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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
_ _ _ _ _ _ _ _ _ _ - _ - _ _ _ -
e' a
- Alibama Power Company 600 North 18th Street Post Office Box 2641
' Birmingham, Alabama 352910400 Telephone 205 250-1835 L
nio ce Pr $4 dent Alabama Power the SOuttem dectic system Docket No. 50-348 10CFR50.55a(g)(6)(i)
March 17, 1988 U. S. Nuclear Regulatory Comission Attention: Document Control Desk Washington, D. C. 20555 Gentlemen: !
Joseph M. Farley Nuclear Plant - Unit 1 Second Ten Year Interval Inservice Testing Program for ASME Code Class 1, 2 and 3 Pumps and Valves Alabama Power Conpany pre' acusly submitted the subject Inservice Testing .-
(IST) Program to the NTc by letters dated September 30 and November 20, 1987. By letter dated December 10, 1987 the NRC granted interim relief for the relief requests subnitted with the program. However, the NRC stated that interim relief for 23 7alves in the high and low head safety injection systems was granted only until the next refueling outage scheduled to start in March 1988. In an effort to expedite additional interim relief, Alabama Power Company has now developed an alternative test methodology as prescribed by the NRC. This methodology incorporates the connents of the conference calls held with the NRC between March 3 and 8, 1988 for the valves in question.
In lieu of the system test previously utilized, valve disassembly on a sampling basis will be employed at the eighth refueling outage to verify valve forward flow operability. This alternative is described in the enclosure, which contains the revised valve tables and relief requests i necessary to accomodate this test method. This enclosure constitutes Revision 1 of the IST Program. j i
p50 apksk 6 9
8803240094 880317 PDR ADOCK 05000348 p DCD
U. S. Nuclear Regulatory Comission March 17, 1988 Page 2 Valve disassembly on a sampling basis will be performed on one valve from each of the following five groups of valves as described in the referenced relief requests:
WESTINGHOUSE SCHEDULAR OPERABILITY TPNS NUMBER NUMBER _RELIEl' RDQUEST RELIEF REQUEST ole 11V021A, B & C 8973A, B & C Q1E11-RV-7 Q1E11-RV-4 Q1E11V051A, B & C 8998A, B & C Q1E11-RV-3 Q1E11-RV-5 Q1E21V062A, B & C 8997A, B & C Q1E21-RV-4 Q1E21-RV-10 Q1E21V066A, B & C 8995A, B & C Q1E21-RV-6 Q1E21-RV-10 Q1E21V078A, B & C 8990A, B & C Q1E21-RV-6 Q1E21-RV-10 01E21V079A, B & C 8992A, B & C Q1E21-RV-6 Q1E21-RV-10 01E21V077A, B & C 8993A, B & C ole 21-RV-11 Q1E21-RV-14 For the record, the NRC also stated in the referenced discussions that a valve which is disassembled for the purpose of operability testing has not, as the Code specifies, "undergone maintenance that could affect its performance." Therefore, operability testing following reassembly to "demonstrate that the performance parameters, which could be affected by the ... maintenance are within acceptable limits," is not required by Section XI, IWV-3200.
It should be noted that the alternative test methodology described above addresses 21 of the 23 valves identified in the NRC letter of December 10, 1987. We remaining two valves, ole 21V076A & B (8988A & B) are passive and serve a safety related function only as primary pressure isolation valves.
h erefore, these valves are not required to open to perform their safety function and verification of individual forward flow capability is not required. On this basis the reliefs requested do not address these valves.
Finally, relief requests Q1E11-RV-2, Q1E11-RV-6, QlE21-RV-12 and Q1E21-RV-13 included in the enclosure contain editorial changes only.
Relief request Q1E21-RV-15 has been deleted since the necessary relief for valves 01E21V077A & B has been combined into a similar relief request (01E21-RV-14) for valve ole 21V077C.
