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EPID:L-2020-LRO-0051, Summary of September 11, 2020, Conference Call with Entergy Nuclear Operations Inc. Regarding the Fall 2020 Steam Generator Tube Inspections at Palisades Nuclear Plant (Open) |
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MONTHYEARML20280A6972020-10-13013 October 2020 20200910 NRC Mid Outage Q and a for Phone Call for Palisades 1R27-Entergy Responses Project stage: Other ML20280A6942020-10-13013 October 2020 Summary of September 11, 2020, Conference Call with Entergy Nuclear Operations Inc. Regarding the Fall 2020 Steam Generator Tube Inspections at Palisades Nuclear Plant Project stage: Request ML20280A6962020-10-13013 October 2020 20200912 NRC Mid Outage Q and a for Phone Call for Palisades 1R27 (Revised) Project stage: Other 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 Project stage: Other 2020-10-13
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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: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
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STEAM GENERATOR TUBE INSPECTION DISCUSSION POINTS Palisades 2020 Inspection (1R27)
Currently Palisades is ~ 90% through the base scope eddy current inspection and starting the special interest inspection scope as of 09/10/2020 at ~ 0900 hours0.0104 days <br />0.25 hours <br />0.00149 weeks <br />3.4245e-4 months <br /> The following discussion points have been prepared to facilitate the conference call arranged with the licensee to discuss the results of the steam generator (SG) tube inspections to be conducted during the upcoming fall 2020, Palisades Nuclear Plant, refueling outage. This conference call is scheduled to occur towards the end of the planned SG tube inspections, but before the inspections and repairs are completed.
The Nuclear Regulatory Commission (NRC) staff plans to document a summary of the conference call, as well as any material that is provided in support of the call.
- 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 27 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 are planned for the 2020 refueling outage (1R27).
- 3. Discuss any exceptions taken to the industry guidelines.
In cycle 22, Palisades submitted a deviation to the NRC: Technical Justification Supporting Deviation from the EPRI Appendix I ETSS for ODSCC Sizing Revision 8 of the EPRI PWR Steam Generator Examination Guideline was incorporated in June 2016. Under this revision, Appendix I now is a more generic approach to how a utility is to develop a data set that can be used for probability of detection (POD) and sizing methodologies.
Palisades uses a modified ETSS for ODSCC. The modified ETSS will be identical to the ETSS approved per Appendix I of the examination guidelines with the exception that only the sub-set of data from CE plants will be used instead of the combined fleet data set used in the approved ETSS.
A comprehensive review of axial ODSCC in Palisades steam generators shows that Appendix I28432 over sizes maximum depth values for axial ODSCC at Palisades. There is a reasonable basis to submit a deviation request for maximum depth sizing of axial ODSCC indications at Palisades. The request is relatively modest since it uses the Combustion Engineering (CE) subset of the
well vetted data of Appendix I28432. The regression slope and standard error of regression are retained. Only the intercept parameter is changed. This provides an across the board reduction of NDE maximum depth sizing of 11.23 %TW.
This will lead to about a 1000 psi increase in calculated condition monitoring burst pressures and much better matching of projected and measured NDE maximum depths.
The deviation was implemented in the 2012 (1R22) refueling outage steam generator inspection for the remaining life of the existing Palisade steam generators.
- 4. For each SG, 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.
Full length ECT bobbin coil examination of all in-service tubes (except row 1, 2, and 3 U-bends) in both SGs.
ECT +Point' coil examinations (both SGs):
- 100% of rows 1, 2, and 3 U-bends.
- 100% of hot leg from TTS + 4 to a minimum of 13.5 below the bottom of the expansion transition.
- 100% of free span dings >5V between TSH and TSC.
- 100% of >2V dents at eggcrate, diagonal bar, and vertical strap intersections between TSH and TSC.
