 2017, Summary of Public Meeting with Entergy Nuclear Operations, Inc. Regarding Upcoming License Amendment Request to Add Setpoint Verification Requirement to Technical Specification Surveillance Requirements ML18113A6592018-04-23023 April 2018 Summary of Open House to Discuss the 2017 End-of-Cycle Plant Performance Assessment of Palisades Nuclear Plant ML18099A0712018-04-16016 April 2018 March 20, 2018, Summary of Meeting with the Nuclear Energy Institute and Other Industry Representatives Regarding the Surveillance Frequency Control Program ML18008A2302018-01-10010 January 2018 Summary of Public Teleconference Meeting with Entergy Nuclear Operations, Inc., Regarding Request to Extend Enforcement Discretion for Tornado-Generated Missile Non-Conformances at Palisades Nuclear Plant ML17338B0502017-12-0505 December 2017 Summary of November 28, 2017, Public Meeting with Entergy Nuclear Operations, Inc. Regarding a Potential Request Associated with an Alternative to the Reexamination Frequency for a Relevant Condition ML17335A0262017-12-0505 December 2017 Summary of November 27, 2017 Public Meeting with Entergy Nuclear Operations, Inc. Regarding Request to Extend Enforcement Discretion for Tornado Missle Non-Confomances ML17227A2742017-08-14014 August 2017 Summary of the July 26, 2017, Public Meeting Regarding Palisades Nuclear Plant ML17173A7672017-07-28028 July 2017 Summary of 6/20/2017 Meeting with Entergy to Discuss Plan for Decommissioning Licensing Actions of Palisades, Pilgrim, Indian Point, Units 2 and 3, and Vermont Yankee ML17164A3112017-06-27027 June 2017 Summary of 06/12/2017, Pre-Submittal Meeting with Entergy Nuclear Operations, Inc. to Discuss Palisades Nuclear Plant Post Shutdown Emergency Plan and Administrative Technical Specification License Amendment Request ML17160A1812017-06-14014 June 2017 Summary of Conference Call with Palisades Nuclear Plant Regarding the Spring 2017 Steam Generator Inspections ML17080A1492017-03-23023 March 2017 Summary of March 20, 2017, Public Meeting with Entergy Nuclear Operations, Inc. Regarding the Cyber Security Plan Implementation Schedule ML16344A0862016-12-20020 December 2016 Summary of Public Meeting with Entergy Nuclear Operations, Inc. Regarding National Fire Protection Association Standard 805 ML16277A6772016-10-11011 October 2016 Summary of Public Meeting with Entergy Nuclear Operations, Inc. Regarding the Proposed Closure Plant for Generic Safety Issue 191, Assessment of Debris Accumulation on Pressurized Water Reactor (PWR) Sump Performance ML16182A5142016-06-30030 June 2016 Summary of the June 23, 2016, Public Meeting Regarding Palisades Nuclear Plant ML16127A1722016-05-0505 May 2016 6/23/16 Notice of Significant Public Meeting to Discuss Nrc'S End-of-Cycle Assessment of the Palisades Nuclear Plant Performance for the 2015 Calendar Year ML16035A4252016-03-0101 March 2016 Summary of January 25, 2016, Pre-Application Teleconference Meeting with Entergy Nuclear Operations to Discuss a Forthcoming License Amendment Request Regarding Steam Generator Cold Leg Alternate Repair Criteria at Palisades Nuclear Plant ( ML15294A2972015-10-27027 October 2015 Steam Generator Tube Inspection Discussion During Palisades 2015 (RF24) Outage (Preliminary Information) ML15294A2922015-10-27027 October 2015 Summary of Conference Call with Palisades Nuclear Plant Regarding the Fall 2015 Steam Generator Inspections ML15272A0652015-09-30030 September 2015 Summary of Telephone Conference on September 28, 2015, Verbal Authorization of Relief Request for Palisades Nuclear Plant ML15261A0392015-09-21021 September 2015 September 17, 2015, Summary of Telephone Conference Verbal Authorization of Relief Request for Palisades Nuclear Plant ML15119A0442015-05-0606 May 2015 Summary of April 14, 2015, Meeting with Entergy Nuclear Operations, Inc. on Plans for Volumetric Examinations of Primary Coolant System Alloy 600 Welds ML15118A0352015-04-27027 April 2015 Meeting Summary with Public to Discuss the 2014 Annual Assessment Results for Palisades Nuclear Plant ML15026A5202015-01-29029 January 2015 Summary of Palisades Nuclear Plant, June 24 - 28, 2013, Audit Associated with License Amendment Request to Transition to National Fire Protection Association 805 Standards (Tac No. MF0382) ML14192B3842014-07-11011 July 2014 Summary of Public Meeting Regarding Palisades Nuclear Plant to Discuss 2013 Annual Assessment ML14093A2432014-04-30030 April 2014 Summary of Conference Call with Palisades Nuclear Plant Regarding the Fall 2014 Steam Generator Inspections ML13347B2862013-12-13013 December 2013 Summary of Public Meeting Webinar Regarding Independent Spent Fuel Storage Installation (ISFSI) Basics ML13296A5402013-10-28028 October 2013 Summary of Pre-Application Teleconference Meeting with Entergy Nuclear Operations, Inc., to Discuss a Forthcoming Palisades Equivalent Margin Analysis Submittal ML13221A5962013-08-0909 August 2013 7/16/2013 - Summary of Public Internet Event Briefing Regarding Palisades Safety Injection Refueling Water Tank (SIRWT) Leak ML13165A2422013-06-13013 June 2013 Summary of Public Meeting Webinar to Discuss Nrc'S Perspectives on Palisades Nuclear Power Plant Effluents 2024-01-23
[Table view] |
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 January 5, 2011 Vice President, Operations Entergy Nuclear Operations, Inc.
