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Category:CORRESPONDENCE-LETTERS
MONTHYEARL-99-035, Forwards non-proprietary & Proprietary Versions of Farley Units 1 & 2 LBB Calculation Results Due to SG Replacement & SG Snubber Elimination Programs, Used to Support SG Replacement Project.Proprietary Encl Withheld1999-10-18018 October 1999 Forwards non-proprietary & Proprietary Versions of Farley Units 1 & 2 LBB Calculation Results Due to SG Replacement & SG Snubber Elimination Programs, Used to Support SG Replacement Project.Proprietary Encl Withheld ML20217G0801999-10-0707 October 1999 Informs That on 990930,staff Conducted mid-cycle PPR of Farley & Did Not Identify Any Areas in Which Performance Warranted More than Core Insp Program.Nrc Will Conduct Regional Insps Associated with SG Removal & Installation ML20217P0661999-10-0606 October 1999 Requests Withholding of Proprietary Rept NSD-SAE-ESI-99-389, Farley Units 1 & 2 LBB Calculation Results Due to SG Replacement & SG Snubber Elimination Programs ML20217B1891999-10-0404 October 1999 Submits Clarification Re Development of Basis for Determining Limiting Internal Pressure Loads Re Review of NRC SE for Cycle 16 Extension Request.Util Intends to Use Guidelines When Evaluating SG Tube Structural Integrity ML20212J8391999-09-30030 September 1999 Forwards RAI Re Request for Amends to Ts.Addl Info Needed to Complete Review to Verify That Proposed TS Are Consistent with & Validate Design Basis Analysis.Request Discussed with H Mahan on 990930.Info Needed within 10 Days of This Ltr ML20212J8801999-09-30030 September 1999 Discusses GL 98-01,suppl 1, Y2K Readiness of Computer Sys at Npps. Util 980731,990607 & 03 Ltrs Provided Requested Info in Subj Gl.Nrc Considers Subj GL to Be Closed for Unit 1 L-99-032, Responds to NRC Re Adequacy of Kaowool Fire Retardant Fire Barriers in Use at Jfnp,Units 1 & 21999-09-23023 September 1999 Responds to NRC Re Adequacy of Kaowool Fire Retardant Fire Barriers in Use at Jfnp,Units 1 & 2 L-99-034, Forwards Comments on Draft Current Tech Specs Discussion of Change Tables for Jm Farley Nuclear Plant.Units 1 & 21999-09-23023 September 1999 Forwards Comments on Draft Current Tech Specs Discussion of Change Tables for Jm Farley Nuclear Plant.Units 1 & 2 ML20212F8861999-09-23023 September 1999 Forwards Revised Relief Request Number 32 for NRC Approval. Approval Requested by 991231 to Support Activities to Be Performed During Unit 1 Refueling Outage Scheduled for Spring of 2000 ML20212E7031999-09-23023 September 1999 Responds to GL 98-01, Year 2000 Readiness of Computer Sys at Npps. Util Requested to Submit Plans & Schedules for Resolving Y2K-related Issues ML20212F1111999-09-21021 September 1999 Discusses Closeout of GL 97-06, Degradation of Steam Generator Internals ML20212C2351999-09-16016 September 1999 Submits Corrected Info Concerning Snoc Response to NRC GL 99-02, Lab Testing of Nuclear-Grade Activated Charcoal ML20212D0101999-09-15015 September 1999 Informs That Submittal of clean-typed Copy of ITS & ITS Bases Will Be Delayed.Delay Due to Need for Resolution of Two Issues Raised by NRC staff.Clean-typed Copy of ITS Will Be Submitted within 4 Wks Following Resolution of Issues ML20212C4641999-09-13013 September 1999 Forwards Info Requested in Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Exams L-99-031, Informs NRC That Review of MOV Testing Frequency & Changes Made to Frequency of MOV Testing Has Been Completed1999-09-13013 September 1999 Informs NRC That Review of MOV Testing Frequency & Changes Made to Frequency of MOV Testing Has Been Completed ML20212C8041999-09-10010 September 1999 Responds to to D Rathbun Requesting Review of J Sherman Re Y2K Compliance.Latest NRC Status Rept on Y2K Activities Encl ML20212D4581999-09-10010 September 1999 Responds to to D Rathbun,Requesting Review of J Sherman Expressing Concerns That Plant & Other Nuclear Plants Not Yet Y2K Compliant ML20212A6951999-09-0909 September 1999 Requests That Licensees Affected by Kaowool Fire Barriers Take Issue on Voluntary Initiative & Propose Approach for Resolving Subj Issues.Staff Plans to Meet with Licensees to Discuss Listed Topics ML20212A8341999-09-0909 September 1999 Requests That Licensees Affected by Kaowool Fire Barriers Take Issue on Voluntary Initiative & Propose Approach for Resolving Subj Issues.Staff Plans to Meet with Licensees to Discuss Listed Topics ML20211N8041999-09-0808 September 1999 Informs That on 990930 NRC Issued GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design-Basis Accident Condition, to Holders of Nuclear Plant Operating Licenses ML20211N4301999-09-0808 September 1999 Discusses Proposed Meeting to Discuss Kaowool Fire Barriers. Staff Requesting That Affected Licensees Take Issue on Voluntary Initative & Propose Approach for Resolving Issues