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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
. _ . _ _ _ .
N
600 North 18tn Street Post Office Box 2541 7
. Birmingham, Atabama 35291 Telephone 205 323-5341 m-L';;oi'sc'e' ,Sh AlabamaPower f >. . *2O the southem erectne sprem y
, December 18, 1979
[
l Docket Nos. 50-348 and 50-364 NRC IE Bulletin 79-15 j- /
/
. Office of Inspection and Enforcement U. S. Nuclear Regulatory Commission Washington, D.C. 20555 Attn: Director, Division of Reactor
- Construction Inspection
Dear Sir:
In response to IE Bulletin 79-15, Deep Draf t Pump Deficiencies, Alabama Power Company submitted a letter dated July 18, 1979. Our response stated that we did not have any of the pumps in use at Farley in the listed systems.
. Subsequent to that response, further review has determined that Farley Plant has deep draft pumps similar to those identified by the bulletin in safety related application. Attached is our supplemental response to IE Bulletin 79-15 addressing the items requested for these pumps.
Yours very truly,
~
F. L. Claytonj Jr.
, . FLCJr/JGS:bhj , , _
7 .~
Attachment cc: Mr. R. A. Thomas ,
Mr. G.
Mr. M.
F.
D.
Trowbridge Hunt, Region II (w/ Attachment)[
j ff 6 'Q
> J. .- Office of Inspection and Enforcement
}:.}.*:._ $ .. .
.Re~ actor Operations Inspection (w/ Attachment) ,
y ,
i, ~ 1:p , ,<
. ~.
A O
$ W &
, _, p D
.. 'o m o u c,. ,-
IE BULLETIN 79-15
- 1. The number of deep draft pumps similar to those shown in Figures 1 and 2 utilized in safety related applications in each facility.
Response: 10 Unit 1 10 Unit 2 (Under Construction)
- 2. Manufacturer, model, capacity and plant application.
Response
Unit 1 Unit 2
~~
Manufacturer: Byron Jackson Johnson Model: -
30 KXE, Single Stage 30 X 18 Type A, 2 Stage 27cc Capacity: 9750 GPM @ 175 TDH 9750 GPM @ 175 TDH Plant Application: River Water Makeup River Water Makeup To Th'e To the Cooling Pond Cooling Pond Manufacturer: Byron Jackson Johnson Model: 32 RXL-28 KXL, Two stage 30 X 18 Type A, 2 Stage 27cc Capacity: 9000 GPM @ 210 TDH 9000 GPM @ 210 TDH Plant Application: Plant Service Water Plant Service Water
- 3. Overall dimensions of Pumps.
Response
Byron Jackson Johnson River Service River Service Total Height: 51'-4 7/8" 45'-2 1/8" 51'-2" 45'-6 1/2" Pump Height: 45'-9 5/8" 40'-2" ---
Min. Submergence: 4'-6" 5'-0" 4'-6" 5'-0" Pump length below
~ ' ' -
' floor: . 41'-7 5/8" 36'-0" 41'-4b" 35'-9"
~Dia. of Suction- ~
Bell: 2'-10" 2'-10" 2'-6" 2'-6" Dia. of Pump Column: 20" 0.D. 20" 0.D. 20" O.D. 20" 0.D.
- 4. Summary of startup, testing, and routine maintenance history.
. , , . . .o . -
~
,(
.' Response: J'
~ ~ -
Model 30 KXE -- BJ River Water Pumps -
171'66.x5i.,,
2 A. River Water Functional and Flush (Startup Preop)
- 1. Flush R.W. lines -
- 2. Test Minimum Flow System
- 3. Test Operation of R.W. System
- 4. Test R.W. Pumps ,. ,
- a. Pump Control Verification
- b. Pump lube and cooling system operation c c. Pump normal operation (1) Running current for each phase (2) Bus voltage (3) Discharge pressure (4) Discharge flow (5) Dead head pressure (6) Pump vibration (7) Bearing temperatures (8) Motor Winding RTD readings
- 5. . Calibration and loop checks B. FNP-1-STP-25.1 & 2 (Monthly) Inservice
.__ FNP-1-STP-25.3 & 4 (Annual) Inservice
- 1. Monthly
- a. Differential pressure measurement
- b. Upper and lower motor oil reservoir levels
- c. Mounting flange vibrations
- 2. Annual
- a. Differential pressure
- b. Upper and lower motor oil reservoir levels
,_. c. Mounting flange vibrations
- d. Bearing temperatures
- 3. Test reviews (monthly)
- #4 RWP vib. high 12/11/77, 1/11/78, 6/13/78, 9/13/78, 11/18/78, 6/19/79
- #5 RWP vib. high 6/13/78
- #2 RWP vib. high 12/15/78
__ - #8 RWP vib. high 12/11/77, 12/27/77, 1/13/78, 4/11/78, 4/15/78, 10/2/78, 12/15/78
- #9 RWP vib. high 6/13/78, 7/20/79, 7/22/79
, f, , - #10 RWP'.vib. high 9/13/78, 10/17/78 .
