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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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-e; -.*A1:bima Power Company
- 40 invIrness C:nt;r Parkway
' Post Ofhce Box 1295 -
Birmingham, Alabama 35201-Telephone 205 808 55D1
<t W. G. Hairston, til Senior Vice President-wcion, ope .ons- NabamaPower August 20. 1990 * *#*" *"C 85*" -
.b' Docket No. 50-348 U. S.-Nuclear. Regulatory Commission i
'Attentloil - ' Document Control Desk l Vashington, D. C. 20555 4 centlement Joseph M. Farley Nuclear Plant - Unit 1 q
' Second Ten-Year Interval Inservice Testing (IST) Program )
for ASME Code Class 1, 2 and 3 Pumps and Valves Alabama Power Company previously submitted Revision 0 of the subject Unit 1 IST q Program.to the NRC by letters dated September 30 and November 20, 1987. o Revision 1 and Revision 2 were submitted by letters dated March 17, 1988 and d September 9, 1988, respectively. Revision 3 was submitted by letter dated 1 October 4,1989.: The NRC granted interim approval for the relief requests submit _ted with Revisions 0 and 1 of the IST Program by lettets dated i December 18, 1987 and March 30, 1988, respectively. To date, Alabama Power '
Company has not received approval for the relief requests submitted with Revisions 2 and 3 of the IST Program.
Enclosed for review and granting.of relief is Revision 4 of the-Unit 1 IST Program. This submittal incorporates-commitments addressed _in Alabama .i Power Company's letter dated December 22, 1989 entitled,'" Reply to a Notice of Violation J. H. 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:
l '. Added provisions for measuring stroke time for Auxiliary Steam admission H valves 01N12V001A and B. l
- 2. Added relief request 01N12-RV-1 to perform disassembly and manual stroke test exercising of 01N12V010A and B on an alternating basis at each refueling outage.
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.1 9008280048 900820 t i PDR ADOCK 05000348 L I P PDC (
4 U. S. Nuclear Regulatory Commission .Page 2 3 AdditionallyLRevision4added,-deletedormodifiednumerouspumprelief' 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-6 4 vas-modified to require the performance of a.flov test and.the measurement-of differential pressure exclusively during cold shutdown. 4 2.- Deleted relief request PR-7 which requested relief from the Code instrument range requirements of IVP-4120 to utilize the installed flov' ,
instrumentation. Deletion was based on a procedural change which increased the test flow rate.. The new test range is within the 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 Vater Pumps P001A-A,-
P001B-A, P0010-AB,' P001D-B and P001E-B to specify the use of a curve of r
reference values to establish the relationship between flow rate.and.
differential pressure.
l
- 5. Deleted pump relief request PR-11 also for the Service Water pumps.which-requests relief from the pump test range. limits specified in Table :
I'1P-3100-2, "Allovable Ranges of Test Quantities. PR-11 is not necessary since expansion of"the allovable ranges of inservice test quantities described by Table IVP-3100-2 is ac.ceptable in accordance with Paragraph i IVP-3210 of the ASME Code,Section XI.
u l 6. Modified relief request PR-15 for Component ooling Vater Pumps P001A-B, P001B-AB and P001C-A which requests relief ^ om the Paragraph IVP-3110
" Reference Values," requirement that both orfferential pressure and flov l rate measurements be'readily duplicated during subsequent inservice tests. [
Subsequent to the NRC's interim approval, this relief.vas modified by Revision 3 to coincide with revisions made to the Unit 2 relief request i which resulted from the NFC's March 31, 1989 letter. Pump performance shall be compared to the l wits of Table IVP-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, Turbine Driven Auxiliary Feedvater and Containment Spray Pumps.
Finally, this revision deleted valve OSV47V003C from the Non-Radioative Vent Valve Test List. An engineering evaluation determined that this valve is not relied on for isolation following any design basis accident condition. Its only isolation function is to isolate the non-safety related computer room in 1'
the event of a computer room fire.
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a,e sU. S.' Nuclear-Regulatory Commission. .Page 3 i
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.ItnisJrespectfully requested that the relief-requests included in Revision 4 of
l the Unit 1 LIST Program be granted by January 31, 1991.- This revision is d i submitted prior to: September.1, 1990 in e.ccordance with:the December 22, 1989-Notice'of Violation Response. Upon grantinglof these relief request's, Alabama-Power Company vill implement Revision 4 of the IST Program.