U. S. Nuclear Regulatory Comibsion March 17, 1988 Page 3 It is respectfully requested that the reliefs described herein be granted by March 25, 1988 on an interim basis until the Unit i ninth refueling outage or until final approval of the reliefs are granted, whichever is earlier. Granting of these interim reliefs will ensure that an approved IST Program is available for utilization during the upcoming outage. A subsequent submittal will be made by Alabama Power Company by March 31, 1988 requesting final approval of these reliefs.
Pursuant to 10CrR170.21, the required application fee of $150.00 is enclosed. If there are any questions please advise.
Respectfully submitted, f
AIMM PNER gmMW ,
I f D' l
l g.-
i R. P. Mcdonald l RPM / SIB:csl-V4 Enclosure cc: Mr. L. B. Long Dr. J. N. Grace Mr. E. A. Reeves Mr. W. H. Bradford l
l l
l i
!!NCI46URE IST PROGRAM REVISION 1
SUMMARY
OF CHANGES RE OVE PAGE INSERT PAGE DESCRIPTION OF CHANGE III-1-2-1 III-1-2-1 Revised relief request references for valves QV021A, B & C.
III-1-2-2 III-1-2-2 Revised relief request references for valves QV021A, B & C.
III-1-2-8 III-1-2-8 Deleted reference to valves QV021A, B
& C and their Code class. .
III-1-2-9 III-1-2-9 Revised the "Basis for Relief" and i
"Alternate Testing" statements.
III-1-2-10 III-1-2-10 Revised the "Basis for Relief" and i "Alternate Testing" statements.
III-1-2-11 III-1-2-11 Revised the "Basis for Relief" and "Alternate Testing" statements.
I III-1-2-12 III-1-2-12 Editorial change to renumber existing relief request Q1E11-RV-6. ,
l l
III-1-2-13 III-1-2-13 New relief request added for valves j QV021A, B & C.
l III-1-2-14 -
Deleted page, i
III-1-7-4 III-1-7-4 Revised relief request reference for valves QV077A & B.
III-1-7-19 III-1-7-19 Revised the "Basis for Relief" and j "Alternate Testing" statements.
l III-1-7-21 III-1-7-21 Revised the "Basis for Relief" and "Alternate Testing" statements.
III-1-7-25 III-1-7-25 Revised the "Basis for Relief" and ;
"Alternate Testing" statements.
!!NCIOSURE IST PROGRAM REVISION 1
SUMMARY
OF CHANGES REMOVE PAGE INSERT PAGE DESCRIPTION OF CHANGE III-1-7-26 III-1-7-26 Revised the "Basis for Relief" and "Alternate Testing" statements.
III-1-7-27 III-1-7-27 Editorial change to renumber existing relief request Q1E21-RV-12.
III-1-7-28 III-1-7-28 Editorial change to renumber existing relief request QlE21-RV-13.
III-1-7-29 III-1-7-29 Revised the "Basis for Relief" and "Alternate Testing" statements.
III-1-7-30 -
Deleted page.
III-1-7-31 -
Deleted page.
III-1-7-32 -
Deleted page. Relief request for valves ov077A & B was combined with relief request valves OV077C (Q1E21-RV-14).
STB:csl-V4 4
P
,,_...-_-,_,.,w-._--- -
%.,-,,.y __- - , - . - - _ y _
, . . _ . _ _ . . - -. - _ - .._. - - _ - -_ . . - - -. - - __. .-. . _. - . .- . . - . -- _ _ _ _ . .x . . _ , -
IMP Unit No. 1
System: LhSI/ Retr Q1[1]
Re l l el' Valve Act. Req. or Valve Glay Dwg No. Size Act. Position or Te.glit_and f req. C. S. Desc ript ion Number 1}l I Coo rd . I pa_L fin.I lyps Typs peo rg iaii $arety Pass. f.L LI }l Im Lgy LI _Just. and Isotes QV001A 1 D-175041 A 12 CA M0 C Al O/C A Y CS CS C - LC Q1[11- RC Loop IC to 1-8701A C-3 CS-1 RHR Pump 1A.
