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Category:INSPECTION REPORT
MONTHYEARIR 05000483/19990101999-10-14014 October 1999 Insp Rept 50-483/99-10 on 990913-16.No Violations Noted. Major Areas Inspected:Plant Support Re Biennial Exercise of Emergency Plan & Procedures IR 05000483/19990111999-09-22022 September 1999 Insp Rept 50-483/99-11 on 990812-20.No Violations Noted. Major Areas Inspected:Operations,Maint & Engineering IR 05000483/19990081999-09-13013 September 1999 Insp Rept 50-483/99-08 on 990725-0904.Noncited Violations Noted.Major Areas Inspected:Operations,Maintenance, Engineering & Plant Support IR 05000483/19990071999-09-10010 September 1999 Insp Rept 50-483/99-07 on 990809-13.No Violations Noted. Major Areas Inspected:Licensed Operator Requalification Program to Determine Whether Program Incorporated Appropriate Requirements for Evaluating Operators IR 05000483/19990061999-08-13013 August 1999 Insp Rept 50-483/99-06 on 990613-0724.One Severity Level 4 Violation Noted & Being Treated as Ncv.Major Areas Inspected:Operations,Maint & Plant Support IR 05000483/19990051999-06-25025 June 1999 Insp Rept 50-483/99-05 on 990502-0612.Two Violations Noted & Being Treated as Noncited Violations.Major Areas Inspected: Operations,Maint,Engineering & Plant Support IR 05000483/19990031999-05-19019 May 1999 Insp Rept 50-483/99-03 on 990321-0501.Noncited Violation Noted.Major Areas Inspected:Operations,Maintenance, Engineering & Plant Support IR 05000483/19990011999-04-0505 April 1999 Insp Rept 50-483/99-01 on 990207-0320.One Violation Occurred & Being Treated as Noncited Violation.Major Areas Inspected: Operations,Maint,Engineering & Plant Support IR 05000483/19980181998-12-0404 December 1998 Insp Rept 50-483/98-18 on 980914-1002.Violations Noted. Major Areas Inspected:Review of Design & Licensing Basis for Essential Service Water Sys,Associated Electrical Support Sys & Review of Program Implement 10CFR50.59 IR 05000483/19980221998-11-25025 November 1998 Insp Rept 50-483/98-22 on 980927-1114.No Violations Noted. Major Areas Inspected:Operations,Maintenance,Engineering & Plant Support IR 05000483/19980241998-11-25025 November 1998 Insp Rept 50-483/98-24 on 981026-30.Violation Noted.Major Areas Inspected:Licensee Implementation of NRC Approved Fire Protection Program IR 05000483/19980231998-10-28028 October 1998 Insp Rept 50-483/98-23 on 981013-15.No Violations Noted. Major Areas Inspected:Operational Status of License Emergency Preparedness Program Was Conducted IR 05000483/19980151998-10-26026 October 1998 Insp Rept 50-483/98-15 on 980706-10.No Violations Noted. Major Areas Inspected:Guidance of Temporary Instruction 2515/137, Insp of Medium-Voltage & Low-Voltage Power Circuit Breakers IR 05000483/19980201998-10-15015 October 1998 Insp Rept 50-483/98-20 on 980817-0904.No Violations Noted. Major Areas Inspected:Operations & Maint IR 05000483/19980211998-10-0909 October 1998 Insp Rept 50-483/98-21 on 980816-0926.No Violations Noted. Major Areas Inspected:Operations,Maint & Engineering IR 05000483/19980191998-09-29029 September 1998 Insp Rept 50-483/98-19 on 980914-18.No Violations Noted. Major Areas Inspected:Plant Support IR 05000483/19980121998-08-21021 August 1998 Insp Rept 50-483/98-12 on 980705-0815.No Violations Noted. Major Areas Inspected:Operations,Maint & Plant Support IR 05000483/19980171998-08-14014 August 1998 Insp Rept 50-483/98-17 on 980803-07.Violations Noted.Major Areas Inspected:Implementation of Solid Radioactive Waste Mgt & Radioactive Matls Transportation Program IR 05000483/19980161998-08-0606 August 1998 Insp Rept 50-483/98-16 on 980713-17.No Violations Noted. Major Areas Inspected:Plant Support IR 05000483/19980131998-07-29029 July 1998 Insp Rept 50-483/98-13 on 980714-17.Violation Noted.Major Areas Inspected:Engineering & Plant Support IR 05000483/19980141998-07-17017 July 1998 Insp Rept 50-483/98-14 on 980629-0702.No Violations Noted. Major Areas Inspected:Operational Status of Licensee Emergency Preparedness Program IR 05000483/19980111998-07-0808 July 1998 Insp Rept 50-483/98-11 on 980524-0704.No Violations Noted. Major Areas Inspected:Operations,Maint,Engineering & Plant Support IR 05000483/19980081998-06-0808 June 1998 Insp Rept 50-483/98-08 on 980412-0523.Violations Noted. Major Areas Inspected:Operation,Maint,Engineering & Plant Support IR 05000483/19980091998-05-19019 May 1998 Insp Rept 50-483/98-09 on 980428-30.No Violations Noted. Major Areas Inspected:Maint & Plant Support IR 05000483/19980071998-05-19019 May 1998 Insp Rept 50-483/98-07 on 980427-0501.Violations Noted.Major Areas Inspected:Radiation Protection Program Focussing on Refueling Outage Activities ML20247M2241998-05-19019 May 1998 Insp Rept 50-483/98-10 on 980428-30.No Violations Noted. Major Areas Inspected:Contingency Plan Developed in Response to Insp Findings in NRC Insp Rept 50-483/98-06 W/Special Emphasis on Training Process Used to Qualify People for Er IR 05000483/19980051998-05-0808 May 1998 Insp Rept 50-483/98-05 on 980413-0501.No Violations Noted. Major Areas Inspected:Maintenance,Engineering & Plant Support ML20217F4881998-04-22022 April 1998 Insp Rept 50-483/98-06 on 980324-26.Violations Noted.Major Areas Inspected:Plant Support IR 05000483/19980031998-04-17017 April 1998 Insp Rept 50-483/98-03 on 980301-0411.No Violations Noted. Major Areas Inspected:Operations,Maint & Engineering IR 05000483/19980041998-04-17017 April 1998 Insp Rept 50-483/98-04 on 980406-10.No Violations Noted. Major Areas Inspected:Licensee Physical Security Program IR 05000483/19980021998-03-26026 March 1998 Insp Rept 50-483/98-02 on 980202-06.Violation Noted.Major Areas Inspected:Maint,Engineering Re Bldg Emergency Filter Sys Adsorber IR 05000483/19980011998-03-0909 March 1998 Insp Rept 50-483/98-01 on 980118-0228.Violations Noted. Major Areas Inspected:Operations,Engineering & Plant Support IR 05000483/19970211998-01-27027 January 1998 Insp Rept 50-483/97-21 on 971207-980117.No Violations Noted. Major Areas Inspected:Operation,Maint,Engineering & Plant