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MONTHYEARML20151B4461988-07-12012 July 1988
Forwards Details of Insps on Class 1E Westinghouse Type Ds Breakers,Per Commitment in 880609 Response to NRC Bulletin 88-01
Project stage: Other
ML20207J2401988-08-25025 August 1988
Concurs W/Util 880712 Submittal of Detailed Data Re Class 1E Breakers,In Response to NRC Bulletin 88-001, Defects in Westinghouse Circuit Breakers. Submittals of Such Addl Data for Unit 2 Will Not Be Necessary
Project stage: Other
1988-07-12
[Table View] |
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Category:CORRESPONDENCE-LETTERS
MONTHYEARL-99-035, Forwards non-proprietary & Proprietary Versions of Farley Units 1 & 2 LBB Calculation Results Due to SG Replacement & SG Snubber Elimination Programs, Used to Support SG Replacement Project.Proprietary Encl Withheld1999-10-18018 October 1999
Forwards non-proprietary & Proprietary Versions of Farley Units 1 & 2 LBB Calculation Results Due to SG Replacement & SG Snubber Elimination Programs, Used to Support SG Replacement Project.Proprietary Encl Withheld
ML20217G0801999-10-0707 October 1999
Informs That on 990930,staff Conducted mid-cycle PPR of Farley & Did Not Identify Any Areas in Which Performance Warranted More than Core Insp Program.Nrc Will Conduct Regional Insps Associated with SG Removal & Installation
ML20217P0661999-10-0606 October 1999
Requests Withholding of Proprietary Rept NSD-SAE-ESI-99-389, Farley Units 1 & 2 LBB Calculation Results Due to SG Replacement & SG Snubber Elimination Programs
ML20217B1891999-10-0404 October 1999
Submits Clarification Re Development of Basis for Determining Limiting Internal Pressure Loads Re Review of NRC SE for Cycle 16 Extension Request.Util Intends to Use Guidelines When Evaluating SG Tube Structural Integrity
ML20212J8391999-09-30030 September 1999
Forwards RAI Re Request for Amends to Ts.Addl Info Needed to Complete Review to Verify That Proposed TS Are Consistent with & Validate Design Basis Analysis.Request Discussed with H Mahan on 990930.Info Needed within 10 Days of This Ltr
ML20212J8801999-09-30030 September 1999
Discusses GL 98-01,suppl 1, Y2K Readiness of Computer Sys at Npps. Util 980731,990607 & 03 Ltrs Provided Requested Info in Subj Gl.Nrc Considers Subj GL to Be Closed for Unit 1
L-99-032, Responds to NRC Re Adequacy of Kaowool Fire Retardant Fire Barriers in Use at Jfnp,Units 1 & 21999-09-23023 September 1999
Responds to NRC Re Adequacy of Kaowool Fire Retardant Fire Barriers in Use at Jfnp,Units 1 & 2
L-99-034, Forwards Comments on Draft Current Tech Specs Discussion of Change Tables for Jm Farley Nuclear Plant.Units 1 & 21999-09-23023 September 1999
Forwards Comments on Draft Current Tech Specs Discussion of Change Tables for Jm Farley Nuclear Plant.Units 1 & 2
ML20212F8861999-09-23023 September 1999
Forwards Revised Relief Request Number 32 for NRC Approval. Approval Requested by 991231 to Support Activities to Be Performed During Unit 1 Refueling Outage Scheduled for Spring of 2000
ML20212E7031999-09-23023 September 1999
Responds to GL 98-01, Year 2000 Readiness of Computer Sys at Npps. Util Requested to Submit Plans & Schedules for Resolving Y2K-related Issues
ML20212F1111999-09-21021 September 1999
Discusses Closeout of GL 97-06, Degradation of Steam Generator Internals
ML20212C2351999-09-16016 September 1999
Submits Corrected Info Concerning Snoc Response to NRC GL 99-02, Lab Testing of Nuclear-Grade Activated Charcoal
ML20212D0101999-09-15015 September 1999
Informs That Submittal of clean-typed Copy of ITS & ITS Bases Will Be Delayed.Delay Due to Need for Resolution of Two Issues Raised by NRC staff.Clean-typed Copy of ITS Will Be Submitted within 4 Wks Following Resolution of Issues
ML20212C4641999-09-13013 September 1999
Forwards Info Requested in Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Exams
L-99-031, Informs NRC That Review of MOV Testing Frequency & Changes Made to Frequency of MOV Testing Has Been Completed1999-09-13013 September 1999
Informs NRC That Review of MOV Testing Frequency & Changes Made to Frequency of MOV Testing Has Been Completed
ML20212C8041999-09-10010 September 1999
Responds to to D Rathbun Requesting Review of J Sherman Re Y2K Compliance.Latest NRC Status Rept on Y2K Activities Encl
ML20212D4581999-09-10010 September 1999
Responds to to D Rathbun,Requesting Review of J Sherman Expressing Concerns That Plant & Other Nuclear Plants Not Yet Y2K Compliant
ML20212A6951999-09-0909 September 1999
Requests That Licensees Affected by Kaowool Fire Barriers Take Issue on Voluntary Initiative & Propose Approach for Resolving Subj Issues.Staff Plans to Meet with Licensees to Discuss Listed Topics
ML20212A8341999-09-0909 September 1999
Requests That Licensees Affected by Kaowool Fire Barriers Take Issue on Voluntary Initiative & Propose Approach for Resolving Subj Issues.Staff Plans to Meet with Licensees to Discuss Listed Topics
ML20211N8041999-09-0808 September 1999
Informs That on 990930 NRC Issued GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design-Basis Accident Condition, to Holders of Nuclear Plant Operating Licenses
ML20211N4301999-09-0808 September 1999
Discusses Proposed Meeting to Discuss Kaowool Fire Barriers. Staff Requesting That Affected Licensees Take Issue on Voluntary Initative & Propose Approach for Resolving Issues
ML20212C0071999-09-0202 September 1999
Forwards Insp Repts 50-348/99-05 & 50-364/99-05 on 990627- 0807.No Violations Noted.Licensee Conduct of Activities at Farley Plant Facilities Generally Characterized by safety-conscious Operations & Sound Engineering
ML20211Q4801999-09-0101 September 1999
Informs That on 990812-13,Region II Hosted Training Managers Conference on Recent Changes to Operator Licensing Program. List of Attendees,Copy of Slide Presentations & List of Questions Received from Participants Encl
ML20211K2131999-08-31031 August 1999
Informs That Snoc Has Conducted Review of Reactor Vessel Integrity Database,Version 2 (RVID2) & Conclude That Latest Data Submitted for Farley Units Has Not Been Incorporated Into RVID2
ML20211K4101999-08-31031 August 1999
Resubmits Relief Requests Q1P16-RR-V-5 & Q2P16-RR-V-5 That Seek to Group V661 Valves from Each Unit Into Sample Disassembly & Insp Group,Per 990525 Telcon with NRC
L-99-030, Forwards SNC Review Comments on Draft SE & marked-up Copy of Draft SE Incorporating SNC Comments Re Proposed Conversion to ITS1999-08-30030 August 1999
Forwards SNC Review Comments on Draft SE & marked-up Copy of Draft SE Incorporating SNC Comments Re Proposed Conversion to ITS
ML20211G6851999-08-26026 August 1999
Informs That During Insp,Technical Issues Associated with Design,Installation & fire-resistive Performance of Kaowool Raceway fire-barriers Installed at Farley Nuclear Plant Were Identified
L-99-029, Forwards Revised Response to Chapter 3.1 RAI Requested in 990726 Conference Call,Rai Response Related to Beyond Scope Issue for Chapter 3.5 Requested by Conference Call on 990805 & RAI Response to Chapter 3.8 Requested on 990615 & 07271999-08-19019 August 1999
Forwards Revised Response to Chapter 3.1 RAI Requested in 990726 Conference Call,Rai Response Related to Beyond Scope Issue for Chapter 3.5 Requested by Conference Call on 990805 & RAI Response to Chapter 3.8 Requested on 990615 & 0727
ML20211B9431999-08-17017 August 1999
Forwards Fitness for Duty Performance Data for six-month Reporting Period 990101-990630,IAW 10CFR26.71(d).Rept Covers Employees at Jm Farley Nuclear Plant & Southern Nuclear Corporate Headquarters
ML20211B9211999-08-17017 August 1999
Responds to NRC Re Violations Noted in Insp Rept 50-348/99-09 & 50-364/99-09.Corrective Actions:Security Response Plan Was Revised to Address Vulnerabilities Identified During NRC Insp
ML20210R5101999-08-12012 August 1999
Forwards Revised Page 6 to 990430 LAR to Operate Farley Nuclear Plant,Unit 1,for Cycle 16 Only,Based on risk- Informed Approach for Evaluation of SG Tube Structural Integrity,As Result of Staff Comments
ML20212C8141999-08-0909 August 1999
Forwards Correspondence Received from Jm Sherman.Requests Review of Info Re Established Policies & Procedures
ML20210T2021999-08-0606 August 1999
Forwards Draft SE Accepting Licensee Proposed Conversion of Plant,Units 1 & 2 Current TSs to Its.Its Based on Listed Documents
ML20210Q4641999-08-0505 August 1999
Informs That NRC Plans to Administer Gfes of Written Operator Licensing Exam on 991006.Authorized Representative of Facility Must Submit Ltr to La Reyes,As Listed,With List of Individuals to Take exam,30 Days Before Exam Date
ML20210J8341999-07-30030 July 1999
Forwards Second Request for Addl Info Re Util 990430 Amend Request to Allow Util to Operate Unit 1,for Cycle 16 Based on risk-informed Probability of SG Tube Rupture & Nominal accident-induced primary-to-second Leakage
ML20210G4901999-07-30030 July 1999