D-351118 C-3 QV0018 1 D-175041 A 12 CA M0 C At 0/C A Y CS CS C -
LC Q1E11- RC Loop 1A to 1-8702A E-3 CS-1 CHR Pump 18.
D-351118 E-3 QVOO9A 2 D-175041 8 8 CA M0 C Al O A Y Q Q O - - -
RHR HX 1A to 1-8706A B-8 Cha rging D-351118 Pump Suction.
B-8 QV009B 2 D-175041 B 8 CA MO C Al O A Y Q Q O - - -
RHR HX 18 to 1-87068 C-8 Cha rging Pump D-351118 Suction.
D-8 QV015A 2 D-175041 C 3x4 SR S C N/A O/C A -
T - - - - -
RHR Pump 1-8708A C-4 Suction.
D-351118 G-4 QV015B 2 0-175041 C 3x4 SR S C N/A O/C A -
T - - - - -
Ri:R Pump 1-8708B [-4 Suction.
D-351118 E-4 QV016A 1 D-175041 A 12 CA M0 C Al O A Y CS CS O -
LA Q1E11- RC Loop IC to 1-87010 C-2 CS-1 RHR Pump 1A.
D-351118 C-2 QV016H 1 D-175041 A 1? CA MO C Al O A Y CS CS O -
LA Q1E11- RC Loop 1A to 1-8702B E-2 CS-1 RHR Pump *B.
D-351118 E-2 QV021A 1 D-175038/2 AC 6 CK S C N/A O A -
R -
ff -
LA Q1E11- RHR Pump Disc.
1-8973A E-1 RV-4 to SIS Injection D-351115/2 Q1E11- CL.
E-1 RV-7 QV0218 1 D-175038/2 AC 6 CK S C N/A 0 A -
R -
FF -
LA Q1E11- RHR Pump Disc.
1-89738 T-1 RV-4 to SIS Injection D-351115/2 QlE11- CL.
f-1 RV-7 03611 Ill-1-2-1 REV. 1 l
- . _ . , . . - , . . . _ _ , _ , , , _ _ _ . . - _ . _ ~ ~ , , . . . - . _ . _ . . . . - - _, m _ , _ _ _ . . - _ - - . - _ . . . , .
(NP Unit No. 1 Valve test List FNP-1-M-042
- System: LHSI/RHR Q1E11 He 1 ic f' Yalve Act. Req. or Valve Class Dwg. No. Size Act. Position or Teils and R eg, C. S. Description Number 111 [fo(Md fai fin.) Lype type No m faei Safety Pass, P1 M 11 pl3 [ky L[ JL and Notes QVO21C 1 D-175038/2 AC 6 CK S C N/A O A -
R -
IF -
LA Q1011- RHR Pump Disc.
1-8973C G-1 RV-4 to SIS Injection D-35111$/2 01011- CL.
G-1 RV-7 QVO23A 2 D-175038/2 0 10 CA MO O Al O/C A Y Q Q C 1-8888B G-3 RHR HX A to RCS CL isolation.
D-3*>1115/2 C-3 QVO238 2 D-175038/2 0 10 CA MO O Al O/C A Y Q Q C 1-8888A i-3 RHR HX B to RCS CL isolation.
D-351115/2 F-3 QVO24A 2 D-115038/2 B 10 GA MO O Al O/C A Y C 1-8681A l-4 Q Q - - -
RHR to RCS ItL Cross Connect.
D-351115/2 I-4 QVO248 2 D-115038/2 0 10 GA MO O Al O/C A Y Q Q C -
1-8881H G-4 RHR to RCS ItL Cross Connect.
D-351115/2 G-4 QVO?5A 2 D-175038/2 A 14 GA MO C Al O/C A -
Q Q O -
LJ Q1E11- Ctat. Sump to 1-8811A J-4 RV-1 RHR Pump 1A.