~
If there~are any questions or-if additional-information is needed,Jplease .
advise..
Respectfully ~ submitted,' 'b ALABAMA POVER COMPANf ulk /L;_ - ,
V. G. Hairston, III
^l VGH,III/DEM/TRHicht-nrc.8.19 -t Enclosure.
cci Mr. S.-D. Ebneter v/1 Mr. S.'T. Hoffman v/1 Mr. G. F. Maxwell v/0 L
FNP-1-M-042 i Summary of Revision 4 to the J. M. Farley Nuclear Plant - Unit 1 ,
2nd Ten Year Inservice Testing Program L
For ASME Class 1, 2, and 3 Pumps and Valves -1 l l l
Page No./ Description / Reason for Change.
. 1
- 1. Pages 11-1-1, 2, 4, and 5: Added reference to new Relief Request PR-19 to provide for pump testing under variable reference conditions, q
- 2. Page II-1-3: Revised headings on top of page to ' reflect " Unit No.1" and I manual number "FNP-1-M-042". Also revised to reflect required lubrication l --
level (LL) check to be performed at refueling in addition to quarterly.
Editorial corrections. ,
L 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. ,
l
- 4. Page 11-1-6: Deleted reference to Relief Request PR-11,
- 5. Page T' 1-12:- Revised- first sentence of " Alternate Testing:" to correct i spell' % 'f word " measurements". Editorial.
L 6. Page 11-2 16: Revised to include relief from performing pump ,1brational measurement at cold shutdown and to clarify alternate testing performed.
- 7. Page 11-1-17: Deleted pump relief request PR-7. This relief request is no. y longer required.
- 8. Page 11-1-20: Changed pump suction pressures from 35 and 40 psig to 23.8' and 50 psig, respectively. Editorial revision.
- 9. .Page.11-1-21: Revised to include provision for evaluating test results over a range of reference values for two-pump test combinations.
- 10. Pages 11-1-22 & 23: Deleted pump relief request PR-11 and renumbered following pages as required. This relief request is not required.
- 11. Page 11-1-26: Revised last sentences of " Test Requirement:" and " Alternate Testing": to clarify ranges of Table IWP-3100-2. j
- 12. Page 11-1-29: Revised last sentence ref. " Basis for Relief:" to reflect '
ASME approval of Code Case N-472.
000814 1 of 2
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(" 13.- Page 11-1-30:' Added new Relief Request PR-19 to provide for. pump testing under variable reference conditions forithe BAT, RHR,'TDAFW and. CS pumps.
-14. Page 111-1-14-1: ~ Valve test requirements for' valves QV001A,B were revised to perform a stroke te:.t (ST) quarterly' and1 valve . test requirements for valves QVn10A,B were recised to incorporate valve disassembly at' refueling; .
and manual :troke test exercising via a new relief request. Per APCo letter-
-to NRC dated 12/22/89 tinled, " Reply to a Notice of Violation J. M. Farley-
- Nuclear Plant- NRC -Impection of October 2-6 and 16-20,1980." Al s o ,'
corrected position in -Doscription and Notes" from closed b ,, pen.
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.15. Page 111-1-14-2: Added new relief request to provide for valve disassembly 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".