Support IR 05000483/19980251998-01-12012 January 1998 Insp Rept 50-483/98-25 on 981115-1226.Violations Noted. Major Areas Inspected:Operations,Maint,Engineering & Plant Support,Including Health Physics & Security IR 05000483/19970191997-12-18018 December 1997 Insp Rept 50-483/97-19 on 971117-1211.No Violations Noted. Major Areas Inspected:Engineering IR 05000483/19970201997-12-16016 December 1997 Insp Rept 50-483/97-20 on 971026-1206.Violations Noted. Major Areas Inspected:Operation,Maint,Engineering & Plant Support IR 05000483/19970181997-11-12012 November 1997 Insp Rept 50-483/97-18 on 971027-31.No Violations Noted. Major Areas Inspected:Access Authorization,Alarm Stations, Communications,Access Control of Personnel,Packages & Vehicles,Assessment Aids & Security Plans IR 05000483/19970171997-11-12012 November 1997 Insp Rept 50-483/97-17 on 970914-1025.Violations Noted.Major Areas Inspected:Operations,Maint,Engineering & Plant Support IR 05000483/19970161997-10-0707 October 1997 Insp Rept 50-483/97-16 on 970915-19.No Violations Noted. Major Areas Inspected:External & Internal Exposure Controls, Dose Assessment & Records,Controls of Radioactive Matl & Contamination & Surveying & Monitoring IR 05000483/19970151997-09-22022 September 1997 Insp Rept 50-483/97-15 on 970802-0913.No Violations Noted. Major Areas Inspected:Operations,Maint,Engineering & Plant Support IR 05000483/19970131997-09-0404 September 1997 Insp Rept 50-483/97-13 on 970811-15.No Violations Noted. Major Areas Inspected:Licensee Performance & Capabilities During full-scale,biennial Exercise of Emergency Plan & Implementing Procedures IR 05000483/19970141997-08-0606 August 1997 Insp Rept 50-483/97-14 on 970622-0802.No Violations Noted. Major Areas Inspected:Operations,Maint & Engineering ML20141E4791997-06-26026 June 1997 Insp Rept 50-483/97-05 on 970210-14 & 24-28.Violations Noted.Major Areas Inspected:Engineering IR 05000483/19970061997-06-20020 June 1997 Insp Rept 50-483/97-06 on 970519-23.No Violations Noted. Major Areas Inspected:Licensed Operator Requalification Program IR 05000483/19970081997-05-20020 May 1997 Insp Rept 50-483/97-08 on 970317-0404.No Violations Noted. Major Areas Inspected:Operations,Maint,Engineering & Plant Support IR 05000483/19970101997-05-19019 May 1997 Insp Rept 50-483/97-10 on 970330-0510.No Violations Noted. Major Areas Inspected:Licensee Operations,Maint,Engineering & Plant Support IR 05000483/19970091997-05-0909 May 1997 Partially Withheld Insp Rept 50-483/97-09 on 970422-25.No Violations Noted.Major Areas Inspected:Licensee Implementation of Land Vehicle Control Measures Implemented IAW 10CFR73, Physical Protection of Plants & Matl IR 05000483/19970071997-04-0808 April 1997 Insp Rept 50-483/97-07 on 970216-0329.No Violations Noted. Major Areas Inspected:Operations,Maint,Engineering & Plant Support IR 05000483/19970011997-03-26026 March 1997 Insp Rept 50-483/97-01 on 970224-28.No Violations Noted. Major Areas Inspected:Competency of Six SRO and Five RO Applicants for Issuance of Operating Licenses IR 05000483/19970041997-02-28028 February 1997 Insp Rept 50-483/97-04 on 970127-31.No Violations Noted. Major Areas Inspected:Routine Insp Reviewed Program to Maintain Occupational Exposures Alara,Training & Qualifications of Radiation Protection Organizations 1999-09-22
[Table view] Category:NRC-GENERATED
MONTHYEARIR 05000483/19990101999-10-14014 October 1999 Insp Rept 50-483/99-10 on 990913-16.No Violations Noted. Major Areas Inspected:Plant Support Re Biennial Exercise of Emergency Plan & Procedures IR 05000483/19990111999-09-22022 September 1999 Insp Rept 50-483/99-11 on 990812-20.No Violations Noted. Major Areas Inspected:Operations,Maint & Engineering IR 05000483/19990081999-09-13013 September 1999 Insp Rept 50-483/99-08 on 990725-0904.Noncited Violations Noted.Major Areas Inspected:Operations,Maintenance, Engineering & Plant Support IR 05000483/19990071999-09-10010 September 1999 Insp Rept 50-483/99-07 on 990809-13.No Violations Noted. Major Areas Inspected:Licensed Operator Requalification Program to Determine Whether Program Incorporated Appropriate Requirements for Evaluating Operators IR 05000483/19990061999-08-13013 August 1999 Insp Rept 50-483/99-06 on 990613-0724.One Severity Level 4 Violation Noted & Being Treated as Ncv.Major Areas Inspected:Operations,Maint & Plant Support IR 05000483/19990051999-06-25025 June 1999 Insp Rept 50-483/99-05 on 990502-0612.Two Violations Noted & Being Treated as Noncited Violations.Major Areas Inspected: Operations,Maint,Engineering & Plant Support IR 05000483/19990031999-05-19019 May 1999 Insp Rept 50-483/99-03 on 990321-0501.Noncited Violation Noted.Major Areas Inspected:Operations,Maintenance, Engineering & Plant Support IR 05000483/19990011999-04-0505 April 1999 Insp Rept 50-483/99-01 on 990207-0320.One Violation Occurred & Being Treated as Noncited Violation.Major Areas Inspected: Operations,Maint,Engineering & Plant Support IR 05000483/19980181998-12-0404 December 1998 Insp Rept 50-483/98-18 on 980914-1002.Violations Noted. Major Areas Inspected:Review of Design & Licensing Basis for Essential Service Water Sys,Associated Electrical Support Sys & Review of Program Implement 10CFR50.59 IR 05000483/19980221998-11-25025 November 1998 Insp Rept 50-483/98-22 on 980927-1114.No Violations Noted. Major Areas Inspected:Operations,Maintenance,Engineering & Plant Support IR 05000483/19980241998-11-25025 November 1998 Insp Rept 50-483/98-24 on 981026-30.Violation Noted.Major Areas Inspected:Licensee Implementation of NRC Approved Fire Protection Program IR 05000483/19980231998-10-28028 October 1998 Insp Rept 50-483/98-23 on 981013-15.No Violations Noted. Major Areas Inspected:Operational Status of License Emergency Preparedness Program Was Conducted IR 05000483/19980151998-10-26026 October 1998 Insp Rept 50-483/98-15 on 980706-10.No Violations Noted. Major Areas Inspected:Guidance of Temporary Instruction 2515/137, Insp of Medium-Voltage & Low-Voltage Power Circuit Breakers IR 05000483/19980201998-10-15015 