|
---|
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] |
Text
_ _ _ - _ _ . _ _ _ _ _ . _ ._ _ . _ ._. _ _ _ . _
/.26.&Y BALCH & BINGHAM e
....-..a sc o
. .m
- s. . a . .c,.m... ,
n.~
o .t te n N t ,5 n.b c ov*ar tc.b
.6 .. . - - ..o e
..,..w.
- v. .. s eu .s m
. .m..m.
. 4. o .
~ ,
. .. .- .e.,.. . . ... . m on.cc o. m
. .,o. -w
,.. a ,
c s.,
..... u.-,a.m . s.
. u. .o.. ..
. ..n . 4 , .mmon,s. n .u,4 am. m. . < , , a .,
.m,~
o.a.H(.,.h (.
i
.H e,a8p{.D
- 9. au . J .. D .s.w. . s.a , u ( 714 j
. .* . u.bh( .%N,
.dl .
' , 63 p ea,.. ( r.= ip o. p. ..oo ggp s . c.as.am, l
.we . . ro. x. uw. , . , a u , -- ~ ,. , ~ . ,.
.so.h
..o, no.m C ..a F. .c,WDC.Q
/ { 8.' t (e. .p ( fg ..,,.
g( , *( . . 4Lga
,.. e.[
s4.&,,.. .a,
- . . .N, ..
.- ~ o ,
.a..--,, a ..., ... m . . .c..,..u.. .e a<...a o..m .u ,
-o a .. .. .
- -6 P 3_c4. . ~m.
.. .. m..a 4 m.~
-n.
. . , . , ..a. . . .m4 . ,
w.
. a c . ~ <.
. ~ . .. o.
. .. u
,.....,....'.J"Z.,L .... , t-. . ,
x .n..n....u., . ... ..m . .......,,, .. .o w..., ...am. .... .o.. u, ~..... m. e. . .a.n
. . .~....c **c. - i e n ,o.,e .o.n o . .. . m....m ..o.m oo. .
....,m.
.me. . ,,, ~ .a .
.n..
.mg. ., .u. ,. mm.
w.. ..
. . . . . . , u ,, r a a*
.4, w,o a
,11 m ..a.
4 s
. . nm.w.m,,.
. i.,uo'o c . o. .m.u .4 . .a . .mo. - -
.u.a. , w . .n.
crm ra,s<.tr w.-yn o x . .a..
.em.<,.o
.,....... .s,
. .~...u.
wa09
.s
.c ,, a . ... .
4 (. .e....s.
M. .( .g ,.s .a 4 g g.
,. . ...., .,.. ... o & ...
WH4. .
<. a.. m.
.o~
hiarch 2,1992 .m m...~.
.sC .
, , . . . a.
. . * .m..,
. fs.,A .,.a 1.~.. ~ -. .
..n.e
~,
jts.sh . MO D,ed J f..C e D.e.. D tac.A4.h- pt e%e G. Paul Hollwerk,111 James H. Carpenter Administrative Judge Administrative Judge Atomic Safety and Licensing Board Atomic Safety and Licensing Board U. S. Nuclear Regulatory Commission U. S. Nuclear llegulatory Commission '
Washington, D.C. 20555 Washington, D.C. 20555 Peter A. hiorris
. Administrative Judge 10825 South Glen Road Potomac, hiaryland 20854 IN Tile MNITER OF Alabama Power Company (Joseph M. Farley Nuclear Pfar;t, Units 1 and 2) . ,
Docket Nos. 50 $CivP; 50 M4.CivP A S L ll P N o. 91626 02.CivP Dcar Administrative Judges: !
L .
l Please find enclosed Alabama Power Company's list of duplicated pre marked r
t exhibits.
L L Respectfully yours,
)
f
.7 , u .
James H hiiller,111 J /h + ,
COUNSEL FOR ALABAhiA POWER COh1PANY Enclosure .
cet Certificate of Service no m,. ..sr ~c . . ..4 4. m .o.,- , n on .a v. ,= .u, cou , u,,e . .mu,~.
7
.a s.42.v!! L C .L .D AM. 35L.O'
..R.d yCee..M A4....M. 3?.,77)J $2.aqi.4GH.M .t AO. .t. MpQ3 .MO ,QQest.f 4....it. De 01 .
