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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
C:lling Address Alabama Power Company 600 Nortn 18th Street Post Office Dox 2641 Birmingham Alabama 35291 Telephone 205 783-6090 R. P. Mcdonald Senior Vice President Flintridge Buildin Mabanla POW'M July 10, 1985 ,
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Docket Nos. 50-348 50-364 Director, Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D.C. 20555 Attention: Mr. S. A. Varga Joseph M. Farley Nuclear Plant - Units 1 and 2 Containment Tendon Anchorhead Failure Reports - Unit 2 Gentlemen:
During meetings held on February 7 and March 1,1985 to discuss tendon anchorhead failures at the Joseph M. Farley Nuclear Plant - Unit 2, Alabama Power Company provided the NRC with its preliminary findings and with a commitment to update these findings after Inryco investigation reports were available. Attachment 1 provides the results of the Inryco investigation which concludes that the tendon anchorheads failed as a result of hydrogen stress cracking caused by moisture in the environment of the tendon anchorheads. Enclosed with Attachment 1 is the Inland Steel Metallurgical Laboratory Report, the Battelle Report and a summary of the load tests and magnetic particle test results as well as the results of the Suburban Laboratories grease sample analyses. Attachment 2 provides a list of minor corrections to the two reports enclosed as part of Attachment 1.
The tendon anchorage inspection and replacement programs have been completed for Units 1 and 2. Laboratory analysis of additional anchors is in progress. Details of the inspection and replacement program and results of additional anchorage analyses will be provided in a supplemental LER.
If there are any questions, please advise.
Yours truly, S
0 850710 K 05000348 gl,). lbrM 5 PDR
'fy '
R. P. Mcdonald /
p' (M h(
RPM / JAR:bdy-D28 Attachments '72 U cc: Mr. L. B. Long Dr. J. N. Grace f/g Mr. E. A. Reeves /
Mr. W. H. Bradford J
INRYCO, Inc.
. C.:ncr't2 Systtms Di*tision 7200 S. N rraginsett Avinus Bedford Park L Chic:go,Illin:is 60638-6087 312 585 7300 Chicago 312 594 7300 Suburban /
TLX 721497 BDPK e ggi l[jj FAX: Ext. 202 InryCO 4 . / ,'
June 3, 1985 y/
V WGHY N M
. JEG "
I DEM Mot JWM wec HDT Alabama Power Co.
P.O. Box 2641 00C. N Bitiningham, AL 35291 Attention: Mr. W. G. Hairston III
SUBJECT:
Joseph M. Farley Nuclear Plant - Unit 2 Failure Investination
Dear Mr. Hairston:
The reports of the anchorhead failures contain minor errors.
They are hereby corrected with the enclosed addenda.
Very truly yours, a H e inager, Contract Management JWH:lgw Enc.
I an inland Steel company
INRYCO, Inc.
l W. G. Hairston Alabama Power Co.
June 3, 1985 ADDENDUM 1 TO METALLURGICAL LABORATORY. INVESTIGATION NO. 19975 - FINAL REPORT INRYCO POST TENSIONING DIVISION JOSEPH M. FARLEY NUCLEAR PLANT, UNIT 2 -
ANCHORHEAD INVESTIGATION Page 1 Line 3 - Correct "Dolton" to read "Dothan".
Page 2. Item 2, line 3 - Correct "nacent" to read " nascent".
Page 1. Introduction, line 1 - Correct "Dolton" to read "Dothan".
Page 1. Investigation No. 19975, line 11 - Correct "three anchorages" to read 4 "two anchorages".
Page 2 Investigation No. 19975, lines 13 and 14 - Correct "... January 25, {
1985. During a 30 day refueling shutdown...." to read "... January 27, 1985.
During a refueling shutdown...".
Page 16 Investigation No. 19975, line 26 and 27 - Revise to read "In addition a water sample obtained from the cover on V-21 was sent to Suburban Laboratory for analysis. The test result was subsequently sent in an Inryco transmittal dated 4-16-85."
Page 17. Investigation No. 19975, line 19 - Correct "nacent" to read " nascent".
l I
t an inland Steel company f
INRYCO, Inc.
$ W. G. Hairston Alabama Power Co.
June 3, 1985 ADDENDUM 1 TO BATTELLE FINAL REPORT DATED APRIL 9, 1985 CW l
INVESTIGATION OF FAILED FIELD ANCHOR HEADS MV016 AND HV038 FROM THE J. M. FARLEY.