October 1998 Insp Rept 50-483/98-20 on 980817-0904.No Violations Noted. Major Areas Inspected:Operations & Maint IR 05000483/19980211998-10-0909 October 1998 Insp Rept 50-483/98-21 on 980816-0926.No Violations Noted. Major Areas Inspected:Operations,Maint & Engineering IR 05000483/19980191998-09-29029 September 1998 Insp Rept 50-483/98-19 on 980914-18.No Violations Noted. Major Areas Inspected:Plant Support IR 05000483/19980121998-08-21021 August 1998 Insp Rept 50-483/98-12 on 980705-0815.No Violations Noted. Major Areas Inspected:Operations,Maint & Plant Support IR 05000483/19980171998-08-14014 August 1998 Insp Rept 50-483/98-17 on 980803-07.Violations Noted.Major Areas Inspected:Implementation of Solid Radioactive Waste Mgt & Radioactive Matls Transportation Program IR 05000483/19980161998-08-0606 August 1998 Insp Rept 50-483/98-16 on 980713-17.No Violations Noted. Major Areas Inspected:Plant Support IR 05000483/19980131998-07-29029 July 1998 Insp Rept 50-483/98-13 on 980714-17.Violation Noted.Major Areas Inspected:Engineering & Plant Support IR 05000483/19980141998-07-17017 July 1998 Insp Rept 50-483/98-14 on 980629-0702.No Violations Noted. Major Areas Inspected:Operational Status of Licensee Emergency Preparedness Program IR 05000483/19980111998-07-0808 July 1998 Insp Rept 50-483/98-11 on 980524-0704.No Violations Noted. Major Areas Inspected:Operations,Maint,Engineering & Plant Support IR 05000483/19980081998-06-0808 June 1998 Insp Rept 50-483/98-08 on 980412-0523.Violations Noted. Major Areas Inspected:Operation,Maint,Engineering & Plant Support IR 05000483/19980091998-05-19019 May 1998 Insp Rept 50-483/98-09 on 980428-30.No Violations Noted. Major Areas Inspected:Maint & Plant Support IR 05000483/19980071998-05-19019 May 1998 Insp Rept 50-483/98-07 on 980427-0501.Violations Noted.Major Areas Inspected:Radiation Protection Program Focussing on Refueling Outage Activities ML20247M2241998-05-19019 May 1998 Insp Rept 50-483/98-10 on 980428-30.No Violations Noted. Major Areas Inspected:Contingency Plan Developed in Response to Insp Findings in NRC Insp Rept 50-483/98-06 W/Special Emphasis on Training Process Used to Qualify People for Er IR 05000483/19980051998-05-0808 May 1998 Insp Rept 50-483/98-05 on 980413-0501.No Violations Noted. Major Areas Inspected:Maintenance,Engineering & Plant Support ML20217F4881998-04-22022 April 1998 Insp Rept 50-483/98-06 on 980324-26.Violations Noted.Major Areas Inspected:Plant Support IR 05000483/19980031998-04-17017 April 1998 Insp Rept 50-483/98-03 on 980301-0411.No Violations Noted. Major Areas Inspected:Operations,Maint & Engineering IR 05000483/19980041998-04-17017 April 1998 Insp Rept 50-483/98-04 on 980406-10.No Violations Noted. Major Areas Inspected:Licensee Physical Security Program IR 05000483/19980021998-03-26026 March 1998 Insp Rept 50-483/98-02 on 980202-06.Violation Noted.Major Areas Inspected:Maint,Engineering Re Bldg Emergency Filter Sys Adsorber IR 05000483/19980011998-03-0909 March 1998 Insp Rept 50-483/98-01 on 980118-0228.Violations Noted. Major Areas Inspected:Operations,Engineering & Plant Support IR 05000483/19970211998-01-27027 January 1998 Insp Rept 50-483/97-21 on 971207-980117.No Violations Noted. Major Areas Inspected:Operation,Maint,Engineering & Plant Support IR 05000483/19980251998-01-12012 January 1998 Insp Rept 50-483/98-25 on 981115-1226.Violations Noted. Major Areas Inspected:Operations,Maint,Engineering & Plant Support,Including Health Physics & Security IR 05000483/19970191997-12-18018 December 1997 Insp Rept 50-483/97-19 on 971117-1211.No Violations Noted. Major Areas Inspected:Engineering IR 05000483/19970201997-12-16016 December 1997 Insp Rept 50-483/97-20 on 971026-1206.Violations Noted. Major Areas Inspected:Operation,Maint,Engineering & Plant Support IR 05000483/19970181997-11-12012 November 1997 Insp Rept 50-483/97-18 on 971027-31.No Violations Noted. Major Areas Inspected:Access Authorization,Alarm Stations, Communications,Access Control of Personnel,Packages & Vehicles,Assessment Aids & Security Plans IR 05000483/19970171997-11-12012 November 1997 Insp Rept 50-483/97-17 on 970914-1025.Violations Noted.Major Areas Inspected:Operations,Maint,Engineering & Plant Support IR 05000483/19970161997-10-0707 October 1997 Insp Rept 50-483/97-16 on 970915-19.No Violations Noted. Major Areas Inspected:External & Internal Exposure Controls, Dose Assessment & Records,Controls of Radioactive Matl & Contamination & Surveying & Monitoring IR 05000483/19970151997-09-22022 September 1997 Insp Rept 50-483/97-15 on 970802-0913.No Violations Noted. Major Areas Inspected:Operations,Maint,Engineering & Plant Support IR 05000483/19970131997-09-0404 September 1997 Insp Rept 50-483/97-13 on 970811-15.No Violations Noted. Major Areas Inspected:Licensee Performance & Capabilities During full-scale,biennial Exercise of Emergency Plan & Implementing Procedures IR 05000483/19970141997-08-0606 August 1997 Insp Rept 50-483/97-14 on 970622-0802.No Violations Noted. Major Areas Inspected:Operations,Maint & Engineering ML20141E4791997-06-26026 June 1997 Insp Rept 50-483/97-05 on 970210-14 & 24-28.Violations Noted.Major Areas Inspected:Engineering IR 05000483/19970061997-06-20020 June 1997 Insp Rept 50-483/97-06 on 970519-23.No Violations Noted. Major Areas Inspected:Licensed Operator Requalification Program IR 05000483/19970081997-05-20020 May 1997 Insp Rept 50-483/97-08 on 970317-0404.No Violations Noted. Major Areas Inspected:Operations,Maint,Engineering & Plant Support IR 05000483/19970101997-05-19019 May 1997 Insp Rept 50-483/97-10 on 970330-0510.No Violations Noted. Major Areas Inspected:Licensee Operations,Maint,Engineering & Plant Support IR 05000483/19970091997-05-0909 May 1997 Partially Withheld Insp Rept 50-483/97-09 on 970422-25.No Violations Noted.Major Areas Inspected:Licensee Implementation of Land Vehicle Control Measures Implemented IAW 10CFR73, Physical Protection of Plants & Matl IR 05000483/19970071997-04-0808 April 1997 Insp Rept 50-483/97-07 on 970216-0329.No Violations Noted. Major Areas Inspected:Operations,Maint,Engineering & Plant Support IR 05000483/19970011997-03-26026 March 1997 Insp Rept 50-483/97-01 on 970224-28.No Violations Noted. Major Areas Inspected:Competency of Six SRO and Five RO Applicants for Issuance of Operating Licenses IR 05000483/19970041997-02-28028 February 1997 Insp Rept 50-483/97-04 on 970127-31.No Violations Noted. Major Areas Inspected:Routine Insp Reviewed Program to Maintain Occupational Exposures Alara,Training & Qualifications of Radiation Protection Organizations 1999-09-22
