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Category:CORRESPONDENCE-LETTERS
MONTHYEARL-99-035, Forwards non-proprietary & Proprietary Versions of Farley Units 1 & 2 LBB Calculation Results Due to SG Replacement & SG Snubber Elimination Programs, Used to Support SG Replacement Project.Proprietary Encl Withheld1999-10-18018 October 1999 Forwards non-proprietary & Proprietary Versions of Farley Units 1 & 2 LBB Calculation Results Due to SG Replacement & SG Snubber Elimination Programs, Used to Support SG Replacement Project.Proprietary Encl Withheld ML20217G0801999-10-0707 October 1999 Informs That on 990930,staff Conducted mid-cycle PPR of Farley & Did Not Identify Any Areas in Which Performance Warranted More than Core Insp Program.Nrc Will Conduct Regional Insps Associated with SG Removal & Installation ML20217P0661999-10-0606 October 1999 Requests Withholding of Proprietary Rept NSD-SAE-ESI-99-389, Farley Units 1 & 2 LBB Calculation Results Due to SG Replacement & SG Snubber Elimination Programs ML20217B1891999-10-0404 October 1999 Submits Clarification Re Development of Basis for Determining Limiting Internal Pressure Loads Re Review of NRC SE for Cycle 16 Extension Request.Util Intends to Use Guidelines When Evaluating SG Tube Structural Integrity ML20212J8391999-09-30030 September 1999 Forwards RAI Re Request for Amends to Ts.Addl Info Needed to Complete Review to Verify That Proposed TS Are Consistent with & Validate Design Basis Analysis.Request Discussed with H Mahan on 990930.Info Needed within 10 Days of This Ltr ML20212J8801999-09-30030 September 1999 Discusses GL 98-01,suppl 1, Y2K Readiness of Computer Sys at Npps. Util 980731,990607 & 03 Ltrs Provided Requested Info in Subj Gl.Nrc Considers Subj GL to Be Closed for Unit 1 L-99-032, Responds to NRC Re Adequacy of Kaowool Fire Retardant Fire Barriers in Use at Jfnp,Units 1 & 21999-09-23023 September 1999 Responds to NRC Re Adequacy of Kaowool Fire Retardant Fire Barriers in Use at Jfnp,Units 1 & 2 L-99-034, Forwards Comments on Draft Current Tech Specs Discussion of Change Tables for Jm Farley Nuclear Plant.Units 1 & 21999-09-23023 September 1999 Forwards Comments on Draft Current Tech Specs Discussion of Change Tables for Jm Farley Nuclear Plant.Units 1 & 2 ML20212F8861999-09-23023 September 1999 Forwards Revised Relief Request Number 32 for NRC Approval. Approval Requested by 991231 to Support Activities to Be Performed During Unit 1 Refueling Outage Scheduled for Spring of 2000 ML20212E7031999-09-23023 September 1999 Responds to GL 98-01, Year 2000 Readiness of Computer Sys at Npps. Util Requested to Submit Plans & Schedules for Resolving Y2K-related Issues ML20212F1111999-09-21021 September 1999 Discusses Closeout of GL 97-06, Degradation of Steam Generator Internals ML20212C2351999-09-16016 September 1999 Submits Corrected Info Concerning Snoc Response to NRC GL 99-02, Lab Testing of Nuclear-Grade Activated Charcoal ML20212D0101999-09-15015 September 1999 Informs That Submittal of clean-typed Copy of ITS & ITS Bases Will Be Delayed.Delay Due to Need for Resolution of Two Issues Raised by NRC staff.Clean-typed Copy of ITS Will Be Submitted within 4 Wks Following Resolution of Issues ML20212C4641999-09-13013 September 1999 Forwards Info Requested in Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Exams L-99-031, Informs NRC That Review of MOV Testing Frequency & Changes Made to Frequency of MOV Testing Has Been Completed1999-09-13013 September 1999 Informs NRC That Review of MOV Testing Frequency & Changes Made to Frequency of MOV Testing Has Been Completed ML20212C8041999-09-10010 September 1999 Responds to to D Rathbun Requesting Review of J Sherman Re Y2K Compliance.Latest NRC Status Rept on Y2K Activities Encl ML20212D4581999-09-10010 September 1999 Responds to to D Rathbun,Requesting Review of J Sherman Expressing Concerns That Plant & Other Nuclear Plants Not Yet Y2K Compliant ML20212A6951999-09-0909 September 1999 Requests That Licensees Affected by Kaowool Fire Barriers Take Issue on Voluntary Initiative & Propose Approach for Resolving Subj Issues.Staff Plans to Meet with Licensees to Discuss Listed Topics ML20212A8341999-09-0909 September 1999 Requests That Licensees Affected by Kaowool Fire Barriers Take Issue on Voluntary Initiative & Propose Approach for Resolving Subj Issues.Staff Plans to Meet with Licensees to Discuss Listed Topics ML20211N8041999-09-0808 September 1999 Informs That on 990930 NRC Issued GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design-Basis Accident Condition, to Holders of Nuclear Plant Operating Licenses ML20211N4301999-09-0808 September 1999 Discusses Proposed Meeting to Discuss Kaowool Fire Barriers. Staff Requesting That Affected Licensees Take Issue on Voluntary Initative & Propose Approach for Resolving Issues ML20212C0071999-09-0202 September 1999 Forwards Insp Repts 50-348/99-05 & 50-364/99-05 on 990627- 0807.No Violations Noted.Licensee Conduct of Activities at Farley Plant Facilities Generally Characterized by safety-conscious Operations & Sound Engineering ML20211Q4801999-09-0101 September 1999 Informs That on 990812-13,Region II Hosted Training Managers Conference on Recent Changes to Operator Licensing Program. List of Attendees,Copy of Slide Presentations & List of Questions Received from Participants Encl ML20211K2131999-08-31031 August 1999 Informs That Snoc Has Conducted Review of Reactor Vessel Integrity Database,Version 2 (RVID2) & Conclude That Latest Data Submitted for Farley Units Has Not Been Incorporated Into RVID2 ML20211K4101999-08-31031 August 1999 Resubmits Relief Requests Q1P16-RR-V-5 & Q2P16-RR-V-5 That Seek to Group V661 Valves from Each Unit Into Sample Disassembly & Insp Group,Per 990525 Telcon with NRC L-99-030, Forwards SNC Review Comments on Draft SE & marked-up Copy of Draft SE Incorporating SNC Comments Re Proposed Conversion to ITS1999-08-30030 August 1999 Forwards SNC Review Comments on Draft SE & marked-up Copy of Draft SE Incorporating SNC Comments Re Proposed Conversion to ITS ML20211G6851999-08-26026 August 1999 Informs That During Insp,Technical Issues Associated with Design,Installation & fire-resistive Performance of Kaowool Raceway fire-barriers Installed at Farley Nuclear Plant Were Identified L-99-029, Forwards Revised Response to Chapter 3.1 RAI Requested in 990726 Conference Call,Rai Response Related to Beyond Scope Issue for Chapter 3.5 Requested by Conference Call on 990805 & RAI Response to Chapter 3.8 Requested on 990615 & 07271999-08-19019 August 1999 Forwards Revised Response to Chapter 3.1 RAI Requested in 990726 Conference Call,Rai Response Related to Beyond Scope Issue for Chapter 3.5 Requested by Conference Call on 990805 & RAI Response to Chapter 3.8 Requested on 990615 & 0727 ML20211B9431999-08-17017 August 1999 Forwards Fitness for Duty Performance Data for six-month Reporting Period 990101-990630,IAW 10CFR26.71(d).Rept Covers Employees at Jm Farley Nuclear Plant & Southern Nuclear Corporate Headquarters ML20211B9211999-08-17017 August 1999 Responds to NRC Re Violations Noted in Insp Rept 50-348/99-09 & 50-364/99-09.Corrective