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Category:Inservice/Preservice Inspection and Test Report
MONTHYEARPNP 2021-003, 2020 Steam Generator Tube Inspection Report2021-03-25025 March 2021 2020 Steam Generator Tube Inspection Report PNP 2021-001, ASME Section XI 90-Day Owner'S Activity Report2021-01-12012 January 2021 ASME Section XI 90-Day Owner'S Activity Report ML18347A4982019-12-13013 December 2019 Palisades Nuclear Power Plant, Third Interval Inservice Inspection Program for Class 1, 2 & 3 Components and Their Supports. PNP 2019-011, ASME Section XI 90-Day Owner'S Activity Report2019-03-22022 March 2019 ASME Section XI 90-Day Owner'S Activity Report PNP 2017-062, Submittal of 2017 Refueling Outage, 1R25, 180-Day Steam Generator Tube Inspection Report2017-10-18018 October 2017 Submittal of 2017 Refueling Outage, 1R25, 180-Day Steam Generator Tube Inspection Report PNP 2017-046, ASME Section XI 90-Day Owner'S Activity Report2017-07-14014 July 2017 ASME Section XI 90-Day Owner'S Activity Report ML16144A7892016-05-18018 May 2016 Biennial Report of MRP-227-A Reactor Internals Inspection Results PNP 2016-006, Inservice Testing Program Plan Fifth 10-Year Interval2016-04-28028 April 2016 Inservice Testing Program Plan Fifth 10-Year Interval ML16092A0902016-03-16016 March 2016 51-9252894-001, 180-Day Steam Generator Tube Inspection Report, 2015 Refueling Outage, 1R24. PNP 2016-002, ASME Section XI 90-Day Owner'S Activity Report2016-01-15015 January 2016 ASME Section XI 90-Day Owner'S Activity Report PNP 2015-089, Inservice Inspection Master Program Fifth 10-Year Interval2015-12-0909 December 2015 Inservice Inspection Master Program Fifth 10-Year Interval PNP 2015-043, Relief Request Number RR 4-22 - Proposed Alternative, Use of Alternate ASME Code Case N-770-1 Baseline Examination2015-07-0707 July 2015 Relief Request Number RR 4-22 - Proposed Alternative, Use of Alternate ASME Code Case N-770-1 Baseline Examination PNP 2015-022, Relief Request Number RR 5-1, Proposed Alternative, Extend the Current ASME Code of Record Into the Fifth 10-year ISI Interval for ISI Related Activities2015-04-29029 April 2015 Relief Request Number RR 5-1, Proposed Alternative, Extend the Current ASME Code of Record Into the Fifth 10-year ISI Interval for ISI Related Activities PNP 2014-072, 2014 Steam Generator Tube Inspection Report2014-08-0505 August 2014 2014 Steam Generator Tube Inspection Report PNP 2014-055, ASME Section XI 90-Day Inservice Inspection Summary Report2014-06-12012 June 2014 ASME Section XI 90-Day Inservice Inspection Summary Report ML14066A4092014-03-0606 March 2014 Supplemental Response to Request for Additional Information Dated February 26, 2014, for Relief Request Number RR 4-18 - Proposed Alternative, Use of Alternate ASME Code Case N-70-1 Baseline Examination PNP 2014-009, 40-Year Containment Tendon Surveillance Report2014-01-31031 January 2014 40-Year Containment Tendon Surveillance Report PNP 2012-069, ASME Section XI 90-Day Inservice Inspection Summary Report2012-08-0303 August 2012 ASME Section XI 90-Day Inservice Inspection Summary Report PNP 2011-033, Generator Tube Inspection Report2011-04-25025 April 2011 Generator Tube Inspection Report PNP 2011-006, ASME Section XI 90-Day Inservice Inspection Summary Report2011-01-25025 January 2011 ASME Section XI 90-Day Inservice Inspection Summary Report ML0920903162009-07-27027 July 2009 ASME Section XI 90-Day Inservice Inspection Summary Report 2009 ML0907606852009-03-12012 March 2009 Request for Information for IP 71111.08, Inservice Inspection ML0823209822008-08-19019 August 2008 Transmittal of Ventilated Storage Cask Inspection Summary Report ML0825400532008-08-14014 August 2008 Response to Request for Additional Information Concerning Authorization to Extend the Third 10-Year Inservice Inspection Interval for Reactor Vessel Weld Examination ML0802205642008-01-21021 January 2008 ASME Section XI 90-Day Inservice Inspection Summary Report ML0708500572007-03-21021 March 2007 Supplement to Request for Relief from ASME Section XI Code Requirements for Repair of Reactor Pressure Vessel Head Penetrations ML0704401872007-02-12012 February 2007 Response to Request for Additional Information Related to 4th Interval Inservice Inspection Plan Relief Requests 4-1 Through 4-12 (TAC Nos. MD2404 - MD2415) ML0626502552006-09-15015 September 2006 Request for Authorization to Extend the Third 10-Year ISI Interval for Reactor Vessel Weld Examination ML0622302752006-08-0202 August 2006 ASME Section XI Inservice Inspection 90-Day Report ML0608904512006-03-24024 March 2006 Inservice Testing Program: Fourth Ten-Year Interval Update ML0603705272006-02-0303 February 2006 Ltr. 02/03/06 Palisades Nuclear Power Plant Request of Information ML0509703192005-03-31031 March 2005 Plant. Request for Authorization to Extend the Third 10-Year IST Interval for Certain Relief Valves ML0509702672005-03-31031 March 2005 Plant. Request for Authorization to Extend the