|
---|
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 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 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 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 L-99-031, Forwards Info Requested in Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Exams1999-09-13013 September 1999 Forwards Info Requested in Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Exams 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 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 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 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 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 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 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 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 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 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 L-99-027, 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 Guidelines1999-07-22022 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 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 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 ML20196J7471999-07-0202 July 1999 Forwards RAI Re Cycle 16 Extension Request.Response Requested within 30 Days of Date of Ltr 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 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 L-99-024, 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 ML20196J3591999-06-30030 June 1999 Forwards SE of TR WCAP-14750, RCS Flow Verification Using Elbow Taps at Westinghouse 3-Loop Pwrs 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 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 ML20196D1931999-06-22022 June 1999 Discusses Requesting Approval & Issuance of Plant Units 1 & 2 ITS by 990930.New Target Date Agrees with Requested Date ML20196A3401999-06-10010 June 1999 Forwards Insp Repts 50-348/99-03 & 50-364/99-03 on 990404-0515.No Violations Noted ML20196H9801999-06-10010 June 1999 Submits Two RAI Re ITS Section 4.0 That Were Never Sent. Reply to RAI Via e-mail L-99-021, 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-99-022, 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 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 ML20212C2351999-09-16016 September 1999 Submits Corrected Info Concerning Snoc Response to NRC GL 99-02, Lab Testing of Nuclear-Grade Activated Charcoal L-99-031, Forwards Info Requested in Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Exams1999-09-13013 September 1999 Forwards Info Requested in Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Exams 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 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 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 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 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, 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 Guidelines1999-07-22022 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 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, 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-99-249, 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-99-025, 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 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 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 ML20195E9581999-06-0707 June 1999 Responds to GL 98-01, Yr 2000 Readiness of Computer Sys at Nuclear Power Plants L-99-022, 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 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-99-021, 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-99-203, 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 L-99-020, 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 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 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 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 L-99-153, 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 Error1999-04-13013 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 L-99-012, Forwards 10CFR50.46 Annual Rept for 1998,re Effects of ECCS Evaluation Model Mod on Peak Cladding Temp Results Since 1997 Annual Rept & Most Recent PCT Error Rept Submitted 9809101999-03-19019 March 1999 Forwards 10CFR50.46 Annual Rept for 1998,re Effects of ECCS Evaluation Model Mod on Peak Cladding Temp Results Since 1997 Annual Rept & Most Recent PCT Error Rept Submitted 980910 ML20205A2871999-03-19019 March 1999 Forwards Rev 0 to W Rept WCAP-15171, Analysis of Capsule Z from Alabama Power Co Jm Farley Unit 2 Reactor Vessel Radiation Surveillance Program, Presenting Surveillance Capsule Test Results from Capsule Z L-99-125, Forwards Rev 0 to W Rept WCAP-15171, Analysis of Capsule Z from Alabama Power Co Jm Farley Unit 2 Reactor Vessel Radiation Surveillance Program, Presenting Surveillance Capsule Test Results from Capsule Z1999-03-19019 March 1999 Forwards Rev 0 to W Rept WCAP-15171, Analysis of Capsule Z from Alabama Power Co Jm Farley