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MONTHYEARML20112E0751985-03-13013 March 1985 Forwards Jm Farley Nuclear Plant 10CFR50,App R Fire Hazards Reevaluation. Review Conducted to Determine Level of Compliance in Light of Interpretations Set Forth in IE Info Notice 84-09 & Generic Ltr 83-33.Fee Paid Project stage: Request ML20138F3151985-10-18018 October 1985 Forwards Revised 10CFR50,App R Fire Protection Exemption Requests as Result of NRC Audit During Wk of 850719 of Util 850313,0626 & 0719 Exemption Requests.Mods Will Be Completed No Later than Second Quarter 1986 Project stage: Other ML20137N6881986-01-27027 January 1986 Forwards Rev 2 to Exemption Request 2-008 Re Requirements of 10CFR50,App R Per NRC Audit,Correcting Error in Installation of Fire Barriers in Area 2-005.List of Fire Doors to Be Included in Exemption Request 1-041 Encl Project stage: Other ML20203D2001986-07-16016 July 1986 Suppls 850313,0531,0626,0719 & 1018 Requests for Exemption from App R Requirements.Implementing Addl Mods to Comply W/ App R for All Areas of Plant Would Represent Unwarranted Burden on Util Resources Project stage: Other ML20213G3881986-11-0606 November 1986 Notice of Environ Assessment & Finding of No Significant Impact Re Util 851018,860127 & 0716 Applications for Exemption from Requirements of 10CFR50,App R Project stage: Approval ML20207J8931986-12-29029 December 1986 Safety Evaluation Granting Exemption from Technical Requirements of 10CFR50,App R,Section Iii.G for 16 Fire Areas Project stage: Approval 1986-01-27
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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 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 L-99-031, Forwards Info Requested in Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Exams1999-09-13013 September 1999 Forwards Info Requested in Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Exams 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 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 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 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 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 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 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 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 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 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 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 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-99-027, 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 Guidelines1999-07-22022 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 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 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 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 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 ML20196J3591999-06-30030 June 1999 Forwards SE of TR WCAP-14750, RCS Flow Verification Using Elbow Taps at Westinghouse 3-Loop Pwrs L-99-024, 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-99-025, 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 ML20196D1931999-06-22022 June 1999 Discusses Requesting Approval & Issuance of Plant Units 1 & 2 ITS by 990930.New Target Date Agrees with Requested Date ML20196A3401999-06-10010 June 1999 Forwards Insp Repts 50-348/99-03 & 50-364/99-03 on 990404-0515.No Violations Noted ML20196H9801999-06-10010 June 1999 Submits Two RAI Re ITS Section 4.0 That Were Never Sent. Reply to RAI Via e-mail 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 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 ML20212C2351999-09-16016 September 1999 Submits Corrected Info Concerning Snoc Response to NRC GL 99-02, Lab Testing of Nuclear-Grade Activated Charcoal L-99-031, Forwards Info Requested in Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Exams1999-09-13013 September 1999 Forwards Info Requested in Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Exams 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 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 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 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-99-027, 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 Guidelines1999-07-22022 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-99-249, 