D-351115/2 J-4 OVH?SH 2 D-175038/? A 14 GA MO C Al O/C A Q 1-88118 Q O -
LJ Q1[11- Ctat. Sump to h-4 RV-1 RHR Pump 18.
D-351115/2 18 - 4 QVO26A 2 D-175038/2 A 14 CA MO C Al O A Y 1-8812A Q Q O -
LJ - Ctat. Sump to J-5 RHR Pump 1A.
D-351115/2 J-5 QVO26B 2 D-175038/2 A 14 GA MO C Al O A Y 1-8812B Q Q O -
LJ - Ctat. Sump to 14 - 5 RHR Pump 18.
D-351815/2 H-5 QVO27A 2 D-175038/2 B 14 GA MO O Al C A Y Q Q C 1-8809A F-10 RWSi to RHR Pump 1A.
D-351115/2 F-10 03618 Ill-1-2-2 REV. 1
. . -l FNP-1-M-042 RELIEF REQUEST Q1E11-RV-2 System: LHSI/RHR Valve: QV042A,QV0428 l
Category: AC Class:
2 Function: LHSI/RHR to RCS cold leg injection line check valves.
ASME Section XI Quarterly Test Requirements: Verify forward-flow operability ,;
quarterly or at cold shutdown (IWV-3521). ,.
I-Basis for Relief: Verification of forward-flow operability.
of these normally closed check valves can only be performed by injecting RER water into the RCS. During normal operation the low-pre.e.ure LHSI/RHR pumps cannot overcome the higher RCS operating pressure. Verification of full design flow rate operability cannot be done at cold shutdown due to back pressure from the reactor coolant system. Verification of full-flow operability can only be done at refueling with the RCS depressurized, the reactor vessel head removed, upper internals in place, and the refueling cavity at refueling level.
Alternate Testing: Valves will be forward-flow verified when the SI/LOSP test is being performed.
0361I III-1-2-8 REV. 1
FNP-1 -M-042 RELIEF REQUEST Q1E11-RV-3 System: LHSI/RHR Valve: QV051 A, QV05103 QV051C Category: C Class: 1 Function: HHSI/LHSI to RCS cold leg injection line check valves ASME Section XI Quarterly Test Requirements: Verify forward flow operability quarterly or at cold shutdown (IWV-3521)
Basis for Relief: Disassembly of these valves can only be done with the RCS depressurized and the reactor vessel level at mid-plane.
Alternate Testing: Valves will be disassembled on a staggered basis at refueling. l E
i
(
i l III-1-2-9 REY. 1 y - -- n,- - - - - - --, r----,.,y-y . , , - -., -----~~,-,.-.-,,---,-we ,--,e-.,,,-.-
.. ; )
RELIEF REQUEST i Q1 Ell-RV-4 :
System: LHSI/RHR Valve: QV021 A, QV0218, QV021C Category: AC Class: 1 ASME Section XI Quarterly Test Requirements: Verify forward flow operability (IWV-3522)
Basis for Relief: These 6-inch Yelan swing check valves are located in the low-head safety injection flow paths to the reactor coolant system cold legs. Individual line flow rate cannot be used to verify individual valve operability due to lack of instrumentation.
Alternate Testing: One of these valves will be disassembled and manually full stroke tested at each refueling on a staggered test basis. If stroke testing reveals that the valve is inoperable, the remaining valves will be disassembled.
III-1 10 REY. 1
FNP-1-M-042 RELIEF REQUEST Q1E11-RV-5 System: LHSI/RHR Valve: QV051 A, QV0518, QV051C Category: C 4
Class: 1 ASME Section XI Quarterly Test Requirements Verify forward flow operability (IWV-3522)
Basis for Relief: These 6-inch Velan swing check valves are located in the shared low-head and high-head safety injection '
Ifnes to the reactor coolant system cold legs.