Actions:Security Response Plan Was Revised to Address Vulnerabilities Identified During NRC Insp ML20210R5101999-08-12012 August 1999 Forwards Revised Page 6 to 990430 LAR to Operate Farley Nuclear Plant,Unit 1,for Cycle 16 Only,Based on risk- Informed Approach for Evaluation of SG Tube Structural Integrity,As Result of Staff Comments ML20212C8141999-08-0909 August 1999 Forwards Correspondence Received from Jm Sherman.Requests Review of Info Re Established Policies & Procedures ML20210T2021999-08-0606 August 1999 Forwards Draft SE Accepting Licensee Proposed Conversion of Plant,Units 1 & 2 Current TSs to Its.Its Based on Listed Documents ML20210Q4641999-08-0505 August 1999 Informs That NRC Plans to Administer Gfes of Written Operator Licensing Exam on 991006.Authorized Representative of Facility Must Submit Ltr to La Reyes,As Listed,With List of Individuals to Take exam,30 Days Before Exam Date ML20210J8341999-07-30030 July 1999 Forwards Second Request for Addl Info Re Util 990430 Amend Request to Allow Util to Operate Unit 1,for Cycle 16 Based on risk-informed Probability of SG Tube Rupture & Nominal accident-induced primary-to-second Leakage ML20210G4901999-07-30030 July 1999 Responds to GL 99-02, Laboratory Testing of Nuclear-Grade Activated Charcoal, Issued 990603.Ltr Contains NRC License Commitment to Utilize ASTM D3803-1989 with Efficiency Acceptance Criteria Utilizing Safety Factor of 2 L-99-028, Responds to NRC 990730 RAI Re 990423 OL Change Request to Allow for Risk Informed Approach for Evaluation of SG Tube Structural Integrity as Described by NEI 97-06, SG Program Guidelines1999-07-30030 July 1999 Responds to NRC 990730 RAI Re 990423 OL Change Request to Allow for Risk Informed Approach for Evaluation of SG Tube Structural Integrity as Described by NEI 97-06, SG Program Guidelines L-99-027, Addresses Clarifications to Selected Responses to Chapter 3.8 RAI Requested in NRC Conference Call on 990624, Resolution of Open Issue Related to Containment Purge in Chapter 3.6 & Response Related to Chapter 3.51999-07-27027 July 1999 Addresses Clarifications to Selected Responses to Chapter 3.8 RAI Requested in NRC Conference Call on 990624, Resolution of Open Issue Related to Containment Purge in Chapter 3.6 & Response Related to Chapter 3.5 ML20210G8181999-07-26026 July 1999 Forwards Insp Repts 50-348/99-04 & 50-364/99-04 on 990516- 0626.One Violation Identified & Being Treated as Noncited Violation IR 05000348/19990091999-07-23023 July 1999 Discusses Insp Repts 50-348/99-09 & 50-364/99-09 on 990308- 10 & Forwards Notice of Violation Re Failure to Intercept Adversary During Drills,Contrary to 10CFR73 & Physical Security Plan Requirements ML20210E4071999-07-22022 July 1999 Responds to NRC 990702 RAI Re Change Request to Allow for Risk Informed Approach for Evaluation of SG Tube Structural Integrity as Described in NEI 97-06, SG Program Guidelines L-99-026, Forwards Response to NRC 990702 RAI Re SG Replacement Related TS Change Request Submitted 981201.Ltr Contains No New Commitments1999-07-19019 July 1999 Forwards Response to NRC 990702 RAI Re SG Replacement Related TS Change Request Submitted 981201.Ltr Contains No New Commitments L-99-264, Responds to NRC 990603 Administrative Ltr 99-02, Operating Licensing Action Estimates, for Fy 2000 & 20011999-07-13013 July 1999 Responds to NRC 990603 Administrative Ltr 99-02, Operating Licensing Action Estimates, for Fy 2000 & 2001 ML20209H4721999-07-13013 July 1999 Responds to NRC 990603 Administrative Ltr 99-02, Operating Licensing Action Estimates, for Fy 2000 & 2001 ML20196J6191999-07-0202 July 1999 Forwards Final Dam Audit Rept of 981008 of Category 1 Cooling Water Storage Pond Dam.Requests Response within 120 Days of Date of Ltr 05000364/LER-1999-001, Forwards LER 99-001-00 Re Reactor Trip Due to Loss of Condenser Vacuum Steam Dump Drain Line Failure.Commitments Made by Licensee,Listed1999-07-0202 July 1999 Forwards LER 99-001-00 Re Reactor Trip Due to Loss of Condenser Vacuum Steam Dump Drain Line Failure.Commitments Made by Licensee,Listed ML20196J7471999-07-0202 July 1999 Forwards RAI Re Cycle 16 Extension Request.Response Requested within 30 Days of Date of Ltr ML20196J5781999-07-0202 July 1999 Forwards RAI Re 981201 & s Requesting Amend to TS Associated with Replacing Existing Westinghouse Model 51 SG with Westinghouse Model 54F Generators.Respond within 30 Days of Ltr Date ML20196J6571999-07-0202 July 1999 Discusses Closure to TAC MA0543 & MA0544 Re GL 92-01 Rev 1, Suppl 1,RV Structural Integrity.Nrc Has Revised Rvid & Releasing It as Rvid,Version 2 as Result of Review of Responses ML20196J3591999-06-30030 June 1999 Forwards SE of TR WCAP-14750, RCS Flow Verification Using Elbow Taps at Westinghouse 3-Loop Pwrs 1999-09-09
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARL-99-035, Forwards non-proprietary & Proprietary Versions of Farley Units 1 & 2 LBB Calculation Results Due to SG Replacement & SG Snubber Elimination Programs, Used to Support SG Replacement Project.Proprietary Encl Withheld1999-10-18018 October 1999 Forwards non-proprietary & Proprietary Versions of Farley Units 1 & 2 LBB Calculation Results Due to SG Replacement & SG Snubber Elimination Programs, Used to Support SG Replacement Project.Proprietary Encl Withheld ML20217P0661999-10-0606 October 1999 Requests Withholding of Proprietary Rept NSD-SAE-ESI-99-389, Farley Units 1 & 2 LBB Calculation Results Due to SG Replacement & SG Snubber Elimination Programs ML20217B1891999-10-0404 October 1999 Submits Clarification Re Development of Basis for Determining Limiting Internal Pressure Loads Re Review of NRC SE for Cycle 16 Extension Request.Util Intends to Use Guidelines When Evaluating SG Tube Structural Integrity L-99-034, Forwards Comments on Draft Current Tech Specs Discussion of Change Tables for Jm Farley Nuclear Plant.Units 1 & 21999-09-23023 September 1999 Forwards Comments on Draft Current Tech Specs Discussion of Change Tables for Jm Farley Nuclear Plant.Units 1 & 2 L-99-032, Responds to NRC Re Adequacy of Kaowool Fire Retardant Fire Barriers in Use at Jfnp,Units 1 & 21999-09-23023 September 1999 Responds to NRC Re Adequacy of Kaowool Fire Retardant Fire Barriers in Use at Jfnp,Units 1 & 2 ML20212F8861999-09-23023 September 1999 Forwards Revised Relief Request Number 32 for NRC Approval. Approval Requested by 991231 to Support Activities to Be Performed During Unit 1 Refueling Outage Scheduled for Spring of 2000 ML20212C2351999-09-16016 September 1999 Submits Corrected Info Concerning Snoc Response to NRC GL 99-02, Lab Testing of Nuclear-Grade Activated Charcoal ML20212D0101999-09-15015 September 1999 Informs That Submittal of clean-typed Copy of ITS & ITS Bases Will Be Delayed.Delay Due to Need for Resolution of Two Issues Raised by NRC staff.Clean-typed Copy of ITS Will Be Submitted within 4 Wks Following Resolution of Issues L-99-031, Informs NRC That Review of MOV Testing Frequency & Changes Made to Frequency of MOV Testing Has Been Completed1999-09-13013 September 1999 Informs NRC That Review of MOV Testing Frequency & Changes Made to Frequency of MOV Testing Has Been Completed