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 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-99-024, 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-99-025, 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 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 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 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-99-022, 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 L-99-021, 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-99-203, 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 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-99-020, 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 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 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 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 L-99-153, 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 Error1999-04-13013 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 L-99-125, Forwards Rev 0 to W Rept WCAP-15171, Analysis of Capsule Z from Alabama Power Co Jm Farley Unit 2 Reactor Vessel Radiation Surveillance Program, Presenting Surveillance Capsule Test Results from Capsule Z1999-03-19019 March 1999 Forwards Rev 0 to W Rept WCAP-15171, Analysis of Capsule Z from Alabama Power Co Jm Farley Unit 2 Reactor Vessel Radiation Surveillance Program, Presenting Surveillance Capsule Test Results from Capsule Z ML20205A2871999-03-19019 March 1999 Forwards Rev 0 to W Rept WCAP-15171, Analysis of Capsule Z from Alabama Power Co Jm Farley Unit 2 Reactor Vessel Radiation Surveillance Program, Presenting Surveillance Capsule Test Results from Capsule Z ML20205A1531999-03-19019 March 1999 Forwards Corrected Typed & marked-up Current TS Pages for Replacing Previous Pages Submitted on 990222,re CR, Penetration Room & Containment Purge Filtration Sys & Radiation Monitoring Instrumentation L-99-012, Forwards 10CFR50.46 Annual Rept for 1998,re Effects of ECCS Evaluation Model Mod on Peak Cladding Temp Results Since 1997 Annual Rept & Most Recent PCT Error Rept Submitted 9809101999-03-19019 March 1999 Forwards 10CFR50.46 Annual Rept for 1998,re Effects of ECCS Evaluation Model Mod on Peak Cladding Temp Results Since 1997 Annual Rept & Most Recent PCT Error Rept Submitted 980910 L-99-010, Forwards ISI Refueling 15,Interval 2,Period 3,Outage 3 for Jfnp,Unit 1, & Vols 1 & 2 to ISI Refueling 15,Interval 3, Period 1,Outage 1 for Jfnp,Unit 1. Summary of Results May Be Found in Tab B of Encl 21999-03-18018 March 1999 Forwards ISI Refueling 15,Interval 2,Period 3,Outage 3 for Jfnp,Unit 1, & Vols 1 & 2 to ISI Refueling 15,Interval 3, Period 1,Outage 1 for Jfnp,Unit 1. Summary of Results May Be Found in Tab B of Encl 2 ML20205A7611999-03-18018 March 1999 Forwards Annual DG Reliability Data Rept for 1998,per Plant TS 6.9.1.12 & 10CFR50.36.Rept Provides Number of Tests (Valid or Invalid) & Number of Failures for DGs at Jm Farley Nuclear Plant.Ltr Contains No New Commitments ML20205H2741999-03-18018 March 1999 Forwards Info on Status of Decommissioning Funding for Jm Farley Nuclear Plant,Units 1 & 2,IAW 10CFR50.75(f)(i) ML20204D4281999-03-16016 March 1999 Forwards SG-99-03-001, Farley Unit-1 1999 Voltage-Based Repair Criteria 90-Day Rept, Per GL 95-05.Required Rept for Fall 1998 SG Insp Is Included in Rept ML20204E5841999-03-15015 March 1999 Submits Info on Current Levels & Sources of Insurance on Jm Farley Nuclear Plant,Units 1 & 2 1999-09-16
[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
_ _ ___m ___m_. _ . . . _ . . _ _ _ _ - _ . _ . . _ . _ _
Milling Addrets Alabama Power Company 600 North 18th Street
, Post Office Box 2641 Birmingham. Alabama 35291 Telephone 205 783-6090 t R. P. Mcdonald Senior Vice President Flintridge Building [jh[g)){g % g [
'^
4 January 27, 1986 '
Docket Nos. 50-348 50-364 9
Di rector, Nuclear R. actor Regulation
- U. S. Nuclear Regulatory Commission l Washington, D.C. 20555
- Attention: Mr. L. S. Rubenstein Joseph M. Farley Nuclear Plant - Units 1 and 2 l 10CFR50, Appendix R Exemption Request Revisions a
Gentlemen:
Alabama Power Company (APCo) submitted exemption requests to the requirements of 10CFR50, Appendix R, based upon an NRC audit by letter dated
- October 18, 1985. This submittal supplemented letters dated March 13, 1985, May 31, 1985, June 26, 1985 and July 19, 1985. .