Individual line flow rate cannot be used to verify individual valve operability due to lack of instrumentation.
Alternate Testing: One of these valves will be disassembled and manually full stroke tested at refueling on a staggered test basis. If stroke test reveals that ,
the valve is inoperable, the remaining valves will be disassembled.
4 111-1-2-11 REV. 1
FNP-1-M-042
. 1 i
RELIEF REQUEST .
Q1E11-RV-6 System: LHSI/RHR Valve: QVO32A, QVO32B, QV033A, QV033B Category: B Class: 2 Function: RHR HX. tube side discharge to SIS (QV032A,B) and RHR HX. bypass (QV033A,B).
ASME Section XI Quarterly Test Requirements: Measure valve stroke time.
Basis for Relief: Valves QV032A,B are the RHR heat exchanger outlet valves and QV033A,B are i
the RHR heat exchanger bypass valves.
Valves QV032A,B are normally open, fail open end valves QV033A,B are normclly closed, fail closed valves. This is the required valve alignment for the LHSI mode of operation. The RHR function of these valves is to control cooldown rate by regulating flow through the RHR heat exchangers. Both the flow control and bypass valves modulate to control the amount of heat removal by the RHR heat exchangers. Valves QVO32A,B modulate in response to a manually controlled position signal and valves QV033A,B automatically modulate to adjust bypass flow in response to the set position of valves QV032A,B. The only way to full stroke the valves is by manually adjusting the flow-control valve position control station through the full range of adjustment.
Alternate Testing: The valves will be tested quarterly by stroking each valve through its full range of travel.
0361I I I I- 1 12 REV. O
FNP-1-M-042 REl.tEF NEQUEST i Q1D1-RV-7 ,
System: LHSI/RHR Valve: QV021 A, QV021B, QV021C Category: AC Class: 1 Function: LHSI/RHR to RCS cold leg injection line check valves ASME Section XI Quarterly Test Requirements: Verify forward flow operability quarterly or at cold shutdown (IWY-3521)
Basis for Relief: Disassembly of these valves can only be done with the RCS depressurized and the reactor vessel level at mid-plane.
Alternate Testing: Valves will be disassembled on a staggered basis at refueling.
I I I-1 13 REY. 1
,1 FNP Unit No. 1 FNP-1-M-042 Valve Test List **
System: Sl/CVCS Q1E21 -
Retier Valve Act. Req. or ,
Valvo CJ_asa Dwg. No. Size Act. Position or Tests and Freg. C. S. Desc ri ption i Number J $.1 (Cold .1 QLL ( in. I hen hpe Norm faii Safety Pa s s . ,P_ l, M SJT. p.R_ isy .M Just. and Notes QVO72 2 0-175038/1 B 3 GA MO C AI O A Y CS CS O - -
Q1E21- HHSI Pump Reci r- !
1-8884 J-6 RV-5 culation to RCS D-351115/1 Hot Legs.
J-6 .
QVO76A 1 D-175038/1 AC 6 C F. S C N/A C P - - - - -
LA -
Wa te r f rom Loop 1-8988A f-4 1 RHR HX to RCS D-351115/1 Hot Leg. See F-4 relier request Q1E21-RV-15.
QV0768 1 D-175038/1 AC 6 CK S C N/A C P - - - - -
LA -
Wa te r f rom Loop 1-89888 C-4 2 RHR HX to RCS D-351115/1 Hot Leg. See G-4 relier request Q1E21-RV-15.
QV077A 1 D-175038/1 AC 6 CK S C N/A 0 A -
R -
FF -
LA Q1E21- LHSI/RHR/HHSI to 1-8993A F-2 RV-11 RCS Hot Leg Loop D-351115/1 Q1E21- 1.
F-2 RV-14 QV077B 1 0-175038/1 AC 6 CL S C N/A 0 A -
R -
FF -
LA Q1021- LilSI/RHR/HHSI to 1-89938 G-2 RV-11 RCS Hot Leg Loop D-351115/1 Q1E21- 2.