..*bHWQ,M D C gQTQ$
9203110027 920302- **)
PDR
-g ADOCK 05000348 PDR
%1P .
J
vi:ie UNITED STATES OF AMERICA "" C NUCLEAR REGULATORY COMMISSION 92 WR -6 P 3 :32 I!EFORE '111F. ATOMIC SAFETY AND 1.1 CENSING llOARQ , y ; y u,. .
nwi m ma.m+
. ii a l in the Matter of: )
) Docket Nos. 50-348-CivP ALABAMA POWER COMPANY ) 50-364-CivP ,
) '
(Joseph M. Farley Nuclear )
Plant, Units 1 and 2) ) ASI HP No. 91626-02 CivP ESTIFICATE OF SERVICE 1 hereby certify that copies of the
- LIST OF DUPLICATED PRE MARKED EXililllTS OF ALAHAM A POWER COMPANY"in the above. captioned proceeding have been served on the following by facsimile as indicated by an asterisk, or otherwise through deposit in First Class United States Mail, this 2nd day of March,1992:
G. Paul Hollwerk, Ill* James 11. Carpenter
- Administrative Judge Administrative Judge Atomic Safety and Licensing Board Atomic Safety and Licensing Board U. S. Nuclear Regulatory Commission U. S. Nuclear Regulatory Commission Washington, D.C. 20555 Washington, D.C. 20555 Peter A. Morris
Administrative Judge Office of the General Counsel 10825 South Glen Road U. S. Nuclear Regulatory Commission Potomac, Maryland 20854 Washington, D.C. 20555 Office of the Secretary (2) Atomic Safety and Licensing Board U. S. Nuclear Regulatory Commission Panel Washington, D.C. 20555 U. S. Nuclear Regulatory Commission Attn: Docketing and Service Section Washington, D.C. 20555 Adjudicatory File (2) Office of Commission Appellate Atomic Safety and Licensing Board Panel Adjudication U. S. Nuclear Regulatory Commission l'. S. Nuclear Regulatory Commission Washington, D.C. 20555 Washington, D.C. 20555 l
-ty-A-g-- av- y auw-.n awg- --- ,,.w,y ---e-wem p- -, - + ** 3+c-%e.-- --w,.gg -
-.wie-,p- ,-e-..,-e-79g y--
- 9 --r-._ m w 79e-m- esw7 e-+-9yg--z -g &---. ,
Mr. W. G. llairston,111 Regional Administrator Southern Nuclear Operating Company, U. S. Nuclear Regulatory Commission.
Inc. Region 11 Post Office Dox 1295 101 Marietta Street Birmingham, Alabama 35201 Suite 2900 Atlanta, Georgia 30323 James Lieberman, Director Office of Enforcement U. S. Nuclear Regulatory Commission Washington, D.C. 20$55 l
/ 'f 1.1 =u, t James 1-1. Miller,111 Counsel for Alabama Power Company
. - - . _ - - - _ _ . - ._ ~ --- - - - - - _-- _-.- - ._ -
APCO 1IST OF DUPLICATED PRE MAIGED EXillBITS (Cross referenced with corresponding staff exhibits)
APCO#/STATT#
- 1. Agenda,8/26 28/87, regarding EO seminar at Sandia APCO ethlbli recelged into esidence, p. 947
- 2. 4. Generic letter to All Power Reattor Licensees and Applicants from Prank J. htiraglia - NRC, dated 04/07/88, regarding hiodified Enforcernent Policy Relating to 10 CFR 50.49,
- Emironmental Qualification of Electrical Equipment important to Safety for Nuclear Power Plantf (Generie letter 88 07); List of Recently issued Generic letters attached Staff Eahlblt recclied into etidence, p.304
- 3. G4/13/78 Petition for Emergency and Remedial Action; Cl.l.78 6; 7 NRC 400,420 APCO ethlbli recclsed into esidence, p. 947
- 4. lE Circular 78 08 to F. L Clayton, Jr. APCo from James P. O Reilly NRC, dated 05/31/78, regarding Erwironmental QualiGcation of Safety Related Electrical Equipment of Nucicar Power Plants; List of I.E. Circulars issued in 1978 attached APCO ethlbli retelied into esidence, p. 947
- 5. 10/11/78 letter to Jamer. P. O'Reilly transmitting Farley response to IE Circular 78-08:
Qualification of Electrical Terminal lilocks; Unavailability of Test Report Due to Terminal 13 locks inside Conta!nment Anociates with Containment isolation Valves, Wide Range and harrow Range Temperature hionitoring, and Power Operated Relief Valves APCO exhibit rycelsed into esidence, p. 947
- 6. letter to F. L Clayton. Jr. Alabama Power Co. from James P. O'Reilly dated 02/08/79 regaiding 1.lL llulletin No. 79-01: Emironmental Qualification of Class IE Equipment; attachments: 1) IE Bulletir, No.79-012) List of IE Bulletins issued in the Past 12 hionths 3)
List of SEP Plants.