In, these exemptibn requests, APCo committed to a schedule of no later than the Unit 2 fourth and Unit 1 seventh refueling outages for development j of detailed shutdown procedures for all fire areas other than a cable spreading room fire. During the development of the detailed shutdown procedure for exemption request #2-008 (fire area 2-005), an error in the :
exemption request was discovered. Installation of fire barriers for the cable trays in this area will not enture a source of RCS makeup water since the solenoids and their associated calles for the valves are unprotected.
As a result, attached is a revised copy of exemption request #2-008.
In addition, APCo was requested serbally by the NRC Staff to provide a list of fire doors to be included in g eneric exemption request #1-041.
Attached is a revised copy of the exemption request that includes a list of the fire doors.
8602040210gh$34e PDR ADOCK PDR ['I
( F
fir. L. S. Rubenstein January 27, 1986 U. S. Nuclear Regulatory Conunission Page 2 If there are any questions, please advise.
Yours very trul O y ,
( ( d'
/ iv' R. P. Mcdonald RPM /DHJ:ddb-043 Attachments cc: fir. L. B. Long Dr. J. N. Grace Mr. E. A. Reeves Mr. W. H. Bradford Mr. Dan Turner
_ .~ .-.
J. M. FARLEY NUCLEAR PLANT 10CFR50 APPENDIX "R" FIRE HAZARDS ANALYSIS REEVALUATION j .
EXEMPTION REQUEST: 2-8 Rev. 2 FIRE AREA: 2-005 LOCATION: UNIT-2 AU1ILIARY BUILDING. EL 100 FT-0 IN.. CHARGING PUMP ROOMS AND STORAGE AREAS Fire area 2-005 consists of the three charging pump rooms (2173, 2174, and 2181), a hallway (2172), a general storage area (2171), and a contaminated storage area (2182). The fire area boundary walls, floors, and ceilings are 3-h fire rated except 4
for the containment wall, and all fire area boundary doors are fire rated. Self expanding cork is installed between the fire area boundary walls and the containment wall.
EXEMPTION: An exemption to section III.G.2.a is requested to the extent that it requires a 3-h fire barrier between redundant safe shutdown cabling and equipment. An exemption is requested to section III.G.2.c to the extent that it requires one train of redundant safe shutdown cable and equipment to be enclosed by a 1-h fire-rated barrier and the installation of an automatic fire suppression system.
CONDITION REOUIRING EXEMPTION:
Physical Separation of the Charging Pumps The fire area contains all three charging pumps, related valves and air handling units. Each charging pump is redundant to the other two. The redundant charging pumps, valves, and air handling units are located in separate rooms. The pump room walls internal to fire area 2-005 are watertight and of 2-ft-thick reinforced concrete. However, the watertight
,~
penetration seals and watertight doors in the subject walls are not fire rated.
Boration/ Makeup Room 2172 in fire area 2-005 contains the control cables and valves for the RWST charging pump suction (LCV11SB and LCV11SD),
the control cables and valves for the RWMT charging pump suction and boric acid dilution injection to the VCT (FCV0ll3B-A and FCV0ll4A-A). In addition control cables for the RWM to the boric acid blender a.id boric acid flow control valves (FCV0114B-A and FCV0t13A-A) transit this room. These components provide redundant suction of makeup water from the RWMT or the RWST. Complete fire barriers and full suppression coverage is not provided for the valves or cables. The analysis of the offects of a fire upon the subject cables in the area shows that 1
the RWST isolation valves could become electrically inoperative in the closed position or makeup to either the VCT or charging pump suction header could be isolated.
2-8-1 Rev. 2
, . ~ _
i J. M. FARLEY NUCLEAR PLANT l
10CFR50 APPENDIX "R" FIRE HAZARDS ANALYSIS REEVALUATION Reactor Coolant Boundary Integrity Control cables of the Train-A pressurizer power operated relief and blocking valves Q2B31PCV0445A-A and Q2B13MOV8000A-A and the reactor head vent valves Q2B13SV2213A-A and Q2B13SV2214A-A are located.in fire area 2-005. The subject cables are associated with the control function from the hot shutdown panel Q2H21NBAPP2605G-A. In addition control cables which shift control from the main control board to the hot shutdown panel via the transfer relay cabinet Q2H22 LOO 2-A are in this area. A fire induced failure having multiple hot shorts could cause the reactor inventory to letdown via the PORV, and reactor head vent paths.