ML20212C4641999-09-13013 September 1999 Forwards Info Requested in Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Exams ML20211K2131999-08-31031 August 1999 Informs That Snoc Has Conducted Review of Reactor Vessel Integrity Database,Version 2 (RVID2) & Conclude That Latest Data Submitted for Farley Units Has Not Been Incorporated Into RVID2 ML20211K4101999-08-31031 August 1999 Resubmits Relief Requests Q1P16-RR-V-5 & Q2P16-RR-V-5 That Seek to Group V661 Valves from Each Unit Into Sample Disassembly & Insp Group,Per 990525 Telcon with NRC L-99-030, Forwards SNC Review Comments on Draft SE & marked-up Copy of Draft SE Incorporating SNC Comments Re Proposed Conversion to ITS1999-08-30030 August 1999 Forwards SNC Review Comments on Draft SE & marked-up Copy of Draft SE Incorporating SNC Comments Re Proposed Conversion to ITS L-99-029, Forwards Revised Response to Chapter 3.1 RAI Requested in 990726 Conference Call,Rai Response Related to Beyond Scope Issue for Chapter 3.5 Requested by Conference Call on 990805 & RAI Response to Chapter 3.8 Requested on 990615 & 07271999-08-19019 August 1999 Forwards Revised Response to Chapter 3.1 RAI Requested in 990726 Conference Call,Rai Response Related to Beyond Scope Issue for Chapter 3.5 Requested by Conference Call on 990805 & RAI Response to Chapter 3.8 Requested on 990615 & 0727 ML20211B9431999-08-17017 August 1999 Forwards Fitness for Duty Performance Data for six-month Reporting Period 990101-990630,IAW 10CFR26.71(d).Rept Covers Employees at Jm Farley Nuclear Plant & Southern Nuclear Corporate Headquarters ML20211B9211999-08-17017 August 1999 Responds to NRC Re Violations Noted in Insp Rept 50-348/99-09 & 50-364/99-09.Corrective Actions:Security Response Plan Was Revised to Address Vulnerabilities Identified During NRC Insp ML20210R5101999-08-12012 August 1999 Forwards Revised Page 6 to 990430 LAR to Operate Farley Nuclear Plant,Unit 1,for Cycle 16 Only,Based on risk- Informed Approach for Evaluation of SG Tube Structural Integrity,As Result of Staff Comments ML20212C8141999-08-0909 August 1999 Forwards Correspondence Received from Jm Sherman.Requests Review of Info Re Established Policies & Procedures ML20210G4901999-07-30030 July 1999 Responds to GL 99-02, Laboratory Testing of Nuclear-Grade Activated Charcoal, Issued 990603.Ltr Contains NRC License Commitment to Utilize ASTM D3803-1989 with Efficiency Acceptance Criteria Utilizing Safety Factor of 2 L-99-028, Responds to NRC 990730 RAI Re 990423 OL Change Request to Allow for Risk Informed Approach for Evaluation of SG Tube Structural Integrity as Described by NEI 97-06, SG Program Guidelines1999-07-30030 July 1999 Responds to NRC 990730 RAI Re 990423 OL Change Request to Allow for Risk Informed Approach for Evaluation of SG Tube Structural Integrity as Described by NEI 97-06, SG Program Guidelines L-99-027, Addresses Clarifications to Selected Responses to Chapter 3.8 RAI Requested in NRC Conference Call on 990624, Resolution of Open Issue Related to Containment Purge in Chapter 3.6 & Response Related to Chapter 3.51999-07-27027 July 1999 Addresses Clarifications to Selected Responses to Chapter 3.8 RAI Requested in NRC Conference Call on 990624, Resolution of Open Issue Related to Containment Purge in Chapter 3.6 & Response Related to Chapter 3.5 ML20210E4071999-07-22022 July 1999 Responds to NRC 990702 RAI Re Change Request to Allow for Risk Informed Approach for Evaluation of SG Tube Structural Integrity as Described in NEI 97-06, SG Program Guidelines L-99-026, Forwards Response to NRC 990702 RAI Re SG Replacement Related TS Change Request Submitted 981201.Ltr Contains No New Commitments1999-07-19019 July 1999 Forwards Response to NRC 990702 RAI Re SG Replacement Related TS Change Request Submitted 981201.Ltr Contains No New Commitments L-99-264, Responds to NRC 990603 Administrative Ltr 99-02, Operating Licensing Action Estimates, for Fy 2000 & 20011999-07-13013 July 1999 Responds to NRC 990603 Administrative Ltr 99-02, Operating Licensing Action Estimates, for Fy 2000 & 2001 ML20209H4721999-07-13013 July 1999 Responds to NRC 990603 Administrative Ltr 99-02, Operating Licensing Action Estimates, for Fy 2000 & 2001 05000364/LER-1999-001, Forwards LER 99-001-00 Re Reactor Trip Due to Loss of Condenser Vacuum Steam Dump Drain Line Failure.Commitments Made by Licensee,Listed1999-07-0202 July 1999 Forwards LER 99-001-00 Re Reactor Trip Due to Loss of Condenser Vacuum Steam Dump Drain Line Failure.Commitments Made by Licensee,Listed L-99-024, Responds to NRC RAI Re Conversion to ITS for Chapters 3.4, 3.5,3.6,3.7,3.9 & 5.0,per 990419-20 Meetings with NRC1999-06-30030 June 1999 Responds to NRC RAI Re Conversion to ITS for Chapters 3.4, 3.5,3.6,3.7,3.9 & 5.0,per 990419-20 Meetings with NRC L-99-025, Forwards Rev 2 to Jfnp Security plan,FNP-0-M-99,IAW 10CFR50.4(b)(4).Attachment 1 Contains Summary of Changes & Amended Security Plan Pages.Encl Withheld from Public Disclosure Per 10CFR73.211999-06-30030 June 1999 Forwards Rev 2 to Jfnp Security plan,FNP-0-M-99,IAW 10CFR50.4(b)(4).Attachment 1 Contains Summary of Changes & Amended Security Plan Pages.Encl Withheld from Public Disclosure Per 10CFR73.21 ML20196J8631999-06-30030 June 1999 Submits Correction to Errors Contained in to NRC Re TS Changes Re Control Room,Penetration Room & Containment Purge Filtration Systems & Radiation Monitoring Instrumentation.Errors Do Not Require Rev of SA L-99-249, Submits Correction to Errors Contained in to NRC Re TS Changes Re Control Room,Penetration Room & Containment Purge Filtration Systems & Radiation Monitoring Instrumentation.Errors Do Not Require Rev of SA1999-06-30030 June 1999 Submits Correction to Errors Contained in to NRC Re TS Changes Re Control Room,Penetration Room & Containment Purge Filtration Systems & Radiation Monitoring Instrumentation.Errors Do Not Require Rev of SA L-99-224, Submits Rev to Unit 2 SG Tube voltage-based Repair Criteria Data Rept.Ltr Contains No Commitments1999-06-0707 June 1999 Submits Rev to Unit 2 SG Tube voltage-based Repair Criteria Data Rept.Ltr Contains No Commitments ML20195F1731999-06-0707 June 1999 Forwards Proprietary & non-proprietary Responses to NRC RAIs Re W TR WCAP-14750, RCS Flow Verification Using Elbow Taps at W 3-Loop Pwrs. W Proprietary Notice,Affidavit & Copyright Notice,Encl.Proprietary Info Withheld L-99-217, Forwards Proprietary & non-proprietary Responses to NRC RAIs Re W TR WCAP-14750, RCS Flow Verification Using Elbow Taps at W 3-Loop Pwrs. W Proprietary Notice,Affidavit & Copyright Notice,Encl.Proprietary Info Withheld1999-06-0707 June 1999 Forwards Proprietary & non-proprietary Responses to NRC RAIs Re W TR WCAP-14750, RCS Flow Verification Using Elbow Taps at W 3-Loop Pwrs. W Proprietary Notice,Affidavit & Copyright Notice,Encl.Proprietary Info Withheld L-99-225, Responds to GL 98-01, Yr 2000 Readiness of Computer Sys at Nuclear Power Plants1999-06-0707 June 1999 Responds to GL 98-01, Yr 2000 Readiness of Computer Sys at Nuclear Power Plants ML20195F0621999-06-0707 June 1999 Submits Rev to Unit 2 SG Tube voltage-based Repair Criteria Data Rept.Ltr Contains No Commitments