Unit 2 Reactor Vessel Radiation Surveillance Program, Presenting Surveillance Capsule Test Results from Capsule Z ML20205A1531999-03-19019 March 1999 Forwards Corrected Typed & marked-up Current TS Pages for Replacing Previous Pages Submitted on 990222,re CR, Penetration Room & Containment Purge Filtration Sys & Radiation Monitoring Instrumentation L-99-010, Forwards ISI Refueling 15,Interval 2,Period 3,Outage 3 for Jfnp,Unit 1, & Vols 1 & 2 to ISI Refueling 15,Interval 3, Period 1,Outage 1 for Jfnp,Unit 1. Summary of Results May Be Found in Tab B of Encl 21999-03-18018 March 1999 Forwards ISI Refueling 15,Interval 2,Period 3,Outage 3 for Jfnp,Unit 1, & Vols 1 & 2 to ISI Refueling 15,Interval 3, Period 1,Outage 1 for Jfnp,Unit 1. Summary of Results May Be Found in Tab B of Encl 2 ML20205A7611999-03-18018 March 1999 Forwards Annual DG Reliability Data Rept for 1998,per Plant TS 6.9.1.12 & 10CFR50.36.Rept Provides Number of Tests (Valid or Invalid) & Number of Failures for DGs at Jm Farley Nuclear Plant.Ltr Contains No New Commitments ML20205H2741999-03-18018 March 1999 Forwards Info on Status of Decommissioning Funding for Jm Farley Nuclear Plant,Units 1 & 2,IAW 10CFR50.75(f)(i) ML20204D4281999-03-16016 March 1999 Forwards SG-99-03-001, Farley Unit-1 1999 Voltage-Based Repair Criteria 90-Day Rept, Per GL 95-05.Required Rept for Fall 1998 SG Insp Is Included in Rept ML20204E5841999-03-15015 March 1999 Submits Info on Current Levels & Sources of Insurance on Jm Farley Nuclear Plant,Units 1 & 2 ML20207H6781999-03-0202 March 1999 Forwards Revised Epips,Including Rev 3 to FNP-0-EIP-8.1, Rev 95 to FNP-0-EIP-8.0,rev 1 to FNP-0-EIP-8.2 & Rev 4 to FNP-0-EIP-8.3 & Rev 32 to EP FNP-0-EP-0.0 ML20207D4261999-02-25025 February 1999 Forwards Relief Request RR-40 for Units 1 & 2 for SG Primary Nozzles Inside Radius.Util Requests NRC Approval of Proposed Relief Request by Mar 4,2000 to Support Unit 1 SG Replacement Outage in Spring of 2000 & Unit 2 SG in 2001 ML20207C2271999-02-22022 February 1999 Forwards Complete Replacement for 970630 Submittal Re TS Amend to Clarify SR Refs to ANSI N510 Sections 10,12 & 13 to ASME N510-1989,with Errata Dtd Jan 1991 & to Add Footnote Which Ref FNP FSAR for Relevant Testing Details ML20207B8591999-02-22022 February 1999 Forwards Proprietary 1998 Form NRC 5 Annual Rept, of Results of Individual Monitoring Carried Out at Plant.Rept Includes Record of Each Individual for Whom Monitoring Was Either Required by 10CFR20.1502 or Not.Encl Withheld 1999-09-16
[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 ML20059J1661990-09-13013 September 1990 Forwards Monthly Operating Rept for Aug 1990 for Jm Farley Nuclear Plant & Rev 10 to ODCM ML20065D5961990-09-13013 September 1990 Responds to Violations Noted in Insp Repts 50-348/90-19 & 50-364/90-19.Response Withheld ML20065D6621990-09-12012 September 1990 Forwards NPDES Permit AL0024619 Effective 900901.Limits for Temp & Residual Chlorine Appealed & Stayed ML20059J2891990-09-12012 September 1990 Confirms Rescheduling of Response to Fitness for Duty Program Notice of Violation 90-18-02,per 900907 Telcon 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 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 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 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 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 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 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 ML20044A6191990-06-26026 June 1990 Suppls 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 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 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 ML20034C9971990-06-0101 June 1990 Advises That Implementation of Vital Area Door Alarms Previously Scheduled for Completion on 900608 Will Now Be Completed on 900716 Due to Other Plant Mods 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 ML20034B5791990-04-23023 April 1990 Responds to Violations Noted in Insp Rept 50-364/90-08. Corrective Actions:Deficiencies on Feedwater Flow Instruments Repaired & Power Range Nuclear Instruments Adjusted to Read within 2% of Actual Power ML20034A3001990-04-12012 April 1990 Responds to NRC 890803 Request for Addl Info Re Inservice Insp Program.Util Will Submit Rev 1 to Program Upon Receipt of Confirmation by NRC That Issues Satisfactorily Resolved 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) ML20033F3501990-03-0808 March 1990 Emphasizes Belief That Info Contained in Util Re Station Blackout Responsive to 10CFR50.63 NL-90-1454, Forwards SPDS Critical Function Status Trees,Per G West Request During 900206 SPDS Audit at Plant.W/O Encl1990-03-0505 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 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 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 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 ML19332F1241989-12-0707 December 1989 Forwards Response to NRC 890803 Request for Addl Info Re Review of Second 10-yr Inservice Insp Program,Per 1990-09-17
[Table view] |
Text
_ _. _.. _ _.
