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Category:Meeting Agenda
MONTHYEARPMNS20240943, Hybrid Public Outreach Meeting with the U.S. Nuclear Regulatory Commission and Holtec Decommissioning Inc. on the Potential Palisades Nuclear Plant Restart2024-07-18018 July 2024 Hybrid Public Outreach Meeting with the U.S. Nuclear Regulatory Commission and Holtec Decommissioning Inc. on the Potential Palisades Nuclear Plant Restart PMNS20240883, Scoping Meeting Related to the Potential Reauthorization of Power Operations of the Palisades Nuclear Plant2024-07-11011 July 2024 Scoping Meeting Related to the Potential Reauthorization of Power Operations of the Palisades Nuclear Plant PMNS20240879, Tribal Information Meeting - Palisades Request for Reauthorization of Power Operations2024-07-0505 July 2024 Tribal Information Meeting - Palisades Request for Reauthorization of Power Operations PMNS20240636, Pre-Submittal Meeting with Holtec Decommissioning International, LLC, to Discuss a License Amendment Request to Approve the Biasi Critical Heat Flux Correlation for Use with the Main Steam Line Break Analysis for the Palisades Nuclear P2024-05-13013 May 2024 Pre-Submittal Meeting with Holtec Decommissioning International, LLC, to Discuss a License Amendment Request to Approve the Biasi Critical Heat Flux Correlation for Use with the Main Steam Line Break Analysis for the Palisades Nuclear Plant PNP 2024-023, Pre-Submittal Meeting Presentation - License Amendment Request to Approve the Biasi Critical Heat Flux (CHF) Correlation for Use with the Palisades Main Steam Line Break (MSLB) Analysis2024-05-0909 May 2024 Pre-Submittal Meeting Presentation - License Amendment Request to Approve the Biasi Critical Heat Flux (CHF) Correlation for Use with the Palisades Main Steam Line Break (MSLB) Analysis PMNS20240555, Notice of Meeting with Holtec Decommissioning International, LLC2024-04-26026 April 2024 Notice of Meeting with Holtec Decommissioning International, LLC PMNS20240417, Hybrid Public Outreach Meeting on the Potential Palisades Nuclear Plant Restart2024-04-16016 April 2024 Hybrid Public Outreach Meeting on the Potential Palisades Nuclear Plant Restart PMNS20240513, Notice of Closed Meeting with Holtec Decommissioning International, LLC2024-04-10010 April 2024 Notice of Closed Meeting with Holtec Decommissioning International, LLC ML24086A5822024-04-0303 April 2024 Construction Permit Application: Initial Environmental & Site Characterization PMNS20240461, Notice of Closed Meeting with Holtec Decommissioning International, LLC2024-03-29029 March 2024 Notice of Closed Meeting with Holtec Decommissioning International, LLC PMNS20240422, Meeting with the U.S. Nuclear Regulatory Commission Petition Review Board and Beyond Nuclear, Michigan Safe Energy Future, and Dont Waste Michigan Regarding a 2.206 Petition Submitted on December 5, 20232024-03-25025 March 2024 Meeting with the U.S. Nuclear Regulatory Commission Petition Review Board and Beyond Nuclear, Michigan Safe Energy Future, and Dont Waste Michigan Regarding a 2.206 Petition Submitted on December 5, 2023 PMNS20240270, Hybrid Palisades Pre-submittal Meeting with Holtec Decommissioning International, LLC on Emergency Plan for Resumption of Power Operations2024-03-15015 March 2024 Hybrid Palisades Pre-submittal Meeting with Holtec Decommissioning International, LLC on Emergency Plan for Resumption of Power Operations PMNS20240299, Notice of Closed Meeting with Holtec Decommissioning International, LLC2024-03-0606 March 2024 Notice of Closed Meeting with Holtec Decommissioning International, LLC ML24036A1082024-02-0606 February 2024 Pre-submittal Meeting for Palisades Nuclear Plant Power Operations Technical Specifications Administrative Controls and Quality Assurance Program (Presentation) PMNS20240061, Virtual Palisades Pre-submittal Meeting with Holtec Decommissioning