ML20195E9581999-06-0707 June 1999 Responds to GL 98-01, Yr 2000 Readiness of Computer Sys at Nuclear Power Plants ML20195C6941999-05-28028 May 1999 Forwards Response to NRC RAI Re GL 96-05 for Farley Nuclear Plant.Farley Is Committing to Implement Phase 3 of JOG Program L-99-021, Forwards Response to RAI Re Conversion to ITSs for Chapter 3.3.Attachment II Includes Proposed Revs to Previously Submitted LAR Re Rais,Grouped by RAI number.Clean-typed Copies of Affected ITS Pages Not Included1999-05-28028 May 1999 Forwards Response to RAI Re Conversion to ITSs for Chapter 3.3.Attachment II Includes Proposed Revs to Previously Submitted LAR Re Rais,Grouped by RAI number.Clean-typed Copies of Affected ITS Pages Not Included L-99-203, Forwards Response to NRC RAI Re GL 96-05 for Farley Nuclear Plant.Farley Is Committing to Implement Phase 3 of JOG Program1999-05-28028 May 1999 Forwards Response to NRC RAI Re GL 96-05 for Farley Nuclear Plant.Farley Is Committing to Implement Phase 3 of JOG Program ML20195F2101999-05-24024 May 1999 Requests That Farley Nuclear Plant Proprietary Responses to NRC RAI Re W WCAP-14750, RCS Flow Verification Using Elbow Taps at W 3-Loop Pwrs, Be Withheld from Public Disclosure Per 10CFR2.790 L-99-180, Forwards Responses to NRC RAI Questions for Chapter 3.8 of Ts.Proposed Revs to TS Previously Submitted with LAR Related to RAI1999-04-30030 April 1999 Forwards Responses to NRC RAI Questions for Chapter 3.8 of Ts.Proposed Revs to TS Previously Submitted with LAR Related to RAI ML20206F4321999-04-30030 April 1999 Forwards Responses to NRC RAI Questions for Chapter 3.8 of Ts.Proposed Revs to TS Previously Submitted with LAR Related to RAI L-99-017, Forwards Responses to NRC RAI Questions for Chapters 3.1, 3.2,3.5,3.7 & 3.9 of Ts.Attached Pages Include Proposed Revs Previously Submitted LAR to Rais,Grouped by Chapters & RAI Numbers1999-04-30030 April 1999 Forwards Responses to NRC RAI Questions for Chapters 3.1, 3.2,3.5,3.7 & 3.9 of Ts.Attached Pages Include Proposed Revs Previously Submitted LAR to Rais,Grouped by Chapters & RAI Numbers ML20206C8021999-04-26026 April 1999 Forwards 1998 Annual Rept, for Alabama Power Co.Encls Contain Financial Statements for 1998,unaudited Financial Statements for Quarter Ending 990331 & Cash Flow Projections for 990101-991231 05000348/LER-1998-007, Forwards SG-99-04-001, Farley-1:Final Cycle 16 Freespan ODSCC Operational Assessment, as Committed to in Licensee & LER 98-007-00.Util Is Revising Plant Administrative SG Operating Leakage Requirements as Listed1999-04-23023 April 1999 Forwards SG-99-04-001, Farley-1:Final Cycle 16 Freespan ODSCC Operational Assessment, as Committed to in Licensee & LER 98-007-00.Util Is Revising Plant Administrative SG Operating Leakage Requirements as Listed L-99-015, Forwards Rev 1 to Jfnp Security plan,FNP-O-M-99,resulting from Implementation of Biometrics Sys.Changes Incorporate Changes Previously Submitted to NRC as Rev 28 by Licensee .Encl Withheld,Per 10CFR73.211999-04-21021 April 1999 Forwards Rev 1 to Jfnp Security plan,FNP-O-M-99,resulting from Implementation of Biometrics Sys.Changes Incorporate Changes Previously Submitted to NRC as Rev 28 by Licensee .Encl Withheld,Per 10CFR73.21 ML20206B4391999-04-21021 April 1999 Forwards Corrected ITS Markup Pages to Replace Pages in 981201 License Amend Requests for SG Replacement L-99-172, Forwards FNP Annual Radioactive Effluent Release Rept for 1998, IAW TSs Sections 6.9.1.8 & 6.9.1.9.Changes to ODCM Revs 16,17 & 18 Are Encl,Iaw TS Section 6.14.21999-04-21021 April 1999 Forwards FNP Annual Radioactive Effluent Release Rept for 1998, IAW TSs Sections 6.9.1.8 & 6.9.1.9.Changes to ODCM Revs 16,17 & 18 Are Encl,Iaw TS Section 6.14.2 ML20205S9501999-04-21021 April 1999 Forwards FNP Annual Radioactive Effluent Release Rept for 1998, IAW TSs Sections 6.9.1.8 & 6.9.1.9.Changes to ODCM Revs 16,17 & 18 Are Encl,Iaw TS Section 6.14.2 ML20205R0431999-04-13013 April 1999 Forwards Correction to 960212 GL 95-07 180 Day Response. Level 3 Evaluation for Pressure Locking Utilized Analytical Models.Encl Page Has Been Amended to Correct Error 1999-09-23
[Table view] Category:UTILITY TO NRC
MONTHYEARML20064A7131990-09-17017 September 1990 Advises That Due to Reassignment,Jj Clark No Longer Needs to Maintain Senior Reactor Operator Licenses ML20059J2811990-09-14014 September 1990 Forwards List of Key Radiation Monitors Which Will Be Used as Inputs to Top Level Radioactivity Status Bar Re Spds.List Identifies Monitors Which Would Provide Concise & Meaningful Info About Radioactivity During Accidents ML20065D5961990-09-13013 September 1990 Responds to Violations Noted in Insp Repts 50-348/90-19 & 50-364/90-19.Response Withheld ML20059J1661990-09-13013 September 1990 Forwards Monthly Operating Rept for Aug 1990 for Jm Farley Nuclear Plant & Rev 10 to ODCM ML20059L0751990-09-12012 September 1990 Forwards Revised Pages to Rev 3 to, Second 10-Yr Interval Inservice Insp Program for ASME Code Class 1,2 & 3 Components ML20059J2911990-09-12012 September 1990 Forwards Operator Licensing Natl Exam Schedules for FY91 Through FY94,per Generic Ltr 90-07.Requalification Schedules & Estimated Number of Candidates Expected to Participate in Generic Fundamental Exam,Also Encl ML20064A7111990-09-12012 September 1990 Forwards Rev 1 to Relief Request RR-1, Second 10-Yr Interval Inservice Insp Program for ASME Code Class 1,2 & 3 Components ML20059J2891990-09-12012 September 1990 Confirms Rescheduling of Response to Fitness for Duty Program Notice of Violation 90-18-02,per 900907 Telcon ML20065D6621990-09-12012 September 1990 Forwards NPDES Permit AL0024619 Effective 900901.Limits for Temp & Residual Chlorine Appealed & Stayed ML20064A3431990-08-28028 August 1990 Forwards Corrected Insertion Instructions to Rev 8 to Updated FSAR for Jm Farley Nuclear Plant ML20059D4711990-08-22022 August 1990 Forwards Fitness for Duty Performance Data for Jan-June 1990 ML20059B5101990-08-22022 August 1990 Forwards Semiannual Radioactive Effluent Release Rept for Jan-June 1990.No Changes to Process Control Program for First Semiannual Period of 1990 Exists ML20056B2751990-08-20020 August 1990 Forwards Relief Requests from Second 10-yr Interval Inservice Testing Program for Class 1,2 & 3 Pumps & Valves. Request Incorporates Commitments in 891222 Response to Notice of Violation ML20056B2741990-08-20020 August 1990 Forwards Rev 2 to Unit Inservice Testing Program,For Review & Approval.Rev Incorporates Commitments Addressed in Util 891222 Response to Notice of Violation & Other Editorial & Technical Changes ML20058Q1481990-08-15015 August 1990 Forwards Rev 3 to FNP-1-M-043, Jm Farley Nuclear Plant Unit 1 Second 10-Yr Inservice Insp Program,Asme Code Class 1,2 & 3 Components ML20058P6201990-08-15015 August 1990 Forwards Rev 1 to FNP-2-M-068, Ten-Yr Inservice Insp Program for ASME Code Class 1,2 & 3 Components, Per 891207 & 900412 Responses to NRC Request for Addl Info ML20055G7701990-07-18018 July 1990 Updates 900713 Response to NRC Bulletin 90-001, Loss of Fill-Oil in Transmitters Mfg by Rosemount ML20055F7411990-07-11011 July 1990 Forwards Monthly