Palisades Nuclear Plant 27780 Blue Star Memorial Highway Covert, MI 49043-9530
SUBJECT:
SUMMARY
OF CONFERENCE CALL WITH PALISADES NUCLEAR PLANT REGARDING THE FALL 2010 STEAM GENERATOR INSPECTIONS (TAC NO. ME4671)
Dear Sir:
On October 15, 2010, the U.S. Nuclear Regulatory Commission (NRC) staff participated in a conference call with representatives of Entergy Nuclear Operations, Inc. (the licensee) regarding the steam generator (SG) inspection activities at Palisades Nuclear Plant. On September 9, 2010, the licensee was provided with the list of questions (Agencywide Documents Access and Management System (ADAMS) Accession No. ML102560350), to discuss the ongoing results of the SG tube inspections prior to completion of the inspections and repairs conducted during the Palisades Nuclear Plant refueling outage. The information provided by the licensee in support of the teleconference is part of the enclosed conference call summary.
Based on the information provided by the licensee, the NRC staff did not identify any issues that warranted immediate follow up action. However, the staff asked to be notified in the event that any unusual conditions were detected during the remainder of the outage. If you have any questions regarding this matter, I may be reached at 301-415-8371.
Sincerely,
//~tvw1&t/h(
Mahesh Chawla, Project Manager Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-255
Enclosure:
Conference Call Summary cc: Distribution via ListServ
CONFERENCE CALL
SUMMARY
PALISADES NUCLEAR PLANT FALL 2010 (1R21) OUTAGE STEAM GENERATOR INSPECTIONS On October 15, 2010, the staff of the Steam Generator Tube Integrity and Chemical Engineering Branch of the Division of Component Integrity participated in a conference call with Entergy Nuclear Operations, Inc. (the licensee) regarding the ongoing steam generator (SG) inspection activities at Palisades Nuclear Plant.
Palisades Nuclear Plant has two Combustion Engineering Model 2530 replacement SGs. There are 8,219 mill-annealed Alloy 600 tubes in each SG. The tubes have a nominal outside diameter of 0.75 inches and a nominal wall thickness of 0.042 inches. The tubes are supported at various locations by stainless steel eggcrate lattice type tube supports, diagonal straps and vertical straps. The tubes were expanded through the full depth of the tubesheet using an explosive process.
Additional clarifying information or information not included in the document provided by the licensee is summarized below.
The licensee noted that this was the first outage where they applied the criteria from Appendix I of the Electric Power Research Institute (EPRI) Steam Generator Examination Guidelines. The licensee stated that Appendix I oversized the outside diameter stress corrosion cracking (ODSCC) indications by 15-20 percent. The licensee further noted that the three tubes that were identified for in-situ testing would not have required in-situ testing if the criteria from Appendix H of the EPRI SG Examination Guidelines had been used.
At the time of the call, the licensee was evaluating whether they would perform the in situ testing at three times the normal operating differential pressure (3~P) or at a pressure greater than 3~P, due to sizing uncertainties.
After the call, the licensee informed the Nuclear Regulatory Commission of the results of the in-situ testing. The licensee successfully tested the three tubes to pressures above that required by EPRI guidelines (e.g. 3~P = 4475 pounds per square inch (psi>>.