Responds to GL 99-02, Laboratory Testing of Nuclear-Grade Activated Charcoal, Issued 990603.Ltr Contains NRC License Commitment to Utilize ASTM D3803-1989 with Efficiency Acceptance Criteria Utilizing Safety Factor of 2
L-99-028, Responds to NRC 990730 RAI Re 990423 OL Change Request to Allow for Risk Informed Approach for Evaluation of SG Tube Structural Integrity as Described by NEI 97-06, SG Program Guidelines1999-07-30030 July 1999
Responds to NRC 990730 RAI Re 990423 OL Change Request to Allow for Risk Informed Approach for Evaluation of SG Tube Structural Integrity as Described by NEI 97-06, SG Program Guidelines
L-99-027, Addresses Clarifications to Selected Responses to Chapter 3.8 RAI Requested in NRC Conference Call on 990624, Resolution of Open Issue Related to Containment Purge in Chapter 3.6 & Response Related to Chapter 3.51999-07-27027 July 1999
Addresses Clarifications to Selected Responses to Chapter 3.8 RAI Requested in NRC Conference Call on 990624, Resolution of Open Issue Related to Containment Purge in Chapter 3.6 & Response Related to Chapter 3.5
ML20210G8181999-07-26026 July 1999
Forwards Insp Repts 50-348/99-04 & 50-364/99-04 on 990516- 0626.One Violation Identified & Being Treated as Noncited Violation
IR 05000348/19990091999-07-23023 July 1999
Discusses Insp Repts 50-348/99-09 & 50-364/99-09 on 990308- 10 & Forwards Notice of Violation Re Failure to Intercept Adversary During Drills,Contrary to 10CFR73 & Physical Security Plan Requirements
ML20210E4071999-07-22022 July 1999
Responds to NRC 990702 RAI Re Change Request to Allow for Risk Informed Approach for Evaluation of SG Tube Structural Integrity as Described in NEI 97-06, SG Program Guidelines
L-99-026, Forwards Response to NRC 990702 RAI Re SG Replacement Related TS Change Request Submitted 981201.Ltr Contains No New Commitments1999-07-19019 July 1999
Forwards Response to NRC 990702 RAI Re SG Replacement Related TS Change Request Submitted 981201.Ltr Contains No New Commitments
L-99-264, Responds to NRC 990603 Administrative Ltr 99-02, Operating Licensing Action Estimates, for Fy 2000 & 20011999-07-13013 July 1999
Responds to NRC 990603 Administrative Ltr 99-02, Operating Licensing Action Estimates, for Fy 2000 & 2001
ML20209H4721999-07-13013 July 1999
Responds to NRC 990603 Administrative Ltr 99-02, Operating Licensing Action Estimates, for Fy 2000 & 2001
ML20196J6191999-07-0202 July 1999
Forwards Final Dam Audit Rept of 981008 of Category 1 Cooling Water Storage Pond Dam.Requests Response within 120 Days of Date of Ltr
05000364/LER-1999-001, Forwards LER 99-001-00 Re Reactor Trip Due to Loss of Condenser Vacuum Steam Dump Drain Line Failure.Commitments Made by Licensee,Listed1999-07-0202 July 1999
Forwards LER 99-001-00 Re Reactor Trip Due to Loss of Condenser Vacuum Steam Dump Drain Line Failure.Commitments Made by Licensee,Listed
ML20196J7471999-07-0202 July 1999
Forwards RAI Re Cycle 16 Extension Request.Response Requested within 30 Days of Date of Ltr
ML20196J5781999-07-0202 July 1999
Forwards RAI Re 981201 & s Requesting Amend to TS Associated with Replacing Existing Westinghouse Model 51 SG with Westinghouse Model 54F Generators.Respond within 30 Days of Ltr Date
ML20196J6571999-07-0202 July 1999
Discusses Closure to TAC MA0543 & MA0544 Re GL 92-01 Rev 1, Suppl 1,RV Structural Integrity.Nrc Has Revised Rvid & Releasing It as Rvid,Version 2 as Result of Review of Responses
ML20196J3591999-06-30030 June 1999
Forwards SE of TR WCAP-14750, RCS Flow Verification Using Elbow Taps at Westinghouse 3-Loop Pwrs
1999-09-09
[Table view]
Category:INCOMING CORRESPONDENCE
MONTHYEARL-99-035, Forwards non-proprietary & Proprietary Versions of Farley Units 1 & 2 LBB Calculation Results Due to SG Replacement & SG Snubber Elimination Programs, Used to Support SG Replacement Project.Proprietary Encl Withheld1999-10-18018 October 1999
Forwards non-proprietary & Proprietary Versions of Farley Units 1 & 2 LBB Calculation Results Due to SG Replacement & SG Snubber Elimination Programs, Used to Support SG Replacement Project.Proprietary Encl Withheld
ML20217P0661999-10-0606 October 1999
Requests Withholding of Proprietary Rept NSD-SAE-ESI-99-389, Farley Units 1 & 2 LBB Calculation Results Due to SG Replacement & SG Snubber Elimination Programs
ML20217B1891999-10-0404 October 1999
Submits Clarification Re Development of Basis for Determining Limiting Internal Pressure Loads Re Review of NRC SE for Cycle 16 Extension Request.Util Intends to Use Guidelines When Evaluating SG Tube Structural Integrity
L-99-034, Forwards Comments on Draft Current Tech Specs Discussion of Change Tables for Jm Farley Nuclear Plant.Units 1 & 21999-09-23023 September 1999
Forwards Comments on Draft Current Tech Specs Discussion of Change Tables for Jm Farley Nuclear Plant.Units 1 & 2
L-99-032, Responds to NRC Re Adequacy of Kaowool Fire Retardant Fire Barriers in Use at Jfnp,Units 1 & 21999-09-23023 September 1999
Responds to NRC Re Adequacy of Kaowool Fire Retardant Fire Barriers in Use at Jfnp,Units 1 & 2
ML20212F8861999-09-23023 September 1999
Forwards Revised Relief Request Number 32 for NRC Approval. Approval Requested by 991231 to Support Activities to Be Performed During Unit 1 Refueling Outage Scheduled for Spring of 2000
ML20212C2351999-09-16016 September 1999
Submits Corrected Info Concerning Snoc Response to NRC GL 99-02, Lab Testing of Nuclear-Grade Activated Charcoal
ML20212D0101999-09-15015 September 1999
Informs That Submittal of clean-typed Copy of ITS & ITS Bases Will Be Delayed.Delay Due to Need for Resolution of Two Issues Raised by NRC staff.Clean-typed Copy of ITS Will Be Submitted within 4 Wks Following Resolution of Issues
L-99-031, Informs NRC That Review of MOV Testing Frequency & Changes Made to Frequency of MOV Testing Has Been Completed1999-09-13013 September 1999
Informs NRC That Review of MOV Testing Frequency & Changes Made to Frequency of MOV Testing Has Been Completed
ML20212C4641999-09-13013 September 1999
Forwards Info Requested in Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Exams
ML20211K2131999-08-31031 August 1999
Informs That Snoc Has Conducted Review of Reactor Vessel Integrity Database,Version 2 (RVID2) & Conclude That Latest Data Submitted for Farley Units Has Not Been Incorporated Into RVID2
ML20211K4101999-08-31031 August 1999
Resubmits Relief Requests Q1P16-RR-V-5 & Q2P16-RR-V-5 That Seek to Group V661 Valves from Each Unit Into Sample Disassembly & Insp Group,Per 990525 Telcon with NRC
L-99-030, Forwards SNC Review Comments on Draft SE & marked-up Copy of Draft SE Incorporating SNC Comments Re Proposed Conversion to ITS1999-08-30030 August 1999
Forwards SNC Review Comments on Draft SE & marked-up Copy of Draft SE Incorporating SNC Comments Re Proposed Conversion to ITS
L-99-029, Forwards Revised Response to Chapter 3.1 RAI Requested in 990726 Conference Call,Rai Response Related to Beyond Scope Issue for Chapter 3.5 Requested by Conference Call on 990805 & RAI Response to Chapter 3.8 Requested on 990615 & 07271999-08-19019 August 1999
Forwards Revised Response to Chapter 3.1 RAI Requested in 990726 Conference Call,Rai Response Related to Beyond Scope Issue for Chapter 3.5 Requested by Conference Call on 990805 & RAI Response to Chapter 3.8 Requested on 990615 & 0727
ML20211B9431999-08-17017 August 1999
Forwards Fitness for Duty Performance Data for six-month Reporting Period 990101-990630,IAW 10CFR26.71(d).Rept Covers Employees at Jm Farley Nuclear Plant & Southern Nuclear Corporate Headquarters
ML20211B9211999-08-17017 August 1999
Responds to NRC Re Violations Noted in Insp Rept 50-348/99-09 & 50-364/99-09.Corrective Actions:Security Response Plan Was Revised to Address Vulnerabilities Identified During NRC Insp
ML20210R5101999-08-12012 August 1999
Forwards Revised Page 6 to 990430 LAR to Operate Farley Nuclear Plant,Unit 1,for Cycle 16 Only,Based on risk- Informed Approach for Evaluation of SG Tube Structural Integrity,As Result of Staff Comments
ML20212C8141999-08-0909 August 1999
Forwards Correspondence Received from Jm Sherman.Requests Review of Info Re Established Policies & Procedures
ML20210G4901999-07-30030 July 1999
Responds to GL 99-02, Laboratory Testing of Nuclear-Grade Activated Charcoal, Issued 990603.Ltr Contains NRC License Commitment to Utilize ASTM D3803-1989 with Efficiency Acceptance Criteria Utilizing Safety Factor of 2
L-99-028, Responds to NRC 990730 RAI Re 990423 OL Change Request to Allow for Risk Informed Approach for Evaluation of SG Tube Structural Integrity as Described by NEI 97-06, SG Program Guidelines1999-07-30030 July 1999
Responds to NRC 990730 RAI Re 990423 OL Change Request to Allow for Risk Informed Approach for Evaluation of SG Tube Structural Integrity as Described by NEI 97-06, SG Program Guidelines
L-99-027, Addresses Clarifications to Selected Responses to Chapter 3.8 RAI Requested in NRC Conference Call on 990624, Resolution of Open Issue Related to Containment Purge in Chapter 3.6 & Response Related to Chapter 3.51999-07-27027 July 1999
