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Category:CORRESPONDENCE-LETTERS
MONTHYEARL-99-035, Forwards non-proprietary & Proprietary Versions of Farley Units 1 & 2 LBB Calculation Results Due to SG Replacement & SG Snubber Elimination Programs, Used to Support SG Replacement Project.Proprietary Encl Withheld1999-10-18018 October 1999 Forwards non-proprietary & Proprietary Versions of Farley Units 1 & 2 LBB Calculation Results Due to SG Replacement & SG Snubber Elimination Programs, Used to Support SG Replacement Project.Proprietary Encl Withheld ML20217G0801999-10-0707 October 1999 Informs That on 990930,staff Conducted mid-cycle PPR of Farley & Did Not Identify Any Areas in Which Performance Warranted More than Core Insp Program.Nrc Will Conduct Regional Insps Associated with SG Removal & Installation ML20217P0661999-10-0606 October 1999 Requests Withholding of Proprietary Rept NSD-SAE-ESI-99-389, Farley Units 1 & 2 LBB Calculation Results Due to SG Replacement & SG Snubber Elimination Programs ML20217B1891999-10-0404 October 1999 Submits Clarification Re Development of Basis for Determining Limiting Internal Pressure Loads Re Review of NRC SE for Cycle 16 Extension Request.Util Intends to Use Guidelines When Evaluating SG Tube Structural Integrity ML20212J8391999-09-30030 September 1999 Forwards RAI Re Request for Amends to Ts.Addl Info Needed to Complete Review to Verify That Proposed TS Are Consistent with & Validate Design Basis Analysis.Request Discussed with H Mahan on 990930.Info Needed within 10 Days of This Ltr ML20212J8801999-09-30030 September 1999 Discusses GL 98-01,suppl 1, Y2K Readiness of Computer Sys at Npps. Util 980731,990607 & 03 Ltrs Provided Requested Info in Subj Gl.Nrc Considers Subj GL to Be Closed for Unit 1 L-99-032, Responds to NRC Re Adequacy of Kaowool Fire Retardant Fire Barriers in Use at Jfnp,Units 1 & 21999-09-23023 September 1999 Responds to NRC Re Adequacy of Kaowool Fire Retardant Fire Barriers in Use at Jfnp,Units 1 & 2 L-99-034, Forwards Comments on Draft Current Tech Specs Discussion of Change Tables for Jm Farley Nuclear Plant.Units 1 & 21999-09-23023 September 1999 Forwards Comments on Draft Current Tech Specs Discussion of Change Tables for Jm Farley Nuclear Plant.Units 1 & 2 ML20212F8861999-09-23023 September 1999 Forwards Revised Relief Request Number 32 for NRC Approval. Approval Requested by 991231 to Support Activities to Be Performed During Unit 1 Refueling Outage Scheduled for Spring of 2000 ML20212E7031999-09-23023 September 1999 Responds to GL 98-01, Year 2000 Readiness of Computer Sys at Npps. Util Requested to Submit Plans & Schedules for Resolving Y2K-related Issues ML20212F1111999-09-21021 September 1999 Discusses Closeout of GL 97-06, Degradation of Steam Generator Internals ML20212C2351999-09-16016 September 1999 Submits Corrected Info Concerning Snoc Response to NRC GL 99-02, Lab Testing of Nuclear-Grade Activated Charcoal ML20212D0101999-09-15015 September 1999 Informs That Submittal of clean-typed Copy of ITS & ITS Bases Will Be Delayed.Delay Due to Need for Resolution of Two Issues Raised by NRC staff.Clean-typed Copy of ITS Will Be Submitted within 4 Wks Following Resolution of Issues ML20212C4641999-09-13013 September 1999 Forwards Info Requested in Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Exams L-99-031, Informs NRC That Review of MOV Testing Frequency & Changes Made to Frequency of MOV Testing Has Been Completed1999-09-13013 September 1999 Informs NRC That Review of MOV Testing Frequency & Changes Made to Frequency of MOV Testing Has Been Completed ML20212C8041999-09-10010 September 1999 Responds to to D Rathbun Requesting Review of J Sherman Re Y2K Compliance.Latest NRC Status Rept on Y2K Activities Encl ML20212D4581999-09-10010 September 1999 Responds to to D Rathbun,Requesting Review of J Sherman Expressing Concerns That Plant & Other Nuclear Plants Not Yet Y2K Compliant ML20212A6951999-09-0909 September 1999 Requests That Licensees Affected by Kaowool Fire Barriers Take Issue on Voluntary Initiative & Propose Approach for Resolving Subj Issues.Staff Plans to Meet with Licensees to Discuss Listed Topics ML20212A8341999-09-0909 September 1999 Requests That Licensees Affected by Kaowool Fire Barriers Take Issue on Voluntary Initiative & Propose Approach for Resolving Subj Issues.Staff Plans to Meet with Licensees to Discuss Listed Topics ML20211N8041999-09-0808 September 1999 Informs That on 990930 NRC Issued GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design-Basis Accident Condition, to Holders of Nuclear Plant Operating Licenses ML20211N4301999-09-0808 September 1999 Discusses Proposed Meeting to Discuss Kaowool Fire Barriers. Staff Requesting That Affected Licensees Take Issue on Voluntary Initative & Propose Approach for Resolving Issues ML20212C0071999-09-0202 September 1999 Forwards Insp Repts 50-348/99-05 & 50-364/99-05 on 990627- 0807.No Violations Noted.Licensee Conduct of Activities at Farley Plant Facilities Generally Characterized by safety-conscious Operations & Sound Engineering ML20211Q4801999-09-0101 September 1999 Informs That on 990812-13,Region II Hosted Training Managers Conference on Recent Changes to Operator Licensing Program. List of Attendees,Copy of Slide Presentations & List of Questions Received from Participants Encl ML20211K2131999-08-31031 August 1999 Informs That Snoc Has Conducted Review of Reactor Vessel Integrity Database,Version 2 (RVID2) & Conclude That Latest Data Submitted for Farley Units Has Not Been Incorporated Into RVID2 ML20211K4101999-08-31031 August 1999 Resubmits Relief Requests Q1P16-RR-V-5 & Q2P16-RR-V-5 That Seek to Group V661 Valves from Each Unit Into Sample Disassembly & Insp Group,Per 990525 Telcon with NRC L-99-030, Forwards SNC Review Comments on Draft SE & marked-up Copy of Draft SE Incorporating SNC Comments Re Proposed Conversion to ITS1999-08-30030 August 1999 Forwards SNC Review Comments on Draft SE & marked-up Copy of Draft SE Incorporating SNC Comments Re Proposed Conversion to ITS ML20211G6851999-08-26026 August 1999 Informs That During Insp,Technical Issues Associated with Design,Installation & fire-resistive Performance of Kaowool Raceway fire-barriers Installed at Farley Nuclear Plant Were Identified L-99-029, Forwards Revised Response to Chapter 3.1 RAI Requested in 990726 Conference Call,Rai Response Related to Beyond Scope Issue for Chapter 3.5 Requested by Conference Call on 990805 & RAI Response to Chapter 3.8 Requested on 990615 & 07271999-08-19019 August 1999 Forwards Revised Response to Chapter 3.1 RAI Requested in 990726 Conference Call,Rai Response Related to Beyond Scope Issue for Chapter 3.5 Requested by Conference Call on 990805 & RAI Response to Chapter 3.8 Requested on 990615 & 0727 ML20211B9431999-08-17017 August 1999 Forwards Fitness for Duty Performance Data for six-month Reporting Period 990101-990630,IAW 10CFR26.71(d).Rept Covers Employees at Jm Farley Nuclear Plant & Southern Nuclear Corporate Headquarters ML20211B9211999-08-17017 August 1999 Responds to NRC Re Violations Noted in Insp Rept 50-348/99-09 & 50-364/99-09.Corrective Actions:Security Response Plan Was Revised to Address Vulnerabilities Identified During NRC Insp ML20210R5101999-08-12012 August 1999 Forwards Revised Page 6 to 990430 LAR to Operate Farley Nuclear Plant,Unit 1,for Cycle 16 Only,Based on risk- Informed Approach for Evaluation of SG Tube Structural Integrity,As Result of Staff Comments ML20212C8141999-08-0909 August 1999 Forwards Correspondence Received from Jm Sherman.Requests Review of Info Re Established