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Category:Inspection Report
MONTHYEARIR 05000266/20230042024-02-0101 February 2024 Integrated Inspection Report 05000266/2023004 and 05000301/2023004 IR 05000266/20234022023-11-14014 November 2023 Security Baseline Inspection Report 05000266/2023402 and 05000301/2023402 IR 05000266/20230032023-10-16016 October 2023 Integrated Inspection Report 05000266/2023003 and 05000301/2023003 IR 05000266/20235012023-08-29029 August 2023 Emergency Preparedness Biennial Exercise Inspection Report 05000266/2023501 and 05000301/2023501 IR 05000266/20230052023-08-24024 August 2023 Updated Inspection Plan for Point Beach Nuclear Plant (Report 05000266/2023005 and 05000301/2023005) IR 05000266/20230022023-07-18018 July 2023 Integrated Inspection Report 05000266/2023002 and 05000301/2023002 IR 05000266/20234012023-07-13013 July 2023 Public-Point Beach Nuclear Plant-Security Baseline Inspection Report 05000266/2023401; 05000301/2023401; Independent Spent Fuel Storage Security Inspection Report 07200005/2023401 IR 05000266/20230012023-05-0101 May 2023 Integrated Inspection Report 05000266/2023001 and 05000301/2023001 IR 05000266/20233012023-03-28028 March 2023 NRC Initial Examination Report 05000266/2023301 and 05000301/2023301 IR 05000266/20220062023-03-0101 March 2023 Annual Assessment Letter for Point Beach Nuclear Plant, Units 1 and 2 (Report 05000266/2022006 and 05000301/2022006) IR 05000266/20230102023-02-23023 February 2023 Comprehensive Engineering Team Inspection Report 05000266/2023010 and 05000301/2023010 ML23009B7002023-01-24024 January 2023 Review of the Spring 2022 Steam Generator Tub Inspections Report IR 05000266/20220042023-01-24024 January 2023 Integrated Inspection Report 05000266/2022004 and 05000301/2022004 IR 05000266/20224012022-12-0808 December 2022 Security Baseline Inspection Report 05000266/2022401 and 05000301/2022401 IR 05000266/20224042022-12-0202 December 2022 Cyber Security Inspection Report 05000266/2022404 and 05000301/2022404 IR 05000266/20220032022-11-0707 November 2022 Integrated Inspection Report 05000266/2022003 and 05000301/2022003 ML22298A2972022-10-27027 October 2022 Review of the Fall 2021 Steam Generator Tube Inspections Report IR 05000266/20220122022-09-29029 September 2022 Biennial Problem Identification and Resolution Inspection Report 05000266/2022012 and 05000301/2022012 IR 05000266/20220052022-08-26026 August 2022 Updated Inspection Plan for Point Beach Nuclear Plant, Units 1 and 2 (Report 05000266/2022005 and 05000301/2022005) IR 05000266/20220112022-08-0303 August 2022 Triennial Fire Protection Inspection Report 05000266/2022011 and 05000301/2022011 IR 05000266/20220022022-07-27027 July 2022 Integrated Inspection Report 05000266/2022002 and 05000301/2022002 IR 05000266/20220012022-05-0404 May 2022 Integrated Inspection Report 05000266/2022001 and 05000301/2022001 IR 05000266/20210062022-03-0202 March 2022 Annual Assessment Letter for Point Point Beach Nuclear Plant, Units 1 and 2 (Report 05000266/2021006 and 05000301/2021006) IR 05000266/20220102022-02-0909 February 2022 Design Basis Assurance Inspection (Programs) Inspection Report 05000266/2022010 and 05000301/2022010 IR 05000266/20210042022-01-28028 January 2022 Integrated Inspection Report 05000266/2021004 and 05000301/2021004 and Exercise of Enforcement Discretion IR 05000266/20214022021-11-10010 November 2021 Security Baseline Inspection Report 05000266/2021402 and 05000301/2021402 IR 05000266/20210032021-10-20020 October 2021 Integrated Inspection Report 05000266/2021003 and 05000301/2021003 IR 05000266/20215012021-10-0505 October 2021 Emergency Preparedness Biennial Exercise Inspection Report 05000266/2021501 and 05000301/2021501 IR 05000266/20213012021-09-14014 September 2021 NRC Initial License Examination Report 05000266/2021301; 05000301/2021301, and 