_ ___ m
.__ _ - ___ _ _ _ _-. _ _. _. _.m
__m.
A'abama Power Comca.y 600 North 18:n Street j
Post Office Bon 2641 0,rmingnam. Alatama 35291 4
Telephone 205 323-5341 m
4 F. L CLAYTON, JR.
e abamaPower Semor Vice Preecent 1
tv s wem eccinc swem I
i April 4, 1980 i
i Docket No. 50-364 I
J j
i Director
)
Office of Nucicar Reactor Regulation i
)
U. S. Nuclear Regulatory Commission i
j Washington, D.C.
20555 1
j Gentlemen:
1
]
.T. M. Farley Nucicar Plant-Unit No. 2 Scismic Qualification Review In accordance with your letter dated February 4, 1980 Alabama Power l
Company submits the enclosed information concerning seismic qualification
]
of safety-related non-NSSS supplied electrical and mechanical equipment.
This information includes an equipment summary list which describes the method of qualification used, service mode requirement, and location. All
]
of the equipment listed is currently installed and is available for inspec-tion.
q j
As agreed to in a telephone conversation on March 27, 1980 between our
[
i representative and the NRC Project Manager for Farley Unit No. 2, we are not j
providing copies of the seismic response spectra at this time due to the i
4 magnitude of the information that is involved. However, a complete set of the seismic response spectra will be made available. to the seismic qualifica-1 tion review team at a pre-meeting to be held prior to the site visit. Con-sequently, the specific building elevations were not provided in the equip-i i
ment summary list.
[
Regarding your request for an acceptable scenario of how to maintain j
the plant in a safe shutdown condition for certain events, we present the following discussion. The design safe shutdown condition for the Farley i
l Nuclear Plant is hot shutdown as described in the FSAR. Thoae structures, l
systems or components required to bring the plant to a safe shutdown (hot' j
shutdown) are Seismic Category I and are designed to continue' functioning during and after an SSE, an OBE, a loss of offsite power and any single failure.
The design is such that the plant can be maintained at hot shutdown j
for an extended period.
These conditions are presented in the FSAR. Many of l
l the-same systems and components are required to place the plant in a cold l
8004100 W, _
l t
o Office of !;uclear Reactor Regulation Page 2 April 4, 1980 shutdown code.
Ilowev er, following an SSE or OBE, or loss of offsite power, combined with any single failure, it is Alabama Power Company's position that a sufficient time period exist to evaluate the conditions of necessary equipment and available options to bring the plant from hot standby to a cold shutdown condition.
Should you have any questions regarding this matter please do not hesitate to call.
Yours truly,,
r
/
q)rc.
F. L. Clayton, Jr.
~
FLCJr/TNE:bhj Enclosure cc:
Mr. C. F. Trowbridge Mr.