Policies & Procedures ML20210T2021999-08-0606 August 1999 Forwards Draft SE Accepting Licensee Proposed Conversion of Plant,Units 1 & 2 Current TSs to Its.Its Based on Listed Documents ML20210Q4641999-08-0505 August 1999 Informs That NRC Plans to Administer Gfes of Written Operator Licensing Exam on 991006.Authorized Representative of Facility Must Submit Ltr to La Reyes,As Listed,With List of Individuals to Take exam,30 Days Before Exam Date ML20210J8341999-07-30030 July 1999 Forwards Second Request for Addl Info Re Util 990430 Amend Request to Allow Util to Operate Unit 1,for Cycle 16 Based on risk-informed Probability of SG Tube Rupture & Nominal accident-induced primary-to-second Leakage ML20210G4901999-07-30030 July 1999 Responds to GL 99-02, Laboratory Testing of Nuclear-Grade Activated Charcoal, Issued 990603.Ltr Contains NRC License Commitment to Utilize ASTM D3803-1989 with Efficiency Acceptance Criteria Utilizing Safety Factor of 2 L-99-028, Responds to NRC 990730 RAI Re 990423 OL Change Request to Allow for Risk Informed Approach for Evaluation of SG Tube Structural Integrity as Described by NEI 97-06, SG Program Guidelines1999-07-30030 July 1999 Responds to NRC 990730 RAI Re 990423 OL Change Request to Allow for Risk Informed Approach for Evaluation of SG Tube Structural Integrity as Described by NEI 97-06, SG Program Guidelines L-99-027, Addresses Clarifications to Selected Responses to Chapter 3.8 RAI Requested in NRC Conference Call on 990624, Resolution of Open Issue Related to Containment Purge in Chapter 3.6 & Response Related to Chapter 3.51999-07-27027 July 1999 Addresses Clarifications to Selected Responses to Chapter 3.8 RAI Requested in NRC Conference Call on 990624, Resolution of Open Issue Related to Containment Purge in Chapter 3.6 & Response Related to Chapter 3.5 ML20210G8181999-07-26026 July 1999 Forwards Insp Repts 50-348/99-04 & 50-364/99-04 on 990516- 0626.One Violation Identified & Being Treated as Noncited Violation IR 05000348/19990091999-07-23023 July 1999 Discusses Insp Repts 50-348/99-09 & 50-364/99-09 on 990308- 10 & Forwards Notice of Violation Re Failure to Intercept Adversary During Drills,Contrary to 10CFR73 & Physical Security Plan Requirements ML20210E4071999-07-22022 July 1999 Responds to NRC 990702 RAI Re Change Request to Allow for Risk Informed Approach for Evaluation of SG Tube Structural Integrity as Described in NEI 97-06, SG Program Guidelines L-99-026, Forwards Response to NRC 990702 RAI Re SG Replacement Related TS Change Request Submitted 981201.Ltr Contains No New Commitments1999-07-19019 July 1999 Forwards Response to NRC 990702 RAI Re SG Replacement Related TS Change Request Submitted 981201.Ltr Contains No New Commitments L-99-264, Responds to NRC 990603 Administrative Ltr 99-02, Operating Licensing Action Estimates, for Fy 2000 & 20011999-07-13013 July 1999 Responds to NRC 990603 Administrative Ltr 99-02, Operating Licensing Action Estimates, for Fy 2000 & 2001 ML20209H4721999-07-13013 July 1999 Responds to NRC 990603 Administrative Ltr 99-02, Operating Licensing Action Estimates, for Fy 2000 & 2001 ML20196J6191999-07-0202 July 1999 Forwards Final Dam Audit Rept of 981008 of Category 1 Cooling Water Storage Pond Dam.Requests Response within 120 Days of Date of Ltr 05000364/LER-1999-001, Forwards LER 99-001-00 Re Reactor Trip Due to Loss of Condenser Vacuum Steam Dump Drain Line Failure.Commitments Made by Licensee,Listed1999-07-0202 July 1999 Forwards LER 99-001-00 Re Reactor Trip Due to Loss of Condenser Vacuum Steam Dump Drain Line Failure.Commitments Made by Licensee,Listed ML20196J7471999-07-0202 July 1999 Forwards RAI Re Cycle 16 Extension Request.Response Requested within 30 Days of Date of Ltr ML20196J5781999-07-0202 July 1999 Forwards RAI Re 981201 & s Requesting Amend to TS Associated with Replacing Existing Westinghouse Model 51 SG with Westinghouse Model 54F Generators.Respond within 30 Days of Ltr Date ML20196J6571999-07-0202 July 1999 Discusses Closure to TAC MA0543 & MA0544 Re GL 92-01 Rev 1, Suppl 1,RV Structural Integrity.Nrc Has Revised Rvid & Releasing It as Rvid,Version 2 as Result of Review of Responses ML20196J3591999-06-30030 June 1999 Forwards SE of TR WCAP-14750, RCS Flow Verification Using Elbow Taps at Westinghouse 3-Loop Pwrs 1999-09-09
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARL-99-035, Forwards non-proprietary & Proprietary Versions of Farley Units 1 & 2 LBB Calculation Results Due to SG Replacement & SG Snubber Elimination Programs, Used to Support SG Replacement Project.Proprietary Encl Withheld1999-10-18018 October 1999 Forwards non-proprietary & Proprietary Versions of Farley Units 1 & 2 LBB Calculation Results Due to SG Replacement & SG Snubber Elimination Programs, Used to Support SG Replacement Project.Proprietary Encl Withheld ML20217P0661999-10-0606 October 1999 Requests Withholding of Proprietary Rept NSD-SAE-ESI-99-389, Farley Units 1 & 2 LBB Calculation Results Due to SG Replacement & SG Snubber Elimination Programs ML20217B1891999-10-0404 October 1999 Submits Clarification Re Development of Basis for Determining Limiting Internal Pressure Loads Re Review of NRC SE for Cycle 16 Extension Request.Util Intends to Use Guidelines When Evaluating SG Tube Structural Integrity L-99-034, Forwards Comments on Draft Current Tech Specs Discussion of Change Tables for Jm Farley Nuclear Plant.Units 1 & 21999-09-23023 September 1999 Forwards Comments on Draft Current Tech Specs Discussion of Change Tables for Jm Farley Nuclear Plant.Units 1 & 2 L-99-032, Responds to NRC Re Adequacy of Kaowool Fire Retardant Fire Barriers in Use at Jfnp,Units 1 & 21999-09-23023 September 1999 Responds to NRC Re Adequacy of Kaowool Fire Retardant Fire Barriers in Use at Jfnp,Units 1 & 2 ML20212F8861999-09-23023 September 1999 Forwards Revised Relief Request Number 32 for NRC Approval. Approval Requested by 991231 to Support Activities to Be Performed During Unit 1 Refueling Outage Scheduled for Spring of 2000 ML20212C2351999-09-16016 September 1999 Submits Corrected Info Concerning Snoc Response to NRC GL 99-02, Lab Testing of Nuclear-Grade Activated Charcoal ML20212D0101999-09-15015 September 1999 Informs That Submittal of clean-typed Copy of ITS & ITS Bases Will Be Delayed.Delay Due to Need for Resolution of Two Issues Raised by NRC staff.Clean-typed Copy of ITS Will Be Submitted within 4 Wks Following Resolution of Issues L-99-031, Informs NRC That Review of MOV Testing Frequency & Changes Made to Frequency of MOV Testing Has Been Completed1999-09-13013 September 1999 Informs NRC That Review of MOV Testing Frequency & Changes Made to Frequency of MOV Testing Has Been Completed ML20212C4641999-09-13013 September 1999 Forwards Info Requested in Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Exams ML20211K2131999-08-31031 August 1999 Informs That Snoc Has Conducted Review of Reactor Vessel Integrity Database,Version 2 (RVID2) & Conclude That Latest Data Submitted for Farley Units Has Not Been Incorporated Into RVID2 ML20211K4101999-08-31031 August 1999 Resubmits Relief Requests Q1P16-RR-V-5 & Q2P16-RR-V-5 That Seek to Group V661 Valves from Each Unit Into Sample Disassembly & Insp Group,Per 990525 Telcon with NRC L-99-030, Forwards SNC Review Comments on Draft SE & marked-up Copy of Draft SE Incorporating SNC Comments Re Proposed Conversion to ITS1999-08-30030 August 1999 Forwards SNC Review Comments on Draft SE & marked-up Copy of Draft SE Incorporating SNC Comments Re Proposed Conversion to ITS L-99-029, Forwards Revised Response to Chapter 3.1 RAI Requested in 990726 Conference Call,Rai