G-2 RV-14 l QV077C 1 0-175038/1 AC 6 CL S C N/A 0 A -
R -
ff -
LA Q1E21- HHSI to RCS Hot 1-8993C G-1 RV-11 Leg Loop 3.
D-351115/1 Q1E21-G-1 RV-14 QVO78A 1 0-175038/1 C 2 CK S C N/A 0 A -
R -
FF - -
Q1E21- HHSI Pump Dis-1-8990A C-3 RV-6 charge to RCS D-351115/1 Q1E21- Hot Leg.
G-h RV-10 QV0788 1 0-175038/1 C 2 CK S C N/A O A -
R -
FF - -
Q1E21- HHSI Pump Dis-1-89908 C-3 RV-6 charge to RCS D-351115/1 Q1E21- Hot Leg.
c-3 RV-iO QV078C 1 0-175038/1 C 2 CK S C N/A O A -
R -
FF - -
Q1021- HHSI Pump Dis-1-8990C G-3 RV-6 charge to RCS D-351115/1 Q1E21- Hot Leg.
G-3 RV-10 03661 111-1-7-4 REV. 1
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FNP-1-M-042 RELIEF REQUEST QlE21-RV-4 System: SI/CVCS Valve: QV062A,QV0628,QV062C Category: C Class: 1 Function: Boron injection tank to RCS cold leg line check valves ASME Section XI Quarterly Test Requirements : Verify forward flow operability quarterly or at cold shutdown (IWY-3521)
Basis for Relief: The only possible way to verify full-flow operability of these check valves is by using the CVCS charging pump flow through the boron injection tank into the RCS cold legs. However, injecting water into the RCS through the boron injection tank during power operation exposes the safety injection nozzles to thennal shock and interrupts nomal charging and letdown. Injection of CYCS charging pump flow at cold shutdown would result in a low l temperature overpressurization of the RCS.
l Verification of full design flow rate operability l cannot he done at cold shutdown due to back pressure Verification of full flow operability from the RCS.
l can only be done at refueling with the RCS
- depressurized, the reactor vessel head removed, upper internals in place, and the refueling cavity at refueling level.
Disassembly of these valves can only be done with the RCS depressurized and the reactor vessel level at mid-plane.
Alternate Testing: Forward flow operability will be verified by full flow test or by disassembly on a staggered basis at l refueling.
I i
111-1-7-19 REY. 1
FNP-1-M-042 l
RELIEF REQUEST l
l Q1E21-RV-6 l
l System: SI/CVCS Valve: QV066A, QV0668, QV066C, QV078A, QV0788, QV078C, QV079A, QV07%, QV079C Category: C Class: 1 Function: Safety injection to the RCS check valves ASME Section XI Quarterly Test .
Requirements: Verify forward flow operability quarterly or at cold shutdown (IWY-3521)
Basis for Relief: Verification of forward flow operability can only be perfomed by injecting charging water into the RCS.
The charging pumps have insufficient head to overcome nomal RCS~ operating pressure for a full flow test. Partial testing using the charging pumps would inject CVCS water which has bypassed the regenerative heat exchanger and would result in themal shock to the RCS piping. Verification of full design flow rate operability cannot be done at cold shutdown due to back pressure from the RCS.
j Verification of full flow operability can only be done at refueling with the RCS depressurized, the reactor vessei head removed, upper internals in place, and the refueling cavity at refueling level.
l Disassembly of these valves can only be done with the RCS depressurized and the reactor vessel level at mid-plane.
Alternate Testing: Forward flow operability will be verified by full flow test or by disassembly on a staggered basis at refueling.