SG B: Tube 75, 96 to 5650 psi no break or leak.
SG A: Tube 9, 150 to 5650 psi no break or leak; Tube 4,59 to 5650 psi no break or leak The staff did not identify any issues that required follow-up action; however, the staff asked to be notified in the event that any unusual conditions were detected during the remainder of the outage.
-2 STEAM GENERATOR TUBE INSPECTION DISCUSSION DURING PALISADES 2010 (1R21)
OUTAGE
- 1. Discuss any trends in the amount of primary-to-secondary leakage observed during the recently completed cycle.
Refer to attached Primary to Secondary Leak Rate for Operational Cycle 21 Primary to Secondary Leak Rate graph. Leakage has been minimal all cycle.
- 2. Discuss whether any secondary side pressure tests were performed during the outage and the associated results.
No secondary side pressure tests were performed in the 2010 refueling outage (1R21).
- 3. Discuss any exceptions taken to the industry guidelines.
No exceptions were taken to industry guidelines in the 2010 refueling outage (1R21).
- 4. For each steam generator, provide a description of the inspections performed including the areas examined and the probes used (e.g., dents/dings, sleeves, expansion-transition, U-bends with a rotating probe), the scope of the inspection (e.g., 100 percent of dents/dings greater than 5 volts and a 20 percent sample between 2 and 5 volts), and the expansion criteria.
Refer to attached Table 4-2 Palisades REFOUT 21 SG Eddy Current Inspection Scope for a description of inspections performed, expansion criteria, and a description of the probe used for the inspections performed.
- 5. For each area examined (e.g., tube supports, dent/dings, sleeves, etc), provide a summary of the number of indications identified to-date of each degradation mode (e.g., number of circumferential primary water stress-corrosion cracking indications at the expansion transition). For the most significant indications in each area, provide an estimate of the severity of the indication (e.g., provide the voltage, depth, and length of the indication). In particular, address whether tube integrity (structural and accident induced leakage integrity) was maintained during the previous operating cycle. In addition, discuss whether any location exhibited a degradation mode that had not previously been observed at this location at this unit (e.g., observed circumferential primary water stress-corrosion cracking at the expansion transition for the first time at this unit).
As of 10/14/2010, (INDICATIONS)
-3 SG Location Tvpe Number Axial A TSH OOSCC 3 Axial A TSH PWSCC 1 Circ A TSH PWSCC 5 Circ A TSH OOSCC 6 A TSH Wear 2 17 Total SG Location Type Number Axial B TSH OOSCC 12 Axial B TSH PWSCC a Circ B TSH PWSCC a Circ B TSH OOSCC a B TSC Wear 2 14 Total SG Location Type Number Axial A Tube Supports OOSCC 30 A Tube Supports Wear 2 32 Total SG Location Type Number Axial B Tube Supports OOSCC 18 B Tube Supports Wear 3 Axial B Freespan OOSCC 1 22 Total Total Indications* 85 Grand Total
- Some tubes have multiple indications Tubesheet and Sludge Pile Most significant axial OOSCC indication is 0.63V from +Pt in 300 kHz channel (69 percent TW using ETSS 128432 method, 55 percent TW using an amplitude regression based on C-E pulled
- 4 tube data). Longest length reported from resolution analysis is 0.80 inch (same indication).
Indication length from profile for this indication is 0.70 inch.
All circumferential ODSCC indications are less than 100 degrees total flaw arc length.
Maximum depth from phase analysis is <50 percent TW.
All PWSCC indications have classified as minor with the largest +Pt amplitude is 1.06V.
Supports Largest P4 (300/100 kHz mix channel) +Pt amplitude is 0.51V. Several indications have total flaw length approaching 2 inches (contact length of eggcrate). Average flaw length is 0.53 inch.
Freespan One tube reported to contain axial ODSCC at a freespan ding. Ding voltage is 2.4 volts, indication was reported by bobbin.
U-Bends One Row 2 tube in SG E-50B is reported to contain axial ODSCC at a ding.
- 6. Describe repair/plugging plans.
Currently there are 48 potential tubes requiring tube plugging in SG E-50A and 31 potential tubes in SG E-50B.
All stress corrosion cracking (SCC) indications will be plugged. Any circumferential SCC indications near top of tubesheet (TTS) will be stabilized and plugged.
All structure wear greater than or equal to 40 percent TW will be plugged.
- 7. Describe in-situ pressure test and tube pull plans and results (as applicable and if available).