Response Related to Beyond Scope Issue for Chapter 3.5 Requested by Conference Call on 990805 & RAI Response to Chapter 3.8 Requested on 990615 & 07271999-08-19019 August 1999 Forwards Revised Response to Chapter 3.1 RAI Requested in 990726 Conference Call,Rai Response Related to Beyond Scope Issue for Chapter 3.5 Requested by Conference Call on 990805 & RAI Response to Chapter 3.8 Requested on 990615 & 0727 ML20211B9431999-08-17017 August 1999 Forwards Fitness for Duty Performance Data for six-month Reporting Period 990101-990630,IAW 10CFR26.71(d).Rept Covers Employees at Jm Farley Nuclear Plant & Southern Nuclear Corporate Headquarters ML20211B9211999-08-17017 August 1999 Responds to NRC Re Violations Noted in Insp Rept 50-348/99-09 & 50-364/99-09.Corrective Actions:Security Response Plan Was Revised to Address Vulnerabilities Identified During NRC Insp ML20210R5101999-08-12012 August 1999 Forwards Revised Page 6 to 990430 LAR to Operate Farley Nuclear Plant,Unit 1,for Cycle 16 Only,Based on risk- Informed Approach for Evaluation of SG Tube Structural Integrity,As Result of Staff Comments ML20212C8141999-08-0909 August 1999 Forwards Correspondence Received from Jm Sherman.Requests Review of Info Re Established Policies & Procedures ML20210G4901999-07-30030 July 1999 Responds to GL 99-02, Laboratory Testing of Nuclear-Grade Activated Charcoal, Issued 990603.Ltr Contains NRC License Commitment to Utilize ASTM D3803-1989 with Efficiency Acceptance Criteria Utilizing Safety Factor of 2 L-99-028, Responds to NRC 990730 RAI Re 990423 OL Change Request to Allow for Risk Informed Approach for Evaluation of SG Tube Structural Integrity as Described by NEI 97-06, SG Program Guidelines1999-07-30030 July 1999 Responds to NRC 990730 RAI Re 990423 OL Change Request to Allow for Risk Informed Approach for Evaluation of SG Tube Structural Integrity as Described by NEI 97-06, SG Program Guidelines L-99-027, Addresses Clarifications to Selected Responses to Chapter 3.8 RAI Requested in NRC Conference Call on 990624, Resolution of Open Issue Related to Containment Purge in Chapter 3.6 & Response Related to Chapter 3.51999-07-27027 July 1999 Addresses Clarifications to Selected Responses to Chapter 3.8 RAI Requested in NRC Conference Call on 990624, Resolution of Open Issue Related to Containment Purge in Chapter 3.6 & Response Related to Chapter 3.5 ML20210E4071999-07-22022 July 1999 Responds to NRC 990702 RAI Re Change Request to Allow for Risk Informed Approach for Evaluation of SG Tube Structural Integrity as Described in NEI 97-06, SG Program Guidelines L-99-026, Forwards Response to NRC 990702 RAI Re SG Replacement Related TS Change Request Submitted 981201.Ltr Contains No New Commitments1999-07-19019 July 1999 Forwards Response to NRC 990702 RAI Re SG Replacement Related TS Change Request Submitted 981201.Ltr Contains No New Commitments L-99-264, Responds to NRC 990603 Administrative Ltr 99-02, Operating Licensing Action Estimates, for Fy 2000 & 20011999-07-13013 July 1999 Responds to NRC 990603 Administrative Ltr 99-02, Operating Licensing Action Estimates, for Fy 2000 & 2001 ML20209H4721999-07-13013 July 1999 Responds to NRC 990603 Administrative Ltr 99-02, Operating Licensing Action Estimates, for Fy 2000 & 2001 05000364/LER-1999-001, Forwards LER 99-001-00 Re Reactor Trip Due to Loss of Condenser Vacuum Steam Dump Drain Line Failure.Commitments Made by Licensee,Listed1999-07-0202 July 1999 Forwards LER 99-001-00 Re Reactor Trip Due to Loss of Condenser Vacuum Steam Dump Drain Line Failure.Commitments Made by Licensee,Listed L-99-024, Responds to NRC RAI Re Conversion to ITS for Chapters 3.4, 3.5,3.6,3.7,3.9 & 5.0,per 990419-20 Meetings with NRC1999-06-30030 June 1999 Responds to NRC RAI Re Conversion to ITS for Chapters 3.4, 3.5,3.6,3.7,3.9 & 5.0,per 990419-20 Meetings with NRC L-99-025, Forwards Rev 2 to Jfnp Security plan,FNP-0-M-99,IAW 10CFR50.4(b)(4).Attachment 1 Contains Summary of Changes & Amended Security Plan Pages.Encl Withheld from Public Disclosure Per 10CFR73.211999-06-30030 June 1999 Forwards Rev 2 to Jfnp Security plan,FNP-0-M-99,IAW 10CFR50.4(b)(4).Attachment 1 Contains Summary of Changes & Amended Security Plan Pages.Encl Withheld from Public Disclosure Per 10CFR73.21 ML20196J8631999-06-30030 June 1999 Submits Correction to Errors Contained in to NRC Re TS Changes Re Control Room,Penetration Room & Containment Purge Filtration Systems & Radiation Monitoring Instrumentation.Errors Do Not Require Rev of SA L-99-249, Submits Correction to Errors Contained in to NRC Re TS Changes Re Control Room,Penetration Room & Containment Purge Filtration Systems & Radiation Monitoring Instrumentation.Errors Do Not Require Rev of SA1999-06-30030 June 1999 Submits Correction to Errors Contained in to NRC Re TS Changes Re Control Room,Penetration Room & Containment Purge Filtration Systems & Radiation Monitoring Instrumentation.Errors Do Not Require Rev of SA L-99-224, Submits Rev to Unit 2 SG Tube voltage-based Repair Criteria Data Rept.Ltr Contains No Commitments1999-06-0707 June 1999 Submits Rev to Unit 2 SG Tube voltage-based Repair Criteria Data Rept.Ltr Contains No Commitments ML20195F1731999-06-0707 June 1999 Forwards Proprietary & non-proprietary Responses to NRC RAIs Re W TR WCAP-14750, RCS Flow Verification Using Elbow Taps at W 3-Loop Pwrs. W Proprietary Notice,Affidavit & Copyright Notice,Encl.Proprietary Info Withheld L-99-217, Forwards Proprietary & non-proprietary Responses to NRC RAIs Re W TR WCAP-14750, RCS Flow Verification Using Elbow Taps at W 3-Loop Pwrs. W Proprietary Notice,Affidavit & Copyright Notice,Encl.Proprietary Info Withheld1999-06-0707 June 1999 Forwards Proprietary & non-proprietary Responses to NRC RAIs Re W TR WCAP-14750, RCS Flow Verification Using Elbow Taps at W 3-Loop Pwrs. W Proprietary Notice,Affidavit & Copyright Notice,Encl.Proprietary Info Withheld L-99-225, Responds to GL 98-01, Yr 2000 Readiness of Computer Sys at Nuclear Power Plants1999-06-0707 June 1999 Responds to GL 98-01, Yr 2000 Readiness of Computer Sys at Nuclear Power Plants ML20195F0621999-06-0707 June 1999 Submits Rev to Unit 2 SG Tube voltage-based Repair Criteria Data Rept.Ltr Contains No Commitments ML20195E9581999-06-0707 June 1999 Responds to GL 98-01, Yr 2000 Readiness of Computer Sys at Nuclear Power Plants ML20195C6941999-05-28028 May 1999 Forwards Response to NRC RAI Re GL 96-05 for Farley Nuclear Plant.Farley Is Committing to Implement Phase 3 of JOG Program L-99-021, Forwards Response to RAI Re Conversion to ITSs for Chapter 3.3.Attachment II Includes Proposed Revs to Previously Submitted LAR Re Rais,Grouped by RAI number.Clean-typed Copies of Affected ITS Pages Not Included1999-05-28028 May 1999 Forwards Response to RAI Re Conversion to ITSs for Chapter 3.3.Attachment II Includes Proposed Revs to Previously Submitted LAR Re Rais,Grouped by RAI number.Clean-typed Copies of Affected ITS Pages Not Included L-99-203, Forwards Response to NRC RAI Re GL 96-05 for Farley Nuclear Plant.Farley Is Committing to Implement Phase 3 of JOG Program1999-05-28028 May 1999 Forwards Response to NRC RAI Re GL 96-05 for Farley Nuclear Plant.Farley Is Committing to Implement Phase 3 of JOG Program ML20195F2101999-05-24024 May 1999 Requests That Farley Nuclear Plant Proprietary Responses to NRC RAI Re W WCAP-14750, RCS Flow Verification Using Elbow Taps at W 3-Loop Pwrs, Be Withheld from Public Disclosure Per 10CFR2.790 L-99-180, Forwards Responses to NRC RAI Questions for Chapter 3.8 of Ts.Proposed Revs to TS Previously Submitted with LAR Related to RAI1999-04-30030 April 1999 