111-1-7-21 REY. 1 l
l l
t
FNP-1-M-042 RELIEF REQUEST QlE21-RV-10 System: SI/CVCS Valve: QV062A, QV0628, QV062C, QV066A, QV0668, QV066C, QV078A, QV0788, QV078C, QV079A, QV0798, QV079C Category: C Class: 1 Function: Safety injection to the RCS check valve ASME Section XI Quarterly Test Requirements: Verify forward flow operability (IWV-3522) t Basis for Relief: These 2-inch Kerotest check valves are located in the parallel high head injection flow paths to the reactor coolant system. Individual line flow rate cannot be used to verify individual valve operability due to lack of instrumentation.
Alternate Testing: One of the valves for the reactor coolant system cold legs (QV078 and QV079) and one for the hot legs (QV062 and QV066) will be disassembled and visually inspected on a staggered test basis at each refueling. If visual inspection reveals that the valve is inoperable, the remaining valves in that group (hot leg or cold leg) will be disassembled and visually inspected.
111-1-7-25 REV. 1
FNP-1-M-042 RELIEF REQUEST Q1E21-RV-11 System: SI/CYCS Valve: QV077A, QV0778, QV077C Category: AC Class: 1 Function: HHSI to RCS hot leg injection line check valves ASME Section XI Quarterly Test Requirements: Verify forward flow operability quarterly or at cold shutdown (IWY-3521)
Basis for Relief: Disassembly of these valves can only be done with the RCS depressurized and the reactor vessel at mid-plane.
Alternate Testing: Valves will be disassembled on a staggered basis at refueling.
l L
t l
l 111-1-7-26 REY. 1 l
I l
ENP-1-I4-042 RELIEF REQUEST ,
1 QlE21-RV-12 System: SI/CVCS Valve: QV115A, QV115B, QV115C Category: AC Class: 2 Functions. CVCS seal injection to RCS pumps.
A'SME Section XI Quarterly Test Requirements: Verify forward flow operability.
Basis for Relief: These valves must remain open to allow operation of the reactor coolant pumps.
and these pumps are required to be operable by Technical Specifications prior to entry into mode 3. Technical Specification 3.4.7.2.e requires a total
- flow of no more than 31 gpm through all three valves. Administrative controls require a flow of at least 6.7 gpm through each valve.
Alternate Testing: The total flow of less than 31 gpm will be monitored every 31 days per Technical Specifications. If flow drops below 6.7 gpm a plant main control board alarm l
. is actuated and flow is reestablished via annunciator response procedures.
i 1
1 III-1-7-27 REV. 0 0366I
n . -
FNP-1-M-042
, RELIEF REQUEST QlE21-RV-13 i
System: SI/CVCS Valve: QV121A, QV121B, QV121C Category: C
. Class: 2 Function: Charging pump min, flow line check valves.
ASME Section XI Quarterly Test Requirements: Verify forward flow operability.
Basis for Relief: In verifying full forward flow operability would require measuring the flow rate through each of the charging pump minimum flow lines. Neither the individual minimum flow lines nor the common header is instrumented to measure flow rate.
Alternate Testing: '
One of these valves will be disassembled and inspected at refueling on a staggered basis. If disassembly reveals that the valve is inoperable, the remaining valves will be disassembled.
1 0366I I I I 7 - 28 REV. O
.. *l FNP-1-H-042 RELIEF REQUEST QlE21-RY-14 System: SI/CVCS Valve: QV077A, QV0778, QV077C Category: AC Class: 1 Function: HHSI to RCS hot leg injection line check valves ASME Section XI Quarterly Test Requirements: Verify forward flow operability (IWY-3522)
Basis for Relief: These 6-inch Yelan swing check valves are located in the safety injection lines to the reactor coolant system hot legs. Individual line flow rate cannot be used to verify valve operability due to lack of instrumentation.
Alternate Testing: One of these valves will be disassembled and manually full stroke tested at each refueling on a staggered test basis. If stroke testing reveals that the valve is inoperable, the remaining valves will be disassembled. .
111-1-7-29 REY. 1 1
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