[Table view] Category:TEXT-INSPECTION & AUDIT & I&E CIRCULARS
MONTHYEARIR 05000483/19990101999-10-14014 October 1999 Insp Rept 50-483/99-10 on 990913-16.No Violations Noted. Major Areas Inspected:Plant Support Re Biennial Exercise of Emergency Plan & Procedures IR 05000483/19990111999-09-22022 September 1999 Insp Rept 50-483/99-11 on 990812-20.No Violations Noted. Major Areas Inspected:Operations,Maint & Engineering IR 05000483/19990081999-09-13013 September 1999 Insp Rept 50-483/99-08 on 990725-0904.Noncited Violations Noted.Major Areas Inspected:Operations,Maintenance, Engineering & Plant Support IR 05000483/19990071999-09-10010 September 1999 Insp Rept 50-483/99-07 on 990809-13.No Violations Noted. Major Areas Inspected:Licensed Operator Requalification Program to Determine Whether Program Incorporated Appropriate Requirements for Evaluating Operators PNO-IV-99-035A, on 990810,heater Drain Line Pipe Rupture Occurred.Caused by Flow Accelerated Corrosion in Conjunction with Moisture Impingement.Licensee Has Completed Replacement of Damage Heater Drain Piping & Conducted Insps of Piping1999-08-18018 August 1999 PNO-IV-99-035A:on 990810,heater Drain Line Pipe Rupture Occurred.Caused by Flow Accelerated Corrosion in Conjunction with Moisture Impingement.Licensee Has Completed Replacement of Damage Heater Drain Piping & Conducted Insps of Piping IR 05000483/19990061999-08-13013 August 1999 Insp Rept 50-483/99-06 on 990613-0724.One Severity Level 4 Violation Noted & Being Treated as Ncv.Major Areas Inspected:Operations,Maint & Plant Support PNO-IV-99-035, on 990810,operators Initiated Manual Rt When High Pressure Heater Drain Line Ruptured in Turbine Bldg. Licensee Is Evaluating Options for Facilitating Repair & Restarting Plant.Region IV Will Conduct Special Insp1999-08-11011 August 1999 PNO-IV-99-035:on 990810,operators Initiated Manual Rt When High Pressure Heater Drain Line Ruptured in Turbine Bldg. Licensee Is Evaluating Options for Facilitating Repair & Restarting Plant.Region IV Will Conduct Special Insp IR 05000483/19990051999-06-25025 June 1999 Insp Rept 50-483/99-05 on 990502-0612.Two Violations Noted & Being Treated as Noncited Violations.Major Areas Inspected: Operations,Maint,Engineering & Plant Support IR 05000483/19990031999-05-19019 May 1999 Insp Rept 50-483/99-03 on 990321-0501.Noncited Violation Noted.Major Areas Inspected:Operations,Maintenance, Engineering & Plant Support IR 05000483/19993021999-05-0303 May 1999 Exam Rept 50-483/99-302 on 990416.Exam Results:Ro License Applicant Passed Retake Written Exam & Test Matl Adequate IR 05000483/19990011999-04-0505 April 1999 Insp Rept 50-483/99-01 on 990207-0320.One Violation Occurred & Being Treated as Noncited Violation.Major Areas Inspected: Operations,Maint,Engineering & Plant Support IR 05000483/19993011999-02-0202 February 1999 NRC Operator Licensing Exam Rept 50-483/99-301 for Exams Administered on 990111-15 ML20199D9261999-01-12012 January 1999 Notice of Violation from Insp on 981115-1226.Violation Noted:Licensee Failed to Perform Written Safety Evaluation, from 840611-980505 IR 05000483/19980181998-12-0404 December 1998 Insp Rept 50-483/98-18 on 980914-1002.Violations Noted. Major Areas Inspected:Review of Design & Licensing Basis for Essential Service Water Sys,Associated Electrical Support Sys & Review of Program Implement 10CFR50.59 ML20198A1231998-12-0404 December 1998 Notice of Violation from Insp on 980914-1002.Violation Noted:Listed Activities Affecting Quality Either Not Prescribed by Documented Instructions Appropriate to Circumstances or Not Accomplished with Procedures PNO-IV-98-059, on 981129,licensee Commenced Plant Shutdown from 100% Power to Mode 3 to Replace Fan Motor.Resident Inspector Monitored Portion of Plant Shutdown from Cr.Info Has Been Discussed with Licensee1998-11-30030 November 1998 PNO-IV-98-059:on 981129,licensee Commenced Plant Shutdown from 100% Power to Mode 3 to Replace Fan Motor.Resident Inspector Monitored Portion of Plant Shutdown from Cr.Info Has Been Discussed with Licensee IR 05000483/19980241998-11-25025 November 1998 Insp Rept 50-483/98-24 on 981026-30.Violation Noted.Major Areas Inspected:Licensee Implementation of NRC Approved Fire Protection Program ML20196G3471998-11-25025 November 1998 Notice of Violation from Insp on 981026-30.Violation Noted: on 981030,control Room Pantry Fire Door,Identified as Being Nonfunctional Without Fire Barrier Impairment Permit or Conpensatory Actions,As Required by Procedure APA-ZZ-00701 IR 05000483/19980221998-11-25025 November 1998 Insp Rept 50-483/98-22 on 980927-1114.No Violations Noted. Major Areas Inspected:Operations,Maintenance,Engineering & Plant Support IR 05000483/19980231998-10-28028 October 1998 Insp Rept 50-483/98-23 on 981013-15.No Violations Noted. Major Areas Inspected:Operational Status of License Emergency Preparedness Program Was Conducted IR 05000483/19980151998-10-26026 October 1998 Insp Rept 50-483/98-15 on 980706-10.No Violations Noted. Major Areas Inspected:Guidance of Temporary Instruction 2515/137, Insp of Medium-Voltage & Low-Voltage Power Circuit Breakers IR 05000483/19980201998-10-15015 October 1998 Insp Rept 50-483/98-20 on 980817-0904.No Violations Noted. Major Areas Inspected:Operations & Maint IR 05000483/19980211998-10-0909 October 1998 Insp Rept 50-483/98-21 on 980816-0926.No Violations Noted. Major Areas Inspected:Operations,Maint & Engineering IR 05000483/19980191998-09-29029 September 1998 Insp Rept 50-483/98-19 