Addresses Clarifications to Selected Responses to Chapter 3.8 RAI Requested in NRC Conference Call on 990624, Resolution of Open Issue Related to Containment Purge in Chapter 3.6 & Response Related to Chapter 3.5
ML20210E4071999-07-22022 July 1999
Responds to NRC 990702 RAI Re Change Request to Allow for Risk Informed Approach for Evaluation of SG Tube Structural Integrity as Described in NEI 97-06, SG Program Guidelines
L-99-026, Forwards Response to NRC 990702 RAI Re SG Replacement Related TS Change Request Submitted 981201.Ltr Contains No New Commitments1999-07-19019 July 1999
Forwards Response to NRC 990702 RAI Re SG Replacement Related TS Change Request Submitted 981201.Ltr Contains No New Commitments
L-99-264, Responds to NRC 990603 Administrative Ltr 99-02, Operating Licensing Action Estimates, for Fy 2000 & 20011999-07-13013 July 1999
Responds to NRC 990603 Administrative Ltr 99-02, Operating Licensing Action Estimates, for Fy 2000 & 2001
ML20209H4721999-07-13013 July 1999
Responds to NRC 990603 Administrative Ltr 99-02, Operating Licensing Action Estimates, for Fy 2000 & 2001
05000364/LER-1999-001, Forwards LER 99-001-00 Re Reactor Trip Due to Loss of Condenser Vacuum Steam Dump Drain Line Failure.Commitments Made by Licensee,Listed1999-07-0202 July 1999
Forwards LER 99-001-00 Re Reactor Trip Due to Loss of Condenser Vacuum Steam Dump Drain Line Failure.Commitments Made by Licensee,Listed
L-99-024, Responds to NRC RAI Re Conversion to ITS for Chapters 3.4, 3.5,3.6,3.7,3.9 & 5.0,per 990419-20 Meetings with NRC1999-06-30030 June 1999
Responds to NRC RAI Re Conversion to ITS for Chapters 3.4, 3.5,3.6,3.7,3.9 & 5.0,per 990419-20 Meetings with NRC
L-99-025, Forwards Rev 2 to Jfnp Security plan,FNP-0-M-99,IAW 10CFR50.4(b)(4).Attachment 1 Contains Summary of Changes & Amended Security Plan Pages.Encl Withheld from Public Disclosure Per 10CFR73.211999-06-30030 June 1999
Forwards Rev 2 to Jfnp Security plan,FNP-0-M-99,IAW 10CFR50.4(b)(4).Attachment 1 Contains Summary of Changes & Amended Security Plan Pages.Encl Withheld from Public Disclosure Per 10CFR73.21
ML20196J8631999-06-30030 June 1999
Submits Correction to Errors Contained in to NRC Re TS Changes Re Control Room,Penetration Room & Containment Purge Filtration Systems & Radiation Monitoring Instrumentation.Errors Do Not Require Rev of SA
L-99-249, Submits Correction to Errors Contained in to NRC Re TS Changes Re Control Room,Penetration Room & Containment Purge Filtration Systems & Radiation Monitoring Instrumentation.Errors Do Not Require Rev of SA1999-06-30030 June 1999
Submits Correction to Errors Contained in to NRC Re TS Changes Re Control Room,Penetration Room & Containment Purge Filtration Systems & Radiation Monitoring Instrumentation.Errors Do Not Require Rev of SA
L-99-224, Submits Rev to Unit 2 SG Tube voltage-based Repair Criteria Data Rept.Ltr Contains No Commitments1999-06-0707 June 1999
Submits Rev to Unit 2 SG Tube voltage-based Repair Criteria Data Rept.Ltr Contains No Commitments
ML20195F1731999-06-0707 June 1999
Forwards Proprietary & non-proprietary Responses to NRC RAIs Re W TR WCAP-14750, RCS Flow Verification Using Elbow Taps at W 3-Loop Pwrs. W Proprietary Notice,Affidavit & Copyright Notice,Encl.Proprietary Info Withheld
L-99-217, Forwards Proprietary & non-proprietary Responses to NRC RAIs Re W TR WCAP-14750, RCS Flow Verification Using Elbow Taps at W 3-Loop Pwrs. W Proprietary Notice,Affidavit & Copyright Notice,Encl.Proprietary Info Withheld1999-06-0707 June 1999
Forwards Proprietary & non-proprietary Responses to NRC RAIs Re W TR WCAP-14750, RCS Flow Verification Using Elbow Taps at W 3-Loop Pwrs. W Proprietary Notice,Affidavit & Copyright Notice,Encl.Proprietary Info Withheld
L-99-225, Responds to GL 98-01, Yr 2000 Readiness of Computer Sys at Nuclear Power Plants1999-06-0707 June 1999
Responds to GL 98-01, Yr 2000 Readiness of Computer Sys at Nuclear Power Plants
ML20195F0621999-06-0707 June 1999
Submits Rev to Unit 2 SG Tube voltage-based Repair Criteria Data Rept.Ltr Contains No Commitments
ML20195E9581999-06-0707 June 1999
Responds to GL 98-01, Yr 2000 Readiness of Computer Sys at Nuclear Power Plants
ML20195C6941999-05-28028 May 1999
Forwards Response to NRC RAI Re GL 96-05 for Farley Nuclear Plant.Farley Is Committing to Implement Phase 3 of JOG Program
L-99-021, Forwards Response to RAI Re Conversion to ITSs for Chapter 3.3.Attachment II Includes Proposed Revs to Previously Submitted LAR Re Rais,Grouped by RAI number.Clean-typed Copies of Affected ITS Pages Not Included1999-05-28028 May 1999
Forwards Response to RAI Re Conversion to ITSs for Chapter 3.3.Attachment II Includes Proposed Revs to Previously Submitted LAR Re Rais,Grouped by RAI number.Clean-typed Copies of Affected ITS Pages Not Included
L-99-203, Forwards Response to NRC RAI Re GL 96-05 for Farley Nuclear Plant.Farley Is Committing to Implement Phase 3 of JOG Program1999-05-28028 May 1999
Forwards Response to NRC RAI Re GL 96-05 for Farley Nuclear Plant.Farley Is Committing to Implement Phase 3 of JOG Program
ML20195F2101999-05-24024 May 1999
Requests That Farley Nuclear Plant Proprietary Responses to NRC RAI Re W WCAP-14750, RCS Flow Verification Using Elbow Taps at W 3-Loop Pwrs, Be Withheld from Public Disclosure Per 10CFR2.790
L-99-180, Forwards Responses to NRC RAI Questions for Chapter 3.8 of Ts.Proposed Revs to TS Previously Submitted with LAR Related to RAI1999-04-30030 April 1999
Forwards Responses to NRC RAI Questions for Chapter 3.8 of Ts.Proposed Revs to TS Previously Submitted with LAR Related to RAI
ML20206F4321999-04-30030 April 1999
Forwards Responses to NRC RAI Questions for Chapter 3.8 of Ts.Proposed Revs to TS Previously Submitted with LAR Related to RAI
L-99-017, Forwards Responses to NRC RAI Questions for Chapters 3.1, 3.2,3.5,3.7 & 3.9 of Ts.Attached Pages Include Proposed Revs Previously Submitted LAR to Rais,Grouped by Chapters & RAI Numbers1999-04-30030 April 1999
Forwards Responses to NRC RAI Questions for Chapters 3.1, 3.2,3.5,3.7 & 3.9 of Ts.Attached Pages Include Proposed Revs Previously Submitted LAR to Rais,Grouped by Chapters & RAI Numbers
ML20206C8021999-04-26026 April 1999
Forwards 1998 Annual Rept, for Alabama Power Co.Encls Contain Financial Statements for 1998,unaudited Financial Statements for Quarter Ending 990331 & Cash Flow Projections for 990101-991231
05000348/LER-1998-007, Forwards SG-99-04-001, Farley-1:Final Cycle 16 Freespan ODSCC Operational Assessment, as Committed to in Licensee & LER 98-007-00.Util Is Revising Plant Administrative SG Operating Leakage Requirements as Listed1999-04-23023 April 1999
Forwards SG-99-04-001, Farley-1:Final Cycle 16 Freespan ODSCC Operational Assessment, as Committed to in Licensee & LER 98-007-00.Util Is Revising Plant Administrative SG Operating Leakage Requirements as Listed
L-99-015, Forwards Rev 1 to Jfnp Security plan,FNP-O-M-99,resulting from Implementation of Biometrics Sys.Changes Incorporate Changes Previously Submitted to NRC as Rev 28 by Licensee .Encl Withheld,Per 10CFR73.211999-04-21021 April 1999
Forwards Rev 1 to Jfnp Security plan,FNP-O-M-99,resulting from Implementation of Biometrics Sys.Changes Incorporate Changes Previously Submitted to NRC as Rev 28 by Licensee .Encl Withheld,Per 10CFR73.21
ML20206B4391999-04-21021 April 1999
Forwards Corrected ITS Markup Pages to Replace Pages in 981201 License Amend Requests for SG Replacement
L-99-172, Forwards FNP Annual Radioactive Effluent Release Rept for 1998, IAW TSs Sections 6.9.1.8 & 6.9.1.9.Changes to ODCM Revs 16,17 & 18 Are Encl,Iaw TS Section 6.14.21999-04-21021 April 1999
Forwards FNP Annual Radioactive Effluent Release Rept for 1998, IAW TSs Sections 6.9.1.8 & 6.9.1.9.Changes to ODCM Revs 16,17 & 18 Are Encl,Iaw TS Section 6.14.2
ML20205S9501999-04-21021 April 1999
Forwards FNP Annual Radioactive Effluent Release Rept for 1998, IAW TSs Sections 6.9.1.8 & 6.9.1.9.Changes to ODCM Revs 16,17 & 18 Are Encl,Iaw TS Section 6.14.2
ML20205R0431999-04-13013 April 1999
Forwards Correction to 960212 GL 95-07 180 Day Response. Level 3 Evaluation for Pressure Locking Utilized Analytical Models.Encl Page Has Been Amended to Correct Error
1999-09-23
[Table view]
Category:UTILITY TO NRC
MONTHYEARML20064A7131990-09-17017 September 1990
Advises That Due to Reassignment,Jj Clark No Longer Needs to Maintain Senior Reactor Operator Licenses
ML20059J2811990-09-14014 September 1990
Forwards List of Key Radiation Monitors Which Will Be Used as Inputs to Top Level Radioactivity Status Bar Re Spds.List Identifies Monitors Which Would Provide Concise & Meaningful Info About Radioactivity During Accidents
ML20065D5961990-09-13013 September 1990
Responds to Violations Noted in Insp Repts 50-348/90-19 & 50-364/90-19.Response Withheld
ML20059J1661990-09-13013 September 1990
Forwards Monthly Operating Rept for Aug 1990 for Jm Farley Nuclear Plant & Rev 10 to ODCM
ML20059L0751990-09-12012 September 1990
Forwards Revised Pages to Rev 3 to, Second 10-Yr Interval Inservice Insp Program for ASME Code Class 1,2 & 3 Components