- 16. Page 111-1-24-1: Revised designation of. actuator type for valves QV002 and
- 4. Editorial correction-
- 17. Page III-l-27-1: Deleted valve QV003C due to lack of safety related function in system. Reference Bechtel letter to.APCo dated 5/10/90 titled,
" Evaluation of Safety Significance of Computer Room.lsolation Valve ,
(ES-90-1722)". i 4
000814 2 of 2 )
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System: Contelnment Sprey gggg3 ,- .i Pump Measured Parameters and Freetsency
.o. gesla~ Dws / Sheet Coords- Pump Pi Po. dP Q v -. _t a Regler-manDer ni number . notes . Descre at ions g es a gt r es s e n les s i t ooel t es 11 1*L1 t aal f reel stee Betta P001A-A 2 0-175038/3 8-8 Containment Spray Q/R Q/R O/R R Q/R -
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System: '8igh Head Safety injection / Chemical Volume and Control System (HHSt/CVCS)
Measured Parameters and Frequency _;
Pump Po dP . Q V -T Lt_ - N Relief' Coordi- Pump Pi ~
I.D. plass Dwg./ Sheet Mumber _ nates _ Desc rip t ions (psig) losig) ( psi ) [gpal f oi 11 L'F1 LMA} ( rpa) ~ Rect- g(eg - =
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- 9/CS N/A PR-1 1,3~ : E-D-351116/3 C-6 T r* 2 re r. . Pet-6 ll PR-18 PR-19. 8
. P00h8-8 3 D-175039/3 H-6 Boric Acid Q/CS Q/CS 4/05 ' CS Q. -
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P001C-A8 3 0-170119/1 H-7 Service Weter Q Q Q Q- 0 N/A Q N/A' - Pft-10 1,3,4,5 D-351130/1 H-7 (SW). l Pet-12 PR-13 PRD~$"
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03s79 81-1-6 REV-' 4 H
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,,4 FNP-1-M-042 PUMP RELIEF REQUEST PR-3 h -
System:- Containment. Spray; 4
Pump: P001A-A, P001B-B-F Class: 2 7
Function:
- To reduce containment pressure-and airborne fission product removal from the post-LOCA containment atmosphere.
Test Requirement:' IWP-3100 requires that each measured
' test quantity be-compared'to the ,
reference value of the same_ quantity. :
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 the measured differential pressure or the measured:
flow rate equals the corresponding-reference value, or by using a fixed l' resistance _ test flow path. Testing the containment spray pumps by varying the .
system resistance is not a' practical !
method, because-to-do so would inject a large quantity of. water into the ')
containment atmosphere. Use of the- i fixed resistance two inch recirculation line back to the refueling water _ storage tank restricts the test' flow rate of -
these 3000 gpm pumps.to cpproximately 150 gpm. Consequently, flow-rate measurements using the recirculation flow path would not provide any useful ;
information to monitor pump operability ;
or degradation.
Alternate Testing: In addition to quarterly pump test measurements of differential pressure and vibration, pump flow rate, l ,
differential pressure, and vibration
' measurements will be performed at refueling when spool pieces are installed and pump full-flow can be directed to the refueling cavity.
0387I II-1-12 REV. 4
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tNP-1-M-042 PUMP RELIEF REQUEST PR 6 t
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System: -CVCS Boric Acid Transfer Pump: P005A A, P005B-B s J
' 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. i 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- i 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 concentrated boric acid to the RCS during normal operations would a@ersely affect the boric acid . :
concentration in the RCS'and could cause a forced plant shutdown. Because of the pump design and significant j 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 t coolant system and is insufficient to perform vibration measurements.
Alternate Testing: Of the test quantities listed in Table IWP-3100-1, pump ;
flow rate and differential pressure will be measured i during boric acid transfer pump operation for borating
! the RCS for entering cold shutdown.
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1 L 000814 11-1-16 Rev. 4 l
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' PUMP RELIEF REQUEST: i l
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' PUMP RELIEF REQUEST i 3
PR-9 l
system: Auxiliary Feedwater Pumps. POO1A-A, POO1B-B, P002 ,
Class: 2 -
'f Function Provide auxiliary fee'dwater to the steam i generators on loss:of main feedwater. >
, Provide-feedwater to the steam "
. generators during startup and shutdown.-
' Test Requirements: IWP-4120' requires that the full-scale range of-each instrument be no more than ;
three times ?he reference value.
4 Basis for Relief: Reference va?.ues for suction pressures for these = pumps 1 are between 23.8 and 50 - .
EL q psig. This would require suction !
4 pressure gauges of 0-75 psig maximum. l. l The accuracy required for these gauges would be 2 percent of 75 psig, which is l<
1 1.5 psig. The. installed pump inlet- u. '
pressure gauges are 0-100 12 psig. ,
Although'the installed instrumants 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 j for taking inlet pressure measurements- 1 during pump testing.
r 0387I II-1-20 REV. 4
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PUMP RELIEF REQUEST: 1
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-system: Service Water Pump P001A-A, P001B-A, P001C-AB,~ P001D-B,:
POOlE-B
' Class:'
3 Function: Provide cooling water to safety-related equipment.
r Test Requirement: IWP-3400(a) requires that an inservice; test be run-on.each pump. J Basis for Relief: Due to the demands of dependent' systems,;
the.' individual testing of service water pumps, as required by IWP-3400,,would?
jeopardize safe plant operation and be. ,
impossible to-accomplish during plant shutdown.