Operating Rept for June 1990 & Corrected Monthly Operating Repts for Nov 1989 Through May 1990.Repts Revised to Correct Typo on Value of Cumulative Number of Hours Reactor Critical ML20055F3781990-07-10010 July 1990 Submits Final Response to Generic Ltr 83-28,Items 4.2.3 & 4.2.4.Util Position That Procedures Currently Utilized by Plant Constitute Acceptable Ongoing Life Testing Program for Reactor Trip Breakers & Components ML20055D4861990-07-0202 July 1990 Requests Authorization to Use Encl ASME Boiler & Pressure Vessel Code Case N-395 Re Laser Welding for Sleeving Process Described by Oct 1990,per 10CFR50.55a,footnote 6 ML20055D1001990-06-26026 June 1990 Responds to Violations Noted in Insp Repts 50-348/90-12 & 50-364/90-12 on 900411-0510.Corrective Actions:Electrolyte Level Raised in Lights Identified by Inspector to Have Low Electrolyte Level ML20044A6191990-06-26026 June 1990 Suppls 900530 Ltr Containing Results of SPDS Audit,Per Suppl 1 to NUREG-0737.One SPDS Console,Located in Control Room,Will Be Modified So That Only SPDS Info Can Be Displayed by Monitor.Console Will Be Reconfigured ML20043G4741990-06-11011 June 1990 Submits Addl Info Re 900219 Worker Respiratory Protection Apparatus Exemption Rev Request.Proposed Exemption Rev Involves Features Located Entirely within Restricted Area as Defined in 10CFR20 ML20043C1851990-05-29029 May 1990 Forwards Proposed Schedules for Submission & Requested Approval of Licensing Items ML20043B5941990-05-25025 May 1990 Provides Rept of Unsatisfactory Performance Testing,Per 10CFR26,App A.Error Caused by Olympus Analyzer Which Allowed Same Barcode to Be Assigned to Two Different Samples. Smithkline Taken Action to Prevent Recurrence of Scan Error ML20042G7461990-05-10010 May 1990 Certifies That Plant Licensed Operator Requalification Program Accredited & Based Upon Sys Approach to Training,Per Generic Ltr 87-07.Program in Effect Since 890109 ML20042F0831990-05-0101 May 1990 Forwards Rev 18 to Security Plan.Rev Withheld ML20042G3081990-04-25025 April 1990 Forwards Alabama Power Co Annual Rept 1989, Unaudited Financial Statements for Quarter Ending 900331 & Cash Flow Projections for 1990 ML20042E4121990-04-12012 April 1990 Provides Addl Info Re Review of Second 10-yr Inservice Insp Program,Per NRC 890803 Request.Relief Request RR-30 Requested Reduced Holding Time for Hydrostatically Testing Steam Generator Secondary Side ML20012E9571990-03-27027 March 1990 Forwards Annual Diesel Generator Reliability Data Rept,Per Tech Spec 6.9.1.12.Rept Provides Number of Tests (Valid or Invalid),Number of Failures for Each Diesel Generator at Plant for 1989 & Info Identified in Reg Guide 1.108 ML20012D9661990-03-22022 March 1990 Forwards Annual ECCS Evaluation Model Changes Rept,Per Revised 10CFR50.46.Info Includes Effect of ECCS Evaluation Model Mods on Peak Cladding Temp Results & Summary of Plant Change Safety Evaluations ML20012D8901990-03-20020 March 1990 Clarifies 891130 Response to Generic Ltr 83-28,Item 2.2.1 Re Use of Q-List at Plant,Per NRC Request.Fnpims Data Base Utilized as Aid for Procurement,Maint,Operations & Daily Planning ML20012C4701990-03-15015 March 1990 Responds to NRC 900201 Ltr Re Emergency Planning Weaknesses Identified in Insp Repts 50-348/89-32 & 50-364/89-21. Corrective Actions:Cited Procedures Revised.Direct Line Network Notification to State Agencies Being Implemented ML20012C6241990-03-14014 March 1990 Informs of Resolution of USI A-47,per Generic Ltr 89-19 ML20012C4651990-03-13013 March 1990 Provides Verification of Nuclear Insurance Reporting Requirements Specified in 10CFR50.54 w(2) ML20012C2051990-03-0505 March 1990 Forwards SPDS Critical Function Status Trees,Per G West Request During 900206 SPDS Audit at Plant.W/O Encl ML20012A1621990-03-0202 March 1990 Forwards Addl Info Inadvertently Omitted from Jul-Dec 1989 Semiannual Radioactive Effluent Release Rept,Including Changes to Process Control Program ML20012A1301990-03-0101 March 1990 Responds to Generic Ltr 90-01 Re Request for Voluntary Participation in NRC Regulatory Impact Survey.Completed Questionnaire Encl ML20043A7481990-02-0202 February 1990 Forwards Util Exam Rept for Licensed Operator Requalification Written Exams on 900131 ML20006D2311990-01-31031 January 1990 Responds to NRC Bulletin 89-003 Re Potential Loss of Required Shutdown Margin During Refueling Operations. Refueling Procedures Will Be Revised to Incorporate Guidance That Will Preclude Inadvertent Loss of Shutdown ML20006A9091990-01-23023 January 1990 Forwards Response to Generic Ltr 89-13 Re Svc Water Sys Problems Affecting safety-related Equipment.Util Has Program to Perform Visual Insps & Cleanings of Plant Svc Water Intake Structure by Means of Scuba Divers ML20005E4931989-12-28028 December 1989 Provides Certification That fitness-for-duty Program Meets 10CFR26 Requirements.Testing Panel & cut-off Levels in Program Listed in Encl ML20005E3681989-12-28028 December 1989 Responds to Violations Noted in Insp Repts 50-348/89-28 & 50-364/89-28 on 891002-06.Corrective Actions:All Piping Preparation for Inservice Insp Work in Containment Stopped & All Participants Assembled to Gather Facts on Incident ML20005E1971989-12-27027 December 1989 Responds to Violations Noted in Insp Repts 50-348/89-22 & 50-364/89-22 on 890911-1010.Corrective Actions:Steam Generator Atmospheric Relief Valve Closed & Core Operations Suspended.Shift Supervisor Involved in Event Counseled ML20011D5041989-12-22022 December 1989 Responds to Violations Noted in Insp Repts 50-348/89-26 & 50-364/89-26.Corrective Actions:Personnel Involved in Preparation of Inservice Test Procedures Counseled. Violation B Re Opening of Pressurizer PORV Denied ML19332F2111989-12-0707 December 1989 Forwards Final Response to NRC 890803 Request for Addl Info Re Review of Updated Inservice Insp Program,Summarizing Results of Addl Reviews & Providing Exam Listing Info ML19332F0791989-12-0707 December 1989 Responds to Violations Noted in Insp Repts 50-348/89-22 & 50-364/89-22.Corrective Actions:All Managers Retrained on Intent of Overtime Procedures & Sys Established to Provide Independent Check of All Time Sheets Each Pay Period ML19332F1141989-12-0707 December 1989 Forwards Description of Instrumentation Sys Selected in Response to Generic Ltr 88-17, Loss of DHR, Per Licensee 890127 Commitment.Hardware Changes Will Be Implemented During Unit 1 Tenth & Unit 2 Seventh Refueling Outages ML19332F1241989-12-0707 December 1989 Forwards Response to NRC 890803 Request for Addl Info Re Review of Second 10-yr Inservice Insp Program,Per 891005 Ltr ML19353B0071989-12-0606 December 1989 Forwards Rev 1 to Safeguards Security Contingency Plan.Rev Withheld 1990-09-17
[Table view] |
Text
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Al:bam3 P:wer Company e,
600 North 18th Street
- 1 Post Offica Box 2641 DrminghIm, Allbama 35291 -
Telephone 205 250-1000 .U' '
' L-
F. L CLAYTON, JR.
Senior Vice President 7
7p g gg. 7 Alabama Power the soortem electic system September 24, 1980 Docket No. 0-348 No 50-364_
Mr. James P. O'Reilly V. S. Nuclear Regulatory Comission Region II St.1te 300 101 Marietta Street, N.W.
