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Category:Inservice/Preservice Inspection and Test Report
MONTHYEARL-2023-103, Inservice Inspection Examination Report2023-08-0303 August 2023 Inservice Inspection Examination Report L-2023-023, Revised Steam Generator Tube Inspection Report2023-03-0303 March 2023 Revised Steam Generator Tube Inspection Report SBK-L-22036, Steam Generator Tube Inspection Report2022-04-25025 April 2022 Steam Generator Tube Inspection Report SBK-L-22003, Inservice Inspection Examination Report2022-01-24024 January 2022 Inservice Inspection Examination Report SBK-L-21126, Fourth 10 Year Interval - Inservice Inspection (ISI) Program Plan2022-01-0404 January 2022 Fourth 10 Year Interval - Inservice Inspection (ISI) Program Plan SBK-L-20132, Fourth Interval Inservice Testing (IST) Program2020-10-21021 October 2020 Fourth Interval Inservice Testing (IST) Program SBK-L-20103, Inservice Inspection Examination Report2020-07-27027 July 2020 Inservice Inspection Examination Report SBK-L-19052, Steam Generator Tube Inspection Report2019-04-19019 April 2019 Steam Generator Tube Inspection Report SBK-L-19001, Inservice Inspection Examination Report2019-01-24024 January 2019 Inservice Inspection Examination Report SBK-L-17166, Generator Tube Inspection Report2017-10-17017 October 2017 Generator Tube Inspection Report SBK-L-17117, Inservice Inspection Examination Report2017-07-18018 July 2017 Inservice Inspection Examination Report SBK-L-16100, Inservice Testing Program for the Third 10-Year Interval2016-07-21021 July 2016 Inservice Testing Program for the Third 10-Year Interval SBK-L-16015, Inservice Inspection Examination Report2016-02-10010 February 2016 Inservice Inspection Examination Report SBK-L-14119, Inservice Inspection Examination Report2014-06-14014 June 2014 Inservice Inspection Examination Report SBK-L-13019, Inservice Inspection Examination Report2013-01-28028 January 2013 Inservice Inspection Examination Report SBK-L-11197, Request for Alternative to Use ASME Code Case N-716 to Implement Risk-Informed Inservice Inspection Program2011-11-0707 November 2011 Request for Alternative to Use ASME Code Case N-716 to Implement Risk-Informed Inservice Inspection Program SBK-L-11191, Third Ten-Year Interval Inservice Inspection Relief Requests2011-09-26026 September 2011 Third Ten-Year Interval Inservice Inspection Relief Requests SBK-L-11170, Inservice Inspection Examination Report2011-08-11011 August 2011 Inservice Inspection Examination Report SBK-L-11132, Submittal of Third Ten-Year Interval Inservice Inspection and Second Ten-Year Containment Inservice Inspection Program2011-06-22022 June 2011 Submittal of Third Ten-Year Interval Inservice Inspection and Second Ten-Year Containment Inservice Inspection Program SBK-L-10027, Inservice Inspection Examination Report for Inspections Conducted Prior to and During the Thirteenth Refueling Outage That Concluded on November 12, 20092010-02-0909 February 2010 Inservice Inspection Examination Report for Inspections Conducted Prior to and During the Thirteenth Refueling Outage That Concluded on November 12, 2009 ML0929201562009-10-0707 October 2009 Seabrook Station - 10 CFR 50.55a Request 2AR-07, Second Interval ISI Program Category B-P Exams - 10-Year Class 1 System Leakage Test SBK-L-09122, Response to Request for Additional Information Regarding a Request for Relief from Inservice Inspection Requirements2009-05-27027 May 2009 Response to Request for Additional Information Regarding a Request for Relief from Inservice Inspection Requirements SBK-L-09038, Supplement to Request for Relief from Inservice Inspection Requirements2009-02-24024 February 2009 Supplement to Request for Relief from Inservice Inspection Requirements SBK-L-08135, Inservice Inspection Examination Report for Inspections Conducted Prior to and During the Twelfth Refueling Outage2008-07-21021 July 2008 Inservice Inspection Examination Report for Inspections Conducted Prior to and During the Twelfth Refueling Outage SBK-L-07088, Steam Generator Inservice Inspection2007-05-23023 May 2007 Steam Generator Inservice Inspection SBK-L-07024, Inservice Inspection