ML20212C0071999-09-0202 September 1999 Forwards Insp Repts 50-348/99-05 & 50-364/99-05 on 990627- 0807.No Violations Noted.Licensee Conduct of Activities at Farley Plant Facilities Generally Characterized by safety-conscious Operations & Sound Engineering ML20211Q4801999-09-0101 September 1999 Informs That on 990812-13,Region II Hosted Training Managers Conference on Recent Changes to Operator Licensing Program. List of Attendees,Copy of Slide Presentations & List of Questions Received from Participants Encl ML20211K2131999-08-31031 August 1999 Informs That Snoc Has Conducted Review of Reactor Vessel Integrity Database,Version 2 (RVID2) & Conclude That Latest Data Submitted for Farley Units Has Not Been Incorporated Into RVID2 ML20211K4101999-08-31031 August 1999 Resubmits Relief Requests Q1P16-RR-V-5 & Q2P16-RR-V-5 That Seek to Group V661 Valves from Each Unit Into Sample Disassembly & Insp Group,Per 990525 Telcon with NRC L-99-030, Forwards SNC Review Comments on Draft SE & marked-up Copy of Draft SE Incorporating SNC Comments Re Proposed Conversion to ITS1999-08-30030 August 1999 Forwards SNC Review Comments on Draft SE & marked-up Copy of Draft SE Incorporating SNC Comments Re Proposed Conversion to ITS ML20211G6851999-08-26026 August 1999 Informs That During Insp,Technical Issues Associated with Design,Installation & fire-resistive Performance of Kaowool Raceway fire-barriers Installed at Farley Nuclear Plant Were Identified L-99-029, Forwards Revised Response to Chapter 3.1 RAI Requested in 990726 Conference Call,Rai Response Related to Beyond Scope Issue for Chapter 3.5 Requested by Conference Call on 990805 & RAI Response to Chapter 3.8 Requested on 990615 & 07271999-08-19019 August 1999 Forwards Revised Response to Chapter 3.1 RAI Requested in 990726 Conference Call,Rai Response Related to Beyond Scope Issue for Chapter 3.5 Requested by Conference Call on 990805 & RAI Response to Chapter 3.8 Requested on 990615 & 0727 ML20211B9431999-08-17017 August 1999 Forwards Fitness for Duty Performance Data for six-month Reporting Period 990101-990630,IAW 10CFR26.71(d).Rept Covers Employees at Jm Farley Nuclear Plant & Southern Nuclear Corporate Headquarters ML20211B9211999-08-17017 August 1999 Responds to NRC Re Violations Noted in Insp Rept 50-348/99-09 & 50-364/99-09.Corrective Actions:Security Response Plan Was Revised to Address Vulnerabilities Identified During NRC Insp ML20210R5101999-08-12012 August 1999 Forwards Revised Page 6 to 990430 LAR to Operate Farley Nuclear Plant,Unit 1,for Cycle 16 Only,Based on risk- Informed Approach for Evaluation of SG Tube Structural Integrity,As Result of Staff Comments ML20212C8141999-08-0909 August 1999 Forwards Correspondence Received from Jm Sherman.Requests Review of Info Re Established Policies & Procedures ML20210T2021999-08-0606 August 1999 Forwards Draft SE Accepting Licensee Proposed Conversion of Plant,Units 1 & 2 Current TSs to Its.Its Based on Listed Documents ML20210Q4641999-08-0505 August 1999 Informs That NRC Plans to Administer Gfes of Written Operator Licensing Exam on 991006.Authorized Representative of Facility Must Submit Ltr to La Reyes,As Listed,With List of Individuals to Take exam,30 Days Before Exam Date ML20210J8341999-07-30030 July 1999 Forwards Second Request for Addl Info Re Util 990430 Amend Request to Allow Util to Operate Unit 1,for Cycle 16 Based on risk-informed Probability of SG Tube Rupture & Nominal accident-induced primary-to-second Leakage ML20210G4901999-07-30030 July 1999 Responds to GL 99-02, Laboratory Testing of Nuclear-Grade Activated Charcoal, Issued 990603.Ltr Contains NRC License Commitment to Utilize ASTM D3803-1989 with Efficiency Acceptance Criteria Utilizing Safety Factor of 2 L-99-028, Responds to NRC 990730 RAI Re 990423 OL Change Request to Allow for Risk Informed Approach for Evaluation of SG Tube Structural Integrity as Described by NEI 97-06, SG Program Guidelines1999-07-30030 July 1999 Responds to NRC 990730 RAI Re 990423 OL Change Request to Allow for Risk Informed Approach for Evaluation of SG Tube Structural Integrity as Described by NEI 97-06, SG Program Guidelines L-99-027, Addresses Clarifications to Selected Responses to Chapter 3.8 RAI Requested in NRC Conference Call on 990624, Resolution of Open Issue Related to Containment Purge in Chapter 3.6 & Response Related to Chapter 3.51999-07-27027 July 1999 Addresses Clarifications to Selected Responses to Chapter 3.8 RAI Requested in NRC Conference Call on 990624, Resolution of Open Issue Related to Containment Purge in Chapter 3.6 & Response Related to Chapter 3.5 ML20210G8181999-07-26026 July 1999 Forwards Insp Repts 50-348/99-04 & 50-364/99-04 on 990516- 0626.One Violation Identified & Being Treated as Noncited Violation IR 05000348/19990091999-07-23023 July 1999 Discusses Insp