Third 10-Year ISI Interval for Reactor Vessel Weld Examination ML0509702632005-03-31031 March 2005 Request for Authorization to Extend the Third 10-Year ISI Interval for Reactor Vessel Visual Examination ML0505406882005-02-15015 February 2005 ASME Section XI Inservice Inspection 90-Day Report ML0327314002003-09-18018 September 2003 Request for Relief from ASME Section XI, Appendix Viii, Supplement 11 Code Requirements ML0319707292003-07-10010 July 2003 ASME Section XI Inservice Inspection 90-Day Report ML0307005342003-02-28028 February 2003 Supplement to Palisades Risk-Informed Inservice Inspection Piping Program ML0223302592002-08-0808 August 2002 Risk Informed Inservice Inspection Program - Response to Request for Additional Information ML0209203632002-03-21021 March 2002 Part 2 of 2, Palisades Nuclear Plant, ASME Section XI Inservice Inspection 90-Day Reports, Form N-2 or Npt Certificate Holders' Report ML0209203552002-03-21021 March 2002 Part 1 of 2, Palisades Nuclear Plant, ASME Section XI Inservice Inspection 90-Day Reports ML18347A5011995-09-18018 September 1995 Inservice Testing of Selected Safety-Related Pumps Relief Request for Containment Spray and Low Pressure Safety Injection Pumps. ML18348A8951978-06-13013 June 1978 Submittal of Update of Inservice Inspection Program ML18348A8541977-05-0303 May 1977 Inservice Inspection Program 2021-03-25
[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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Text
Entergy Nuclear Operations, Inc.
Palisades Nuclear Plant 27780 Blue Star Memorial Highway Covert, MI 49043 Tel269 764 2000 August 19,2008 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Director, Spent Fuel Project Office Office of Nuclear Material Safety and Safeguards Washington, DC 20555-0001 Palisades Nuclear Plant Dockets 50-255 and 72-7 License No. DPR-20 Ventilated Storaae Cask Inspection Summarv Report
Dear Sir or Madam:
Entergy Nuclear Operations, Inc. (ENO) is providing the summary report required by Section 1.3.3, of Attachment A, of the dry fuel storage (DFS) Certificate of Compliance.
Section 1.3.3 requires that the ventilated concrete cask (VCC) interior surfaces and the multi-assembly sealed basket (MSB) exterior surfaces of the first ventilated storage cask (VSC) placed in service be inspected after every five years in service. The inspection is to identify potential air flow blockage and material degradation. A report summarizing the findings is required to be submitted within 30 days from the conclusion of the inspection. The first VSC, serial number CVCC-24-01, was placed in service at the Palisades Nuclear Plant on May 12, 1993. The previous inspection was conducted in June 2003.
A remote visual inspection of the VCC interior surfaces was performed on July 22, 2008. Surfaces inspected included the VCC cooling air flow paths, the VCC liner interior and the MSB exterior. The inspection concluded:
- 1. The VSC cooling paths were free of air flow blockage.
- 2. The VCC interior surfaces and the MSB exterior surfaces were in good condition and considered to be normal for the VSC service environment and the specified materials of construction described in the Safety Analysis Report (SAR).
- 3. No additional degradation mechanisms affecting system performance were identified.
The inspection summary report is provided in Enclosure 1.
Document Control Desk Page 2 Summary of Commitments This letter contains no new commitments and no revisions to existing commitments.
Site Vice President Palisades Nuclear Plant Enclosure (1)
CC Regional Administrator, USNRC, Region Ill Project Manager, USNRC, NRR NRC Resident Inspector - Palisades
ENCLOSURE 1 DRY STORAGE OF SPENT FUEL lMSPECTlON OF FIRST VSC-24 PLACED IN SERVICE
SUMMARY
REPORT PURPOSE This report summarizes the results of the ventilated concrete cask (VCC) interior surface inspection conducted on ventilated storage cask (VSC) serial number CVCC-24-01, which is the first VSC-24 cask placed in service at the Palisades Nuclear Plant (PNP). The VCC interior surfaces and the multi-assembly sealed basket (MSB) exterior surfaces of the first VSC placed in service are required to be inspected after every five years in service, as specified in Section 1.3.3, of Attachment A, of the VSC-24 Certificate of Compliance, to identify potential air flow blockage and material degradation.
The VSC air flow cooling path surfaces that were inspected are the VCC air inlet and air -
outlet assemblies, the VCC interior and the MSB exterior. The VCC inlet, outlet, and interior surfaces are coated with Carboline Carbo Zinc (CZ)-11HS inorganic zinc primer and the MSB exterior surfaces are coated with a two-part coating system consisting of a CZ-11HS base coat and a Keeler & Long E-1-7155 epoxy enamel top coat.
lnspection Equipment The inspection was performed with an Everest Visual lnspection Technologies PXLA875A probe with an internal light source to illuminate the surfaces for inspection.