Examination Report, for Inspections Conducted Prior to and During the Eleventh Refueling Outage That Concluded on November 10, 20062007-02-0202 February 2007 Inservice Inspection Examination Report, for Inspections Conducted Prior to and During the Eleventh Refueling Outage That Concluded on November 10, 2006 SBK-L-05145, Inservice Inspection Examination Report2005-07-29029 July 2005 Inservice Inspection Examination Report SBK-L-04040, Steam Generator Inservice Inspection2004-10-12012 October 2004 Steam Generator Inservice Inspection ML0403601082004-02-18018 February 2004 Review of Steam Generator Tube Inservice Inspection Report for the 2002 Refueling Outage ML0403706262004-01-29029 January 2004 Transmittal of Inservice Inspection Examination Report ML0331804642003-11-0303 November 2003 Steam Generator Tubes Plugged During Ninth Inservice Inspection ML0327314152003-09-23023 September 2003 Revision to Inservice Test Program Relief Request PR-3 ML0312200282003-04-24024 April 2003 Generator Inservice Inspection ML0225500502002-08-29029 August 2002 Inservice Inspection Examination Report 2023-08-03
[Table view] Category:Letter
MONTHYEARML24009A1152024-01-29029 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L 2023 LLE-0043 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) L-2024-010, Point Units 3 and 4, Seabrook, Duane Arnold, and Point Beach Units 1 and 2, Nuclear Property Insurance - 10 CFR 50.54(w)(3)2024-01-25025 January 2024 Point Units 3 and 4, Seabrook, Duane Arnold, and Point Beach Units 1 and 2, Nuclear Property Insurance - 10 CFR 50.54(w)(3) ML24022A0652024-01-22022 January 2024 Senior Reactor and Reactor Operator Initial License Examinations L-2024-003, NextEra Energy Seabrook, LLC - 10 CFR 50.46 - Emergency Core Cooling System LBLOCA 30-Day Report2024-01-11011 January 2024 NextEra Energy Seabrook, LLC - 10 CFR 50.46 - Emergency Core Cooling System LBLOCA 30-Day Report ML23312A1822023-12-22022 December 2023 Issuance of Amendment No. 172 Revision to Cooling Tower Service Water Loop or Cell Requirements L-2023-173, Quality Assurance Topical Report (FPL-1) Revision 30 Update2023-12-15015 December 2023 Quality Assurance Topical Report (FPL-1) Revision 30 Update L-2023-180, Submittal of Changes to the Technical Specification Bases2023-12-13013 December 2023 Submittal of Changes to the Technical Specification Bases L-2023-177, Supplement to Seabrook Exemption Request Regarding Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Final Rule2023-11-29029 November 2023 Supplement to Seabrook Exemption Request Regarding Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Final Rule L-2023-155, Supplement to Response to Request for Additional Information, Revised NextEra Common Emergency Plan, and Revised Site-Specific Emergency Plan Annexes Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-06542023-11-28028 November 2023 Supplement to Response to Request for Additional Information, Revised NextEra Common Emergency Plan, and Revised Site-Specific Emergency Plan Annexes Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, L-2023-160, Part 73 Exemption Request Regarding Enhanced Weapons, Firearms, Background Checks, and Security Event Notifications Final Rule2023-11-16016 November 2023 Part 73 Exemption Request Regarding Enhanced Weapons, Firearms, Background Checks, and Security Event Notifications Final Rule ML23318A0772023-11-14014 November 2023 Request for Information and Notification of Conduct of IP 71111.21.N.04, Age-Related Degradation, Reference Inspection Report 05000443/2024011 IR 05000443/20234032023-11-0707 November 2023 Security Baseline Inspection Report 05000443/2023403 and Independent Spent Fuel Storage Installation 07200063/2023401 IR 05000443/20230032023-11-0606 November 2023 Integrated Inspection Report 05000443/2023003 IR 05000443/20230102023-10-19019 October 2023 Triennial Fire Protection Inspection Report 05000443/2023010 ML23346A1322023-10-0606 October 2023 Communication from C-10 Research & Education Foundation Regarding NextEra Common Emergency Fleet Plan License Amendment Request and Related Documents Subsequently Published ML23275A0522023-10-0202 