Repts 50-348/99-09 & 50-364/99-09 on 990308- 10 & Forwards Notice of Violation Re Failure to Intercept Adversary During Drills,Contrary to 10CFR73 & Physical Security Plan Requirements ML20210E4071999-07-22022 July 1999 Responds to NRC 990702 RAI Re Change Request to Allow for Risk Informed Approach for Evaluation of SG Tube Structural Integrity as Described in NEI 97-06, SG Program Guidelines L-99-026, Forwards Response to NRC 990702 RAI Re SG Replacement Related TS Change Request Submitted 981201.Ltr Contains No New Commitments1999-07-19019 July 1999 Forwards Response to NRC 990702 RAI Re SG Replacement Related TS Change Request Submitted 981201.Ltr Contains No New Commitments L-99-264, Responds to NRC 990603 Administrative Ltr 99-02, Operating Licensing Action Estimates, for Fy 2000 & 20011999-07-13013 July 1999 Responds to NRC 990603 Administrative Ltr 99-02, Operating Licensing Action Estimates, for Fy 2000 & 2001 ML20209H4721999-07-13013 July 1999 Responds to NRC 990603 Administrative Ltr 99-02, Operating Licensing Action Estimates, for Fy 2000 & 2001 ML20196J6191999-07-0202 July 1999 Forwards Final Dam Audit Rept of 981008 of Category 1 Cooling Water Storage Pond Dam.Requests Response within 120 Days of Date of Ltr 05000364/LER-1999-001, Forwards LER 99-001-00 Re Reactor Trip Due to Loss of Condenser Vacuum Steam Dump Drain Line Failure.Commitments Made by Licensee,Listed1999-07-0202 July 1999 Forwards LER 99-001-00 Re Reactor Trip Due to Loss of Condenser Vacuum Steam Dump Drain Line Failure.Commitments Made by Licensee,Listed ML20196J7471999-07-0202 July 1999 Forwards RAI Re Cycle 16 Extension Request.Response Requested within 30 Days of Date of Ltr ML20196J5781999-07-0202 July 1999 Forwards RAI Re 981201 & s Requesting Amend to TS Associated with Replacing Existing Westinghouse Model 51 SG with Westinghouse Model 54F Generators.Respond within 30 Days of Ltr Date ML20196J6571999-07-0202 July 1999 Discusses Closure to TAC MA0543 & MA0544 Re GL 92-01 Rev 1, Suppl 1,RV Structural Integrity.Nrc Has Revised Rvid & Releasing It as Rvid,Version 2 as Result of Review of Responses ML20196J3591999-06-30030 June 1999 Forwards SE of TR WCAP-14750, RCS Flow Verification Using Elbow Taps at Westinghouse 3-Loop Pwrs 1999-09-09
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARL-99-035, Forwards non-proprietary & Proprietary Versions of Farley Units 1 & 2 LBB Calculation Results Due to SG Replacement & SG Snubber Elimination Programs, Used to Support SG Replacement Project.Proprietary Encl Withheld1999-10-18018 October 1999 Forwards non-proprietary & Proprietary Versions of Farley Units 1 & 2 LBB Calculation Results Due to SG Replacement & SG Snubber Elimination Programs, Used to Support SG Replacement Project.Proprietary Encl Withheld ML20217P0661999-10-0606 October 1999 Requests Withholding of Proprietary Rept NSD-SAE-ESI-99-389, Farley Units 1 & 2 LBB Calculation Results Due to SG Replacement & SG Snubber Elimination Programs ML20217B1891999-10-0404 October 1999 Submits Clarification Re Development of Basis for Determining Limiting Internal Pressure Loads Re Review of NRC SE for Cycle 16 Extension Request.Util Intends to Use Guidelines When Evaluating SG Tube Structural Integrity L-99-034, Forwards Comments on Draft Current Tech Specs Discussion of Change Tables for Jm Farley Nuclear Plant.Units 1 & 21999-09-23023 September 1999 Forwards Comments on Draft Current Tech Specs Discussion of Change Tables for Jm Farley Nuclear Plant.Units 1 & 2 L-99-032, Responds to NRC Re Adequacy of Kaowool Fire Retardant Fire Barriers in Use at Jfnp,Units 1 & 21999-09-23023 September 1999 Responds to NRC Re Adequacy of Kaowool Fire Retardant Fire Barriers in Use at Jfnp,Units 1 & 2 ML20212F8861999-09-23023 September 1999 Forwards Revised Relief Request Number 32 for NRC Approval. Approval Requested by 991231 to Support Activities to Be Performed During Unit 1 Refueling Outage Scheduled for Spring of 2000 ML20212C2351999-09-16016 September 1999 Submits Corrected Info Concerning Snoc Response to NRC GL 99-02, Lab Testing of Nuclear-Grade Activated Charcoal ML20212D0101999-09-15015 September 1999 Informs That Submittal of clean-typed Copy of ITS & ITS Bases Will Be Delayed.Delay Due to Need for Resolution of Two Issues Raised by NRC staff.Clean-typed Copy of ITS Will Be Submitted within 4 Wks Following Resolution of Issues L-99-031, Informs NRC That Review of MOV Testing Frequency & Changes Made to Frequency of MOV Testing Has Been Completed1999-09-13013 September 1999 Informs NRC That Review of MOV Testing Frequency & Changes Made to Frequency of MOV Testing Has Been Completed ML20212C4641999-09-13013 September 1999 Forwards Info Requested in Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Exams ML20211K2131999-08-31031 August 1999 Informs That Snoc Has