R. A. Thomas
h 8
r
~
StPMJtT EQUIPMENT LIST SEISMIC o A IFICATION Category Mechanical J. M. FARLEY n'JCLEAR PtMT-UNIT 2 hoe 1 of 6 QtALIFICATICM METHC3 ftST AsAtT515 "I
II#
bc Stagte Amts Elastal Statt:
Dynamie VE MTES katural Frecuency freqdncy Ants Asis Single l Nlti Single l Nlti Sinale l Nlti sinale l N1 t f ESF Equiprent Room Auxilia ry C
X 7597-20-Md7 Coolers Building 1
Ib97-20'Ib7' N ESF Equipr;ent Room Auxilia ry C
X 21.2 rnolers Buildino I
E5F Equipment Rooet Cooler Auxiliary C
X 7597-20-K37 Thermostats Buildino 2
Containeent Coolers Contaircent C
X 7597-20-M12-5-3 Contain ent Hydroger Contair. ment D
X 31 0 7597-20-M57 Mixing Fans 1
Reactor Cavity Hydregen Containment D
X 7597-20-!bl g Cilution Fans 2
Containment Vent Filter Auxiliary D
X 7597-20-H57 G Unit Ruilding i
~ Auxiliary feedwater Auxiliary A
X 7B7-20-M10 ~
Purp, Turbine Driven Building 2
Auxiliary feedwater Auxiliary A
X 7597-20-H10 Pump, !btor Driven Building 2
Auxiliary Feedwater Auxiliary A
X
~
7597-20-N10-4 5-G Pump lbtor Building 1
Energency Air Compressor Auxiliary B
X 7597-20-N -b-Building 33-1 Control Room Filtration Auxiliary C
X 7597-20-M103 G Unit Fan Building
)
Penetration Room Air Fil-Auxil iary D
X 7597-20-M103
Component Cooling Water luxil ia ry C
X 7597-20-M 2-4 3-G Pumps Building 2
Coeponent Cooling Water Auxiliary C
X 25.9 7597-20-N2 Heat Exchanger Building 1
temp;nent Cooling Water Auxiliary T
X 7TM N 2-4T-Surge Tank Building 2
s SLte%2f ECCIPMEhT LIST Cat'Ic 7 Mechanical 5EISMIC QbALIFICATION J. M. TAMEY huCLEAR PLANT-UNIT 2 j
Page 2 or 6 QuAltflCATION METHOD TEST 44LYSf5
[do NT LMIM WEs stagle Aals Blastal Static Dynamic E
IO" hatcal Frequency Fregancy Aats Ails Single l Nlti Single l Niti Sfnole l Nitt Sinole l Nitt Sump Pumps Aux. Building C
X 7597-20-N1 and Ctmt.
33-1 Peactor Make-up Water Outdoor C
X 7597-20-M95 Pumos 1
Recycle Hold-up Tanks Auxiliary C
X 7597-20-H30 Building 2
Boric Acid Tanks Auxiliary C
X 7597-20-M36 Building 2
HVAC Daepers, Single Blade Auxiliary C
x 90,1 7d97-20-M107-Il Buildinq 2
IF/AC Dampers, Multi-Blade Auxiliary
~C X
16.7~ 7597-20->il07 Building 1
G Limit Switch, liVAC Dampers Auxiliary C
X 7597-20-M107-121 Building
-1
._ Containment Purge Filtra-Auxiliary D
X E97 N13,
tion Unit Building 1
Lube Water Booster Pumps River Wtr.&
C X
7597-20-143 Serv.Wtr.
1 Structures Lube Water Booster Pump River Wtr.&
C X
7597-20-FM3 g Motors Serv.Wtr.
3 Structures Control Room A/C Unit Auxiliary C
X 7597-03-M101-8d-Building 1
Mini-Purge Fans Auxiliary C
X 7597-03-M109-16'.
G Building
-1
~
Battery Room Exhaust Fans Auxiliary C
X 156 7597-03-Ft109 lhters lyDAino 3
Service Water Strainer Serv.Wtr.
C X
7597-20-l1153 Intake Str.
7-1
J stPfcRY EQUIP 4hT Lisi J. M.
kuCL th!T 2 M*U - O3 I
Page 3 of 6 QiALIFICATION METH00 Test AAAlvsts
[gR E
NNT MTIM t
single Amts Stautai static Dynamic RE ERE t IO" Frecuency Frequency Amis Anis single lMuitt stacie I mitt stnateImitt staaie I mitt vm 7
River Water Pumps River Water C
X 7597-20-M43 Johnson Intake Str.
1 Service Water Pumps Service Wtr.
C X
7597-20-M 3 Intake Str.
1 River Water & Service Intake Strs.
C X
24.1 7597-20-N 3 Water Pumps fbtors t'ain Stean Isolation Auxiliary
~~
I E
X 230 U205110(M5d.3-Valves Building 39-4)
Excess Flow Check Valves Conta intrent E
X U2764 92(FS8.3-Building 604-01 )
i Main Steam Bypass Valves Aux ilia ry E
X 36 U405414 (M56.3-Building 454-01)
Aux.Fw.t'otor Operated Auxiliary T
X 82 GTOT413(Is8.3-Valves Building 450-01) 4"-150# to Gate Valve Various C
X 27 U205417(M58.3-1 3'i-01) 6"-150# M0 Gate Valve Ctat. & Aux.