Based on the available data to date, three tubes will require insitu testing.
SG Tube Number Location Depth Length Voltage SGA R9C150 02H Eggcrate 60% 2.00 0.44 SGA R4C59 01 H Eqqcrate 64% 1.98 0.47 SGB R75C96 Hot Leg Sludge 68% 0.70 0.63 Pile I
- 8. Discuss the following regarding loose parts:
- What inspections are performed to detect loose parts?
The hot-leg TTS region is inspected with +Pt up to 3 inches above TTS. A similar inspection is performed for the cold-leg TTS region (3 tubes deep along periphery and tube lane. Foreign
-5 object search and retrieval (FOSAR) is performed for the periphery, tube lane annulus, and stay cavity areas.
- A description of any loose parts detected and their location within the SG Loose parts verified with wear in SGA - HL 129-62 and 131-62 and SGB - CL 110-35 and 111 36TSC PLP E-50A 171 PLP Calls in 144 Tube Locations E-50B 105 PLP Calls in 105 Tube Locations
- If the loose parts were removed from the SG FOSAR is scheduled in SG E-50A for 10/18/2010 and in SG E-50B on 10/17/2010.
- Indications of tube damage associated with the loose parts Currently there are 2 locations that have indication of wear associated with a loose part. Loose parts verified with wear in:
SGA - HL 129-62 and 131-62 and SGB - CL 110-35 and 111-36 TSC
- 9. Discuss the scope and results of any secondary side inspection and maintenance activities (e.g., in-bundle visual inspections, feedring inspections, sludge lancing, assessment deposit loading, etc).
Visual inspection scheduled both SG E-50A and SG E-50B tubesheet periphery regions and in bundle top of hot and cold-leg tubesheets, FOSAR and sludge lancing the top of cold and hot leg tubesheets.
- 10. Discuss any unexpected or unusual results.
There are three indications that will need to be in-situ tested.
The need for in-situ pressure testing has been entered into the Entergy Corrective Action Program. CR-PLP-201 0-04929 for SG Band CR-PLP-201 0-05055 for SG A.
- 11. Provide the schedule for steam generator-related activities during the remainder of the current outage.
Currently bobbin and top of tubesheet +Pt RPC are essentially complete in both SGs. Special interest is in progress and will be completed this weekend in both SGs (this includes dingsldents, u-bend, cold leg top of tubesheet, eggcrate etc.).
SG E-50 A and B FOSAR and sludge lancing will also be started early next week.
Tube plugging will start as early as 10/15 and in-situ testing on 10/16.
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-7 Table 4-2. Summary of SG Tube De ~radation Mechanisms and Inspection Requirements: Palisades 1R21 Degradation Location Probe Type Detection Inspection/Expansion Plan Mechanism Inspection Sample Plan Expansion Plan Existing Degradation Mechanisms Tube Wear Non dented Tube Bobbin 100% vertical straight length Rows 1 thru 3, N/A Support Structures 100% full length Rows 4 and higher, both SGs AxialOOSCC Non dented Tube Bobbin 100% vertical straight length Rows 1 thru 3, N/A Support Structures 100% full length Rows 4 and higher, both SGs Plus Point 100% all OSI or %TW signals at eggcrates, 100% historical wear sites between OBH 100% newly reported bobbin signals between and OBC for confirmation of OOSCC at OBH and OBC inclusive historical wear site not previously RPC tested.
AxialOOSCC Freespan, Freespan Bobbin 100% vertical straight length Rows 1 thru 3, N/A dings~5V 100% full length Rows 4 and higher, both SGs Plus Point 100% all bobbin I-codes N/A AxialOOSCC Freespan dings >5V Plus Point 100% dings >5V in both SGs, all elevations N/A and locations AxialOOSCC Dented eggcrates, Plus Point 100% dented eggcrates, diagonal bars, N/A diagonal bars, vertical straps >2V vertical straps >2V Circumferential HL TIS expansion Plus Point 100% from 3" above to 12.5" below expansion See Note (1).
and Axial transition and sludge transition, both SGs OOSCC pile Axial PWSCC HL TIS expansion Plus Point 100% from 3" above to 12.5" below expansion See Note (1) transition and transition, both SGs expandedtubesheet Axial PWSCC Row 1, 2, and 3U Plus Point 100% Row 1, 2, and 3 U-bends using mid 100% of Row 4 for indication in Row 3.
bends range coil (2) Redefine plan if indications detected in Row 4.
