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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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b J' Nabama Power Comp:.ny . '
- @ #0 inverness C:nter Parkw:y , I
% Post Offico Box 1295 . 1 Dirmingham, Alabama 35201- ,
Telephone 205 808 5581 :
W. G. Hairston, til . .
Senior Vice President Nuclear Operations ,Jahyg g g August 20, 1990 the southern etctrcsystern f
a 10CFR50.55a(g) ,
I!
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s Docket No. 50-364 7 f
U. S. Nucle ~ar' Regulatory Commission 3 Attention: Document Control Desk !
,Vashington, D. C. >20555 Gentlemen: .
n!
Joseph M.-Farley Nuclear Plant - Unit 2 1
, Ten-Year' Inservice Testing (IST) Program >
for ASME Code Class 1, 2 and 3 Pumps and Valves Alabama Pover~ Company previously submitted an updated IST Program and related [
relief requests for Farley Nuclear Plant, Unit 2 on December 15,'1988. The NRC; j granted interim approval for the relief requests by letter dated March 31, l[
1989 however, Enclosure 1 of that same letter denied certain relief requests. ^
Following- a. discussion with the NRC Staf f on April 6,1989, Alabua Pover-Company evaluated the issues surrounding the denied relief requests and
. incorporated changes into Revision 1 which was submitted for review.by letter
. dated July 20, 1989. To date, Alabama Power Company has not received approval for-the relief. requests submitted with Revicion 1. j Enclosed for review and granting of relief is Revision 2 of the Unit 2 :
IST Prograni. This submittal incorporates commitments addressed in Alabama. ?
Power Company's letter dated December 22, 1989 entitled, " Reply to a. Notice of Violation J. M. Farley Nuclear Plant NRC Inspection October 2-6 and October ;
16-20, 1989" and other editorial and technical changes. Changes'resulting from the' Notice of Violation include:
'1. Added provisions for measuring stroke time for Auxiliary Steam admission -
valves 02N12V001A and B.
2' . Addedreliefrequest02N12-RV-1toperformdisassemblyandmanualstr$ke test exercising of 02N12V010A and B on an alternating basis at each refueling outage, n r m. ,
9008280045 9008-20 PDR ADOCK 05000364 P PDC
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t U.-S. Nuclear. Regulatory Commission. Page 2 Additionally Revision 2 added, deleted or modified numerous pump relief-requests as follows:
- 1. Modified the Boric Acid Transfer Pump Test List to delete vibration monitoring during cold shutdown testing. In addition, relief request PR ,
was modified to~ require the performance of a flow test and-the measurement- l of differential pressure exclusively during cold shutdown.- -
t
- 2. Deleted relief request PR-7 which requested relief from the Code instrument range requirements of IVP-4120 to utilize the installed flov instrument.ation. Deletion was based on a procedural change which- t increased the test flow rate. The new test range is within1the full-scale range requirements of Paragraph IVP-4120.-
- 3. Modified relief request PR-9, which also requests relief from the Code instrument range requirements of IVP-4120, to list the inlet pressures currently used to perform testing. This change does not negate the need.
for relief.
- 4. Modified relief request PR-10 for the Service Water Pumps P001A-A, o
P001B-A, P001C-AB, P001D-B and P001E-B to specify the use of a curve of reference values to establish the relationship between flow rate and differential pressure.
- 5. Deleted pump-relief request PR-11 also for.the Service Vater pumps which i requests relief from the pump test range limits specified in Table IVP-3100-2, "Allovable Ranges of Test Quantitler." PR-11 is not necessary since expansion of the allovable ranges of inservice test quantities described by Table IVP-3100-2 is acceptable in accordance with Paragraph IVP-3210 of the ASME Code, Section XI.
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- 6. Modified relief request PR-15 for Component Cooling Vater Pumps P001A-B, P001B-AB and P001C-A which requests relief-from the Paragraph IVP-3110,
" Reference Values," requirement that both differential pressure and flov-rate measurementu be readily duplicated during subsequent inservice tests.
Pump petformance shall be compared to the limits of Table IUP-3100-2 as specified in IVP-3210.