Forwards Responses to NRC RAI Questions for Chapter 3.8 of Ts.Proposed Revs to TS Previously Submitted with LAR Related to RAI ML20206F4321999-04-30030 April 1999 Forwards Responses to NRC RAI Questions for Chapter 3.8 of Ts.Proposed Revs to TS Previously Submitted with LAR Related to RAI L-99-017, Forwards Responses to NRC RAI Questions for Chapters 3.1, 3.2,3.5,3.7 & 3.9 of Ts.Attached Pages Include Proposed Revs Previously Submitted LAR to Rais,Grouped by Chapters & RAI Numbers1999-04-30030 April 1999 Forwards Responses to NRC RAI Questions for Chapters 3.1, 3.2,3.5,3.7 & 3.9 of Ts.Attached Pages Include Proposed Revs Previously Submitted LAR to Rais,Grouped by Chapters & RAI Numbers ML20206C8021999-04-26026 April 1999 Forwards 1998 Annual Rept, for Alabama Power Co.Encls Contain Financial Statements for 1998,unaudited Financial Statements for Quarter Ending 990331 & Cash Flow Projections for 990101-991231 05000348/LER-1998-007, Forwards SG-99-04-001, Farley-1:Final Cycle 16 Freespan ODSCC Operational Assessment, as Committed to in Licensee & LER 98-007-00.Util Is Revising Plant Administrative SG Operating Leakage Requirements as Listed1999-04-23023 April 1999 Forwards SG-99-04-001, Farley-1:Final Cycle 16 Freespan ODSCC Operational Assessment, as Committed to in Licensee & LER 98-007-00.Util Is Revising Plant Administrative SG Operating Leakage Requirements as Listed L-99-015, Forwards Rev 1 to Jfnp Security plan,FNP-O-M-99,resulting from Implementation of Biometrics Sys.Changes Incorporate Changes Previously Submitted to NRC as Rev 28 by Licensee .Encl Withheld,Per 10CFR73.211999-04-21021 April 1999 Forwards Rev 1 to Jfnp Security plan,FNP-O-M-99,resulting from Implementation of Biometrics Sys.Changes Incorporate Changes Previously Submitted to NRC as Rev 28 by Licensee .Encl Withheld,Per 10CFR73.21 ML20206B4391999-04-21021 April 1999 Forwards Corrected ITS Markup Pages to Replace Pages in 981201 License Amend Requests for SG Replacement L-99-172, Forwards FNP Annual Radioactive Effluent Release Rept for 1998, IAW TSs Sections 6.9.1.8 & 6.9.1.9.Changes to ODCM Revs 16,17 & 18 Are Encl,Iaw TS Section 6.14.21999-04-21021 April 1999 Forwards FNP Annual Radioactive Effluent Release Rept for 1998, IAW TSs Sections 6.9.1.8 & 6.9.1.9.Changes to ODCM Revs 16,17 & 18 Are Encl,Iaw TS Section 6.14.2 ML20205S9501999-04-21021 April 1999 Forwards FNP Annual Radioactive Effluent Release Rept for 1998, IAW TSs Sections 6.9.1.8 & 6.9.1.9.Changes to ODCM Revs 16,17 & 18 Are Encl,Iaw TS Section 6.14.2 ML20205R0431999-04-13013 April 1999 Forwards Correction to 960212 GL 95-07 180 Day Response. Level 3 Evaluation for Pressure Locking Utilized Analytical Models.Encl Page Has Been Amended to Correct Error 1999-09-23
[Table view] Category:UTILITY TO NRC
MONTHYEARML20064A7131990-09-17017 September 1990 Advises That Due to Reassignment,Jj Clark No Longer Needs to Maintain Senior Reactor Operator Licenses ML20059J2811990-09-14014 September 1990 Forwards List of Key Radiation Monitors Which Will Be Used as Inputs to Top Level Radioactivity Status Bar Re Spds.List Identifies Monitors Which Would Provide Concise & Meaningful Info About Radioactivity During Accidents ML20065D5961990-09-13013 September 1990 Responds to Violations Noted in Insp Repts 50-348/90-19 & 50-364/90-19.Response Withheld ML20059J1661990-09-13013 September 1990 Forwards Monthly Operating Rept for Aug 1990 for Jm Farley Nuclear Plant & Rev 10 to ODCM ML20059L0751990-09-12012 September 1990 Forwards Revised Pages to Rev 3 to, Second 10-Yr Interval Inservice Insp Program for ASME Code Class 1,2 & 3 Components ML20059J2911990-09-12012 September 1990 Forwards Operator Licensing Natl Exam Schedules for FY91 Through FY94,per Generic Ltr 90-07.Requalification Schedules & Estimated Number of Candidates Expected to Participate in Generic Fundamental Exam,Also Encl ML20064A7111990-09-12012 September 1990 Forwards Rev 1 to Relief Request RR-1, Second 10-Yr Interval Inservice Insp Program for ASME Code Class 1,2 & 3 Components ML20059J2891990-09-12012 September 1990 Confirms Rescheduling of Response to Fitness for Duty Program Notice of Violation 90-18-02,per 900907 Telcon ML20065D6621990-09-12012 September 1990 Forwards NPDES Permit AL0024619 Effective 900901.Limits for Temp & Residual Chlorine Appealed & Stayed ML20064A3431990-08-28028 August 1990 Forwards Corrected Insertion Instructions to Rev 8 to Updated FSAR for Jm Farley Nuclear Plant ML20059D4711990-08-22022 August 1990 Forwards Fitness for Duty Performance Data for Jan-June 1990 ML20059B5101990-08-22022 August 1990 Forwards Semiannual Radioactive Effluent Release Rept for Jan-June 1990.No Changes to Process Control Program for First Semiannual Period of 1990 Exists ML20056B2751990-08-20020 August 1990 Forwards Relief Requests from Second 10-yr Interval Inservice Testing Program for Class 1,2 & 3 Pumps & Valves. Request Incorporates Commitments in 891222 Response to Notice of Violation ML20056B2741990-08-20020 August 1990 Forwards Rev 2 to Unit Inservice Testing Program,For Review & Approval.Rev Incorporates Commitments Addressed in Util 891222 Response to Notice of Violation & Other Editorial & Technical Changes ML20058Q1481990-08-15015 August 1990 Forwards Rev 3 to FNP-1-M-043, Jm Farley Nuclear Plant Unit 1 Second 10-Yr Inservice Insp Program,Asme Code Class 1,2 & 3 Components ML20058P6201990-08-15015 August 1990 Forwards Rev 1 to FNP-2-M-068, Ten-Yr Inservice Insp Program for ASME Code Class 1,2 & 3 Components, Per 891207 & 900412 Responses to NRC Request for Addl Info ML20055G7701990-07-18018 July 1990 Updates 900713 Response to NRC Bulletin 90-001, Loss of Fill-Oil in Transmitters Mfg by Rosemount ML20055F7411990-07-11011 July 1990 Forwards Monthly Operating Rept for June 1990 & Corrected Monthly Operating Repts for Nov 1989 Through May 1990.Repts Revised to Correct Typo on Value of Cumulative Number of Hours Reactor Critical ML20055F3781990-07-10010 July 1990 Submits Final Response to Generic Ltr 83-28,Items 4.2.3 & 4.2.4.Util Position That Procedures Currently Utilized by Plant Constitute Acceptable Ongoing Life Testing Program for Reactor Trip Breakers & Components ML20055D4861990-07-0202 July 1990 Requests Authorization to Use Encl ASME Boiler & Pressure Vessel Code Case N-395 Re Laser Welding for Sleeving Process Described by Oct 1990,per 10CFR50.55a,footnote 6 ML20055D1001990-06-26026 June 1990 Responds to Violations Noted in Insp Repts 50-348/90-12 & 50-364/90-12 on 900411-0510.Corrective Actions:Electrolyte Level Raised in Lights Identified by Inspector to Have Low Electrolyte Level ML20044A6191990-06-26026 June 1990 Suppls 900530 Ltr Containing Results of SPDS Audit,Per Suppl 1 to NUREG-0737.One SPDS Console,Located in Control Room,Will Be Modified So That Only SPDS Info Can Be Displayed by Monitor.Console Will Be Reconfigured ML20043G4741990-06-11011 June 1990 Submits Addl Info Re 900219 Worker Respiratory Protection Apparatus Exemption Rev Request.Proposed Exemption Rev Involves Features Located Entirely within Restricted Area as Defined in 10CFR20 ML20043C1851990-05-29029 May 1990 Forwards Proposed Schedules for Submission & Requested Approval of Licensing Items ML20043B5941990-05-25025 May 1990 Provides Rept of Unsatisfactory Performance Testing,Per 10CFR26,App A.Error Caused by Olympus Analyzer Which Allowed Same Barcode to Be Assigned to Two Different Samples. Smithkline Taken Action to Prevent Recurrence of Scan Error ML20042G7461990-05-10010 May 1990 Certifies That Plant Licensed Operator Requalification Program Accredited & Based Upon Sys Approach to