APCO ethlbit recclsed into evidence, p. 947
- 7. 27. Bulletin to F. L Clayton, Jr. APCo from James P. O'Reilly NRC, dated 06/06/79 regarding Supplement 1.E. Ilulletin 79-OlA; attachments: 1) 1.E. Ilulletin No. 79 01 A 2) List of I.E.
Ilulletins luued in the Past 12 Months 3) List of SEP Plants Staff ethlbli recelsed into esidence, p. 889
- 8. Bulletin to F. L Clayton, Jr. APCo from James P. OTteilly NRC, dated 01/17/80 transmitting 1.E. Hulletin No. 79-0111 Regarding Emironmental Qualification of Class 1.E.
Equipment; Enclosures dated 01/14/80 APCO exhibli recelsed into esidence, p.1194
- 9. CLI 80 21 dated 05/27/80 APCO eshlbli recelsed into esidence, p. 947 l
- 10. hiemo to 7 R. Rositoery from Frank Ashe, Joel Paige, William Ikiothr, and htarilee Slosson, i dated 05/27/81, transmitting Trip Report Audit of Alabama Power Company's Test Data and/or Documentation Concerning Erwironmental Qualification of Electrical Equipment Per NUREG 05SS for Farley 2 Nuclear Station APCO eshlblt recclsed into esidence, p,947 t
l l
1
e 11. Letter to R. P. h{sDonald APCo irom C. E. hiurphy NRC dated 01/15/81 tratamitting Report Nos 50-348/$0 38 and 50 364/80-49; Special Inspution Conducted Dy T. D. Gibbons on 12/02/B0 to 12/05/B0 APCO cahibit rnelied into coldence, p. 947
- 12. Technical Evaluation Report entitled Environmental Qualification of Safety Related Elmtrical Equipment IED 7941H Farley Unit No. I prepared by N. hterriweather on 12/10/80 APCO exhibli rnched into cildence, p. 947
- 13. Letter to F. L. Clayton, Jr. APCo from Thomas ht. Novak NRC dated 02/13/81 regarding 4 Preliminary Results of NRC Review of EQ's of SafetpRelatal Electrical Equipment at Farley Plant, Unit No.1; attachment: Environmental Qualification Report APCO eshihlt rneited into ciidence, p. 947
- 14. Letter to F. L. Clayton, Jr. - APCo from Steven A. Varga NRC dated 05/21/81 transmitting NRC Safety Evaluation for the Environmental Qualification of Safety Related Electrical Equipment at Parley Unit No. It attachments: Safety Evaluation Report and Technical Evaluation Rrport dated 11/14/80 APCO eshibit rnelied into cildence, p. 947
- 15. htarch 1981 Safety Evaluation Report Unit 2, Docket No. 50-364, APCo, supplernent No. 6 to NUREG 75/034 APCO eshibit racited into ciidence, p. 947
- 16. 01/14/83 Technical Evaluation Report: Review of Licensecs' Resolution of Outstandmg issues From NRC Equipment Environmental Qualification Safrty Evaluation Reports (F il and D40);
Farley Unit 1; prepared by The Franklin Institute APCO eshibit rnelied into etidence, p. 947
- 17. 01/17/83 Technical Evaluation Report: Review of Licensecs' Resolution of Outstanding issues from NRC Equipment Environmental Qualification Safety Evaluation Reports (F 1I and B40);
Farley Unit 2; prepared by *lte Franklin Reacarch Center Al'CO exhibit receited into cildence, p. 947
- 18. letter to F. L. Clayton, Jr. APCo irom Steven A. Varga NRC dated 02/04/83 tratamitting Safety Evaluation Report for Environmental Qualification of Safety Related Electrical Equipment -
Farley Unit No.1 APCO exhibit rnelied into evidence, p. 947
- 19. 1.rtier to F. L. Clayton, Jr. - APCo from Steven A. Varga NRC dated 02/04/83 transmitting Safety Evaluation Report for Environmental Qualification of Safety RelatW Electrical Equipment -
Parley Unii No. 2 APCO eshibl; rneited into evidence, p. 947
- 20. Letter to S. A. Varga NRC from F. L. Clayton, Jr. APCo dated 02/29/84 concerning Safety Evaluation Reports and Technical Evaluation Reports Noting Deficiencies Concerning Documentation of Qualification for Several Safety Related items at FNP; attachments: 1)