- 7. Added relief request PR-19 to provide for pump testing under variable reference conditions for the Boric Acid Transfer, Residual Heat Removal and Turbine Driven Auxiliary Feedvater Pumps. ,
It is respectfully requested that the relief requests included in Revision 2 of the Unit 2 IST Program be granted by January 31, 1991. This revision is submitted prior to September 1, 1990 in accordance with the December 22, 1989 Notice cf Violation response. Upon granting of these relief requests, Alabama Power Company vill implement Revision 2 of the IST Program.
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.U. S. Nuclear Regulatory Commission. Page 3.
s EIf.there are any questions-or if' additional information is needed, please '
advise.
n Respectfully: submitted, '
"1 .
ALABAMA POWER COMPANY :
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> (;Y _W V. G. Hairston, III e
t VGH,III/DEM/TRHicht-nrc.8.30 l Enclosure
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10r. G. F. Maxwell . v/0 1
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FNP-2-M-067 g Summary of-Revision-2 to the o' J. M. Farley Nuclear Plant - Unit 2 Ten Year Inservice Testing Program ,
For ASME Class 1, 2, and 3 Pumps and Valves !
Page No./ Description / Reason for Change .
l ~. Pages 11-1-1, 4, and 5: Added reference to new Relief _ Request PR-19 to l
-provide for pump testing under variable reference conditions.
]
- 2. Page 11-1-3: Revised.to reflect required lubrication level (LL). check to be
. performed at refueling in addition to quar _terly. Editorial correction.
- 3. Page 11-1-4: Deleted pump vibrational measurement (V) at cold shutdown and deleted relief request reference PR-7. Editorial correction-and-PR-7 is no longer required.- (
- 4. Page 11-1-6: Deleted reference to Relief Request PR-ll.
- 5. Page 1I-1-16: Revised to include relief ~from performing pump vibrational measurement at cold shutdown and to clarify alternate testing performed. ;
s
- 6. Page 11-1-17: Deleted pump relief request PR-7. This relief request is no
' longer required.
- 7. Pages:11-1-20: Changed pump suction pressures from 35 and 40 psig to 23.8 and 50 psig, respectively. Editorial revision.
- 8. Page 11-1-21: Revised to include provision for evaluating tests results d over a range of reference values for two-pump test combinations.
l
- 9. Pages 11-1-22 & 23: Deleted pump r.-Aief request PR-ll and renumbered l following pages as required. This relief request is not required.
- 10. Page 11-1-26: Revised last sentences of " Test Requirement:"' and " Alternate l Testing:" to clarify ranges of Table IWP-3100-2. l
- 11. Page 11-1-29: Revised last sentence of " Basis for Relief:" to reflect ASME
~
approval of Code Case N-472.
- 12. Page 11-1-30: Added new Relief Request PR-19 to provide for pump testing I under variable reference conditions for the BAT, RHR, and TDAFW pumps. .I
- 13. Page 111-1-14-1: Valve test requirements for valves QV001A,8 were revised to perform a stroke test (ST) quarterly and valve test requirements for valves QV0010A,B were revised to incorporate valve disassembly at refueling and manual stroke test exercising via a new relief request. Per APCo letter to NRC dated 12/22/89 titled, " Reply to a Notice of Violation J. M. Farley l Nuclear Plant NRC Inspection of October 2-6 and 16-20,1989". Also, corrected position in " Description and Notes" from closed to open.
l 000815 1 of 2
"T:e" ?-. t e ;:-
- FNP-2-M-067 I Summary'of,Rev. 2-(Cont'd)l l
s I
14'.Page
. 111-l~-14-2: 1 Added new relief request to- provide. for valve' disassembly' d
at refueling and manual' stroke test exercising. Per APCo letter to NRC'
- - dated 12/22/89 titled, " Reply to a Notice of Violation J. M. Farley Nuclear -
Plant NRC Inspection of October. 2-6 and 16-20,1989".-
15.' Page'111-1-24-1:' Revised designation of actuator type for: valves QV002 and
- 4. - Editoriali correction.
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INP-2-M-067 -
TNP Uni t No. 2 . .
Pump Test t.ist Q2EI I .. ,,
j System: ResiduaI ifeat Removaf _.