C X
~ 63 0402467(M5d.3-Building 598-01) 24 "-150 f f 0 Ga te Va l ve Auxiliary C
X 27 U4054 66(M58.3-Building 587-01)]M5d.3-3"-600# A0 Stop Check Auxil ia ry C
X 63 U405459 Valve Building 575-01) 6"-150# IV Globe Valve Ctmt. & Aux.
C X
35 040:>459(M58.3-Building 471-01) 8"-150f M0 Globe Valve Auxil ia ry C
X 91 U405325(M58.3-Building 253-01) 12"-150# 10 Gate Valve Auxilia ry C
X ~
31 U405324(M58.3-Building 257-01) l T0"-150# M0 Gate Valve Ctmt. & Aux C
X 24 U405323(if58.3-j Bullding 256-01) l
s siff%AT EQUIPMkT LIST SEliMIC QUALIFICATION Mechanical Category J. M. FARLEY huCLEAR Pt.AAT.ut!T 2 Page 4 of 6 l
QUALIFICATION ETHOD TEST ANALYSf 5 D
RfC Single Amts 81ssiel Static Dynamic E
M Natural Frequency frequency Aals Amts Single l Nitt Single l Nitt Sinole l Nitt sincie l N1ti 8"-150# MO Gate Valve Auxiliary C
X 22 U405322(M58.3-Building 255-01) 6"-150# [10 Gate Valve Ctat.& Aux.
C X
37 U40532)(M38.3-Buildino 254-01)
~
2"-Y-Type m Globe Valve Various C
X U405556(M58.5-G 77-1) 3/4"&l"-Y-Type MO Globe various C
X U405557(Mao.5-g Valve 78-1) 1507 - Relief Valves Auxiliary C
X 202 U277575(M61-122-I Building
, lj 150# - Relief Valves Auxiliary C
X 04155025(M61 G Building 5)
Main Strn Safety Relief Auxiliary C
X 117 U40$025(M61 '
valve Building 2L P&S" tiMK11-Class 3
~ Containment C
X 4217 lug 56TSTk53.4-Butterfly Valves 136-1) 30" NXL Triton Butterfly Auxiliary C
X N055U3(MSS.4-G Valve Building 54-1) 36" NXL Triton Butterfly Yard C
X U405503(h5d.4-G Valve 48-1) 30" tiXL Triton Butterfly Yard C
X U405503(M53.4-G
_ Valve 49-1) 42" 14XL Triton Butterfly Yard C
X 0405503(M58.4-G Val ve 50-1) 6",8",10" 12" 14",16".18" Auxiliary C
X, 33 WO5503(M58.4-20"$24" Butterfly Valves Building 53-1) 2" Rockwell Valve for Auxiliary C
X 1317 0405503(M5d.5-Seal Injection Line Building 141-1) 48" Purge Va.lves Ctmt. & Aux E
X U405503 (M13 G Building 2)
Bettis Actuator T-412-5R3 Ctmt. & AE T X_
Tli465503(M13 G Building 2)
I stPNARY ECu1PMwT LIST 5ElsMIC 0@tIFICATION Mechanical g, tem J. M. FARLEY N'JCLEAR PLANT-lNIT 2 Pa p 5 of 6 i
QUALIFICATION E TICD TEsf AutV515
[,*ED T
LMIm WEs sing *e Aals 8tantal Static Dynamic E
E Natural Frecancy Frequency Amts Aats sinole l Mtt sta,le l mitt single I mitt since l M et
'fNf#
36" Butterfly Valve Containment C
X 165 U405503(M13 1)
Butterfly Valves Auxiliary C
X 161 L405503(M13 02E15V001A-D Bullding 1)
Butterfly Valves Auxiliary C
X 127 U405503(M13-s3-02E15V002A&B
_ Building 1]
Butterfly Valves Auxiliary C
X 142 U403503(M13 Q2E15V003A&B Bullding 1)
Butterfly Valves Auxiliary C
X 135 U405503(M13 -
_Q2V48V001 A &B Building lj Bettis Actuator T416-SR2 Auxiliary C
X 0405503(M13 g Building 1) 8" Butterfly Valves (Spares C
X 776 U405503(M13 1)
'l8" Purge Valves Ctmt. & Aux <
E X
724 040dbO3(M13-d7-Building 1)
River Water Pumps River Wtr.