Summary of Each Deficiency identified in the TER's for Units 1 and 2; 2) Resolutions to Specific NRC Staff Comments identified at the 01/11/84 htecting; 3) Westinghouse Affidavit Requesting information in Supplements 1,2,3 and 4 To Be Withheld from Public Disclosure APCO eshibit rneited into evidence, p. 947 t
. 21. Safety Evaluatiora dated 12/13/84 for Units I and 2; propmed re4olutions for deficiencica identified in Safety E"aluations dated 01/31/83 and in the 01/14/83 and 01/17/83 Franklm 7 ER's and to your proposed Llat JCO's are not neceaary APCO eshibit trcched into evidence, p. 947
- 22. Letter to S. A. Varga + NRC from R. P. hicDonald APCo dated 01/28/85 transnutting Units 1 and 2 Response to Generic lette 84 24; Sworn Statement that as EQ program is in place, the plant has at least one path to safe shutdown, and equipment is quall'ied or operating under JCO.
APCO eshibit retched I,ito eildence, p. 947.
- 23. FNP Envitonmental Qualification Program implementation: FNP-0 ETP-4108 Revision 0 APCO eshibit rtrched into ciidence, p.1060
- 24. Excerpt from of The Lineman's andfableman's llandtmk, section 33, entitled, ' Splicing Cable
- APCO exhibit ricched into coldence, p. 962
- 25. 21. Okonite Report No. NQRN 3, Rev.1. June 30,1982, entitled, ' Nuclear Environmental Qualification Report for OLoguard Insulated Cables and T 95 and No. 35 Splicing Tape' Stati eshibit recched into esidence, p. 442
- 26. 16. 07/30/87 letter to NRC Document Control Desk from R. P. hicDonald transmitting Farley Unit 1 Licensee Event Report No. LER 87-012-00 Stafi eshibit rnched into ciidence, p. 442
- 27. NEQ Test Report 17859-02D performed by Wyle Laborstories: Qualification Test Program on Ray Chem Nuclear Cable Splices, Okonite Tape Splices, Kente Tape Splices, Scotch Tape Splices and Amp Dutt Splices as Installed on Various Wire insulations at Commonwcalth Edium Companies LaSalle Drexlen and Quad Cities Generating Stations, volumes I and 2 (htarch II,1987)
APCO eshibit recched into evidence, p. 962
- 28. 9. Generic letter 8615 entitled
- Environmental Qualification of Electric Equipment important to Safety for Nuclear Power Plants,' dated 09/22/86 Staff eshibit rneised into c51dence, p. 304
- 29. Jesse E. Love resume APCO eshibit retched into eildence, p.1191
- 30. James E. Sundergill resume APCO eshibit recched into evidence, p.1191
- 31. General Design Criterion 4,10 CFR Part 50, Appendit A APCO eshibit retched into evidence, p.1191
- 32. Regulatory Guide 1.97, Rev. 2.
APCO eshibit recched into esidence, p.1891 1 33, 2. 08/15/88 Notice of Violation and Proposed Imposition of Civil Penalty (NRC Inspection Report Nos. $0-348,364/8725 and 50 348,364/87) transmitted to Alabama Power Company from NRC
- 34. 3. 08/21/90 Order impasing a Civil hionetary Penalty at Farley StafT eshibit recched into evidence, p. 304
- 35. Regulatory Guide 1.89, Rev.1 APCO eshibit receited into esidence, p.1191 1
1
- 36. IEEE Standard 3231974, Standard for Qualifying Clau IE Electric Equipruent for Nudear Power Generating Stations APCO eshlbli recelied into eildence, p.1191
- 37. IEEE 3231971, Standard for Qualifying Clau IE Elutric Equipment for Nucicar Power Generating Stations APCO exhibit rnched into etidence, p.1191
- 36. APCO Detail Nos. A.172389172398: generic design details regarding terminations APCO eshibit rncited into esidence, p.1891 l l
- 39. 25. Wyle Test Report 17947-01 dated 10/08/87 with Addendum I dated 11/19/88 Staff exhibit rnelted into evidence, p. 442 APCO eshibit rweited into evidence, p. 947.