Measured Parameters and fregtLi*n 1c Ptamp ..
Pi Po dP Q V._ -1 14. . N ' fle I Ie r Class Dwg./ Sheet Coo rd i- Pump Reg 90o te s .
- 4.0.
ISS- Number -nates Descriptions {gsi31 {psiq) [ psi) (qpal (mil] [*D {NAl ( rpm)
Number Q Q Q Q- Q-. -
Q N/A PR 1 P001A-A 2 D-2050841 C-7 Residual llea t . PR-2 D-356358 G Removal ( RitR ) PR-18
-PR-19 l-Q TQ Q
. Q N/A PR-1.- 1 1-7 Residual stea t Q Q PR-2 P0018-B 2 D-205041 D-356358 E-7 Removal (RitH) PR-18 _ _ -
PR-19' E le:
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' .j Pump Test List .
.TMP-2-M-067i ^1 System: High Head Safety. Injection / Chemical Volume and Control . System (HHSI/CVCS) 02E21 Pump .
Measured Parameters and Frequency 1.D. Class Dwg / Sheet Coordi- Pump Pi , - Po dP- I Number ist Number Q V LL N- Re t ier ..
najes Desc D 3 ions [psJgl {p_s s ig) 1psil [gpm] ( m i l ) [* FJ ' ( NA ) bg Reg. Notes-P002A-A 2 D-205039/2 F-5 Cha rging (ifHSI). Q/R. ' Q/R ~Q/R A'
R Q/R -
Q/R N/A PR-1 1 D-356356/2 r-5 PR-4 PR-3 PR-18 P0028-AB 2 0-205039/2 C-5 Cha rg i ng . ( HHS I ) . Q/R 0-356356/2 c-5 Q/R Q/R R Q/R - Q/R N/A PR-1 PR-4 1
PR-5 PR-18 POO2C-B 2 0-20',039/2 H-5 Cha rg i ng ( HHS I ) . Q/R 0-356356/2 H-5 Q/R~ -Q/R R Q/R - Q/R N/A PR-1 PR-4 1
PR-5 PR-18 _
Of601 4
Il-1-3 _
.Rev. 2..
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Pump lest List System: Boric Acid Ts ansrc r/CVCS . 02E21. '
Psep . .
. Measured Parameters and f requency I.D. Class -Dwg./ Sheet Coordi- Pump Pi . Po dP Q . V. I LL- N Reller-Number 8St _ Number' n:s tes Descriptions [psig } {p_sig) {ps,,i} (qpml (mi t ) [*D {NAJ (rpml _ Req. Notes.
POOSA-A 3 - D-205039/3 C-6 Boric Acid Q/CS ~ Q/CS Q/CS CS Q -
Q/CS N/A PR-1l 1,3 D-356356/3 C-6 PR-6 I rans re r. -
=PR 'PR-19 l POOSB-B 3 D-205039/3 11- 6 Boric Acid Q/CS Q/CS Q/CS CS Q -
Q/CS N/A PR 1,3 D-356356/3 81- 6 I rans re r. PR-6 .
PR TR-19. E.
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Pump lest List ._.
System: Auxiliary Feedwater ( ATW) Q29823 ,
Paimp . Mcastered Pa ramegers and Fregtpency 1.D. Class' Dwg./ Sheet Coordi- Pump Pi Po , dP Q V I. . Lt N ReliefL Niembe r JSI Number : nates DescripJ i ons (psiq) { psi s3 ] (ps] {3pm} (mill- [*Q (NA) (rpm) Reg flotes
.+
P001A-A .3 D-20'>001 0-S Motor Driven ' Q/CS Q/CS Q/CS CS Q/CS .- ..Q/CS N/A PR-11 1
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Aux i l ia ry f eed-D-356346- B-5
' PR-8 'l water ( Af W). PR-9
- PR-18 P'0018-8 3 U-205007 E-5 Motor Driven Q/CS O/CS ~Q/CS CS Q/CS' - Q/CS N/A PR-1 - 1' E Aux i 1 ia ry I eed-D-3'>6 3 fs6 PR-8 vater ( AIW). PR-9~
PR POO2 3 D-20'>OO 7 11 - 5 itsrbine Oriven Q Q Q Q O- -
Q Q' PR-1 D-356346 H-$ Auxiliary feed- PR-9' wa te r ( AI W). PR-18 ,.