C X
U-I t>0eb5 Byron Structure Jackson 8" Vacuun Breakers River Wtr.
C X
U-162937 G
Structure 60* tbtor Operated River Wtr.
C X
U-161283 G
Butterfly Valves Structure 54" Motor Operated River Wtr.
C X
U-161284 G
Butterfly Valves Structure Pressure Switches River Wtr.
C X
U-162934 Structure 20" Metal Expansion Joints River Wtr.
C X
29 U-187237 Structure Emergency Diesel fuel Oil Dsl. Fuel C
X U-161945 Pumps Oil Tank
3 I
SLFriAAY EQUIPMEhT LIST Category Mechanical
}
J. M.
1 N CL R LEIT 2 Fage 6 of 6
QRIFICATION METHOD NT NTIm TEST ANALTSIS y, ;ED Single Aats Stautal Static Dynamic R1 E NCE FOR Ne twal Frec ency Frequency Amis Amis Single Ni tt Single I Nitt Sinale ! Multi single I Nitt Ecergency Diesel Fuel Oil Dsl. Fuel C
X 35 U-162978 Pump Motor Oil Tank IS" biesel Fue'. Oil Dsl. Fuel C
X 27 U-le776 Y-Strainer 011 Tank Eraergency Diesel Fuel Oil Buried near C
X U-161194 Storage Tank Dsl. bldg.
Refueling Water Storage Yard C
X U-161437 Tank Condensate Storage Tank Yard C
X CBNI Contract No. 72-4860 Reactor Make-up Storage Yard C
X CBNI Contract Tank No. 72-4858
P SUM *ARY EQUIPPENT LIST SE!5MIC cuALIFICAT!Cn Category Electrical J. M. FARLET NUCLEAR PLANT-tmIT 2 Page I of 6 QuALIF! CAT!ON METH03 TEST A%Alv515 7fg,"ED CC M ENT M ION WEs single Auf s Blautal Static Dynamic E
FOR Na ttarel Frequency Freq e cy Aats Aals stagle l Nitt Sinale l N1tt 51 mole l Nitt single l Nitt 4.16KV Switchgear Auxiliary C
X 7597-20ES.1-Building 223-1 6007 Load Centers Auxiliary C
X 7597-20E6.1-236-Building 1 thru 242'l Emergency Ltg. Batt. Packs Various D
X 7597-20E14.5 2 Control Rm. Louvered Control D
X 177 7697-03E14.4 Celling Roo:n 1(Units 1 and 2i Heat Trace Equipment Auxiliary C
X 7597-20E80.1 -130
~
Building thru 132 Med. Voltage Elect. Penet.
Containment C
X 7597-20E22-56-1 100 Series Elect. Penet.
Containment C
X 7597-20E22 Motor Control Centers Auxiliary, C
X M97-20E7.1-105-Diesel 3
Buildings Station Batteries Auxiliary C
X 7597-20E10.4 Building I
Emergency Pwr. Pnl Boards Auxiliary C
X 7597-20 Ell-92-2, Building 93-2 Battery Chargers Auxiliary C
X 7597-20E10.d _ Building
_1 Local Control Panels Auxiliary C
X 7597-20Eo.1-242-Buildin9 1
Power Center Transformers Auxiliary C
X 7597-20E6.1-225 Building 3
Local Cont.Pnl.(125VDC)
Auxiliary C
X 64.5
~7597-20 Ell-93-1 Building AKD-5 Low Voltage Swgr.