- 25% of historical %TW calls at diagonal bars and vertical straps
- 100% of historical trackable (TRA) indications
- The outer 3 peripheral tubes at the cold leg from TTS+4 to TTS-2 for detection of possible loose parts or wear signals. The periphery region is defined to be the outer three (3) tubes exposed to the annulus, all tubes in rows 1 through 4, and the inner three (3) tubes around the stay cylinder region.
Special interest examinations which include but are not limited to:
- All current outage bobbin I-code signals
- All eggcrate bobbin %TWs called during the current outage
- All wear scars 40%TW by bobbin
- All new %TWs indications regardless of location
- The hot leg square bend region of tubes surrounding SGB tube R99-C140
- All bobbin foreign object and foreign object wear indications
- Bounding of foreign object signals (new in 1R27 and RPC-confirmed PLPs from 1R26) and foreign object wear at all elevations. These bounding exams will continue until a one tube deep perimeter has been examined in which no PLP or foreign object wear indication is identified.
- Bounding of locations in tubes recently plugged that had PLP indication or foreign object wear near the TTS. See Table 5-2 for list of plugged tubes that meet this requirement.
- Mag-biased +Point' coil examination of all bobbin PVN indications that cannot be eliminated using non-mag-biased +Point' coil.
- All tube regions which cannot be examined effectively with bobbin probe due to data quality concerns.
- Any other location specified by TIE as required to support CMOA.
- 5. For each area examined (e.g., tube supports, dent/dings, sleeves, etc.), provide a summary of the number of indications identified to date for each degradation mode (e.g., number of circumferential primary water stress-corrosion cracking (PWSCC) 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 PWSCC at the expansion transition for the first time at this unit).
As of 9/10/2020 @ 0900 hours0.0104 days <br />0.25 hours <br />0.00149 weeks <br />3.4245e-4 months <br /> Number Number Integrity SG Location Type Indications Tubes Acceptable A TSH Axial ODSCC 4 4 YES A TSH Axial PWSCC 0 0 N/A A TSH Circ PWSCC 0 0 N/A A TSH Circ ODSCC 13 13 YES A TSH Volumetric 1* 1* YES A TEC to TEH Wear > 40 1 1 YES B TSH Axial ODSCC 4 4 YES B TSH Axial PWSCC 1 1 YES B TSH Circ PWSCC 0 0 N/A B TSH Circ ODSCC 4 3 YES B TSH Volumetric 2 1 N/A B TEH to TEC Wear > 40 0 0 YES A Tube Supports Axial ODSCC 6* 5* YES A Freespan Axial ODSCC 0 0 N/A B Tube Supports Axial ODSCC 0* 0* YES B Freespan Axial ODSCC 0 0 N/A Total 36 33
- Some indications have been identified but are not completely through the data resolution process as of this snapshot. Updated quantities may be presented verbally during the phone call.
SGA
+Point Probe, ETSS I-28431 100 90 Limit 80 Flaws 70 Burst Equivalent Depth (%TW) 60 50 40 30 20 10 0
0.00 0.25 0.50 0.75 1.00 1.25 1.50 1.75 2.00 2.25 2.50 Burst Equivalent Length (Inches)
- Circ ODSCC at TSH. Max indication parameters (not the same indication):
o Voltage: 0.81 V o Circumferential extent: 0.71 (109 degrees) o Depth: 78 %TW o PDA: 7.44 o SIPC and AILPC criteria satisfied
o Max depth: 41 %TW o SIPC and AILPC criteria satisfied
- Historical (carryover from previous inspection) foreign object wear flaws o Max depth: TBD %TW o SIPC and AILPC criteria satisfied
- No newly-identified foreign object wear flaws SG B
+Point Probe, ETSS I-28431 100 90 Limit 80 Flaws 70 Burst Equivalent Depth (%TW) 60 50 40 30 20 10 0
0.00 0.25 0.50 0.75 1.00 1.25 1.50 1.75 2.00 2.25 2.50 Burst Equivalent Length (Inches)
- Axial PWSCC within tube sheet:
o Max Voltage: 0.52 V o Max Length: 0.14 o Max Depth: 42.9 %TW o SIPC and AILPC criteria satisfied
- Circ ODSCC at TSH. Max indication parameters (not the same indication):
o Voltage: 0.84 V o Circumferential extent: 0.79 (116 degrees) o Depth: 53 %TW o PDA: 6.73 o SIPC and AILPC criteria satisfied
o Max depth: 40 %TW o SIPC and AILPC criteria satisfied
- Historical (carryover from previous inspection) foreign object wear flaws o Max depth: 23 %TW o SIPC and AILPC criteria satisfied
- No newly identified foreign object wear flaws Both SGs - Support Structure Wear
- Average growth is essentially zero
- 95/50 growth rate is <2.0 %TW/EFPY
Freespan There are no free span repairable indications reported as of this date. Some support indications have been identified but are not completely through the data resolution process as of this snapshot. Updated quantities may be presented verbally during the phone call.