41 Test Reviews (Annual) ,
- #8 RWP vib.~high 4/15/78 C. FNP-1-GMP-5.0 Vibration measurements 766-252 .
.FNP-1-GMP-9.0 General pump inspection ,
s
, , . _ _[, ,,
. FNP-1-GMP 21.0 Coupling ' Alignment
. ; r:n . . ., -
~
Maintena'nce History
*"D.
#4 RWP - packing adjustments & vibration problems
#5 RWP - packing adjustments
#8 RWP - packing adjustments & vibration problems s- . .
#9 RWP - packing adjustments
#10 RWP - packing adjustments & vibration problems Model 32 RXL - 28 KXL - BJ Service Water Pumos A. Service Water Preop
- 1. Verify pump minimum flow bypass
- 2. Verify design flows for Cold Shutdown conditions
- 3. Verify design flows for normal operation
- 4. Verify individual SW pump design and operation
- a. Running current for each phase
- b. Bus voltage
- c. Discharge pressure
- d. Pump vibration
-- e. Pump rpm
- f. Bearing temperature
- g. Dead head pressure
- 5. Pump lube and cooling system operation B. FNP-1-STP-24.1 & 2 (Monthly) Inservice FNP-1-STP-24.3 & 4 (Annual) Inservice
- 1. Monthly
- a. Total Dynamic Head
-. b. Upper and lower oil reservoir levels
- c. Flow rate
- d. Mounting flange vibration
- 2. Annual
- a. Total Dynamic Head
- b. . Upper & lower oil reservoir levels
- c. Flow rate
-- d.. Mounting flange vibration
- e. Bearing temperature
- f. Discharge pressure ,
. s . -
- 3. Test reviews (monthly) -
- #1D SWP vib. high 11/18/78 .
- #E SWP vib. high 11/18/78, 11/28/78 j f { g. l} } }..
- 4. Test ~ reviews (annual) '
s - ., - .' - . , Eh .
F. .;1,/ - . -(No' discrepancies .>-
- , - + -
77 .
C. FNP-1-CMP-5.0 Vibration Measurements FNP-1-GMP-9.0 General Pump Inspection ,7 ,
FNP-1-GMP-21.0 Coupling Alignment . V '
4
.h. .
.,.e C,
D. Maintenance History
#1A SWP - packing adjustments,1/18/79: Major inspection, lift setting
#1B SWP - packing adjustments, lif t setting
#1C SWP - packing adjustments, lube / cooling flow, lif t setting
#1D SWP - packing adjustments, minor vibration problem, lif t setting
#1E SWP - packing adjustments, minor vibration problem, lif t setting Model 30 X 1B Type A, 2 stage - Johnson River Water and Service Water Pumps These pumps have been operated some but the preoperation test has not yet been performed.
- 5. Operational problems and major repair efforts.
-- Response:
Unit 1
#10 RWP: 11/78 - Put on spare bowl and sent original bowl assembly to BJ for repair.
#9 RWP: 12/78 - Repaired on site.
#4 RWP: 2/79 - Put repaired bowl from #10 RWP on and sent suction bell to BJ.
#5 RWP: 9/79 - BJ has original bowl assembly, will return in + 2 weeks.
November, 1978 -
#10 pump had high vibration. The pump was removed and disassembled. The suction bearing was seized to the shaf t and had rotated in its housing. The line bearings were worn out of tolerance. The vanes on the impellor were cracked on the leading edge at the hub.
The bowl was repla:ed, all bearings were replaced and several shafts were replaced.
December, 1978 - #9 RW pump was disassembled due to high vibration and
-- experience with #10.
Same general condition was observed. The wear ring
. . fclearances were satisfactory. Hence the bowl was not replaced. The impellor was replaced.
February, 1979 - f4 RW pump was disassembled due to experience with #9
, and #10. Same general condition was observed. Bowl
. assembly was replaced.