October 2023 Requalification Program Inspection IR 05000443/20234012023-09-0808 September 2023 Cybersecurity Inspection Report 05000443/2023401 (Cover Letter Only) IR 05000443/20234202023-09-0505 September 2023 Security Baseline Inspection Report 05000443/2023420 IR 05000443/20230052023-08-31031 August 2023 Updated Inspection Plan for Seabrook Station (Report 05000443/2023005) L-2023-114, Proposed Turkey Point Units 6 and 7; Seabrook Station; Point Beach Units 1 and 2 - Official Service List Update2023-08-17017 August 2023 Proposed Turkey Point Units 6 and 7; Seabrook Station; Point Beach Units 1 and 2 - Official Service List Update IR 05000443/20233022023-08-16016 August 2023 Operator Licensing Retake Examination Report 05000443/2023302 IR 05000443/20230022023-08-0808 August 2023 Integrated Inspection Report 05000443/2023002 L-2023-098, and Point Beach Units 1 and 2 - Response to Request for Additional Information Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 22023-08-0707 August 2023 and Point Beach Units 1 and 2 - Response to Request for Additional Information Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 2 ML23201A0872023-08-0303 August 2023 Audit Plan in Support of Review of License Amendment L-2023-104, Preparation and Scheduling of Operator Licensing Examinations2023-08-0303 August 2023 Preparation and Scheduling of Operator Licensing Examinations L-2023-103, Inservice Inspection Examination Report2023-08-0303 August 2023 Inservice Inspection Examination Report ML23192A0782023-07-11011 July 2023 Operator Licensing Retake Examination Approval L-2023-087, Florida Power & Light/Nextera Energy, Results of the Safety Culture Program Effectiveness Review, March 20, 2023 (ADAMS Accession No. ML22340A452)2023-06-29029 June 2023 Florida Power & Light/Nextera Energy, Results of the Safety Culture Program Effectiveness Review, March 20, 2023 (ADAMS Accession No. ML22340A452) SBK-L-23053, Radiological Emergency Plan (Ssrep), Revision 802023-06-22022 June 2023 Radiological Emergency Plan (Ssrep), Revision 80 ML23157A0722023-06-0606 June 2023 Notification of Conduct of a Fire Protection Team Inspection L-2023-074, Addendum to 2021 Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation Ctsfsi) Financial Assurance Update2023-06-0202 June 2023 Addendum to 2021 Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation Ctsfsi) Financial Assurance Update L-2023-071, NextEra Energy Quality Assurance Topical Report (FPL-1) Revision 29 and Florida Power and Light Company Quality Assurance Program Description for 10 CFR Part 52 Licenses (FPL-2) Revision 11, Annual Submittal2023-05-22022 May 2023 NextEra Energy Quality Assurance Topical Report (FPL-1) Revision 29 and Florida Power and Light Company Quality Assurance Program Description for 10 CFR Part 52 Licenses (FPL-2) Revision 11, Annual Submittal IR 05000443/20233012023-05-15015 May 2023 Initial Operator Licensing Examination Report 05000443/2023301 L-2023-064, License Amendment Request 23-01, Revision 1, Update the Period of Applicability (Poa) for the Pressure-Temperature Limits (PTL) and Low Temperature Overpressure Protection (L Top) Curves2023-05-11011 May 2023 License Amendment Request 23-01, Revision 1, Update the Period of Applicability (Poa) for the Pressure-Temperature Limits (PTL) and Low Temperature Overpressure Protection (L Top) Curves IR 05000443/20230012023-05-11011 May 2023 Integrated Inspection Report 05000443/2023001 ML23129A0312023-05-0909 May 2023 Reactor Operator Retake License Examination ML23117A3652023-05-0404 May 2023 Supplemental Information Needed for Acceptance of Requested Licensing Action Amendment Request to Remove Period of Applicability from PTL and Low Temperature Over Pressure Protection Curves SBK-L-23044, 2022 Annual Radiological Environmental Operating Report2023-04-28028 April 2023 2022 Annual Radiological Environmental Operating Report SBK-L-23031, 2022 Annual Radioactive Effluent Release Report2023-04-28028 April 2023 2022 Annual Radioactive Effluent Release Report SBK-L-23033, 2022 Annual Environmental Operating Report2023-04-11011 April 2023 2022 Annual Environmental Operating Report