07200005/2021301 IR 05000266/20210052021-09-0101 September 2021 Updated Inspection Plan for Point Beach Nuclear Plant, Units 1 and 2 (Report 05000266/2021005 and 05000301/2021005) IR 05000266/20214032021-08-0404 August 2021 Security Baseline Inspection Report 05000266/2021403 and 05000301/2021403 IR 05000266/20210022021-07-29029 July 2021 Integrated Inspection Report 05000266/2021002, 05000301/2021002, and 07200005/2021001 IR 05000266/20210102021-07-0101 July 2021 Triennial Inspection of Evaluation of Changes, Tests and Experiments Baseline Inspection Report 05000266/2021010 and 05000301/2021010 IR 05000266/20210012021-04-21021 April 2021 Integrated Inspection Report 05000266/2021001 and 05000301/2021001 IR 05000266/20214012021-03-16016 March 2021 Security Baseline Inspection Report 05000266/2021401; 05000301/2021401; Independent Spent Fuel Storage Security Inspection Report 07200005/2021401 IR 05000266/20200062021-03-0404 March 2021 Annual Assessment Letter for Point Beach Nuclear Plant, Units 1 and 2 (Report 05000266/2020006 and 05000301/2020006) IR 05000266/20200902021-02-0909 February 2021 Final Significance Determination of a Green Finding; NRC Inspection Report 05000266/2020090 and 05000301/2020090 IR 05000266/20200042021-02-0808 February 2021 Integrated Inspection Report 05000266/2020004 and 05000301/2020004 IR 05000266/20204022020-12-14014 December 2020 Security Baseline Inspection Report 05000266/2020402 and 05000301/2020402 IR 05000266/20200032020-11-0404 November 2020 Integrated Inspection Report 05000266/2020003 and 05000301/2020003 IR 05000266/20200102020-09-24024 September 2020 Biennial Problem Identification and Resolution Inspection Report 05000266/2020010 and 05000301/2020010 IR 05000266/20200052020-09-0101 September 2020 Updated Inspection Plan for Point Beach Nuclear Plant, Units 1 and 2 (Report 05000266/2020005 and 05000301/2020005) IR 05000266/20200022020-08-0606 August 2020 Integrated Inspection Report 05000266/2020002 and 05000301/2020002 IR 05000266/20200122020-08-0303 August 2020 NRC Inspection Report 05000266/2020012 and 05000301/2020012; Preliminary White Finding and Apparent Violations IR 05000266/20200112020-07-29029 July 2020 Design Basis Assurance Inspection (Teams) Inspection Report 05000266/2020011 and 05000301/2020011 IR 05000266/20200012020-05-13013 May 2020 Integrated Inspection Report 05000266/2020001 and 05000301/2020001 ML20100G8902020-04-0707 April 2020 Request for Information for an NRC Triennial Baseline Design Bases Assurance Inspection (Team): Inspection Report 05000266/2020-011 and 05000301/2020-011 IR 05000266/20204012020-03-30030 March 2020 Security Baseline Inspection Report 05000266/2020401 and 05000301/2020401 IR 05000266/20190062020-03-0303 March 2020 Annual Assessment Letter for Point Beach Nuclear Plants, Units 1 and 2 (Report 05000266/2019006 and 05000301/2019006) IR 05000266/20190042020-02-0505 February 2020 Integrated Inspection Report 05000266/2019004 and 05000301/2019004 2024-02-01
[Table view] Category:Letter
MONTHYEARML24036A2652024-02-0505 February 2024 Notice of Inspection and Request for Information for the NRC Age-Related Degradation Inspection: Inspection Report 05000266/2024010 and 05000301/2024010 IR 05000266/20230042024-02-0101 February 2024 Integrated Inspection Report 05000266/2023004 and 05000301/2023004 ML24030A0352024-01-30030 January 2024 Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection L-2024-001, Relief Request CISl-03-01 for Relief Concerning Containment Unbonded Post-Tensioning System Inservice Inspection Requirements2024-01-26026 January 2024 Relief Request CISl-03-01 for Relief Concerning Containment Unbonded Post-Tensioning System Inservice Inspection Requirements 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) ML24005A3242024-01-24024 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0040 