NUCLEAR POWER PLANT, UNIT 2 CONTAInumrT l
Page 21, last line, last word - Delete "tt".
Page 27 second to'last line - Correct " failed" to read " failure".
Page 32, line 19 - Correct "A3222" to read "A322".
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an inland Steel company
I INRYCO, Inc.
Concr:te Syst:ms Dreisi:n 7200 S. N:rrtgensett Avenu3
, Bedf rd Park Chic go,lihnois 60638 6087
- Y 312 585 7300 Chicago 312 594 7300 Suburban TLX 721497 BDPK FAX: Ext. 202 W i i
April 16, 1985
~
\
Alabama Power Company P.O. Box 2641 Birmingham, Alabama 35219 Attention: Mr. W. C. Hairston III SUBJgCT: Joseph M. Farley Nuclear Power Plant Containment Building 2 Failure Investigation of Post Tensioned Field Anchorheads HV016 and HV038
Dear Mr. Hairston:
We are enclosing reports entitled " Joseph M. Farley Nuclear Plant, Unit No. 2, Anchorhead Investigation: Metallurgical Laboratory Investigation No. 19975 - Final Report" dated March 27, 1985, from l
Inland Stool Co. and Final Report dated April 9, 1985 from Battelle Columbus Laboratories. Inryeo generated ti.ese reports as part of the subject failure investigation at your request: Your P.O. #40578 Dated 1/29/85, as Amended.
These investigations concluded that the anchorheads failed as a result of hydrogen stress cracking caused by the moisture in the l environment of the anchorhead. Intergranular separation (ICS) was l found on the fracture faces supporting the embrittlement l conclusion. The labs also found evidence of water, both in the I grease can that surrounds the anchorage, as well as grease on the l anchorhead of HV038. '
As stated in meetings with the NRC, the source of water might be from rain, water present during installation or from ground water.
The environment of the anchorhead must be free of water to preclude further anchorhead problems.
an inland Steel company
_ _~_ _ __. - .. - - - - - - . .. - - - - - --
INRYCO, Inc.
s Mr. W. G. Hsirstes III Alabama Power Co.
Page Two April 16, 1985
.The presence of water in contact with high strength steel (the anchorhead), stressed to a high value, and also in contact with Zinc constituted a galvanic corrosion cell. The corrosipn reaction
- released nascent hydrogen at the steel surface and oxidized the zinc. The hydrogen thus released entered the atomic lattice of the
~
steel and caused cracking of the highly stressed steel. The cracks continued to grow as long as the galvanic action continued to produce nascent hydrogen, until it reached critical dimensions, at which point complete failure of the remainder of the anchorhead occurred. These final crack paths were transgranular (cleavage) and even ductile.
The origin of the cracks was typically in the perforated region, on the shim surface; in the conter of the anchorhead. Once they were initiated the cracks propagated radially from ligament to ligament, as well as upward in the direction of the anchorhead depth. Final failure occurred when the crack entered the unperforated portion of the anchorhead and propagated radially outward and upward through the last piece of resistance.
There are several other failure mechanisms that result in intergranular cracking. They were ruled out on the basis of our testing as outlined in the reports. Temper-Embrittlement was an early candidate that we subsequently eliminated based on the fact that the unfractured portions of the steel had high strength and ductility characteristics. This was also coupled with the fact that temper-embrittlement is not time - dependent. Certain anchors were re-tempered and showed no significant differences in properties from the other anchorheads. In general, the anchorhead steel unaffected by Hydrogen had good to excellent tenslie properties, and would not have failed in a neutral environment.
1 an inland Steel company
INRYCO, Inc.
d .
Mr. W. G. Hairston III Alabama Power Co.
Page Three April 15, 1985 Inland Steel Co., Operating Technology Department and Battelle Columbus Laboratories performed all metallurgical evaluation.
Inland Steel also performed the grease analyses. Additional grease analyses were done at suburban Laboratories, Hinsdale, Illinois.
The structural laboratory at the University of Illinois, Chanpaign-Urbana, performed the load test. Magnetic Particle tests were conducted at our own facilities. Copies of these have been previously submitted and are submitted for completeness.
Very truly yours,
/t k H se
% nager, Contract Management JH:1gw Enclosures .
cc: Mr. D. Mansfield, Alabama Power Co.