on 980914-18.No Violations Noted. Major Areas Inspected:Plant Support IR 05000483/19980121998-08-21021 August 1998 Insp Rept 50-483/98-12 on 980705-0815.No Violations Noted. Major Areas Inspected:Operations,Maint & Plant Support ML20237B8931998-08-14014 August 1998 Notice of Violation from Insp on 980803-07.Violation Noted: on 980804,inspector Noted Three Containers of Dry Active Waste Stored within 10 Feet of Permanent Structure IR 05000483/19980171998-08-14014 August 1998 Insp Rept 50-483/98-17 on 980803-07.Violations Noted.Major Areas Inspected:Implementation of Solid Radioactive Waste Mgt & Radioactive Matls Transportation Program IR 05000483/19980161998-08-0606 August 1998 Insp Rept 50-483/98-16 on 980713-17.No Violations Noted. Major Areas Inspected:Plant Support IR 05000483/19980131998-07-29029 July 1998 Insp Rept 50-483/98-13 on 980714-17.Violation Noted.Major Areas Inspected:Engineering & Plant Support ML20236V3251998-07-29029 July 1998 Notice of Violation from Insp on 980714-17.Violation Noted: Grinding Needle Gun Work Performed on 2,000 Ft Elevation of Cb Liner Floor Plate W/O Performing Surveys to Evaluate Concentration or Quantities of Radioactive Matl IR 05000483/19980141998-07-17017 July 1998 Insp Rept 50-483/98-14 on 980629-0702.No Violations Noted. Major Areas Inspected:Operational Status of Licensee Emergency Preparedness Program IR 05000483/19980111998-07-0808 July 1998 Insp Rept 50-483/98-11 on 980524-0704.No Violations Noted. Major Areas Inspected:Operations,Maint,Engineering & Plant Support ML20248L2621998-06-0808 June 1998 Notice of Violation from Insp on 980412-0523.Violation Noted:On 980419,workman Protection Assurance 26226 Was Inadequate to Ensure Safety During Work on Valve EJHV8804A IR 05000483/19980081998-06-0808 June 1998 Insp Rept 50-483/98-08 on 980412-0523.Violations Noted. Major Areas Inspected:Operation,Maint,Engineering & Plant Support IR 05000483/19980071998-05-19019 May 1998 Insp Rept 50-483/98-07 on 980427-0501.Violations Noted.Major Areas Inspected:Radiation Protection Program Focussing on Refueling Outage Activities ML20247M2241998-05-19019 May 1998 Insp Rept 50-483/98-10 on 980428-30.No Violations Noted. Major Areas Inspected:Contingency Plan Developed in Response to Insp Findings in NRC Insp Rept 50-483/98-06 W/Special Emphasis on Training Process Used to Qualify People for Er IR 05000483/19980091998-05-19019 May 1998 Insp Rept 50-483/98-09 on 980428-30.No Violations Noted. Major Areas Inspected:Maint & Plant Support IR 05000483/19980051998-05-0808 May 1998 Insp Rept 50-483/98-05 on 980413-0501.No Violations Noted. Major Areas Inspected:Maintenance,Engineering & Plant Support ML20217F4491998-04-22022 April 1998 Notice of Violation from Insp on 980324-26.Violations Noted: on 970529,licensee Made Changes to Emergency Plan W/O Commission Approval,That Decreased Effectiveness of Plan & Did Not Continue to Meet Planning Standard 50.47(b)(2) ML20217F4881998-04-22022 April 1998 Insp Rept 50-483/98-06 on 980324-26.Violations Noted.Major Areas Inspected:Plant Support IR 05000483/19980031998-04-17017 April 1998 Insp Rept 50-483/98-03 on 980301-0411.No Violations Noted. Major Areas Inspected:Operations,Maint & Engineering IR 05000483/19980041998-04-17017 April 1998 Insp Rept 50-483/98-04 on 980406-10.No Violations Noted. Major Areas Inspected:Licensee Physical Security Program ML20217F1921998-03-26026 March 1998 Notice of Violation from Insp on 980202-06.Violation Noted: Licensee Did Not Demonstrate That Either Train of Auxiliary Fuel Bldg Emergency Filter Sys Adsorbers Could Comply W/Ts 4.7.7.b.2 Until Charcoal from Each Train Was Replaced IR 05000483/19980021998-03-26026 March 1998 Insp Rept 50-483/98-02 on 980202-06.Violation Noted.Major Areas Inspected:Maint,Engineering Re Bldg Emergency Filter Sys Adsorber ML20216A7971998-03-0909 March 1998 Notice of Violation from Insp on 980118-0228.Violation Noted:On 980216,instructions to Work Authorization C612323 Did Not Provide Adequate Guidance for Concrete Core Drilling Work,As Result,Licensee Personnel Drilled Into Power Cable IR 05000483/19980011998-03-0909 March 1998 Insp Rept 50-483/98-01 on 980118-0228.Violations Noted. Major Areas Inspected:Operations,Engineering & Plant Support IR 05000483/19970211998-01-27027 January 1998 Insp Rept 50-483/97-21 on 971207-980117.No Violations Noted. Major Areas Inspected:Operation,Maint,Engineering & Plant Support IR 05000483/19980251998-01-12012 January 1998 Insp Rept 50-483/98-25 on 981115-1226.Violations Noted. Major Areas Inspected:Operations,Maint,Engineering & Plant Support,Including Health Physics & Security IR 05000483/19970191997-12-18018 December 1997 Insp Rept 50-483/97-19 on 971117-1211.No Violations Noted. Major Areas Inspected:Engineering IR 07100026/20120061997-12-16016 December 1997 Notice of Violation from Insp on 971026-1206.Violation Noted:Licensee Personnel Failed to Follow Documented Instructions During Preventive Maint Task to Record Differential Pressure Across Essential Svc Water Supply 1999-09-22
[Table view] |
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ENCLOSURE U.S. NUCLEAR REGULATORY COMMISSION
REGION IV
J Docket No.: 50-483 License No.: NPF-30 Report No.: 50-483/98-05 '
l Licensee: Union Electric Company i
l Facility: Callaway Plant
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Location: Junction Hwy. CC and Hwy. o Fulton, Missouri Dates: April 13 through May 1,1998 Inspector: 1. Bames, Technical Assistant Accompanied by: D. Kupperman, Argonne National Laboratory Approved By: Arthur T. Howell Ill, Director Division of Reactor Safety ATTACHMENT: Supplemental Information
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EXECUTIVE SUMMARY Callaway Plant l NRC Inspection Report 50-483/98-05 l
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Refueling Outage RF9 eddy current examination acquisition and analysis activities appeared effectively controlled, with good overall contractor performance noted
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(Section M1.1).