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) ML23352A2752024-01-23023 January 2024 Issuance of Amendment Nos. 274 and 276 Regarding Revision to Technical Specification 5.5.17, Pre-Stressed Concrete Containment Tendon Surveillance Program 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-2023-174, Subsequent License Renewal Application - Third Annual Update2023-12-13013 December 2023 Subsequent License Renewal Application - Third Annual Update L-2023-176, Supplement to Exemption Request Regarding Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Final Rule2023-11-29029 November 2023 Supplement to 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-2023-159, Part 3 Exemption Request Regarding Enhanced Weapons, Firearms Background Checks and Security Event Notifications Final Rule2023-11-16016 November 2023 Part 3 Exemption Request Regarding Enhanced Weapons, Firearms Background Checks and Security Event Notifications Final Rule IR 05000266/20234022023-11-14014 November 2023 Security Baseline Inspection Report 05000266/2023402 and 05000301/2023402 ML23279A0672023-11-0909 November 2023 Issuance of Relief Request I6 RR 02 - Examination of the Unit 2 Steam Generator Feedwater Nozzle Extension to Nozzle Weld Sixth 10 Year Inservice Inspection Program Interval IR 05000266/20230032023-10-16016 October 2023 Integrated Inspection Report 05000266/2023003 and 05000301/2023003 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 L-2023-128, License Amendment Request to Revise TS 5.5.17, Pre-Stressed Concrete Containment Tendon Surveillance Program2023-09-19019 September 2023 License Amendment Request to Revise TS 5.5.17, Pre-Stressed Concrete Containment Tendon Surveillance Program ML23243A9102023-09-0606 September 2023 Closeout of Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors IR 05000266/20235012023-08-29029 August 2023 Emergency Preparedness Biennial Exercise Inspection Report 05000266/2023501 and 05000301/2023501 ML23208A2262023-08-28028 August 2023 Exemption from the Requirements of 10 CFR 50,46, Acceptance Criteria for Emergency Core Cooling Systems for Light Water Nuclear Power Reactors (EPID L-2022-LLE-0026) - Letter ML23208A0952023-08-28028 August 2023 Issuance of Amendment Nos. 273 and 275 Regarding Revising Licensing Basis to Address Generic Safety Issue-191 and Respond to Generic Letter 2004-02 Using a Risk Informed Approach IR 05000266/20230052023-08-24024 August 2023 Updated Inspection Plan for Point Beach Nuclear Plant (Report 05000266/2023005 and 05000301/2023005) ML23160A0642023-08-21021 August 2023 Issuance of Amendment Nos. 272 and 274 Regarding Revision to Use Beacon Power Distribution Monitoring System 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 ML23221A0522023-08-0909 August 2023 Confirmation of Initial License Examination, March 2024 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-2023-089, Refueling Outage Owner'S Activity Report (OAR-1) Unit 2 for Inservice Inspections2023-07-24024 July 2023 Refueling Outage Owner'S Activity Report (OAR-1) Unit 2 for Inservice Inspections IR 05000266/20230022023-07-18018 July 2023 Integrated Inspection Report 05000266/2023002 and 05000301/2023002 IR 05000266/20234012023-07-13013 July 2023 Public-Point Beach Nuclear Plant-Security Baseline Inspection Report 05000266/2023401; 05000301/2023401; Independent Spent Fuel Storage Security Inspection Report 07200005/2023401 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) ML23178A2422023-06-28028 June 2023 Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch III L-2023-088, 10 CFR 50.55a Requests, Relief Requests I6-RR-1, I6-RR-2, and I6-RR-3 Sixth Ten-Year Inservice Inspection Program Interval2023-06-27027 June 2023 10 CFR 50.55a Requests, Relief Requests I6-RR-1, I6-RR-2, and I6-RR-3 Sixth Ten-Year Inservice Inspection Program Interval ML23171B1062023-06-21021 