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Category:INSPECTION REPORT
MONTHYEARIR 05000327/20240042025-01-28028 January 2025 Integrated Inspection Report 05000327/2024004 and 05000328/2024004 IR 05000327/20240902025-01-27027 January 2025 Final ASP Analysis Sequoyah 1 and 2, Failure of EDG 1B During Testing IR 05000327 2024 090 Precursor IR 05000327/20240102024-12-19019 December 2024 Design Basis Assurance Inspection (Programs) Inspection Report 05000327/2024010 and 05000328/2024010 IR 05000327/20240032024-11-0606 November 2024 Integrated Inspection Report 05000327/2024003 and 05000328/2024003 IR 05000327/20250102024-10-29029 October 2024 Notification of Sequoyah, Units 1 and 2 - Comprehensive Engineering Team Inspection - U.S. Nuclear Regulatory Commission Inspection Report 05000327/2025010 and 05000328/2025010 IR 05000327/20240052024-08-26026 August 2024 Updated Inspection Plan for Sequoyah Nuclear Plant, Units 1 and 2 - Report 05000327/2024005 and 05000328/2024005 IR 05000327/20240022024-07-31031 July 2024 Integrated Inspection Report 05000327/2024002 and 05000328/2024002 ML24145A0852024-05-30030 May 2024 1B-B Diesel Generator Failure - Final Significance Determination Letter IR 05000327/20240012024-04-17017 April 2024 Integrated Inspection Report 05000327/2024001 and 05000328/2024001 ML24066A1972024-03-19019 March 2024 NRC Inspection Report 05000327-2024090 and 05000328-2024090 and Preliminary Greater than Green Finding and Apparent Violation IR 05000327/20244012024-03-12012 March 2024 – Security Baseline Inspection Report 05000327/2024401 and 05000328/2024401 IR 05000259/20230062024-02-28028 February 2024 Annual Assessment Letter for Sequoyah Nuclear Plant, Units 1, 2 - Report 05000259/2023006, 05000260/2023006 and 05000296/2023006 IR 05000327/20230042024-02-12012 February 2024 Integrated Inspection Report 05000327/2023004 and 05000328/2023004 and Apparent Violation IR 05000327/20234422024-01-11011 January 2024 95001 Supplemental Inspection Report 05000327/2023442 and 05000328/2023442 and Follow-Up Assessment Letter IR 05000327/20234202023-11-28028 November 2023 Security Baseline Inspection Report 05000327/2023420 and 05000328/2023420 IR 05000327/20230032023-11-0303 November 2023 – Integrated Inspection Report 05000327/2023003 and 05000328/2023003 IR 05000327/20230112023-10-16016 October 2023 Triennial Fire Protection Inspection Report 05000327/2023011 and 05000328/2023011 IR 05000327/20234032023-09-14014 September 2023 Cyber Security Inspection Report 05000327/2023403 and 05000328/2023403 (Cover Letter) IR 05000327/20230052023-08-29029 August 2023 Updated Inspection Plan for Sequoyah Nuclear Plant, Units 1 and 2 - Report 05000327/2023005 and 05000328/2023005 IR 05000327/20230022023-07-31031 July 2023 Integrated Inspection Report 05000327/2023002 and 05000328/2023002 IR 05000327/20230102023-07-20020 July 2023 – Biennial Problem Identification and Resolution Inspection Report 05000327/2023010 and 05000328/2023010 ML23163A0392023-06-13013 June 2023 – Notification of an NRC Fire Protection Team Inspection (FPTI) (NRC Inspection Report 05000327/2023011, 05000328/2023011) and Request for Information (RFI) IR 05000327/20233012023-05-15015 May 2023 – NRC Operator License Examination Report 05000327/2023301 and 05000328/2023301 IR 05000327/20230012023-05-0202 May 2023 Integrated Inspection Report 05000327/2023001 and 05000328/2023001 and Exercise of Enforcement Discretion IR 05000327/20234412023-04-20020 April 2023 Final Significance Determination for a Security-Related Greater than Green Finding, Nov & Assessment Followup Letter, 05000327/2023441 & 05000328/2023441 IR 05000327/20234022023-04-13013 April 2023 Security Baseline Inspection Report 05000327/2023402 and 05000328/2023402 IR 05000327/20220062023-03-0101 March 2023 Annual Assessment Letter for Sequoyah Nuclear Plant, Units 1 and 2 Report 05000327/2022006 and 05000328/2022006 IR 05000327/20234402023-02-13013 February 2023 – NRC Inspection Report 05000327/2023440 and 05000328/2023440; Preliminary Greater than Green and Apparent Violation Cover Letter IR 05000327/20220042023-02-10010 February 2023 Integrated Inspection Report 05000327/2022004 and 05000328/2022004 IR 05000327/20234012023-02-0606 February 2023 – Security Baseline Inspection Report 05000327/2023401 and 05000328/2023401 IR 05000327/20224402023-01-17017 January 2023 – Special Inspection Report 05000327/2022440 and 05000328/2022440 and Apparent Violation - Cover IR 05000327/20220032022-11-0707 November 2022 – Integrated Inspection Report 05000327/2022003 and 05000328/2022003 IR 05000327/20224012022-10-18018 October 2022 Material Control and Accounting Program Inspection Report 05000327/2022401 and 05000328/2022401 IR 05000327/20220052022-08-30030 August 2022 Updated Inspection Plan for Sequoyah Nuclear Plant, Units 1 and 2 - Report 05000327 2022005 and 05000328 2022005 - Final IR 05000327/20220022022-08-0101 August 2022 Integrated Inspection Report 05000327 2022002 and 05000328 2022002 IR 05000327/20223012022-07-21021 July 2022 Operator License Examination Report 05000327/2022301 and 05000328/2022301 IR 05000327/20220012022-05-11011 May 2022 Integrated Inspection Report 05000327/2022001, 05000328/2022001 and 07200034/2010002 IR 05000327/20220102022-04-25025 April 2022 Design Basis Assurance Inspection (Teams) Inspection Report 05000327/2022010 and 05000328/2022010 IR 05000327/20224022022-03-28028 March 2022 Security Baseline Inspection Report 05000327/2022402 and 05000328/2022402 IR 05000327/20210062022-03-0202 March 2022 Annual Assessment Letter for Sequoyah Nuclear Plant, Units 1 and 2 - (Report No. 05000327/2021006 and 05000328/2021006) IR 05000327/20210042022-02-0707 February 2022 Integrated Inspection Report 05000327/2021004 and 05000328/2021004 IR 05000327/20210032021-11-10010 November 2021 Integrated Inspection Report 05000327/2021003 and 05000328/2021003 and Apparent Violation and Exercise of Enforcement Discretion IR 05000327/20210052021-08-18018 August 2021 Updated Inspection Plan for Sequoyah Nuclear Plant, Units 1 and 2 Report 05000327/2021005 and 05000328/2021005 IR 05000327/20210022021-07-27027 July 2021 Integrated Inspection Report 05000327/2021002 and 05000328/2021002 IR 05000327/20210112021-07-19019 July 2021 Biennial Problem Identification and Resolution Inspection Report 05000327/2021011 and 05000328/2021011 IR 05000327/20210012021-04-27027 April 2021 Integrated Inspection Report 05000327/2021001 and 05000328/2021001 IR 05000327/20210102021-04-21021 April 2021 NRC Inspection Report 05000327/2021010 and 05000328/2021010 IR 05000327/20214012021-04-21021 April 2021 NRC Inspection Report 05000327/2021401 and 05000328/2021401 (U) IR 05000327/20200062021-03-0303 March 2021 Annual Assessment Letter for Sequoyah Nuclear Plant, Units 1 and 2 - Report 05000327/2020006 and 05000328/2020006 IR 05000327/20200042021-01-29029 January 2021 Integrated Inspection Report 05000327/2020004 and 05000328/2020004 2025-01-28
[Table view] Category:NRC-GENERATED
MONTHYEARIR 05000327/19990051999-09-27027 September 1999 Insp Repts 50-327/99-05 & 50-328/99-05 on 990718-0828. Violations Noted.Major Areas Inspected:Mitigating Sys IR 05000327/19990041999-08-13013 August 1999 Insp Repts 50-327/99-04 & 50-328/99-04 on 990601-0717.One Potentially Safety Significant Issue Noted.Major Areas Inspected:Licensee Emergency Preparedness IR 05000327/19990031999-06-30030 June 1999 Insp Repts 50-327/99-03 & 50-328/99-03 on 990328-0531.Non- Cited Violations Noted.Major Areas Inspected:Aspects of Licensee Operations,Maint & Engineering IR 05000327/19990021999-04-23023 April 1999 Insp Repts 50-327/99-02 & 50-328/99-02 on 990214-0327.No Violations Noted.Major Areas Inspected:Licensee Operations, Maint & Engineering IR 05000327/19990011999-03-15015 March 1999 Insp Repts 50-327/99-01 & 50-328/99-01 on 990103-0213. Violations Noted & Being Treated as non-cited Violations. Major Areas Inspected:Aspects of Licensee Operations,Maint & Engineering IR 05000327/19980111999-02-0101 February 1999 Insp Repts 50-327/98-11 & 50-328/98-11 on 981122-990102. Violations Noted.Major Areas Inspected:Licensee Operations, Maint & Engineering IR 05000327/19980101998-12-0707 December 1998 Insp Repts 50-327/98-10 & 50-328/98-10 on 981011-1121.No Violations Noted.Major Areas Inspected:Operations,Maint & Engineering IR 05000327/19980141998-12-0404 December 1998 Insp Repts 50-327/98-14 & 50-328/98-14 on 981102-06.No Violations Noted.Major Areas Inspected:Observation & Evaluation of Biennial Emergency Preparedness Exercise for Sequoyah Nuclear Plan IR 05000327/19980131998-11-24024 November 1998 Insp Repts 50-327/98-13 & 50-328/98-13 on 980914-1016. Violations Noted.Major Areas Inspected:Aspects of Licensee maint,testing,engineering,self-assessment & Problem Evaluations of Licensee Ice Condenser Sys IR 05000327/19980091998-11-0909 November 1998 Insp Repts 50-327/98-09 & 50-328/98-09 on 980830-1010. Violations Noted.Major Areas Inspected:Licensee Operations, Maint,Engineering Plant Support & Effectiveness of Licensee Controls in Identifying,Resolving & Preventing Problems IR 05000327/19980081998-09-18018 September 1998 Insp Repts 50-327/98-08 & 50-328/98-08 on 980719-0829.No Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support,Licensee Conducted Radiological Emergency Plan Drill IR 05000327/19980071998-08-0404 August 1998 Insp Repts 50-327/98-07 & 50-328/98-07 on 980607-0718. Violations Noted.Major Areas Inspected:Aspects of Licensee Operation,Maint,Engineering,Plant Support & Effectiveness of Licensee Controls in Identifying & Preventing Problems IR 05000327/19980061998-06-26026 June 1998 Insp Repts 50-327/98-06 & 50-328/98-06 on 980426-0606. Violations Noted.Major Areas Inspected:Operations, Maintenance,Engineering & Plant Support IR 05000327/19980051998-06-12012 June 1998 Insp Repts 50-327/98-05 & 50-328/98-05 on 980504-08.No Violations Noted.Major Areas Inspected:Maint Procedure.Insp Team Comprised Region II & Headquarters Personnel.Switchgear & Surrounding Areas Found in Good Matl Condition IR 05000327/19980031998-04-10010 April 1998 Insp Repts 50-327/98-03 & 50-328/98-03 on 980201-0314. Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support IR 05000327/19980011998-03-30030 March 1998 Insp Repts 50-327/98-01 & 50-328/98-01 on 980126-0213.No Violations Noted.Major Areas Inspected:Operations,Maint & Engineering IR 05000327/19980021998-03-0505 March 1998 Insp Repts 50-327/98-02 & 50-328/98-02 on 980202-06.No Violations Noted.Major Areas Inspected:Aspects of Licensee Operations & Maint.Review of Initial & Requalification Training Programs Were Also Conducted IR 05000327/19970181998-02-19019 February 1998 Insp Repts 50-327/97-18 & 50-328/97-18 on 971221-980131. Violations Noted.Major Areas Inspected:Licensee Operations, Maint,Engineering,Plant Support & Effectiveness of Licensee Controls in Identifying & Resolving Problems IR 05000327/19970171998-01-16016 January 1998 Insp Repts 50-327/97-17 & 50-328/97-17 on 971109-1220.No Violations Noted.Major Areas Inspected:Operations,Maint, Engineering,Plant Support & Effectiveness of Licensee Controls in Identifying,Resolving & Preventing Problems IR 05000327/19970141997-12-0808 December 1997 Insp Repts 50-327/97-14 & 50-328/97-14 on 970928-1108.No Violations Noted.Major Areas Inspected:Operations,Maint, Engineering,Plant Support,Effectiveness of License Controls in Identifying,Resolving & Preventing Problems IR 05000327/19970161997-12-0505 December 1997 Insp Repts 50-327/97-16 & 50-328/97-16 on 971103-06.No Violations Noted.Major Areas Inspected:Evaluation of 971017 Wire Damage Event at Electrical Penetration 22 IR 05000327/19970121997-10-24024 October 1997 Insp Repts 50-327/97-12 & 50-328/97-12 on 970824-0927.No Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support & Operator Requalification Program IR 05000327/19970151997-10-23023 October 1997 Insp Repts 50-327/97-15 & 50-328/97-15 on 970922-29.No Violations Noted.Major Areas Inspected:Emergency Preparedness ML20198H7911997-09-11011 September 1997 Insp Repts 50-327/97-13 & 50-328/97-13 on 970725-0904. Violations Noted.Major Areas Inspected:Insp Scope,Event Synopsis & Observations & Findings IR 05000327/19970061997-07-28028 July 1997 Insp Repts 50-327/97-06 & 50-328/97-06 on 970525-0705. Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support IR 05000327/19970071997-07-24024 July 1997 Insp Repts 50-327/97-07 & 50-328/97-07 on 970623-27. Violations Noted.Major Areas Inspected:Aspects of Licensee Plant Support ML20141G0441997-06-20020 June 1997 Insp Repts 50-327/97-04 & 50-328/97-04 on 970413-0524. Violations Noted.Major Areas Inspected:Operations Re Physics Testing,Maint,Engineering & Plant Support ML20148F9631997-05-27027 May 1997 Special Insp Repts 50-327/97-05 & 50-328/97-05 on 970324-0522.Violations Noted.Major Areas Inspected:Events Associated W/Unit 1 Inadvertent RCS Drain Down on 970324 ML20141C9881997-05-12012 May 1997 Insp Repts 50-327/97-03 & 50-328/97-03 on 970302-0412. Violations Noted.Major Areas Inspected:Operations, Maintenance,Engineering & Plant Support IR 05000327/19970021997-03-24024 March 1997 Insp Repts 50-327/97-02 & 50-328/97-02 on 970203-14.No Violations Noted.Major Areas Inspected:Detailed Reviews of Corrective Actions 14-1,14-2,14-3,15 & 16 ML20137F7081997-03-18018 March 1997 Insp Repts 50-327/97-01 & 50-328/97-01 on 970119-0301. Violations Noted.Major Areas Inspected:Operations, Maintenance,Engineering,Plant Support & Effectiveness of Licensee Controls in Identifying & Preventing Problems IR 05000327/19960171997-02-14014 February 1997 Insp Repts 50-327/96-17 & 50-328/96-17 on 961208-970118.No Violations Noted.Major Areas Inspected:Operations, Maintenance,Engineering,Plant Support & Plant Status ML20134G1851997-01-13013 January 1997 Insp Repts 50-327/96-16 & 50-328/96-16 on 960923-1219. Violations Noted.Major Areas Inspected:Review of Corrective Actions Implemented for Problem Evaluation Repts IR 05000327/19960141996-12-31031 December 1996 Insp Repts 50-327/96-14 & 50-328/96-14 on 961027-1207.No Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support IR 05000327/19960151996-12-23023 December 1996 Insp Repts 50-327/96-15 & 50-328/96-15 on 961104-08.No Violations Noted.Major Areas Inspected:Control Room Simulator,Tsc,Osc,Cecc & Joint Info Ctr of Biennial Emergency Preparedness Exercise ML20134Q1721996-11-25025 November 1996 Insp Repts 50-327/96-13 & 50-328/96-13 on 960919-1102. Violations Noted.Major Areas Inspected:Events Associated W/Reactor Shutdown & Subsequent Manual Tripping of Unit 2 on 961011 IR 05000327/19960111996-11-19019 November 1996 Insp Repts 50-327/96-11 & 50-328/96-11 on 960915-1026. Violations Noted.Major Areas Inspected:Licensee Operations, Maint,Engineering,Plant Support, & Effectiveness of Licensee Controls in Identifying,Resolving & Preventing Problems ML20129A2141996-10-10010 October 1996 Insp Repts 50-327/96-09 & 50-328/96-09 on 960728-0914. Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support ML20128H8021996-09-27027 September 1996 Insp Repts 50-327/96-10 & 50-328/96-10 on 960708,10-12 & 0819-22.Non Cited Violations Noted.Major Areas Inspected: Plant FP Program & Action Taken of Insp Findings Previously Identified IR 05000328/20060151995-06-15015 June 1995 Insp Repts 50-387/95-08 & 50-388/95-08 on 950328-0615. Violations Noted.Major Areas Inspected:Plant Operations, Maint & Surveillance,Engineering & Plant Support.Initiatives Selected for Insp Plant Mgt Walkdowns IR 05000327/19940091994-05-0202 May 1994 Resident Insp Repts 50-327/94-09 & 50-328/94-09 on 940306- 0402.Violations Noted.Major Areas Inspected:Plant Operations,Plant Maint,Plant Surveillance,Evaluation of Licensee self-assessment Capability & LER Closeout IR 05000327/19940111994-04-29029 April 1994 Partially Withheld Insp Repts 50-327/94-11 & 50-328/94-11 on 940328-0401,per 10CFR73.21.No Violations Identified.Major Areas Inspected:Physical Security Program for Power Reactors,Alarm Stations,Assessment Aids & Testing & Maint IR 05000327/19930521993-12-23023 December 1993 Insp Repts 50-327/93-52 & 50-328/93-52 on 931107-1204. Violations Noted.Major Areas Inspected:Plant Operations, Maint,Plant Surveillance,Evaluation of Licensee self-assessment Capability & LER Closeout IR 05000327/19930371993-12-17017 December 1993 Insp Repts 50-327/93-37 & 50-328/93-37 on 931115-19. Violations Noted.Major Areas Inspected:Operator Requalification Program,Exam Development & Administration & Training Staff Qualifications & Training IR 05000327/19930531993-12-17017 December 1993 Insp Repts 50-327/93-53 & 50-328/93-53 on 931115-19.No Violations Noted.Major Areas Inspected:Meteorological Monitoring,Control Room Emergency Ventilation,Audits & Secondary Water Chemistry IR 05000327/19930511993-12-13013 December 1993 Partially Withheld Insp Repts 50-327/93-51 & 50-328/93-51 on 931115-19 (Ref 10CFR73.21).No Violations Noted.Major Areas Inspected:Mgt Support,Security Program Plans & Implementing Procedures & Security Program Audit IR 05000327/19930501993-11-24024 November 1993 Insp Repts 50-327/93-50 & 50-328/93-50 on 931011-1106. Violations Noted.Major Areas Inspected:Plant Operations, Plant Maintenance,Plant Surveillance,Evaluation of Licensee self-assessment Capability & LER Closeout IR 05000327/19930421993-11-0909 November 1993 Insp Repts 50-327/93-42 & 50-328/93-42 on 930904-1010. Violations Noted.Major Areas Inspected:Plant Operations, Maint & Surveillance,Evaluation of Licensee self-assessment Capability & Licensee Event Rept Closeout IR 05000327/19930481993-11-0909 November 1993 Insp Repts 50-327/93-48 & 50-328/93-48 on 931006-08. Violation Noted.Major Areas Inspected:Qualifications of Acting Lab Supervisor,Use of Expired Stds in Alcohol breath-analysis Equipment & Testing Lab Procedures IR 05000327/19930491993-11-0202 November 1993 Insp Repts 50-327/93-49 & 50-328/93-49 on 930929-1004.No Violations Noted.Major Areas Inspected:Civil/Structural Items Which Will Remain Open After Restart 1999-09-27
[Table view] Category:INSPECTION REPORT
MONTHYEARIR 05000327/20240042025-01-28028 January 2025 Integrated Inspection Report 05000327/2024004 and 05000328/2024004 IR 05000327/20240902025-01-27027 January 2025 Final ASP Analysis Sequoyah 1 and 2, Failure of EDG 1B During Testing IR 05000327 2024 090 Precursor IR 05000327/20240102024-12-19019 December 2024 Design Basis Assurance Inspection (Programs) Inspection Report 05000327/2024010 and 05000328/2024010 IR 05000327/20240032024-11-0606 November 2024 Integrated Inspection Report 05000327/2024003 and 05000328/2024003 IR 05000327/20250102024-10-29029 October 2024 Notification of Sequoyah, Units 1 and 2 - Comprehensive Engineering Team Inspection - U.S. Nuclear Regulatory Commission Inspection Report 05000327/2025010 and 05000328/2025010 IR 05000327/20240052024-08-26026 August 2024 Updated Inspection Plan for Sequoyah Nuclear Plant, Units 1 and 2 - Report 05000327/2024005 and 05000328/2024005 IR 05000327/20240022024-07-31031 July 2024 Integrated Inspection Report 05000327/2024002 and 05000328/2024002 ML24145A0852024-05-30030 May 2024 1B-B Diesel Generator Failure - Final Significance Determination Letter IR 05000327/20240012024-04-17017 April 2024 Integrated Inspection Report 05000327/2024001 and 05000328/2024001 ML24066A1972024-03-19019 March 2024 NRC Inspection Report 05000327-2024090 and 05000328-2024090 and Preliminary Greater than Green Finding and Apparent Violation IR 05000327/20244012024-03-12012 March 2024 – Security Baseline Inspection Report 05000327/2024401 and 05000328/2024401 IR 05000259/20230062024-02-28028 February 2024 Annual Assessment Letter for Sequoyah Nuclear Plant, Units 1, 2 - Report 05000259/2023006, 05000260/2023006 and 05000296/2023006 IR 05000327/20230042024-02-12012 February 2024 Integrated Inspection Report 05000327/2023004 and 05000328/2023004 and Apparent Violation IR 05000327/20234422024-01-11011 January 2024 95001 Supplemental Inspection Report 05000327/2023442 and 05000328/2023442 and Follow-Up Assessment Letter IR 05000327/20234202023-11-28028 November 2023 Security Baseline Inspection Report 05000327/2023420 and 05000328/2023420 IR 05000327/20230032023-11-0303 November 2023 – Integrated Inspection Report 05000327/2023003 and 05000328/2023003 IR 05000327/20230112023-10-16016 October 2023 Triennial Fire Protection Inspection Report 05000327/2023011 and 05000328/2023011 IR 05000327/20234032023-09-14014 September 2023 Cyber Security Inspection Report 05000327/2023403 and 05000328/2023403 (Cover Letter) IR 05000327/20230052023-08-29029 August 2023 Updated Inspection Plan for Sequoyah Nuclear