Atlanta, Georgia 30303
Dear Mr. O'Reilly:
As requested by I.E. Bulletin 80-20. " Failures of Westinghouse Type W-2 Spring Return to Neutral Control Switches," dated July 31, 1930 Alabama Power Company submits the enclosed response for Units 1 and 2 of the Farley Nuclear Plant.
lf ther'c are any questions, please advise.
Yours ver u ,
\ }/)? /
,_ F. L. Clayton, Jr. l RWS:de Enclosures cc: Mr. R. A. Thomas Mr. G. F..Trowbridge Mr. L. L. Kintner Mr. E. A. i'eeves Mr. W. H. Bradford Office of I&E Division of Reactor Operations Inspection Washington, D.C.
Office of I&E 1 Division of Construction Inspection Washington, D.C.
Mr. M. D. Hunt I&E, Regic. II vyy1Clish COYY 8010y oo l r3 g h . .. .-
- O ACTIONS TO BE TAKEN BY LICENSEES AND HOLDERS OF CONSTRUCTION PERMITS:
1 Determine whether Westinghcuse Type W-2 control switches with spring return to neutral position are used in safety-related appli-cations at your facility. If so, identify the safety-related i
systems using these switches and the total number of switches so used. If no such switches are used in your facility, you should indicate that this is the case and ignore the remaining questions.
RESPONSE
l All safety related systems have been reviewed to identify all
- Westinghouse Type W-2 control switches with spring return to neutral position. A total of 67 of the subject switches were identified at FNP 4
Unit 1 and 49 in FNP Unit 2. The function of each switch is shown in Appendix A.
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.' 2. Licensees of operating plants using Type W-2 spring return to' neutral control switches in safety-related applications shall perform continuity tests on all such switches. These tests shall be performed with the switch operator in the neutral position and completed within ten (10) days of the date of this bulletin. In addition, this continuity test shall be repeated at least every thirty-one (31) days after the initial test and after each manipulation of the switch from its neutral position. These continuity tests may be discontinued subsequent to implementing the longer term corrective measures described below.
RESPONSE
Unit 1 The 67 switches identified in FNP Unit 1 have been reviewed to determine t' effect of a failure of the neutral contacts to close properly, 58 ;f the identified switches do not use the neutral contacts.
Of the nine unit 1 switches utilizing the neutral contacts, only two are configured such that the subject failure would not be detected and result in defeat of an automatic function. These switches, their function and associated immediate corrective actions are as follows:
- a. Local handswitch at 600V load center ID local control panel (LCP). ED13 p"R TO MCC 15 from 600V load center ID. A failure of this handswitch could prevent auto closure of the
" breaker if the associated " REMOTE-LOCAL" handswitch is in the
" LOCAL" position. The normal position is " REMOTE".
INTERIM CORRECTIVE ACTION:
The " REMOTE-LOCAL" handswitch has been tagged in the " REMOTE" position. Continuity of the neutral contacts of switch ED-13 will be checked prior to placing the " REMOTE-LOCAL" switch to
" LOCAL", after ear,h manipulation of ED-13 when the " REMOTE-LOCAL" switch is in " LOCAL", and every 31 days.
- b. Local handswitch on 600 volt bus 1R LCP. ER02-INCOMING BREAKER.
A failure of this handswitch could prevent automatic bus transfer of 600 volt load center 1R from Unit 1 power to Unit 2 power.
INTERIM CORRECTIVE ACTION: ,
The' automatic bus transfer function is not required to be
, operable prior to Unit 2 operation. The testing requirements of item 2 of this bulletin will be implemented from fuel loading until long term corrective action is completed.
PAGE 2
- c. Local handswitch on 600 volt bus 15 LCP. ES02-INCOMING BREAKER. ;
Local handswitch on 600 volt bus ID LCP. ED12-INCOMING BREAKER.
Local handswitch on 600 volt bus ll LCP. EE12-INCOMING BREAKER.
Local handswitch on 600 volt bus 1D LCP. E002-INCOMING BREAKER.
Local handswitch on 600 volt bus lE LCP. EE02-INCOMING BREAKER.
A failure of the switches could prevent an audible alarm on the EPB of a breaker trip.
INTERIM CORRECTIVE ACTION:
Due to the fact that failure of these handswitches will not affect the visual position indication on the EPB, Load Center or Local Control Panel indicating a breaker trip, no corrective action is necessary prior to the implementation of the longer term corrective action.
- d. Handswitch on Main Control Board NICllHS-2109G - REACTOR BREAKER TRIP.
Handswitch on Main Control Board N1CllHS-2109H - REACTOR BREAKER TRIP.
A failure of these switches to makeup in the neutral position would prevent reset of the reactor trip breakers.
INTERIM CORRECTIVE ACTION:
Due to the fact that the failure of these switches' neutral position contacts to makeup in no way impairs their ability to perform their '
trip (or safety) function, no interim corrective action is to be implemented pending implementation of the long term corrective action.
e Unit 2 Of the 49 switches identified in FNP Unit 2, 40 do not use the neutr al contacts. Of the remaining nine, only two are configured such that the subject failure would not be detected and result in defeat of an automatic function. These switches are as follows:
- a. Local handswitch at 600 volt load center 2D LCP, ED-13-BKR TO MCC 15 from 600V load center 2D. A failure of this handswitch is identical to that of ED-13 in Unit 1 (see item 2a above).
- b. Local handswitch at 600 volt load center 1R LCP.
ER-05-INCOMING BKR. A failure of this handswitch could prevent automatic bus transfer of 600 volt load center 1R from Unit 2 power +o Unit 1 power.
INTERIM CORRECTIVE ACTION:
O FNP Unit 2 is presently not operational, therefore, this item does not apply; ho,'ever, subsequent to Unit 2 fuel loading, the testing requirements of item 2 of this bulletin will be implemented until long term cor rective action is completed. .
Page 3
- c. Local handswitch on 600 volt bus 2D LCP. ED12-INCOMING BREAKER.
. Local handswitch on 600 volt bus 2E LCP. eel 2-INCOMING BREAKER.
Local handswitch on 600 volt bus 20 LCP. ED02-INCOMING 3REAKER.
Local handswitch on 600 volt bus 2E LCP. EE02-INCOMING BREAKER.
Local handswitch on 600 volt bus IS LCP. ES05-INCOMING BREAKER.
A failure of these switches could prevent an audible alarm on the EPB of a breaker trip.
INTERIM CORRECTIVE ACTION:
Due to the fact that failure of these handswitches will not affect the visual position indication of the EF , Load Center, or local Control Panel indicating a breaker trip, no corrective action is necessary prior to the implementation of the longer term corrective action.
- d. Handswitch on Main Control Board N2CllHS-2109G - REACTOR BREAKER TRIP.
Handswitch on Main Control Board N2CllHS-2109H - REACTOR BREAKER TRIP.
A failure of these switches to makeup in the neutral position would .
prevent reset of the reactor trip bre;kers.
INTERIM CORRECTIVE ACTION:
l Due to the fact that the failure of these switches' neutral position contacts to makeup in no way impairs their abilit'; to perform their trip (or safety) function, no interim correctivc action is to be implemented pending implementation of the long term corrective action.
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3.