Conducted Review of Reactor Vessel Integrity Database,Version 2 (RVID2) & Conclude That Latest Data Submitted for Farley Units Has Not Been Incorporated Into RVID2 ML20211K4101999-08-31031 August 1999 Resubmits Relief Requests Q1P16-RR-V-5 & Q2P16-RR-V-5 That Seek to Group V661 Valves from Each Unit Into Sample Disassembly & Insp Group,Per 990525 Telcon with NRC L-99-030, Forwards SNC Review Comments on Draft SE & marked-up Copy of Draft SE Incorporating SNC Comments Re Proposed Conversion to ITS1999-08-30030 August 1999 Forwards SNC Review Comments on Draft SE & marked-up Copy of Draft SE Incorporating SNC Comments Re Proposed Conversion to ITS L-99-029, Forwards Revised Response to Chapter 3.1 RAI Requested in 990726 Conference Call,Rai Response Related to Beyond Scope Issue for Chapter 3.5 Requested by Conference Call on 990805 & RAI Response to Chapter 3.8 Requested on 990615 & 07271999-08-19019 August 1999 Forwards Revised Response to Chapter 3.1 RAI Requested in 990726 Conference Call,Rai Response Related to Beyond Scope Issue for Chapter 3.5 Requested by Conference Call on 990805 & RAI Response to Chapter 3.8 Requested on 990615 & 0727 ML20211B9431999-08-17017 August 1999 Forwards Fitness for Duty Performance Data for six-month Reporting Period 990101-990630,IAW 10CFR26.71(d).Rept Covers Employees at Jm Farley Nuclear Plant & Southern Nuclear Corporate Headquarters ML20211B9211999-08-17017 August 1999 Responds to NRC Re Violations Noted in Insp Rept 50-348/99-09 & 50-364/99-09.Corrective Actions:Security Response Plan Was Revised to Address Vulnerabilities Identified During NRC Insp ML20210R5101999-08-12012 August 1999 Forwards Revised Page 6 to 990430 LAR to Operate Farley Nuclear Plant,Unit 1,for Cycle 16 Only,Based on risk- Informed Approach for Evaluation of SG Tube Structural Integrity,As Result of Staff Comments ML20212C8141999-08-0909 August 1999 Forwards Correspondence Received from Jm Sherman.Requests Review of Info Re Established Policies & Procedures ML20210G4901999-07-30030 July 1999 Responds to GL 99-02, Laboratory Testing of Nuclear-Grade Activated Charcoal, Issued 990603.Ltr Contains NRC License Commitment to Utilize ASTM D3803-1989 with Efficiency Acceptance Criteria Utilizing Safety Factor of 2 L-99-028, Responds to NRC 990730 RAI Re 990423 OL Change Request to Allow for Risk Informed Approach for Evaluation of SG Tube Structural Integrity as Described by NEI 97-06, SG Program Guidelines1999-07-30030 July 1999 Responds to NRC 990730 RAI Re 990423 OL Change Request to Allow for Risk Informed Approach for Evaluation of SG Tube Structural Integrity as Described by NEI 97-06, SG Program Guidelines L-99-027, Addresses Clarifications to Selected Responses to Chapter 3.8 RAI Requested in NRC Conference Call on 990624, Resolution of Open Issue Related to Containment Purge in Chapter 3.6 & Response Related to Chapter 3.51999-07-27027 July 1999 Addresses Clarifications to Selected Responses to Chapter 3.8 RAI Requested in NRC Conference Call on 990624, Resolution of Open Issue Related to Containment Purge in Chapter 3.6 & Response Related to Chapter 3.5 ML20210E4071999-07-22022 July 1999 Responds to NRC 990702 RAI Re Change Request to Allow for Risk Informed Approach for Evaluation of SG Tube Structural Integrity as Described in NEI 97-06, SG Program Guidelines L-99-026, Forwards Response to NRC 990702 RAI Re SG Replacement Related TS Change Request Submitted 981201.Ltr Contains No New Commitments1999-07-19019 July 1999 Forwards Response to NRC 990702 RAI Re SG Replacement Related TS Change Request Submitted 981201.Ltr Contains No New Commitments L-99-264, Responds to NRC 990603 Administrative Ltr 99-02, Operating Licensing Action Estimates, for Fy 2000 & 20011999-07-13013 July 1999 Responds to NRC 990603 Administrative Ltr 99-02, Operating Licensing Action Estimates, for Fy 2000 & 2001 ML20209H4721999-07-13013 July 1999 Responds to NRC 990603 Administrative Ltr 99-02, Operating Licensing Action Estimates, for Fy 2000 & 2001 05000364/LER-1999-001, Forwards LER 99-001-00 Re Reactor Trip Due to Loss of Condenser Vacuum Steam Dump Drain Line Failure.Commitments Made by Licensee,Listed1999-07-0202 July 1999 Forwards LER 99-001-00 Re Reactor Trip Due to Loss of Condenser Vacuum Steam Dump Drain Line Failure.Commitments Made by Licensee,Listed L-99-024, Responds to NRC RAI Re Conversion to ITS for Chapters 3.4, 3.5,3.6,3.7,3.9 & 5.0,per 990419-20 Meetings with NRC1999-06-30030 June 1999 Responds to NRC RAI Re Conversion to ITS for Chapters 3.4, 3.5,3.6,3.7,3.9 & 5.0,per 990419-20 Meetings with NRC L-99-025, Forwards Rev 2 to Jfnp Security plan,FNP-0-M-99,IAW 10CFR50.4(b)(4).Attachment 1 Contains Summary of Changes & Amended Security Plan Pages.Encl Withheld from Public Disclosure Per 10CFR73.211999-06-30030 June 1999 Forwards