International, LLC on Proposed License Amendment for Changes to Technical Specifications Administrative Controls and Discussion on Quality Assurance Plans2024-01-23023 January 2024 Virtual Palisades Pre-submittal Meeting with Holtec Decommissioning International, LLC on Proposed License Amendment for Changes to Technical Specifications Administrative Controls and Discussion on Quality Assurance Plans ML23334A1322023-12-0505 December 2023 Pre-submittal Meeting with Holtec for Palisades Nuclear Plant Power Operations Technical Specifications (Presentation) PMNS20231299, Notice of Pre-submittal Meeting with Holtec Decommissioning International, LLC to Discuss Power Operations Technical Specifications2023-11-30030 November 2023 Notice of Pre-submittal Meeting with Holtec Decommissioning International, LLC to Discuss Power Operations Technical Specifications PMNS20231056, Notice of Meeting with Holtec Decommissioning International, LLC2023-10-0202 October 2023 Notice of Meeting with Holtec Decommissioning International, LLC PMNS20230918, Notice of Meeting with Holtec Decommissioning International, LLC2023-08-23023 August 2023 Notice of Meeting with Holtec Decommissioning International, LLC PMNS20230617, Notice of Meeting with Holtec Decommissioning International, LLC2023-05-19019 May 2023 Notice of Meeting with Holtec Decommissioning International, LLC PMNS20230222, Notice of Meeting with Holtec Decommissioning International, LLC2023-03-20020 March 2023 Notice of Meeting with Holtec Decommissioning International, LLC ML22262A3032022-09-22022 September 2022 Post-Shutdown Decommissioning Activities Report Public Meeting Slides - September 22, 2022 PMNS20220887, Post-Shutdown Decommissioning Activities Report Public Meeting2022-08-30030 August 2022 Post-Shutdown Decommissioning Activities Report Public Meeting PMNS20220594, NRC Webinar on Palisades Nuclear Power Plant Decommissioning2022-06-0303 June 2022 NRC Webinar on Palisades Nuclear Power Plant Decommissioning ML21130A0542021-05-10010 May 2021 Pre-submittal Teleconference with Entergy Nuclear Operations, Inc. (Entergy) Regarding a Permanently Defueled Technical Specification License Amendment Request for Palisades Nuclear Plant (Palisades) ML20342A0882020-12-0707 December 2020 Pre-submittal Teleconference with Entergy Nuclear Operations, Inc. (Entergy) and Holtecinternational (Holtec) Regarding the Planned License Transfer Application for Palisades Nuclear Plant (Palisades) ML20271A0012020-09-27027 September 2020 Pre-submittal Teleconference Regarding Request for One-Time Exemption from the Requirements of 10 CFR Part 50, Appendix E, Biennial Emergency Preparedness Exercise for Palisades Nuclear Plant ML15183A4632015-07-0101 July 2015 Ltr. 07/01/15 Monticello U.S. Nuclear Regulatory Commission Region III 2015 Operator Licensing Workshop (Public Meeting) (Drm) ML15183A4552015-07-0101 July 2015 Ltr. 07/01/15 Palisades U.S. Nuclear Regulatory Commission Region III 2015 Operator Licensing Workshop (Public Meeting) (Drm) ML15183A4452015-07-0101 July 2015 Ltr. 07/01/15 Perry U.S. Nuclear Regulatory Commission Region III 2015 Operator Licensing Workshop (Public Meeting) (Drm) ML15183A4722015-07-0101 July 2015 Ltr. 07/01/2015 Fermi U.S. Nuclear Regulatory Commission Region III 2015 Operator Licensing Workshop (Public Meeting) (Drm) ML15183A4782015-07-0101 July 2015 Ltr. 07/01/15 Duane Arnold U.S. Nuclear Regulatory Commission Region III 2015 Operator Licensing Workshop (Public Meeting) (Drm) ML15183A4792015-07-0101 July 2015 Ltr. 07/01/15 D.C. Cook U.S. Nuclear Regulatory Commission Region III 2015 Operator Licensing Workshop (Public Meeting)(Drm) ML15183A3992015-07-0101 July 2015 Ltr. 07/01/15 Point Beach U.S. Nuclear Regulatory Commission Region III 2015 Operator Licensing Workshop (Public Meeting) (Drm) ML15183A4842015-07-0101 July 2015 Ltr. 07/01/15 Davis-Besse U.S. Nuclear Regulatory