PR-19 ~ .B.
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FNP Unit No. 2 _ '
Ptep Test t.ist 'Q2P16 System: Service Water (SW)
Nea stered_ Pa r_ase_t e rs and F re_qteency Ptep Pi . 'Po d P.- - -Q -V T t t. N Re l i e r ..
Pamp I.D. Class (N9./ Sheet Coordi-Descript ions . {psig) (psiql {psy 13]pej f milI j,.'F_1 (NA) {rpal Ree. ~ 180 te s .
Ntambe r g Number nates Q Q N/A Q. N/A PR-10 1,3,4,5 POO1A-A 3 D-200013/2 Il- 3 Service Water Q Q Q[
E D-356370/2 14 - 3 (SW). PR-12 PR-13 PR-18 Q Q Q Q~ Q N/A Q ft/A PR-10 1,3,4,5 P0018-A 3 D-200013/2 01 - 5 Service Water.
.8.
D-356370/2 11 - 5 (SWl. ,
PR-13 PR-18 Q Q Q Q Q N/A Q N/A PR-10 1,3,4,5 P001C-AB 3 D-200013/2 It-7 Service Water '
g 0-356370/2 ti- 7 (SW). PR-12 PR-13 Pff-18 Q Q Q' Q Q N/Al Q N/A PR-10 1,3,4,5 P001D-B 3 D-200013/2 68- 9 Service Water .E D-356310/2 II-9 (SW). PR-12 PR-13 PR-18 Q Q Q_ Q N/A Q N/A PR-10' 1,3,4,5 P001E-B 3 0-200013/2 11 - 1 1 - Service Water O l
D-356370/2 H-11 (SW). PR-12 PR-13 PR ._
ff-1-6.
Rev. 2 01608 4
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FNP 2 M 067 o PUMP RELIEF REQUEST L
PR 6 System: CVCS Boric Acid Transfer Pump: P005A A, POOSB-B Class: 3 Function: Transfer of concentrated boric acid from the boric acid tanks to the chemical and volume control system (CVCS).
Test Requirement: Quarterly measurement of pump flow rate.
Basis for Relief: Quarterly pump testing is performed using the orificed pump discharge test line which runs back to the boric acid storage tank. This line does not have any installed flow-measuring instrumentation. To utilize the system flow meter would require a test flow path which would transfer highly concentrated boric acid from the boric acid tank into the CVCS and into the
,' RCS through the operating CVCS charging pump. The addition of concentyated boric acid to the RCS during normal operations would adversely affect the boric acid concentration ir, the RCS and could cause a forced plant shutdown. Because of the pump design and significant difference in flow path and operating conditions between quarterly and cold shutdown testing, pump vibration data taken at cold shutdown may not be useful to monitor pump degradation and could result in unnecessary pump repair. In addition, cold shutdown test duration is limited by the amount of concentrated boric acid that can be transferred to the reactor coolant system and is insufficient to perform vibration measurements.
Alternate Testing: Of the test quantities listed in Table IWP 31001, pump flow rate and differential pressure will be measured during boric acid tranfer pump operation for borating the RCS for entering cold shutdown.
000815 11-1-16 Rev. 2 i
\,
FNP-2-M-067 PUMP RELIEF RECUEST PR-7 del.ETEL -'
(Not Required)
\
i 04601 II-1-17 Rev. 2 l l
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PUMP RELIEF REQUEST PR-9
-i System: Auxiliary Feedwater Pump: POOIA-A, P001B-B, POO2 Class: 2 Function Provide auxiliary 12edwater to the steam generators on loss of main feedwater.
Provide feedwater to the steam generators during startup and shutdown.
Test Requirements: IWP-4120 requCres that the full-scale range of each instrument be no more than three times the reference value.
Basis for Relief: Reference values for suction pressures.
for these pumps are between 23.8 and 50
psig. This would require suction pressure gauges of 0-75 psig maximum.