Engineering l .
The licensee appropriately responded to areas of weakness in the eddy current data analysis guidelines that were identified during a prior NRC inspection (Section E1.1).
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The use of the plus point probe was viewed as an indicator of management support for examination initiatives that would provide for early detection of degradation (Section E1.2).
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An increase in axial and circumferential flaw indications at the top-of-tube sheet location was noted during Refueling Outage RF8 (i.e.,108 tubes pluggad versus 30 tubes in Refueling Outage RF7). The total decreased to 65 tubes in Refueling Outage RF9 for
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top-of-tube sheet axial and circumferential flaw indications (Section E1.2).
Plant Suocort l
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The licensee has successfully maintained iron transport to the steam generators at low levels since adoption in 1993 of ethanolamines for pH control (Section R1.1).
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-3-Reoort Details Summarv of Plant Status l
The unit was in a refueling outage during the onsite portion of the inspectio . Maintenance M1 Conduct of Maintenance M1.1 Review of Tube Examination Activities
! Insoection Scone (50002)
l The inspector and NRC consultant performed limited observations of the acquisition, l analysis, and resolution processes, including review of a sample of eddy current data j from Refueling Outage RF Observations and Findinas The NRC consultant reviewed a sample of plus point eddy current data for tubes, which had been determined by the resolution process, to contain inside diameter and outside diameter axial and circumferential crack-like indications at the top-of-tube sheet location. Included in the review were checks of the reported flaw location, phase angle, volts, and l the three letter defect code. The NRC connultant agreed with the reported results, and noted that the eddy current analysts were, in general, conservative in the calls made. A review was also performed by the NRC consultant of a sample of single circumferential and axial defect calls, that were subsequently changed during review by the lead analyst and independent qualified data analyst (performing oversight of analysis activities for the licensee) to a final call of no detectable degradation' . Appropriate bases for the changes
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were provided by the independent qualified data analyst when questione l t
The current licensee data analysis guidelines, Procedure ETP-BB-01309, Revision 008, ,
indicates that current freespan differential and manufacturing burnish mark indications i should be compared against history prior to making a final call regarding the nature of !
! - the indications. The NRC consultant reviewed this process and noted that changes in j bobbin coil design since 1992 tend to complicate comparison of older bobbin coil signals j with current data (i.e., the earlier coils had a higher resonance frequency and, as a result, i produced voltages that are approximately twice that produced by a current design coil from the same reflector). In addition, bobbin probe speeds have increased in the last
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3 years, with up to 40 inches per second being used during acquisition of eddy current data. The NRC consultant noted, however, during review of a sample of these types of indications, that Lissajous figures could still be readily compared. Variations in the " fine" ,
structure of the Lissajous figures, related to differences in probe speed, were observe However, even in those cases, the similarity of the Lissajous primary features was clear when an indication was present in both historical and current bobbin coil dat l l
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l -4-l The inspector reviewed acquisition activities with respect to compliance with program requirements for: (1) verification of use of correct probe, (2) bobbin coil noise criteria, and (3) performance of ASME Code required 4-hour calibrations. No problems were noted during this review, with good contpliance to program requirements noted in contractor performanc Conclusions
Refueling Outage RF9 eddy current examination acquisition and analysis activities
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appeared effectively controlled, with good overall contractor performance noted.
11 Enaineerina E1 Conduct of Engineering l
E1.1 Review of Steam Generator Tube Examination Program Requirements l l Insoection Scoce (50002)
The inspector and NRC consdtent reviewed the steam generator tube examination program requirements contained in: (1) Engineering Technical Procedure ETP-BB-01309, " Steam Generator Eddy Current Testing Acquisition and Analysis Guidelines, Revision 008; (2) Document S-1032, " Technical Specification l for Steam Generator Maintenance Services," Revision 6; (3) Westinghouse Procedure MRS 2.4.2 GEN-35, " Eddy Current inspection of Preservice and ,
inservice Heat Exchanger Tubing," Revision 7; and (4) the site-specific performance demonstration requirements developed for Refueling Outage RF i Observations and Findings l
During the initial baseline steam generator tube integrity review inspection, which was documented in inspection Report 50-483/96-10, the inspectors noted areas of weakness in the Procedure ETP-BB-01309 data analysis guidelines. These areas of weakness were indicated to include: (1) absence of criteria for establishing when eddy current noise data was unacceptable, (2) a lack of restrictions on assigning through-wall depths from bobbin coil data, and (3) absence of specific requirements for disposition of potential manufacturer's burnish mark indications. The inspector and NRC consultant .