ML20059J2911990-09-12012 September 1990
Forwards Operator Licensing Natl Exam Schedules for FY91 Through FY94,per Generic Ltr 90-07.Requalification Schedules & Estimated Number of Candidates Expected to Participate in Generic Fundamental Exam,Also Encl
ML20064A7111990-09-12012 September 1990
Forwards Rev 1 to Relief Request RR-1, Second 10-Yr Interval Inservice Insp Program for ASME Code Class 1,2 & 3 Components
ML20059J2891990-09-12012 September 1990
Confirms Rescheduling of Response to Fitness for Duty Program Notice of Violation 90-18-02,per 900907 Telcon
ML20065D6621990-09-12012 September 1990
Forwards NPDES Permit AL0024619 Effective 900901.Limits for Temp & Residual Chlorine Appealed & Stayed
ML20064A3431990-08-28028 August 1990
Forwards Corrected Insertion Instructions to Rev 8 to Updated FSAR for Jm Farley Nuclear Plant
ML20059D4711990-08-22022 August 1990
Forwards Fitness for Duty Performance Data for Jan-June 1990
ML20059B5101990-08-22022 August 1990
Forwards Semiannual Radioactive Effluent Release Rept for Jan-June 1990.No Changes to Process Control Program for First Semiannual Period of 1990 Exists
ML20056B2751990-08-20020 August 1990
Forwards Relief Requests from Second 10-yr Interval Inservice Testing Program for Class 1,2 & 3 Pumps & Valves. Request Incorporates Commitments in 891222 Response to Notice of Violation
ML20056B2741990-08-20020 August 1990
Forwards Rev 2 to Unit Inservice Testing Program,For Review & Approval.Rev Incorporates Commitments Addressed in Util 891222 Response to Notice of Violation & Other Editorial & Technical Changes
ML20058Q1481990-08-15015 August 1990
Forwards Rev 3 to FNP-1-M-043, Jm Farley Nuclear Plant Unit 1 Second 10-Yr Inservice Insp Program,Asme Code Class 1,2 & 3 Components
ML20058P6201990-08-15015 August 1990
Forwards Rev 1 to FNP-2-M-068, Ten-Yr Inservice Insp Program for ASME Code Class 1,2 & 3 Components, Per 891207 & 900412 Responses to NRC Request for Addl Info
ML20055G7701990-07-18018 July 1990
Updates 900713 Response to NRC Bulletin 90-001, Loss of Fill-Oil in Transmitters Mfg by Rosemount
ML20055F7411990-07-11011 July 1990
Forwards Monthly Operating Rept for June 1990 & Corrected Monthly Operating Repts for Nov 1989 Through May 1990.Repts Revised to Correct Typo on Value of Cumulative Number of Hours Reactor Critical
ML20055F3781990-07-10010 July 1990
Submits Final Response to Generic Ltr 83-28,Items 4.2.3 & 4.2.4.Util Position That Procedures Currently Utilized by Plant Constitute Acceptable Ongoing Life Testing Program for Reactor Trip Breakers & Components
ML20055D4861990-07-0202 July 1990
Requests Authorization to Use Encl ASME Boiler & Pressure Vessel Code Case N-395 Re Laser Welding for Sleeving Process Described by Oct 1990,per 10CFR50.55a,footnote 6
ML20055D1001990-06-26026 June 1990
Responds to Violations Noted in Insp Repts 50-348/90-12 & 50-364/90-12 on 900411-0510.Corrective Actions:Electrolyte Level Raised in Lights Identified by Inspector to Have Low Electrolyte Level
ML20044A6191990-06-26026 June 1990
Suppls 900530 Ltr Containing Results of SPDS Audit,Per Suppl 1 to NUREG-0737.One SPDS Console,Located in Control Room,Will Be Modified So That Only SPDS Info Can Be Displayed by Monitor.Console Will Be Reconfigured
ML20043G4741990-06-11011 June 1990
Submits Addl Info Re 900219 Worker Respiratory Protection Apparatus Exemption Rev Request.Proposed Exemption Rev Involves Features Located Entirely within Restricted Area as Defined in 10CFR20
ML20043C1851990-05-29029 May 1990
Forwards Proposed Schedules for Submission & Requested Approval of Licensing Items
ML20043B5941990-05-25025 May 1990
Provides Rept of Unsatisfactory Performance Testing,Per 10CFR26,App A.Error Caused by Olympus Analyzer Which Allowed Same Barcode to Be Assigned to Two Different Samples. Smithkline Taken Action to Prevent Recurrence of Scan Error
ML20042G7461990-05-10010 May 1990
Certifies That Plant Licensed Operator Requalification Program Accredited & Based Upon Sys Approach to Training,Per Generic Ltr 87-07.Program in Effect Since 890109
ML20042F0831990-05-0101 May 1990
Forwards Rev 18 to Security Plan.Rev Withheld
ML20042G3081990-04-25025 April 1990
Forwards Alabama Power Co Annual Rept 1989, Unaudited Financial Statements for Quarter Ending 900331 & Cash Flow Projections for 1990
ML20042E4121990-04-12012 April 1990
Provides Addl Info Re Review of Second 10-yr Inservice Insp Program,Per NRC 890803 Request.Relief Request RR-30 Requested Reduced Holding Time for Hydrostatically Testing Steam Generator Secondary Side
ML20012E9571990-03-27027 March 1990
Forwards Annual Diesel Generator Reliability Data Rept,Per Tech Spec 6.9.1.12.Rept Provides Number of Tests (Valid or Invalid),Number of Failures for Each Diesel Generator at Plant for 1989 & Info Identified in Reg Guide 1.108
ML20012D9661990-03-22022 March 1990
Forwards Annual ECCS Evaluation Model Changes Rept,Per Revised 10CFR50.46.Info Includes Effect of ECCS Evaluation Model Mods on Peak Cladding Temp Results & Summary of Plant Change Safety Evaluations
ML20012D8901990-03-20020 March 1990
Clarifies 891130 Response to Generic Ltr 83-28,Item 2.2.1 Re Use of Q-List at Plant,Per NRC Request.Fnpims Data Base Utilized as Aid for Procurement,Maint,Operations & Daily Planning
ML20012C4701990-03-15015 March 1990
Responds to NRC 900201 Ltr Re Emergency Planning Weaknesses Identified in Insp Repts 50-348/89-32 & 50-364/89-21. Corrective Actions:Cited Procedures Revised.Direct Line Network Notification to State Agencies Being Implemented
ML20012C6241990-03-14014 March 1990
Informs of Resolution of USI A-47,per Generic Ltr 89-19
ML20012C4651990-03-13013 March 1990
Provides Verification of Nuclear Insurance Reporting Requirements Specified in 10CFR50.54 w(2)
ML20012C2051990-03-0505 March 1990
Forwards SPDS Critical Function Status Trees,Per G West Request During 900206 SPDS Audit at Plant.W/O Encl
ML20012A1621990-03-0202 March 1990
Forwards Addl Info Inadvertently Omitted from Jul-Dec 1989 Semiannual Radioactive Effluent Release Rept,Including Changes to Process Control Program
ML20012A1301990-03-0101 March 1990
Responds to Generic Ltr 90-01 Re Request for Voluntary Participation in NRC Regulatory Impact Survey.Completed Questionnaire Encl
ML20043A7481990-02-0202 February 1990
Forwards Util Exam Rept for Licensed Operator Requalification Written Exams on 900131
ML20006D2311990-01-31031 January 1990
Responds to NRC Bulletin 89-003 Re Potential Loss of Required Shutdown Margin During Refueling Operations. Refueling Procedures Will Be Revised to Incorporate Guidance That Will Preclude Inadvertent Loss of Shutdown
ML20006A9091990-01-23023 January 1990
Forwards Response to Generic Ltr 89-13 Re Svc Water Sys Problems Affecting safety-related Equipment.Util Has Program to Perform Visual Insps & Cleanings of Plant Svc Water Intake Structure by Means of Scuba Divers
ML20005E4931989-12-28028 December 1989
Provides Certification That fitness-for-duty Program Meets 10CFR26 Requirements.Testing Panel & cut-off Levels in Program Listed in Encl
ML20005E3681989-12-28028 December 1989
Responds to Violations Noted in Insp Repts 50-348/89-28 & 50-364/89-28 on 891002-06.Corrective Actions:All Piping Preparation for Inservice Insp Work in Containment Stopped & All Participants Assembled to Gather Facts on Incident
ML20005E1971989-12-27027 December 1989
Responds to Violations Noted in Insp Repts 50-348/89-22 & 50-364/89-22 on 890911-1010.Corrective Actions:Steam Generator Atmospheric Relief Valve Closed & Core Operations Suspended.Shift Supervisor Involved in Event Counseled
ML20011D5041989-12-22022 December 1989
Responds to Violations Noted in Insp Repts 50-348/89-26 & 50-364/89-26.Corrective Actions:Personnel Involved in Preparation of Inservice Test Procedures Counseled. Violation B Re Opening of Pressurizer PORV Denied
ML19332F2111989-12-0707 December 1989
Forwards Final Response to NRC 890803 Request for Addl Info Re Review of Updated Inservice Insp Program,Summarizing Results of Addl Reviews & Providing Exam Listing Info
ML19332F0791989-12-0707 December 1989
Responds to Violations Noted in Insp Repts 50-348/89-22 & 50-364/89-22.Corrective Actions:All Managers Retrained on Intent of Overtime Procedures & Sys Established to Provide Independent Check of All Time Sheets Each Pay Period
ML19332F1141989-12-0707 December 1989
Forwards Description of Instrumentation Sys Selected in Response to Generic Ltr 88-17, Loss of DHR, Per Licensee 890127 Commitment.Hardware Changes Will Be Implemented During Unit 1 Tenth & Unit 2 Seventh Refueling Outages
ML19332F1241989-12-0707 December 1989
Forwards Response to NRC 890803 Request for Addl Info Re Review of Second 10-yr Inservice Insp Program,Per 891005 Ltr
ML19353B0071989-12-0606 December 1989
Forwards Rev 1 to Safeguards Security Contingency Plan.Rev Withheld
1990-09-17
[Table view] |
Text
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Alabama Power Company 600 North 18th Street .