Mr. R. Lawler Mr. H. Hendrickson Mr. D. Waitkus Mr. H. Presswalla l
)
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-... . . . .r - . . . ~
FARLEY NUCLEAR POWER PLANT - 417-2400 "
ANCHORHEAD TESTING
SUMMARY
FORM FNP-ATP-8 ANCHOR Mo. OF CRACKS (MPT) man TEST COMPOSITION MEAD TOP MECHANICAL TESTING (transverse) METarrm;tAPNY FRACTOGRAFNY BOT PULT MODE 4140/42 ? TS (ksi) YS 'ksi) RA (%)
I.D. PRE POST PRE Posf % GUTS GRAIN INCLUSION (REMARES) l L= Minh Loet Minh Lott Minh SIZE RATING NV0161 -- -- -- --.
A3-4M flex YES 199 201 164 168 13.9 18.6 8 or 32N ICS and i
failure finer temo M cleavane MV0381 -- -- - - - flex YES 193 202 161 161 11.1 13.4 A3-4N failure temo M MV039 0 0 3 12 137 A3-4M ICS on flex YEs 200 207 170 184 15.9 15.9
' 32N' pro cracks crack tems M ' only MV028 0 0 0 0 140 some A3-4M YES 192 203 159 173 ' 10.7 14.5 33M No ICs teso M MV0272 0 0 0 13 115 A3-4M flex YEs 183 191 157 168 5.5 14.1 crack 32M No ICs temo M MV049I O O 0 11 120 flex A3-4H YES 188 196 156 175 9.3 17.4 32N No ICs
_ crack temo M i
NOTE: 1) Fiele Failure of Aachorbead
- 2) Rotempered 0 830*F. for 4 hrs. before load test *
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STRUCTURAL TESTING ANCHORNEADS PROCEDURE QC TESTING DOCUMENTATION FOAM FNP-LT BF anIniend Steelcompany sold 30185 FA!!AFRK Lead LOAD IN & 9F REMARES LOAD IN EIPS 1178 MMM 4- TENDON SFTS Eleutes Target Asteal Asteel Describe treature TIIB Target Astual or other evoets.
. 1.0 S00 500
~ .
1.0 1000 I***
1.0 1500 JJoa f
1.0 1s00 JF00 203^ 8 1%$ -l ,
1.0 2000 2,888 W~
2 9m0-I'1 (Y
- c = i 1.0 2200 22.* 4 2 fee - I l!#*
~
1.0 2400 2y00 1.0 26002Ge
- Fracters Lead or 2.0 2800 2.90o Fra hPT_CfEKS
- Fest WT Aacherhead Nest Code N Y#3 I Bataland Distorties at 2800 EiFs MFA7[ Bushing Beat Code M!A visible cracks YU [(WT(# w tt -
e Acca YEI Reject M*Lvsmskrost$t Back ties setse is emitted during testing, that valse in Elps will be desumsated.
Data Recorded by:
p y, sissed b .M .'
Title 7M 9W c v '
A. , ~C" ( h .'
nat. '2.-It-95 Witaama:
81.med AR 1 A m ne mein a,L. n y Agency b A Y1) bgLg 1A I
(-
a E:"" 2-18-85 ZZ,A
- d*5**iA N flP$(-8*Se f RFf D f or
2-J
'Y STRUCTURAL TRSTING ANCMORMEADS PROCROURE QC TESTING DOCUMENTATION FORM FNP-LT SP an intend Steelcorneeny Nold 30185 PAILUBE l Lead LOAD IN % OF RENARES 1AAD IN EIPS EIPS MODE 8( TENDON SUTS i
Niestes farset Actual Asteal Tm Desaribe feastere l Target Astual or other events. I
. 1.0 ' S00 500 1.0
i 1.0 1800 l800 1
1.0 2000 1 8'8
, s..
1.0 2200 22 oo .