June 2023 Info Meeting with a Question and Answer Session to Discuss NRC 2022 EOC Plant Performance Assessment of Ptbh, Units 1 and 2 ML23163A2422023-06-13013 June 2023 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000266/2023004 L-2023-075, Response to Request for Additional Information (RAI) Regarding Exemption Request, License Amendment Request and Revised Response in Support of a Risk-Informed Resolution of Generic Letter 2004-022023-06-0909 June 2023 Response to Request for Additional Information (RAI) Regarding Exemption Request, License Amendment Request and Revised Response in Support of a Risk-Informed Resolution of Generic Letter 2004-02 L-2023-073, Subsequent License Renewal Application, Second Annual Update Request for Additional Information Set 1 Response2023-06-0101 June 2023 Subsequent License Renewal Application, Second Annual Update Request for Additional Information Set 1 Response ML23103A1332023-06-0101 June 2023 Issuance of Amendment Nos. 271 and 273 Regarding Technical Specifications to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b 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 ML23118A1762023-05-0404 May 2023 Audit Summary for License Amendment Request Regarding Risk-Informed Approach for Closure of Generic Safety Issue 191 IR 05000266/20230012023-05-0101 May 2023 Integrated Inspection Report 05000266/2023001 and 05000301/2023001 ML23114A1222023-04-25025 April 2023 Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection L-2023-058, 2022 Annual Monitoring Report2023-04-10010 April 2023 2022 Annual Monitoring 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 2024-02-05
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t i- Committed to Nuclear Excellenc Point Beach Nuclear Plant Operated by Nuclear Management Company, LLC February 21, 2006 NRC 2006-0027 10 CFR 50.36 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington DC 20555 Point Beach Nuclear Plant Unit 1 Docket No. 50-266 License No. DPR-24 Fall 2005 Unit 1 (U1 R29) Stream Generator Tube Inspection Report In accordance with the requirements of Point Beach Nuclear Plant Technical Specification 5.6.8, "Steam Generator Tube Inspection Report," Nuclear Management Company, LLC (NMC), is submitting the results of the fall 2005 Unit 1 (U1 R29) steam generator tube inservice inspections.
The enclosed report includes the following:
- 1. Number and extent of tubes inspected.
- 2. Location and percent of all thickness penetration for each indication.
- 3. Identification of tubes plugged or repaired.This letter contains no new commitments and no revisions to existing commitments.
Dennis L. Koehl Site Vice-President, Point Beach Nuclear Plant Nuclear Management Company, LLC Enclosure cc: Administrator, Region Ill, USNRC Project Manager, Point Beach Nuclear Plant, USNRC Resident Inspector, Point Beach Nuclear Plant, USNRC PSCW 6590 Nuclear Road
920.755.2321 AcD(47 ENCLOSURE FALL 2005 UNIT 1 (U1R29) STEAM GENERATOR TUBE INSPECTION REPORT The Point Beach Nuclear Plant (PBNP) steam generator tube inspection program for Ul R29 was conducted in accordance with the requirements of PBNP Technical Specifications 5.5.8 and 5.6.8, NEI 97-06, "Steam Generator Program Guidelines," and EPRI 1003138, "PWR Steam Generator Examination Guidelines." The 29th refueling outage was completed on November 24, 2005. Past inspections of these steam generators have resulted in classification of Category C-1; therefore, this inspection was not required by PBNP Technical Specifications, NEI, or EPRI guidelines.
However, because of secondary side steam generator fouling, NMC performed an additional inspection of the Unit 1 'A' steam generator.
The PBNP Unit I steam generators are Westinghouse Model 44F with thermally treated, 7/8-inch outer diameter, 0.050 inch wall, Inconel 600 tubing manufactured by Westinghouse.