The accuracy required for these gauges l :
would be 2 percent of 75 psig, which is 11.5 psig. The installed pump inlet lg pressure gauges are 0-100 22 psig.
Although the installed instruments are above the maximum range limits, they are essentially equal to the accuracy requirements and are therefore adequate for pump testing.
Alternate Testing: The installed instruments will be used for taking inlet pressure meusurements during pump testing.
- 04601 21-1-20 Rev. 2
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! FNP 2 M-067 i- PUMP RELIEF REQUEST PR-10 System: Service Water Pump: P001A-A, P0018-A, P0010-AB, P001D B, P001E-B Class: 3 Function: Provide cooling water to safety related ,
p equipment.
Test Requirement: IWP 3400(a) requires that an inservice test be run on each pump.
Basis for Relief: Due to the demands of dependent systems, the individual testing of service water pumps, as required by IWP-3400, would feopardize safe plant .
operation and be impossible to accomplish during plant shutdown.
Alternate Testing: Tests involving combination of two pumps within each train will indicate the hydraulic condition of the pumping system. The con.binations are arranged such that each pump is included in at loast one combination test in each train. The test results are applied to both pumps in the combination and will be compared with a curve of ,
reference values which establish the relationship i between flow rate and differential pressure in a band arounc' the design point.
i 000900 11-1-21 Rev. 2 ;
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FNP 2-M-067 PUMP RELIEF REQUEST ,
PR 11 l
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11-1-22 Rev. 2
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. . i FNP-2-N-067 l PUMP RELIEF REQUEST {
PR-12 System: Service Water tump: P001A-A, P0018-A, POOIC-AB, P001D-B, P001E-B l Class: 3 Function: Provide cooling water to saf3ty-related equipment. .
l Test Requirement: IWP-4500 specifies measuring vibration at a pump housing or its structural ;
support unless it is separated from its driver by a resilient mounting, q Basis for Relief: These pumps are submerged in a pit which makes them inaccessible for measuring vibration amplitudo at the pump bearings.
Alternate Testing: Vibration amplitude is to be measured on the top of the motor housing (which contains the motor j thrust bearing) horizontally in two planes 90 ]
degrees apart.
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04601 II 23 Gen. Rev. 2 -
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! PUMP RELIEF REQUEST PR-15 ;
System: Component Cooling Water 3 Pump: P001A-B, P001B-AB, P001C-/.
Class: 3 l
Function: Provide cooling water to safety-related equipment.
Tes+.-Requirement: IWP-3100 requires that each measured
- test quantity be compared to the reference value of the same quantity. !
Any deviations determined shall be l compared to the limits given in Table .
IWP-3100-2 as specified in IWP-3210.
l Basis for Relief: This system does not have an installed
- pump test line and system operating conditions will not allow adjusting system resistance without significant impact on plant opertions. This is variable resistance system that is in ,
continuous operation during all modes of plant operation. Depending on plant operating conditions and climatic conditions, the cooling requirements range from minimum cooling loads to 100 percent with many of the loads automatically placed in operation in .
response to local temperature '
requirements. Because of these normal operating requirements, it is not possible to specify a reference test flow path or flow rate that can be repeated for each test.
Alternate Testing: Pump testing will be performed with the system in the as-found operating configuration and the test results compared with a curve of reference values which establish the relationship between flow rate and differential pressure in a band around the design point. The " Required Action" and " Alert" ranges of Table IWP-3100-2 as specified in IWP-3210 will be applied.
04601 II-1-26 Rev. 2
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. l FNP-2-M-067 l 1
PUMP RELIEF REQUEST l PR-16 System: . Diesel Generators Fuel Oil Transfer i
Pump: P503B-B, ?505A-A * '
l Class: 3 i
Function: Transfer diesel generator fuel oil from ,
the storage tanks to the diesel generator day tanks. I Test Requirement: Measure pump test anlet pressure, differeutial pressure and flow rate in i accordknee with the requirements of l IWP-3100 and pump test du;ation i requirements of IWP-3500.