A monitor was used to view the surfaces and a Sony DVD recorder was used to provide a record of the inspection.
lnspection Methodolo~y Access for the inspection of the VCC interior and the MSB exterior surfaces was achieved through the VCC air inlet and air outlet assemblies. The air inlet and air outlet protective screens were partially removed to facilitate entry of the video probe. The interior surfaces of the air outlet assernblies, the VCC liner interior, and the MSB exterior surfaces (which form the air flow annulus) down to the top of the air inlet hole in the floor of the VCC were inspected via access through the air outlet assembly. Then, the air inlet assemblies were inspected up to the air inlet hole in the floor of the VCC via access through the air inlet assemblies.
lnspection Results The results are summarized below for the VSC cooling path (inlet, annulus, outlet) surfaces inspected.
Page 1 of 4
Air Outlet Assembly Interior Surfaces The VCC liner outlet vents had areas of considerable rust bleed-through in areas where proper surface preparation was difficult to attain. The areas where the coating has flaked are considered to have light to medium rust with minor pitting. The pitting was previously noted in the 1998 and 2003 report. However, there appears to be no significant progression of the rust when comparing the 2003 and the 2008 video tape recordings. The function of the outlet vent steel is maintained with the existing condition.
VCCIMSB Annulus The VCCIMSB annulus from the air outlet assemblies to the air inlet hole in the floor of the VCC was free of blockage.
e VCC Liner Interior Surface -
The VCC liner interior exhibited small areas of light rust near the air outlets and light rust or discoloration approximately midway down. The circumferential weld exhibited some intermittent light rust or coating discoloration. There was no noticeable change in coating degradation when compared to the 2003 inspection video.
MSB Exterior Surface As expected, the epoxy enamel coating near the top of the MSB exhibited some flaking and light rust bleed through the weld heat-affected zone. However, there was not a noticeable increase in degraded coating as compared to the 2003 inspection results. The condition of the remaining coated surface area of the MSB was very good. There was apparent discoloration of the epoxy (originally light blue), however the coating has maintained its gloss and is not experiencing any chalking. There were several areas near the bottom of the MSB, which were previously noted in 1998 and 2003, where light rust bleed through is evident; however, the rusting has not progressed significantly.
Air Inlet Assembl~lnterior Surfaces The air inlet assemblies, from the protective screens to the air inlet hole in the floor of the VCC, were found to be free of blockage. Minor debris (paint chips, leaves, small twigs) were identified in the air inlet assembly. The VCC inlet steel surfaces exhibited some light to medium rusting, as noted in the 1998 and 2003 inspection. There was no significant .change in the condition of the VCC inlet liner steel.
Page 2 of 4
SUMMARY
EVALUATION Evaluation of the results from the VCC interior inspection on VSC serial number CVCC-24-01 after fifteen years in service indicates the following:
The internal air flow paths inside the VCC were found to be free of obstruction.
This is consistent with the daily thermal performance monitoring data. Thus, there is indication that the thermal performance of the cask has not degraded and that the cask is operating properly.
There were no significant changes from the results summarized in the 2003 inspection.
The MSB shell exterior surface was found to exhibit some small local areas of rusting which are of no consequence since the shell thickness was designed to withstand more than 50 years of corrosion in an uncoated condition in a coastal, -
marine environment.
Flaking of the epoxy enamel top coat on the MSB was observed at the top and bottom of the shell. This top coat was added to facilitate decontamination of the MSB exterior surface following removal from the spent fuel pool during loading.
The flaking epoxy enamel top coat is of no design significance, as the top coat is no longer functionally required. Operability continues to be demonstrated by the daily surveillances which assure that the air inlet/outlet screens are free from blockage and verify satisfactory cask thermal performance.
Rusting was noted on the interior surfaces of the air inlet and air outlet assemblies. These assemblies serve only as a concrete form during fabrication and perform no structural or shielding function.
The VCC liner interior surfaces exhibited small areas of rusting near the air outlet assemblies and at the mid length. The VCC liner performs a structural and shielding function during use. The rusting noted will not affect the VCC liner's ability to perform its function since:
The light rust observed had no perceptible depth. Therefore, the liner's structural strength is not affected.
The reduction in wall thickness due to rusting is not a shielding concern because the rate of fuel decay exceeds the corrosion rate of the liner material.
Air Inlet Assemblies - Minor debris that has no impact on air flow pathway observed.
Page 3 of 4
CONCLUSION The VSC cooling paths were found to be free of air flow blockage. The VCC air inlet and air outlet assemblies, the VCC interior surfaces and the MSB exterior surfaces were found to be in good condition and are considered to be normal for the VSC service environment and the specified materials of construction described in the safety analysis report (SAR). The inspection did not identify any degradation mechanisms affecting system performance that were not identified in the SAR.
The VSC was found to be performing as described in the SAR, and no additional degradation mechanisms affecting system performance were identified.
Page 4 of 4