1.0 2400 1400 1.0 2600 1600 Fractura Load or t.0 2800 2. W*
- Pro MPT Op2[9/85 Post MPT Aashorhead Neat Code M VO 2.8 Retataed Distortion at 2800 Eips M#MI Dushiss Neat Code M/A ,
)
Visible Cracks N a#6 Accept YES tejoet Each time noise is emitted during testing, that value is Elps will be desamented.
j Data Recorded by:
M%h 179E sissed b T7/=d- r' WD # ^^ h l sit 1. -fA w -
us.., L '
Date . i,1 - /9- IES,Mf
, l i
Witness I
)
Sissed , 1 sitte a rf u vaL -w i h K s e rn sS..., 4..lsJ l
Date A,A_./X
'JL","a 2 18-8s ;;;;;=,A ra.-
,. m ..,
=a -> A 1 .f I
...c..... I
P 95 l
STRUCTURAL TESTING ANCMORMIADS TESTING DOCUMENTATION F0ml FWF-LT OF PROCEDURE QC 4 kwyce aninland Steelcomparv E
Mold NOISE FAILURE 14&D IN 5 QF f Emed Le&D IN EXPS EIPS REua323 NDOS E TWID05 SffS
- Ninetes , Target Asteal Amtsel TDE Target Describe feastsee Astsel er other events.
. 1.0 ,
500 5*o .
1.0 1000 I888 h 1.0 1500 1500 1.0 1800 lSOO 1.0 2000 2.o a o g' A #5 l 1.0 2200 2200 1.0 2400 2. Y a o 1.0 2600 2.680 9%:,
2tff e resetsre 1Sf
- 2. c eeo yI [ y j - -
.m. ,
.0 .0 .... =.
1 70.
. a-
/ 2.Y W .
are urf OK 2/'8I6Feet BrT_ )
Asenerhead meat code _)Mo2.!?
Batained Distorties at 2000 ElFs Aieuf mushias meat code M/A
! Yksible Cracks NONI Assept _ YES Reject Beek time satse is emitted during testias, that valse la Rips will he desumented.
Data Recorded by:
81need %WY. ,d g et Fy,*g g y4 % y,p,ggy Title 7M W f C': -- V"C5 -
Ageesy nV
.N-Bete le } 9
l -
} MhAAAA8 sisned k N Title mstAbiAas A bl & W Aseesy Sk &l ,
Date W2wW
/I ~
d["'* 2-18-85
[OA *
,,, n y . . o r...... ...
q p.
r STRUCTURAL TESTING ANCMORNEADS PROCBDURE QC sust y w w TESTING DOCUMENTATION FORM FNF-LT DF en intend Steelesmeeny sold 301st FAttygg. EAAD IN E OF Lo.4 IAAD 1m EIPs REMAREs EXPs 2 0s &- Tsuen W Ts Minetes Target Asteal Actual Describe feastare TIIE ., Target Actual er other events.
W
. 1.0 500 500 1"" ' # g* f~* "4 '
1.0 1000 1888 1 G ** * - 1 1.0 1500 I5*o 3*19*-I ,-
Igee -/ W ' -
1.0 1800 l700 1 88* - 8 ~3 1 11eo - 1 I:e4/
1.0 2000 2eso 2Fle-/ '
19es-l 1.0 2200 1188 .
1.0 2400 2.488 1.0 2600 '3480 Fracture Lead er 2.0 2000 190* ,
), o 290o z 9o5 -
Fra urf D K 'I/lI M es F t u r f Aseherhead Neat code M V0W Batained Distortion at 2800 Kips M
- A/E s shins seat code M/A
)/fS espTif 16LES Visible Cracks 3#iai SvMAcf Accept YEI Rajinct Back time sense is emitted duries testing, that value la Eips will be desmosated.
Data nesorded bys
%Q--!s tJe*Ff V4+ r Ur-tc/s3 sissed b Y, NMf=/ NMWre 8+r Title 7 8 21 J 7 A . ,, w _
e, h. M.
o te '6 19,'87 i
witaans: ;
l
! sissed T1tne pT)}/am,n(-L A Jn. %
As...y Rulfzl
Ul.", " " 2-is-as 0';'*0.A *auS= A '* 2 *r 2 r.~ mu siu n.mo. u~ . - ..
. _ , r- aia wmo SUBURBAN LABORATORIES, Inc.
4140 UTT ORIVE HILLS 40E, ILUNOIS 80142 1183 EMILL floSEMBEAG HJL THoedAS,Jelt Preemens owector February 21, 1985 Concrete Systems Division
~
7200 South Narragansett Avenue Bedford Park .
Oticago, Illinois 60638 Re: P. O. #4172400-8 Attention:,
W. Harry Hendrickson Neutralization No Samles Received: 2/14/85 Chlorides Nitrates Sulfides 1 dater Content Total Base No.