L-2023-053, Core Operating Limits Report for Cycle 232023-04-0505 April 2023 Core Operating Limits Report for Cycle 23 ML23088A1522023-03-29029 March 2023 Summary of Meeting Between Nrc/Region I and C-10 - Questions Regarding Seabrook 4Q2022 Inspection Report L-2023-021, Units, 1 and 2, Turkey Point, Units 3 and 4, Seabrook Station and Point Beach, Units 1 and 2 - Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation (ISFSI) Financial Assurance Update2023-03-28028 March 2023 Units, 1 and 2, Turkey Point, Units 3 and 4, Seabrook Station and Point Beach, Units 1 and 2 - Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation (ISFSI) Financial Assurance Update L-2023-028, and Point Beach Units 1 and 2, 10 CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications2023-03-27027 March 2023 and Point Beach Units 1 and 2, 10 CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications ML23073A1562023-03-23023 March 2023 Relief Request 4RA-22-01, Relief from the Requirements of the ASME Code L-2023-012, License Amendment Request 23-01, Remove Period of Applicability (Poa) from Pressure Temperature Limits (PTL) and Low Temperature Overpressure Protection (L Top) Curves2023-03-15015 March 2023 License Amendment Request 23-01, Remove Period of Applicability (Poa) from Pressure Temperature Limits (PTL) and Low Temperature Overpressure Protection (L Top) Curves L-2023-025, Fleet Relief Request (Frr) 23-01, Proposed Alternative to ASME Section XI Authorizing Implementation of ASME Code Case N-752-12023-03-15015 March 2023 Fleet Relief Request (Frr) 23-01, Proposed Alternative to ASME Section XI Authorizing Implementation of ASME Code Case N-752-1 L-2023-029, and Point Beach Units 1 and 2 Nuclear Property Insurance - 10 CFR 50.54(w)(3)2023-03-10010 March 2023 and Point Beach Units 1 and 2 Nuclear Property Insurance - 10 CFR 50.54(w)(3) L-2023-023, Revised Steam Generator Tube Inspection Report2023-03-0303 March 2023 Revised Steam Generator Tube Inspection Report ML23020A1002023-03-0303 March 2023 OEDO-22-00419 - 2.206 Petition for Seabrook Station Structure Concrete Concerns (EPID L-2022-CRS-0000)- Closure Letter 2024-01-29
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FPL Energy Seabrook Station FPL Energy Seabrook Station P.O. Box 300 Seabrook, NH 03874 (603) 773-7000 May 23, 2007 Docket No. 50-443 SBK-L-07088 U. S. Nuclear Regulatory Commission Attention:
Document Control Desk Washington, DC 20555-0001 Seabrook Station Steam Generator Jnservice Inspection FPL Energy Seabrook, LLC encloses pursuant to Seabrook Station Technical Specification Surveillance Requirement 4.4.5.5b, a report documenting the results of inservice inspections conducted on the Steam Generators during the eleventh refueling outage that occurred in October 2006.Should you require further information regarding this matter, please contact Mr. Michael Ossing, Manager of Engineering Support, at (603) 773-7512.Very truly yours, FPL Energy Seabrook, LLC Gene St. Pierrese Site Vice President cc: S. J. Collins, NRC Region I Administrator G. E. Miller, NRC Project Manager, Project Directorate 1-2 W. J. Raymond, NRC Senior Resident Inspector 4C) 14 7 an FPL Group company ENCLOSURE TO SBK-L-07088 Steam Generator 12 Month Inservice Inspection Report 1.0 Introduction In October 2006, FPL Energy, Seabrook LLC (Seabrook Station) eleventh refueling outage, Steam Generators (SGs) A, B, C, and D were inspected.
This was accomplished in accordance with Seabrook Station Technical Specification 4.4.5. This report presents the results of the inspection pursuant to Technical Specification 4.4.5.5.b.
and NEI 97-06.Seabrook Station is a Westinghouse four-loop pressurized water reactor with Model F steam generators.
The generators are U-bend heat exchangers, with tube bundles fabricated using thermally treated alloy 600 tubing. A row and column number identifies each tube. There are 59 rows and 122 columns in each steam generator, for a total of 5,626 tubes. Nominal tube OD is 0.688" with a 0.040" nominal wall thickness.
The EPRI Steam Generator Examination Guidelines, Revision 6, defines the required inspection periods and their duration.