Alternate. Testing: Tests involving combinations of two pumps within each train will indicate the hydraulic condition of the pumping .,
system. The combinations are arranged !
such that each pump is included in at ,
least 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 between flow rate and differential pressure in-a band around the design point.
0387I 11-1-21 REV . 4
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-PUMPf,. RELIEF REQUEST
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0387I II-1-22 REV. 4
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~ PUMP RELIEF REQUEST PR-12 q
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. System Service Water Pump: P001A-A, P001B-A, P001C-AB,'P001D-B, POOlE-B
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Class: 3 Function: Provide cooling water to safety-related' equipment.
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.
Basis for' Relief: These pumps are submerged in a. pit.which makes.them inaccessible for measuring'. i vibration amplitude at the pump bearings.- l Alternate Testing: Vibration amplitude'is to be measured on the top of the motor housing (which contains the motor thrust bearing) horizontally in' .
two planes 90 degrees apart. .t t
0387I II 23 Gen. REV. 4
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.- - FNP-1-M-042 PUMP RELIEF REQUEST PR-14 Systems. Service Water Pump: P001A-A,LP0018-A, P001C-AB, P001D-B,.
- P001E-B I Class: 3-Function: Provide cooling water to safety-related ;
equipment .
3 Test Requirement: Table IWP-4120 requires that the full-scale range of each-instrument be
.no more than three times the reference. :l value.
Basis for. Relief: Reference-values for discharge pressureL for these pumps are between;88 and 92 , s psig. ' Dais would. require discharge i
pressure gauges.of.0-265 psig. maximum, The accuracy required for these gauges . t would be 2 percent of 265 psig, which-is 15.3 psig. The installed' pump discharge '
pressure' gauges are 0-300 16.0 psig. '
Although the installed instruments are above the maximum range limits, they are essentially equal to the accuracy requirements and are therefore: adequate 3 for pump testing.
Alternate Testing: The installed instruments will be used for taking inlet pressure neasurements during pump testing.
t 03871 II 25 GEN REV.4
4 FNPJ 1-M-042
!PUMPLRELIEF REQUEST' PR-15 System: Component Cooling _ Water j
- Pump: _ P001A-B, Pli;o-AB, P001C-A Class: 3 '
l Function: Provide cooling water to safety-related- i
. equipment.
1
. Test Requirement: IWP-3100 requires that each measured ;
test quantity be compared to the- (l reference value of the same quantity.
Any' deviations determined _shall' be l compared to the limits given in Table 1 IWP-3100-2 as specified in IWP-3210.' I .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 ~l continuous operation during-all modes-of 1
'. ant operation. Depending on plant , !
operating conditions and' climatic j conditions, the ' oling requirements .l
- range from mi ..ium cooling-loads to 100 percent with aany of the loads automatically placed in' operation in i 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.
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Alternate Testing: Purap testing will be performed with the I system in the as-found operating configuration and the test results ;
compared with a curve of reference l va?.ues which establish the relationship j 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.
03871 I1-1-26 REV . 4
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FN P-1 -M-Da2 AM RE!.IEF REQUEST PR-16 System: Diesel Generators Fuel Oil Transfer Pump: P501 A A, P5018-8, P502A-A, PS028-B, P503A-A, P5038-e, P504A-A, P5048-B
{ Class: 3 Function: Transfer diesel generator fuel oil f rom the storage
= tanks to the diesel generator day tanks.
h Test Requirtment: Measure pump test inlet pressure, differe,.Lial pressure E
and flor rate in accordance with the requirements of IWP-3100 and pump test duration requirements of IW P-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 tari. None of the pumps have installed instrumentation to measure either flow or discharge pressure. The only possible flow measurement is by measuring change in day ;
tank level over time. The 4075 K.W. Diesel Generators !
have, by design, a maximum fuel consumption of 5.6 gpm l and the 2850 K.W. units nave a fuel cor.sumption of 4.2 gpm. Plant procedures require that day tank level be
- maintained approximately 80 percent full. To comp 1v i
{-- with the Codt requirement to run the pumps for five '
- minutes prior to taking test measurements would requiet draining the day tanks below a safe operating level.