-8 Table 4-2. Summary of SG Tube De Jradation Mechanisms and Inspection Requirements: Palisades 1R21 Degradation Location Probe Type Detection Inspection/Expansion Plan Mechanism Inspection Sample Plan Expansion Plan Tube Wear Dented Vertical Bobbin: 100% vertical straight length Rows 1 thru 3, N/A Straps, Diagonal 0.610" 100% full length Rows 4 and higher, both SGs Bars and Eggcrates , diameter (active mechanism dictates plan)
<5V Dented Vertical Plus Point: 100% >2V dents will be performed as part of N/A Straps, Diagonal 0.610"/0.580" ODSCC inspection plan Bars and Eggcrates, diameter
>5V Tube Wear Square bend region Bobbin 100% vertical straight length Rows 1 thru 3, N/A (freespan) 100% full length Rows 4 and higher, both SGs (active mechanism dictates plan)
Plus Point Highest eggcrate through square bend, tubes N/A surrounding R99 C140 in SGB Tube Wear TIS periphery, tube Bobbin 100% full length bobbin +FOSAR in both SGs Plus Point all surrounding tubes with (loose parts) lane loose part or loose part wear sig nals Plus Point 100% hot-leg TTS region plus 3 tube deep on Plus Point all surrounding tubes with cold leg periphery from 2" above to 2" below loose part or loose part wear sig nals TIS, plus special interest testing of PLP signals from bobbin in freespan, at eggcrates, and vertical straps, diagonal bars Resolution for Classification of Indications Potential MBMs All Bobbin 100% vertical straight length Rows 1 thru 3, N/A 100% full length Rows 4 and higher, both SGs Plus Point Flaw confirmation of bobbin indications with Review specific occurrences of flaw change or no history detection and establish expansion plan based on observed parameters
-9 Table 4-2. Summary of SG Tube De Jradation Mechanisms and Inspection Requirements: Palisades 1R21 Degradation Location Probe Type Detection Inspection/Expansion Plan Mechanism Inspection Sample Plan Expansion Plan To Be Defined Bobbin Signals at Plus Point 25% historical DB and VS wear sites 100% DB and VS wear sites in both SGs Suspected Wear for detection of ODSCC Sites not yet characterized Potential Degradation Mechanisms Circ PWSCC Row 1and 2 U- Plus Point 100% Row 1, 2, and 3 U-bends in both SGs 100% of Row 4 for indication in Row 3.
bends in both SGs using mid-range coil (2) Redefine plan if indications detected in Row 4.
Circ PWSCC HL TIS expansion Plus Point 100% from 3" above to 12.5" below expansion See Note (1).
transition and transition, both SGs expandedtubesheet CircODSCC Dented Vertical Plus Point Controlled by inspection requirements for 100% all dings/dents for confirmation of Strap Locations existing or potential mechanisms, PLUS tube eire ODSCC locations listed in Section 4.5, item 5 Pitting Sludge pile Bobbin Controlled by inspection requirements for N/A existing or potential mechanisms Non-Relevant Degradation Mechanisms Included in the 1R21 Eddy Current Inspection Scope Axial PWSCC Dented support Plus Point Controlled by inspection requirements for 100% all dings/dents for confirmation of structures existinq or potential mechanisms axial PWSCC Axial and Circ Cold-leg expanded Plus Point 3 tubes deep on cold-leg periphery from 2" 100% cold-leg from 2" above to 13 inches PWSCC tube in tubesheet above to 2" below TIS (controlled by loose below TIS part detection program)
AxialODSCC Wear sites Bobbin Controlled by inspection requirements for N/A existinq or potential mechanisms Plus Point 25% historical wear sites between DBH and 100% all wear sites between DBH and DBC DBC for confirmation of combined mode axial ODSCC + wear scar
- 10 (1) 20 percent cold-leg TIS Plus Point expansion at either 1R21 or 1R22 from 3" above to 12.5" below bottom of expansion transition in SG with C-3 condition or if failure of performance criteria at TIS is determined.
(2) Any Row 1 or Row 2 U-bend with mid-range +Pt coil noise exceeding the value specified in Appendix B will be tested with a high frequency +Pt coil probe.
ML103640046 *M emo dated Novem ber 10 20 10 f rom I to R Pascare RT ayior I OFFICE NRR/LPL3-1/PM NRR/LPL3-1/LA NRRlCSGB/BC* NRRlLPL3-1/BC NAME MChawla BTuily RTaylor RPascarel1i DATE 1 lOS 111 1 lOS 111 1 lOS 111 1 105/11