Plant, Units 1 and 2 - Report 05000327/2023005 and 05000328/2023005 IR 05000327/20230022023-07-31031 July 2023 Integrated Inspection Report 05000327/2023002 and 05000328/2023002 IR 05000327/20230102023-07-20020 July 2023 – Biennial Problem Identification and Resolution Inspection Report 05000327/2023010 and 05000328/2023010 ML23163A0392023-06-13013 June 2023 – Notification of an NRC Fire Protection Team Inspection (FPTI) (NRC Inspection Report 05000327/2023011, 05000328/2023011) and Request for Information (RFI) IR 05000327/20233012023-05-15015 May 2023 – NRC Operator License Examination Report 05000327/2023301 and 05000328/2023301 IR 05000327/20230012023-05-0202 May 2023 Integrated Inspection Report 05000327/2023001 and 05000328/2023001 and Exercise of Enforcement Discretion IR 05000327/20234412023-04-20020 April 2023 Final Significance Determination for a Security-Related Greater than Green Finding, Nov & Assessment Followup Letter, 05000327/2023441 & 05000328/2023441 IR 05000327/20234022023-04-13013 April 2023 Security Baseline Inspection Report 05000327/2023402 and 05000328/2023402 IR 05000327/20220062023-03-0101 March 2023 Annual Assessment Letter for Sequoyah Nuclear Plant, Units 1 and 2 Report 05000327/2022006 and 05000328/2022006 IR 05000327/20234402023-02-13013 February 2023 – NRC Inspection Report 05000327/2023440 and 05000328/2023440; Preliminary Greater than Green and Apparent Violation Cover Letter IR 05000327/20220042023-02-10010 February 2023 Integrated Inspection Report 05000327/2022004 and 05000328/2022004 IR 05000327/20234012023-02-0606 February 2023 – Security Baseline Inspection Report 05000327/2023401 and 05000328/2023401 IR 05000327/20224402023-01-17017 January 2023 – Special Inspection Report 05000327/2022440 and 05000328/2022440 and Apparent Violation - Cover IR 05000327/20220032022-11-0707 November 2022 – Integrated Inspection Report 05000327/2022003 and 05000328/2022003 IR 05000327/20224012022-10-18018 October 2022 Material Control and Accounting Program Inspection Report 05000327/2022401 and 05000328/2022401 IR 05000327/20220052022-08-30030 August 2022 Updated Inspection Plan for Sequoyah Nuclear Plant, Units 1 and 2 - Report 05000327 2022005 and 05000328 2022005 - Final IR 05000327/20220022022-08-0101 August 2022 Integrated Inspection Report 05000327 2022002 and 05000328 2022002 IR 05000327/20223012022-07-21021 July 2022 Operator License Examination Report 05000327/2022301 and 05000328/2022301 IR 05000327/20220012022-05-11011 May 2022 Integrated Inspection Report 05000327/2022001, 05000328/2022001 and 07200034/2010002 IR 05000327/20220102022-04-25025 April 2022 Design Basis Assurance Inspection (Teams) Inspection Report 05000327/2022010 and 05000328/2022010 IR 05000327/20224022022-03-28028 March 2022 Security Baseline Inspection Report 05000327/2022402 and 05000328/2022402 IR 05000327/20210062022-03-0202 March 2022 Annual Assessment Letter for Sequoyah Nuclear Plant, Units 1 and 2 - (Report No. 05000327/2021006 and 05000328/2021006) IR 05000327/20210042022-02-0707 February 2022 Integrated Inspection Report 05000327/2021004 and 05000328/2021004 IR 05000327/20210032021-11-10010 November 2021 Integrated Inspection Report 05000327/2021003 and 05000328/2021003 and Apparent Violation and Exercise of Enforcement Discretion IR 05000327/20210052021-08-18018 August 2021 Updated Inspection Plan for Sequoyah Nuclear Plant, Units 1 and 2 Report 05000327/2021005 and 05000328/2021005 IR 05000327/20210022021-07-27027 July 2021 Integrated Inspection Report 05000327/2021002 and 05000328/2021002 IR 05000327/20210112021-07-19019 July 2021 Biennial Problem Identification and Resolution Inspection Report 05000327/2021011 and 05000328/2021011 IR 05000327/20210012021-04-27027 April 2021 Integrated Inspection Report 05000327/2021001 and 05000328/2021001 IR 05000327/20210102021-04-21021 April 2021 NRC Inspection Report 05000327/2021010 and 05000328/2021010 IR 05000327/20214012021-04-21021 April 2021 NRC Inspection Report 05000327/2021401 and 05000328/2021401 (U) IR 05000327/20200062021-03-0303 March 2021 Annual Assessment Letter for Sequoyah Nuclear Plant, Units 1 and 2 - Report 05000327/2020006 and 05000328/2020006 IR 05000327/20200042021-01-29029 January 2021 Integrated Inspection Report 05000327/2020004 and 05000328/2020004 2025-01-28
[Table view] Category:UTILITY
MONTHYEARIR 05000327/19900341990-11-16016 November 1990 Insp Repts 50-327/90-34 & 50-328/90-34 on 901006-1105.One Violation & One Apparent Violation Noted.Major Areas Inspected:Operational Safety Verification Including Control Room Observations & Sys Lineups IR 05000327/19900361990-11-0909 November 1990 Augmented Insp Team Repts 50-327/90-36 & 50-328/90-36 on 901011-19.Insp Included Review of Events That Led to Discovery of Multiple Failures of Main Steam Check Valves on 901008 IR 05000327/19900321990-11-0101 November 1990 Insp Repts 50-327/90-32 & 50-328/90-32 on 900906-1005. Violations Noted.Major Areas Inspected:Operational Safety Verification,Including Control Room Observations,Operations Performance,Sys Lineups & Radiation Protection IR 05000327/19900331990-10-31031 October 1990 Insp Repts 50-327/90-33 & 50-328/90-33 on 901009-12.No Violations or Deviations Identified.Major Areas Inspected: Emergency Preparedness Program:Emergency Detection & Classification,Protective Action decision-making IR 05000327/19900291990-10-0505 October 1990 Insp Repts 50-327/90-29 & 50-328/90-29 on 900827-31. Violation Noted.Major Areas Inspected:Measurement of Incore Power Distributions,Calibr of Nuclear Instruments, Measurement of Thermal Power & Followup of LERs IR 05000327/19900311990-09-26026 September 1990 Insp Repts 50-327/90-31 & 50-328/90-31 on 900910-14.No Violations or Deviations Noted.Major Areas Inspected: Occupational Exposure During Extended Outages & Licensee Actions to Correct Previously Identified Weaknesses IR 05000327/19900261990-08-30030 August 1990 Insp Repts 50-327/90-26 & 50-328/90-26 on 900706-0805. Violations Noted But Not Cited.Major Areas Inspected:Control Room Observations,Operations Performance,Sys Lineups, Radiation Protection & Safeguards ML20059H0431990-08-21021 August 1990 Insp Repts 50-327/90-23 & 50-328/90-23 on 900625-29.No Violations or Deviations Noted.Weaknesses in Program Implementation Noted.Major Areas Inspected:Plant Program to Maintain Occupational Dose to Workers ALARA IR 05000327/19900211990-07-31031 July 1990 Insp Repts 50-327/90-21 & 50-328/90-21 on 900709-13.No Violations or Deviations Noted.Major Areas Inspected: Observation & Evaluation of Annual Emergency Response Exercise IR 05000327/19900201990-06-29029 June 1990 Insp Repts 50-327/90-20 & 50-328/90-20 on 900506-0605.No Violations or Deviations Noted.Major Areas Inspected: Operational Safety Verification,Including Control Room Observations,Operations Performance & Sys Lineups IR 05000327/19900191990-05-21021 May 1990 Insp Repts 50-327/90-19 & 50-328/90-19 on 900423-27.No Violations or Deviations Noted.Major Areas Inspected: Radiation Protection Activities,Including Review of Licensee Organization & Mgt Controls & Training IR 05000327/19900131990-05-21021 May 1990 Insp Repts 50-327/90-13 & 50-328/90-13 on 900423-27.No Violations or Deviations Noted.Major Areas Inspected: Emergency Facilities,Equipment,Instrumentation,Supplies, Organization & Mgt Control & Independent Review/Audits ML20043A5271990-05-16016 May 1990 Insp Repts 50-327/90-17 & 50-328/90-17 on 900406-0505. Violations Noted.Major Areas Inspected:Control Room Observations,Sys Lineups,Radiation Protection,Safeguards, Surveillance Testing & Followup to Generic Ltr 88-17 IR 05000327/19900141990-05-0303 May 1990 Insp Repts 50-327/90-14 & 50-328/90-14 on 900326-30 & 0409-13.Violations Noted.Major Areas Inspected:Inservice Testing,Containment Integrity & Followup on Previous Insp Findings IR 05000327/19900111990-04-25025 April 1990 Insp Repts 50-327/90-11 & 50-328/90-11 on 900306-0405. Violations Noted.Major Areas Inspected:Control Room Observations,Operations Performance,Sys Lineups,Radiation Protection,Safeguards & Housekeeping Insps ML20034C4651990-04-25025 April 1990 Partially Withheld Insp Repts 50-327/90-15 & 50-328/90-15 on 900326-30 (Ref 10CFR2.790 & 73.21).Violations Noted.Major Areas Inspected:Physical Security Program Including, Inspector Reviewed Barriers & Detection Aids IR 05000327/19900161990-04-12012 April 1990 Partially Withheld Insp Repts 50-327/90-16 & 50-328/90-16 on 900326-30.No Violations or Deviations Noted.Major Areas Inspected:Review of Procedures,Records,Operations & Physical Inventory,Control & Accountability of SNM IR 05000327/19900121990-04-10010 April 1990 Insp Repts 50-327/90-12 & 50-328/90-12 on 900326-30.No Violations or Deviations Noted.Major Areas Inspected: Inservice Insp (Isi),Including Review of NDE Procedures,Isi Plan for Outage & Observations of in Progress NDE Exams IR 05000327/19900081990-04-0404 April 1990 Insp Repts 50-327/90-08 & 50-328/90-08 on 900226-0302.No Violations Noted.Several Examples of Corrective Action Procedure Ambiguities Noted.Major Areas Inspected: Operational Events & Employee Concerns Program IR 05000327/19900071990-04-0303 April 1990 Insp Repts 50-327/90-07 & 50-328/90-07 on 900226-0302.No Violations or Deviations Noted.Major Areas Inspected: Radiological Effluents & Waste Treatment,Radiological Environ Monitoring & Primary & Secondary Water Chemistry IR 05000327/19900031990-03-14014 March 1990 Insp Repts 50-327/90-03 & 50-328/90-03 on 900105-0205.No Violations Noted.Major Areas Inspected:Operational Safety Verification,Maint Observations,Surveillance Testing Observations,Review of Insp Findings & Followup of Events IR 05000327/19900021990-03-0909 March 1990 Insp Repts 50-327/90-02 & 50-328/90-02 on 900122-26. Violations Noted.Major Areas Inspected:Design Changes & Mods,Procurement & Licensee Action on Previously Identified Findings ML20033F3361990-02-22022 February 1990 Partially Withheld Insp Repts 50-327/90-05 & 50-328/90-05 on 900130-0202.Violations Noted.Major Areas Inspected: Routine,Unannounced Insp of Licensee Physical Security Program of Power Reactors Including,Plans,Audits & Maint IR 05000327/19900041990-02-14014 February 1990 Insp Repts 50-327/90-04 & 50-328/90-04 on 900122-26.No Violations Noted.Major Areas Inspected:Radiation Protection Program & pre-outage Activities for Radiation Protection Program.Licensee Identified Violation Cited IR 05000327/19890291990-01-31031 January 1990 Insp Repts 50-327/89-29 & 50-328/89-29 on 891205-900109. Violations Noted.Major Areas Inspected:Operational Safety Verification,Including Control Room Observations,Safeguards, Radiation Protection & Sys Lineups IR 05000327/19890281990-01-26026 January 1990 Insp Repts 50-327/89-28 & 50-328/89-28 on 891113-17. Violation Noted Re Failure to Source Check Effluent Gas Monitors Per Tech Specs.Major Areas Inspected:Radiological Effluents & Waste Treatment,Water Chemistry & QA IR 05000327/19890271990-01-0202 January 1990 Insp Repts 50-327/89-27 & 50-328/89-27 on 891106-1205. Violations Noted.Major Areas Inspected:Operational Safety Verification,Including Control Room Observations,Operations Performance,Sys Lineups,Radiation Protection & Safeguards IR 05000327/19890251989-12-0505 December 1989 Insp Repts 50-327/89-25 & 50-328/89-25 on 891006-1108. Violations Noted.Major Areas Inspected:Operational Safety Verification Including Control Room Observations,Operations Performance,Sys Lineups,Radiation Protection & Safeguards IR 05000327/19890261989-11-0909 November 1989 Insp Repts 50-327/89-26 & 50-328/89-26 on 891023-27.No Violations or Deviations Noted.Major Areas Inspected: Allegation Followup to Establish Validity & to Verify Corrective Actions Implemented for Invalid Allegations IR 05000327/19890231989-11-0808 November 1989 Insp Repts 50-327/89-23 & 50-328/89-23 on 891002-06.No Violations or Deviations Noted.Major Areas Inspected:Fire Prevention/Fire Protection IR 05000327/19890221989-11-0707 November 1989 Insp Repts 50-327/89-22 & 50-328/89-22 on 890906-1005.No Violations or Deviations Noted.Major Areas Inspected: Operational Safety Verification Including Control Room Observations,Operations Performance & Sys Lineups IR 05000327/19890241989-10-25025 October 1989 Insp Repts 50-327/89-24 & 50-328/89-24 on 890927-29.No Violations Noted.Major Areas Inspected:Radiation Protection Program,Followup on Previous Inspector Identified Items & Employee Safety Concerns IR 05000327/19890201989-08-29029 August 1989 Insp Repts 50-327/89-20 & 50-328/89-20 on 890717-20.No Violations or Deviations Noted.Major Areas Inspected:Annual Emergency Exercise,Including Staffing & Response of Emergency Organizations in Control Room & Support Ctrs IR 05000327/19890141989-08-28028 August 1989 Insp Repts 50-327/89-14 & 50-328/89-14 on 890424-28. Violations Noted.Major Areas Inspected:Surveillance & Operational Records & Procedures.Discussions Held W/ Operations,Engineering & Transmissions Personnel IR 05000327/19890191989-08-25025 August 1989 Insp Repts 50-327/89-19 & 50-328/89-19 on 890706-0805. Violations Noted.Major Areas Inspected:Operational Safety Verification,Including Control Room Observations,Operations Performance,Sys Lineups & Radiation Protection ML20245L3191989-08-0101 August 1989 Insp Repts 50-327/89-11 & 50-328/89-11 on 890626-30. Violations Noted.Major Areas Inspected:Radiation Protection Program,Follow Up on Previous Inspector Identified Items & IE Info Notices IR 05000327/19890171989-07-28028 July 1989 Partially Withheld Safeguards Insp Repts 50-327/89-17 & 50-328/89-17 on 890522-26 (Ref 10CFR2.790(d) & 73.21)). Violations Noted.Major Areas Inspected:Physical Security Program for Power Reactors & Protected Area Alarms ML20246B6511989-06-26026 June 1989 Insp Repts 50-327/89-15 & 50-328/89-15 on 890506-0605. Violations Noted.Major Areas Inspected:Operational Safety Verification,Operations Performance,Sys Lineups,Radiation Protection,Safeguards & Housekeeping Insps ML20245D4191989-06-14014 June 1989 Insp Repts 50-327/89-16 & 50-328/89-16 on 890508-12. Violation Noted.Major Areas Inspected:Review of Completed Unit 2,Cycle 4 Initial Criticality & Post Refueling Start Up Tests & Evaluation of Thermal Power Measurements for Unit 1 IR 05000327/19890121989-05-24024 May 1989 Insp Repts 50-327/89-12 & 50-328/89-12 on 890406-0505. Violation Noted.Major Areas Inspected:Radiation Protection, Safeguards & Operational Safety Verification,Including Control Room Observations & Operational Performance IR 05000327/19890131989-05-16016 May 1989 Insp Repts 50-327/89-13 & 50-328/89-13 on 890417-21.No Violations or Deviations Noted.Major Areas Inspected: Emergency Preparedness,Including Review of Programmatic Elements & Radiological Emergency Plan & Training IR 05000327/19890101989-05-0404 May 1989 Insp Repts 50-327/89-10 & 50-328/89-10 on 890316-20.No Violations or Deviations Noted.Major Areas Inspected: Containment Integrated Leak Rate Testing,Review of Test Procedures & Evaluation of Test Results ML20246K0751989-05-0303 May 1989 Insp Repts 50-327/89-09 & 50-328/89-09 on 890305-0405. Violations Noted.Major Areas Inspected:Operational Safety Verification,Including Operations Performance,Sys Lineups, Radiation Protection,Safeguards & Housekeeping Insps IR 05000327/19890071989-04-13013 April 1989 Insp Repts 50-327/89-07 & 50-328/89-07 on 890205-0304. Violations Noted.Major Areas Inspected:Operational Safety Verification,Including Operations Performance,Sys Lineups, Radiation Protection,Safeguards & Housekeeping ML20244C3911989-04-0404 April 1989 Insp Repts 50-327/88-50 & 50-328/88-50 on 881212-890126. Violations Noted.Major Areas Inspected:Plant Operations, Surveillance & Sys Outage Control,Corrective Action Program, Maint Activities & Qualified Reviewer Process IR 05000327/19890051989-03-13013 March 1989 Special Team Insp Repts 50-327/89-05 & 50-328/89-05 on 890131-0209.Violations Noted.Major Areas Inspected:Radwaste, Radiological Controls,Corporate QA Audits & Site Chemistry ML20247F3461989-03-13013 March 1989 Special Team Insp Repts 50-327/89-05 & 50-328/89-05 on 890131-0209.Violations Noted.Major Areas Inspected:Radwaste, Radiological Controls,Corporate QA Audits & Site Chemistry IR 05000327/19890061989-03-10010 March 1989 Partially Withheld Insp Repts 50-327/89-06 & 50-328/89-06 on 890123-27 (Ref 10CFR2.790(d) & 73.21).Violation Noted.Major Areas Inspected:Physical Security Program for Reactors, Including Security Mgt,Audit,Barriers,Alarms & Maint IR 05000327/19890021989-03-0909 March 1989 Insp Repts 50-327/89-02 & 50-328/89-02 on 890105-0204.No Violations or Deviations Noted.Major Areas Inspected: Operational Safety Verification Including,Operations Performance,Sys Lineups & Radiation Protection IR 05000327/19890081989-03-0303 March 1989 Insp Repts 50-327/89-08 & 50-328/89-08 on 890213-17. Violations Noted.Major Areas Inspected:Inservice Insp, Including Eddy Current Exam of Unit 2 Steam Generator Tubing,Reviews of NDE Exams Procedures & Exam Verifications 1990-09-26
[Table view] Category:TEXT-INSPECTION & AUDIT & I&E CIRCULARS
MONTHYEARIR 05000327/19990051999-09-27027 September 1999 Insp Repts 50-327/99-05 & 50-328/99-05 on 990718-0828. Violations Noted.Major Areas Inspected:Mitigating Sys IR 05000327/19990041999-08-13013 August 1999 Insp Repts 50-327/99-04 & 50-328/99-04 on 990601-0717.One Potentially Safety Significant Issue Noted.Major Areas Inspected:Licensee Emergency Preparedness IR 05000327/19990031999-06-30030 June 1999 Insp Repts 50-327/99-03 & 50-328/99-03 on 990328-0531.Non- Cited Violations Noted.Major Areas Inspected:Aspects of Licensee Operations,Maint & Engineering IR 05000327/19990021999-04-23023 April 1999 Insp Repts 50-327/99-02 & 50-328/99-02 on 990214-0327.No Violations Noted.Major Areas Inspected:Licensee Operations, Maint & Engineering IR 05000327/19990011999-03-15015 March 1999 Insp Repts 50-327/99-01 & 50-328/99-01 on 990103-0213. Violations Noted & Being Treated as non-cited Violations. Major Areas Inspected:Aspects of Licensee Operations,Maint & Engineering IR 05000327/19983021999-03-12012 March 1999 NRC Operator Licensing Exam Repts 50-327/98-302 & 50-328/98-302 (Including Completed & Graded Tests) for Test Administered on 980928-1001 IR 05000327/19980111999-02-0101 February 1999 Insp Repts 50-327/98-11 & 50-328/98-11 on 981122-990102. Violations Noted.Major Areas Inspected:Licensee Operations, Maint & Engineering ML20202J5471999-02-0101 February 1999 Notice of Violation from Insp on 981122-990102.Violation Noted:Following Unit 1 RT on 981109,procedural Requirements of EOP ES0.1 Were Not Properly Implemented,In That RCS Temperatures Were Not Monitored & Steam Not Dumped IR 05000327/19980101998-12-0707 December 1998 Insp Repts 50-327/98-10 & 50-328/98-10 on 981011-1121.No Violations Noted.Major Areas Inspected:Operations,Maint & Engineering IR 05000327/19980141998-12-0404 December 1998 Insp Repts 50-327/98-14 & 50-328/98-14 on 981102-06.No Violations Noted.Major Areas Inspected:Observation & Evaluation of Biennial Emergency Preparedness Exercise for Sequoyah Nuclear Plan ML20196D6081998-11-24024 November 1998 Notice of Violation from Insp on 980914-1016.Violation Noted:As of 980916,requirements of 0-MI-MXX-061-001 Not Implemented IR 05000327/19980131998-11-24024 November 1998 Insp Repts 50-327/98-13 & 50-328/98-13 on 980914-1016. Violations Noted.Major Areas Inspected:Aspects of Licensee maint,testing,engineering,self-assessment & Problem Evaluations of Licensee Ice Condenser Sys ML20195G5521998-11-0909 November 1998 Notice of Violation from Insp on 980830-1010.Violation Noted:Licensee Failed to Assure That All Testing Required to Demonstrate That Safety Related Circuit Breakers Would Perform Satisfactorily in Svc IR 05000327/19980091998-11-0909 November 1998 Insp Repts 50-327/98-09 & 50-328/98-09 on 980830-1010. Violations Noted.Major Areas Inspected:Licensee Operations, Maint,Engineering Plant Support & Effectiveness of Licensee Controls in Identifying,Resolving & Preventing Problems IR 05000327/19980081998-09-18018 September 1998 Insp Repts 50-327/98-08 & 50-328/98-08 on 980719-0829.No Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support,Licensee Conducted Radiological Emergency Plan Drill ML20237B1851998-08-0404 August 1998 Notice of Violation from Insp on 980606-0718.Violations Noted:On or Before 971103,conditions Adverse to Qualify Were Not Promptly Identified & Corrected,In That Licensee Failed to Correct &/Or Initiate Problem Evaluation Rept IR 05000327/19980071998-08-0404 August 1998 Insp Repts 50-327/98-07 & 50-328/98-07 on 980607-0718. Violations Noted.Major Areas Inspected:Aspects of Licensee Operation,Maint,Engineering,Plant Support & Effectiveness of Licensee Controls in Identifying & Preventing Problems IR 05000327/19980061998-06-26026 June 1998 Insp Repts 50-327/98-06 & 50-328/98-06 on 980426-0606. Violations Noted.Major Areas Inspected:Operations, Maintenance,Engineering & Plant Support ML20236J6591998-06-26026 June 1998 Notice of Violation from Insp on 980426-0606.Violation Noted:Inservice Testing of Valves Not in Accordance with Section XI of ASME Boiler & Pressure Vessel Code & Applicable Addenda as Required by 10CFR50.55a IR 05000327/19983001998-06-25025 June 1998 NRC Operator Licensing Exam Repts 50-327/98-300 & 50-328/98-300 (Including Completed & Graded Tests) for Tests Administered on 980601-02 IR 05000327/19980051998-06-12012 June 1998 Insp Repts 50-327/98-05 & 50-328/98-05 on 980504-08.No Violations Noted.Major Areas Inspected:Maint Procedure.Insp Team Comprised Region II & Headquarters Personnel.Switchgear & Surrounding Areas Found in Good Matl Condition ML20247L5781998-05-15015 May 1998 Notice of Violation from Insp on 980315-0425.Violation Noted:Licensee Failed to Perform Surveillance Requirement 4.8.1.1.1.a,within 1 H & at Least Once Per 8 H Thereafter ML20216H7701998-04-10010 April 1998 Notice of Violation from Insp on 980201-0314.Violation Noted:License Failed to Rept an Adverse Condition on Work Request/Work Order &/Or Problem Evaluation Rept IR 05000327/19980031998-04-10010 April 1998 Insp Repts 50-327/98-03 & 50-328/98-03 on 980201-0314. Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support IR 05000327/19980991998-04-0101 April 1998 SALP Repts 50-327/98-99 & 50-328/98-99 for Period 960728- 980221 IR 05000327/19980011998-03-30030 March 1998 Insp Repts 50-327/98-01 & 50-328/98-01 on 980126-0213.No Violations Noted.Major Areas Inspected:Operations,Maint & Engineering ML20217K3751998-03-30030 March 1998 Notice of Violation from Insp on 980126-0213.Violation Noted:On Listed Dates,Licensee Made Changes to Facility as Described in FSAR W/O Adequate Written SE Which Provides Bases for Determination That Changes Did Not Involve USQ IR 05000327/19980021998-03-0505 March 1998 Insp Repts 50-327/98-02 & 50-328/98-02 on 980202-06.No Violations Noted.Major Areas Inspected:Aspects of Licensee Operations & Maint.Review of Initial & Requalification Training Programs Were Also Conducted IR 05000327/19970181998-02-19019 February 1998 Insp Repts 50-327/97-18 & 50-328/97-18 on 971221-980131. Violations Noted.Major Areas Inspected:Licensee Operations, Maint,Engineering,Plant Support & Effectiveness of Licensee Controls in Identifying & Resolving Problems ML20203J5411998-02-19019 February 1998 Notice of Violation from Insp on 971231-980131.Violation Noted:On 980126 Individuals Failed to Monitor Themselves in Whole Body Contamination Monitor or W/Hand & Foot Frisk Monitor ML20216D8431998-02-0606 February 1998 EN-97-109A:on 980206,informs of Withdrawal of Proposed Civil Penalty of $55,000 Issued to Licensee.Credit for Identification Appropriate to Recognize Diligence of TVA Training Instructor Who Discovered Vital Battery Problem IR 05000327/19970171998-01-16016 January 1998 Insp Repts 50-327/97-17 & 50-328/97-17 on 971109-1220.No Violations Noted.Major Areas Inspected:Operations,Maint, Engineering,Plant Support & Effectiveness of Licensee Controls in Identifying,Resolving & Preventing Problems IR 05000327/19970141997-12-0808 December 1997 Insp Repts 50-327/97-14 & 50-328/97-14 on 970928-1108.No Violations Noted.Major Areas Inspected:Operations,Maint, Engineering,Plant Support,Effectiveness of License Controls in Identifying,Resolving & Preventing Problems ML20197F5541997-12-0808 December 1997 Notice of Violation from Insp on 970725-0704 & Proposed Imposition of Civil Penalty in Amount of $55,000.Violation Noted:Sro Failed to Implement Step 8.4.8 of Soi 0-S0-250-1. Predecisional EC Agenda & Documentation Encl IR 05000327/19970161997-12-0505 December 1997 Insp Repts 50-327/97-16 & 50-328/97-16 on 971103-06.No Violations Noted.Major Areas Inspected:Evaluation of 971017 Wire Damage Event at Electrical Penetration 22 ML20197F6971997-12-0303 December 1997 EN-97-109:on 971208,notice of Proposed Imposition of Civil Penalty in Amount of $55,000 Issued to Licensee.Action Based on Severity Level III Problem Re Failure to Maintain Direct Current Vital Battery Channel Energized & Operable IR 05000327/19973001997-11-0606 November 1997 Exam Repts 50-327/97-300 & 50-328/97-300 on 970919-1007. Exam Results:Four Out of Seven Candidates Passed Exam.One Candidate Was Marginal Performer IR 05000327/19970121997-10-24024 October 1997 Insp Repts 50-327/97-12 & 50-328/97-12 on 970824-0927.No Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support & Operator Requalification Program IR 05000327/19970151997-10-23023 October 1997 Insp Repts 50-327/97-15 & 50-328/97-15 on 970922-29.No Violations Noted.Major Areas Inspected:Emergency Preparedness PNO-II-97-057, on 971017,discovered 12 of 14 Instrument Cables Damaged in Unit 2 Containment Electrical Penetration. Sequoyah Unit 2 in Outage & All Fuel Removed from Reactor Vessel.Licensee Continues to Investigate Event1997-10-17017 October 1997 PNO-II-97-057:on 971017,discovered 12 of 14 Instrument Cables Damaged in Unit 2 Containment Electrical Penetration. Sequoyah Unit 2 in Outage & All Fuel Removed from Reactor Vessel.Licensee Continues to Investigate Event PNO-II-97-055, on 971006,contaminated Person Transported from Sequoyah Nuclear Plant to Offsite Medical Facility,Following Apparent Heart Attack.Victim Pronounced Dead at Hosp,Due to Apparent Heart Attack.Licensee Responded to Media Inquirie1997-10-0606 October 1997 PNO-II-97-055:on 971006,contaminated Person Transported from Sequoyah Nuclear Plant to Offsite Medical Facility,Following Apparent Heart Attack.Victim Pronounced Dead at Hosp,Due to Apparent Heart Attack.Licensee Responded to Media Inquirie ML20211E2531997-09-22022 September 1997 Notice of Violation from Insp on 970706-0823.Violation Noted:On 970714,containment Isolation Valve 1-FCV-31C-229 Failed to Exhibit Required Change of Obturator Position & Was Not Repaired or Replaced & Data Not Analyzed ML20198H7911997-09-11011 September 1997 Insp Repts 50-327/97-13 & 50-328/97-13 on 970725-0904. Violations Noted.Major Areas Inspected:Insp Scope,Event Synopsis & Observations & Findings IR 05000327/19970061997-07-28028 July 1997 Insp Repts 50-327/97-06 & 50-328/97-06 on 970525-0705. Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support ML20141H9531997-07-28028 July 1997 Notice of Violation from Insp on 970525-0705.Violation Noted:Licensee Failed to Implement Prompt Corrective Actions to Resolve Condition Adverse to Quality IR 05000327/19970071997-07-24024 July 1997 Insp Repts 50-327/97-07 & 50-328/97-07 on 970623-27. Violations Noted.Major Areas Inspected:Aspects of Licensee Plant Support ML20149L5671997-07-24024 July 1997 Notice of Violation from Insp on 970623-27.Violation Noted: on 960627,licensee Had Loss of Security Electronic Equipment & Failed to Post Officers in Position to Provide Surveillance of Entire Protected Area Perimeter ML20149G8681997-07-10010 July 1997 Notice of Violation from Insp on 970324-0522.Violation Noted:Licensee Failed to Esatblish Measures to Assure That Significant Condition Adverse to Quality Was Promptly Identified & Corrected & C/A Taken to Preclude Repetition ML20141G0361997-06-20020 June 1997 Notice of Violation from Insp on 970413-0524.Violation Noted:Each Intermediate & Power Range Channel Was Not Subj to Channel Function Test within 12 H Prior to Initiating Physics Test ML20141G0441997-06-20020 June 1997 Insp Repts 50-327/97-04 & 50-328/97-04 on 970413-0524. Violations Noted.Major Areas Inspected:Operations Re Physics Testing,Maint,Engineering & Plant Support 1999-09-27
[Table view] |
Text
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NUCLEAR REIULATORY COMMISSION
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101 MARIETTA STREET, N.W., SUITE 2900
o ATLANTA, CEORGIA 30323
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50-327/87-21 and 50-328/87-21 Licensee:
Tennessee Valley Authority 6N/38A Lookout Place 1101 Market Street Chattanooga, TN 37402-2801 Docket Nos.:
50-327 and 50-328 License Nos.:
DPR-77 and DPR-79 Facility Name: Sequoyah 1 and 2 Inspection Conducted: March 23-2 and April 1-3, 1987
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Inspector:
B. R. Crowley
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Date Signed'
i Accompanying Personnel:
T. K. McLellan, Reactor Construction Engineer IE, DI, RCPB Approved by:
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J/. Blake, Section Chief Date Signed
[DvisionofReactorSafety n ineering Branch i
SUMMARY Scope:
This routine, announced inspection was conducted in the areas of licensee action on previous enforcement matters (Units 1 and 2) and inspector followup items -(IFI) (Units 1 and 2).
Results: No violations or deviations were identified.
-
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REPORT DETAILS 1.
Persons Contacted Licensee Employees
- L. M. Nobles, Plant Manager
R. Wallace, Site Directors Office
- M. R. Harding, Site Licensing Manager
- G. B. Kirk, Compliance Licensing Manager
- G. A. Lundin, Weld Project Manager
- W. H. Mackay, Mechanical Test Supervisor
- C. W. Hatmaker, Assistant Project Engineer - Welding Project
- R. A. Montgomery, Lead Engineer - Welding Project
- J. L. Adams, Lead Welding Engineer
- R. O. Barnett, Chief, Civil Engineer
- R. N. Thompson, Licensing Engineer
- M. A. Cooper, Compliance Licensing Engineer
- B. Hall, Regulatory Licensing Engineer D. F. Goetcheus, Steam Generator Project Manager J. Galbreth, Employee Concerns Other licensee employees contacted included engineers, technicians, security force members, and office personnel.
NRC Resident Inspectors
- K. Jenison, Senior Resident Inspector P. Harmon, Resident Inspector D. Loveless, Resident Inspector K. Poertner. Resident Inspector
- Attended exit interview 2.
Exit Interview The inspection scope and findings were summarized on April 3,1987, with those persons indicated in paragraph 1 above. The inspector described the areas inspected and discussed in detail the inspection findings.
No dissenting comments were received from the licensee.