Training,Per Generic Ltr 87-07.Program in Effect Since 890109 ML20042F0831990-05-0101 May 1990 Forwards Rev 18 to Security Plan.Rev Withheld ML20042G3081990-04-25025 April 1990 Forwards Alabama Power Co Annual Rept 1989, Unaudited Financial Statements for Quarter Ending 900331 & Cash Flow Projections for 1990 ML20042E4121990-04-12012 April 1990 Provides Addl Info Re Review of Second 10-yr Inservice Insp Program,Per NRC 890803 Request.Relief Request RR-30 Requested Reduced Holding Time for Hydrostatically Testing Steam Generator Secondary Side ML20012E9571990-03-27027 March 1990 Forwards Annual Diesel Generator Reliability Data Rept,Per Tech Spec 6.9.1.12.Rept Provides Number of Tests (Valid or Invalid),Number of Failures for Each Diesel Generator at Plant for 1989 & Info Identified in Reg Guide 1.108 ML20012D9661990-03-22022 March 1990 Forwards Annual ECCS Evaluation Model Changes Rept,Per Revised 10CFR50.46.Info Includes Effect of ECCS Evaluation Model Mods on Peak Cladding Temp Results & Summary of Plant Change Safety Evaluations ML20012D8901990-03-20020 March 1990 Clarifies 891130 Response to Generic Ltr 83-28,Item 2.2.1 Re Use of Q-List at Plant,Per NRC Request.Fnpims Data Base Utilized as Aid for Procurement,Maint,Operations & Daily Planning ML20012C4701990-03-15015 March 1990 Responds to NRC 900201 Ltr Re Emergency Planning Weaknesses Identified in Insp Repts 50-348/89-32 & 50-364/89-21. Corrective Actions:Cited Procedures Revised.Direct Line Network Notification to State Agencies Being Implemented ML20012C6241990-03-14014 March 1990 Informs of Resolution of USI A-47,per Generic Ltr 89-19 ML20012C4651990-03-13013 March 1990 Provides Verification of Nuclear Insurance Reporting Requirements Specified in 10CFR50.54 w(2) ML20012C2051990-03-0505 March 1990 Forwards SPDS Critical Function Status Trees,Per G West Request During 900206 SPDS Audit at Plant.W/O Encl ML20012A1621990-03-0202 March 1990 Forwards Addl Info Inadvertently Omitted from Jul-Dec 1989 Semiannual Radioactive Effluent Release Rept,Including Changes to Process Control Program ML20012A1301990-03-0101 March 1990 Responds to Generic Ltr 90-01 Re Request for Voluntary Participation in NRC Regulatory Impact Survey.Completed Questionnaire Encl ML20043A7481990-02-0202 February 1990 Forwards Util Exam Rept for Licensed Operator Requalification Written Exams on 900131 ML20006D2311990-01-31031 January 1990 Responds to NRC Bulletin 89-003 Re Potential Loss of Required Shutdown Margin During Refueling Operations. Refueling Procedures Will Be Revised to Incorporate Guidance That Will Preclude Inadvertent Loss of Shutdown ML20006A9091990-01-23023 January 1990 Forwards Response to Generic Ltr 89-13 Re Svc Water Sys Problems Affecting safety-related Equipment.Util Has Program to Perform Visual Insps & Cleanings of Plant Svc Water Intake Structure by Means of Scuba Divers ML20005E4931989-12-28028 December 1989 Provides Certification That fitness-for-duty Program Meets 10CFR26 Requirements.Testing Panel & cut-off Levels in Program Listed in Encl ML20005E3681989-12-28028 December 1989 Responds to Violations Noted in Insp Repts 50-348/89-28 & 50-364/89-28 on 891002-06.Corrective Actions:All Piping Preparation for Inservice Insp Work in Containment Stopped & All Participants Assembled to Gather Facts on Incident ML20005E1971989-12-27027 December 1989 Responds to Violations Noted in Insp Repts 50-348/89-22 & 50-364/89-22 on 890911-1010.Corrective Actions:Steam Generator Atmospheric Relief Valve Closed & Core Operations Suspended.Shift Supervisor Involved in Event Counseled ML20011D5041989-12-22022 December 1989 Responds to Violations Noted in Insp Repts 50-348/89-26 & 50-364/89-26.Corrective Actions:Personnel Involved in Preparation of Inservice Test Procedures Counseled. Violation B Re Opening of Pressurizer PORV Denied ML19332F2111989-12-0707 December 1989 Forwards Final Response to NRC 890803 Request for Addl Info Re Review of Updated Inservice Insp Program,Summarizing Results of Addl Reviews & Providing Exam Listing Info ML19332F0791989-12-0707 December 1989 Responds to Violations Noted in Insp Repts 50-348/89-22 & 50-364/89-22.Corrective Actions:All Managers Retrained on Intent of Overtime Procedures & Sys Established to Provide Independent Check of All Time Sheets Each Pay Period ML19332F1141989-12-0707 December 1989 Forwards Description of Instrumentation Sys Selected in Response to Generic Ltr 88-17, Loss of DHR, Per Licensee 890127 Commitment.Hardware Changes Will Be Implemented During Unit 1 Tenth & Unit 2 Seventh Refueling Outages ML19332F1241989-12-0707 December 1989 Forwards Response to NRC 890803 Request for Addl Info Re Review of Second 10-yr Inservice Insp Program,Per 891005 Ltr ML19353B0071989-12-0606 December 1989 Forwards Rev 1 to Safeguards Security Contingency Plan.Rev Withheld 1990-09-17
[Table view] |
Text
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Alabama Power Comparty j
. lnverness Ctrct Parkw:y
. Fbst Offee Bm I?95 ,
Dwmingham. Alabunt 35N1 Telephone 205 BGB-5581 ,
W. Q. Hairston,111 i
Senior Vice Presloent Nuclear Operations January 23, 1990 Ob3@U D U i the Southern t%ctrC Sy Ettrm I
Docket Hos. 50-348 50-364 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Vashington, D. C. 20555 ;
Gentlemen: ;
i Joseph M. Farley Nuclear Plant - Units 1 and 2 '
Service Water System Problems Affecting Safety Related Equipment (NRC Generic Letter 89-13)
Generic Letter 89-13 was issued to require licensees e.nd applicants to supply information about their respective service water systems to assure the NRC of their compliance with General Design Criteria (GDC) 44, 45 and >
46 of 10CTR Part 50, Appendix A, and Section XI, " Test Control", of -
10CFR50 Appendix B and-to confirm that the safety functions of their respective service water systems are being met. Generic Letter 89-13 also requested that licensees and applicants perform five recommended actions listed in the generic letter, or equally effective actions, to ensure that their service water systems are and vill be maintained in compliance with the above stated regulatory requirements. Furthermore, Generic Letter 89-13 states that if a course of action is chosen different from the recommended actions, justification that the heat i removal requirements of the service water system are satisfied by use of the alternative program should be documented and retained in appropriate l
plant records. ;
I Alabama Power Company has reviewed the requirements of the generic letter and determined that programs have been developed or vill be developed for the safety related portions of the service water system prior to startup from the Unit 2 Fall 1990 Refueling Outage to meet the intent of the five recommended actions contained within the generic letter. The Alabama Power Company response to each of the five recommended actions is provided in the Enclosure to this letter. Alabama Power Company intends .
to implement this program; however, should other means become available i for implementing these actions in the future, the program may be revised accordingly. Additionally, confirmation that these initial tests and activities have been completed and that continuing programs have been l established will be submitted within 30 days after completion of all initial tests and activities identified in this program.
i-
' 9001300471 900123 ADOCK 0500 48
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9 U. S. Nuclear Regulatory Commission Page 2 The information provided herein is true to the best of my knowledge and belief. If you have any questions, please advise.
