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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
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Al b ma Power Company 600 Nortn 18th street Post Office Box 2641 Birmingham, Alabama 35291 Telephone 205 250-1000 F. L CLAYTON, JR. t senior Vice President Alabama Power the southem elec:rc system September 24, 1980 Docket No. 50-364 Director of Nuclear Reactor Regulation U. S. Nuclear Regulator Commission Washington, D. C. 20555 Attention: Mr. R. L. Tedesco JOSEPH M. FARLEY NUCLEAR PLANT - UNIT 2 REQUEST FOR ADDITIONAL INFORMATION Gentlemen:
Enclosed is Alabama Power Company's response to NRC Power Systems Branch questions 040.1 through 040.14.
If there are any questions, please advise.
Yours very_,trtriy, ,A lb *
( % L. Clayton, Jr.
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cc: Mr. R. A. Thomas Mr. G. F. Trowbridge Mr. L. L. Kintner Mr. W. H. Bradford N \
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OUESTIONS CONCERNING DIESEL GENERATORS C'].1 Provide a discussion of the measures that have been" taken in int design
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of the standby diese1 generator air starting systas to preclude the .
l fculing of the air start valve or filter with moisture and contaminant-such as oil carryover and rust. (SRP 9.5.6, Part III, item 1).
020.2 Experience at some operating plants has shown that diesel engines have (9.5.3) failed to start due to accumulation of dust and other delitarious .
material on electrical equipment associated with starting of the diesel generators (e.g., auxiliary rele. contacts, control switches - etc.).
1 Describe the provisions that have been made in your diesel generator l t -
building design, electrical st. :ing systa=, and combustien-air and ventilation air intake design ( ' to preclude this tendition to assure availability of the diesel generator on demand.
-- Also describe under normal plant operation what p.acedure(s) will be used to minimi:e accumulation of dust in the diesei generator room, specifically address concrete dust control. In your responses also .
consider the condition when Unit 1 is in operation ana Unit 2 is . . _
under construction (abnormal generation of dust).
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4 J 040.3 The diesel generators are required to start automatically on loss of (9.5.3) all offsite power and in the event of a LOCA. The diesel generator sets should be capable of operation at less than full load for extended periods without degradation of perfomance or reliabiltty. Should a LOCA occur with availability of offsite power, discuss the design
- provisions and other parameters that have been considered in tb election .
of the diesel generators to enable them to run unloaded (on standby) for extended periods without degradation of engine perfomance or reliability.
Expand your PSAR/FSAR to include and expitef tly define the capah.flity of your design with regard to this requirement. (SP.P 9.5.5, Part III, Item 7).
- C40.4 Section 9.5.4.1 emrsency diesel engine fuel all storage and transfer system (9.5.4) u (EDEFSS' does not specifically reference AMSI Standard N195 " Fuel Oil Systems for Standby Diesel Generators". Indicata if you intend to co@ly with this stan-dard in your de:ign of the EDEFSS; othentise provide justification for non-co=pitance. (SR? 9.5.4, Rev.1. Part II, item 12).
040.5 Assume an unlikely event has occurred requiring operation of a diesel generator (9.5.4) for a prolonged period that would require replenishment of fuel oil without in-
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i terrupting operation of the diesel generator. What provision will be made in the design of the fuel oil storage fill system to minimize the creation of tur-bulence of the sediment in the botten of the storage tank. Stirring of this sediment during addition of new fuel has the potential of causing the overall que ity of the foal to become unaccepta51e and could potentially lead to the degradation or failure of the diesel generator.
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1 040.6 Discuss the precautionary measures that will be taken to assure the quality (9.5.4) and reliability of the fuel oil supply for eeergency diesel generator operaticn.- )
Inc1ude the type of fuel oil, igurity and quality limitations as well as diesel l '
index number or its equivalent, cloud point, entrained c:ctsture, sulfur, parti- l 1
culates and other deliterious insoluble substances; procedure for testing newly l delivered fuel, periodic sagling and testing of on-site fuel oil (including )
interval bety:een tests), interval of time between periodic removal of conden-sate from fuel tanks and periodic system inspection. In your dise:ssion in-clude reference to industry (or other) standard which will be followed to assure a reliable fuel oil supply to the emergency generators. (SRP 9.5.4, Part III, iter.s 3 and 4).