!August,1979 - -
'#5 RW pump was disassembled. Same general condition
]; ; (, s
[ #' . was observed. The impellor had experienced sever c
, , tation at some thme. The cracking in the vane area um again present. The impellor had been repaired at some time before - it showed signs of brazing, etc. The bowl assembly was replaced.
April, 1979 - 1A pump was disassembled based on experience with R.W.
,,_ _ .: . Bearings were out of' tolerance at the bottom.5 The lubrication line to lower bearing was clogged 99%.
Bearings were replaced. ,.
,. _,_ 1-766~254
Unit 2 Unit still under construction.
- 6. The longest interval that each pump has been available for operation without corrective maintenance. Identify the number of cycles of operation during this interval, the duration of each cycle and the operating model(s) (recirculation, rated flow, etc.). Identify the longest continuous operation at or near rated flow conditions for each pump and the status of the pump operability at the end of the run.
Response
Unit 1 River Water Pumps QSP25P004-B Longest interval of availability: 12/6/77 to 2/21/79 Cycle Duration Mode 1 1 day, 4 hours Rated Flow 2 2 drys, 16 hours 3 4 days, 16 hours 4 0 Jays, 8 hours 5 ".2 days, 8 hours
~-' "
6 0 days, 20 hours 7 0 days, 4 hours 8 0 days, 8 hours 9 0 days, 8 hours 10 2 days, 12 hours 11 0 days, 8 hours 12 8 days, 4 hours 13 0 days, 8 hours 14 0 days, 4 hours .
15 0 days, 12 hours cl6 3 days, 4 hours 17 1 day, 12 hours
- j. l.l ' .
.18 4 days, 20 hours e, .19 11 days, 4 hours .
20 27 days, 4 hours -" -
21 5 days, 20 hours 22 1 day, 4 hours 23 3 days, 20 hours 24 0 days, 16 hours
-*25. O days, 8 hours
!O5I-5
' .'. 2 6 ~ 2 days, 20 hours -
"' ~, 1 .
27 0 days, 8 hours " -
~
~
28 0 days, 16 hours -
29 0 days, 16 hours 30 ,2 days, 4 hours "
4 days, 4 hours 31 32 0 days, 12 hours
.33:
- O days, 8 hours ,,
e-
-.. 1766 ~2~55 s . .
' ^
, .. ' ' 2 .*
Cycle Duration Mode 34 1 day, O hours Rated Flow 35 10 days, 4 hours 36 "
0 days, 8 hours 37 "
5 days, 16 hours 38 4 days, 16 hours 39 0 days, 16 hours "
40 2 days, O hours "
41 "
7 days, 12 hours 42 "
0 days, 8 houra 43 "
2 days, 16 hours 44 41 days, 20 hours "
45 "
0 days, 8 hours 46 2 days, 12 hours 47 0 days, 4 hours "
48 "
3 days, 20 hours 49 17 days, 8 hours 50 3 days, 0 hours "
51 42' days, O hours 52 0 days, 4 hours "
53 21 days, O hours 54 "
25 days, 8 hours 55 3 days, 12 hours "
Pump S/D for major maintenance on the bowl assembly.
QSP25P005-B Longest interval of availability: 12/8/77 to beyond 8/13/79 Cycle Duration Mode 1 2 days, 3 houts Rated Flow 0 days, 20 hours "
L2
.3 0 days, 8 hours "
4 1 day, 4 hours "
5 0 days, 16 hours 6 1 day, 4 hours "
._. 7. 3 days, 16 hours "
8 _ 0 days, 4 hours 9 0 days, 4 hours "
10 10 days, 8 hours "
11 0 days, 8 hours "
12 0 days, 4 hours "
13 .3. days, 12 hours "
_. . ;'. 14 2' days, 16 hours '"_. ,. . : ,.