Auxiliary C
X 7597-20E11 2 Building States Terminal Blocks Ctmt. & Aux C
X 7597-03/20 E-95 l
Building i
e o
$tw.*JtY ECUIPMENT LIST stismic c a FICATION J. M. FARLEY NAEAR PLANT-th!T 2 Cat W Electrical Page 2 of 6 QUALIF! CATION METH03 TEST ANAtYSIS WENT MTim fE-W E5 37KED Single Amis Blamtal Static Dynamic hE FOR Frequency Frequency Amis Ants 7
single
' Nitt single l Nitt
$1nale I Nitt sin 9 e l Nitt (Hz) l Sola Regulators Auxiliary C
X 7597-03/20A7d-Building 143 Uninterruptable Power Auxiliary C
X 7597-03/20E10.4 Supply Building 14-1 CDP Panel Boards Auxiliary C
X 7597-20 Ed2.1-Building
~3-1 Misc. Cont. Stat.& Devices Auxiliary C
X 75f7-20 E90 Buildirg 2
D.C. GRD. CET. CAB.
S. W.
C X
SCSE-1 Building a
3attery and Charger S. W.
C x
SCSE-2 Building 3attery Rack S. W.
C X
28.6 SCSE-3 Building Gen. Neutral Grd. Resistor Diesel C
x SCSE-4 Building L
Diesel Gen. Relay Panel Diesel C
x SCSE-S Building Pond Level Cat,inet Diesel C
X SCSE-6 Building fuel Oil Transfer Cab Diesel C
X SCSE-6 Building HVAC Control Diesel RW &
C x
SCSE-6 Cab i SW Building 1VAC :cntrol Diesel RW &
C x
SCSE-6 Cas 2 SW Building Coolir.g and Lube Water RW & SW C
X SCSE-6 Control Cab Ruildino Auto Transfer Switch Diesel C
X SCSE-7 Building Surge Protection Package RW & SW C
x SCSE-8 Building
t a
$L'?%RY E00!PaaINT L!si SElsat!C CLAIFICATION Ca te9er, El ec trical J. M. FAntty nuctuR Put1T-m!T 2 Pa9e 3 of 6 QUALIFICATION PET)CD TfsT A%Alvsfs E-7,'yPED 2
MT!m TEs single Aals Blantai static Dynamic FOR E
Fregancy Frequency Aals Axis 7
si,91. l Nitt sir.gie i mitt sino1 I mitt singie I mitt
( ri Relays for Diesel Gen.
Diesel C
X SCSE-9 Panel Building Diesel Generator Diesel C
X SCSE-12 F.H Building
- 3. C. Undervoltage and S. W.
C X
SCSE-13 3att. Fuse Cabinet Building lattery Fuse Box S. W.
C x
SCSE-14 Building
- 3. C. Dist. Cabinet
- 5. W.
C X
SCSE-15 Building 3attery Charger Transfer S. W.
C F
$ witch Building
-let Pit Level Inst. Jct.
S. W.
C F
lox
~ Building WTC Fan Tiner S. W.
C F
Building lVAC Emergency Purge Sta-Diesel C
F tion _
Building iVAC Ventilator Shutoff Diesel C
F station Building 0
0
e a
~
\\
StM*ARY EQUIP 4NT List Qtege d ecM cal _
J. M.
NJcl T tm!T 2 4
of b
Fage QUALIFICATION ETIC 3 TEsi ANAlvsts CNMT LMIm W E5 7019 0 single Asts Blantal static Cynamic ERifH.E FOR Nataal Freqancy Frequency Amts A41s Single l Nlti Single l Nlti Single ! Nitt Sinole l Nitt Electrical Cabinets, Auxiliary C
X F213.1 -0061 -01 Printed Circuit Card-Building g
analog Conparator. Elec-tronic Switch Pressure and Differential Auxiliary A
X H213.1 -0064-01 Pressure Transmitters Building Annubar Orifice Plates Conta inment C
r pci M213.1 -0134-02 Annubar Orifice Plates Aux. Bldg.