Post Office Box 2641 Birmingham, Alabama 352914400 Telephone 205 2501837 i i
W. G. Hairston,Ill Senior Vice President I
Nuclear operations Alabama Power R July 12, 1988 !
Docket No. 50-348 U. S. ' Nuclear Regulatory Comnission ATIN: Document Control Desk Washington, D. C. 20555 Gentlemen:
Joseph M. Farley Nuclear Plant - Unit 1 NRC Bulletin 88-01:
Defects in Westinghouse Circuit Breakers (TAC 67665)
By letter dated June 9, 1988, Alabama Power Company submitted to the NRC a confirmrition letter on completion of short and long term inspections on Class lE Westinghouse Type DS breakers installed in Farley Nuclear Plant, Unit 1. As denoted in the June 9, 1988 letter, Alabama Power Company informed the NRC that, although not specifically required by NRC Bulletin 88-01, details of the inspections would be submitted by July 15, 1988. These details are hereby submitted and are shown in the attached.
If there are any questions, please advise.
Respectfully submitted, Id, b. h"-
W. G. Hairston, III WGH,III/RGW:mV.8.48 Attachment cc: Mr. L. B. Long Dr. J. N. Grace Mr. E. A. Reeves Mr. W. H. Bradford a
t\\
8807200370 880712 PDR ADOCK 05000348 O PDC 3
ATTACHMENT-Page 1
- EREMER CRITERIA NWEIER TYPE DESCRIPTION 601.1/ 6.1.2/ 6.2/ 7.1/ 7.2 OtseEmirs FA08 DS-416 Bus Tie Breaker F F M F
- Left Stop Lever Weld failed 7.1 due.to cracks and (Normal to Deergency) non-continuous weld.
Left Pole Lever Weld failed 6.1.1 and 6.1.2 due to porosity, undercut, splatter and profile.
Center Pole Lever Weld failed 6.1.1 rnd 6.1.2 due to insufficient weld length.
Anti-Bounce Iever Weld failed 7.1 due to profile, inclusion and undercut.
Right Pole Lever Weld failed 6.1.1 and 6.1.2 due to undersized weld.
New pole shaft installed.
FA09 DS-416 Alternate Supply F P R F
- Left Stop Lever Weld failed 7.1.
From 600V LC 1D Left Pole Lever Weld failed 6.1.1 and passed 6.1.2.
Center Pole Lever Weld failed 6.1.1 and passed 6.1.2.
Right Pole Lever Weld failed 6.1.1 and passed 6.1.2.
Right Stop Lever Weld failed 7.1.
New pole shaft installed.
FA10 DS-206 Containment F P NA F
- Left Pole Lever Weld failed 6.1.1 due to Cooler 1A - undersized weld and passed 6.1.2.
High Speed Center Pole Lever Weld failed 6.1.1 due to undersized weld and passed 6.1.2.
Anti-Bounce Lever Weld failed 7.1 due to insufficient weld length.
Right Pole Lever Weld failed 6.1.1 due to insufficient weld length and passed 6.1.2.
New pole shaft installed.
Fall DS-206 Pressurizer F F NA F
- Left Stop Lever Weld failed 7.1 due to Heaters - undersized weld.
Backup Group Left Pole Lever Weld failed 6.1.1 and 6.1.2 1.' . due to undersized weld.
Center Pole Lever Weld failed 6.1.1 and 6.1.2 due to undersized weld.
Right Pole Lever Weld failed 6.1.1 and 6.1.2 due to undersized weld.
P.ight Stop Lever Weld failed 7.1 due to undersized weld.
- 'Ihe new pole shafts were inspected and passed New pole shaft installed.
, Bulletin 88-01 Criteria 6.1.1, 7.1 and 7.2.
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Page 2 BREMER CRITERIA -
NUBEER TYPE DESCRIPTION 6.1.1/ 6.1.2/ 6.2/ 7.1/ 7.2 COMENTS EAl2 DS-206 Spent Fuel Pool F F NA F
- Left Pole Lever We m Siled 6.1.1 due to Pump 1B insufficient .seld length and passed 6.1.2.
Center Fale Lever Weld failed 6.1.1 and 6.1.2 due to insufficient weld length.
Lever for Auxiliary SW Drive length failed 7.1 due to lack of fusion.
Right Pole Lever Weld failed 6.1.1 and 6.1.2 due to insufficient weld length.
New pole shaft installed.
EA13 DS-206 Supply to F F NA F
- Left Stop Lever Weld failed 7.1 due to undersized Lighting weld.
Transformer Left Pole Lever Weld failed 6.1.1 and 6.1.2 due 1A to undersized weld.
Center Pole Lever Weld failed 6.1.1 and 6.1.2 due to undersized weld.
Anti-Bounce Lever Weld failed 7.1 due to undersized weld.
Right Pole Lever Weld failed 6.1.1 and 6.1.2 due to undersized weld.
Right Stop Lever Weld failed 7.1 due to undersized weld.
New pole shaft installed.
EA14 DS-206 Supply to F F NA F
- Left-Stop Lever Weld failed 7.1 due to Lighting undersized weld.
Transformer Left Pole Lever Weld failed 6.1.1 and 6.1.2 due 1B to undersized weld.
Center Pole Lever Weld failed 6.1.1 and 6.1.2 due to undersized weld.
Anti-Bounce Lever Weld failed 7.1 due to insufficient weld length.
Right Pole Lever Weld failed 6.1.1 and 6.1.2 due to undersized weld.
Right Stop Lever Weld failed 7.1 due to undersized weld.
New pole shaft installed.
o 'Ihe new pole shafts were inspected and passed Bulletin 88-01 Criteria 6.1.1, 7.1 and 7.2.
Page 3 BREAKER CRITERIA ~s NLEEER TYPE DESCRIPTION 6.1.1/ 6.1.2/ 6.2/ 7.1/ 7.2 00BGENTS EC08 DS-416 Bus Tie Breaker F F NA F
- Left Pole Lever Weld failed 6.1.1 due to (Normal to Emergency) undersized weld and passed 6.1.2.
Center Pole Lever Weld failed 6.1.1 due to insufficient weld length and passed 6.1.2.
Right Pole Lever Weld failed 6.1.1 and 6.1.2 due to undersized weld.
Right Stop Lever Weld failed 7.1 due to undersized weld.
New pole shaft installed.
EC09 DS-206 Spent Fuel Pool F F NA P
- Left Pole Lever Weld failed 6.1.1 and passed Pump 1A 6.1.2.
Right Pole Lever Weld failed 6.1.1 and 6.1.2 due to porosity.
New pole shaft installed.
EC10 DS-416 Alternate Supply F F NA P
- Left Pole Lever Weld failed 6.1.1 and passed From 600V LC lE 6.1.2.
Center Pole Lever Weld failed 6.1.1 and passed 6.1.2.
Right Pole Lever Weld failed 6.1.1 and 6.1.2 due to undersized weld.
New pole shaft installed.
EC11 DS-206 Pressurizer Heaters F F NA F
- Left Pole Lever Weld failed 6.1.1 due to Backup undersized weld ano passed 6.1.2.
Group 1B Center Pole Lever Weld failed 6.1.1 and 6.1.2 due to undersized weld.
Right Pole Lever Weld failed 6.1.1 due to undersized weld and passed 6.1.2.
Right Stop Lever Weld failed 7.1 due to undersized weld.
New pole shaft installed.
o The new pole shafts inspected were passed Bulletin 88-01 Criteria 6.1.1, 7.1, and 7.2
Page 4 IEEEAIGR CRITERIA '
NUBEER TYPE DESCRIPTIN 6.1.1/ 6.1.2/ 6.2/ 7.1/ 7.2 00BGE!NTS ECl2 DS-206 Containment F F NA F
- Left Stop Lever Weld failed 7.1.
Cooler 1D - Left Pole Lever Weld fu led 6.1.1 and passed High Speed 6.1.2.
Center Pole Lever Weld .fabe6 5.1.1 and 6.1.2.
Right Pole Lever Weld failed 6.1.1 and passed 6.1.2.
Right Stop Lever Weld failed 7.1.
Nes pole shaft installed.
Ecl3 DS-206 Supply to F F NA F
- Left Stop Lever Weld failed 7.1.
Lighting Left Pole Lever Weld failed 6.1.1 and 6.l.2.
Transformer Center Pole Lever Weld failed 6.1.1 and passed lE 6.1.2.
Anti-Bounce Lever Weld failed 7.1 due to arc strike and undercut.
Right Pole Lever Weld failed 6.1.1 and pasced 6.1.2.
Right Stop Lever Weld failed 7.1 due to undercut.
New pole shaft installed.
ECl4 DS-206 Supply to F F NA F
- Left Stop Lever Weld failed 7.1 due to lack of Lighting fusion.