Respectfully submitted, ALABAMA POVER COMPANY t.d.b. $ W V. G. Hairston, III VGH.III/LCTimV.1340 Enclosure SVORN TO AND SUBSCRIBED BEFORE ME cet Mr. S. D. Ebneter Mr. E. A. Reeves THIS d . AY OF Ojunau , 1990 Mr. G. F. Maxwell A>lo u . A c] /r M , / / ~
No @ry Public My Commission Expires: lu 00Co;Sil0N LW.ES Ltc.15.!D?2 l
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.i Enclosure 'I Alabama Power Company (APCo). *
[ Response to Actions Recommended in NRC Generic Letter 89-13 m:
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I. NRC Recommended Actions For open-cycle service water systems, implement and maintain an ongoing program of' surveillance and control techniques to significantly reduce the incidence of flow blockage problems as a result of bioforling. The following program, or an equally -
effective program, is acceptable: .
t A. The intake structure should be visually inspected, once ver c refueling cycle, for macroscopic biological fouling organisms-- ,
(i.e., Asiatic clams), sediment and corrosion.- Inspec tions- '
should be performed either by scuba' divers or-'by devatering'the !
intake structure or by-other' comparable methods. Any fouling accumulations should be removed.
B. The service water system should be continuously (for: example,.
during spawning)' chlorinated (or equally effectively treated _vith
- another biocide) whenever the potential for a macroscopic- j-biological luuling species exists (for example's Asiatic ~ clams-et freshwater plants). Precautions should be'taken to_ obey Federal, 4 State and local environmental regulations regarding'the-use of biccides. 3 C. Redundant and infrequently used cooling loops should be flushed and flow tested periodically at the'waximum. design flow to ensure that they are not fouled or clogged. Other components in the-F service water system should be tested on a regular' schedule to ensure that they are not fouled-or clogged. Service water cooling loops should be filled with chlorinated or equivalently-treated water before lay-up. Systems.that use raw service'vrter L
as a source, such as some fire > protection systemsi should also be chlorinated or equally effectively treated beforeElay-up'to help L prevent microbiologically influenced corrosion (HIC)'.
L Precautions should be taken to obey Federal, State'and local.
- L environmental regulations regarding the_use of biocides.
D. Samples of vater and substrate should be collected annually to-determine if Asiatic clams have populated the water source.
Water and substrate sampling is only necessary at freshwater -
plants that have not previously detected the presence of i _
! freshwater clams in their source water bodies. If Asiatic clams
! are detected, this sampling activity may be' discontinued'1f desired and the chlorination treatment program should be modifiedi .l to be in agreement with paragraph B, above. ;
)
- a
^ .
, APC) R3:p:nsi to j
<s , G:n:ric Let tar 89-13 Pago 2
A. APCo has a program:to' perform visual-inspections and cleanings of '
the Farley Nuclear Plant (PNP) service water intake structure for ,
both-Units 1 and 2 by means of scuba' divers to remove any_ :
accumulations of macroscopic biological-fouling organisms and j sedimentation.: Since the intake structure is constructed of i concrete, corrosion is'not a problem in the FNP' intake structure. '
The next inspection is currently planned for<the summer of 1990. t Based on the previous inspections, future inspections v111f initially be established on a two year frequency. . Should the
.results of these inspections indicate that the frequency;for, -
inspecting or c1 caning the_ intake structure need'be modified, the appropriate changes vill be made. Additionally, since:the ,
previous inspections and cleanings were; performed by, scuba-j divers, devatering of the intake structure was not necessary. .
B. APCo currently treats the service water system'during spawning !
seasons for Asiatic clams. The current program or an equally I effective program vill continue for treating the service water system whenever the potential for Asiatic clams' exists.- This chlorination process is in-accordance with.our existing-plant ,
effluent discharge permit which is based on Federal, State _and local environmental requirements. +
C. The service water _ system at FNP is basically a once-through-system with most: safety related loads-continuously supplied service water in a-parallel flow arrangement. Thus, the safety' related portions of the FNP service water system'do'not contain-I redundant and infrequently used cooling. loops as referred to in ,,
the above recommended' action.
The FNP service water system does, _ however, contain :various lines in the safety related-portions-of-the system which are infrequently used. APCo vill develop a program prior to startup from the Unit 2 Fall 1990 Refueling Outage to periodically, place -
these lines in normal operation, flush these lines at normal operating conditions or at conditionsiconsistent with normal -
plant operations, or inspect the lines for fouling. The schedule for operating, flushing or inspecting these lines v111' be defined l
i by the program, The FNP program for testing safety related heat exchangers is '
addressed in the response to Action II below. Other service water system components (i.e., vents, drains and instrument-lines) are not included in this program. Additionally.-cooling loops of the FNP service vater system are not placed in lay-up.
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.5 ' . ~APCi R =p nsa to ]
.G:n2ric Lettsr 89-13 i
,Pega 3- .;
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The fire protection water suppression system,Jexcluding the ,
standpipes inside containment, does not use service vater as a' normal vater source. Therefore, chlorinating or equivalently ;
treating the. fire protection _ vater. suppression system is not required. A connection from the service water system.to the-fire protection' vater suppression system exists but it is there only - -
as'a' backup water source and the. fire protection design does not-rely upon.this connection as an available water source. . This.
connection vill be included in the program discussed above for
! periodically _ operating, flushing-or inspecting infrequently used ,
lines. The normal water source for the standpipes inside l containment'is the service vater system. These lines will also^ .!
, be' included in the-program discussed above for periodically i i
operating, flushing or inspecting infrequently used lines.
Accordingly, chlorinating or equivalently treating these-lines is .;
not necessary, 1 D. The presence of Asiatic clams has been previously detected in the !
service water pond at FNP. Thus, the annual sampling to determine if Asiatic clams have populated the-vater source is not-required for FNP. Accordingly, the chlorination' treatment program discussed in response to paragraph B addresses the chemical treatment for clams.
II. NRC Recommended Actions Conduct a test program to verify the heat transfer capability of all safety related heat exchangers cooled by service water. The total test program should consist of an initial test program and a periodic retest program,.and should include. heat'exchangers connected to or cooled by one or more open-cycle systems.' The initial frequency for the periodic _ retesting should be at'least once per' fuel cycle, but after three tests,-licensees and applicants should determine the best frequency'for testing to provide assurance that the equipment vill perform the intended safety functions during.
the intervals between tests and meet the requirements of GDC 44, 45 and 46. The minimum final testing frequency should be nnce every five years. A summary of the program should be documented, including the schedule for tests, and all relevant documentation should be retained in appropriate plant records. .
3 The need for testing of closed-cycle _ system heat exchangers has not been considered necessary because of the assumed high quality of existing chemistry control programs. If the adequacy of these chemistry control programs cannot be confirmed over the total operating history of the plant or if during the conduct of the total testing program any unexplained downward trend in heat exchanger.
performance is identified that cannot be remedied by maintenance of 4
an open-cycle system, it may be necessary to selectively extend the test program and the routine inspection and maintenance program addressed in Action III below to the attached closed-cycle systems.
7
. *~
. APCo'R0cp:nsa to- '
si*
G:ntric Letter 89-13
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Testing should be'done with necessary and sufficient- . .
instrumentation,-though the-instrumentation need not be permanently installed. The relevant temperatures should be verified to be within design limits.- If similar or equivalent; tests have not been ,
performed during the past year, the initial tests should be completed before plant.startup following the first refueling. outage ;
beginning nine months or more after the date'of this letter. ,
I-As a part of the initial test program,.it may be decided to take.
corrective action before testing. Tests should be performed for;the * ;
heat exchangers after the' corrective actions are taken to establishi baseline data for future monitoring of heat exchanger performance.
In the_ periodic retest program, the best frequency for testing toL provide assurance that the equipment' vill perform the intended-safety: functions during the intervals between tests should be determined after the completion 1of three tests. Therefore, in'the , i periodic retest program, testing.should be' performed for the' heat ,
exchangers before any corrective actions'are taken. LAs in.the i initial test program, tests should be repeated after any corrective actions are taken to establish baseline data'for future monitoring of heat exchanger performance.