Commission Region III 2015 Operator Licensing Workshop (Public Meeting) (Drm) ML15183A3862015-07-0101 July 2015 Ltr. 07/01/15 Prairie Island U.S. Nuclear Regulatory Commission Region III 2015 Operator Licensing Workshop (Public Meeting) (Drm) ML15182A4412015-07-0101 July 2015 Notice and Agenda - 2015 Operator Licensing Workshop ML15107A3062015-04-14014 April 2015 April 14, 2015, Public Meeting Slides for Primary Coolant System Branch Connection Weld Volumetric Examination Status - Palisades Nuclear Plant ML14169A5682014-06-13013 June 2014 Operator License Workshop Invitation ML13261A2282013-09-23023 September 2013 Notice of Forthcoming Conference Call with Entergy Nuclear Operations, Inc., on Palisades Equivalent Margins Analysis ML12305A5472012-11-0101 November 2012 Pre-application Meeting Notice Palisades ME9852 ML12138A3312012-05-17017 May 2012 05/31/2012, Notice of Significant Licensee Meeting (non-public) Regarding Operator Licensing Workshop and Meeting ML1117906392011-06-28028 June 2011 Summary of Meeting with Entergy Operations Inc ML1115704052011-06-0606 June 2011 Notice of Meeting with Entergy Operations, Inc., to Discuss Implementation of Quality Oversight and Verification Programs at Entergy Sites Including Actions Being Taken to Enhance Effectiveness ML1111605022011-05-0505 May 2011 EOC NRC Slides Presentation for Public Meeting ML1107504052011-03-21021 March 2011 Notice of Meeting with Entergy Operations, Inc., to Discuss Fleetwide Submittal for Proposed Technical Specification and Quality Assurance Program Manual Changes Related to Unit Staff Qualification Requirements ML1018105082010-07-0606 July 2010 Notice of Pre-Application Meeting with Entergy Nuclear Operations, Inc. to Discuss Palisades Spent Fuel Pool Submittal ML1017400612010-06-22022 June 2010 Palisades NRC Planning Meeting TLAA 10 CFR 54.21(c)(1)(iii) Pressurized Thermal Shock 10CFR50.61 (Slides) ML1015506112010-06-0909 June 2010 Notice of Pre-Application Meeting with Entergy Nuclear Operations Inc. to Discuss Pressurized Thermal Shock Analysis ML1015403862010-06-0202 June 2010 Documentation for Pressurized Thermal Shock Evaluation Meeting 2024-07-05
[Table view] Category:Meeting Briefing Package/Handouts
MONTHYEARML24212A3452024-07-30030 July 2024 August 1, 2024 Holtec Public Meeting Presentation on Potential Palisades Nuclear Plant Restart ML24193A0252024-07-11011 July 2024 NRC Presentation on Palisades Nuclear Plant Potential Reauthorization Scoping Meeting PNP 2024-023, Pre-Submittal Meeting Presentation - License Amendment Request to Approve the Biasi Critical Heat Flux (CHF) Correlation for Use with the Palisades Main Steam Line Break (MSLB) Analysis2024-05-0909 May 2024 Pre-Submittal Meeting Presentation - License Amendment Request to Approve the Biasi Critical Heat Flux (CHF) Correlation for Use with the Palisades Main Steam Line Break (MSLB) Analysis ML24116A2932024-04-29029 April 2024 Pre-Submittal Meeting on April 29, 2024 - Palisades Nuclear Plant Power Operations Quality Assurance Program Manual ML24086A5822024-04-0303 April 2024 Construction Permit Application: Initial Environmental & Site Characterization ML24074A3302024-03-18018 March 2024 March 18, 2024 Pre-submittal Meeting for Proposed Emergency Plan at the Palisades Nuclear Plant (Presentation) ML24036A1082024-02-0606 February 2024 Pre-submittal Meeting for Palisades Nuclear Plant Power Operations Technical Specifications Administrative Controls and Quality Assurance Program (Presentation) ML23334A1322023-12-0505 December 2023 Pre-submittal Meeting with Holtec for Palisades Nuclear Plant Power Operations Technical Specifications (Presentation) 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 ML23235A1802023-08-29029 August 2023 Public Meeting 08/29/23 - Palisades Nuclear Plant - Return to Power Operations - Exemption to CFR 50.82(a)(2) ML23139A1922023-05-24024 May 2023 