[- Alternate Testing: Pump test flow rate will be obtained by measuring a :
change in day tank level over time. A day tank levei change of approximately 10 pertent shall be timed and
=
the flow rate determined from tank curycs. An Alert Range of +61 and a Required Action Range of +10% shall be appliel as provided by IWP-3210 and clariTied by Code Interpretation XI-1-79-19. Also, flow rates of 5.6 gal. Anin. for the P501 A/B and P502 A/B pumps and 4.2 gal./ min. for the P503 A/B and PSO4 A/B pumps will L be applied as an absolute minimum.
9 0380L II 27 Gen. Rev. 4 s
t PNP-1-M-042 PUMP RELIEF REQUEST PR-17 System: Diesel G'.nerators Puel oil Transfer Pump: P501A-A, P5018-B, P502A-A, P502B-8, P503A-A, P503B-8, P504A-A, P5043-B l
Class: 3 '
Function: Transfer diesel generator fuel oil from the storage. 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 a flange on top of the tank.
The p* amps are inaccessible for pump i-bearing vibration measurements.
Alternate Testing: Motor vibration measurements will be performed. quarterly in lieu ef Code required pump vibration measurements.
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03871 II 28 Gen. REV. 4
FNP.I.M 042 PUMP REllEF REQUEST PR 18 7
System: All Pump: All Class: 2, 3 function: Various Test Requirement: IWP 4120 requires that the full scale rar.ge 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 818 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 I'lD provides a digital display of vibration measurement to three (3) decimal places. This instrument provides significantly higher accuracy than an analog amplitude nieter which is read visually and subject to human error and parallax.
The use of a digital vibration meter has been reviewed by the AStiE 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 j PR-19 i
System: CVCS Boric Acio Transfer, Residual Heat. Removal, Auxilairy Feedwater (TDAFW), Containment Spray .
Pump: P005A A, P005B B, P001A A, P001B-B, P002, P001A-A, ,
P001B-B Class: 3,2,3,2 Test Requirement: IWP 3100 requires that each measured test quantity be compared ?o the reference value of the same ;
quantity. Any deviation determined shall be e compared to the limits given in Table IWP-3100 2.
Basis for Relief: Section IWP 3100 reouires quarterly pump t;, ting to be >erformed by varying the system resistr.nce until .
eit1er 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 ccntain flow control provisions sufficier.tly accurata to repeat an 1 xact reference condition. ,
, 'nate Testing: Pump testing will be performed at conditions as close to the reference conditions as can be "
reasonably achie/ed and the test data compared with a curve of reference values which establish the relationship between flow rate and differential pressure in a band around the reference point. ,
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000814 21 1-30 Rev. 4 1
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1 System: Auxiliary Steam Q1N12 Retlef' Vsive Act. Re q. or valve Class Dwg. No.. Sire Act. Pesition or fests_e_nd freq. C. S. .De sc ri pt ion Number ist [ Coo rd.1 Cat (in,) TyEe IYPe More fait Safety I'a s s, P' 'ti SI UR fSV Q ._Just,_ _snd Slotes r:V001 A 2 D-175033/2 BC 3 SC A0 C O O/C A Y Q Q FF - - -
Main Stese 8 to HV3235A t-8 5 Q - - - Intbine Driven u-D-351110/2 Q BS Aux. Feed. Pump f-8 Shutoff Valve.
Air Operster Maintains Velve Open.
QVOO18 2 D-115033/2 BC 3 SC A0 C 0 0/C A Y Q Q fr - - -
99ain Stese C to HV3235B D-8 S Q BS - - -
Turbine Driven D-351110/2 O Piemp feed. hnap t-6 Shtstorr Valve.