% 26. 05/16/90 Qualification of taped splices for tu.e in instrument circuits subject to harsh environments. Waterford Steam Elutrie Station Unit 3 Staff eshibit rnched into eiidence, p. 442
- 41. Circular 6010 regarding Failure to Maintam Environmental Quahfication of Equipment, dated N/29/80 APCO exhibit rnehed into evidence, p.1191 42, 23. NUREG-05BB, Rev.1: Interim Statf Position on Environmental Quah6 cation of Safety Related Electrical Equipment Stalicshibit recched into esidence, p 442
- 43. 30. 09/23/87 Elutrie ilydrogen Recombiner Splices -- Justification for continued Operation StafT eshibit rnelied into eiidence, p. 304 44, 32. WCAP 7709 L: Electrical liydrogen Recombiner for Water Reactor Containments, produced by Westinghouse Electric Corp.
Staff eshibit receited into evidence, p. 529 4$. 29. 09/17/87 Electric ilydrogen Recombiner Splices - Justi6 cation for Continued Operation Staff eshibits rneited into esidente, p. 529
- 46. letter to APCO from Westinghouse regarding 5101 terminations, dated 09/22/87 APCO eshibit receited into evidence, p.1191 l
47, 31. WCAP 9347: Qualification Testing for Model B Electric liydrogen Recombiner, produced by Westinghouse Electric Corp.
l Sta!T exhibits receited into evidence, p. 529 48, letter to Thomas Anderun. Westinghouse from John F. Stolz NRC dated 06/22/78 transmitting evaulation of WCAP 7709L Re: liydrogen Recombiners APCO eshibit recched into evidence, p.1191
! 49. Westinghouse Electric liydrogen Recombiner Tnhnical Manual APCO eshibit receiicd into evidence, p. Il91 l
l l 50. Wyie Test Report 443541, dated 03/08/79 APCO exhibit rneiied into evidence, p.1191
~ _
. - - - -. -_. - . - - - = ._ -- ~_ .
- 51. 48. 06/15/841.E. Information Notice No. 84-47: Environmental Qualification Tests of Electrical Terminal Blocks APCO exhibit tweived into evidence, p.1191 Staff exhibit received into evidence, p. 779
- 52. APCO response to Circular 78-08 and Notice 84-47 regarding terrainal Mocks and loop accuracy APCO exhibit received into evidence, p,1191
- 53. Eacerpt from IPS-107:Conat Test Report IPS 107 Connection NSS3 Terminal Blocks APCO uhibit retened into evidence, p,1191
- 54. Picture of CR151B terminal block taken from vendor's catalogue APCO exhibit received into evidence, p.1191
- 55. 12. Letter to R. P. Mcdonald APCo from J. Nelson Grace NRC dated 02/04/88 transmitting NRC Inspection Report Nes. 50-348/87 30 and 50-364/87 30 Staff exhibit received into evidence, p. 304
- 56. Graph representing terminal block Connectron Nss3/#16 AWG Wires, Conax Test Report IPS-107; representation of IR values over time.
APCO exhibit receited inti 6 dence, p.1191 57, One-page illustration of Comectron terminal block taken fron vendor's catalogue APCO exhibit received into evidence, p.1191
.a. Qualification test reports for GE OR151B terminal blocks
- 59. 11/24I87 Justification for Continued Operation Unit 1 - Terminal Blocks Used in Instrument Circuits
- 60. 39. Raychem Report EDR 5033/Wyle report 58442-2, dated 04/81
. Staff exhibit reccited into evidence, p 889
- 61. Test Report 2BE-1049-3: submergenve testing of Chico A/Raychem seal.
APCO exhibit received into evident , p,1191
- 62. 33. Bechtel qualification testing of Raychem seals Staff exhibit received into evidence, p. 889.