Slides for Public Meeting on 5/24/23 PNP 2023-012, Presentation on Regulatory Path to Reauthorize Power Operations2023-03-16016 March 2023 Presentation on Regulatory Path to Reauthorize Power Operations ML22262A3032022-09-22022 September 2022 Post-Shutdown Decommissioning Activities Report Public Meeting Slides - September 22, 2022 ML21196A0872021-07-15015 July 2021 Slideshow for the July 1, 2021 Public End of Cycle Meeting for Palisades Nuclear Plant ML21124A0062021-05-12012 May 2021 Pre-Application PDTS Meeting Slides (L-2021-LRM-xxxx) ML20342A0022020-12-0808 December 2020 NRC License Transfer Application Pre-Submittal Meeting ML20269A3452020-09-28028 September 2020 Pre-submittal Meeting for Request for One-Time Exemption from 10 CFR Part 50, Appendix E, Biennial EP Exercise (Offsite) Due to COVID-19- Entergy Presentation Slides ML19231A2852019-08-19019 August 2019 NEIMA Meeting Slides - August 21 Palisades Meeting ML18107A3342018-04-10010 April 2018 Tech Spec 3.3.5.2a Change Pre-Submittal Meeting Presentation Slides ML17150A0012017-06-20020 June 2017 6/20/2017 Meeting Slides - Entergy Nuclear Operations, Inc. - Licensing Action Submittal Plan - Decommissioning (CAC Nos. MF9624, MF9625, MF9626, MF9627, and MF9628) ML17166A2892017-06-20020 June 2017 Entergy Slides for 06/20/2017 Public Meeting, Licensing Action Submittal Plan - Decommissioning. ML17080A1782017-03-20020 March 2017 3/20/2017, Meeting Slide Re. Palisades Nuclear Plant License Amendment Request; Application Meeting Cyber Security Plan Milestone 8 Implementation Schedule Change ML16344A0882016-12-0707 December 2016 December 7, 2016, Summary of Public Meeting with Entergy Nuclear Operations, Inc.- Meeting Slides ML16277A6212016-09-28028 September 2016 GSI-191 Closure Plan: September 28, 2016 - Meeting Slides ML16167A3722016-06-23023 June 2016 Nrc'S Annual Performance Assessment of Palisades for 2015 ML15107A3062015-04-14014 April 2015 April 14, 2015, Public Meeting Slides for Primary Coolant System Branch Connection Weld Volumetric Examination Status - Palisades Nuclear Plant ML15107A3072015-04-14014 April 2015 April 14, 2015, Corrected Public Meeting Slides for Primary Coolant System Branch Connection Weld Volumetric Examination Status - Palisades Nuclear Plant ML15093A2902015-04-0303 April 2015 Licensee End-of-Cycle Meeting Slides ML15093A2942015-04-0303 April 2015 NRC Meeting Slides ML14175A2992014-06-24024 June 2014 Licensee Presentation for Palisades 2013 Annual Assessment Public Meeting ML13193A3302013-07-16016 July 2013 NRC Internet Event Briefing - Palisades Safety Injection Refueling Water Tank (SIRWT) Leak Repair and Inspections ML13190A2552013-07-16016 July 2013 NRC Internet Event Briefing - Palisades Safety Injection Refueling Water Tank (SIRWT) Leak Repair and Inspections ML13140A3582013-05-20020 May 2013 May 23, 2013 NRC Presentation ML13091A1172013-04-0101 April 2013 EOC Licensee Slides for April 2, 2013 Meeting ML13080A3852013-03-21021 March 2013 NRC Slides for EOC Meeting 4/2/13 ML13010A2822013-01-10010 January 2013 January 12, 2013 Webinar Presentation Slides ML12338A1072012-12-11011 December 2012 NRC Public Meeting Slides for 12-11-12 PNP 2012-109, Public Meeting Slides for December 11, 2012 Meeting2012-12-0707 December 2012 Public Meeting Slides for December 11, 2012 Meeting ML12314A3712012-11-13013 November 2012 NFPA 805 Presubmittal Meeting 11 9 12 Rev 8 ML12255A0092012-09-11011 September 2012 Licensee Slides for Public Meeting September 12, 2012 ML12074A0692012-03-14014 March 2012 NRC EOC Slide Presentation for Public Meeting ML12058A4912012-02-27027 February 2012 Public Meeting Slides, Palisades Nuclear Plant ML1201000572012-01-11011 January 2012 Swp Presentation for Meeting January 11, 2012 at 9am ML1117906392011-06-28028 June 2011 Summary of Meeting with Entergy Operations Inc ML1111605022011-05-0505 May 2011 EOC NRC Slides Presentation