040.7 A study of the University of Dayton has shown that accumulation of water in (9.5.6) the starting air system has been one of the most frequent causes of diesel RSP engine failure to start on demand. Condensation of entrained moisture in compressed air lines leading to control and starting air valves, air start
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c:stors, and condansation of noisture on the working surfaces of these .
c:mponents has caused rust, scale and water itself to build up and score and jam the' internal working parts of these vital components thereby preventing starting of the. diesel generators. ,,
in the event of 1oss of offsite power the diesel generators mst function since they are vital to the safe shutdown of the reactor (s). Failure of the diesel engines to start from the effects of catsture condensation in air starting systects and from other causes have lowered their operational reliability to substantia 11y less than the desired reliability of 0.99 as
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specified in Branch Technical Position ICSE (PSB) 2 " Diesel Generator Reliability Testing" and Regulatory Guide 1.108 " Periodic Testing of Diesel Generator Units Used as Onsite Dectric Power Syste 2 at Nuclear Power Plants."
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In an effort toward improving diesel' engine starting reliability we require that compressed air starting system desigvis include air dryers for the removal of entrained reisture. The two air dryers ecst connonly used are the dessicant and refrigerant types. Of these two types, the refrigerant type is the one :nost suited for this appiteation and therefore is pre-ferked. Starting air should be dried to a dew point of not more than 500 F when installed in a normally controlled 700F environment, otherwise the starting air dew potnt should be controlled to at le'ast 100F less than !
the lowest expected ambient temperature.
Revise your design of the diesel engine air starting system accordingly, describe this feature of your design.
000.8 Operating experience at certain nuclear power plants which have two (8.3)
RSP cycle turbecharged diesel engines manufactured by the Dectromottye Division (EMD) of General Netors driving emergency generators have experienced a significant number of turbocharger mechanical gear drive fail ures . The failures have occurred as the result of running the emergency diesel generators at no load or itght load conditions for extended periods. No load or light load operation could occur during
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periodic equipment testing or during accident c nditions with availability of offsite power. When this equipment is operated under no load conditions insufficient exhaust gas volume is generated to operate the tur!pcharger.
As a result the turbocharger is driven mechanically from a gear drive in order to supply enough c:mbuston air to the engine to maintain rated speed. The turbocharger and mechanical drive gear normally sapplied with these engines are not designed for standby service encountered in nuclear power plant application where the equipment may be called upon to operate at no load or light load condition and full rated speed for a prolonged, period. The EMD equipment was originally designed for locerctive service .
where no load speeds for the engine and generator are much' lower than full load speeds. The locomotive turbecharged diesel hardly ever runs at full speed except at full load. The DiO has strongly recede'nded to users of this diesal engine design against operation at no load or light load conditions at full rated speed for extended periods because of the short life expectancy of the turbocharger mechanical gear drive unit normally furnished. .% load or light load operation also causes general i deterioration in any diese1 engine.
l To cope with the severe service the equipeent is norna11y, subjected to and in the interest of reducing failures and increasing the availability of j their equipment EMD has deve1oped a heavy duty turDCCharger drive gear unit that can replace existing equipment. This is available as a ,
replacement kit, or engines can be ordered with the heavy duty turbo-charger drive sear assembly. 4 D"30 *D TTh WA af .1 Ahh
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. 1 To assure optimum availability of emergency diesel generators on demand, Applicant's who have on order or intend to order emergency generators .
s driven by two cycle diesel engines manufactured by E".D should be provided with the heavy duty turbocharger =echanical drive gear assembly as reccmended by EMD for the class of service encountered in nuclear power plants. Conftm your comp 1tance with this requirement.
040.9 Provide a detati discussion (or plan) of the level of training proposed (8.3) for.your operators, maintenance crew, quality assurance, and supervisory personnel responsible for the operation and maintenance of the emergency diese1 generators. Identify the number and type ef. personnel that will be dedicated to the operations and maintenance of the emergency diesel generators and the nc.ber and type that will be assigned from your general plant operations and maintenance groups to assist when needed.