JUSTIFICATION:
Physical Separation of the Charging Pumps i The redundant charging pumps, valves, and air-handling units are located in independent, highly segregated rooms. Rooms 2171 and 2182 do not contain redundant safe shutdown cabling or equipment. An analysis was performed to demonstrate that a fire limited to one of the four areas identified below would not
- jeopardize the safe shutdown of the plant,
- 1. RM 2181 - Train-A Charging Pump Room
- 2. RM 2174 - Swing Charging Pump Room
- 3. RM 2173 - Train-B Charging Pump Room 3
- 4. RM's 2172, 2171, 2182 - Storage rooms and hallway The following justification is provided to show that a fire would be contained in one of the four areas listed above.
The charging pump rooms (2173, 2174, and 2181) are watertight i with 2-ft-thick reinforced concrete walls. The penetrations in the pump room walls internal to fire area 2-005 are sealed to provide a watertight boundary. The seals utilized to provide the watertight boundary are of the type (foam, welded plate, or grout) to provide an adequate barrier to inhibit the spread of fire, smoke, or gas. The doors are watertight and are normally i maintained closed. Lubricating oil and cable insulation are the only combustibles present in the pump rooms. Lubricating oil would be contained within the individual rooms or would drain into the sump pump servicing the room. In addition there is a fixed suppression system installed in room 2172 (hallway) which provides additional protection in the area of the pump room doors which communicate with this hallway. A smoke detection system is installed throughout the area including the three
- charging pump rooms. The maximum combustible loading in any room of this fire is estimated to be, less than 48,000 Btu /ft*
i with a maximum fire severity of less than 1 h. Based upon l the evaluation of the protection provided, a credible fire would 2-8-2 Rev. 2
J. M. FARLEY NUCLEAR PLANT 10CFR50 APPENDIX "R" FIRE HAZARDS ANALYSIS REEVALUATION be contained within the zone of its initiation. Credit has been taken for the separ-ation afforded by the subject pump room boundaries. As discussed during the NRC site exemption request walkdown, to ensure that the as-built configuration is maintained, the sealed penetrations shall be placed in the surveillance program.
Boration/ Makeup A fire barrier has been provided for raceway sections AHF15A, AHD128, AID 258, AID 12B and AID 15B in rooms 2182 and 2172 of fire area 2-005. These barriers protect cables for the boric acid flow control and the RWM to the boric acid blender valves (FCV0113A-A and FCV0114B-A) as they transit rooms 2182 and 2172 of fire area 2-005.
These subject barriers also provide protection for the RWMT charging pump suction, boric acid dilution injection to the VCT cables (FCV0113B-A and FCV0114A-A) and the redundant RWST charging pump suction train A cables (LCV0115B-A), with separation of approximately 19 feet. Partial suppression coverage is provided for the subject cables and valves in this area of FCV0113B-A and FCV0114A-A. There is approximately 15 feet of separation between the RWMT charging pump suction valve and cables (FCV0113B-A) and the redundant train B RWST suction valve and cables (FCV0113B-A) and the redundant train B RWST suction valve and cables (LCV01150-B). Again partial suppression coverage is provided in the area of FCV0113B-A and FCV0114A-A. Detection is provided in the aNa of the subject components. Due to the barriers provided; the spatial separation, detection and partial suppression coverage and the low insitu combustible loading (much of which has now been covered in a fire barrier) a credible exposure fire would not affect both redundant sources of borated makeup water. In the event of a fire in Room 2181, the Train B RWST isolation valve, LCV115D-B will be operable. An automatic suppression system covers the raceway to be protected with the exception of 18 feet of raceway sections AHF15A, AHD12B and AID 15B in Room 2172 and 10 feet of AHF15A and AHD12B in Room 2182.