for Public Meeting ML1110401532011-04-13013 April 2011 Licensee Slides from 4/13/11 Meeting with Entergy Operations, Inc., to Discuss Proposed National Fire Protection Programs Standards 805 License Amendment Submittal for Arkansas Nuclear One, Units 1 & 2 ML1020206332010-07-21021 July 2010 July 21, 2010, Areva Meeting Slides ML1017400612010-06-22022 June 2010 Palisades NRC Planning Meeting TLAA 10 CFR 54.21(c)(1)(iii) Pressurized Thermal Shock 10CFR50.61 (Slides) ML1012602072010-05-11011 May 2010 Slides, Presentation for Palisades Annual Assessment Meeting - Reactor Oversight Program - 2009 ML1013002252010-05-0707 May 2010 Draft Responses to NRC RAI in Preparation for Meeting on May 12 and 13, 2010 - GL 2004-02 2024-07-30
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- CPCo MEETING WITH NRC PALISADES PRESSURIZER SAFE-END CRACK ENGINEERING ANALYSIS AND ROOT CAUSE EVALUATION OCTOBER 12, 1993 consumers Power
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CONSUMERS POWER COMPANY MEETING WITH NRC PALISADES PRESSURIZER SAFE-END CRACK
- ENGINEERING ANALYSIS AND ROOT CAUSE EVALUATION OCTOBER 12, 1993 AGENDA
- 1. Introduction and Plant Status GBSlade
- 2. Sequence of Events DJVandeWa 11 e
- 3. Safety Assessment DJVandeWalle
- 4. Metallurgical Examination Results DJVandeWa 11 e
- 5. Cause of the Safe-End Crack RBJenkins
- 6. Repair of the Pressurizer.Safe-End RBJenkins
- 7. Examination Methods and Flaw Detectability BVVanWagner
- 8. Evaluation of Other Pressurizer Nozzles DJVandeWalle
- 9. Other PCS Welds with Dissimilar Metals DJVandeWalle
- 11. Response to NRC Requests for Information
- 12. Long Term Corrective Actions PD Fitton DJVandeWall e DJVandeWa 11 e 13 . Summary GBSlade
PALISADES PRESSURIZER SAFE-END CRACK Sequence of Events June, 1993 Possible flaw identified in pressurizer relief valve nozzle safe end. Flaw evaluated and dispositioned as original construction flaw which would not grow.
September 16 Shortly after plant reached hot shutdown (532"F, 2060 psia), 0.2 gpm leak was identified on containment sump level instrumentation. Auxiliary operator reported steam leak in pressurizer shed shortly thereafter.
September 17 Plant achieved cold shutdown permitting direct visual and NDE examination of crack. Crack was characterized as circumferential, in safe end of pipe, near safe-end to pipe weld and approximately three inches in length .
PALISADES PRESSURIZER SAFE-END CRACK Safety Assessment
- The root cause of the P~SCC crack in the pressurizer relief valve safe-end has been identified.
- The repaired safe-end will be suitable for service for at least one more operating cycle. A final repair to the pressurizer relief valve safe-end and PORV line will be performed during the next refueling outage as committed in the long term action plan.
- Similar (circumferential) through wall cracks in other similar pressurizer or PCS nozzle safe-ends or welds containing inconel or austenitic stainless steel are unlikely based on our understanding of the pressurizer nozzle safe-end cracking mechanism and the inspections of potentially susceptible nozzle safe-ends that have been performed.
- However, should a crack occur in a nozzle safe-end, the leak will be detected by the Palisades leakage monitoring systems and the plant safely shut down before the load carrying capability of the safe-end will no longer be adequate to 'withstand normal and faulted condition.
- The Palisades primary coolant system leakage monitoring systems are
- capable of detecting leakage from the type and size of crack that occurred in the pressurizer relief valve nozzle safe-end within a very short period of time and prompt action will be taken on the part of
- the operations personnel to shut down the plant .
PALISADES PRESSURIZER SAFE-END CRACK Metallurgical Examination Results
- Cracking mode was int~rgranular in the safe-end heat affected zone.