In your discussion identify the aynt and kind of training that will be
_ received by each of the above cate'gories and the type of ongoing training program planned to assure optimum availabtitty of the emergency generators.
l Also discuss the level of education and mintmum experience requirements l for the various categories of operations and maini:enance personnel associated with the e ergency diese1 generators.
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! 040.10 Several fires have occurred at some operating plants in the area of .
(9.5.7) .
the diesel engine exhaust manifold and inside the turbocharger housing ;
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- which have resulted in equipment unavailability. The fires were started frem lube oil leaking and accumulating on the engine exhaust manifold and accumulating and igniting inside the turbocharger housing.
- Accumulation of lube oil in these areas, on se=e engines, is apparently caused from an excessively long prelube period, generally longer than five minutes, prior to manual starting of a diesel generator. This condition does not occur on an emergency start sine- the prelube parfod is minimal. .
- _. When manually starting the diesel generators for any reason, to sintmize the potential fire ha:ard and to improve equipeent availabil't'ty, the prelube period should be limited to a maximum of three to five minutes unless otherwise recc.:: ended by the diesel engine :r.anufacturer. Confirs your compliance with this requirement or provide your justtfication for requiring a 1 cager prelube time interval perior to manual starting of the diesel generators. Provide the prelube time interval your diesel engine will be exposed to prior to manual start.
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040.11 An erargency diesel generator unit in a nuclear power plant is normally (9.5.7) in'the ready standby mode unless there is a loss of offsite power, an RSP accident, or the diesel generator is under test. Long periods on standby have a tendency to drain or nearly empty the engine. lube oil piping system. On an emergency start of the engina as much as 5 to 14 or acre
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seconds may elapse from the start of cranking until full lube oli pressure is attained even though full e.ngine speed is generally reached in about five seconds. With an essenttally dry engine, the ::cmentary lack of lubrication at the various moving parts ray damage bearing surfaces pro-ducing incipient or actual component failure with resultant equipment unavailability.
The emergency conditten of readiness requires this equip =ent to attain full rated speed and enable automatic sequencing of electric load within ten seconds. For this reason, and to improve upon the availahtitty of this equipment on demand, it is necessary to establish as quickly as possible an oil film in the wearing parts of the diesel engine. Lubricating oil is normally delivered to the engine wearing parts by one or more engine driven pump (s). Euring the starting cycle the pump (s) accelerates slowly with tne engine and may not supply the required quantity of lubricating' oil where needed fast enough. To remedy this condition, as a miMmum, an electrically driven lubricating oil pump, powered from a reliable DC power sup' ply, should be installed in the lube oli system to operate in parallel with the engine 4
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driven main lube pump. The electric dr!ven prelube pu=p should operate only during the engine cranking cycle or untti satisfactory lube oil pressure is estabitshed in the engine main labe distribution header.
The installation of this prelube pu=p should be c ordinated with the some diesel engines include. a lube oil respective engine manufacturer,
-- ctreulating pump as an intregal part of the lube oil preheating system which is in use while the diesel engine is in the standby mde. In this case an additional prelube oil pu=p may not be needed.
Confirm your c =pliance with the above requirement er provida y$ur justification for not installing an electric prelube oti pump, i _
u N 0.12 periodic testing and test loading of an emergency diesel generate ,
(8.3)
RSp in a n'uclear pcwer plant is a necessary function to demonstrate the operability, capabiltty and availahtitty of the unit on de=end. Periodic testing coupled with good preventive maintenance practices will assure optic:.;:n equip::ent readiness and availability on des:and. This is the desired goal .
To achieve this optimum equfpment readiness status the following ,
requirements should be met: -
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. 1. The equf pment should be tested with a mtnt=un loading of 25 percent of rated load, h) lead or If ght lead operation will cause incomp1'ete combustion of fuel resultfng in the for ation of gu:n and varnish
- deposits on the cylinder walls, intake and exhaust YalVes e pistons D"*D
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and piston rings, etc., and accumulation of unburned fuel in the turbocharger and exhaust system. The consequences of no load or l 1
light load operation are potential equipment failure due to the gum and varnich deposits and fire in the engine exhaust system.