Transformer Left Pole Lever Weld failed 6.1.1 and 6.1.2 due to 1F undersized weld and lack of fusion.
Center Pole Lever Weld failed 6.1.1 and 6.1.2 due to undersized weld, porosity and lack of fusion.
Anti-Bounce Lever Weld failed 7.1 due to undersized weld and lack of fusion.
Right Pole Lever Weld failed 6.1.1 and 6.1.2 due to undersized weld.
Right Stop Lever Weld failed 7.1 due to undersized weld.
New pole shaft installed.
- The new pole shafts were inspected and passed Bulletin 88-01 Criteria 6.1.1, 7.1, and 7.2 i
Page 5 BREMER CRT11!RIA IstmeER TYPE DESCRIPTION 6.1.1/ 6.1.2/ 6.2/ 7.1/ 7.2 00lWE!NTS ED02 DS-416 Station Service F F NA P
- Ieft Pole Lever Weld failed 6.1.1 and passed Transformer 6.1.2.
1D Center Pole Lever Weld failed 6.1.1 and pasted 6.1.2.
Right Pole Lever Weld failed 6.1.1 and 6.1.2.
New pole shaft installed.
ED03 DS-206 CRDM Motor F F NA F
- Left Pole Lever Weld failed 6.1.1 and 6.1.2 due to Generator undersized weld.
Ser lA Center Pole Lever Weld failed 6.1.1 and 6.1.2 due to undersized weld.
Anti-Bounce Lever Weld failed 7.1 due to undersized weld.
Right Pole Lever Weld failed 6.1.1 and passed 6.1.2.
New pole shaft installed.
ED04 DS--206 Battery Charger F P NA P
- Left Pole Lever Weld failed 6.1.1 and passed 1A (Auxiliary) 6.1.2.
Right Pole Lever Weld failed 6.1.1 and passed 6.1.2.
New pole shaft installed.
ED05 DS-206 Supply to F F NA F
- Left Stop Lever Weld failed 7.1.
MCC 1F Left Pole Lever Weld failed 6.1.1 and 6.1.2.
Center role Lever Weld failed 6.1.1 and 6.1.2.
Right Pole Lever Weld failed 6.1.1 and passed 6.1.2.
Right Stop Lever Weld failed 7.1.
New pole shaft Installed.
O n e new pole shafts were inspected and passed Bulletin 88-01 Criteria 6.1.1, 7.1 and 7.2
Page 6 BaENWR CRrtERIA NLEEER TYPE DESCRIPTION 6.1.1/ 6.1.2/ 6.2/ 7.1/ 7.2 COMENTS ED06 DS-206 Reactor Cavity F F NA F
- Left Pole Lever Weld failed 6.1.1 and 6.1.2 due to Dilution Fan lA insufficient weld length.
Center Pole Lever Weld failed 6.1.1 and 6.1.2 due to insufficient weld length.
Anti-Bounce Lever Weld failed 7.1 due to insufficient weld length.
Right Pole Lever Weld failed 6.1.1 due to undersized weld and passed 6.1.2.
New pole shaft installed.
ED08 DS-416 LC 1A F F NA F
- Left Pole Lever Weld failed 6.1.1 and 6.1.2.
Alternate Center ' ole Lever Weld failed 6.1.1 and 6.1.2.
Anti-Bounce Lever Weld failed 7.1.
Right Pole Lever Weld failed 6.1.1 and passed 6.1.2.
Right Stop Lever Weld failed 7.1.
New pole shaft installed.
ED09 DS-206 Battery Charger F F NA P
- Left Pole Lever Weld failed 6.1.1 due to 1C insufficient weld length and passed 6.1.2 .
Center Pole Lever Weld failed 6.1.1 and 6.1.2 due to insufficient weld length.
Right Pole Lever Weld failed 6.1.1 and 6.1.2 due to insufficient weld length and undersized weld.
New pole shaft installed.
- 'Ihe new pole shafts were inspected and passed Bulletin 88-01 Criteria 6.1.1, 7.1, and 7.2
Pap 7 ,
BRENWR CRITERIA NLNBER TYPE DESCRIPTION 6.1.1/ 6.1.2/ 6.2./ 7.1/ 7.2 COME!NTS ED10 DS-206 r.CC 1A F F NA F
- Left Stop Lever Weld failed 7.1 due to undersized weld.
Left Pole Lever Weld failed 6.1.1 due to undersized weld and passed 6.1.2.
Center Pole Lever Weld failed 6.1.1 and 6.1.2 due to undersized weld.
Anti-Bounce Lever Weld failed 7.1 due to undersized weld.
Right Pole Lever Weld failed 6.1.1 and 6.1.2 due to undersized weld.
Right Stop Lever Weld failed 7.1 due to porosity and undersized weld.
New pole shaft installed.
EDil DS-206 CRDM Cooling F F NA F
- Left Pole Lever Weld failed 6.1.1 and 6.1.2.
Fan 1B Center Pole Lever Weld failed 6.1.1 and passed 6.1.2.
Anti-Bounce Lever Weld failed 7.1.
Right Pole Lever Weld failed 6.1.1 and passed 6.1.2.
Right Stop Lever Weld failed 7.1.
New pole shaft installed.
ED12 DS-416 Alternate Feed F P NA P
- Left Pole Lever Weld failed 6.1.1 due to 600v LC 1F undersized weld and passed 6.1.2.
Center Pole Lever Weld failed 6.1.1 due to undersized weld and passed 6.1.2.
Right Pole Lever Weld failed 6.1.1 due to undersized weld and passed 6.1.2.
New pole shaft installed.
- 'Ihe new pole shafts were inspected and passed Bulle'.in 88-01 Criteria 6.1.1, 7.1 and 7.2.
Page 8 MEMER CRITERIA MUBEMIR TYPE DESCRIPTION 6.1.1/ 6.1.2/ 6.2/ 7.1/ 7.2 ODfEENTS ,
EDl3 DS-206 MCC 1S F F NA F
- Left Stop Lever Weld failed 7.1 due to undersized weld.
Left Pole Lever Weld failed 6.1.1 due to undersized weld and passed 6.1.2.
Center Pole Lever Weld failed 6.1.1 and 6.1.2 due to undersized weld.
Anti-Bounce Lever Weld failed 7.1 due to undersized weld.
Right Pole Lever Weld failed 6.1.1 due to undersized weld and passed 6.1.2.
Right Stop Lever Weld failed 7.1 due ta undersized weld.
New pole shaft installed.
EDl4 DS-206 MCC 1U F P NA F
- Left Pole Lever Weld failed 6.1.1 due to undersized weld and passed 6.1.2.
Center Pole Lever Weld failed 6.1.1 due to insufficient weld length and passed 6.1.2.
Lever for Auxiliary SW Drive Link Weld failed 7.1 due to lack of fusion.
Right Pole Lever Weld failed 6.1.1 due to lack of fusion and passed 6.1.2.
New pole shaft installed.
- '1he new pole shafts were inspected and passed Bulletin 88-01 Criteria 6.1.1, 7.1 and 7.2
Page 9' EEgDUWR CRITERIA MEWER TYPE MPrIm 6.101/ 6.1.2/ 6.2/ 7.1/ 7.2 00sengers EI)l5 DS-206 Containment F F NA F
- I4ft Stop Lever Weld failed 7.1 due to undersized Cooler weld.
IA - Low Speed Left Pole Lever Weld failed 6.1.1 and 6.1.2 due to undersized weld.
Center Pole Lever Weld failed 6.1.1 due to undersized weld and passed 6.1.2.
Right Pole Lever Weld failed 6.1.1 and passed.
6.1.2.
Right Stop Lever Weld iailea.7.1.
New pole shaft installed.
.\J
[
l I 1
\
EDl6 DS-206 Containment F F NA F
- Left Pole Lever Weld failed 6.1.1 and 6.1.2 due to -!
> Cooler 1B- insufficient weld length.
l Low Speed Center Pole Lever Weld failed 6.1.1 due to l insufficient weld length and passed 6.1.2.
) Anti-Bounce Lever Weld failed 7.1 due to l insufficient weld length.
l Right Pole Lever Weld failed 6.1.1 and 6.1.2 due to insufficient weld length.
Right Stop Lever Weld failed 7.1 due to insufficient weld length.
New pole shaft installed.
o The new pole shafts were inspected and passed Bulletin 88-01 Criteria 6.1.1 , 7.1 and 7.2.
l l
1 l
l
< s
Page 10 .
BRENWR CRTITRIA NLEEER TYPE DESCRIPTION 6.1.1/ 6.1.2/ 6.2/ 7.1/ 7.2 00leegrIS EE02 DS-416 Station Service F F NA F
- Left 3 top Lever Weld failed 7.1 due to Transformer 1E insufficient weld length.
Left Pole Lever Weld failed 6.1.1 and 6.1.2 due to lack of fusion and undersized weld.
Center Pole Lever Weld failed 6.1.1 due to undersized weld and passed 6.1.2.
Anti-Bounce Lever Weld failed 7.1 due to undersized weld.
Right Pole Lever Weld failed 6.1.1 and 6.1.2 due to undersized weld.
Right Stop Lever Weld failed 7.1 due to undersized weld.
New pole shaft installed.
EE03 DS-206 CRDM Motor F P NA P
- Left Pole Lever Weld failed 6.1.1 and passed Generator 6.1.2.
Set 1B Center Pole Lever Weld failed 6.1.1 and passed j
6.1.2.
Right Pole Lever Weld failed 6.1.1 and passed 6.1.2.
1 New pole shaft installed.
l 1
EE05 DS--206 Battery Charger F F NA F
- Left Pole Lever Weld failed 6.1.1 and 6.1.2 IB due to weld profile and undercut.
Center Pole Lever Weld failed 6.1.1 and 6.1.2 due to weld profile and porosity.
Anti-Bounce Lever Weld failed 7.1 due to weld profile and inclusions.
Right Pole Lever Weld failed 6.1.1 and 6.1.2 due to weld profile and porosity.
l Right Stop Lever Weld failed 7.1 due to undersized weld.