;Uf
' " ' "15-2t days,~8 hours '"
16' .5 days, 20 hours "
17 1 day, 4 hours "
18 1 day, O hours "
. 19 2 days, 12 hours "
20 0 days, 20 hours 21 ' O days, 20 hours "
22 : 1 day,12 hours -
'1/66 ,256.-
Cycle Duration Mode 23 1 day, 8 hours Rated Flow 24 1 day, O hours 25 1 day, 20 hours 26 0 days, 20 hours 27 6 days, 20 hours 28 1 day, O hours 29 5 days, 4 hours 30 0 days, 8 hours 31 50 days, 12 hours 32 0 days, 20 hours 33 1 day, 8 hours 34 21 days, 16 hours 35 5 days, 20 hours
-- 36 1 day, 12 hours f 37 0 days, 20 hours 38 1 day, 4 hours 39 0 days, 16 hours 40 1 day, 8 hours 41 1 day, 4 hours '
42 1 day, 8 hours 43 1 day, 4 hours 44 3 days, 20 hours 45 1 day, 0 hours 46 0 days, 16 hours 47 0 days, 8 hours 48 "
0 days, 8 hours 49 0 days, 4 hours 50 0 days, 12 hours 51 0 days, 12 hours 52 0 days, 12 hours, "
53 1 day, O hours 54 14 days, 12 hours 55 13 days, 20 hours 56 3 days, O hours
-- 57 1 day, O hours 58 1 day, o hours 59 1 day, 8 hours
'60 .5 days, 4 hours
.61 2. days, 4 hours "-
, 62 "
3 days, 20 hours 3 63 7 days, 16 hours 64 1 day, 16 hours 65 l' day, 20 hours "
66 0 days, 4 hours 7 .5 days, O hours
+. 5 . -
v, 4_=gg
-6 268'67- .
;2-! days, 8 hours " .
2 days, 16 hours a t,
.c4 ,
~69 -
70 1 1 day, 20 hours -
71 7 days, 16 hours 3 72 18 days, 8 hours _
o . r ,
' 0 days, 8 hours "
_ 73 17166 ' 25 ~/ "
s,
' 9_ ,,
~
. , . , e. . . - - . . . .
Cycle Duration Mode 74 3 days, 4 hours Rated Flow 75 0 days, 12 hours 76 6 days, 20 hours 77 0 days, 16 hours 78 2 days, 12 hours 79 0 days, 8 hours 80 "
0 days, 4 hours 81 "
0 days, 8 hours 82 1 day, 16 hours 83 "
1 day, 16 hours 84 0 days,.16 hours 85 0 days, 4 hours 86 1 day, 12 hours
__ 87 0 days, 20 hours 88 "
0 days, 12 hours 89 0 days, 12 hours 90 "
0 days, 12 hours 91 8 days, 0 hours 92 1 day, 8 hours 93 4 days, O hours 94 0 days, 4 hours 95 9 days, 8 hours 96 0 days, 12 hours 97 1 day, 4 hours 98 0 days, 12 hours
._, 99 3 days, 4 hours 100 3 days, 8 hours "
101 0 days, 16 hours "
102 0 days, 4 hours "
103 14 days, 8 hours "
104 11 days, 4 hours 105 5 days, 12 hours "
106 2 days, 4 hours "
107/ 1 day, 8 hours 108 0 days, 20 hours "
_ 109 35 days, 8 hours.
8/13/79 is the cutoff for this research
.. , - ,. . 3 . . -
- QSP25P008-A
' Longest interval of availability: 12/1/77 to beyond 8/13/79 Cycle Duration Mode
. '~. _
, f ;. , .jl; O days, 4 hours Rated Flow
, [,.sf ^', - - ' .; ,(2 7 0 days,.8: hours '
[ . ., .. .i -
3: "I day, 20 hours " -
~
-~*-
'4 .
23 days,.0 hours '-
.5 0 days, 16 hours
~~
2 days, 0 hours "
. x .,6 .
~~?77~ 1 day, 16 hours ec .P76~6:258
,; ' .J . .n
. - . '..,, . 4
- Cycle Duration Mode 8 0 days, 4 hours Rated Flow 9 0 days, 8 hours 10 "
0 days, 20 hours 11 0 days, 12 hours 12 0 days, 16 hours 13 1 day, 4 hours 14 0 days, 4 hours 15 0 days, 4 hours 16 23 days, 4 hours 17 18 days, 4 hours 18 0 days, 8 hours 19 6 days, 12 hours 20 0 days, 4 hours 21 '6 days, O hours 22 "
0 days, 12 hours 23 0 days, 4 hours 24 0 days, 12 hours 25 1 day, O hours 26 1 day, 8 hours 27 5 days, 16 hours 28 0 days, 16 hours 29 1 day, O hours 30 2 days, 8 hours 31 6 days, 16 hours 32 1 day,~4 hours 33 1 day, 8 hours 34 4 days, O hours 35 0 days, 8 hours "
36 0 days, 12 hours "
37 0 days, 16 hours 38 0 days, 8 hours 39 0 days, 8 hours 40 0 days, 4 hours "
41 0 days, 12 hours 42 0 days, 12 hours "
43 2 days, 20 hours "
44 0 days, 12 hours (9 , , 55 4 7 days, 8 hours . .
