|
---|
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
, Milling Address Alabama Power Company
- 600 North 18th Street Post Office Box 2641 Birmingham, Alabama 35291 Telephone 205 783-6090 R. P. Mcdonald
%%ek'*"fo*"' Alabama Power July 19, 1985 Docket Nos. 50-348 Director, Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D.C. 20555 Attention: Mr. S. A. Yarga Joseph M. Farley Nuclear Plant - Units 1 and 2 10CFR50.48 and 10CFR50, Appendix R Fire Protection Exemption Requests Gentlemen:
By letter dated March 13, 1985, Alabama Power Company submitted for NRC approval technical exemption requests from the provisions of 10CFR50, Appendix R for fire areas in Unit 2 and fire areas shared by Units 1 and 2.
On July 8,1985, it was determined that adequate circuit coordination is not provided between 125V DC safe-shutdown circuits and associated nonsafe-shutdown circuits in the service water intake structure. A fire could cause a loss of power to one of the 125V DC distribution panels in the service water intake structure. Consequently, a technical exemption is requested, pursuant to 10CFR50.12, from the requirement of 10CFR50.48( c) (3) . Attached is an addendum to exemption request 1-003, fire area 72, that provides in detail justification for the exemption.
In addition, typographical errors were discovered in exemption requests 2-019 revision 1 and 2-036 revision i submitted by letter dated June 26, 1985. Attached is revision 2 to these exemption requests.
If you have any questions, please advise.
Yours very tr y, 5072go g 80 0 R. P. Mcdonald RPM /DHJ:gri-D30 Attachments cc: Mr. L. B. Long Dr. J. N. Grace Mr. E. A. Reeves A d g [,
Mr. W. H. Bradford /f
ADDENDUM TO EXEMPTION REQUEST 1-3, FIRE AREA 72 EXEMPTION: Request an exemption from Section III.G.2 to the extent it requires safe-shutdown equipment to be isolated from associated non-safety circuits.
CONDITION REQUIRING EXEMPTION:
An associated circuit review indicated that adequate coordination is not
, provided between safe-shutdown circuits and associated nonsafe-shutdown
- circuits . powered from 125V DC Distribution Panels 1N, 2N, IM, 2M. The safe-shutdown circuits from these distribution panels provide control power for safe-shutdown breakers. A short circuit in an associated cable from one
.of the distribution panels could result in a loss of power to the panel, and
! therefore, a loss of control power to the safe-shutdown breakers powered from the affected panel.
JUSTIFICATION:
A loss of power to one of the 125V DC Distribution Panels 1N, 2N,1M or 2H
' will result in the loss of breaker control power for the following
' safe-shutdown loads controlled from that panel as shown below.
! Distribution Panel IN: 4 kV Breaker DLO2 to Load Center L 600 V Load Center Tie Breaker ELOS Service Water Pump 1C Service Water Pump 1D Service Water Pump 1E 600V Load Center Breaker ELO9 4 kV Tie Breaker DG02 Distribution Panel 2N: Service Water Pump 2C
- Service Water Pump 2D Service Water Pump 2E 4 kV Breaker DLO2 to Load Center L
' Distribution Panel 1M: 4 kV Breaker DK02 to Load Center K 600V Load Center Tie Breaker EK05 Service Water Pump 1A Service Water Pump 1B Service Water Pump 1C 600V Load Center Breaker EK03 Service Water Pump 2A Distribution Panel 2M: Service Water Pump 28 Service Water Pump 2C l
4 kV Breaker DK02 to Load Center K 4 kV Tie Breaker DF02 i
_ , , _ . , _ , -- . _ - _ . _ , , . _ , _ _ . - , _ . . _ . _ . _ , _ , . . _ _ . _ . , _ , _ , , , . , _ _ . . - , - _ _ , _ - - . - - .__,._..,m.,...,__- _ _ _ -
Addendum to Exemption Request 1-3, Fire Area 72 Page 2 I
)
A loss of breaker control power from the single effected panel will not interrupt the operation of the load powered by the breaker. However, electrical control of the breaker including breaker protection circuits and handswitch operation will not be functional. A loss of power to one of the subject DC distribution panels will not preclude any necessary control and operation of safe-shutdown equipment. Should the need arise, manual operation of the affected breaker would be possible.