Rev 2 to Jfnp Security plan,FNP-0-M-99,IAW 10CFR50.4(b)(4).Attachment 1 Contains Summary of Changes & Amended Security Plan Pages.Encl Withheld from Public Disclosure Per 10CFR73.21 ML20196J8631999-06-30030 June 1999 Submits Correction to Errors Contained in to NRC Re TS Changes Re Control Room,Penetration Room & Containment Purge Filtration Systems & Radiation Monitoring Instrumentation.Errors Do Not Require Rev of SA L-99-249, Submits Correction to Errors Contained in to NRC Re TS Changes Re Control Room,Penetration Room & Containment Purge Filtration Systems & Radiation Monitoring Instrumentation.Errors Do Not Require Rev of SA1999-06-30030 June 1999 Submits Correction to Errors Contained in to NRC Re TS Changes Re Control Room,Penetration Room & Containment Purge Filtration Systems & Radiation Monitoring Instrumentation.Errors Do Not Require Rev of SA L-99-224, Submits Rev to Unit 2 SG Tube voltage-based Repair Criteria Data Rept.Ltr Contains No Commitments1999-06-0707 June 1999 Submits Rev to Unit 2 SG Tube voltage-based Repair Criteria Data Rept.Ltr Contains No Commitments ML20195F1731999-06-0707 June 1999 Forwards Proprietary & non-proprietary Responses to NRC RAIs Re W TR WCAP-14750, RCS Flow Verification Using Elbow Taps at W 3-Loop Pwrs. W Proprietary Notice,Affidavit & Copyright Notice,Encl.Proprietary Info Withheld L-99-217, Forwards Proprietary & non-proprietary Responses to NRC RAIs Re W TR WCAP-14750, RCS Flow Verification Using Elbow Taps at W 3-Loop Pwrs. W Proprietary Notice,Affidavit & Copyright Notice,Encl.Proprietary Info Withheld1999-06-0707 June 1999 Forwards Proprietary & non-proprietary Responses to NRC RAIs Re W TR WCAP-14750, RCS Flow Verification Using Elbow Taps at W 3-Loop Pwrs. W Proprietary Notice,Affidavit & Copyright Notice,Encl.Proprietary Info Withheld L-99-225, Responds to GL 98-01, Yr 2000 Readiness of Computer Sys at Nuclear Power Plants1999-06-0707 June 1999 Responds to GL 98-01, Yr 2000 Readiness of Computer Sys at Nuclear Power Plants ML20195F0621999-06-0707 June 1999 Submits Rev to Unit 2 SG Tube voltage-based Repair Criteria Data Rept.Ltr Contains No Commitments ML20195E9581999-06-0707 June 1999 Responds to GL 98-01, Yr 2000 Readiness of Computer Sys at Nuclear Power Plants ML20195C6941999-05-28028 May 1999 Forwards Response to NRC RAI Re GL 96-05 for Farley Nuclear Plant.Farley Is Committing to Implement Phase 3 of JOG Program L-99-021, Forwards Response to RAI Re Conversion to ITSs for Chapter 3.3.Attachment II Includes Proposed Revs to Previously Submitted LAR Re Rais,Grouped by RAI number.Clean-typed Copies of Affected ITS Pages Not Included1999-05-28028 May 1999 Forwards Response to RAI Re Conversion to ITSs for Chapter 3.3.Attachment II Includes Proposed Revs to Previously Submitted LAR Re Rais,Grouped by RAI number.Clean-typed Copies of Affected ITS Pages Not Included L-99-203, Forwards Response to NRC RAI Re GL 96-05 for Farley Nuclear Plant.Farley Is Committing to Implement Phase 3 of JOG Program1999-05-28028 May 1999 Forwards Response to NRC RAI Re GL 96-05 for Farley Nuclear Plant.Farley Is Committing to Implement Phase 3 of JOG Program ML20195F2101999-05-24024 May 1999 Requests That Farley Nuclear Plant Proprietary Responses to NRC RAI Re W WCAP-14750, RCS Flow Verification Using Elbow Taps at W 3-Loop Pwrs, Be Withheld from Public Disclosure Per 10CFR2.790 L-99-180, Forwards Responses to NRC RAI Questions for Chapter 3.8 of Ts.Proposed Revs to TS Previously Submitted with LAR Related to RAI1999-04-30030 April 1999 Forwards Responses to NRC RAI Questions for Chapter 3.8 of Ts.Proposed Revs to TS Previously Submitted with LAR Related to RAI ML20206F4321999-04-30030 April 1999 Forwards Responses to NRC RAI Questions for Chapter 3.8 of Ts.Proposed Revs to TS Previously Submitted with LAR Related to RAI L-99-017, Forwards Responses to NRC RAI Questions for Chapters 3.1, 3.2,3.5,3.7 & 3.9 of Ts.Attached Pages Include Proposed Revs Previously Submitted LAR to Rais,Grouped by Chapters & RAI Numbers1999-04-30030 April 1999 Forwards Responses to NRC RAI Questions for Chapters 3.1, 3.2,3.5,3.7 & 3.9 of Ts.Attached Pages Include Proposed Revs Previously Submitted LAR to Rais,Grouped by Chapters & RAI Numbers ML20206C8021999-04-26026 April 1999 Forwards 1998 Annual Rept, for Alabama Power Co.Encls Contain Financial Statements for 1998,unaudited Financial Statements for Quarter Ending 990331 & Cash Flow Projections for 990101-991231 05000348/LER-1998-007, Forwards SG-99-04-001, Farley-1:Final Cycle 16 Freespan ODSCC Operational Assessment, as Committed to in Licensee & LER 98-007-00.Util Is Revising Plant Administrative SG Operating Leakage Requirements as Listed1999-04-23023 April 1999 Forwards SG-99-04-001, Farley-1:Final Cycle 16 Freespan ODSCC Operational Assessment, as Committed to in Licensee & LER 98-007-00.Util Is Revising Plant Administrative SG Operating Leakage Requirements as Listed L-99-015, Forwards Rev 1 to Jfnp Security plan,FNP-O-M-99,resulting from Implementation of Biometrics Sys.Changes Incorporate Changes Previously Submitted to NRC as Rev 28 by Licensee .Encl Withheld,Per 10CFR73.211999-04-21021 April 1999 Forwards Rev 1 to Jfnp Security plan,FNP-O-M-99,resulting from Implementation of Biometrics Sys.Changes Incorporate Changes Previously Submitted to NRC as Rev 28 by Licensee .Encl Withheld,Per 10CFR73.21 ML20206B4391999-04-21021 April 1999 Forwards Corrected ITS Markup Pages to Replace Pages in 981201 License Amend Requests for SG Replacement L-99-172, Forwards FNP Annual Radioactive Effluent Release Rept for 1998, IAW TSs Sections 6.9.1.8 & 6.9.1.9.Changes to ODCM Revs 16,17 & 18 Are Encl,Iaw TS Section 6.14.21999-04-21021 April 1999 Forwards FNP Annual Radioactive Effluent Release Rept for 1998, IAW TSs Sections 6.9.1.8 & 6.9.1.9.Changes to ODCM Revs 16,17 & 18 Are Encl,Iaw TS Section 6.14.2 ML20205S9501999-04-21021 April 1999 Forwards FNP Annual Radioactive Effluent Release Rept for 1998, IAW TSs Sections 6.9.1.8 & 6.9.1.9.Changes to ODCM Revs 16,17 & 18 Are Encl,Iaw TS Section 6.14.2 ML20205R0431999-04-13013 April 1999 Forwards Correction to 960212 GL 95-07 180 Day Response. Level 3 Evaluation for Pressure Locking Utilized Analytical Models.Encl Page Has Been Amended to Correct Error 1999-09-23
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- Satherr. Nuclear Operatng Company Pos Othee Box 1295 Bem.'vaham, M'Arra 35201 Telepcme 205 dGS5066 r ,
E.m 3 o, , ,,, Southern Nudear Operating Company
"'?n'] June 22, 1992 W' *th*0 e'eCI"C S) Stem
/
.a Nos. 50-348 50-364 %
t..t. lear Regulatory Commission U.
tocument Control Desk
,o .n. DC 20555 (
Josept. M. Farley Nuclear Plant Emeroency Response Data System Gentlemen:
~
=
During a telephone conversation held on June 12, 1992, Mr. John Jolicouer of the NRC requesteo additional information relating to the Emergency Response Data System Data Point Library for Farley Nuclear Plant which was submitted in a Southern Nuclear to NRC letter dated February 28, 1992.
Attachment I lists the questions regarding the five parameter data points in question. r. 'dN as Attachment 2 are the revised Reference Files for Units ' and 2.
If time are any additional questions, please advise.
5 Respectfully submitted, hh mY J. D,. Woodard JDW/BHW: map 2654 I
Attathments 1, 2 ,
cc: Mr. S. D. Ebneter Mr. S. T. Hoffman Mr. G. F. Maxwell f
.;u u u.) igj g
ip 9206290263 920622 PDR APOCK 05000348 PLR
~
S I
i ATTACHMENT 1 NRC Questions Regarding ERDS Parameter Data Points i
k.
rs e,
1 NRC Questions Pressuti zer Level What percont level corresponds to the top of the heaters and how many r gallons dci s that represent?
Reactor Vessel level udder PIEHum What is the distance from the top of the active fuel to the 100 percent level indication?
Reactor Vessel Level Upp3r Head What is the distance from the top of the active fuel to the 100 percent level indication?
EWST Level What is the conversion factor for feet to gallons?
Containment Sump level What is the conversion fa-tor for feet to gallons?
4 1
ATTACHMENT 2 Revised Data Point Library Reference Files l.
I i
i i
i
DATA POINT LIBRARY REFERENCE FILE Date: February 28, 1992 Reactor Unit: FAI Data Feeder: PPC/SPDS NRC ERDS Parameter: PRZR Level Point ID: LC 1600 A Plant Spec Point Desc: PRZR Leve) Avg 1 MA Generic /Cond Desc: Primary System Pressurizer Level Analog / Digital: A Engr Units / Dig States: %
Engr Units Conversion: N/A Minimum Instr Range: 0 t o Maximum Instr Range: 100%
Zero Foint
Reference:
PRZR Lowar Tap Reference Point Notes: 0% corresponds to 294 gallons and 100%
corresponds to 10,179 gallons. Top of heaters is 15% which corresponds to 1,777 gallons.
PROC or SENS: PROC Number of Sensors: 3 How Processed: Redundant Sensor Algorithm Avg Sensor Locations: At lower tap near bottom of PRZR Alarm / Trip Set Points: N/A NI Detector Power Supply Cut-Off Power Level: N/A NI' Detector Power Supply Turn-on Power level: N/A Instrument Failure Mode: Low Temperature Compensation for DP Transmitters: N/A Leve1 Reference Leg: ,
Wet Unique System Desc: Composite Avg from LT0459, LT0460 and LT0461.
Transmitters are calibrated for 6540f and 2,270 psia l
r !
- a. .
l hATA POINT LIBRARY-REFERENCE FILE
.- 'Date: February 28, 1992 Reactor Unit: FAl Data Feeder: PPC/SPDS NRC ERDS Parameter: REAC VES LEV Point Ju: LC 1603 Plant Spec Point Desc: Lowest Upper Plenum levei Generic /Cond Desc: Reactor Vessel Water Level
- Analog / Digital: A Engr Units / Dig States: %
Engr Units Conversion: N/A
. Minimum Instr Range: 0
. Maximum Instr Range: 100 Zero Point
Reference:
TAF Reference Point Notes: 0% is I ft. 1 in, above TAF. 100% is 9 ft. 9 in above TAF.