U-Bends There are no U-bend repairable indications reported to date.
- 6. Describe repair/plugging plans.
Currently there are 24 potential tubes requiring tube plugging in SG E-50A and 9 potential tubes in SG E-50B.
All stress corrosion cracking (SCC) indications will be plugged. Any circumferential SCC indications near the top-of-tube sheet (TTS) will be stabilized and plugged. C* depth is applicable to the HL and CL.
All wear indications (at support structures) greater than or equal to 40%TW will be plugged.
Any indication of foreign objects that present a threat to tube integrity will be plugged and stabilized as necessary. Presently, there are no such indications.
- 7. Describe in-situ pressure test and tube pull plans and results (as applicable and if available).
Based on the available data to date, no tubes will require in-situ pressure testing and none is planned for any reason.
No tube pulls were planned before the outage and there is presently no plan or reason to conduct a tube pull.
- 8. Discuss the following regarding loose parts:
- what inspections are performed to detect loose parts; The hot leg top of tube sheet (TTS) region is inspected with +Pt up to a nominal 4 inches, but not less than 3.5 inches and not less than the height of the sludge pile, above TTS. A similar inspection is performed for the cold leg TTS region 3 tubes deep along periphery and tube lane and 3 inches above the TTS. Foreign object search and retrieval (FOSAR) will be performed for the periphery, tube lane annulus, and stay cavity areas. This is similar to last outage.
- a description of any loose parts detected and their location within the SG (including the source or nature of the loose part, if known);
Since FOSAR has not yet started, no objects have been removed from the secondary side.
As of 9/10/2020 at 0900 hours0.0104 days <br />0.25 hours <br />0.00149 weeks <br />3.4245e-4 months <br />, the following are the number of PLP (potential loose part) indications identified with the plus point inspection:
E-50A 150 PLP Calls in 143 Tube Locations E-50B 99 PLP Calls in 95 Tube Locations The vast majority (over 85%) of the indications are historical. None have resulted in tube degradation. Anticipate FOSAR start on 9/11/2020
- if the loose parts were removed from the SG; and Anticipate FOSAR to start on 9/11/2020.
- indications of tube damage associated with the loose parts Anticipate FOSAR to start on 9/11/2020.
- 9. Discuss the scope and results of any secondary side inspection and maintenance activities (e.g., in-bundle visual inspections, feed-ring inspections, sludge lancing, assessing deposit loading).
No secondary side inspection and maintenance activities are scheduled for 1R27.
- 10. Discuss any unexpected or unusual results.
Currently there are no unexpected or unusual results. There are no tubes that have failed the screening criteria requiring in-situ pressure testing
- 11. Provide the schedule for SG-related activities during the remainder of the current outage.
The base scope bobbin and top of tube sheet inspections are nearly complete. Special interest examinations are ongoing. U-bend examinations are pending. Nominal SG schedule is as follows:
Scheduled complete ECT 9/12/2020 Scheduled complete repair 9/13/2020 Scheduled SG closeout 9/14/20208
Attachment 1 Primary to Secondary Leakage