In the unlikely event that a fire in this area caused a loss of these three independent sources of reactor makeup water, the additional fire barriers that have been installed in Rooms 2182 and 2172 will ensure that a fire induced RCS letdown will not exist thus increasing the time margin available to establish makeup.
Reactor decay heat will be sufficient to maintain RCS temperature and thereby prevent shrinkage of the RCS until manual action can be taken to restore makeup water. In addition, the Reactor Coolant Pump seal integrity can be maintained by the normal seal injection flow path f rom the VCT or by using Component Cooling Water. These flow paths will not be affected by a fire in this area; therefore, the integrity of the pump seals will not be jeopardized while makeup is being established.
Reactor Coolant Boundary Integrity Cables for the subject reactor coolant boundary integrity valves are also routed in the raceway for which the addition of a fire barrier was implemented under boration/
makeup. t$ased on the implementation of the modification implemented under boration/
makeup, the following scenario applies to a fire in Room 2181 only.
Fire induced failures (hot shorts) to the control cables for the transfer relay cabi-net Q2H22L002-A could cause control for the pressurizer power operated relief and blocking valves and the reactor head vent valves, to shift from their normal main control board alignment to the remote hot shutdown panel. Subsequent fire induced f ailures (hot shorts from adjacent control cables in the shared raceway) of the control cables for 2-8-3 Rev. 2
J. M. FARLEY NUCLEAR PLANT 10CPR50 APPENDIX "R" PIRE HAZARDS ANALYSIS REEVALUATION
~
Q2B31PCV0445A-A, pressurizer power operated relief valve Q2B13SV2213A-A, and Q2B13SV2214A-A reactor head vent valves, could result in the valves being energized to open. The power relief blocking valves (MOV) could become electrically inoperative in the open position. In the unlikely event of the multiple hot shorts occuring, this condition can be mitigated by removing power from the transfer relays and manual operation (handle) of the affected relay thereby shifting control to the main control board. To remove power from the transfer relay open breaker 9 on de distribution panel 2C (Q2R41LOOlC-A) located in Room 2312, fire area 2-004. Then go to transfer relay cabinet TRC-1 (Q2H22 LOO 2-A) in fire area 2-035 room 2347 and manually shift transfer relays TR1 (02B13SV2213A-A), TR2 (Q2B13SV2214A-A), TR3 (Q2B31PCV0445A-A), and TRS (Q2B31MOV8000A-A) placing control back to the main control board to allow the operator to mitigate the letdown.
FIRE AREA INFORMATION:
MAXIMUM ROOM NUMBERS / SHUTDOWN COMBUSTIBLE FIRE LOAD FIRE TITLES TRAIN MATERIAL QUANTITY (Btu /ft21 SEVERITY Room 2173 B Cable Insul. 148 lb 27,563 <30 min Charging / Lube Oil 35 gal Safety Injec-tion Pump Room Room 2174 A, B, C Cable Insul. 103 lb 28,508 <30 min Charging / Lube Oil 35 gal Safety Injec-tion Pump Room Room 2181 A Cable Insul. 625 lb 47.414 <1 h Charging / Lube Oil 35 gal Safety Injec-tion Pump Room i
Room 2171 Cable Insul.
Combustible Area (a)
! Room 2172 A, C Cable Insul. 2,393 lb(b)31,820(b)<30 min (b) l Hallway l Room 2182 . A Cable Insul.
- Contamination i Storage Area
- a. Room 2171 is utilized to store combustible material, usually in the form of contaminated clothing, cables, and tools in drums.
- b. Applies to rooms 2171, 2172, 2182 collectively.
w % e
J. M. PARLEY NUCLEAR PLANT 10CFR50 APPENDIX "R" FIRE HAZARDS ANALYSIS REEVALUATION DESIGN FEATURES:
Construction: Floors, ceilings, and walls forming the area boundary are of reinforced concrete. Self-expanding cork is installed between the fire area boundary walls and the containment.