Although not part of the justification for this exemption request, a design change has been initiated to improve the breaker coordination. This design change is currently scheduled to be installed prior to the end of the Unit i seventh refueling outage in 1986. Upon completion, the potential for the fire damage will no longer exist.
DHJ/gri-D30
J. M. FARLEY NUCLEAR PLANT ~
.3 '
10CFR50 APPENDIX 'R" J.,- FIRE HAZARDS ANALYSIS REEVALUATION w.
EXEMPTION REQUEST: 2-19 Rev. 2
_A
) FIRE AREA: 2-009 LOCATION:
TRAIN-B INSIDE CABLE CHASES, AUXILIARY BUILDING EXEMPTION:
Request exemption from section III.G.2.c to the extent that it requires one train of redundant safe shutdown cables to be enclosed by a barrier having a 1-h fire -rating.
CONDITIONS REOUIRING EXEMPTION:
Instrument Air a Fire area cable 2-009 contains electrical Train-B power and control raceways. The analysis of the potential effects of a fire in this area upon cabling shows that the plant could lose the y
entire electrical Train-B system. Due to loss of the electrical Train-B system, the following redundant safe shutdown valves J could become inoperable in the closed position.
EQUIPMENT m FUNCTION N2P19HV3885-B
[ Q2B13BV2228-B Instrument Air to Penetration Room '
Q2831PCV0445A-A Backup Air /Na Supply to Pressurizer PORVs Pressurizer PORV, Train A Q2831PCVO444B-B Pressurizer PORV, Train B Q2E21HV8145-N
~
Pressurizer Auxiliary Spray Il2P19HV3885-B and N2P19HV3825-A.In addition, Fire Area 2-009 contains in theposition.
closed area upon these cables shows the valves could become inopera Reactor Coolant Boundary _
r Fire area 2-009 pressurizer power contains operated control relief cables and blocking for thevalves Train-B
]- Q2831PCV0444B-B and Q2B13MOV8000B-B, valves Q2B13SV2213B-B and Q2B13SV2214B-B.and thecables The subject reactor head vent i
j cre associated control board. with A firecontrol induced fromfailure both the having hot shutdown and main multiple hot shorts and couldhead reactor causeventthepaths.
reactor inventory to letdown via the PORV f Auxiliary Feedwater Auxiliary feedwater isolation valves Q2N23MOV3764B, Q2N23MOV3764C, j
from the point of view that they isolate flow in redundantand Q2N23MOV3 cuxiliary feedwater supply lines.
p valves are routed through the fire area. Control cables for all three The analysis of the potential effects of a fire on these control cables shows that '
D 2-19-1 Rev. 2 !
l
,,-,__-n- ~ - - ' - ~ ' ' " ' ' ~ ' ' ~ ' ' ~ ~
h_
, J. M. FARLEY NUCLEAR PLANT 10CFR50 APPENDIX "R" FIRE HAZARDS ANALYSIS REEVALUATION O
~
tpurious operation of the auxiliary feedwater isolation valves could occt{r.
Component Cooling Water .
Fire area 2-009 contains a control cable for the CCW heat cxchanger 2B service water discharge valve (Q2P16SV3009-B). A fire induced failure resulting in a hot short from adjacent i
cables in the same raceway, could energize the solenoid and l close the valve.
JUSTIFICATION:
l Instrument Air - Justification Failure of valve Q2E21HV8145-N in the closed position will disable the Pressurizer Aux. Spray system which provides one method to achieve depressurization of the RCS. Pressurizer PORY's Q2831PCV0445A-A and Q2831PCV04448-B provide another means of achievir.g RCS depressurization. Valves N2P19HY3885-8, Q2813HY2228-B and N2P19HY3825-A could fail in the closed position as a result of fire damage. This will isolate the instrument air supply to the Pressurizer PORY's Q2B31PCV0445A-A i
and 02831PCV0444B-B. PORY Q2831PCV0444B-B will also be inoperable due to loss of the Train-B DC power supply. However, the Train-A DC supply to PORY Q2831PCV0445A-A is not affected due to a fire in this area. Since only one of the PORV's is required for RCS depressurization and RCS ilepressurization is a long term requirement, the operator has adequate time to take manual action to restore the instrument air by hand wheel operation of valve N2P19HY3885-8 and N2P19HV3825-A.