Licensees of operatinp plants and holders of construction permits shall describe the longer term corrective measures planned and the date by which such nicasures will be implemented by actual instal-lation or by design char.ge, as appropriate. As a minimum, the longer' term corrective measures should include rewiring the indicating light as shown in Figure 1 provided the light is readily visible to the control room operator. If not, failures of the neutral position contacts should be annunciated in the. control 1
room.
RESPONSE
The nine FNP Unit 1 and the nine FNP Unit 2 switches utilizing neutral position contacts will be replaced as soon as replacements are available and plant conditions permit.
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APPENDIX "A" UNIT 1 l
ELEM. NORdiL REMARKS ITEM DIAG. SWITCH & BKR N0. & POSITION NO. DWG. NO. LOCATION SERVICE CONTACT USED
_ 1 D-177047 LHS AT 600V EA08-L.C. lA NO L.C. IA LCP BUS TIE BKR 2~ D-177050 LHS AT 600V EA09-L.C. IA NO L.C. IA LCP TIE BKR TO L.C. ID 3 D-177058 LHS AT 600V EC08-L.C. 1C N0 )
L.C. 1C LCP BUS TIE BKR l 4 lD-177059 LHS AT 600V EC10-L.C. 1C NO L.C. IC LCP TIE BKR T0 i L.C. 1E I
5 D-177064 LHS AT 600V ED08-L.C. 1D N0 '
L.C. 1D LCP TIE BKR TO L.C. IA t
_ 6 D-177070 LHS AT 600V EE07-L.C. 1E N0 L.C. 1E LCP TIE BKR TO L.C. IC l 7 D-177072 HS AT 600V E012-L.C. Ib YES SW W/ FULL TO L.C. 10 LCP INC BKR FROM CONTACT USED LOCK-0VT IN L.C. 1F FOR EPB ALARM TRIP POSITION 8 D-177072 liS AT 60:7V EE12-L.C. 1E
_ L.C. IE LCP INC BKR FROM L.C. 1F 9 D-177074 HS AT 600V ED02-L.C. 1D L.C. 1D LCP INC BKR FROM STA SERVICE XFMR ID 10 D-177074 HS AT 600V EE02-L.C. 1E L.C. 1E LCP INC BKR FROM
- V STA SERVICE XFMR 1E 11 D-177077 HS AT 600V ED04- BKR TO NO L.C. 10 LCP BATT CHRGR 1A 12 D-177077 HS AT 600V EE05- BKR TO N0 L.C. IE LCP BATT CHRGR IB PAGE A-1 l
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. UNIT 1 j ELEM. NORMAL REMARKS
-l ITEM DIAG. SWITCH &
NO. DWG. NO. LOCATION SERVICE CONTACT USED j 13 D-177078 HS AT 600V E009- BKR TO N0 i L.C. 10 LCP BATT CHRGR 1C 14 D-177078 HS AT 600V EE06- BKR TO N0 L.C. 1E LCP BATT CHRGR 1C 15 D-177089/1 LHS AT 600V ED10-BKR TO NO
, L.C. ID LCP MCC 1A l "
l 16 LHS AT 600V EE10-BKR TO NO j L.C. IE LCP MCC IB
.i LHS AT 600V ED05- BKR TO NO ,
, L.C. 10 LCP MCC 1F N0 4
! 18 LHS AT 600V EE11- BKR TO j L.C. 1E LCP MCC 1G t
l 19 LHS AT C00V EE14-BKR TO NO l
! L.C. 1E LCP MCC IT
! 20 LHS AT 600V ED14- BKf! TO N0 i L.C. 1D LCP MCC IU a
e i 21 V LHS AT 600V EE15- PKR TO NO L.C. 1E LCP MCC IV 22 0-177089/2 LHS AT 600V ED13- BKR TO YES - IN AUTO '
L.C. 1D LCP MCC 1S CLOSE CKT WHEN CTR. IS XFER'D TO
' LOCAL' 23 D-177222/1 LHS AT 600V ED15 - CTMT NO L.C. 1D LCP CLR 1A 24 LHS AT 600V ED16 - CTMT NO L.C. 1D LCP CLR 1B i
25 LHS AT 600V EE08 - CTMT NO L.C. 1E LCP CLR 1C 26 V LHS AT 600V EE16 - CTMT NO L.C. IE LCP CLR ID 27 D-177262 LHS AT 600V EDil - CRDM NO L.C. 10 LCP CLNG FAN 1B 28 D-177262 LHS AT 600V EE13 - CRDM NO L.C. IE LCP CLNG FAN 1A PAGE A-2
UNIT 1
. ELEM. .
NORMAL REMARKS ITEM DIAG. SWITCH & BKR NO. & POSITION NO. DWG N0. LOCATION SERVICE CONTACT USED 29 2825 600V BUS EK02 NO 1K LCP INC. BREAKER 30 2826 EK03 NO FDR. TO MCC IK 31 28E. v EK05 NO BUS TIE BRKR.
32 2825 600V BUS ELO2 NO IL LCP INC. BREAKER 33 2826 ELOS NO ,
BUS TIE BRKR. I 34 2826 v ELO9 NO FDR. TO MCC IL i 1
35 2825 600V BUS EH02 NO 1H LCP INC. BREAKER ,
36 2826 EH03 N0 l FDR. TO MCC IX l
37 2E26 y EH05 NO -
} BUS TIE BRKR.
38 2829 600V BUS EJ02 N0 IJ LCP INC. BREAKER 39 2826 EJ05 NO
. BUS TIE BRKR.
40 2826 v EJ09 NO FDR. TO MCC 1Y 41 2831 600V BUS ER02 YES FAILURE OF CONTACT 1R LCP INC. BREAKER WOULD PREVENT AUTO.
BREAKER CLOSE 42 2832 ER03 NO
'r FDR. TO MCC IN 43 2831 600V BUS ES02 YES. CONTACT USED IN IS LCP INC. BREAKER BREAKER TRIP A'_ ARM (EPB) 44 2832 ES03 N0 FDR. TO MCC IP PAGE A-3
1 UNIT 1
! ELEM. NORMAL REMARKS ITEM DIAG. SWITCH & BKR. N0. & POSITION NO. DWG. NO. LOCATION SERVICE CONTACT USED 45 2831 600V BUS ESO4 NO 15 LCP FIRE PROT. PUMP HOUSE l _. 46 2775 DIESEL 1-2A DIESEL 1-2A N0 l LCP SPEED CONT.
47 2775 DIESEL 1-2A YES FAILURE OF CONTACT l
MAN. VOLT. CONT. CLOSURE WILL NOT AFFECT DIESEL 48 2775 DIESEL 1-2A YES FAILURE OF CONTACT V AUTO. VOLT. CONT. CLOSURE WILL NOT AFFECT DIESEL 49 2779 DIESEL 18 DIESEL 1B N0 LCP SPF.ED CONT.
50 2779 DIESEL 1B YES FAILURE OF CONTACT MAN. VOLT. CONT. CLOSURE WILL NOT AFFECT DIESEL Si- 2779 DIESEL 1B YES FAILURE OF CONTACT V AUTO. V0LT. CONT. CLOSURE WILL NOT AFFECT DIESEL 52 2783 DIESEL 1C DIESEL 1C N0
- LCP SPEED CONT.
1 53 2783 DIESEL IC YES FAILURE OF CONTACT MAN. VOLT. CONT. CLOSURE WILL NOT j' AFFECT DIESEL
! 54 2783 DIESEL IC YES FAILURE OF CONTACT l
y AUTO. V0LT. CONT. CLOSURE WILL NOT AFFECT DIESEL 55 2794 DIESEL 2C DIESEL cC NO LCP SPEED CONT.