Basis for Relief: The diesel generator fuel oil transfer pumps are located inside the storage tank with the pump discharge plenum and motor bolted to a flange on top of the tank. None of the pumps have installed instrumentation to measure either flow or discharge pressure. The only possible flow measurement is by 1 measuring change in day tank level over )
time. The 4075 KW diesel generators '
have, by design, a maximum fuel J consumption of 5.6 ypm. Plant 1 procedures require that day tank level '
be maintained approximately 80 percent full. To comply with the Code requirement to run the pumps for five minutes prior to taking test -
measurements would require draining the ,
day tanks below a safe operating level.
Alternate Testing: Pump test flow rate will be obtained by measuring a thange in day tank level over time. A day tank level change of approximately 10 percent shall be timed and the flow rate determined from tank .
- curves. An Alert Range of +6% and a Required Action Range of +1D% shall be appliod as provided by IWP-3210 and clarified by Code Interpretation X1-1-79-19. Also, flow rate of 5.6 gal./m.1n. for the P503 B-B and P505 A-A pumps kill be applied as an absolute l minimum l
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04601 II 27 Gen, Rev. 2
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PUMP ~ RELIEF REQUEST PR-17
. i, System: Diesel Generators Fuel 011 Transfer Pump P503B-B, P505A-A i Class: 3 l Function: Transfer diesel generator fuel oil from the atorage tanks to the diesel generator day tanks.
Test Requirement: Measure pump vibration in accordance [
with IWP-3100.
Basis for Relief: The diesel generator fuel oil pumps are :
located inside the storage tanks with the pump discharge plenum and motor bolted to . flange on top of the tank. -
The pumps are it.:cessible for pump bearing viiratio.: measurements.
Alternate Testing: Motor vibration measurements will be <
performed quarterly in lieu of Code required pump vibration measurements.
0460I I I 28 Gen. Rev. 2
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i-I FNP-2-M-067 PUMP RELIEF REQUEST L
PR-18 Systems All Pump All Class: 2,3 Function: Various Test Requirement: IWP-4120 requires that the full scale range of each instrument be no more than three times the reference value.
Basis for Relief: FNP uses an IRD Model 818 for monitoring pump vibrations. The IRD Model 918 is a microprocessor controlled digital vibration monitor. When used in the English measurement mode the instrument autoscales in decade ranges. The requirement of IWP-4120 is not appropriate for vibrational measurement using this type of instrument. The accuracy of the instrument is 15% over all ranges. The IRD provides a digital display of vibration measurement to three (3) decimal places. This instrument provides significantly higher accuracy than an analog amplitude meter which is read visually and subject to human error and parallax. The use of a digital vibration meter has been reviewed by the ASME Code Committee and approved per Code Case N-472.
Alternate Testing: The autoscaling digital vibration monitor will be used for Code required pump vibration measurements.
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PUMP REllEF REQUEST PR-19 ,
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System: CVCS Boric Acid Transfer, Residual Heat Removal, Auxiliary Feedwater (TDAFW) j Pump: P005A A, P0058 B, P001A A, P0018-B, P002 ,
Class: 3,2,3 Test Requirement: IWP-3100 requires that each measured test quantity be compared to the reference value of the same quantit,. Any deviation determined '
shall be compared to the limits given in Table IWP 3100-2.
Basis for Relief: Section IWP 3100 requires quarterly pump -
testing to be performed by varying the system resistance until either the measured differential pressure or the measured flow rate equals the corresponding reference value, or by using a fixed resistance test flow path. The '
test flow paths used to test these pumps do not contain flow control provisions sufficiently accurate to repeat an exact reference ,
condition. l r
Alternative Testing: Pump testing will be performed at conditions as close to the reference conditions as can be reasonably achieved and the test data compared with a curve of reference values which ;
establish the relationship between flow rate l and differential pressure in a band around the '
reference point.
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E 000900 11-1-30 Rev. 2
- .. q FNP Uni t No. 2 F N P-2-M-067 Valve Test List ,
System: Auxiliary Steam 0 2911 2 Re t ie r Valve Act. Reg. Or Valve Class Dwg. No. Site Act. Position or- s Tes_ts_and Freq, C. S. Description Niembe r ist [ Coo rd . ) QLt ( in. ) Type Type Norm iast Safety Pass, PI Et Si DR f 5% . Li _Just. _and_Ilotes QV001A HV3235A 2 D-205033/2 BC 3 E-6 SC A0 S
C O O/C A Y Q Q
Q FF - - -
Main Steam B to Turbine Driven Q BS -
0-356350/2 Aux. Teed. Pump F-8 ShuteFr Valve.