' ; (, - f46 0 days, 16 hours " '
'47 0 days, 20 hours 48 1 day, 12 hours "
49 5 days, 16 hours 50- 1 day, 20 hours
; 51. O days, 4 hours "
+;f ' -
'O days, 16 hours "
.. .' 52 :
3';' : t O' days, 8 hours ~"
.V(*
~
f .vi", 5 y
. ;.54' 7 days, 12 hours .
2 days, 8 hours "
~55
~"
- 56. 8 days, O hours 57- 1 day, 16 hours 0 days, 4 hours "
58 59 0 days, 4 hours
_.,-z .
. 4766 259'
- s .
g .
_ 9 _. _
Cycle Duration Mode 60 33 days, O hours Rated Flow 61 5 days, O hours "
62 0 days, 12 hours "
63 0 days, 4 hours "
64 0 days, 16 hours "
65 0 days, 20 hours "
66 0 days, 8 hours "
67 0 days, 12 hours "
68 0 days, 4 hours "
69 0 days, 12 hours "
70 0 days, 4 hours "
71 1 day, O hours "
. 72 0 days, 12 hours "
73 0 days, 16 hours "
'74 0 days, 4 hours "
75 6 days, 12 hours "
76 2 days, 8 hours "
77 1 day, 16 hours "
76 2 days, 20 hours "
79 1 day, 8 hours "
80 0 days, 16 hours "
l 81 1 day, 12 hours "
82 0 days, 16 hours "
83 1 day, 4 hours "
l
- 84 0 days, 4 hours "
-- 65 1 day, O hours "
86 1 day, 16 hours "
87 0 days, 8 hours "
88 6 days, O hours "
89 0 days, 6 hours "
90 0 days, 8 hours "
' 91 3 days, 8 hours "
2 days, 4 hours 92 "
93 1 day, 4 hours "
- 94 1 day, O hours "
!' 95. 8 days, 16 hours "
J 96 2 days, 0 hours "
97 'l day, 8 hours .
3; 98- 2 days, O hours d '~
8 days, O hours F . . 99 ~ "
Y 100 1 day, 12 hours "
101 ,
9 days, 12 hours I -
8/13/79 is the cutoff for this research.
c '
G .
g~ ,'_ 'OSP25P009-A a
'i M '
lb:h ' 4 ~. longest int'erval of avail. ability: 12/1/77 to'12/7/78.u : :. :
Q _
Mode Cycle Duration y '
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fj 1 . 10 days, 4 hours Rated Flow
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0 days, 8 hours 2
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3 0 days, 20 hours p
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Cycle Duration Mode 4 1 day, 12 hours Rated Flow 5 0 days, 4 hours 6 0 days, 12 hours 7 9 days, 12 hours 8 0 days, 4 hours 9 0 days, 16 hours 10 16 days, 4 hours 11 34 days, 16 hours 12 0 days, 8 hours 13 2 days, 12 hours 14 0 days, 16 hours 15 0 days, 8 hours 16 1 day, 12 hours J' 0 days, 12 hours 18 0 days, 4 hours 19 0 days, 8 hours 20 1 day, O hours
'21 1 day, 0 hours 22 0 days, 8 hours 23 "
0 days, 8 hours
~24 5 days, 16 hours 25 1 day, 12 hours 26 21 days, 20 hours 27 2 days, 16 hours "
28 18 days, 20 hours "
__., 29 3 days, 8 hours 30 0 days,16 hours 31 0 days, 8 hours "
32 0 days, 8 hours 33 0 days, 4 hours "
34 "
0 days, 12 hours 35 0 days, 12 hours 36 0 days, 4 hours "
37 1 day, O hours "
38 0 days, 12 hours 39 2 days, 12 hours 40 0 days, 8 hours
, _41 7 days, 8 hours
. n; ., ., ;4 2 0 days, 12 hours "
'43: 0 days, 12 hours 44 0 days, 16 hours 45 0 days, 20 hours 46 0 days, 4 hours 47 3 days, 12 hours
, _ . _ 48 ., _,1, day, 20 hours
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. . i 4 9 11 day, O hours -
-5 '
-50,- -
1 day, O hours'- " ., .
7 b 62b.}.
$51 1 day, 4 hours " !
16 days, O hours "
52
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53 14 days, 12 hours "
.54 J3 days, 12 hours Pump S/D for major maintenance on the bowl assembly (repaired on site).