2 Periodic surveillance testing should be performed in accordance with the applicable NRC guidelines (R.g.1.103), and with the recomendations l of the engine manufacturer. Conflicts between any such recomendations and the NRC guidelines, particularly with respect to test, frequency, loading and duration, should be identified and justified,
,_ 3. Preventive maintenance should go beyond the normal routine adjust-
- ments, se. vicing and repair of co=ponents when a malfunction occurs.
Preventive raintenance should encompass investigative testing of components which have a history of repeated malifunctioning and require c5nstatt attention and repair. In such cases consideration
_- should be given 4 replacement of those components with other preducts which have a record of demonstrated reliability, rather than repetitive repair and maintenance of the existing components. Testing of the unit after adjustments or repairs have been made only confir=s that the equipment is operable and does not necessarily mean s that the root cause of the problem has been eliminated or alleviated.
4 ; mci completion of repairs or maintanance and prior to an actual '
start, run, and lead test a final equipment check should be made to assure that all electrical circuits are fu$ctional, i.e., fuses are in
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d place, switches ano' circuit breakers are in their proper position, no loose wires, all test leads have been removed, and all valves are in the proper position to permit a manu.1 start of the equipment. After the unit has been satisfactorily started and load tested, return the unit to ready automatic standby service and under the control of the e
control room operator, Provide a discussion of how the above requirements have been implemented in the emergency diesel generator system design and how they will be considered when the plant is in comercial operation, i.e., by what means will the above require =ents be enforced. -
040.13 The availability en de and of an emergency diesel generator is .- .
(8.3) .
RSP dependent upon, a-eng other things, the proper functioni,ng of its controls and monitoring instrumentation. This equipraent is generally panel mounted an2 in some instances the panels are pounted directly
__- on the diesel ganarator skid. Major diesel engine damage has occurred at so:e operating plants from vibration induced wear en skid ecunted control and cenitoring instrumen'tation. This sensittye instrumentation is not rade to withstand and function accurately for prolonged periods .
under continuous vibrational stresses normally encountered with internal combustion engines. Operation of senstive instrumentation under \
this
environment rapidly deteriorates calibration,. accuracy and control l
f signal output. .
Therefore, except for sensors ar.d other equipment (that cust be directly nounted on the engine or associated piptng, the controls and s.snitoring mm m . .
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instrumentation should be installed on a free standing floor nounted
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panel separate from the engine skids, and located on a vibration free j
floor area or equipped with vibraticn = cunts. )
- f Confim your compliance with the above requirement or provfde justification for noncompliance, ,
040.14 Provide the design characteristics for the diesel engine (engine -
(8.3) l horsepower, number of cylinders, manufacturer, model numberl and any other pertinent information.
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l RESPONSES TO DIESEL GENERATOR QUESTIONS 040.1 RESPONSE (9.5.6)
Each standby diesel generator is equipped with two in-dependent air starting systems. Each air start system l is piped to six of the twelve cylinders of the engine and will start the engine should the other system fail to function.
Each air start system is equipped with the following components that remove contaminants from the air to preclude fouling of the air start valve:
- 1. Compressor Air Inlet Filter
- 2. Compressed Air Cooler
- 3. Air Dryer (Dessicant)
- 4. Air Dryer Automatic Drain Valve
- 5. Air Receiver Drain Valve (Manual)
- 6. Air Start Valve Inlet Air Filter (Equipped with manual blow-down valve) l l
The manual drain and blow-down valves listed above are periodically operated to remove contaminants from the air system.
In addition, the filters, compressors, and dryer are on a preventive maintenance program to ensure the re-liability of the system.
040.2 (9.5.8)- RESPONSE The Diesel Generator Building houses five diesel units in five separate rooms. Each diesel has a dedicated combustion air inlet system which is independent of the diesel room ventilation system. Combustion air is drawn directly from outside the building through an inlet structure equipped with louvered doors, screens, and filters to the engine.
Engine exhaust is piped to the building exterior through an exhaust ventilator.
Each diesel room is provided with an independent vent-ilation system. Temperature controlled motor operated louvers are provided on ventilation air inlet and ex-0 haust openings. Two screens, separated by 90 turns in the inlet path are provided. Exhaust fans discharge through roof ventilators and are sequenced "on" bet-0 ween 75-105 F to control diesel room temperature.