(ppe) (ppe) (ppe) , 5 (as ros/g)
S/L #1537 - Sample A, hcontrolled Button Head Surface Field End, HV038V21 w/ tape 4.30 0.113 0.002 3 21' 46.97 S/L #1538 - Sample B, ancontro11ed around Threads Field Ehd HV038 Y21 0.70 0.113 0.007 1.02 47.86 S/L #1539 - Sample #1, Y64 hoontrolled 1.40 0.113 0.007 0.18 51 35 S/L #1540 - Grease Can, Y102 Top 0.40 0.075 0.012 0.19 49.48 S/L #1541 - Beated Pumped Out Y21, Top 0 70 0.075 0.007 0.17 50.57 S/L #1542 - #840069 Tendon Y-17 Top #1 1.40 0 325 0.007 0.27 50.88 S/L #1543 - #840070 Tendon Y-17 Top #2 2 90 0.150 0.002 0.18 48.50 S/L #1544 - #840071 Y-17, Botton Grease 2.00 0.180 0.012 1.52 48.18 from Lowest Point #3
- S/L #1545 - #840072 Tendon Y-17, Botton 1st from Can #4 1.40 0 300 0.012 en 50.02 S/L #1546 - #840073 Y-17, Bottos Upper Portion #5 1.40 0.230 0.012 1 34 45.84 (Continued)
- - __- _ ~ - .. .. . ..
l -
t .
1 .
Inryco, Inc.
February 21, 1985 Fage #2 Neutralization No:
Samples Received: 2/14/85 Chlorides uitrates Sulfides Water content Total Base No.
- (ppe) (ppe) (ppe) 5 (as ros/s)
Field Anchor Cap / Y-21 S/L #1547 - Grease wrapped in Plastic 1.40 0.250 0.012 1.11 48.36 S/L #1548 - Layer #1," Top Edge 0.40 0.280 0.016 0.54 46 33 l S/L #1549 - Iayer f1, Top Center 0 70 0.280 0.002 0 77 44 37 S/L #1550 - 14yer #3, Edge 0 70 0.280 0.0 16 0.27
' 46.95 3/L #1551 - tayer #3, Centor 0 70 0.300 0.020 0.44 45.46 S/L #1552 - Layer #4, Edge 2.00 0.300 0.012 0 38 45 74 j 3/L #1553 - Layer #4, Center 0 70 0.300 0.012 . 0.54 47.67 l S/L #1554 - Layer #6, Botton Edge 0.70 0.325 0.016 0 70 45 37 S/L #1555 - !ayer #6, Botton Center 2.00 0 325 0.012 1.42 46.55 Interior Anchor Head S/L #1556 - Field Ehd / V-17 0.70 0.280 0.012 es se j Dates Tested: 2/19/85 & 2/20/85 2/20/85 2/20/85 2/19/85 i
ANALYSIS CERTIFIED BY:
'/
< , Director (ERT:ih)
Chlorides (Sect. 5.11) Method: ASTM D-512 Nitrates -* Method: ASTM D-992 4
Sultides
~
Mater content (Sect. 5.2) ,
Method: ASTM 4-95 seutralisation Ember (Sect. 5 3) Method: ASTM D-97,4 (Modified)
- Black color appears in the water layer ~
Insufficient sample teameers of Arnerican Chemical Secteer . American Society for Micsoedotog Weemr Featutaen Contpel Federatten . Institute of Food Technoingy 1
Cert.f cat cas. U S O A e1783
- E Dept.of % Heesth ai7136 . Amer.SeceTrade Asan. . F 0A 8tes #1419878 118. EPA 8100191 ga
s*
Teeephone (312) 644-3200 SUBURBAN LABORATORIES, Inc.
4140 LITT DRIVE HILLSIDE. ILLINOIS 00182 1183 mg,noogasseng .,' H.R. THOMAS JR.
possement Detector February 25, 1985 i
Inryoo, Inc.
Concrete Systems Division 7200 South Narragansett Avenue Bedford Park Chioago, Illinois 60638 Attention: W. H. Hendrickson Saanle Received: 2/22/85 Source: S/L #1880 - Mater from Y-21 Field Cap Chloride (ppa) 180.80 I
ANALYSIS CERTIFIED BY: , Director (HRT:ih) f Momtiere of American Chemical Sectety e American Society for M4crotnoto0V Water Postutaan Contaos FeeeratNm
- Institute of Food Technoso0F Certif6catione. U S D A.e1783 +
118 Dept.of PutW6c Health 817136
- Amer. Sp6ce Trees Aeon. . F.D A Aeg 81419876
. - - -- . . - - - - . . , . -.