Once air is restored, PORV Q2B31PCVO445A-A will be operable to cchieve RCS depressurization.
Roactor Coolant Boundary - Justification Fire induced failure (hot short) of the individual control ccbles for Q2B31PCVO444B-B power operated relief valve, Q2B13SV2213B-B, and Q2B13SV2214B-B reactor head vent valves cculd result in the valves to be energized to open. The power cperated relief blocking valve (MOV) could become electrically inoperative in the open position. In the unlikely event of the multiple fire induced failures (hot shorts from adjacent control etbles in the shared raceway) occuring, this condition can be 2-19-2 Rev. 2
m J. M. FARLEY NUCLEAR PLANT 10CFR50 APPENDIX "R" FIRE HAZARDS ANALYSIS REEVALUATION
, mitigated raceway. by removing 125 V-dc power from cables in the shared This can be. accomplished by opening breaker on the
- 125 V-de switchgear distribution panels,bus 2B (Q2R42B001B-B) for 125 V-dc 2D, 3E, and 2F.
}
Auxiliary Feedwater - Justification '
The. control cable associated with at least one of the auxiliary feedwater isolation valves has been protected by two 1-in.
layers of Knowool blanket with an overall la or it will be rerouted out of the fire area.yerThe of Zetex subject fabric valves E
and associated cables are as follows:
Q2N23MOV3764B: 2VBFV-M5C Q2N23MOV3764C: 2VBFV-Y2C Q2N23MOV3764E: 2VBFV-R2C Component Cooling Water - Justification be in the oligned open position to electrical Train A.only when the swing CCW pump 2B isTh In the unlikely event of such hot shorts resulting in the closed position of the service water discharge valve, the valve'can be manually repositioned.
Plant o fire procedures in area 2-009. will be revised to include the above action for FIRE PROTECTION:
A cresmoke detection provided systemthe throughout and automatic water suppression system chase. In addition, water hoses and portable extinguishers located in rooma 2185 (area 2-6) and 2319 (crea 2-42) are available for use in the area.
FIRE AREA INFORMATION:
- ROOM NUMBERS / SHUTDOWN COMBUSTIBLE MAXIMUM TITLES TRAIN MATERIAL FIRE LOAD FIRE QUANTITY _(Btu /ft8) SEVERITY Rooms 2117, 2198, 2247, B Cable Insul. 4,489 lb 2,921,199 <9 h 2338 Cable Chase i
2-19-3 Rev. 2 w_ . -
= _
_._.r, ..~g .
g g g y N 8+f E 9 3 M #~"
3 J. M. FARLEY NUCLEAR PLANT 10CFR50 APPENDIX "R" FIRE HAZARDS ANALYSIS REEVALUATION w
ROOM NUMBERS_ TRAIN TITLES / SHUTDOWN COMBUSTIBLE FIRE LOAD MAXIMUM
_ MATERIAL QUANTITY FIRE Rooms 2246, (Btu /ft") SEVERITY B
l 2344 Cable Cable Insul. 2,135 lb 180,180 <2-1/2 h Chase DESIGN FEATURES:
Construction: Floor, ceiling, boundary are of reinforced concrete.and walls forming the area Doors:
and 2185 (area 2-6) and between rooms 2338 and 233 -
l -
an airtight (area 2-41).UL Class-A door exists between rooms 2344 and 2343 Piping and Electrical Penetrations:
the area boundary are sealed with silicone foam or NelsonAll penetrations throug fittings.
1 j
Ventilation:
Fixed smoke removal capability has not been providedThere is no Floor Drains:
There are no floor drains.
l l
L i
2-19-4 Rev. 2
- B J. M. FARLEY NUCLEAR PLANT 10CFR50 APPENDIX "R" FIRE HAZARDS ANALYSIS REEVALUATION EXEMPTION REQUEST: 2-36 Rev. 2 FIRE AREA!- 2-001 LOCATION: UNIT-2 AUXILIARY BUILDING, EL 83 FT - 0 IN., 100 FT - 0 IN., AND 121 FT - 0 IN.
i Fire area 2-001 consists of the following rooms:
, El 83 Ft - 0 In.