56 2794 DIESEL 2C YES FAILURE OF CONTACT l
MAN. VOLT. CONT. CLOSURE WILL NOT AFFECT _THE DIESEL
! 57 2794 DIESEL 2C YES FAILURE OF CONTACT y AUTO VOLT. CONT. CLOSURE WILL NOT AFFECT THE DIESEL i PAGE A-4
UNIT 1 ELEM. NORMAL REMARKS
, ITEM DIAG. SWITCH & BKR. NO. & POSITION NO. DWG. NO. LOCATION SERVICE CONTACT USED 58 U-260544- 128 CTMT ISOLATION U-175907 MCB SEC. Al PHASE "B" NO 59 129 CTMT ISOLATION MCB SEC. Al PHASE "B" N0 60 27 CTMT ISOLATION NO l
MCB SEC. A2 PHASE "B" 61 28 CTMT ISOLATION NO MCB SEC. A2 PHASE "B" l
'62 29 CTMT ISOLATION NO l MCB SEC. A2 PHASE "A" !
l l
63 30 SAFETY INJ. N0 MCB SEC. A2 64 31 REACTOR TRIP YES MCB SEC. A2 65 80 REACTOR TRIP YES MCB SEC. C 66 81 SAFETY INJ. NO MCB SEC. C 67 y 82 CTMT ISOLATION NO MCB SEC. C PHASE "A" c
.I PAGE A-5
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. APPENDIX "A"
~
UNIT 2 ELEM. NORMAL REMARKS ITEM DIAG. SWITCH & BKR. NO. & POSITION NO. DWG. N0, LOCATION SERVICE CONTACT USED 1 0-207047 LHS AT 600V EA08- L.C. 2A NO L.C. 2A LCP BUS TIE BKR 2 D-207050 LHS AT 600V EA09- L.C. 2A NO L.C. 2A LCP TIE BKR T0 i L.C. 20 3 D-207058 LHS AT 600V EC08- L.C. 2C NO L.C. 2C LCP BUS TIE BKR 4 D-207059 LHS AT 600V EC10- L.C. 2C NO L.C. 2C LCP TIE BKR TO L.C. 2E 5 D-207064 LHS AT 600V ED08- L.C. 2D NO L.C. 2D LCP TIE BKR TO L.C. 2A 6 D-207070 LHS AT 600V EE07- L.C. 2E NO L.C. 2E LCP TIE BKR TO L.C. 2C 7 D-207072 HS AT 600V ED12- L.C. 20 YES SW W/ PULL TO L.C. 2D LCP INC BKR FROM CONTACT USED LOCK-00T IN L.C. 2F FOR EPB TRIP POSITION ALARM 8 D-207072 HS AT 600V EE12-L.C. 2E L.C. 2E LCP INC BKR FROM L.C. 2F 9 D-207074 H5 AT 600V E002- L.C. 2D L.C. 2D LCP INC BKR FROM STA SERVICE XFMR 20 10 D-207074 HS AT 600V ~ EE02- L.C. 2E L.C. 2E LCP INC BKR FROM STA SERVICE
" V XFMR 2E 11 D-207077 HS AT 600V ED04- BKR TO NO L.C. 2D LCP BATT CHRGR 2A 12 D-207077 HS AT 600V EE05- BKR TO NO L.C. 2E LCP BATT CHRGR 2B PAGE A-6
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. ._ - _x_... -
. UNIT 2
. ELEM. NORMAi. REMARKS l ITEM DIAG. SWITCH & BKR. NO. & POSITION j NO. DWG. N0. LOCATION SERVICE CONTACT USED
! 13 D-207078 HS AT 600V ED09- BKR TO NO l L.C. 2D LCP BATT CHRGR 2C l
14 D-207078 HS AT 600V EE06- BKR TO NO L.C. 2E LCP BATT CHRGR 2C
, 15 D-207089/1 LHS AT 600V ED10- BKR TO NO L.C. 2D LCP MCC 2A
! 16 LHS AT 600V EE10- BKR TO N0 j L.C. 2E LCP MCC 28 l 17 LHS AT 600V ED05- BKR TO NO L.C. 2D LCP MCC IF
- 18 LHS AT 600V EE09- BKR TO NO l L.C. 2E LCP l MCC IG t 19 LHS AT 600V EE14- BKR TO N0 j L.C. 2E LCP MCC 2T )
! 20 LHS AT 600V ED14- BKR TO N0 L.C. 2D LCP MCC 20 l 21 v LHS AT 600V EE15- BKR TO N0 l L.C. 2E LCP MCC 2V
! 22 D-207089/2 LHS AT 600V ED13- BKR TO YES - IN l l L.C. 2D LCP MCC IS AUTO CLOSE CKT WHEN l CTRL IS
, I XFER'D TO
' LOCAL' I 23 D-207222/1 LHS AT 600V ED15 - CTMT N0 l L.C. 2D LCP CLR 2A i
1 24 LHS AT 600V ED16 - CTMT N0 l L.C. 2D LCP CLR 28 25 LHS AT 600V EE08 - CTMT N0
, i L.C. 2E LCP CLR 2C I
26 V LHS AT 600V EE16 - CTMT l'0 l
. L.C. 2E LCP CLR 2D 27 D-207262 LHS AT 600V ED11 - CRDM f!0 L.C. 2D LCP CLNG FAN 2A PAGE A-7
UNIT 2 t ELEM. NORHAL- REMARKS ITEM DIAG. SWITCH & BKR. NO. & POSITION NO. DWG. N0. LOCATION SERVICE CONTACT L' SED 28 D-207262 LHS AT 600V EE13- CRDM NO L.C. 2E LCP CLNG FAN 2B 29 D-207089/1 LHS AT 600V ED06- BKR TO NO L.C. 2D LCP MCC 2CC 30 D-207089/1 LHS AT 600V EEll- BKR TO NO L.C. 2E LCP MCC 2DD 31 D-202825/1 LHS AT 600V EH08 - 600V L.C. NO L.C. 1H LCP 2H INC BKR 32 D-202825/1 LHS AT 600V EJ08 - 600V L.C. NO L.C. 1J LCP 2J INC BKR 33 0-202825/2 LHS AT 600V EK08 - 600V L.C. N0 L.C. 1K LCP 2K INC BKR 34 D-202825/2 LHS AT 600V ELO8 - 600V L.C. NO L.C. IL LCP 2L ING BKR 35 D-202831/1 LHS AT 600V ES0S - 600V L.C. YES L.C. IS LCP IS INC BKR FR CONTACT USED STA SERV XFMR 2S FOR EPB ALARM 36 D-202831/2 LHS AT 600V EROS - 600V L.C. YES L.C. IR LCP 1R INC BKR FR CONTACT USED STA SERV XFMR 2R IN AUT0-CLOSE CKT
. 37 D-202779 LHS/GS AT DSL GEN #2B NO DSL LOCAL SPEED CTRL ;
CTRL PNL 1 38 D-202779 LHS/MV AT DSL GEN #2B YES DSL LOCAL MANUAL V0LT. CONTACT USED CTRL PNL CTRL IN MAN. VOLT.
CTRL CKT.
39 D-202779 LHS/AV AT DSL GEN #2B YES j DSL LOCAL AUTO. V0LT. CONTACT USED CTRL PNL CTRL IN AUTO VOLT CTRL CKT 40 U-260544 128 CTMT ISOLATION N0 U-175907 MCB SEC. Al PHASE "B" PAGE A-8 l 1
, UNIT 2 I ELEM. NORMAL REMARKS
' ITEM DIAG. SWITCH & BKR. N0. & POSITTON NO. DWG. NO. LOCATION SERVICE CONTACT USED I
41 U-215854 129 CTMT ISOLATION NO l
. U-215853 MCB SEC. Al PHASE "B" 42 27 CTMT ISOLATION NO ,
MCB SEC. A2 PHASE "B" j l
43 28 CTMT ISOLATION N0 MCB SEC. A2 PHASE "B" 44 29 CTMT ISOLATION NO MCB SEC. A2 PHASE "A" i
j 45 30 SAFETY INJ. N0 i MCB SEC. A2 I 46 31 REACTOR TRIP YES
! MCB SEC. A2 i
47 80 REACTOR TRIP YES MCB SEC. C 48 81 SAFETY INJ. NO MCB SEC. C 49 v 82 CTMT ? SOLATION NO I MCB SEC. C PHASE "A" l
l O
PAGE A-9
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