New pole shaft installed.
o The new pole shafts were inspected and passed Bulletin 88-01 Criteria 6.1.1, 7.1, and 7.2
Page 11 -
BETE N E R CPlTERIA lemmER TYPE DESCRIPTION 6.1.1/ 6.1.2/ 6.2/ 7.1/ 7.2 COBWENTS EE06 DS-206 Battery Charger F P NA P
- Left Pole Lever Weld failed 6.1.1 due to 1C insufficient weld length and passed 6.1.2.
Center Pole Lever Weld failed 6.1.1 due to insufficient weld length and passed 6.1.2.
Right Pole Lever Weld failed 6.1.1 due to insufficient weld length and passed 6.1.2.
New pole shaft installed.
EE07 DS-206 Alternate Feed F P NA F
- Left Stop Lever Weld failed 7.1 due to-600v LC 1C insufficient weld size.
Center Pole Lever Weld failed 6.1.1 and passed 6.1.2.
Lever for Auxiliary SW Drive Link Weld failed 7.1 due to undersized weld.
Right Pole Lever Weld failed 6.1.1 and passed 6.1.2.
Right Stop Lever Weld failed 7.1 due to undersized weld.
New pole shaft installed.
EE08 DS-206 Containment F F NA P
- Left Pole Iever Weld failed 6.1.1 due to Cooler undersized weld and passed 6.1.2.
1C - Center Pole Lever Weld failed 6.1.1. due to Low Speed undersized weld and passed 6.1.2.
Right Pole Lever Weld failed 6.1.1 and 6.1.2 due to undersized weld.
New pole shaft installed.
o The new pole shafts were inspected and passed Bulletin 88-01 Criteria 6.1.1, 7.1, and 7.2
Page 12 NEENER CRITERIA -
NIfEER TYPE DESJtIFFION 6.1.1/ 6.1.2/ 6.2/ 7.1/ 7.2 00meurs EE09 DS-206 Reactor Cavity F F NA F
- Left Stop Lever Weld failed 7.1 due to H2 Dilution Fan undersized weld.
1B Left Pole Lever Weld failed 6.1.1 due to undersized weld and passed 6.1.2.
Center Pole Lever Weld failed 6.1.1 and 6.1.2 due to undersized weld.
i Right Pole Lever Weld failed 6.1.1 due to insufficient weld length and passed 6.1.2.
Right Stop Lever Weld failed 7.1 due to insufficient weld length.
New pole shaft installed.
EE10 DS-206 MCC 1B F F NA F
- Left Stop Lever Weld failed 7.1 due to undersized weld.
Left role Lever Weld failed 6.1.1 due to undersized weld and passed 6.1.2.
Center Pole Lever Weld failed 6.1.1 and 6.1.2 due to porosity.
Anti-Bounce Lever Weld failed 7.1 due to undersized weld.
Lever for Auxiliary SW Drive Link Weld failed 7.1 due to lack of fusion.
Right Pole Lever Weld failed 6.1.1 due to undersized weld and passed 6.1.2.
Right Stop Lever Weld failed 7.1 due to underr.ized weld.
New pole shaft installed.
EEll DS-206 MCC 1G F F NA F
- Left Stop Lever Weld failed 7.1 due to undersized weld.
Left Pole Lever Weld failed 6.1.I and 6.1.2 due to undersized weld.
Center Pole Lever Weld failed 6.1.1 and 6.1.2 due to undersized weld.
Right Pole Lever Weld failed 6.1.1 and 6.1.2 due to undersized weld.
Right Stop Lever Weld failed 7.1 due to undersized weld.
New pole shaft installed.
- The new pole shafts were inspected and passed Bulletin 88-01 Criteria 6.1.1, 7.1, and 7.2
Page 13 m CdTSIA REWER TYPE DESCRIPTION 6.1.1/ 6.1.2/ 6.2/ 7.1 / 7.2 00BGE!NTS EE12 DS-416 Alternate Feed F P !& P
- Left Pole Lever Weld failed 6.1.1 due to 600v LC 1F undersized weld and passed 6.1.2.
Center Pole Lever Weld failed 6.1.1 due to undersized weld and passed 6.1.2.
Right Pole Lever Weld failed 6.1.1 due to undersized weld and passed 6.1.2.
New pole shaft installed.
i EE13 DS-206 CRDM Cooling F P fa F
- Left Pole Lever Weld failed 6.1.1 due to
, Fan IA undersized weld and passed 6.1.2.
Center Pole Lever Weld failed 6.1.1 due to undersized weld and passed 6.1.2.
Anti-Bounce Lever Weld failed 7.1 due to undersized weld.
Right Pole Lever Weld failed 6.1.1 due to undersized weld and passed 6.1.2.
New pole shaft installed.
EE14 DS-206 MCC IT F P !& F
- Left Pole Lever Weld failed 6.1.1 and passed 6.1.2.
3 Center Pole Lever 'Aeld failed 6.1.1 and passed 6.1.2.
Right Pola LLver Weld fl.iled 6.1.1 and passed 6.1.2.
Right Stop Lever Weld failed 7.1 New pole shaft installed.
o 'Ihe new pole shafts were inspected and passed Bulletin 88--01 Criteria 6.1.1, 7.1, and 7.2
Page 14 EEgmKER CRITERIA asseER TYPE DESCRIPTION 6.1.1/ 6.1.2/ 6.2/ 7.1/ 7.2 00BGE N TS EE15 2S-206 MCC lV F F NA F
- Left Stop Lever Weld failed 7.1 due to undersized weld.
Left Pole Lever Weld failed 6.1.1 due to insufficient weld length and passed 6.1.2.
Center Pole Lever Weld failed 6.1.1 and 6.1.2 due to lack of fusion.
Right Pole Lever Weld failed 6.1.1 and 6.1.2 due to porosity.
New pole shaft installed.-
EE16 DS-206 Containment F F NA F
- Left Pole Lever Weld failed 6.1.1 and 6.1.2 Cooler ID due to insufficient weld length.
Low speed Center Pole Lever Weld failed 6.1.1 due to undersized weld and passed 6.1.2.
Anti-Bounce Lever Weld failed 7.1 due to undersized weld.
Right Pole Lever Weld failed 6.1.1 due to undersized weld and passed 6.1.2.
Right Stop Lever Weld failed 7.1 due to undersized weld.
New pole shaft installed.
- The new p>1e shafts were inspected and passed Bulletin 38-01 Criteria 6.1.1, 7.1, and 7.2
^
Page 15 MIENWR -
CRITERIA NLEWER TYPE DESCRIPTION 6.1.1/ 60102/ 602/ 701/ 7.2 CDEENTS EF03 DS-416 Alternate Feed F P NA F
- Left Stop Lever Weld failed 7.1 due to undersized to 600V LC 1A weld.
Left Pole Lever Weld failed 6.1.1 due to undersized weld and passed 6.1.2.
Center Pole Iever Weld. failed 6.1.1 due to insufficient weld length and passed 6.1.2.
Lever for Auxiliary SW Drive Link failed 7.1 due to porosity.
Right Pole Lever Weld failed 6.1.1 due to insufficient weld length and passed 6.1.2.
New pole shaft installed.
EH02 DS-206 Station Service P NA NA P P EH02 passed all criteria.
Transformer 1H EH03 DS-206 MCC 1X F F NA F
- Left Stop Iever Weld failed 7.1 due to undersized weld.
Left Pole Lever Weld failed 6.1.1 and 6.1.2 due to undersized weld.
Center Pole Lever Weld failed 6.1.1 and 6.1.2.
Anti-Bounce Lever Weld failed 7.1 due to undersized weld.
Right Pole Lever Weld failed 6.1.1 and 6.1.2 due to undersized weld.
New pole shaft installed.
EH05 DS-206 Tie Breaker F P NA P
- Left Pole Lever Weld failed 6.1.1 due to undersized LC 1H - LC 2H weld and passed 6.1.2.
Center Pole Lever Weld failed 6.1.1 due to undersized weld and passed 6.1.2.
Right Pole Lever Weld failed 6.1.1. due to undersized weld and passed 6.1.2.
New pole shaft installed.
o The new pole shafts were inspected and passed Bulletin 88-01 Criteria 6.1.1, 7.1 and 7.2
Page 16 BaupuGR CRP MtIA leismER TYPE DESCRIPTICBI 6.1.1/ 6.1.2/ 6.2/ 7.1/ 7.2 COEWEENTS EH09 DS-206 River Water F F NA P
- Left Pole Lever Weld failed 6.1.1 and 6.1.2 due to Screen Wash insufficient weld length.
Pump 1A Center Pole Lever Weld failed 6.1.1 due to insufficient weld length and passed 6.1.2.
Right Pole Lever Weld failed 6.1.1 and passed 6.1.2.
New pole shaft installed.
EJ02 DS-206 Station Service F F NA F
- Left Stop Lever Weld failed 7.1 due to undersized Transformer IJ weld and insufficient weld length.
Left Pole Lever Weld failed 6.1.1 and passed 6.1.2.
Center Pole lever Weld failed 6.1.1 and passed 6.1.2.
Anti-Bounce Lever Weld failed 7.1 due to undersized weld.
Right Pole Lever Weld failed 6.1.1 and 6.1.2 due to undersized weld.
Right Stop Lever Weld failed 7.1 due to undersized weld.
New pole shaft installed.
EJ03 DS-206 River Water F F NA F
- Left Pole Lever Weld failed 6.1.1 and 6.1.2 due to Screen Wash undersized weld.
Pump 1B Center Pole Lever Weld failed 6.1.1 and 6.1.2 due to undersized weld.
Anti-Bounce Lever Weld failed 7.1 due to undersized weld.
Right Pole Lever Weld failed 6.1.1 due to undersized weld and passed 6.1.2.
Right Stop Lever Weld failed 7.1 due to undersized weld.
New pole shaft installed.