C X
25 M213.1-0134-02 Resistance Thermoicters Auxiliary C
X f 213.1-0109-01 Buildinq Level Transmitter Containment C
X f!213.1 -0114-01 Dif f. Pressure Trans-Auxilia ry C
X M213.1-Oll2-01 attters Building M213.1 -0113-01 Indicators. Edgewise Auxil ia ry C
x N2T3.1 -Ol l o-01~
Duilding
' Air Operated Globe Valve Containment C
X 27 f1004.04-0236 thru 0274 Air Operated Butterfly Auxilia ry C
X
~20 f1004.04-0236 Val ve Building thru 0274 Air Operated Globe Auxiliary A
X 15 FUO4.06-0015-Valve Used for Building 01 G
"ain Stm Atmospheric Relief Valves Solenoid Valve R.W. Pmp C
X Asco Test Report Wet Pit No. 1357-4 Ind. Flow Controller S.W. Pmp C
X U-187065 Wet Pit Ind. Flow Controller R.W. Pmp C
X U-ld7035 Wet Pit P?'esTuTe HegliDTor
-~S~- D. Pop T
X U TH7041 (Nitrogen Bottle)
Wet Pit
SUMMARY
EcU!PKMT List g
sIlsMIC Q'JALIFICATION Electrical Ca tW J. M. FARLET huCLEAR Pt.AMT.tMIT 2 Page 5 of 6
CuALIFlcATIOn METHO3 TEST A'tALYS!$
W T!m 7;,'ED single Amis Biastal static Dynamic RE E
IO" f"[
Freg ency frequency Axis Amis p
$1n11e l Multi Single I Pblti Sinole l Multi Single l Nlti fur)
Sressure Regulator R. W. Pmp C
X U-187tM1 (Nitrogen Cottle)
Wet Pit uevel Transmitter S. W. Pmp C
X U-187022 Wet Pit Level Transmitter R. W. Pmp C
X U-187022 Wet Pit
- evel Alarn Switches S. W. Pep C
X U-ld7133 Wet Pit Level Alarm Switches R. W. Pmp C
X U-187133 Wet Pit 3
- .evel Switches Pond In-C X
U-187536 take
' evel Switches (Flooding) 71v Box at C
X U-162760 S.W. Str.
Level Switches (Flooding)
Diesel Gen.
C X
U-162760 Butiding Level Switches (Flooding)
River In-C X
U-162760 Take Str.
Level Switches (Flooding)
Dsl. Gen fuel C
X U-162760 Oil Sto.Rm.
Level 5 witches (Flooding)
- 5. W.
C X
U-lb2/bu Intake Pressure Gages-Dsl. Gen. Aux.. Diesel C
X U-162953 o p for Jacket Water Genera tor m
System River Water Pump Lube &
R. W.
C X
U-162735 Cooling Water Strainer Structure Service Water Pump Lube &
S. W.
C X
U-162735 Cooling Water Strainer Structure Pressure Switch S. W. Pmp C
X U-187133 Wet Pit Pressure Switch R. W. Pmp C
X U-187133 Wet Pit
i l
r l
I s'JHutf EQUIPMWT LIST SEtsMIC QUALIFICATION J. M. FARLEY NUCLEAR PLANT-tMIT 2 Ca tegory Electrical Page 6 of 6 QtJALIFICATICM KTM)3 TEST AMAtv515
- E-MT T!m 3gRE0 str.gle Aals Stanial Static Oynamic RE RE E I$
FOR Frequency Frequev y Amts Amts tu Staqle l Nlti Single l Nitt 51mclelK.Itt Stagle Nl t t fwr)
I Solenoid Valve S. W. Pmp C
X Asco Test k'et Pi t Report No.1357-4 Vertical Scale Indicators Control Rn.
C X
U-187039 Power Supply Control Pa.
C X
North Elect.
Standard No.
662-1780-196/1 Differential Pressure R. W.
C X
U-162767 o
Switch Structure a
e O
e
9 JOSEPH M. FARLEY NUCLEAR PLANT - UNIT 2 NOTES FOR
SUMMARY
EQUIPMENT LIST A)
Hot Standby B)
Cold Shutdown C)
Both Hot Standby and Cold Shutdown 0)
Neither Hot Standby or Cold Shutdown E)
Component not needed for normal plant shutdown; however, integrity must be maintained during an accident and/or seismic event.
F)
Documentation search continuing.
G)
Components for which no natural frequency is given, or for which the natural frequency indicated is on the amplified part of the response spectrum; the static analysis performed included seismic
' forces that were obtained by using the peak response spectrum acceleration value or by using a conservative value of 39 or greater.
H)
Calculated natural frequencies of components contained in document reference.
?
i t
-