For alloy 600TT tubing, the first inspection interval is up to 120 Effective Full Power Months (EFPM); the second inspection interval is 90 EFPM; the third and subsequent inspection intervals are 60 EFPM. OR 1I is the approximate mid-point of the second inspection interval (90 EFPM) at Seabrook Station. The requirement to complete inspection of 50% of the tubes by the mid-point of the inspection interval is met by the inspections performed at ORI 1.2.0 Scope of Inspections Performed The inspection program required by Seabrook Station Technical Specifications and the EPRI Steam Generator Examination Guidelines, Revision 6, addresses the known degradation mechanisms observed in Seabrook in prior inspections as well as those regarded as relevant and potential degradation mechanisms.
The defined scope implemented in all 4 SGs during ORI 1 included the following, the percentages indicating the approximate inspection sample needed to satisfy the mid-period requirements of EPRI Steam Generator Examination Guidelines, Revision 6: 0 100% Bobbin examination of tubes, full length except for Rows 1 and 2, which are inspected with the bobbin from tube end to TSP#7 on both Hot Leg (HL) and Cold Leg (CL).0 30% of the U-bends in each of Rows 1 and 2 with + Point.* 30% HL Top of Tube Sheet (TTS), +/- 3", mid-range
+ Point examination to complete 50% with tubes examined in OR09.* 30% Dings and Dents > 5 Volts: HL dings/dents with the mid-range
+Point probe. The HL includes the U-bend to just above the top TSP on the CL.0 50% sample of the hot leg tubesheet expansion zone bulges (BLG) and overexpansions (OXP) in the region from the TTS to the TTS-17"; mid-range
+Point examination.
Special interest, mid-range
+Point tests at hot leg and cold leg bobbin possible flaw locations (including U-bends), including all "I-code" indications that were new or not resolved after history review.* Visual inspection of mechanical and weld plugs.* +Point inspection to bound the tubes exhibiting possible loose parts (PLP) signals during the inspection.
The NRC granted Seabrook Station a one-time technical specification change that effectively changed the definition of where a steam generator tube starts in the tube sheet. This allowed the inspection program to not consider or inspect the portion of the steam generator tubing below 17 inches from the top of the tubesheet on the hot leg side.Inspection Expansion No expansion of the inspection plan was required.
For Anti-Vibration Bar (AVB) wear, a 100%inspection of the affected tubes was performed in the base bobbin program. No other operational degradation was detected that required expansion of the inspection sample.3.0 Active Degradation Mechanisms The EPRI Steam Generator Examination guidelines Revision 6 define "Active Damage Mechanism" as: (1) A combination of 10 or more new indications of degradation
(> 20% through-wall distance[TWD]) of thinning, pitting, wear (excluding loose part wear), or impingement and previous indications that display an average growth rate > 25% of the repair limit in one inspection-to-inspection interval in any one SG.(2) Alternatively, the existence of 1 or more new or previously identified indications
(>20% through-wall) which display a growth > the repair limit in one inspection-to-inspection interval.(3) Any crack indication (outside diameter intergranular attack/stress corrosion cracking or primary side corrosion cracking).
There are no active degradation mechanisms in any of the Seabrook SGs. However, AVB wear is clearly an ongoing (relevant) degradation mechanism.
Based on the above definitions of an active degradation mechanism, for AVB wear to be an active degradation mechanism, a combination of at least ten or more new indications greater than 20%TWD and/or previously detected indication with growth rates greater than 10% would be required.4.0 NDE Techniques for Damage Mechanisms The NDE (Non Destructive Examination) techniques used met the applicable industry guidance and were qualified, also in accordance with applicable industry guidance, for site specific use.5.0 Pluein2 Twenty-one tubes were plugged during OR 1I at Seabrook.
Table 1 lists the plugged tubes and summarizes what the degradation is attributed to. No tubes were plugged in SG-A. In SG-B, a tube that was identified after restart after OR09 with potentially elevated residual stress was administratively plugged. This tube was inspected prior to plugging and was found free of any degradation.
In SGs C and D, several tubes were plugged for AVB wear that exceeded the 40% TWD Technical Specification plugging limit. Other tubes with significant AVB wear were examined for unusual wear patterns and growth rates; none was judged to have growth rates or wear patterns that indicated administrative plugging was warranted.