The tubes are on a 1.234" square pitch and were hydraulically expanded the full depth of the tubesheet.
The row 1 U-bends have a 2.19" radius, and the first 8 rows were stress relieved after bending. The tubes are supported by a stainless steel flow distribution baffle with round holes, six stainless steel tube support plates with quatrefoil holes and two sets of chrome-plated Inconel anti-vibration bar assemblies.
The PBNP Unit 1 steam generators were replaced late in 1983, during refueling outage 11. The replacement steam generators have accumulated approximately 17.7 effective full power years of operation since then.The U1 R29 steam generator inspection wvas limited to the 'A' steam generator and consisted of the following.
- Bobbin coil inspection of 50% (1607 tubes) of the active tubes over the full length of the tube. This included all tubes with previous anti-vibration bar wear and signature tubes. Signature tubes have potential elevated susceptibility to tube support plate Outside Diameter Stress Corrosion Cracking based on evaluation of past inspection data. The 'A' steam generator has 45 signature tubes.* Rotating pancake coil inspection of 20% (19 tubes) of the row 1 U-bends.* Rotating pancake coil inspection of 20% (644 tubes) of the tubesheel:
full length hot leg tubes to 3" above the tubesheet.
- Rotating pancake coil inspection of 146 special interest tests, including all freespan dings/dents over 5 volts and dings/dents over 2 volts at supports.As a result of this inspection, no steam generator tube degradation that required plugging was detected, and no tubes were plugged. The plugging limit at P13NP is 40% through-wall as specified in PBNP Technical Specification 5.5.8.a.6.
Tubes are Page 1 of 7 I also plugged upon any indication of circumferential or axial cracking.
Minor tube wear at the anti-vibration bars, at the hot leg top of tubesheet and at the cold leg supports continues to be monitored.
Fifty-two wear indications in 31 tubes were found in the 'A' SG anti-vibration bar area.None of these indications were required to be repaired, and all tubes remained in service. Table 1 shows all anti-vibration bar wear indications along with an historical comparison.
Based on the growth rate of the wear indications, no indications are expected to exceed the plugging criterion during the next two cycles.Table I -Anti-Vibration Bar Wear History, % Through-Wall, SG A Row Column Location 2005 2004 2001 1998 1995 22 8 AV3 3% ----32 14 AV3 7% 5% 3% 9% 4%33 18 AV3 18% 25% 21% --33 18 AV4 11% 16% 13% -35 18 AV2 11% 10% 6% INR 9%38 22 AV3 10% 12% 6% 10% 8%40 25 AV2 9% 6% 5% 9% 6%40 27 AV3 8% 5% 4% 6% 5%34 33 AV1 14% 10% 10% 5% 11%34 33 AV2 11% 7% 7% 7% 10%33 37 AV4 14% 9% 13% 7% 8%45 41 AV1 10% 6% 6% 7% 6%45 41 AV4 8% 7% 6% 7% 6%40 42 AV1 14% 12% 13% -23%45 42 AVI 14% ----38 43 AV1 24% 23% 19% 12% 11%38 43 AV2-1 17% 16% ---38 43 AV2+1 22% 23% 19% 12% 8%45 43 AV1 18% 13% 12% 15% 11%45 43 AV4 9% 8% 8% --40 44 AV3 11% 13% 10% 7% 5%40 47 AV3 15% 10% 13% 10% 12%33 48 AV3 9% 13% 9% --45 49 AV1 15% 19% 14% 13% 18%45 52 AV4 5% ---19 54 AV1 8% ----19 54 AV2 17% 12% 14% 13% 7%19 54 AV4 17% 12% 16% 12% 13%38 54 AV3 26% 25% 18% 14% 15%38 54 AV4 9% ---35 56 AVI 18% 14% 15% 5% 6%35 56 AV2 27% 27% 27% 9% 13%Page 2 of 7 Row Column Location 2005 2004 2001 1998 1995 19 61 AVI 13% 12% 18% 10% 12%19 61 AV2 16% 15% 23% 13% 14%19 61 AV4 5% 6% 8% --31 63 AV2 18% 20% 14% 9% 12%31 63 AV3 11% 10% 5% 5% 2%34 65 AV3 5% 9% 6% 1% -34 65 AV4 11% 15% 12% 6% 7%33 66 AV1 14% 20% 14% 9% 8%33 66 AV2 10% 13% 11% 9% 4%33 66 AV3 4% 5% 5% 4% 4%39 68 AV4 9% 9% 8% 9% 6%34 69 AV1 8% 3% 7% 1%34 69 AV2 16% 11% 14% 6% 9%27 71 AV2 10% 6% 11% 5% 4%27 71 AV3 15% 10% 12% 3% 2%27 71 AV4 7% 5% 6% -32 71 AV2 15% 11% 9% 10% 6%32 71 AV3 11% ----33 71 AV2 16% 13% 17% 5% 6%33 71 AV3 14% 6% 10% --Nineteen wear indications in 16 tubes were found in the 'A' SG peripheral hot leg tubes at the top of tubesheet.