Each engine is equipped with two parallel electrical start circuits. The components of these circuits are housed in three electrical panels two of which are equipped with door seals and no ventilation louvers.
The local engine controls and local generator monitoring instrumentation are housed in the third panel which is not ventilated. Access door seals will be added to this panel.
The diesel building is cleaned on a routine basis.
A sealant has been applied to the diesel generator building floors to preclude the generation of con-crete dust by personnel traffic.
The FNP diesel generator building is located on the Unit 1 side of the plant which is complete except for backfit work. The grounds are landscaped, grassed, and roads are paved. Unit 2 construction is essentially complete; however, unpaved access roads necessary for construction are wetted to limit dust generation by construction traffic.
In addition to the above measures, routinely scheduled preventive maintenance is accomplished on electrical panels (eg includes cleaning of components) and vent-11ation components.
040.3 (9.5.5) RESPONSE:
FNP diesel generators have no mechanical limit on the length of time operated unloaded at rated speed; this
. . l has been reverified with Colt as a result of this l question. However, following extended periods of no load operation, the diesel specifications require load be applied in order to clear the exhaust system of ;
lubricating oil that may have accumulated. The re- i quirements is implemented in our standard operating practices by loading the diesels every fifth start. I This is in response to formal and informal questions '
addressed to Colt concerning oil accumulation in ;
exhaust manifolds.
An emergency start of the diesel engines with off-site power available will cause the engines to operate unloaded until the emergency start signal has been cleared. Should a loss of offsite power occur while in this condition, loads will be auto-matically sequenced onto each operating diesel l
generator.
Alabama Power feels that diesel generator operation i is adequately addressed in Volume IX, Chapter 8.0 of l
our FSAR. No additional amendment is deemed necessary at this time.
040.4 (9.5.4) RESPONSE FNP diesel fuel oil storage and transfer system has been compared to the requirements of ANSI Standard N195 " Fuel Oil Systems for Standby Diesel Generators" and meets its requirements except:
- 1. N195 Paragraph 6.3 requires a duplex fuel oil strainer be provided in the fuel transfer pump suction.
Our design provides a single element strainer in the discharge line of each of two pumps that transfer fuel oil from each engine's supply tank to the day tank.
One pump is sequenced "on" and "off" automatically while the other pump must be started manually in the event of a day tank low-low level alarm. Should this occur, there is at least a one hour's supply of fuel remaining in the day tank.
- 2. N195 Paragraph 7.5 requires a strainer in the supply tank fill line.
No fill line strainer is provided; however filters are installed as discussed in Item 1 above and a duplex filter is installed in the fuel header for each engine.
FNP has experienced no problems with fuel oil quality which is maintained within the requirements of Federal Specification VV-F-800b and ASTM D-975-78 by FNP sur-veillance and procurement requirements as discussed in the response to 040.5 and 040.6 respectively.
. sed on the above, Alabama Power feels that the re-quirements of N195 have been met by the design and operation of our system.
040.5 (9.5.4) RESPONSE: I A sample from each fuel oil storage tank is taken !
every three months and analyzed for water and sediment ;
in accordance with ASTM D-270-65. Before sampling, the contents of each tank is recirculated for a period of at least two hours. In the event that sample analyses do not meet ASTM D-975-78, the contents of the tank is discharged and fuel oil meeting the requirements of Federal Specification VV-F-800b and ASTM D-975-78 is loaded into the tank.
Since our sampling procedure ensures that any sediment is mixed with the fuel oil prior to sampling, the mixing of sediment by tank fill operations should not cause degradation of the fuel oil quality.
In addition, each fuel transfer pump is equipped with a discharge filter and each engine fuel header is equipped with a duplex filter.
040.6 (9.5.4) RESPONSE:
Diesel fuel oil No. 2 is used in the FNP emergency diesels. This fuel oil is procured as a safety re-lated item (QA Review Code A) from Chevron, USA, under blanket P. O. #2101 and must meet Federal Specification VV-F-800b dated April 2, 1975, and ASTM Specification D-975-7d. A statement of conformance certifying com-pliance with the above specifications is required at the time of delivery in lieu of testing the new de-livered oil onsite.