R:om 2101 Waste Decay Tank Room R;om 2102 Valve Compartment Room R:om 2103 Corridor R:om 2104 Passageway to Unit 1 Room 2105 Catalytic Ha Recombiner-A Room R:om 2106 Catalytic Hz Recombiner-B Room R:om 2108 Waste Monitor Tank Room l R:om 2109 Waste Monitor Tank Pump Room i
Room 2110 Monitor Control Panel Room R:om 2111 Containment Spray Pump Room A R om 2112 Access to Tendon Access Gallery
{ Room 2113 Valve Encapsulation
! R:om 2114 Pipe Chase .
R om 2115 Hallway
- R
- om 2118 Floor Drain Tank Room j R:om 2119 Waste Holdup Tank Room
~
Rtem 21?O corridor R om 2121 Floor Drain Tank Pmr.p Room
) R om 2122
)
Waste Evaporator Feed Pump Room R:om 2123 Pipe Chase R:om 2124 Valve Encapsulation R:om 2125 Containment Spray Pump Room B R om 2126 Pipe Chase R om 2127 Pipe Chase R:om 2128 RHR Heat Exchanger Room
) R:om 2129
) RHR Low Head Pum p Room B R:om 21'30 -- Pipe T,hase --
R om 2131 RHR Low Head Pump Room A
)
y El 100 Ft - 0 In.
R:om 2183 Tendon Access Gallery Entrance R:om 2184 Piping Penetration Room R:om 2169 Pipe and Duct Chase R om 2196 Tendon Access Gallery I
2-36-1 '
Rev. 2
J. M. FARLEY NUCLEAR PLANT 10CFR50 APPENDIX "R" FIRE HAZARDS ANALYSIS REEVALUATION 3
El 121 Ft - 0 In.
Room 2223 Piping Penetration Room All of the fire area boundary walls, floors, and celiings are 1 rated as 3-h fire barriers except for a non-rated steel hatch cover between 2163 (area *-4). the ceiling of room 2103 and the floor of room for a 3-h rating. All electrical and piping penetrations sealed 1 Class-A or Class-B rated.All doors in the boundary walls are UL EXEMPTION:
1.I the extent it requires one train of redundant safe shutdownAn exem cable to be automatic enclosed fire suppression.by a barrier having a 1-h fire rating and
=
CONDITIONS REQUIRING EXEMPTIONS:
Exemptions equipment asare required described for safe shutdown related cable and below.
Instrument Air Isolation A fire induced failure in control cables for instrument air isolation valve Q2P19HV3611 and N2P19HY3825-A may cause the valve to fail closed.
{ A loss of instrument air causes the normal charging line j isolation valve Q2E21HV8146 and the alternate charging line isolation valve Q2E21HV8147 to fail open.
It may be necessary to close these valves during the course of shutdown to isolate charging flow.
l A fire induced backup air /W failure in the control cable for the pressurizer PORV 1 closed. 2 supply valve Q2B13HV2228-B may cause the valve to fail h If instrument air isolation valve Q2P19HY3611 or N2P19HV3825-A and the pressurizer PORY backup air2/Nsupply valve Q2B13HY2228-B in the closed position. fail closed, the pressurizer PORY's will be inoperable required to achieve depressurization of the RCS. Operation of the pressurizer PO Initiation of Safety Signals l
Fire area 2-001 the following channels, redundant contains containmentinstrumentation pressure instrumentcables associated with i
PT950-P1 CTMT Pressure Channel 1 PT951-P2 CTMT Pressure Channel 2 PT952-P3 CTMT Pressure Channel 3 PT953-P4 CTMT Pressure Channel 4 I .
2-36-2 Rev. 2 '
~ :-
Y-
=s J. M. FARLEY NUCLEAR PLANT 10CFR50 APPENDIX "R" FIRE HAZARDS ANALYSIS REEVALUATION ll '
These instrument loops are not required for post-fire safe shutdown,,.but due to fire induced failures, the circuitry could cause initiation of safety signals (SI, CI, and CVI). i Main Steam Atmospheric Relief Control cables associated with the three redundant atmospheric relief valves are routed through fire area 2-001. An analysis of potential effects of a fire upon these cables has shown that the subject position. valve could become inoperable in the closed Charging Pump Miniflow Power and control cables associated with charging pump miniflow isolation valve MOV8106-A are routed through fire area 2-001.