Doors: A fire-rated airtight door is installed between rooms 2172 and 2161 (area 2-4).
Pipe and Electrical Penetrations: All penetrations through the area' boundary are scaled with silicone foam or Nelson fittings.
Ventilation: There is no normal ventilation for the area. There are four ventilation openings through the area ceiling into room 2223 (area 2-1): UL Class-A fire damper doors are installed in these openings. Fixed smoke removal capability is not provided.
Floor Drains: A 4-in. diameter floor drain having a 100-gal /m capacity is located in rooms 2173, 2174, and 2181, and drains to a separate sump for each room. The sumps for rooms 2173 and 2181 are located in the rooms while the sump for room 2174 is located immediately outside the room in room 2172. The sumps have two 100-gal /m pumps each that discharge to the waste holdup tank or to the floor drain tank. Four 4-in. diameter floor drains having a 100-gal /m capacity each are located throughout the remainder of the area and drain into the floor drain tank.
FIRE PROTECTION:
A smoke detection system is installed throughout this area. A manual hose station CO2 hose reel, portable dry chemical extinguishers, portable CO2 extinguishers, and portable smoke removal equipment located in the corridor just outside the area are available for use in the area. An automatic sprinkler system is installed in room 2172.
l 2-8-5 Rev. 2
J. M . rARLELNOC,L. EAR PLANT" _
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J. M. FARLEY NUCLEAR PLANT 10CFR50 APPENDIX "R" FIRE HAZARDS ANALYSIS REEVALUATION GENERIC EXEMPTION REQUEST: 1-41 Rev. 1 FIRE AREA: N/A LOCATION: FIRE AREAS IN THE UNIT 1 AND UNIT 2 AUXILIARY BUILDING, THE DIESEL GENERATOR BUILDING AND THE SERVICE WATER INTAKE STRUCTURE.
EXEMPTION Request exemption from the provision of 10CFR50, Appendix R III.G.2 to the extent that a deviation from the National Fire Protection Association Standard for Fire Doors and Windows (NFPA 80) which specifies the maximum clearance between the bottom of a fire-rated door and its sill or the floor results in the doors potentially having a rating of less than 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />. NFPA 80.3-6.1 states that the noncombustible clearance between the bottom of flush mounted doors and a raised noncombustible sill shall not exceed 3/8 inch, or where there is no sill, the maximum clearance between the bottom of the door and the floor shall not exceed 3/4 inch. The attached list of doors deviates slightly from this standard.
JUSTIFICATION Various doors in the fire area boundaries in the locations identified in the attachment exceed NFPA 80 gap specifications. In the majority of instances, the NFPA standard is exceeded by less than 3/4 inches. Most of the excess clearances result from an unintentional unevenness of or a deliberate slope in the poured concrete floors.
Smoke or heat detection systems are installed on both sides of the affected doors except as noted on the attached list. There are fourteen exceptions.
Eleven of these exceptions ir tolve stairwells; nine instances wherein the stairwell does not have detection, and two instances where small unprotected vestibules (Rooms 115 and 2115) are adjacent to protected stairwells. The remaining three exceptions involve doors between the diesel generator building switchgear rooms and the diesel generator-auxiliary building cable tunnels. These doors all have smoke detection on their diesel generator building side and automatic water suppression systems on their tunnel side.
The in-situ combustible loading in the vicinity of the bottom of the doors is minimal. Transient loads are unlikely to be located near the doors because access to fire doors is routinely kept clear. Since the excessive gaps are located at the bottom of the doors, passage of smoke and heat is minimized in the event of a fire. The results of a liquid spill near a door with excessive clearance would not differ significantly from one near a door with prescribed clearance since a flow path exists under both doors.