Each diesel fuel oil tank is sampled at least once per 92 days in accordance with ASTM-D270-65 to ensure the oil is within the specifications of Table 1 of ASTM-D975-74 when checked for viscosity, water and sediment.
No problems due to condensation in these tanks have been experienced since they were placed in operation. The diesel generators and diesel fuel oil day tanks are checked by operations personnel once per four hours as part of their routine inspections. Part of this in-spection involves checking the water-in-fuel-oil monitor for each day tank. Operability of the diesel fuel oil transfer system is checked at least once per 31 days as a prerequisite of running each diesel.
040.7 (9.5.6) RESPONSE:
The diesel generator starting air system as described in the response to 040.1 is the results of several modifications intended to eliminate moisture problems encountered in the original systea. This modified system has been in operation for over one year and no problems associated with entrained moisture have occured.
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l However, we have evaluated our present system and i I
determined that it is designed to provide compressed air at a dew point of 64 F at 100 PSA with a 90 F service water inlet to the compressed air cooler and compressor inlet air at saturation. The actual dew point provided by i.9 system will depend on operating space ambient temperiture (maintained by design above a minimum of 40 F - actual operating experience has shown that the temperature does not fall nearly this low), service wacer temperature and inlet air moisture content.
Entrained mositure has not been a ,:r?blem since placing our current system in operation. Therefore, we be-lieve the system is adequate based on our operating !
experience.
l 040.8 (8.3) RESPCNSE:
This paragraph is not applicable to our diesel engines l which are manufactured by Colt Industries.
040.9 !
(0.3) RESPONSE: l All plant operators, assistant plant operators, equipment operators and operations supervisory personnel receive training in the theory of diesel operation, auxiliary systems to support diesel operation, and on-the-job-training in d!esel operating procedures and practices.
Plant operators and operations supervisory per:onnel re-ceive training and periodic retraining on diesel seq-uencing, Surveillance Test Procedures for ensuring diesel generator operability and Technical Specifications dealing with the diesels.
Plant operators, assistant plant operators, and equipment operators receive a " walk through" of plant systems (in-cluding diesel systems) under their cognizance by shift supervision as part of their qualification process.
Additionally, maintenance personnel receive basic in-structions in diesel operations.
Two maintenance supervisory foremen and two plant in- l structors have attended diesel maintenance courses at j the Fairbanks Morse Diesel Training Center. Also, one additional maintenance foreman has over 20 years of '
previous experience in diesel maintenance and operations including one year as a Colt Industries technical rep-resentative.
FNP does not generally dedicate specific operations and maintenance personnel to operate and maintain a parti-cular system or piece of equipment. Personnel recieve applicable training as discussed above and are qualified as discussed in the next paragraph. On each shift, an equipment operator is responsible for the physical con-dition of the diesel and making diesel log entries. Op-erations supervisory personnel routinely review the logs i during each shift and make rootine tours of the diesel. I Maintenance personnel are assigned to perform diesel corrective maintenance on as "as needed" basis and to perform preventative maintenance when scheduled or in-dicated by diesel performance.
All maintenance and operations personnel assigned to FNP are required to meet the minimum qualifications of ANSI N18.1 concerning level of education and experience requirements.
040.10 (9.5.7) RESPONSE:
On the two 2850 KW opposed piston diesels, the vendor manual requires a prelube of not less than two minutes or more than three minutes. FNP procedures require a prelube of no less than 2-1/2 minutes or more than three minutes on the 2850 KW diesels. On the three 4075 KW "V" type diesels, the vendor manual requires a prelube of 10 min-utes duration. FNP procedures require a 10 minute prelube on the 4075 KW diesels.
040.11 (9.5.7) RESPONSE:
This section requires the addition of an electric driven lube oil pump which would start upon receipt of the diesel emergency start signal. The intent of this proposed addition is to get lubrication to the dry bearings within the first few seconds of an emergency start.
Three of the five diesels at FNP are Pielstick engines that have a keep warm oil circulation system that keeps the bearings lubricated at all times.