- 63. 40. 02/01/79 Testing and Irradiation of Four Inch Eys Cendulet, performed by Southwest Re, search Institute Staff exhibit received into evidence, p. 889
- 64. 47. Letter f a D, M. Verrelli - NRC from R. P. Mcdonald - APCo dated 01/08/88 transmitting Additional Documentation Supporting Environmental Qualification of Ray Chem / CHICO Sealant and Tenninal Blocks at Farley; attachments: 1) Correspondence from Bechtel Eastern Power Co.
to APCo Regarding Ray Chem / CHICO sealant Environmental Qualification Evaluation; 2)
Correspondence from DiBenedetto Associates, Inc. to APCo Regarding Qualification of GE and States Terminal Blocks Staff exhibit received into evidence, p. 779
- 65. 35. 11/20/85 EQ Test R'eport of Raychem NEIS Environmental Interface Seal Kits on Stainless Steel Pipe (EDR-6063)
Staff exhibit received into evidence, p. 889
, 4 '
Ucch'al Drawing No. A 177541: Tray and Conduit General Details and Notes.
Staff ahibit received into evidence, p. 889
- 67. 54. Limitorque Corporation Nuclear Qualification B0058, Parts and 2 Staff exhibits received into evidence, p. 643
- 68. 52. Limitorque Report 600198: Limitorque Valve Control Tot Report Staff exhibits received into evidence, p. 643
- 69. 53. Limitorque Report 600456: Qualification Type Test Report Staff exhibits receivM into evidence, p. 643
- 70. NUGEQ Report ' Clarification of Information Related to the Environmental Qualificction of Limitorque Motorized Valve Operators,' dated April 1986.
- 71. Limitorque Report B00119. Rev, I dated !!/15/82: 'Qu ..wm type Test Report of Multi-Point Terminal Strips for Ui.e in Limitorque Vaive Actus i cWR Service
- APCO exhibit received into eiidence, 1.>.
- 72. 55. 10/28/831.E. Information Notice 83 72: Environmental Qualification Testing Experience Staff exhibits received into evidence, p. 643
- 73. 01/14/861.E. Information No, 86-03; Potential Deficiencies in Environmental Qualification of Limitorque Motor Valve Operator Wiring APCO exhibit received into evidence, p.1191 74, excerpt from Texaco's 1988 ' Lubricating Oil, Grease and Antifreeze Coolant Digest
- APCO exhibit received into esidence, p.1191
- 75. Telecopy to Frank Watford from Thomas P. Gr; ory dated 06/10/76 regarding Texaco Lubricant Recommendations Per Equirnent Lists APCO exhibit received into evidence, p. 574
- 76. ' Wyle Test Report No. 40196-1: Radiation Exposure and Accident Simula. ion Test Program on Texaco Greases and Oils dated 12/05/88 APCO exhibit received into evidence, p.1191
- 77. Chevron SRI-2 telecopy from Bolt /Bechtel APCO exhibit received into evidence, p.1191 77a. Robert O. Bolt resume l 78. Letter to W. Gillairston, hl - APCo from Caudie A. Julian NRC dated 10/31/89 transmitting l _NRC Inspection Report Nos. 50-348/89-23 and 50 364/89 23; Inspection to Review APCo's l
Corrective Actions in Response to Previous inspection Findings (Bates #57180)
APCO exhibit received into evidence, p.1297 i
- 79. Philip A. DiBenedetto resume APCO exhibit received into evidence, p.1297 l 80. - NRC Order dated 03/30/90: EQ civil penalty at H. B. Robinson l APCO exhibit received into evidence, p.1297 l
t
=
- 81. NUGEQ Report ' Clarification of Information Related to the Environmental Qualification of Limitorque Motoriud Valve Operators,' dated August 1986.