Therefore, the existence of the gaps at the bottom of the fire doors greater than those recommended in the NFPA 80 does not prevent each door from performing its intended function.
LIST OF FIRE DOORS THAT EXCEED NFPA MAXImlM GAP ALLOWANCE REFERENCE GENERIC EXEMPTION REQUEST 1-41 UNIT 1 000R NO. BETWEEN ROOMS LOCATION DESCRIPTION ELEV.
101 104 & Unit 2 Hallway to Unit 2 - WS 83' 150 155 & Unit 2 Hallway to Unit 2 - WS 100' 163 183 & 162 Hallway E of Spray Add Tank 100' 155 172 & 161 Corridor to Chg Pump Area 100' 102 103 & 107 Corridor to Storage Room 83'
- 105 Str. #2 & 115 Stairwell - WS to Spray Pumps 77' 165 116 & 185 Entry to Cable Chase - CCW 100' 169 Str. #1 & 185 Stairwell to CCW 100' 201 254 & Unit 2 HSP Room to Unit 2 121' 207 202 & 210 Communications Room 121' 202 205 & Unit 2 Hallway to Unit 2 - C 121'
- 205 208 & Str. #8 Stai rwell - ES 121' 203 207 & Unit 2 Corridor to Unit 2 - ES 121' 210 212 & 213 Battery Room 1B 121' 217 226 & 225 SWGR 1B to Charger Room 121' 216 213 & 225 Charger Room to Corridor 121' 211 213 & 214 Corridor to Battery Room A 121' 219 228 & 229 Corridor to SWGR Room - N 121' 223 234 & 235 Corridor to CRDM Room - N 121' 224 234 & 235 Corridor to CRDM Room - S 121'
- This door has automatic smoke / heat detection on one side only.
LIST OF FIRE DOORS THAT EXCEED NFPA MAXIM)M GAP ALLOWANCE REFERENCE GENERIC EXEMPTION REQUEST 1-41 UNIT 1 000R NO. BETWEEN ROOMS LOCATION DESCRIPTION ELEV.
225 234 & Str. #1 Stai rwell - WS 121' 227 233 & 235 CRDM to SWGR Room 121' 240 250 & 235 Half Door to Cable Chase - E 121' 301 319 & Unit 2 Corridor to Unit 2 - WS 139' 302 316 & Unit 2 Corridor to Unit 2 - C 139' 304- 309 & Unit 2 Big Door to Unit 2 - ES 139' 318 333 & 334 Room between Elect. Pen Rms - W 139' 311 317 & 322 Pen Filt Room 139' i 312 318 & 319 Corridor to Cable Spr Room - N 139' 324 335 & 338 SWGR Room to Cable Chase - M 139'
- _ 322 343 & 339 Corridor to SWGR Room - S 139' 447 429 & Str. #2 Stairwell to Radwaste Vent Room 155' 402 405 & Unit 2 Double Doors Corridor to 2 - ES 155' 411 409 & Str. #2 Stai rwell - WS 155' 0333 604 & Str. #10 Hallway to Stairwell 130' DIESEL BUILDING 0732 56C & Cable Tunnel SWGR Room to West Tunnel 155' i
734 56A & 56B Center Foyer to E SWGR 155' OThis door has automatic smoke / heat detection on one side only.
LIST OF FIRE DOORS THAT EXCEED NFPA MAXIMUM GAP ALLOWANCE REFERENCE GENERIC EXENPTION REQUEST 1-41 UNIT 1 000R NO. BETWEEN ROOMS LOCATION DESCRIPTION ELEV.