An analysis of the potential effects of a fire upon these cables has shown pump miniflow thatline.
MOV8106-A could close and isolate the charging Reactor Coolant Boundary Integrity control cables for the Train-A pressurizer power operated relief tnd blocking valves Q2B31PCV0445A-A and Q2B13MOV8000A-A, and the reactor head vent valves Q2B13SV2213A-A and Q2B135V2214A-A are located in fire area 2*Q01. The subject cables are associated with the control function from the hot shutdown panel Q2H21NBAFP2605G-A.
In addition control cables which shift via the transfer relay cabinet Q2H22 LOO 2-A are inA this area.centro fire induced failure having multiple hot shorts could cause the reactor paths. inventory to letdown via the PORV, and reactor head vent ,
s j
JUSTIFICATIONS FOR EXEMPTIONS:
)
Instrument Air Isolation - Justification equipped with a handwheel to facilitate In the manual operation i event the valves fall closed an operator can manually open them.
actionand valves willtherestore instrument pressurtzer charline isolation This PORV's. air to the 1tng l
i Q2B13NY2228-8,to be taken on the pressurizer PORY 2 supply valve backup afr/NConseque 1
1 2-36-3 m.2
_ _ __.__w-*-e-- - - * - "
I @ a ,M J. M. FARLEY NUCLEAR PLANT 10CFR50 APPENDIX "R" FIRE HAZARDS ANALYSIS REEVALUATION Initiation of Safety Signals - Justification l
t
, Fire induced cable failures in fire area 2-001 to non-post-fire cafe shutdown circuitry could potentially result in a false SI, CVI, or CI safety signal initiation from the solid state protection system. Plant procedures exist, or will be developed, for resetting spurious SI, CVI, and CI safety signals from the main control room and can be used if required for a fire in this area.
Main Steam Atmospheric Relief - Justification one of the three main steam atmospheric relief valves and its rolated steam generator are required to be operable to achieve oteam release for cooldown. The atmospheric relief valves are provided with hand wheels such that the valves may be manually
- cpened or closed without electrical controls or air supplies.
The operator would establish manual control of the atmospheric rolief valves by closing the manual air control valvoz to icolate the air supply and by opening the manual air vent valve to bleed off air from the diaphragm of the valve actuator. Both the air control and air vent valves are located in the vicinity of their associated atmospheric relief valve and would be cccessible despite a fire in area 2-001. The capability to control steam generator pressure and reactor coolant system tcmperature with the use of the manually controlled atmospheric rolief valves was demonstrated during the Unit-2 natural circulation and cooldown startup testing. Consequuntly, a fire in area 2-001 would not prevent the operation of at least one rcdundant atmospheric relief valve.
Charging Pump Miniflow - Justification Volve Q2E21MOV8106-A is required to be maintained open to Cstablish charging pump miniflow. In the event this valve fails closed, miniflow will be discontinued. The charging pump can be run safely with miniflow isolated and with a minimum of 24 gpm i of seal injection flow for a period of up to I h. This will cllow the operator time to take manual action to open the valve and re-establish miniflow. .
R: actor Coolant Boundary Integrity - Justification Fire induced failures (hot shorts) to the control cables for the transfer relay cabinet Q2H22 LOO 2-A could cause control for the p: war operated relief and blocking valves and the reaction head 1
. I 2-36-4 Rev. 2
i J. M. FARLEY NUCLEAR PLANT 10CFR50 APPENDIX "R" ;
FIRE HAZARDS ANALYSIS REEVALUATION 3
vent valves, alignment, to the remote hot shutdown panel.to shift from their normal main cont 3 Subsequent fire induced fhilures (hot shorts for adjacent control cables in the operatedraceway) shared relief valve, of Q2B13SV2213A-A, the control cables for Q2B31PCV044SA-A, power head open. vent valves could result in the valves being energized toand 2B13SV2214A-A rea The power relief blocking valve olectrically inoperative in the open pos(MOV) could become cvent of the multiple hot shorts occuring, ition. In the unlikely l citigated by removing power from the transfer relays and manualthis condition can be cperation (handle) of the effected relay, thereby shifting control to the main control board.