- Cracking initiated from the inside surface of the safe-end.
- Cracks ran perpendicular to the inside surface without significant propagation in the axial and azimuthal directions.
- The outside surface of the crack consisted of six discontinuous cracks, the total length was about three inches.
- An original weld root repair, apparently made from the inside of the safe-end, was located adjacent to the crack initiation point.
- There was evidence of grinding on the root of the weld.
- A significant (1/16") mismatch existed between the ID of the safe-end and the stainless steel pipe.
- Shallow intergranular penetrations were present on the inner surface of the heat affected zone.
- A black oxide was present on the fracture surface indicating that the crack had existed for some period of time prior to the refueling outage .
- Base metal and heat affected zone consist of large, course grains with a continuous intergranular carbide network and numerous fine intrragranular carbides.
- Chemical composition of base metal and heat affected zone is consistent with ASME purchase specification for this material.
PALISADES PRESSURIZER SAFE-END CRACK Cause of the Safe-End Crack
A metallurgical condition An aggressive steam/water environment A threshold stress valve
- The safe-end was made of a material with a high yield stress which made it vulnerable to PWSCC. These vulnerabilities are reflected by:
A high hardness HRC-22 A high yield stress of 77KSI An assumed low (1600-1700°F) post-forging heat treatment
- The safe-end was exposed to stagnant steam at approximately 640°F .
The material would be highly sensitive to cracking at this temperatures.
- Although externally applied piping system loads induced by pressure, weight, thermal expansion and potential flow stratification meet design requirements and are relatively low, significant local stresses appear to exist at the Inconel/stainless steel safe-end weld. These stresses are due to The field welding process The mismatch in pipe/safe-end sizes The materials mismatched thermal effects To add insight into the load assessment, analysis of dissimilar metal effects and flow stratification were conducted. These evaluations led to the conclusion that the external piping loads as induced by the piping support system were not the driving forces for the crack. The local pipe/safe-end configuration and fabrication process are viewed as the primary contributors .
PALISADES PRESSURIZER SAFE-END CRACK Repair of the Pressurizer Safe-End
- The heat affected zone of the inconel material was removed and the weld prep machined to assure that the new heat affected zone does not have intergranular penetration or discontinuities that could act as stress risers.
- The fit-up between the safe-end and stainless steel pipe was improved .
- The inner surface of the weld was ground smooth .
- There were no repair weld deposits made to the inner surface of the weld.
- All of these improvements and changes will extend potential crack initiation time significantly, resulting in increased lifetime for the repaired weld as compared to the original weld.
- Very conservative crack propagation calculations indicate more than 20 months at temperature and pressure (640"F, 2060 psia) would be required for a crack to grow through wall.
- Time to crack initiation in the heat affected zone of the new safe-end should be comparable to that of the original safe-end heat affected zone. No credit is _taken for this in the calculation of time to through wall cracking .
- Therefore, the lifetime of the new weld will exceed one operating cycle .
PALISADES PRESSURIZER SAFE-END CRACK Examination Methods and Flaw Detectability
Dye penetrant (PT), Radiography (RT) and Ultrasonic Testing (UT) were used to examine the PORV line and the additional sample of welds.
Where possible, a combination of examinations was used to provide the highest confidence possible.
Also where possible, mockups were utilized to further address the effectiveness of the examinations performed.
All examinations were preformed utilizing qualified personnel and procedures.
For all new welds, radiography and dye penetrant were utilized for acceptance.
CPCo has a high degree of confidence in the NDE performed and our ability to detect the crack sizes which could grow through wall during the next plant operating cycle .
- CPCo believes radiography did detect the crack in the PORV safe-end in June of 199
PALISADES PRESSURIZER SAFE-END CRACK Evaluation of Other Pressurizer Nozzles
- Other pressurizer nozzles: pressurizer heater sleeves (120),
temperature instruments (2), level instruments (8), safety relief valve flanges (3), spray nozzle, surge nozzle
Palisades heater sleeves characterized as having low susceptibility by CE Owners Group Work. Characterization was based on low yield strength of Inconel material and absense of pre-installation reaming of the sleeves.
Cracking mode will be axially oriented and thus do not represent a safety issue.
Visual inspections per CEOG recommendations have not identified any leaks.