PROC or SENS: PROC Number of Sensors: 6 l How Processed: Lowest Sensor locations: Within the HJTC probe below the upper support plate
-Alarm / Trip Set Points: Sensor Delta-T Exceeding 2000F NI Detector Power Supply Cut-Off Power level: N/A NI Detector Power Supply _
Turn-on Power Level: N/A Instrument Failure Mode: Low Temperature Cc.,oensation for DP Transmiti.'rs: N/A Level Reference Leg: N/A Unique System Desc: RVL probes each contain 8 sensors (heated and unheated TCs). Uncovery cf a sensor causes the delta-T between the sensor TCs to exceed 2000 F.
Each ICCMS processor determines RVL by deduction from uncovered sensors.
. DATA POINT LIBRARY REFERENCE FILE Date: February 28, 1992 Reactor Unit: FAI
-Data feeder: PPC/SPDS i
NRC ERDS Parameter: REAC VES LEY Point ID: LC 1602 i
. Plant Spec Point Desc: Lowest Upper Head Level Generic /Cond Desc: Reactor Vessel Water Level Analog / Digital: A Engr Units / Dig States: %
Engr Units Conversion: N/A Minimum Instr Range: 0 Maximum instr Ra. ige: 100
.Zero Point
Reference:
TAF Reference Point Notes: 0% is 10 ft. 10 in, above TAF. JOS% is 13 ft.
8 in, above TAF.
PROC or SENS: PROC Number of Sensors: 2 l How Processed: Lowest Sensor-Locations: Within the HJTC probe a.bove the upper support plate 8,larm/ Trip _ Set Points: Sensor Delta-T Exceeding 2000 F NI Detector Power Supply
~ Cut-Off Power Level: N/A L NI Detector Power Supply Turn-on Power Level: N/A Instrument Failure Mode: Low Temperature Compensation for DP Transmitters: N/A Level Reference Leg: N/A Unique System Desc: RVL probes each contain 8 sensors (heated and unheated TCs). Uncovery of a sensor causes the delta-T between the sensor TCs to exceed 2000 F.
Each ICCMS processor determines RVL by deduction from uncovered sensors.
-DATA POINT LIBRARY REFERENCE-FILE
. Date: February 28, 1992 Reactor Unit: FAI Data Feeder:- PPC/SFDS NRC ERDS Parameter: BWST Level Point ID: LT 0501 Plant Spec Point Desc: RWST Level Channel 1 Generic /Cond Desc: Borated Water Storage Tank Level Analog / Digital: A Engr Units / Dig States: Feet Engr Units Conversion: 12,433 gallons per foot l Minimum Instr Range: 0 Maximum Instr Range: 40 Zero Point
Reference:
TNKBOT Reference Point Notes: N/A PROC or SENS: SENS Number of Sensors: 1 How Processed: N/A Sensor Locations: RWST Alarm / Trip Set Points: Lo 12.6 HI Detector Power Supply Cut-Off Power Level: N/A NI Detector Power Sepply Turn-on Power Level: N/A Instrument Failure Mode: Low Temperature Compensation for DP Transmitters: N/A Level Reference Leg: N/A Unique System Desc: One of two channels
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. DATA POINT LIBRARY REFERENCE FILE Date: February 28, 1992 Reactor-Unit: FAl Data Feeder: PPC/SPDS NRC ERDS Parameter: CTMNT SMP R Point ID: LC 1501 Plant Spec Point Desc: CTMT Sump Level Avg Generic /Cond Desc: Containment Sump Level-Analog / Digital: A Engr Units / Dig States: Feet Engr Units Conversion: 67,000 gallons per foot for lowest 6 ft. 6 in, and 42,500 galions per foot for upper 2 ft.
Minimum Instr Range: 0 Maximum Instr Range: 10 Zero Point
Reference:
Bottom of Sump Reference Point Notes: N/A PROC or SENS: PROC l Number of Sensors: 2 How Processed: . Redundant Sensor Algorithm Avg Sensor Locations: Containment Sump Alarm / Trip Set Point;: Lo 1.0, Hi 5.0 NI Detector Power Supply Cut-Off Power Level: N/A NI Detector Power Supply l- Turn-on Power Level: N/A i
Instrument Failure Mode: Low
' Temperature Compensation for DP Transmitters: N/A Level Reference Leg: N/A L Unique System Desc: Containment Sump Level Avg of LT 3594A and LT 3594B l i l
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. DATA POINT LIBRARY REFERENCE FILE
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Date: February 28, 1992 Reactor Unit: FA2 Data Feeder: PPC/SPDS NRC ERDS Parameter: PRZR Level Point ID: LC 1600 A Plant Spec' Point Desc: PRZR Level Avg 1 MA Generic /Cond Desc: Primary System Pressurizer Level Analog / Digital:- A Engr Units / Dig States: %
Engr Units Conversion: N/A Minimum Instr Range: 0
. Maximum Instr Range: 100%
Zero Point
Reference:
PRZR Lower Tap Reference Point Notes: 0% corresponds to_294 gallons and 100%
corresponds to 10,179 gallons. . Top of heaters is 15%.which corresponds to 1,777 gallons.