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QSP25P010-A Longest interval of availability: 12/1/77 to 11/25/78 Cycle Duration Mode 1 0 days, 4 hours Rated Flow 2 4 days,16 hours 3 0 days, 8 hours 4 1 day, 8 hours 5 0 days, 20 hours 6 0 days, 12 hours 7 0 days, 8 hours 8 21 days, 20 hours 9 0 days, 12 hours 10 0 days, 16 hours
' 11 1 day, 16 hours 12 0 days, 16 hours 13 0 days, 8 hours 14 2 days, 8 hours 15 0 days, 8 hours 16 2 days, 12 hours 17 0 days, 4 hours -
18 0 days, 4 hours 19 0 days, 20 hours 20 0 days, 12 hours 21 1 day, O hours 22 1 day, 4 hours
~~ "
23 1 day, 16 hours 24 6 days, O hours 25 0 days, 4 hours 43 days, 20 hours "
'26 27 2 days, 8 hours 28 1 day, 20 hours 29 8 days, 20 hours 30 0 days, 4 hours 31 2 days, 20 hours
.32 0 days, 16 hours ,
Pump S/D for major maintenance on s-
-bow 1; assembly. . _ , -
.: 1766'262
. Service Water Pumps Q1P16P001-A ~ ,
', Longest interval of availability: 4/3/78 to 2/20/79
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9 5' Cycle, #
,' - Duration'
~
Mode :' -
- . c y ,. ;.-
1 8 days, 8 hours Rated Flow
'2' " 195 days, 4 hours
'3 . 32 days, O hours 63 days, 12 hours "
4 S/D to replace packing
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Q1P16P001-B Longest interval of availability: 4/4/78 to 8/2/79 Cycle Duration Mode 1 9 days, 12 hours Rated Flow 2 "
0 days, 16 hours 139 days, O hours "
3 4 "
9 days, 8 hours 5 114 days, 16 noars 6 44 days, 16 hours 7 48 days, 8 hours 8 37 days, 16 hours
__ S/D to check and adjust impeller list setting.
QlP16P001-C Longest interval of availability: 12/1/77 to 5/5/79 Cycle Duration Mode 1 86 days, 20 hours Rated Flow 2 "
. O days, 20 hours 3 "
0 days, 4 hours 4 "
__. 0 days, 12 hours 5 0 days, 4 hours 6 "
0 days, 8 hours 7 1 day, 8 hours "
8 34 days, O hours "
9 0 days, 8 hours 10 0 days, 8 hours "
11 1 day, 4 hours 12 15 days, 16 hours
__ 13 0 days, 8 hours 14- 1 day, 4 hours "
15 29 days, O hours 16 32 days, 12 hours
.17 0 days, 12 hours 18 0 days, 12 hours -
19 20 0 days, 12 hours 9 days, 8 hours
" g- }g} .
21 0 days, 20 hours
- 22- 5 days, O hours ,
;23s 28 days, 20 hours " -
'f,,1,f 't 0: days,.4 h'ours 2 4 , . , ', _ ,.
'^A ' "
251 6~ days, 4 hours u-
- 26 O days, 4 hours
; 27. : 0' days, 4 hours
~28' 0 days, 12 hours 1 da , 4 hours "
29 30 0 days, 8 hours
_ > 31 67 days, 12 hours
' 32 , 8 days, 4 hours - "
S/D to rep. ace packing
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QlP16P001-D Longest interval of availability: 4/5/78 to 6/25/79 Cycle Duration Mode 1 16 days,16 hours Rated Flow 2 149 days, 20 hours 3 51 days, 20 hours 4 "
0 days, 4 hours 5 120 days, 12 hours 6 15 days, 16 hours 7 59 days, 4 hours 8 - 20 days, 8 hours S/D to replace packing
.QlP16P001-E Longest interval of availability: 4/6/78 to 8/2/79 Cycle Duration Mode 1 77 days, 8 hours Rated Flow 2 279 days, O hours "
3 , 10 days, O hours 4 "
61 days, 4 hours 5 24 days, 8 hours "
6 4 days, O hours "
7 10 days, 4 hours 8 "
8 days, 16 hours S/D to check and adjust impeller lift setting.
Unit 2 Unit still under construction.
Files have been established to collect the identified items listed in the
' bulletin. An evaluation will be conducted within 60 days of this letter to identify any actions needed to improve performance and/or reliability . .
of these pumps.
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