In SG-C, two tubes were identified initially with possible loose part (PLP) signals in an area that could not be accessed for removal of the foreign object. These tubes exhibited wear signal suggesting that the foreign object was still present; therefore they were plugged. The 14 un-degraded tubes surrounding the tubes were also plugged to create a conservative boundary for the degraded tubes.In SG-D, a tube was plugged with a volumetric (wear) indication below the 6 th TSP that was sized at 40% TWD using ETSS 29881. The location was bounded by +Point examination; no foreign objects were detected in any of the surrounding tubes.Table 1 Steam Generator Tube Plugging in ORl 1 SG Tube Attribution Notes A none NA NA B R27C97 Administrative Tube with potentially high residual stress R51 C69 AVB Wear 44% TWD at AVB5 C R51C45 AVB Wear 42% TWD at AVB3 R58C54 Foreign Object. Wear DSI,PLP,SVI,PCT 39% @ O1C+0.51 R59C57 Foreign Object. Wear DSI, SVI, PCT 48%R58C55 Administrative PLP Box R59C55 Administrative PLP Box R57C56 Administrative PLP Box R58C56 Administrative PLP Box R59C56 Administrative PLP Box R57C57 Administrative PLP Box R58C57 Administrative PLP Box R57C58 Administrative PLP Box R58C58 Administrative PLP Box R59C58 Administrative PLP Box R57C55 Administrative PLP Box R57C53 Administrative PLP Box R58C53 Administrative PLP Box R57C54 Administrative PLP Box D R52C44 AVB Wear 41% TWD at AVB4 R11C102 Volumetric SVI @ 06C-0.74; 40%TWD Note: SVI PLP DSI PCT TWD AVB Single Volumetric Indication Possible Loose Part Distorted Support Indication Percent Though Wall Distance Anti-Vibration Bar The following table (table 2) shows the total number of tubes plugged by steam generator and the effective percentage plugged in each steam generator as well as total tubes plugged and total effective plugging percentage.
Table 2 Total Tubes Plugged and Plugging Percentage S/G A S/G B S/G C S/G D Total Tubes Plugged 31 24 46 60 161 Percent lugged 0.55% 0.43% 0.81% 1.07% 0.72%6.0 Condition Monitoring Assessment Results.All indications found in OR 1I satisfy the condition monitoring requirements of NEI 97-06 for structural and leakage integrity.
No indications were found to exceed structural limits. These conclusions are based on the evaluations included in this report and summarized below: 1. Based on the OR11 inspection results, the Seabrook Station steam generators currently meet all of the performance criteria as specified in NEI 97-06, Revision 2, "Steam Generator Program Guidelines." 2. No indications of cracking were observed at any location in all four SGs.3. The maximum observed AVB wear indication (44% TWD) meets the structural requirements of draft Reg. Guide 1.121 when the NDE uncertainties 5.3% at 95% CL (based on the use of a 0/20/40 standard) for AVB wear sizing are added to the observed wear depths.4. AVB wear, classified as a relevant (on-going) degradation mechanism in all four SGs in the pre-outage degradation assessment, is not an active degradation mechanism in any of the SGs based on the OR 1I results. The overall incidence of AVB wear in the Seabrook SGs is consistent with the Model F SG operating experience.
- 5. The previously reported wear at the flow distribution baffle (FDB) was reported again during OR11 at Seabrook.
Examination of the prior inspection signals shows that the signals are not changing.
FDB wear is attributed to the application of pressure pulse cleaning of the SGs and is observed in other Model F SGs at the same locations and depths. The magnitude of the wear does not challenge the requirements for condition monitoring.
- 6. Volumetric (wear) indications meet the requirements for Condition Monitoring at 95%probability and 50% confidence.
The maximum observed indication was 40% TWD.7. Wear due to foreign objects meets the performance requirements for Condition Monitoring.
The maximum wear observed due to foreign objects was 48% TWD; the structural limit for the local wear is 75%. The 95/50 evaluation of the observed wear flaw shows that the requirements for condition monitoring are met.8. No pitting was observed.9. No degradation indications were observed related to potential precursor signals such as dents and dings, or to interference such as permeability variations, etc.10. No degradation was observed in the tubesheet expansion zone during the BLG/OXP program from the TTS to -17 inches.