An example of an alternative action that.vould be acceptable to the NRC is frequent regular maintenance of a heat eithanger in lieu of testing for degraded performance of the heat exchanger. This alternative might apply to small heat exchangers, such as lube oil coolers, pump bearing coolers or readily serviceable heat exchangers located in low radiation areas of the facility. >
The following program, or an equally' effective program to ensure ~ l satisfaction of the heat removal requirements of the service water i
~
system, is acceptable:
\
A. All Heat Exchangers l
~
Monitor and record cooling water flow and inlet and outlet temperatures for all affected heat exchangers during the modes of operation in which cooling water is flowing through the heat exchanger. . For each measurement, verify that the cooling water temperatures and flows are within design limits for the
, _ conditions of the measurement. The test results from. periodic I testing should be trended to ensure that flow blockage or
!- excessive fouling accumulation does not exist.
(
B. Water-to-Vater Heat Exchangers (In addition to Item A above) i l-
- 1. Perform functional testing with the heat exchanger operating, if practical, at its design heat removal' rate to verify its-capabilities. Temperature and flov' compensation should-be made to adjust the results to the design conditions.- Trend L
I the results, as explained above, to monitor degradation.
- 2. If it is not practical to test the heat exchanger at the i design heat removal rate, then trend test results for the heat exchanger efficiency or overall heat transfer coefficient. Verify that heat. removal vould be adequate for +
the system' operating with the most limiting combination of i flow and temperature.
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.i i .- APC) R3sp:nsa to. -
G:nzric Letter 89-13
, Pega 5 C. Air-to-Vater Heat Exchangers (In' addition te' Item'A~above)
- 1. Perform etficiency testing (for example, in conjunction'vith. !
surveillance testing) with the heat exchanger _ operating .;
under the maximum heat load'that,can be obtained practically .:
F and' correct the results for off-design conditions.L Verify.
design heat removal capacity-and trend results to_ identify any degraded equipment..-
- 2. If it-is not possible to test the heat exchanger.'to' provide
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j statistically significant results (for: example, if error in
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the' measurement exceeds the~value of the parameter being:
measured), then trend test results for.both the air andz vater flow rates in the heat exchangers and perform visual
~ inspections, where possible, of both the air and water sides of the heat exchanger to ensure cleanliness'of the heat exchanger. >
D. Heat Exchangers Other than Vater-to-Vater and Air-to-Vater '
(In Addition to Item A above)
- 1. If plant conditions allow testing at design heat removal conditions, verify.that'the heat exchanger performs its intended functions and trend the test:results to monitor-degradation.
7 2 .- If testing at design conditions is not possible', then._ _
provide for extrapolation of test' data to design. conditions., ,
The heat exchanger ef ficiency or the' overall--heat transfer a coefficient of the heat exchanger,should be determined ~ )
whenever possible. Where possible, provide for visual inspection of the heat exchanger.
APCo Responset APCo vill develop a test program prior to startup:from the Unit 2 Fall ,
1990 Refueling Outage to verify the-performance capability of safety it related heat exchangers cooled by service water to: ensure they can perform their safety related function. The test program vill require the performance testing of each heat exchanger.once during'ench refueling cycle for'three cycles. The results will.be'used to !
determine the appropriate frequency for future testing to provide. .
assurance that the equipment vill perform the intended safety.
functions during the intervals between tests. Tests will:also'be-performed after any corrective maintenance that could: affect.the heat-exchanger performance. .All relevant documentation vill be retained in appropriate plant records.
APCo has reviewed the chemistry control program for the component cooling water (CCV) system and verified-that chemistry control for.the- ,
CCW system has been implemented over the operating history for-both-Units-1 and 2. If the performance of the CCW heat. exchanger trends-downward vithout logical explanation and-the' downward trend cannot be- '
remedied by corrective action on the service _ vater side of the CCW heat. exchanger, APCo will investigate the reasons for'the downward v trend in the heat exchanger performance and determine the appropriate- 7 corrective action fcr the CCV system.
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?.- . APCD Risp:ns3-to" q 4
G:nsric Lattor 89-13 t .
P2g3 6. ] 3 e g -
l L Testing of the safety related heat exchangers cooled by service' vater . ,
vill be performed with necessary and= sufficient' instrumentation,-
considering both permanently installed and temporary > instrumentation. )
The test program vill address the: evaluation of relevant temperatures-vith respect to. design limits.. )
Vith regard to frequent regular maintenance of a heat exchanger in j L lieu of testing for degraded performance, APCo currently has in place ,
regularly-scheduled preventive maintenance (PM) tasks for inspecting-and cleaning, as necessary, the following safety related heat exchangers:
i ;
L t Diesel Generator Jacket Unter Coolers-
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- 1. j
- 2. Diesel Generator Lube Oil Coolers
- 3. Diesel Generator Turbocharger /Aftercoolers ,
- 4. All~scfety related room coolers-
- 5. CCW Heat Exchanger Alabama Power Company plans to continue to perform these PM tasks'for ,
each of these heat exchangers; however, the PM tasks'for the diesel:
generator lube oil coolers'and turbocharger.aftercoolers vill be used in lieu of periodic testing to ensure acceptable performance of these heat exchangers.
FNP has a heat exchanger testing program in placeLfor safety related room coolers (air-to-vater heat exchangers) cooled by service water.
The purpose of this program is to monitor the heat-removal capability of the heat exchangers by determining the overall heat transfer coefficient for the heet exchanger based on the test conditions and '
comparing this information to the overall heat. transfer coefficient required to temove the design safety function heat removal. -The overall heat transfer coefficient determined from=the test has also been used to predict when corrective action (such as cleaning:of the heat exchanger) needs to be performed.- This testing methodology i provides a means for comparing the heat exchanger performance to the l design heat removal requirements and allows the performance-to be j trended. Accordingly, APCo plans to' adopt this same methodology to i I
the other heat exchangers required to be tested in response to this ~
) generic letter.
The following information addresses the aspects of the heat exchanger testing program described.in Enclosure 2 to the generic letter as they relate to the service water system safety related heat exchanger testing program being developed for FNP.
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. APCo Rssp:nta to? . j
- gin 2ric Lettsr 89-13' ';
. Paga:7:> -j 1
A. All Heat Exchangers ]
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The' service water flow and the service' vater inlet and outlet temperatures vill be verified to be within design limits for the conditions of the measurement. LAs described above, the
-determination of the overall heat transfer coefficient for the i heat exchanger at the conditions of the measurement.and the
-comparison of this information-to the overall. heat transfer
. coefficient.at the design heat removal requirements provides an. ,
adequate means to ensure'that-flow blockage or excessive' fouling ,
accumulation does not-exist.- Additionally, since service water J flows will'be measured as a part of.this program, APCo' vill trend 1
- the flow measurements' for indications :of potential: flow blockage - '.
or excessive fouling. accumulations.-
t B.. Water-to-Vater Heat Exchangers (In addition to Item A above)
The safety related. vater-to-vater heat exchangers cooled by service water are the CCW heat-exchangers and the diesel ,
generator jacket water coolers. 'As described above, PM tasks are performed on both of these heat exchangers. However, a heat exchanger testing program vill be developed for_both of these heat exchangers which determines the.overall heat transfer coefficient at the conditions of'the measurement and compares it-to the design heat removal rate.
I C.- Air-to-Vater Heat Exchangers (In addition to Item'A above) l As . discussed 'previouslyi = APCo has a heat exchanger: testing -
program in place for the safety related' room coolers cooled by.
service water. The other safety related air-to-vater, heat '
exchangers cooled by service water are the containment coolers-and the diesel generator turbocharger aftercoolers. ..A testing-program vill be developed for,the containment coolers / consistent with the room cooler testing program. The diesel generator turbocharger.aftercoolers vill-be periodically inspected and j cleaned as a PM task in-lieu'of testing.
Furthermore, if it is not possible to'obtain' statistically significant results (i.e., the error in the measurement exceeds the value of the parameter being measured), APCo vill ~either
~
verify _that the service water flow meets the design requirements and perform a visual inspection'of the air-side of the heat'
-exchangers or retest the heat exchanger at an. appropriate time to obtain statistically significant results.-
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]
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^*f. ~APCo R:sp:ns2'to.