Air Operator-Maine.s!ns Vsive Open. E QV010A 3 D-175033/2 C 4 CK S C M/A O A -
Q - FF - - -
Main Steam to I-6 R M ""- "'d - ""*P D-351110/2 Q1N12 ^ Turbine.
r-6 RV-1 QV0100 3 0-175033/2 C as CA S C N/A 0 A -
Q - FF - - -
Main Steso to C-6 A reed. n.mp D-33 n io/2 R RM Q1N12Turbine.
ux.
t- 6 RV-1 HV3226 3 0-175033/2 B 3 CL A0 C O O A Y Q Q O Q - -
Main Steam to D-5 ' iterbine Driven D-351110/2 Atsu . feed. Ptamp D-5 Auto. Vsave.
HV323tsA 2 D-175033/2 B 1 CL A0 0 C C A Y Q Q C Q - ' - Stese Line B to C-8 Tetrbine Driven D-351110/2 Atts. feed. Ptump G-8 Wefleup Line Isotation.
IfV323a8 2 D-17$033/2 B 1 CL A0 ') C C A Y Q Q O Q - -
Main Steam Line C-8 C to iterbine D-351110/2 Driven Aesx.
C-8 ieed. Pump Were-up Line.
0368: :::-1-ta-i arv.4
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FNP-1-M 042 REllEF REQUEST Q1N12 RV-1 System: Auxiliary Steam Yalve: QV010A,QV010B Category: C Class: 3 Function: Main steam to auxiliary feedwater pump supply line check valves.
ASME Sectiov,XI 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 staggered test basis. The valve internals will be verified as structurally sound (no loose or corroded 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 valve will also be disassembled, inspected, and manually full stroke exercised during the same outage.
000814 111-1-14-2 Rev. 4
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Valve Test List System: Instrument Air EllP19 Relief' Valse Act. Req. Or valve Class Dwg. eso. Site .Act. Position or Tesjs ani. Lreq. C. S. Description Nuenber M ( Coo rd. ) Caj fin.) Type Typ_e mo_rin 7, all_ parety Pass. Pt ET ST OR 1.)_Y Li _Just. . sad getes QV002 2 0-175034/3 AC 2 CK S O N/A C A -
R -
BS -
U Q1P19- Ctet. Instrweent D-2 RV-1 Air Supply. Pen.
D-151111/3 48.
D-1 OV004 2 0-175034/1 AC 1/2 CK S C N/A C A - R - f4 -
U Q1P19- Ctet. Instrument l C-10 RV-1 Ai r Sepp Iy. Pen.
D-351111/1 979 D-!O HV2228 2 D-175034/1 A 3/4 CL A0 C C C P - - - - -
U - Rechup Air -=*
C-9 Supply to Press..
D-351111/1 PORVs. Pen.
D-9 979. Mainteined Closed During Operation.
HV3611 2 0-175034/2 A 2 CL A0 0 C C A Y CS CS C CS U Q1P19- Instrument Alr E-11 CS-1 Supply to Ctet.
D-351111/2 Pen. 48.
E-11 4
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03898 18t-1-24-1 REY. 4
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System: soon-Redioective Vent QSwtg7
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Retlef Valve Act. Reg, or Valve GJlay Dwg. 800. Size Act. % : tion or Tests and s~reeg. C. S. Descriptioes Number JJ1 (Coord.1 pg (in.1 Type Type teorm fail Safety Pass. Pt El Si DR f 5J M Just. aftal IIntE QV001A -
D-205012 8 I ts B A0 0 C C A Y Q Q C Q - -
Contret stoom HV3620s F-5 HVAC.
D-351125 F-5 QV0018 -
D-205012 8 Its B AO O C C A Y Q Q C Q - - Control Room HV3625 C-5 HVAC.
D-351125 C-5 QV002A -
D-205012 B 20 8 .W O C C A Y Q Q C Q - - Computer Room '
HV3623 C-3 HVAC.
D-351125 C-3 -
QV0028 -
D-205012 8 20 B AO O C C A Y Q Q C Q - - Computer Room HV3622 G-3 HVAC.
D-351125 G-3 QV003A -
D-205012 8 2es B AO O C C A Y Q Q C Q - -
Control Room HV3626 f-5 HVAC.
D-351125 i-5 QV003B -
D-205012 8 24s B A0 0 C C A Y Q Q C Q - -
Control Room HV3627 G-5 HVAC.
D-351125 C-5 I
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03938 is1-1-27-1 REY.4
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