- The new pole shafts were inspected and passed Bulletin 88-01 Criteria 6.1.1, 7.1, and 7.2.
q Page 17 ,
M OtITERIA ~
MBEER TYPE DESCRIPTIGt 6.1.1/ 6.1.2/ 6.2/ 7.1/ 7.2 atzeenrrs EJ05 DS-206 Tie Breaker F P NA P
- Center Pole Lever Weld failed 6.1.1 due to lack of Ir1J - LC2J fusion and passed 6.1.2.
Right Pole Lever Weld failed 6.1.1 due to undersized weld and passed 6.1.2..
New pole shaft installed.
EJ09 DS-206 MCC 1Y F P NA P
- Left Pole Lever Weld failed 6.1.1 and passed 6.1.2.
Center Pole Lever Weld failed 6.1.1 and passed 6.1.2.
Right Pole Lever Weld failed 6.1.1 and passed 6.1.2.
New pole shaft installed.
- The new pole shafts were inspected and passed Bulletin 88-01 Criteria 6.1.1, 7.1 and 7.2.
~
Page 18 BEEN2R CRITERIA ,
sameER TYPE DSSCRIPTI N 6.1.1/ 6.1.2/ 6.2/ 7.1/ 7.2 00psmarts EK02 DS-206 Station Service F P R P
- Left Pole Lever Weld failed 6.1.1 due to Transformer 1K undersized weld and passed 6.1.2.
Center Pole Lever Weld failed 6.1.1 due to undersized weld and passed 6.1.2.
Right Pole Lever Weld failed 6.1.1 due to undersized weld and passed 6.1.2.
New pole shaft installed.
EK03 W 206 MCC 1K F F M F
- Left Pole Lever Weld failed 7.1 due to undersized weld.
Left Pole Lever Weld failed 6.1.1 and 5.1.2 due to insufficient weld length and undersized weld.
Center Pole Lever Weld failed 6.1.1 and 6.1.2 due to lack of fusion and undersized weld.
Right Pole Lever Weld failed 6.1.1 and 6.1.2 due to undersized weld.
New pole shaft installed.
EK05 DS-206 Tie Breaker F F NA F M Left Stop Lever Weld failed 7.1 due to undersized weld.
Left Pole Iever Weld failed 6.1.1 and 6.1.2 due to undersized weld.
Center Pole Lever Weld failed 6.1.1 and 6.1.2 due to lack of fusion.
Lever for Auxiliary SW Drive Link Weld failed 7.1 due to lack of fusion.
Right Pole Lever Weld failed 6.1.1 due to undersized weld and passed 6.1.2.
New pole shaft installed.
- 'Ihe new pole shafts were inspected and passed Bulletin 88-01 Criteria 6.1.1, 7.1 and 7.2.
~
Page 19 BREMtER CRITERIA
- utseER TYPE DESCRIPTION 6.1.1/ 6.1.2/ 6.2/ 7.1/ 7.2 COMENTS EK09 DS-206 River Water F P NA F
- Left Pole Lever Weld failed 6.1.1 due to screen Wash insufficient weld length and passed 6.1.2.
Pump Center Pole Lever Weld failed 6.1.1 due to undersized weld and passed 6.1.2.
Right Pole Lever Weld failed 6.1.1 due to insufficient weld length and passed 6.1.2.
Right Stop Lever Weld failed 7.1 dee to undersized weld.
New pole shaft installed.
ELO2 DS-206 Station Service F P NA P
- IAft Pole Lever Weld failed 6.1.1 due to Transformer lL undersized weld and passed 6.1.2.
Center Pole Lever Weld failed 6.1.1 due to undersized weld and passed 6.1.2.
Right Pole Iever Weld failed 6.1.1 due to undersized weld and passed 6.1.2.
New pole shaft installed.
- The new pole shafts were inspected and passed Bulletin 88-01 Criteria 6.1.1, 7.1 and 7.2
Page 20 BIENER Otr MtIA BEBEIER TYPE NYPTIN 6.1.1/ 6.1.2/ 6.2/ 7.1/ 7.2 CK3egarrs ELO3 DS-206 Service Water Screen F F NA F
- Left Pole Lever Weld failed 6.1.1 due to Wash Pump 1B undersized weld and passed 6.1.2.
Center Pole Lever Weld failed 6.1.1 and 6.1.2 due to insufficient weld length.
Anti-Bounce Lever Weld failed 7.1 due to insufficient weld length.
Right Pole Lever Weld failed 6.1.1 and 6.1.2 due to undersized weld.
Right Stop Lever Weld failed 7.1 due to undersized weld.
New pole shaft installed.
ELOS DS-206 Tie Breaker F F NA F
- Left Stop Lever Weld failed 7.1 due to undersized LC lL - LC 2L weld.
Left Pole Lever Weld failed 6.1.1 due to undersized weld and passed 6.1.2.
Center Pole Lever Weld failed 6.1.1 and 6.1.2 due to lack of fusion.
Anti-Bounce Lever Weld failed 7.1 due to lack of fusion.
Right Pole Lever Weld failed 6.1.1 dand 6.1.2 due to porosity.
Right Stop Lever Weld failed 7.1 due to undersi2.ed weld.
New pole shaft installed.
f ELO9 DS-206 MCC IL F F NA F = Left Stop Lever Weld failed 7.1.
Left Pole Lever Weld failed 6.1.1 and 6.1.2.
Ces.ter Pole Iever Weld failed 6.1.1 and 6.1.2.
Anti-h'. mce Lever Weld failed 7.1.
Right Polt. Lever Weld failed 6.1.1 and passed 6.1.2.
Right Stop taver Weld failed 7.1 New pole shaft installed.
o The new pole shafts were inspected and passed Bulletin 88-01 Crit.cria 6.1.1, 7.1, and 7.2
_w
Page 21 EnEMmm asseER TYPE DESCRIPTION 6.1.1/ 6.1.2/ 6.2/ 7.1/ 7.2 CDIWEINTS ER02 DS-206 Station Service F P NA F
- Left Stop Lever Weld failed 7.1 due to lack of Transformer 1R fusion.
Left Pole Lever Weld failed 6.1.1 due' to undersized weld and passed 6.1.2.
Center Pole Lever Weld failed 6.1.1 due to -
undersized weld and passed 6.1.2.
Right Pole Lever Weld failed 6.1.1 due to insufficient weld length and passed 6.1.2.
New pole shaft installed.
ER03 DS-206 MCC IN F P NA F
- Left Pole Lever Weld failei 6.1.1 due to undersized weld and passed 4.1.2.
Center Pole Lever Weld fail d 6.1.1 due to undersized weld and passed 0.1.2.
Right Pole Lever Weld failed 6.1.1 and passed 6.1.2.
Right Stop Lever Weld failed 7.1 due to undersized weld.
New pole shaft installed.
EROS DS-206 Station Sesvice F P NA P
- Left Pole Lever Weld failed 6.1.1 due to Transformer M insufficient weld length and passed 6.1.2.
Center Pole Iever Weld failed 6.1.1 due to insufficient weld length and passed 6.1.2.
Right Pole Lever Weld failed 6.1.1 due to insufficient weld length and passed 6.1.2.
New pole shaft installed.
ES02 DS-206 Station Service F P NA F
- Left Pole Lever Weld failed 6.1.1 due to Transformer undersized weld and passed 6.1.2.
1S Center Pole Lever Weld failed 6.1.1 due to undersized weld and passed 6.1.2.
Lever for Auxiliary SW Drive Link Weld failed 7.1 due to lack of fusion.
Right Pole Lever Weld failed 6.1.1 due to undersized weld and passed 6.1.2.
New pole shaft installed.
- '1he new pole shafts were inspected and passed Bulletin 88-01 Criteria 6.1.1, 7.1, and 7.2
Page 22 BIEE N G R CRITERIA IEEEER 6.1.1/ 6.1.2/ 6.2/ 7.1/ 7.2 TTPE DESCRIFFI(DI 00Essarts ES03 DS-206 MCC 1P F F NA F
- Left Stop Lever Weld failed 7.1.
Left Pole Lever Weld failed 6.1.1 and passed 6.1.2.
Center Pole Lever Weld failed 6.1.1 and 6.1.2.
Right Pole Lever Weld failed 6.1.1 and passed 6.1.2.
New pole shaft installed.
j ESO4 DS-206 600V F F NA F
- Left Stop Lever Weld failad 7.1 due to undersized I
Distribution weld.
Panel FPPH Left Pole Lever Weld failed 6.1.1 and 6.1.2 due to undersized weld.
Center Pole Lever Weld failed 6.1.1 and 6.1.2 due to porosity.
Right Pole Lever Weld failed 6.1.1 due to undersized weld and passed 6.1.2.
Right Stop Lever Weld failed 7.1 due to lack of fusion.
New pole shaft installed.
- The new pole shafts were inspected and passed Bulletin 88-01 Criteria 6.1.1, 7.1 and 7.2
Page 23 EEENDER CRITERIA :
IEEEER TYPE DESCRIPTION 6.1.1/ 6.1.2/ 6.2/ 7.1/ 7.2 00ssearts
- ES05 DS-206 Tie Breaker F F NA F
- Left Pole Lever Weld failed 6.1.1 due to LC ls - LC 25 undersized weld and passed 6.1.2.
Center Pole Lever Weld failed 6.1.1. due to undersized weld and passed 6.1.2.
Right Pole Lever Weld failed 6.1.1 and 6.1.2 due to porosity. .
Right Stop I4ver Weld failed 7.1 due to undersized weld.
New pole shaft installed.
ES07 DS-206 MCC II F F NA F
- Left Pole Lever Weld failed 6.1.1 due to undersized weld and passed 6.1.2.
Center Pole Lever Weld failed 6.1.1 and 6.1.2 due to lack of fusion and undersized weld.
Anti-Bounce Lever Weld failed 7.1 due to lack of fusion.
Right Pole Lever Weld failed 6.1.1 due to undersized weld and passed 6.1.2.
Right Stop Iever Weld failed 7.1 due to insufficient w ld length.
New pole shaft installed.
- 'Ihe new pole shafts were inspected and passed Bulletin 88-01 Criteria 6.1.1, 7.1, and 7.2