noted during the current inspection that the licensee had implemented for Refueling l Outage RF9: (1) quantitative noise criteria for determining when bobbin coil probes j should be replaced; (2) a restriction on assignment of bobbin coil through-wall depths to '
I only anti-vibration bar wear; and (3) a process stipulating review of potential i l manufacturer's burnish mark indications against prior eddy current examination history to I verify pre-existence of an indication prior to making a final cal The NRC consultant reviewed the handling of noisy data during Refueling Outage RF9 and noted that, at current noise limits, the main features, which determine the indication call, were not distorted enough to miss a flaw. The inspector concluded that the basic i
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l-5-licensee approach was commendable, in that it removed the onus from the eddy current data analyst in determining when eddy current data was of sufficient quality for analysi As noted in Section M1.1 above, the NRC consultant was able to readily determine when I eddy current indications characteristic of manufacturer's burnish marks were evident in historical eddy current data despite the complications created by changes in bobbin coil probe design and increased acquisition speed During the inspection documented in Inspection Report 50-483/96-10, areas of concern were noted regarding the adequacy of the practices used for training and testing of eddy current data analysts. The specific subjects of concern were: (1) the absence of plus l point probe data in the site-specific performance demonstration test, despite selection of this probe for use in Refueling Outage RF8; and (2) the limited number of stress corrosion cracking eddy current data indications present in the site-specific performance demonstration data base, which resulted in some analysts successfully completing the i site-specific performance demonstration test while analyzing only a small number of stress corrosion cracking indication As a result of the prior observations, an additional review was performed in the current inspection of the Refueling Outage RF9 training and site-specific performance demonstration testing for eddy current data analyst The NRC consultant ascertained that the site-specific performance demonstration test for Refueling Outage RF9 included a time restricted written open book examination on the steam generator design, inservice inspection history, and eddy current data acquisition and analysis requirements. The test was considered to adequately address the most important facets for the eddy current data analysts. The noted absence of lesson plans for the written examination was viewed to be of increasing importance, if degradation modes and locations increased during commercial service. The site specific practical examination required examination of numerous flaw signals from e;1 optical disk containing previous Callaway Plant indications. This test was noted to contain good examples of anti-vibration bar wear, manufacturing burnish marks, and stress corrosion cracking. The inspector considered that the test would be further strengthened by inclusion of data from other plants relative to tube support plate and freespan cracking, and inclusion of data from laser welded sleeve Conclusions The licensee has appropriately responded to areas of weakness in the eddy current data analysis guidelines that were identified during a prior NRC inspection documented in Inspection Report 50-483/96-10.
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-6-E Review of Unit Reoair History and Refuelino Outaae RF9 Examination Scoce and Results Insoection Scooe (50002)
The inspector reviewed the tube examination scope and methods that were used in Refueling Outage RF9 with respect to technicM specification requirements, industry guidance, and as a result of emerging degradation modes. A review was also performed of tube plugging history for the unit steam generators in Refueling Outage RF Observations and Findinas
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The licensee planned eddy current examination scope for Refueling Outage RF9 consisted of: (1) a full-length bobbin probe examination of all active tubes in Steam Generators B and C; (2) plus point probe examination at the top-of-tube sheet location cf all active tubes on the hot-leg side of Steam Generators A, B, C, and D; (3) plus point probe examination of all Row 1 low radius U-bend sections in Steam Generator A; (4) plus point probe examination of a sample of 40 laser welded sleeves that were installed in Steam Generators A and C during Refueling Outage RF8; (5) plus point probe examination of a minimum sample of 20 percent of dents with a bobbin coil amplitude of 5 volts or greater; and (6) plus point probe examination of distorted and non-quantifiable bobbin coil indication The inspector considered the overall examination scope to be comprehensive when evaluated against current degradation history. The use of the plus point probe was viewed as an indicator of management support for examination initiatives that would provide for early detection of degradation. The inspector considered the performance of bobbin probe examinations of all active tubes in individual steam generators every two cycles to be an acceptable approach, provided the current absence of flaw indications at tube support locations continue Table 1 lists the cumulative repair history for the individual steam generators. As of the end of Refueling Outage RF9, the respective tube plugging totals in Steam Generators A, B, C, and D during commercial service were 119,38,126, and 75, which corresponded to respective inservice repair pewintages of 1.37,0.68,1.68, and 1.3 The inservice repair percentages were calculated to take into account the presence of tubes in Steam Generators A and C that were repairec by installation of laser welded sleeves in Refueling Outage RF8, with 20 laser-welded sleeves considered thermally equivalent to 1 pit Table 2 shows a cumulative compilation for the unit of inservice tube degradation history by degradation mode. A previous review of tube degradation history through Refueling Outage RF8 was documented in Inspection Report 50-483/96-10. The inspectors noted from the Refueling Outage RF8 eddy current examination results that an increase had occurred from the prior outage in detected axial and circumferential flaw indications at the top-of-tube sheet location (i.e.,108 tubes versus 30 tubes in Refueling Outage RF7). i
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Time of Effective Full SG A SG B SG C SG D Repair Power Years Refueling of Operation Outage (RF) Ot Cu Ot Cu Ot Cu Ot Cu IS% IS% IS% IS%
(g) (g) (g) (g)
l Preservice l N/A 3 N/A l7 N/A 7 N/A l RF1(5/1986) l (a) 0 (b) -
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l0 0.00 l l M*(4/1987) l (b) - 2 0.04 l3 0.05 l(b) -
l RF2(9/1987) .05 (b) -
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l5 0.09 l RF3(4/1989) l (b) - 4 0.11 l9 0.21 l(b) -
l RF4 (10/1990) l .16 (b) -
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l 16 0.37 l RF5 (4/1992) l (b) - 15 0.37 l14 0.46 l 2i' O 41 l l RF6(10/1993) l .50 (b) -
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l 18 0.73 l l RF7(4/1995) l .69 5 0.46 l20 0.82 l4 0.80 l l RF8(10/1996) l 9.97 48* 0.80"" 8 0.60 l44m j 04m> l25 1.24 32 1.37*) 4 0.68 36 1.68*) 5 Tntal Renmirt 177 41 1 133 I R7 (a) - Not provided; (b) - Steam generator tubes not examined during outage; (c) - Maintenance outage; (d)- Steam generator tubes not examined. Two tubes preventively plugged based on Refueling Outage RF4 examination results; (e) - 44 tubes repaired with laser welded sleeves; (f) - 33 tubes repaired with laser welded sleeves; (g) - Cumulative inservice plug equivalent percentage; (h) - Based on 20 laser welded sleeves being considered thermally equivalent to 1 plu l l