APCO exhibit received into evidence, p.1297
- 82. Vincent S, Noonan resume APCO exhibit received into evidence, p.1297
- 83. License Condition for Farley Unit 2 APCO exhibit receited into evidence, p. 305 -
- 84. 05/23/85 Evaluation and Status of License Conditions for Joe.epb M. Farley Unit 2; transmitted from Mr. Steven A. Varga to Mr. R. P. Mcdonald APCO exhihti recelied into evidence, p. 305
- 85. 08/29/80 correspondence from NRC to APCO transmitting Order for Modificcion of Liceme APCO exhibit received into evidence, p. 305
- 86. Memo to NRC Regional Administrators Regions 15 from James Liberman dated 06/21/88 transmitting Guidance for the Preparation of Enforcement Cases Related to EQ Violations; follow-up to Generic Letter 88 07 describing modified enforcement policy for environt ,tal quahfication actions APCO exhibit received into e5idence, p. 305
- 87. Notice of violation for Indian Point Unit 2. dated 11/03/88 APCO exhibit received into evidence, p. 305
- 88. Notice of violation for Indian Point Unit 3, dated 09/21/88 APCO exhibit received into evidence, p. 305
- 89. Notice of violation for Susquehanna Units I and 2, dated 09/19/88 APCO exhibit received into evidence, p. 305
. 90. *EQ Scoreboard
- APCO exhibit received into evidence, p. 305
- 91. Notice of violation for Consumers Power Company's Palisades Nuclear Plant, dated 11/23/88 APCO exhibit received into evidence, p. 305
- 92. Timeline prepared by Alabama Power Company APCO exhibit received into evidence, p. 791
- 93. Tl 2515/76 Inspection Module, entitled, " Evaluation of Licensee's Program for Qualification of Electrical Egiipment Imcated in Harsh Environments' APCO exhibit received into evidere : ,p.336 94, Correspondence from NRC to APCO regarding " Summary of Meeting Held on September 24, 1987, Between NRC Staff and APCO Representatives to Discuss Recent Problems Related to Qualification of V Type Electrical Splices at Farley Site
- APCO exhibit received into evidence, p. 442
- 95. 09/28/87 correspondence from Wyle Laboratories to APCO regarding Environmental Qualification Test Results on Okonite and 3M Tape Splice Assemblies for the Farley Nuclear Gener. ting Station.
. APCO exhibit received into evidence, p. 443
i 96. Correspondence from Jackie Graham of Southern Company Services to APCO dated 10/29/87, transmitting assessment of V-type tape splices.
APCO nhibit received into evidence, p. 451
- 97. execrpt from Reliance Manual B-3620-8 APCL uhibit receited into esidence, p. 574
- 98. excerpt from Reliance Manual B 3620-19 APCO exhibit received into evidence, p. 574.
- 99. Installation and Maintenance Manual for Joy Series 1000 Axivane Direct Connected Single and Two Stage Axial Flow Fans APCO exhibit received into esidence, p. 574 100. excerpt from Reliance Manual B 3628 Rev 9 APCO uhibit received into evidence, p. 574 101. excerpt from Reliance Manual B 3628 Rev.10 Alto exhibit received into nidence, p. 574 102. Physical specimen: EA 180 Seal (Cross-section of Raychem 3oot)
APCO nhibit retelved into evidence, p.1192 103. Physical specimen: EA 180 Namco Limit Switch (Full version)
APCO exhibit receised into evidence, p.1192 104. Drawing A 177541 Rev. O, dated 07/16/82: Procedure for Applying Chico-A4 Compound to the Nipple of Namcvs EA-180 Limit Switch Where Raychem Break-Out is Attached APCO nhibit received into evidence, p. 890 105. Physical specimen: V-type splice APCO exhibit aceived into e5idence, p.1192 106. Physical specimen: 5-to-1 splice APCO exhibit received into evidence, p.1192 107. Physical specimen: T-drain APCO exhibit received into evidence, p.1192 108. 09/30/87 correspondence from APCO to NRC regarding 09/24/87 meeting APCO exhibit received into evidence, p. 947 109. 05/07/86 memo transmitting 05/122/86 NUGEQ memo entitled, " Clarification of Information Related to the Environmental Qualification of Limitorque Motorized Valve Operators
- 110. J. E. Love markup of Board Exhibit 1 APCO nhibit received into evidence, p.1223 111. I page excerpt from Sandia report: Figure 2, Phase 11 Environmental Temperature Profile, Jesse leve markup.
APCO nhibit receised into evidence, p.1223 l
>- NOTES
-APCO 39 and Staff 25 have been received into evidence; APCO 39 includes Addendum 1.
-Staff 32, which has been received into evidence, is missing pages; refer to APCO 44.
-Staff 27, which has been received into evidence, is missing pages; refer to APCO 7.
l L
l i
j ..
- . - . . . _ - . . - - _ . _ ._ _