Plant procedures for fire-area 2-001. will be revised to include the above actions FIRE AREA INFORMATION:
[ ROOM NUMBERS /
TITLES SHUTDOlIN COMBUSTIBLE FIRE LOAD MAXIMUM TRAIN ___ MATERIAL FIRE QUANTITY (Btu /ft8) r SEVERITY Room 2101 -
[ Waste Gas Cable Insul. 29 lb 1,2 51 * *
Room Room 2102 Cable Insul.
Volve Ccmpartment Room Rcom 2103 B f Corridor Cable Insul.
Rcom 2105 B Catalytic Cable Insul. 490 lb'*' 7,634'**
I Ha Re- Panels 28 lb <30 min'**
ccmbiner-A Rcom Room 2106 -
Catalytic Cable Panels Ha Re-ccmbiner-B Room (0)
Applies to rooma 2101 and 2102 collectively.
(b)
Applies to rooms 2103, 2105, and 2106 collectively.
2-36-5
J. M. FARLEY NUCLEAR PLANT 10CFR50 AP'ENDIX "R" FIRE HAZARDS ANALYSIS REEVALUATION 1
MAXIMUM 1 ROOM NUMBERS TITLES $ / SHUTDOWN COMBtJSTIBLE
_ TRAIN MATERIAL FIRE LOAD FIRE QUANTITY _(Btu /ft8) SEVERITY Room 2104 B
} Passageway to Unit 1 Cable Insul. '
Room 2109 B 1 Waste Monitor Cable Insul. 417 lb 5,742'**
Tank Pump Lube 011 0.25 gal <30 min'**
Room
) Room 2110 l Monitor Cable Insul.
Panels 14 lb Control Panel 1 Room Room 2108 Cable Insul.
Waste Monitor Charcoal 75 lb 19,457 <30 min Tank Room 375 lb Filter
. Room 2169 -
None Duct and -
0 0 Pipe Chase .
Room 2118 l Cable Insul.
Floor Drain 22 lb 831 <30 min Tcnk Room Room 2119 W2ste Holdup Cable Insul. 60 lb 2,711 <30 min Tcnk Room Room 2120 B, C l Carridor Cable Insul. 42 lb 5,540 <30 min I R om 2121 B, C i Floor Drain Cable Insul. 287 lb 21,402 l Tcnk Lube 011 0.25 gal <30 min I Pump Room Rcom 2122 B, C W0ste Cable Insul. 287 lb 21,402 Evaporator Lube Oil 0.25 gal <30 min Fccd Pump Room (c)
Applies to rooma 2104, 2109, and 2110 collectively.
I 2-36-6 R ev. 2
~I *
' ] J. M. FARLEY NUCLEAR PLANT 10CFR50 APPENDIX "R" FIRE HAZARDS ANALYSIS REEVALUATION r
] ROOM NUMBERS /
TITLES SHUTDOWN COMBUSTIBLE ,
_ TRAIN MATERIAL QUANTITY FIRE LOAD (Btu /ft8)
MAXIMUM FIRE Room 2127 S_EVERITY B, C None Pipe Chase O O O Room 2128 A, C RHR Heat Cable Insul. 454 lb 2,607 3 Exchanger <30 min Room
] Room 2129 RHR Low B, C Cable Insul. 217 lb 3,837
<30 min Head Pump Room B Room 2130 -
Pipe Chase None 0 0 0 3 Room 2131 -
RER Low Head Cable Insul. 222 lb 6,332 Pump Room A <30 min Room 2126 -
Pipe' Chase None 0 0 0 '
Room 2124 -
Valve Cable Insul. 7 lb 6,329 Encapsulation <30 min Room 2125 -
Cable Insul.
] Containment Spray Pump Room B Lube Oil 261 lb O.25 gal 3,569 <30 min I
Room 2114 3 Pipe Chase Cable Insul. 7 lb 3,885
<30 min Room 2111 -
containment Cable Insul. 101 lb 3,469 Spray Pump Lube Oil 0.25 gal <30 min i Room A
[
z I
L 2-36-7 Rev. 2 I '
- ~ _ r
] .