The licensee did not identify as proprietary any of the materials provided to or reviewed by the inspector during this inspection.
3.
Licensee Action on Previous Enforcement Matters a.
(Closed) Unresolved Item 327,328/86-13-03, Resolution of NRC NDE Van Inspection Findings.
See RII Reports 50-327, 328/86-33 and 50-327, 328/86-59 for previous inspections of this item.
After RII Report
.)
.
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86-59, the only issues remaining to be resolved were relative to TVA Items 2, 15 and 21.
These issues have been resolved as summarized below.
(1)
(Closed) TVA Drawing 47A055-170 (TVA Item 2) - In addition to the problems identified by TVA and the NRC Van inspections, additional discrepancies were identified by(See IFI 327, the NRC team inspection documented in RII Report 86-33 328/86-33-05).
TVA re-inspected this item and documented and resolved all discrepancies.
In addition to performing calculations where needed to resolve discrepant conditions, the original calculations for the support were regenerated (See paragraph 3.b. below).
Where needed, drawings will be revised (See Significant Condition Report (SCR) SQNCEB8606).
i This item is closed based on review of TVA inspection documentation, SCR SQNCEB8606 and Engineering Calculations (See paragraph 5.a. below relative to review of calculations).
(2)
(Closed) TVA Item 15, Weld 1-46 - Welds were different from that shown on drawings.
Drawings reviewed by the NRC were TVA field drawings, which should not show vendor welds.
Per SCR SQNCEB8606, TVA drawings will be revised (See paragraph 5.c.
below).
(3)
(Closed) TVA Item 21, Welds C1, C2, C3 and C4.
This item is closed based on review of calculations for undersized welds (See paragraph 5.d. below).
b.
(Closed) Violation 327/86-65-01, Inadequate Design Control of the HVAC Seismic Supports.
TVA's letter of response, dated February 27, 1987, has been reviewed and determined to be acceptable by RII. The inspector held discussions with responsible personnel and examined corrective actions as stated in the letter of response.
The violation pertained to the inability of TVA to retrieve the original design calculations for a Unit 1 HVAC duct support (TVA Item 2 - See paragraph 3.a.(1) above).
As part of the corrective action, TVA i
regenerated the calculations for the support.
The inspectors
!
reviewed the regenerated calculations (See paragraph 5.a. below).
In addition, as part of an ongoing Design Basis Verification Program, TVA issued Policy Memorandum (PM) 86-02 to establish a program for
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achieving a consistent, continuous approach in development and
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maintenance of civil discipline calculations.
The PM identifies the calculations which are essential and also requires a project specific Implementation Plan.
The Sequoyah Implementation Plan contains criteria to categorize essential calculations as pre-start or post-start.
NRC's ongoing inspections of the Design Basis J
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Verification Program will satisfy verification of this portion of the corrective action for this violation.
TVA's letter of response stated that calculations designated as required for restart by the Sequoyah Implementation Plan would be verified for retrievability, or regenerated if necessary, by April 1, 1987 for Unit 2.
The April 1, 1987 date was not met.
TVA stated that the April 1,1987 date was based on an earlier restart date than is now feasible. At the time of the current NRC inspection, a letter was in preparation to change the April 1,1987 date to be more compatible with the current projected restart date. Closure of this item is based on the understanding that the new date will be prior to restart.
c.
(0 pen) Violation 327, 328/86-59-01, Failure to Meet Test Frequency Requirements for Category A and B Valves. TVA's letter of response, dated January 23, 1987, has been reviewed and determined to be acceptable by RII.
The inspector held discussions with responsible personnel and examined corrective actions as stated in the letter of response.
At the time of the current NRC inspection, revised procedures were in the review cycle and scheduled for issue prior to restart of Unit 2.
This item remains open pending review of the revised procedures.
4.
Unresolved Items Unresolved items were not identified during the inspection.
5.
Review of Engineering Calculations (Units 1 and 2)
The inspector reviewed engineering calculations, as detailed below, relative to problems identified in RII Reports 50-327, 328/86-13, 86-33, and 86-65.
See RII Report Nos. 50-327, 328/86-13, 86-33 and 86-59 for previous inspections in this area. The additionally supplied calculations were reviewed for completeness, consistency of documentation, engineering evaluations and mathematical accuracy of calculations.
The accuracy of the design loads used in the calculations were not reviewed since such a review is considered to be outside the scope of this inspection.
a.
TVA Item 2, HVAC Support - In addition to the welding discrepancies identified in RII Reports 50-327, 328/86-13 and 86-33, TVA was unable to provide the original design calculations when requested by the NRC inspector. This inability to retrieve calculations was identified as Violation 327/86-65-01 (See paragraph 3.b. above).
As a result of the violation, TVA has regenerated the original calculations for typical HVAC duct support 47A055-144 which includes HVAC seismic supports 1030 HDABHVAC - 0820, 0822 and 7965.
In addition, calculations were provided relative to welding discrepancies identified by TVA during their reinspection (See paragraph 3.a.(1)
above).
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The HVAC calculations were reviewed by the NRC inspector and found to be acceptable, b.
TVA Item 6A, Instrument Support - The support was constructed in accordance with Support Variance Sheet 51-19-221 which allowed a gusset to be added so that the support could be installed at an angle to the baseplate.
Calculations for this variance were not found and new calculations were requested.
The NRC inspector reviewed the new calculations as reflected in Support Variance Sheet 51-19-221 and found them to be acceptable.
c.
TVA Item 15, Instrument Support - The NRC van inspection found that
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the welds were different from that shown on the drawing.
The weld l
details were missing for some welds and the location and length were not per the drawing for other welds.
TVA's investigation revealed that the drawing used by the NRC was a TVA field drawing and that the support was a vendor furnished item.
Therefore, the vendor weld details should not have appeared on the TVA field drawing. The welds appeared on the field drawing because of a drafting error.
TVA's investigation determined that the welds in place were satisfactory.
The TVA drawing is being revised in accordance with SCR SQNCEB8606 to identify which welds are vendor welds.
In addition to review of TVA's evaluation, the NRC inspector reviewed the " Summary" of the
" Seismic Simulation Test Program on Instrumentation Rack" and found the test to be acceptable, d.
TVA Item 21, Cable Tray Support - Calculations were missing for undersized welds C1, C2, C3 and C4 on detail D.
During this inspection, TVA personnel informed the NRC inspectors, that Detail
"D" was mislabeled and the welds should have been labeled "A",
"B" and "N" on Detail "D".
Subsequently, the NRC inspector reviewed the related documentation to mislabeling of Detail
"D" and concurs with TVA's finding and resolution.
Calculations for unacceptable welds on Item 21 were reviewed by the NRC inspectors and found to be acceptable.
e.
TVA Group 1, Mechanical Welds - A number of piping welds were rejected for underfill, undercut, or inadequate leg length. The TVA package of engineering calculations supporting the discrepant conditions were reviewed and found to be acceptable.
Within the areas inspected, no violations or deviations were identified.
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6.
Employees Concerns The inspector evaluated the following employee concerns, a.
Case No. RII 85-A-0144, Weir Walls May Not Have Been Installed Properly This concern questioned whether reactor coolant pump weir plates were installed at Sequoyah and Watts Bar.
The concern was referred to TVA for investigation and was investigated for Sequoyah under TVA Concern No. ECP-86-SQ-252-01.
TVA's investigation, as documented in TVA report approved January 12, 1987, revealed the following:
Westinghouse initiated ECN's TVA-10524 and TEN-10515, dated
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August 22, 1973, to install weir plates in the reactor coolant pumps at Sequoyah.
TVA's letter 3973, dated August 23, 1974, provided engineering
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justification for not installing the weir plates.
Westinghouse cancelled the ECN's by memorandum, dated August 28,
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1974.
On July 9,1986, the SQN Project Engineer confirmed that the
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weir plates had not been installed at Sequoyah.
This concern is being investigated at Watts Bar under Employee
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Concern ECP-86-WB-4601-01.
Based on TVA's investigation, Case No. RII-85-A-0144 can be closed.
b.
Case No. RII-86-A-0117, IE-86-A-019, Technical Concerns Expressed by a TVA employee at Sequoyah Relative to CCW Heat Exchangers As a result of this employee concern, technical questions have been raised relative to the Component Cooling Water (CCW) Heat Exchanger at Sequoyah.
The first question related to substandard shell material for the heat exchangers.
TVA has determined that the questions relate to laminations identified in the shell material during opening the shells for internal modifications during 1980 and 1981.
TVA's investigation determined that laminations were acceptable for the material in question.
This concern was not pursued during the current inspection other than to review the following documents:
Memorandum to C. E. Curigton from D. F. Goetcheus, dated
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August 14, 1986 - Sequoyah Nuclear Plant (SQN) Units 1 and 2 -
Investigation of Component Cooling Heat Exchanger Concern -
Technical Evaluation, l
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SQN Work Plan 8588, Original, R1 and R2 - This work plan was
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issued in April of 1980 for modification to the heat exchanger and required cutting windows in the shells for the modification.
Review of the records copy of the Work Plan revealed that the modifications were performed and the windows welded in the shells as follows:
Unit A (Unit 1) -
May and June, 1980 Unit B (Unit 2) -
July and August, 1980 UnitC(Common)-
May and June, 1981 Maintenance Requests (MRs) 051677, 051678, and 051679 including
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associated Magnetic Particle (MT) inspection reports where the window welds were stripped of paint and MT inspected in September of 1982 - The MT reports indicate that linear indications were removed during the MT inspection. There are no records as to the location or nature of the linear indications.
The second concern related to porosity in the heat exchanger support to foot pad welds.
As noted in the August 14, 1986 memo identified above. TVA has investigated this concern and determined that some minor repairs are needed. An MR had been issued for the repair. The
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following summarizes the inspector's examination of this concern:
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The inspector visually observed the support and noted that
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significant porosity is present in the support to foot pad welds. Also, some welds contain minor overlaps. Other than the porosity and minor overlaps, the welds are uniform with good appearance (The welds are painted).
No specific receiving inspection documentation could be
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identified relative to the supports.
The heat exchangers were inspected in the vendor's (Industrial Process Engineers) plant under TVA Inspection and Test (I&T) program.
A sample of I&T reports was reviewed.
There was no specific reference to the support welds.
The TVA Contract No, is 71C33-92691, Specification No. 1339.
In
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accordance with the contract, the applicable code isSection VIII of the ASME Boiler and Pressure Vessel Code.
The contract specifies that welding be in accordance with ASME Section IX but does not specify any NDE or acceptance criteria for the support welds.
The supports are outside the Section VIII boundary and Section VIII only specifies that the vessel be supported in such a way as to provide for the maximum imposed loading.
Nonmandatory Appendix G to Section VIII contains suggested rules for supports.
Appendix G states that the details of supports should conform to good structural practice.
Also reference is
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made to the AISC Manual.
Therefore, there are no contractual requirements, other than good structural practice, for the support welds.
Since AISC is referenced in the nonmandatory Appendix G to Section VIII, TVA considered using AWS D1.1 for inspection of the supports.
At the close of the inspection TVA was considering using NCIG-01, Visual Weld Acceptance Criteria for Structural Welding at Nuclear Power Plants, for reinspection of the support to foot pad welds.
TVA also aointed out to the NRC inspector that plans have been
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made to clange out the heat exchangers with a new design.
New heat exchangers have been procured and are on site.
The following is the tentative schedule for the change out:
A - Unit 1, cycle 5 11/02/90 B - Unit 2, cycle 3 02/12/88 C - Unit 1, cycle 4 04/07/89 Case No. RII-86-A-0117, IE-86-A-019 will remain open pending further evaluation by the NRC.