Table 2 lists the percent through-wall of these indications.
All of these indications were reported in 2004, except a 1 % indication in row 33/column 78 and a 5% in row 41/column
- 28. Both of these minor indications were present in 2004 data but not reported by eddy current. These indications first appear in the UI R28 inspection data, and this wear was concluded to be the result of damage from maintenance equipment during Ul R26. Secondary side visual inspection during Ul R28 and the current inspection confirmed that no objects that could cause continued wear are present. Comparison of the 2004 and 2005 data supports this original conclusion.
The depth of these indications is significantly below the plugging criterion, and since the source of the wear is no longer present, no growth is anticipated, and all tubes remained in service.Page 3 of 7 Table 2 -Mechanical Wear History, % Through-Wall, SG A Row Column Location 2005 004 37 20 TSH +0.61" 4% 4%37 20 TSH +0.70" 1% 1%41 28 TSH +0.54" 5% -42 30 TSH +0.57" 5% 5%43 33 TSH +0.60" 3% 5%44 36 TSH +0.66" 4% 6%45 41 TSH +0.64" 3% 4%45 42 TSH +0.66" 1% 3%45 43 TSH +0.63" 2% 1%45 44 TSH +0.64" 3% 4%45 45 TSH +0.59" 4% 100%45 46 TSH +0.57" 2% 7%45 47 TSH +0.56" 2% 5%43 60 TSH +0.53" 7% 7%42 63 TSH +1.55" 1% 1%42 63 TSH +2.67" 1% 1%42 63 TSH +0.57" 11% 11%33 78 TSH +0.75" 1% -31 80 TSH +0.73" 4% 3%Four wear indications in 4 tubes were found in the 'A' SG at cold leg supports.
Three of these were reported in 2004, but had never been reported previous to 2004. When compared to 1995 inspection data, these indications showed no significant change.Table 3 lists the percent through-wall of these indications.
The depth of these indications is significantly below the plugging criterion, and all tubes remained in service.Table 3 -Cold Leg Support Wear, % Through-Wall, SG A Row Column Location 2005 2004 39 24 03C +0.38" 11% 12%41 65 02C +0.41" 16% 18%39 67 02C +0.38" 7% -21 85 02C +0.38" 12% 10%During this inspection of the 'A' steam generator, 3 dents were identified at :2.0 to 4.99 volts and 131 dings identified at 2.0 to 4.99 volts. Two of the dents were at supports, and 54 of the dings were located at supports or anti-vibration bars. An additional 53 dings were identified at 5 volts or greater. These indications were further investigated with rotating pancake coil, and the results were "no defect found." Page 4 of 7 The 'A' steam generator has one manufacturing anomaly. The tube at row 38/column 69 is not expanded the full length of the tubesheet.
This tube is routinely inspected by rotating pancake coil from the tube end to the top of tubesheel:
and during Ul R29, as in the past, no degradation was found. The tube remains in service.One possible loose part indication was reported by eddy current in SG 'A' at 0.36 inch above the hot leg top of tubesheet in row 8/column 25. No degradation was observed in conjunction with the indication.