J. M. FARLEY NUCLEAR PLANT 10CFR50 APPENDIX "R" FIRE HAZARDS ANALYSIS REEVALUATION J
MAXIMUM
] ROOM NUMBERS /
TITLES SHUTDOWN
_ TRAIN COMBUSTIBLE MATERIAL QUANTITY FIRE LOAD (Btu /ft")
FIRE SEVERITY Room 2113
]
Cable Insul. 6 lb 3,333 <30 min Valve '
Encapsulation Room 2115 -
Cable Insul. 4 lb 1,655
] Hallway <30 min Room 2112 Cable Insul.
]
4 lb 175 <30 min Access to Tendon Access Gallery Room 2196 -
Cable Insul. 4 lb , 175 Access to <30 min Tendon Access Gallery Room 2123 -
None 0 0 Pipe Chase 0
' Room 2183 A Cable Insul. 1,050 lb'** 6,405888 Tendon Access <30 min
Gallery Entrance Room 2184 -
Cable Insul.
] Piping Penetration Room, El J 100 Et - 0 In.
Room 2223 A, B Cable Insul. 16,663 lb 40,625 <1 h
,] Penetration Room El Charcoal 400 lb 121 Et - 0 In.
J J
(d) Applies to rooms 2183 and 2184 collectively.
]
2-36-8 Rev. 2
ll .
~
i J. M. FARLEY NUCLEAR PLANT l
I 10CFR50 APPENDIX "R" FIRE HAZARDS ANALYSIS REEVALUATION
] DESIGN FEATURES:
Construction: Floors and walls forming the area boundary are of reinforced concrete. The ceiling of room 2223 has tendon access openings to room 2334 (area 2-34). Steel plates with'3-h rated l} coatings and which are topped by removable concrete slabs have been installed over the tendon access openings. ;fhe steel h'tch a cover located in the el 100 ft - 0 in, floor slab between room 2103 l (area 2-001) and 2163 (area 2-004) is protected by a suppression system designed for extra hazards to limit the i spread of fire to adjacent fire areas.
Doors: An airtight,'UL Class-B door is installed between room
, 2223 and stairway No. 2. The door between room 2184 and room 2162 (area 2-4) is an airtight UL Class-A door. Nonairtight I, Class-B stairway doors No. 2.are installed between room 2110 and 2115 and Piping and Electrical Penetrations: Penetrations through the
]-
area boundary are sealed wi,th silicone foam. Three-h rated fire -
dampers are installed between 2169 and 2163 (area 2-4).
Ventilation: No normal ventilation exists. Fixed smoke removal
- capability has not been provided.
y Floor Drains: Twenty-one 4-in. diameter floor drains with a j
100-gal /m capacity each are located throughout the area. Sumps are provided in rooms 2103, 2111, 2125, 2128, 2129, and 2131.
u The sumps contain two 100-gal /m pumps each. The sump pumps
} discharge to the waste holdup tank or the floor drain tank. The floor drains tank. above el 77 ft - 83 in. drains to the floor drain The other floor drains drain to the sumps.
f FIRE PROTECTION:
P A detection system covers the majority of the area. Exceptions to this2169, 2130, coverage are rooms 2112, 2114, 2115, 2123, 2126, 2127, and 2196.
s The western half of the piping penetration room on el 121 ft - 0 in is the only part of fire area 2-001 covered by automatic suppression.
p Portable extinguishers, smoke removal equipment, and water hose cabinets are located throughout the fire area for use by the fire brigade.
} -
[
B
[ 2-36-9 Rev. 2 0 -
e
, \
=> \
J. M. FARLEY NUCLEAR PLANT 10CFR50 APPENDIX "R" FIRE HAZARDS ANALYSIS REEVALUATION J !
JUSTIFICATION FOR FIRE PROTECTION:
The rooms in fire area 2-001 without detection (2112,' 2114, 2115, 2123, 2126, 2127, 2130, 2169, and 2196.) contain little ;
or no combustible material and contain no safe shutdown cable or equipment. The western half of the piping penetration room on
,] el 121 ft - O in. is the only part of fire area 2-001 covered by an automatic suppression system. This is the only part of fire area 2-001 that has cables or equipment that are associated with
] redundant hot shutdown systems. One train of redundant cables are provided with fire barriers consisting of two 1-in. layers of Knowool blanket with overall layer of Zetex cloth within this
} area.
]
]
]
]
] .
I s
i
}
J
]
]
0397n 2-36-10 Rev. 2
. .