7.
Inspector Followup Items (92701) (Units 1 and 2)
a.
(Closed) Inspector Followup Item 327,328/86-09-03, Clarification of Terms " Adequate for Service" and " Meets all Requirements" Relative to TVA Welding Program.
This item pertained to the fact that the TVA Secuoyah Phase I Welding Action Plan appeared to use the terms
"Acequate for Service" and " Meets all Requirements" interchangeably.
The NRC pointed out that the first step should be to determine if commitments / requirements were met and the second step to determine adequacy for service.
Review of TVA activities during the welding inspection program at Sequoyah revealed that in actual practice, TVA did perform the two separate steps.
Section 1.0 of the TVA Phase II Welding Pro Report states that the purpose of the welding noject is ".. ject
.to assure that installed weldments... meet TVA Coce, and regulatory requirements and are adequate for service.
In addition, TVA is going to revise the paragraph at the bottom of page 12 of Section 4.0 of the Phase II Report to further clarify that the two separate steps were used in the welding inspection program.
b.
Inspector Followup Items in RII Report 50-317, 328/86-33 are identified in notes to tables in the report.
Each item number may be defined by several parts, each part being described by a note in the table.
Therefore, closecut action is addressed by table number and note number for each individual part of each item.
A number of items aertain to areas where welds or configuration deviate from that slown on applicable design drawing.
The drawing requires one type of weld when, in fact, the actual weld was found to be some other type.
TVA has shown that even though welds were not in accordance with drawings in some cases, the welds were satisfactory J
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based on engineering calculations.
For the cases where welds were found to deviate from drawings, by TVA inspection or NRC inspection, TVA has issued Significant Condition Report (SCR) SQNCEB8606 to revise the drawings to reflect the "as-built" welds.
The SCR also addresses specification of the Quality Level on the drawings.
For drawings not covered by the SCR, Section 3 of Volume II of TVA's revised Nuclear Performance Plan for Sequoyah provides an action plan that includes reconciliation of "as constructed" and "as designed" drawings to achieve a single set of plant drawings and improvement in the design control program for Sequoyah when implemented (See Executive Summary to RII Report 50-327,328/86-33).
(1)
(Closed) Inspector Followup Item 327, 328/86-33-01, Pipe Weld Deficiencies.
l Table 1 Note 4 - The Weld documentation showed that a
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single weld material verification was performed by the quality control inspector.
Dual process welding procedure was required by the weld data sheet.
Welds 2 - AFDF-25AA and 2-AFDF-25BB:
Resolution of this problem for these two welds is addressed in TVA Discrepancy Report (DR) 86-03-065R.
Weld 1 - AFDF-38:
This weld was on original construction weld, welded and accepted October 29, 1977.
TVA Justification (Summary)
Field evaluation has been made to determine the welding process utilized for the cap pass.
The evaluation shows that the cap pass was made with shielded metal arc weld process with the stringer bead technique.
Weld 1-AFDF-38 is in agreement with its recorded
documentation.
The weld material identified on the fitup and cleanliness record (E70S3) is in agreement with the weld process specified for the root pass and field inspection has verified that the cap pass is in agreement with the specific process.
The program in effect at the time the work was performed required that the inspector record the filler material in the welder's possession.
The records indicates the welder had the proper material for the root pass.
The program did not explicitly require the identification of additional material.
The weld was re-inspected by TVA (See TVA Welding Project Phase II Report) and by NRC and found to be acceptable.
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This item is closed based on:
TVA Justification Even though the weld record does not identify the weld material for the SMA portion of weld, it appears that the procedure in effect at the time was met and that the correct welding material was used.
Table 1, Note 5 - Visual inspection of the weld revealed
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that the SMAW process was used.
Weld data record shows incorrectly that the GTAW process was used.
TVA Justiff t.ation (Summary)
The weld in question was an original construction
weld, welded and accepted October 22, 1977.
The records for weld 1-AFDF-40 identify the GTAW process as being used for the complete weld. A field inspection has determined that the cap pass was made by the shielded metal arc process.
The fitup and cleanliness record shows that the proper material (70S3) for the specified procedure was in the welders possession at the time of the fitup inspection. Since this weld is adjacent to a valve, TVA disassembled the valve and verified the GTAW process was used for the root pass.
An extensive records search has been made to determine
if any modification or maintenance changes to the welds have been made that would cause the weld to not agree with the original record.
Evidence to indicate rework for this weld has not been found.
!.
The weld has been reinspected by TVA and the NRC and
is acceptable as reported in the Phase II Report (Welding Project Vol. 3).
The documentation discrepancy for weld 1-AFDF-40 is considered to be nonsignificant and of no consequence to the weld quality since acceptable SMAW procedures were available for use and visually, the weld cap appears to have been welded with an acceptable (carbon steel)
SMAW material.
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This item is closed based on:
TVA Justification
The problem appears to be a paper problem only.
Approved SMAW procedures were available for the weld and the weld cap appears to have been welded with a SMAW carbon steel material.
Table 1, Note 6 - Underfilled Weld.
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This item is closed based on review of Appendix 4.4 of TVA Welding Project Sequoyah Phase II Report and review of calculations (See Paragraph 5.e above).
Table 1, Note 7 - One of the eight inspected hanger pads
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was found to have a missing hard stamped material heat number. The heat number verification sign off was noted on the weld data record with no notation as to the number of pads checked.
TVAJustification-(Summary)
Applicable procedure SQN Proc. M-7, required traceability of heat numbers of attachments only until installed.
The weld history record indicates that the " Material Release" hold point was specified and signed off by the inspector; heat number 7469628 was listed for component 1-CCH-675.
This indicates that the inspector did identify the eight lugs prior to assembly to the process line.
The most likely explanation for the one lug not having visible marking is that the inspector verified the component identification and heat numbers on the lug prior to fitup on the process line.
After this verification, the lugs were fitup to the process line with the die stamped surface against the process line for the one lug.
The inspector visually observed the lugs and the one lug without marking appears visually to be identical to the other seven lugs.
The paint was scraped from the lug and the painted mark number appeared on the lug.
This item is closed based on TVA's justification and visual inspection of the lugs.
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(2)
(Closed) Inspector Followup Item 327,328/86-33-02, Pipe Support Weld Deficiencies Table 2, Note 6 - Vertical location of Support in error by 3'-6" when compared with drawing.
This item is closed based on SCR SQNCEB8606.
(3)
(Closed) Inspector Followup Item 327, 328/86-33-03, Instrument Tubing Support Weld Deficiencies Table 4, Note 1 - The weld contained undercut, slag,
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overlap and incomplete fusion.
This item is closed based on review of TVA Welding Project Sequoyah Nuclear Plant Phase II Review and Program Results (Phase II Welding Report) and review of TVA calculations (See RII Report 50-327,328/86-59).
Table 4, Note 2 - The weld was underfilled or undersized.
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This item is closed based on review of TVA calculations (See RII Report 50-327,328/86-59).
Table 4, Note 3 - The drawings specified in two places that
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the connection between pieces of square tubing be full-penetration square groove butt welds.
This type of joint is defined as a K, Y, or T connection by the AWS D1.1 structural welding code.
The AWS D1.1 Code requires a special qualification test for welders who weld on T, Y, and K connections.
The review of a sample of welder
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qualifications indicated that some welders were qualified
on a plate using backing strap which does not qualify them i
to weld on a T, Y, and K connections in structural steel tubing.
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i TVA Justification -
i T. K and Y connections involve intersecting elements
!
of tubular structures.
Design and fabrication requirements for such structures are addressed in Chapter 10 of the AWS D1.1 Code.
This chapter currently contains requirements for both complete and
partial penetration groove welds in tubular members.
l Complete penetration T, K and Y connections are unique j
among the prequalified joints of the D1.1 Code in that they permit design credit for a complete penetration a
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>
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>
weld without the use of a backing strap or backgouging and back-welding.
Because of the difficulty of making such. welds, the code requires a special rigorous welder performance test.
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TVA does not design for complete penetration T, K and Y connections and, therefore, does not give the special welder performance qualification test for these welds.
TVA does design for partial penetration groove welds and fillet welds in square and recta'ngular (box section) tubing for which welders are qualified by standard plate qualification tests.
In accordance with TVA SCR SQNCEB8606, TVA is revising weld symbols on drawings to clearly show the type weld required and that full penetration welds were not intended.
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This item is closed based on:
TVA Justification For the editions of AWS applicable to Sequoyah (1969 and 1972), the qualification requirements for the type welds at Sequoyah, i.e. welds between square tubing of the same size where two sides of the weld are fillets and the other two sides a partial penetration weld similar to a partial penetration flare bevel weld, are not clear.
In later editions of AWS, some clarification has been made, but it is still not clear that the restrictive T, K,.Y qualification test applies to the type welds at Sequoyah.
a Welders at Sequoyah were qualified on full penetration
grove welds in plates.
Practically, this appears to be adequate for the type welds at Sequoyah.
Table 4. Note 4 - The support was constructed in accordance
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with Support Variance Sheet 51-19-221 which allowed a gusset to be added so that the support could be installed at an angle to the baseplate.
Calculations for this variance were not found and new calculations have been requested.
This item is closed based on review of calculations (See paragraph 5.b.above).
Table 4, Note 5 - The weld had an unacceptable crater and
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clustered porosity.
This item is closed based on review of calculations (See RII Report 50-327,328/86-59).
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Table.4, Note 6 - The support was constructed in accordance with drawing 47A053-10A.
The drawing specified that the connection between the unistrut and the supporting steel be
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a full penetration square butt weld. The drawing symbol is a
Y incorrect because in this case it is not possible to make a square butt weld.
A This item is closed based on TVA SCR SQNCEB8606.
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Table 4, Note 7 - The length of intermittent welds were too
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m short, but the welds were closely spaced.
$
T This item is closed based on review of calculations (See RII Report 50-327,328/86-59).
(4)
(Closed) Inspector Followup Item 327, 328/86-33-04, Electrical Support Weld Deficiencies Table 5, Note 1 - The drawing did not specify which
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material and weld quality level requirements apply.
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This item is closed based on:
There was no evidence of the incorrect quality level
$
being used.
TVA SCR SQNCEB8606 requires that the quality level be added to the drawing in question.
"
TVA's letter, dated January 30, 1987, in response to NRC draft Safety Evaluation Report, states that quality levels will be specified on all new or revised
.s drawings.
Table 5, Note 2 - The stitch weld was deficient with
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respect to the requirements stated on the drawing. Drawing required 2 on 6 weld, while the actual weld was 2 inches long on 8-inch centers.
No calculations were made to evaluate the deficient stitch weld.
This item is closed based on review of calculations made after report 86-33 (See RII Report 50-327,328/86-59).
Table 5, flote 3 - The drawing symbols do not match the
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actual weld configuration.
This item is closed based on TVA SCR SQNCEB8606.
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Table 5, Note 4 - No weld details were found for the dust
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Covers.
This item is closed based on TVA SCR SQNCEB8506.
Table 5, Note 6 - Undersized weld found on floor
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connection. No calculations have been made to evaluate the undersized weld.
This item is closed based on review of calculations (See paragraph 5.d. above).
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Table 5, Note 7 - Variance drawing does not show one cross member in side view.
This item is closed based on review of calculations (See RII Report 50-327,328/86-59) and TVA SCR SQNCEB8606.
(5)
(Closed) Inspector Followup Item 327,328/86-33-05, HVAC Support Weld Deficiencies
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Table 6, Note 1 - TVA's reinspection rejected a number of welds for being undersized fillets or underfilled flare welds. Also, a number of welds were identified as missing.