. Generic LettOr 89-13 :
Paga,8L J
D. Elent Exchangers.0ther than Vater-to-Vater'and.
Air-to-Vater -(In ' addition to Item A above)
The safety related heat exchangers cooled by service' I t.
water in'this category are the_ control room air ~
L conditioning condenser (Freon), the diesel generator lube oil coolers (oil), and.the_ service water pump motor i lube oil coolers-(oil).; As previously mentioned, the. 1 diesel generator lube oil coolers are periodically _ '
cleaned through PM tasks and are therefore not' required
!- to.be addressed in the testing-program. APCo. vill
. develop'a testing program for.the control' room air conditioning condenser.and the service water pump motor lube oil coolers basedion.the previously described room ;
cooler testing program.- l!
i:
III. NRC Recommended Action:
L Ensure by establishing a routine' inspection and maintenance L program for open-cycle service water system' piping and-l.
components that corrosion, erosion, protective coating _
failure, silting and biofouling cannot degrade the 1
- i. performance of the safety related systems supplied by ~!
l' service water. The maintenance program should have at f least the following purposes: 1 p
-1. To remove excessive accumulations of biofouling agents,-
corrosion products, and silti-i p 2. To repair defective protective coatings and corroded service l vater system piping and components.that could adversely l
I_
affect performance of their intended safety functions.;
1
- This program should be established before plant startup following the first refueling outage beginning 9 months .
after the date of this letter. A description of,the '
program and the results of these maintenance. inspections. I should be documented. All relevant documentation should be retained in appropriate plant records, i APCo Response:
)
As discussed in the' response to Action II, APCo j periodically inspects the safety related room coolers, the '
CCV heat exchangers, and the diesel generator heat exchangers which are cooled by service water for fouling, j corrosion products and silting accumulations. APCo has ;
also previously inspected portions of the service water ;
system piping utilizing ultrasonic testing and radiographic testing to identify pipe thinning and pipe blockage.- Where appropriate, corrective actions have been instituted.
These corrective actions include sandjet cleaning of some !
lines and replacement of safety related two inch and under carbon steel lines with stainless steel to reduce fouling i accumulations in the lines. Additionally, APCo plans to i start adding a chemical dispersant to the service water 1 system in 1990 to aid in removing solids from the service water system.
P E,. '. APCp R p;ns3 to ;
G:nsric Lettor 89 . Paga 9
- Furthermore, the FNP administrative procedure;for contro11 '
of plant maintenance contains a-clam inspection report
- which must be completed any time a heat exchanger supplied by service water is opened. These inspection and r maintenance actions are a part of the overall program that ensures the' acceptable performance of'the service water system. APCo vill develop-an ongoing inspection and maintenance' program for the service water system safety :
related heat exchangers and piping prior to plant startup from the Unit 2 seventh; refueling outage,. currently scheduled for the Fall of 1990.
l The room cooler performance testing has been used as a' -
means to indicate when corrective maintenance on the system.
is needed. The total heat exchanger performance testing l ._
. program vill be used in the future to indicate.vhen corrective maintenance on the system is needed. Since the heat exchanger testing, program vill form the baseline for ,
verifying the service water system meets its' design requirements, this testing program vill also form the basis ;
for the APCo inspection and maintenance program. All relevant documentation will be retained in appropriate
. plant records.
IV. NRC Recommended Action:
Confirm that the service water system vill perform its intended function in accordance with the licensing basis for the plant. Reconstitution of the design basis of the system'is not intended. This confirmation should include a review of the ability to perform required safety functions in the event of failure of a-single active component.- To ensure-that'the as-built system is in accordance with the appropriate licensing basis documentation, this confirmation should include recent.(vithinlthe past 2 years) system walkdown inspections. 'This confirmation should be completed before plant startup following the first refueling outage beginning 9 months or more after the date of this letter. Results should.be documented and retained in appropriate plant records.
APCo Response APCo conducted a Self-initiated Safety System Assessment (SSSA)-of the service water system in May and June of 1989 and the.CCV system in August and-September of'1989. These SSSAs were based upon the vertical-slice inspection sampling technique utilized in NRC Safety System Functional Inspections-(SSFIs)=and consisted of an integrated design' and operation review for consistency and adequacy. As a part.of the design-review performed in these SSSAs,
-potential single failures and common mode failures were postulated and evaluated for the adequacy of the system design. Selected plant operating and maintenance procedures and practices were then reviewed for consistency i
t
' L. ; . "APC3 R:sp:n23.to
^
'; G:n2ric Lettor 89-13
. P gs 10-vith the design and licensing basis to: ensure that the 'I
. system' vill. perform its intended function in accordance with the licensing basis for the plant.- For.the service- '
vater system SSSA,fselected system valkdowns were also conducted. ,
one of the corrective actions resulting from the: service. d
-vater system SSSA is-the development of a system flow-; ,
balance model.. Although not yet complete, this action involves'the review of piping physical and-isometric drawings to accurately model the system, reevaluation of l the failure' modes'and consequences for the: service water ,
system, and field = flow, measurements for validation of the model. As a~ result'of developing this model, the' system b configuration and system operation has been further . i reviewed for-potential single failures. Upon' completion of? +
the model and evaluation of the post-accident. response of
~
the service vater system, the appropriate changes vill be '
implemented, as necessary. Additionally, this new model vill supersede the old design 1 basis hydraulic calculations b .for the service water system.
l The field flow measurements for validation of the mo' del-consisted of measurements of flov to each diesel generator, total service water pump motor lube oil cooling flow, flow to'all other safety related heat exchangers cooled.by service water, flows to some.non-safety related' loads on ;
the system, and other strategic locations (such as pump: '
discharge flows, total flows to separate buildings, and potential 1 bypass flows). The valkdowns performed in L
preparation for, and in conjunction with, these flov measurements did not identify any physical-discrepancies -
between the as-built system and.the licensing basis-documentation. Some minor differences in'-system operating -
practices and the previous design basis hydraulic calculations were observed and are being-factored-into the flow balance model development. -Although a complete-system =
valkdown has not been conducted, APCo believes sufficient valkdowns have been performed to ensure the safety'related portions of the service water system are in accordance with the appropriate licensing basis documentation.
Since the CCW SSSA did not contain system valkdowns, selected system valkdowns of the CCW system vill be i conducted for consistency with the appropriate licensing basis documentation prior to startup from the Unit 2 Fall j'
1990 Refueling.0utage and the' Unit l' Spring 1991' Refueling
1 APCo considers the reviews performed by the SSSAs'and the corrective actions resulting from the SSSAs, including the j service water system flow balance model development,. !
sufficient to ensure the service water system and the CCV system vill perform their intended function in accordance with the licensing basis of the plant. 1 4
l
\
- - . . . 'i- .APCa1Risp:nr3 to . :
- 'G:nsric Letter 89-13' i Pega ll; ' l ;
- .,, s
.V., NRC Recommended Action Confirm that maintenance practices, operating and emergency procedures, and training that involves the-service vater system are adequate to ensure that safety related equipment J cooled by the service water. system vill function as
-intended and-that operators oftthis equipment vill perform effectively. This confirmation:should include recent _ l (within the past.2 years) reviews of practices, procedures- i and training modules.- The~ intent of this action is to !
reduce human errors in~the operation, repair and. ;
maintenance of the service vater system. This confirmation. ;
should be completed before plant.startup following~the i first refueling outage beginning 9 months or more after the date of this>1etter. -Results should be. documented and'
. retained in appropriate plant records.
APCo Response
i As discussed above in the~ response to Action'IV, the 9 service water system and CCW system SSSAsl reviewed selected maintenance practices and operating procedures. -The emergency operating procedures as they relate to the service water system and CCV system were reviewed during the SSSAs. The service water system SSSA also reviewed the training program as it relates to the service water system. -
Corrective actions necessary to ensure proper system operation vere documented as a part of the SSSAs, Additionally, the effects.of-operating. practices upon the flow balance of the service water system are being incorporated into the flow balance modelidevelopment. Any changes in operating or' maintenance practices, emergency-procedures or the training program-necessary to ensure'the acceptable operation of the service vater system as a result of completing the SSSA corrective actions,: including the service water system flow balance model, vill-be addressed.
Furthermore, APCo plans-to develop a functional system
, system in 1990. The purpose of the FSDs is to' consolidate current system and component functional ~ design requirements '
- i. for all modes of operation of these systems,in an understandable and easy-to use format. The FSDs vill then be reviewed against current. operating and. maintenance practices and procedures, emergency procedures, the -
training program and other plant programs, as appropriate, to ensure consistency between the design 1 functional requirements and these procedures and programs. This reviev vill provide added assurance that the' service water 1 system and CCW system vill function as intended and that operators of this equipment will-perform effectively. 'APCo plans to complete this review prior to plant startup from the Unit 2 Fall 1990 Refueling Outage.
LCT/m.1432
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