The other two diesels are opposed piston Colt Industries
- 3800 TD 8-1/8 engines. Due to their design the keep warm circulation system does not prelube the bearings, such design is not feasible on these engines. Experience to date with these engines has shown no deleterious effects due to the operation of the lube oil system as designed.
040.12.1 (8.3) RESPONSE:
Each diesel generator is tested at a load greater than or equal to its continuous rating and operated for greater than or equal 60 minutes in accordance with the frequency specified in applicable NRC Guidelines (R. G. 1.108). These test frequencies are implemented by our Technical Specification surveillance requirements.
040.12.2 1 (8.3) RESPONSE: 1 Diesel engine surveillance testing is performed in accordance with the applicable NRC Guidelines (R.G.1.108).
The diesel engine manufacturer recommends that the engines be exercised once per week for about one hour.
This recomended test frequency would at least quadruple the testing required by R. G. 1.108.
Alabama Power believes that weekly testing would cause undue wear on the engines and not contribute to the engine reliability.
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t Therefore, we will continue to perform diesel sur-veillance testing in accordance with R. G. 1.108 and technical specification requirements.
040.12.3 (8.3) RESPONSE:
The Maintenance Group and other plant groups, through the review of Work Requests, Licensee Event Reports and Surveillance Test Reports, maintain awareness of problems associated with the diesels and other plant equipment.
Repeated problems with any equipment or component immed-iately becomes a subject for a plant investigation to determine if the cause of the problem is related to im-proper maintenance, improper operation, poor design, or manufacturing deficiencies. If the problem is determined to be caused by improper maintenance or operation, proper training or procedure changes are implemented. If the problem is determined to be caused by design or manufacture, a request is made to engineering for an evaluation and/or solution. Task forces have previously been constituted to address problems with tha diesel generators. These task forces are typically composed of personnel from Colt, plant operations and maintenance, design and engineering and offsite management.
040.12.4 (8.3) RESPONSE:
Administrative Procedures, FNP-0-AP-16 (Conduct of Operations - Operations Group) and FNP-0-AP-52 (Equipment i Status Control & Maintenance Authorization), specify for listed systems (diesel included) that shift supervision shall " require a checklist to be performed on the affected system and on portions of other systems located in the areas in which significant maintenance was performed." Based on the activities performed, this checklist includes such items as valve, electrical and instrument alignments, tests, etc.
Furthermore, for the diesels, a second individual will perform an independent verification of the valve and electrical / instrument alignments listed on this checklist.
040.13 (8.3) RESPONSE:
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Each skid mounted diesel engine gauge panel is equipped with vibration mounts. This panel houses the crankcase manometer, starting air, lube oil, fuel oil, service water and jacket coolant pressure gauges, jacket coolant and lube oil temperature instruments, engine tachometer and pyrometer.
The generator control and monitoring instrumentation is housed in the local control panel which is mounted off skid.
The manufacturer has stated that skid mounted control and instrumentation equipment is not subject to mis- )
operating due to engine vibration and the equipment l that is sensitive to vibration is mounted in remote panels. In addition no vibration induced problems with engine mounted components have been experienced on farley Unit 1 diesel generators.
In view of the above, vibration should not effect performance of diesel control and instrumentation equipment.
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040.14 '
(8.3) IC & 2C 1A, 1B & 28 Manufacturer Fairbanks Morse Colt-Pielstiek Model 3800 TD 8-1/8 PC - 2V Type of Engine In line Opposed Piston V Supercharged by Supercharged by Exhaust Driven Centrifugal Exhaust Driven Centrifugal Compressor Compressor Engine-Driven Scavenging Air Blower Size of Engine Cylinder 12 12 Bore, inch 8-1/8 15.75 Stroke, inch 10 18.11 Rated Speed, RPM 900 514 i Piston Speed, ft. P. M. 1500 1550 bhp @ 2850 KW bhp (SeaLevel) 3950 (Sea Level) 6000 Unit Rating, XW Continuous (8,760 hrs /yr) 2850 4075 Extended (2,000 hrs /yr) 3100 4353 Overload ( 300 hrs /yr) 3250 4474 Overload (30 Minutes in 4
24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period) 3500 4881 7?
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