Similar to heater sleeves in that nozzles are solid inconel and welded to pressurizer by partial penetration welds.
Cracks will axially oriented and thus not a safety concern .
Low alloy nozzles with inconel transition piece and stainless steel safe-end.
Consumers Power sponsored study of residual stresses in the butt welds in these nozzles. The study showed only compressive or relatively low tensile stresses.
Inconel material is of relatively low yield strength (46.2 ksi).
Conclusion is that cracking is unlikely but would be axially oriented .
PALISADES PRESSURIZER SAFE-END CRACK Evaluation of Other Pressurizer Nozzles
Fabricated from same high nozzle.
yi~ld strength inconel as relief valve Axial stresses may be present in the flanges.
Flanges experiences high temperatures in the pressurizer vapor space.
Nozzles and flanges were stress relieved in the shop during fabrication of the pressurizer. This will reduce weld residual stresses.
- Nozzle to flange weld area has been extensively inspected with dye penetrant, ultrasonic and radiography with no recordable indications noted. Also, there is no evidence in original construction records or from visual examination of the welds of any weld repairs made from the inside of the nozzle.
Conclusion is that flanges are suitable for service.
Fabricated from same high yield strength inconel as relief valve nozzle.
Axial stresses may be present in the welds and safe-end.
Temperature of the welds and safe-end is considerably lower than the pressurizer steam due to the continuous flow of cooler water at cold leg temperature.
The nozzle and nozzle-to-safe-end weld were stress relieved in the shop during fabrication of the pressurizer. This will reduce weld residual stresses. The safe-end-to-pipe weld was not stress relieved.
Nozzle-to-safe-end and safe-end-to-pipe welds were examined using dye penetrant and radiography with no recordable indications.
Conclusion is that spray nozzle and safe-end are suitable for service .
PALISADES PRESSURIZER SAFE-END CRACK Evaluation of Other Pressurizer Nozzles
Fabricated from a different heat of inconel material with significantly lower yield strength {51 ksi). The time to initiation
- of PWSCC will be approximately four times as long for this material as the pressurizer relief valve safe-end material, everything else being the same.
Axial stresses may be present in the welds and safe-end.
Temperature of the welds and safe-end is near the pressurizer temperature.
The nozzle and safe-end are exposed to pressurized water as opposed to steam. The majority of PWSCC occurrences, and all leaks, in industry pressurizers involving inconel material of the same ASME material specification {SB-166) have occurred in the pressurizer steam space.
The nozzle and nozzle-to-safe-end weld were stress relieved in the shop during fabrication of the pressurizer. This will reduce weld residual stresses. The safe-end-to-pipe weld was not stress relieved.
Nozzle-to-safe-end and safe-end-to-pipe welds were examined using IGSCC qualified ultrasonic techniques last weekend with no recordable indications .
Conclusion is that surge nozzle and safe-end are suitable for service .
PALISADES PRESSURIZER SAFE-END CRACK Cracking of Other Materials in PCS Dissimilar Metal Welds
- The root cause of these failures has been attributed to high weld residual stresses, sensitization of the stainless steel and high oxygen content in the coolant.
- The solution for the BWR problem has been the introduction of a hydrogen water chemistry designed to lower the electro-chemical potential of the coolant. In operating PWRs, the normal ECP is well below the critical potential for IGSCC.
- There have been several events of IGSCC in PWRs, including CROM seal housings, but all have involved geometries where aerated water was trapped.
- Therefore, IGSCC in the austenitic stainless steel welds in the Palisades PCS is unlikely. *
PALISADES PRESSURIZER SAFE-END CRACK Inconel 600 Program
PALISADES PRESSURIZER SAFE-END CRACK Long Term Corrective Actions The design of the pressurizer relief valve nozzle and PORV line will be reviewed and appropriate modifications will be made during the next refueling shutdown to assure a suitable lifetime for the pressurizer relief valve nozzle safe-end. The review will be coordinated with the safety-related piping reverification project (SRPRP) review of the PORV line.
- A comprehensive program to deal with Inconel 600 issues at Palisades will be developed. The program will guide future inspections and replacements of Inconel 600 components in the primary coolant system.
- Further evaluation and qualification of non-destructive examination techniques for detection of PWSCC will be conducted. This will include development of an appropriate mockup and qualification of ultrasonic examination techniques for PWSCC .