However, all tubes adjacent to this indication were also tested with rotating pancake coil. Secondary side visual inspection verified that no loose part was present, and this indication was subsequently dispositioned, and the tube remains in service.A small foreign object was found and retrieved during the secondary side visual inspection near cold leg row 1 &2/column
- 78. The object was a small steel pin approximately 1-1/4" long by approximately 1/4" diameter.
Subsequently, 18 tubes in the vicinity of this location were inspected with rotating pancake coil. No degradation was observed in conjunction with the loose part in any of the tubes. The site investigated possible sources of the part and concluded that the object was not transported to the steam generator, but may have been from steam generator maintenance equipment.
The secondary side of the 'A' steam generator was cleaned and inspected.
Sludge lance equipment fit up properly, validating that the wrapper plate has not shifted.Therefore, wrapper plate inspection was not performed as discussed in our response to NRC Generic Letter 97-06. Sludge lancing removed 31 pounds of sludge from the top of the tubesheet.
The post sludge lancing visual inspection of the tubesheet confirmed that some hard adhering scale was not being washed off the tubesheet, acnd future chemical cleaning of the secondary side is planned. Inspection of the upper support plate revealed no degradation, nor was support plate degradation anticipated given that the plates are stainless steel. However, the inspection did confirm the presence of heavy scale on the outside of the tubes. The 'A' steam generator steam drum was also inspected and no significant degradation of the swirl vanes, moisture separators or feed ring J nozzles were found. Note that samples of these areas are visual inspected, and it is not practical to inspect 100% of all these areas. Minor weld burn through from construction was noted in two closely spaced J nozzles. The condition was evaluated and determined not to affect nozzle function.
No flow induced corrosion was found.The 'B' steam generator was not cleaned or inspected during the Ul R29 outage.Since the Unit 1 steam generators were replaced, tube wear has been minimal. There are presently a total of 10 tubes plugged in the Unit 1 steam generators
-four tubes in the 'A' steam generator and six tubes in the 'B' steam generator.
No tubes have been plugged for stress corrosion cracking and only four of these ten tubes were plugged as a result of service-induced wear -one tube in the 'A' steam generator and three in the'B' steam generator.
There are three tubes in the 'A' steam generator and cne tube in the 'B' steam generator that were plugged prior to placing the steam generators in Page 5 of 7 service, plus an additional two tubes in 'B3' steam generator were plugged because of damage during steam generator wrapper modification.
Tubes Plugged in Steann Generator A Row Column Date Plugged 1 5 During Manufacture (Welded in plugs)3 90 During Manufacture (Welded in plugs)20 87 During Manufacture (Welded in plugs)21 63 April 1991(690TT plugs)Tubes Plugged in Steam Generator B Row Column Date Plugged 1 1 April 1988/ Replaced with 690TT plugs in April 2001 2 1 April 1988 / Replaced with 690TT plugs in April 2001 30 60 April 1991 (6901T plugs)32 38 April 2001 (690TT plugs)35 51 April 1995 (690TT plugs)43 40 March 1984 / Replaced with 690TT plugs in April 2001 A steam generator tubesheet map is depicted on the next page to aid in the understanding of tube locations.
In summary, based on the inspection results, no tubes needed to be repaired.
The tube integrity and leakage criterion specified in NEI 97-06 are expected to be satisfied for the next cycle of operation.
In accordance with Point Beach Technical Specifications and EPRI Steam Generator Examination Guidelines, the next scheduled inspection of Unit 1 steam generators is planned for refueling outage 30 during the spring of 2007.Abbreviations AVx Various Anti-Vibration bar locations, numbered from hot leg to cold leg.If Anti-Vibration location is superscripted, there are multiple indications at the location.TSH Top of Tubesheet Hot Leg 02C 2nd support plate cold leg side 03C 3rd support plate cold leg side Indication Not Reportable Condition where a previously reported indication is detectable INR but does not meet the current reporting level.Page 6 of 7 Lo, mfl cost~g INLET NOZZLE NOZZLE SIDE MANWAY SIDE