Ai r Opera tor Maintains vaive Open.
QV0010 2 D-20'iO 3 3 /2 BC 3 SC A0 C 3 O/C A Y Q Q FF - - -
Main Steam C to HV32350 0-8 5 Q Q BS - - -
Turbine Driven D-356350/2 Pump ieed. Pump E-8 ShutoFr Valve.
Air Operator Maintains Valve Open. l QV010A 3 D-205033/2 C 4 CK S C N/A O A -
Q - FF - - -
Main Steam to E-6 R RM Q2N12 Aux. feed. Pump D-356350/2 Turbine.
r-6 RV-1 -
t4.P nB 3 D-20$033/2 C 4 CK S C N/A O A -
Q -
FF - - -
Main Steam to C-6 R m "*- d- """"
D-356350/2 Q2N12 ^ Turbine.
E-6 RV-1 HV3226 3 D-205033/2 B 3 CL AO C O C A V 'Q Q O Q - -
Main Sten ::
D-5 Turbine Driven D-356350/2 Aux. Feed. Pump D-5 Auto. Valve.
HV3234A 2 9 ~'05033/2 B 1 CL A0 0 C C A Y. Q Q C Q - -
Stcom Line B to G-8 Turbine Driven 0-356350/2 ,.ux. Feed. Pump G-8 Warmup Line Isolation.
HV32348 2 0-205033/2 8 1 GL ,)'
O C C A Y Q Q C Q - -
Mein Steem Line C-8 C to Turbine D-356350/2 Driven Aux.
C-8 Feed. Pump Worm-up Line.
04388 111-1-14-1 Rev. 2
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RELIEF REQUEST l Q2N12-RV-1 1 System: Auxiliary Steam i
Valve: QV010A, QV010B l Cttegory: C 4
Class: 3 Function: Main steam to auxiliary feedwater pump supply line check valves.
-ASME Section XI i
Quarterly Test Requirements: Verify reverse flow closure.
Basis for Relief: There are no system design provisions for verification '
of reverse flow closure.
Alternate Testing: One of the QV010A,B valves will be disassembled and ,
manually full stroke tested at each refueling on a l staggered test basts. The valve internals will be .,
verified as structurally sound (no loose or corroded j parts) and the disk manually exercised to verify full stroke capability. If the disassembled valve is not ;
capable of being full-stroke exercised or there is binding or failure of valve internals, the remaining i valve will also be disassembled, inspected, and manually =-
full-stroke exercised during the same outage.
i 000815 111-1-14 2 Rev. 2 l
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Valve Tess List .'
System: Instrument Air GPP19 .
l c 9 Valve Act.
Regler Reg. or
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valve Class Dwg. peo. Size Act. Position or Tests and Freg. C. S. Description ;
plumbe r I}.1 (Coord.1 Cat Iin.1-Type Type : foorm Faii SMety Pass, H H SI- DM iSV L.1 _Just. _end Ilotes e QV002 2 D-205034/4 AC 2 E-3 CK S 0 W/A C A - R -
BS -
U . 02P19 Ctet. Instrument RV-1 Air Supply. Pen. l~ k 9
D-356351/4 48.
- D-4 :l QV004 2 D-205034/4 AC 1/2 CK S C N/A C A - R -
BS -
U O2Pt9- Ctet. instrtsesmt l. O B-6 RV-1 Ai r Supp ly. Pen. .8 D-356351/4 979. c D-10 i QV006 2 D-20'J D34/4 A 3/4 CL AO C C C P - - - - -
U - Backup Air . .f HV2226 B-4 Supply to Press, t D-356351/4 PORVs. Pen. [.
D-9 975. MeIntaIned i Closed During i" Operation.
t HV3611 2 D-205034/2 A 2 CL AO O C C A- Y CS CS C CS U 02P19- Instrument Air D-11 D-356351/2 CS-1 Supply to Ctet. -
Pen. 48.
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