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.g-The inspector considered the inferred (or probable) degradation mechanism for the axial and circumferential eddy current indications to be stress corrosion cracking. The tube l plugging total for top-of-tube sheet axial and circumferential indications decreased in
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Refueling Outage RF9 to 65 tubes. The inspector noted during the onsite portion of the i inspection that the flaws appeared in general to be small, with none viewed as potentially l not meeting Regulatory Guide 1.121 structuralintegrity criteria. No degradation was detected in the thermally treated Rows 1 through 10 tubes. Examination of the sample of laser welded sleeves found no evidence of defects after one cycle of operatio Conclusions The use of the plus point probe was viewed as an indicator of management support for examination initiatives that would provide for early detection of degradation. An increase in axial and circumferential indications at the top-of-tube sheet location was noted during i Refueling Outage RF8 (i.e.,108 tubes plugged versus 30 tubes in Refueling Outage l RF7). The corresponding plugging total for this type of degradation decreased in Refueling Outage RF9 to 65 tube E8 Miscellaneous Engineering issues E LClosed) Violation 50-483/9610-01: Failure to assure use during analysis of plus point probe data cf settings for span and phase rotation that were qualified in accordance with Appendix H of the Electric Power Research Institute, "PWR Steam Generator Examination Guidelines," Revision The inspector verified that span and phase rotation settings had been established in the Refueling Outage RF9 analysis technique specification sheets for the plus point probe method, which were technically appropriate and consistent with the Appendix H (of the Electnc Power Research Institute "PWR Steam Generator Examination Guidelines")
qualifications. Additionally, the licensee had a contractor perform an independent review of all analysis technique specification sheets to assure their consistency with Appendix H requirement E (Closed) Unresolved item 50-483/9610-02: Monitoring of power used in laser welding of sleeves in steam generator tube The inspector reviewed the correspondence (included as Attachment 4 in inspection ;
Report 50-483/96-10) on this item and infrared feedback data that was collected by i Westinghouse during the testing and qualification of weld heads. The inspector noted during the review of the infrared feedback data that the data did provide an indication of l
when degradation was occurring in laser energy reaching the weld. Accordingly, the inspector concluded that the infrared feedback system could be considered to perform a I power monitoring function, which together with the nondestructive examinations of the
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l completed welds, provided assurance of maintenance of required weld qualit i
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-10-IV. Plant Suonort R1 Radiological Protection and Chemistry Controls R fron Transoort to Steam Generators (50002) Insoection Scooe The inspector performed a review of trend data from November 1995 through March 1998 for iron transport to the steam generators, Observations and Findings The results of initial review of iron transport to the steam generators through Cycle 8 were documented in Inspection Report 50-483/96-10. It was noted (at the time of the initial review) that the licensee had successfully maintained iron transport below the Electric Power Research Institute secondary water chemistry guideline limit of 5 ppb, since the replacement of ammonium hydroxide with ethanolamines for pH control in l September 1993. The inspector noted during the current review that feedwater iron
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values ranged from approximately 2.5 ppb to 3.5 ppb in the first 3 months of 1996 and from approximately 2.5 to 3 ppb in the first quarter of 1998. A 2.75 ppb average value was documented for Cycle 9, indicating the licensee is continuing to maintain iron transport at low levels; thereby, minimizing fouling and deposit buildup in the steam l generators. The inspector considered the iron transport history to be an indicator of both l excellent chemistry staff performance and management support for steam generator tube integrity initiatives.
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The licensee has successfully maintained iron transport to the steam generators at low l levels since adoption in 1993 of ethanolamines for pH contro V. Management Meetinas X1 Exit Meeting Summary The inspector presented the results of the onsite inspection to members of licensee management on April 17,1998, at the conclusion of the onsite inspection. The licensee acknowledged the findings presented. No information was identified during this meeting as being considered proprietary. During the exit meeting, the inspector informed licensee management that the inspection would remain in an open status until the final eddy current examination results became available and had been reviewed. A final telephone conversation regarding the eddy current examination results was held with licensee staff on May 1,199 _ _ - _ _ _ _ _ - _ - _ - _ _ _ _ _ _ _ _ _
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ATTACHMENT
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SUPPLEMENTAL INFORMATION l 1 PARTIAL LIST OF PERSONS CONTACTED Licensee R. Affolter, Plant Manager T. Hermann, Supervising Engineer, NSSS and HVAC Design G. Hughes, Acting Quality Assurance Manager E. Olson, Supervisor, Chemistry T. Pettus, Steam Generator Engineer G. Randolph, Vice President and Chief Nuclear Officer 1
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M. Reidmeyer, Engineer, Quality Assurance E. Thornton, Quality Assurance Engineering Evaluator i I
NflR F. Brush, Resident inspector J. Hanna, Reactor Engineer D. Passehl, Senior Resident inspector i INSPECTION PROCEDURES USED 50002 Steam Generators t
92903 Followup-Engineering ITEMS CLOSED Closed 50-483/9610-01 VIO Failure to assure use during analysis of plus point probe data of settings for span and phase rotation that were qualified in accordance with Appendix H of the Electric Power Research Institute "PWR Steam Generator Examination Guidelines,"
Revision 4 50-483/9610-02 URI Monitoring of power used in laser welding of steam generator tube sleeves LIST OF DOCUMENTS REVIEWED Procedures / Documents
I ETP-BB-01309, " Steam Generator Eddy Current Testing Acquisition and Analysis Guidelines,"
Revision 008 l
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-2-S-1032, " Technical Specification for Steam Generator Maintenance Services," Revision 6 MRS 2.4.2 GEN-35 (Westinghouse), " Eddy Current inspection of Preservice and inservice Heat Exchariger Tubing," Revision 7 Callaway Plant Refuel IX Site Specific Written Exam, Test 1 and 2, dated April 1998
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Acquisition Technique Specification Sheet SCP-01-198, Revision 1 Acquisition Technique Specification Sheet SCP-02-198, Revision 1 l Acquisition Technique Specification Sheet SCP-03-198, Revision 0 Acquisition Technique Specification Sheet SCP-04-198, Revision 1 Acquisition Technique Specification Sheet SCP-05-198, Revision 1 Acquisition Technique Specification Sheet SCP-06-198, Revision 1 Acquisition Technique Specification Sheet SCP-07-198, Revision 3 Acquisition Technique Specification Sheet SCP-08-198, Revision 1 Acquisition Technique Specification Sheet SCP-09-198, Revision 1 Analysis Technique Specification Sheet SCP-A-198 (Bobbin), Revision 2 Analysis Technique Specification Sheet SCP-B-198 (Plus Point MRPC), Revision 1 Analysis Technique Specification Sheet SCP-C-198 (U Bend Plus Point MRPC), Revision 1 Analysis Technique Specification Sheet SCP-D-198 (520-Plus Point MRPC), Revision 2 Analysis Technique Specification Sheet SCP-E-198 (Sleeve Plus Point MRPC), Revision 1 Analysis Technique Specification Sheet SCP-F-198 (Cecco), Revision 1 l
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