In some cases the weld specified on the drawing could not have been made because of the joint design.
Some weld symbols on the drawing did not show weld sizes.
The NRC NDE van inspection identified similar problems.
A number of welds were considered to be inaccessible by TVA.
The structure was inspected by the NRC NDE van team and many of the welds identified as inaccessible were inspected by the NRC. Weld surface problems such as craters, weld profiles, undercut, weld surface slag, and one missing weld were identified in addition to the problems identified by TVA.
During the current inspection (86-33), the NRC inspectors noted that the drawing and variance were not clear as to the weld size required for weld "A".
The weld size was accepted by TVA inspectors with a note that no weld size was specified on the drawing.
Engineering accepted the weld by calculations based on the fact that only a 0.050 inch weld size is needed.
The fitup gap for one weld was greater than the maximum allowed 3/16-inch gap.
This item is closed based on a review of calculations (See paragraph 5.a. above and RII Report 50-327,328/86-59)and TVA SCR SQNCEB8606.
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Table 6, Note 2 - TVA's reinspection rejected a number of fillet welds for being undersized.
The NRC NDE van inspection team did not inspect this support.
During the
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current-inspection (86-33), the NRC team noted that for pad-to-beam welds, the variance drawing was poor and did not specify where the 3/16 inch fillet was to be welded.
The pads are 4" wide welded on 4" wide beams.
Therefore, the 3/16 inch fillet welds must be welded across the beam even though the variance drawing was not clear.
Those welds were undersized.
The seams between the edges of the pads and the beams were seal welded even though the variance drawing did not show the welds.
This item is closed based on review of calculations (See RII Report 50-327,328/86-59) and TVA SCR SQNCEB8606.
Table 6, Note 3 - TVA's reinspection rejected a number of
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fillet welds for being undersize.
The NRC NDE van team inspection identified similar problems. During the current inspection (86-33), the NRC team noted that the variance drawing was very poor and did not detail the full-penetration weld for weld "A-10."
This item is closed based on review of calculations (See NRC Report 50-327,328/86-33) and TVA SCR SQNCEB8606.
Table 6, Note 4 - This support was not a part of TVA's
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reinspection sample. The NRC NDE van inspection identified that the spacing on skip fillet welds did not meet drawing requirements.
During the current inspection (86-33), the NRC team noted that the welding symbols on the variance drawings for the square-tube-to-square-tube welds did not agree with the type of welds that are in place.
The drawings are not clear whether fillet welds or flare bevel welds are required.
The variance drawings also were found to be of poor quality.
Only support number 824 was inspected.
This item is closed based on review of calculations (see RII Report 50-327,328/86-59) and TVA SCR SQNCEB8606.
Table 6, Note 5 - This was not a part of TVA's reinspection
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sample.
This item was inspected by the NRC NDE van team.
During the current inspection (86-33), the NRC inspectors noted that the drawing welding symbol for the corner joints connecting the square tubing is incorrect.
The symbol shows a flare bevel all around.
It appears that a partial penetration weld was used on top and bottom, a fillet weld on the inside, and a seal weld on the end.
This item is closed based on TVA SCR SQNCEB8606.
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(6) (Closed) Inspector Followup Item 327, 328/86-33-06, Welder Qualification Deficiencies Table 7, Note 1 - Welder qualification test record showed
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that a dual process GTAW/SMAW was used to weld a 7" diameter A-106,1" thick test coupon.
The record also showed that this test was used to qualify the welder to weld from 3/16 inch to unlimited thickness.
There is no record of deposit thickness.
Above is not in compliance with Section IX of the ASME Code.
TVA Justification -
G-29M Process Specification 1.M.1.2 (General Welding Procedure Specification), paragraph 17.1, defines the gas tungsten arc root pass of dual process walds as being a minimum of two layers and a maximum of 3/8".
This definition is applicable to qualification testing and production welding.
A nominal value of 3/16" may reasonably be assigned for the thickness of the gas tungsten arc process; the remaining thickness would be that of the other process.
Note that all dual process Performance Qualification Tests were deleted from G-29M in General Revision No. 18, dated June 12, 1981.
This item is closed based on:
TVA justification An interview by the inspector of a previous weld test shop supervisor (supervisor in the 1970s) revealed that the common practice for dual process qualification was to weld two layers with the GTA process.
Therefore, TVA's assignment of 3/16" for the GTA process is reasonable.
Assuming 3/16" thickness for the GTA process, for the 1" test coupon in question, 13/16" thickness would remain for the SMA process for unlimited thickness qualification for that process.
Practically, whether the thickness of the SMA portion of the test coupon was 5/8" (allowed by TVA procedures) or 3/4" (required by code for unlimited thickness qualification), is of little significance in determining a welders ability.
As noted in the TVA justification, as of June 12, 1981, dual process qualification were no longer allowed by Process Specification G29M.
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Table 7, Note 2 - The required visual examination of the test
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coupon was not recorded on the qualification test record.
This item is closed based on:
The applicable editions (1969 and 1972 per the FSAR) of AWS Welding Standard did not require visual inspection of plate tests.
Based on an interview with a previous TVA Weld Test Supervisor (Supervisor in 1970's), standard practice in the test shop was for the test shop supervisor to visually inspect the welder qualification test coupon during welding and in the completed condition.
Certification on the test record that test welds were prepared, welded, and tested in accordance with the requirements of AWS D1.0 code, serve as documentation for satisfactory completion of activities mandated by the code.
(7)
(Closed) Inspector Follow Item 327, 328/86-33-07, Welding Procedure Deficiencies.
Table 8, Note 2 - WPS qualification for impact tested application is not in compliance with ASME Section IX of the Code concerning separate qualification requirements for P-1 Group 1 and P-1 Group 2 materials.
TVA Justification -
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Procedure GT-SM11-0-38, prior to Revision 8, was supported by qualification tests performed on P-No.1, Group 1 base materials.
Revision 8 of the procedure incorporated, by reference, procedure qualification test GT-SM11-0-3C which was performed on P-No. 1, Group 2 material. With Revision 8, Procedure GT-SM11-0-3B was, therefore, qualified to weld P-No. 1, Groups 1 and 2 material on impact tested applications.
Similarly, procedure SM11-B-3, was originally supported by qualification tests performed on P-NO.1, Group 2 material and was later revised (R7) to reference qualification tests performed on P-No. 1, Group 1 material.
It should be noted that during SQN construction, assignment of welding procedures for components / piping under the jurisdiction of the B31.7 Code was made by Engineering (Knoxville) via controlled drawings. Assignment of welding procedures for specific weld joints was based upon l
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l applicable requirements for preheat, post-weld heat treatment, material type, thickness, impact test requirements etc.
This system effectively assured that appropriately qualified procedures were utilized.
It should also be noted that the mechanical component / piping codes of record for SQN (831.7 1969 + 1970 Addenda and B31.1 1967 ed.)
predate the subdivision of P-No.1 materials into sub-groups which occurred in the 1974 edition of Section IX.
There is no requirement in Section IX or the Codes of record that would require backfit/requalification of procedures to accommodate this particular change in Section IX.
This item is closed based on TVA's justification.
(8)
(Closed) Inspector Followup Item 327, 328/86-33-08, Weld Filler Material Certification Deficiencies.
Table 9,
Note 1 The TVA PF-1019, Revision 2,
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specification requires mechanical test data after post-weld heat treatment (PWHT).
The record shows no test data for yield strength and reduction of area of the material.
TVA Justification - The requirement of ASME Section III is that the tensile strength of the test specimen (when tensile tests are required) meet the requirements of the SFA Specification.
Although yield strength, percentage elongation, and percentage reduction of area are commonly reported, the omission of these latter properties is not considered a technical or code compliance issue.
This item is closed based on:
TVA Justification - ASME Section III is not clear relative to requirements for reporting yield strength, elongation, and reduction in area when testing for tensile strength.
Code interpretation 111-1-78-151 tends to support TVA's interpretation.
The SQN piping Codes of record (B 31.7, 1969 plus 1970 addenda and 831.1,1967) only require material to the SFA specifications.
Specific test are not specified to certify the welding material.
Based on review in the past of numerous test reports for heats of E70S-3 materials with chemistry and tensile strength similar to that of the material in question, it is unlikely that the yield strength, elongation and reduction in area do not meet SFA values.
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Table 9, Note 3 - The record shows tensile test values to
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be less than those specified by the ASME SFA 5.18 specification.
This note applies to two heats (422C3841 and 432C1271) of E-70S-3 Welding Material.
TVA Justification -
The CMTR for Ht. No. 422C3841 is annotated and initialed to indicate that material was not received at SQN.
(The inspector noted that if notes to Table 3 in SFA 5.18 (1971 Ed.) are considered, the results for this material meet SFA 5.18).
For Ht. No. 432C1271 -
Physical test data from an all weld metal tensile specimen made from the subject material and tested after post-weld heat treatment (PWHT) of 1150 F for six hours indicates a tensile strength of 67900 psi.
No test data is available for this material in the as-welded condition.
The mechanical component / piping codes of record for SQN (B31.7.1969 with 1970 addenda and B31.1 1967 Ed.)
require that welding materials comply with ASME Section IX.
They do not require physical test data for each heat and lot of welding material.
Section IX, in turn, references standard SFA filler metal specifications.
For the subject material (E70S-3, Ht. No 432C1271) the applicable specification is SFA5.18.
This specification does not require or provide criteria values for weld metal tensile tests in other than the as-welded condition.
Murex letter to TVA, dated September 24, 1974, states that the subject material meets the requirements of SFA5.18.
On the basis of this letter, the material is considered to meet code requirements applicable to SQN.
To address the probable minimum tensile strength in the as-welded condition, a review of other test reports giving both as-welded and PWHT values for other heats of similar material was performed. Tensile test results of nine heats of Murex E70S-3 (Murex Type 1316) were compared in the as-welded and PWHT condition.
Results indicate a reduction in the tensile strength of 6000 to 10,000 psi for the PWHT J
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samples.
Therefore, it can be reasonable assumed that the tensile strength (67,900 psi after PWHT) of the subject material would equal or exceed 70,000 psi in the as welded condition.
This item is closed based on:
TVA's justification The codes and material specifications applicable at
the time of material procurement do not provide PWHT acceptance criteria.
It appears that if results were available, material would meet as welded tensile strength requirements of SFA 5.18.
(9)
(Closed) Inspector Followup Item 327, 328/86-33-09, Base Material Certification Deficiencies.
Table 10, Note 1 - The recorded tensile strength was below the required minimum for the material.
For Mk/Ht. No. 72C54-76081 Structural Shape, the vendor material test report recorded an ultimate tensile strength of 57,640 psi versus a specification requirement of 58,000 psi. TVA retrieved a memorandum dated February 24, 1972, from R. C. Miles to files with Engineering justification for the use of the material in items the material was procured for.
This item is closed based on TVA Engineering justification, dated February 24, 1972.
c.
(0 pen) Inspector Followup Item 327, 328/86-59-02, Clarification of Pump Testing Requirements.
This item questioned the method of insuring that paragraphs IWP-4220 (pressure tap construction)
and IWP-4520 (instruments to measure vibration) of ASME Section XI are met.
TVA reviewed Typical drawings 47A7, 47A6 and 47A5 covering pressure taps designs and found that all pressure taps meet IWP-4220.
Therefore, this portion of the item has been resolved.
Procedure TI-96.1, Vibration Observation - Pumps and Motors, which identifies vibration instruments consistent with paragraph IWP-4520, had been written and was in the TVA review cycle. This item is open pending review of the procedure.
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