PROC or SENS: PROC Number of Sensors: 3 How Processed: Redundant Sensor Algorithm-Avg Sensor Locations: At lower tap near bottom of PRZR Alarm / Trip Set Points: N/A NI Detector Power Supply l Cut-Off' Power Level: N/A NI Detector Power Supply Turn-on Power level: N/A Instrument Failure Mode: Low Temperature Compeni.atun for DP Transmitters: N/A Level Reference Leg: Wet l Unique System Desc: Composite Avg from LT0459, LT0460 and LT0461.
Transmitters are calibrated for 6540F and 2,270 psia
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' DATA POINT LIBRARY REFERENCE FILE Date: February 28, 1992 Reactor Unit: FA2 Data Feeder: PPC/SPDS NRC ERDS Parameter: REAC VES LEY Point ID: LC 1603 Plant Spec Point Desc: Lowest Upper Flenum level Generic /Cond Desc: Reactor Vessel Water Level Analog / Digital: A Engr Units / Dig-States: %
Engr Units Conversion: N/A Minimum Instr Range: 0
-Maximum Instr Range: 100 Zero Point
Reference:
TAF Reference Point Notes: 0% is 1 ft. 1 in above TAF. 100% is 9 ft. 9 in. above TAF.
PROC or SENS: PROC Number of Sensors: -6 l
'How Processed: Lowest Sensor Locations: Withia tte HJTC probe below the upper support plate Alarm / Trip Set Doints: ' Sensor Delta-T Exceeding 2000F L NI Detector Power Supply
-Cut-Off Power Level: ' !A NI Detector Power Supply Turn-on Power Level: N/A
!.. Instrument Failure Mode: Low Temperature Compensation for DP Transmitters:- N/A Level Reference Leg: N/A
, Unique System Desc: RVL probes each contain 8 sensors (heated and unheated TCs). Uncovery of a sensor causes the delta-T between the sensor TCs to exceed 2000 F.
Each ICCMS processor determines RVL by deduction from uncovered sensors.
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g, ._ DATA POINT LIBRARY REFERENCE FILE r Date: February 28,-1992 Reactor Unit: FA2 Data Feeder: PPC/SPDS NRC ERDS Parameter: REAC VES LEV PointID: LC 1602 Plant Spec Point Desc: Lowest Upper Head Level Generic /Cond nesc: Reactor Vessel Water Level Analog / Digital: A Engr Units / Dig States: %
Engr Units Conversion: N/A Minimum Instr Range: 0 Maximum Instr Range: 100 Zero Point
Reference:
TAF
' Reference Point Notes: 0% is 10 ft.10 in, above IAF. 100% is 13 ft.
8 in, above TAF.
PROC or SENS: PROC Number of Sensors: 2 l
How: Processed: Lowest Sensor Locations: Within the HJTC probe above the upper support plate alarm / Trip Set Points: Sensor Delta-T Exceeding 2000 F NI Detector Power Supply Cut-Off Power Level: N/A NI Detector Power Supply Turn-on Power Level: N/A Instrument' Failure Mode: Low Tenperature Compensation for DP Transmitters: N/A Level Peference Leg: N/A J Unique System Desc: RVL probes each contain 8 sensors (heated and unheated TCs). Uncovery of a sensor causes the delta-T between the sensor TCs to exceed 2000 F.
Each ICCMS processor determines RVL by deduction from uncovered sensors.
4 DATA POINT LIBRARY-REFERENCE FILE Date: February 28, 1992 Reactor Unit: FA2 Data Feeder: PPC/SPDS NRC ERDS Parameter: BW5T tevel Point 10: LT 0501 Plant Spec Point Desc: RWST Level Channel 1 Generic /Cond Desc: Borated Water Storage Tank level Analog / Digital: A Engr Units / Dig States: leet Engr Units Conversion: 12,433 gallons per foot l Minimum Instr Range: 0-Maximum Instr Range: 40 Zero Point
Reference:
TNKBOT Reference Point Notes: N/A PROC or SENS: SENS Number of Sensors: 1 How Processed: N/A Sensor Locations: RWST Alarm / Trip Set Points: Lo 12.6 NI Detector Power Supply Cut-Off_ Power level: N/A NI Detector Power Supply Turn-on Power Level: N/A Instrument Failure Mode: Low Temperature Compensation for DP Transmitters: N/A Level Reference Leg: N/A Unique System Desc: One of two channels i
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DATA POINT LIBRARY REFERENCE FILE-Date: February 28, 1992 Reactor _. Unit: FA2 Data Feeder: PPC/SPDS NRC ERDS Parameter: CTMNT SMP R
~ Point ID: LC 1501 Plant Spec Point Desc: CTMT Sump Level Avg-Generic /Cond Desc: Containment Sump Level Analog / Digital: A Engr. Units / Dig States: Feet Engr Units Conversion: 61,000 gallons per foot for lowest 6 ft. 6 in.
i and 42,500 gallons per foot for upper 2 ft.
Minimum-Instr Range: 0 Maximum Instr Range:- _ 10 Zera Peint
Reference:
Bottom of Sump Reference Point Notes: N/A
> PROC or SENS: PROC l-Number of Sensors: 2 How Processed: Redundant Sensor Algorithm Avg Sensor Locations: Containment Sump Alarm / Trip Set Points: Le 1.0, Hi 5.0 NI Detector Power Supply Cut-Off Power Level: N/A L NI Detector Power Supply.
-Turn-on Power Level: N/A Instrument Failere. Mode: Low l Temperature Compensation l
.for DP' Transmitters: N/A Level Reference Leg: N/A
! Unique System Dese: Containment Sump Level Avg of LT 3594A and LT 35948 l-L