715 56A & 61 SWGR to 1-2A Diesel Room 155' 716 56A & 60 SWGR to 1C Diesel Room 155' 717 568 & 59 Foyer to 2B Diesel Room 155' 718 56C & 58 SWGR to IB Diesel Room 155' 719 56C & 57 SWGR to 2C Diesel Room 155' 701 71 & 61 South Hillway to 1-2A Diesel 155' 704 71 8 60 South Hallway to 1C Diesel Room 155' 707 71 & 59 South Hallway to 2B Diesel Room 155' 710 71 & 58 South Hallway to 1B Diesel Room 155' 713 71 & 57 South Hallway to 2C Diesel Room 155' 700 71 & 66 Hallway to 1-2A Day Tank Room 155' 703 71 & 65 Hallway to IC Day Tank Room 155' 706 71 & 64 Hallway to 2B Day Tank Room 155' 709 71 & 63 Hallway to IB Day Tank Room 155' 712 71 & 62 Hallway to 2C Day Tank Room 155'
- 731 56A & Cable Tunnel SWGR Room to East Tunnel Unit II 155'
- 733 56C & Cable Tunnel SWGR Room to West Tunnel Unit II 155' SERVICE WATER BUILDING 851 72C & 73 Foyer to IB Battery Room 155' 853 72D & 74 Foyer to 1A Battery Roon 155'
- This door has automatic smoke / heat detection on one side only.
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LIST OF FIRE DOORS THAT EXCEED NFPA MAXIM)M GAP ALLOWANCE REFERENCE GENERIC EXEMPTION REQUEST 1-41 UNIT 2 DOOR BETWEEN NO. ROOMS LOCATION DESCRIPTION ELEV.
- 2105 Str. #2 & 2115 Stair No. 2 77'
- 2154 Str. #8 & 2160 Stair No. 8 100' 2155 2172 & 2161 Corridor 100' 2159 Str. 2 & 2162 Hallway 100' 2163 2183 & 2162 Hallway 100' 2165 2197 & 2185 CCW HX Room 100' 2167 2198 & 218 CCW Hx Room 100' 2169 Str. #1 & 2185 Stair No.1 100'
- 2205 Str. #8 & 2207 Hatch Area 121' 2207 2202 & 2210 Corridor 121' 2212 Str. #2 & 2209 Hallway 121' 2215 2224 & 2225 Battery Charger Room 121' 2216 2225 & 2213 Battery Service Room 121' 2217 2226 & 2225 Battery Charger Room 121' 2222 2233 & 2228 Corridor 121' 2223 2235 & 2234 Hallway 121' 2224 2235 4 2234 Hallway 121' 2225 2234 & Str. #1 Stai r No. I 121' 2227 2235 & 2233 Switchgear Room 121'
- This door has automatic smoke / heat detection on one side only.
c LIST OF FIRE DOORS THAT EXCEED NFPA MAXIRM GAP ALLOWANCE REFERENCE GENERIC EXEMPTION REQUEST 1-41 UNIT 2 DOOR BETWEEN NO. ROOMS LOCATION DESCRIPTION ELEV.
2241 2249 & 2235 Control Sys. Cab. Room 121'
- 2305 Str. #8 & 2309 Hatch Area 139' 2312 2318 & 2319 Corridor 139' 2317 2334 & 2322 Hallway 139' 2318 2333 & 2334 Elec. Pene. Room 139' 2319 2337 & 2335 Load Center Room 139' 2322 2343 & 2339 Corridor 139' 2324 2338 & 2335 Load Center Room 139' 2329 2604 & 2602 Blow Down Panel Room 130'
- 2333 2604 & Str. #10 Stai r No.10 130'
- 2335 2609 & Str. #10 St ai r No.10 130' 2403 2405 & 406 Decon Room 155' 2404 2408 & 407 Hot Machine Shop 155' 2406 2405 & 407 Hot Machine Shop 155'
- 2407 2405 & Str. #8 Stair No. 8 155'
- 2431 2422 & Str. #10 Stair No. 10 155' 2439 2452 & Str. #1 Stair No. I 155' 2447 2429 & Str. #2 Stai r No. 2 155' 2327 2339 & 2346 MG Set Room 139'
- This door has automatic smoke / heat detection on one side only.
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