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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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_. . . _ _ _ . . _ . _ _ . . _ . . _ _ . . . . . _ - . _ _ _ . ._ __ __ - _ _ . _ . _ _ . . _ . _ _
Alabama Power Company 1
- 40 inverness Center Parkway Post Othce Box 1295 Ditmmgham. Alabama 35201 Telephone 205 868 5581 1
W. G. Hairston, lit - '
Senior Vee President Nuclear Orerations Magg3 gg the Golfhorn tdttitc systern I Docket No. 50-348 U. S. Nuclear Regulatory Commission i
ATTN: Document Control Desk Vashington, D. C. 20555 Gentlemen Joseph H. Farley Nuclear Plant -_ Unit 1 NRC Bulletin No. 88-11 Pressurizer surge Line Thermal Stratification
)
By let ter datbd March 3,1989, ' Alabama. Pover Company requested an alternate schedule-to that requested in Bulletin 88-11. A schedule of two years from receipt of the Bulletin was rquested to obtafn_the necessary additional monitoring. data. define thermal transients, perform all required analyses and update the stress and. fatigue analyses to ensure compliance with applicable code and regulatory requirements. The j requested schedule, though different from that stated in action 1.b of i Bulletin 88-11, was consistent with the requirement to. update the stress and fatigue analyses within two years as stated =in_ action 1.d of the Bulletin, j
-i Vestinghouse has performed a stress and fatigue analysis for Alabama Power Company of the Unit 1 pressurizer surge line including the effects of.
thermal stratification and striping. The results of'the analysis are contained in the enclosed VCAP from Vestinghouse. The existing surge line configurations for both units have been analyzed by this VCAP. The analysis indicates contact between the pipe and the pipe whip restraints on Unit 1. Even with this contact, the analysis has determined that Unit 1 pipe stress and the code fatigue cumulative usage factor are within the code allovables.
It is Alabama Pover Company's intent to develop-a' leak-before-break-(LBB) '
analysis for the Unit 1 surge line to allow the removal of the pipe whip restraints and _ thus eliminate the contact with the piping. The results of ;
c that analysis vill be submitted to the NRC for approval in accordance with GDC 4 vithin the next three months. After NRC reviev and approval of-the LBB analysis, Alabama Power Company vill remove the postulated pipe rupture of the surge line fromithe design basis. . Alabama Power Company currently plans on removing _the whip restraints within two refueling outages _following LBB approval. ,
The results of this plant specific _ analysis on Unit lidemonstrates -
j acceptance to the requirements of the ASME Code Section III, including i
both stress limits and fatigue usage, for the: full' licensed life of the-L unit. The enclosed report coapletes the response to NRC Bulletin 8f 'O
- j. for Farley Unit 1.
q l
l -l 9102060385 DR 910131 <
l: ADOCK 05000348 PDR
[- j
i e
U. S. Nuclear Regulatory commission-ATTH: Document Control Desk Page 2 3
Enclosures contain: ;
- 1. VCAP-12855 - Structural Evaluation of-the Farley Units 1 and 2 i Pressurizer Surge Lines, Considering the Effects of Thermal-Stratification (Proprietary). j
- 2. VCAP-12856 - Structural Evaluation of=the Farley Units 1 and 2-Pressurizer Surge-Lines, Considering the Effects of Thermal Stratification (Non-Proprietary).-
Also enclosed are a Vestinghouse authorization letter, CAV-91-122, i
- accompanying affidavit, Proprietary Information Notice, and Copyright Notice.
As VCAP 12855 contains information proprietary to Vestinghouse Electric Corporation,-it is supported by an-affidavit signed by Westinghouse, the.
owner of the information. The aftidavit sets forth the basis on"which the information may be withheld from public disclosure by the Commission and addresses with specificity the considerations listed in paragraph-(b)(4) of Section 2.790 of the Commission's regulations..
Accordingly, it is respectfully requested that the information which is ;
proprietary to Vestinghouse be withheld from public disclosure in accordance with 10 CFR Section 2.790 of the Commission's.: regulations.
Correspondence with respect to the copyright-or proprietary, aspects of the items listed above or the supporting Vestinghouse Affidavit.should
/
reference CAV-91-122 and should be-addressed to R.-P. DiPiazza, Manager, Operating Plant Licensing Support, Vestinghouse Electric Corporation, P. O. Eox 355, Pittsburgh, Pennsylvania. 15230-0355. 1 The sr!<rmation provided herein is;true to_the best of my knowledge and bellet. If you have any questions, please' advise.
-Respectfully submitted, ALABAMA POWER COMPANY-
\
VGH,III/JGSimaf2216 Enclosures
-SVORN TO AND SUBSCRIBED.BEFORE HE E
ct Mr. S. D. Ebneter
, 1991.
Mr. S. T. Hoffman THIS J /
- DAY 0F d u m y~ g th. G. Aaviell -
J7j6w) 7 l 4k)dl ~
( Not Public
/
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9
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Westinghouse Energy Systems - jj,3Mg,,,,,,
Electric Corporation '
,g33 January-29, 1991- )
CAW 91-122=
}
' Document Control Desk --
US Nuclear Regulatory Commission- l Washington, DC- 20555 -
- Attention: Dr.~ Thomas Murley,-. Director
- APPLICATION FOR WITHHOLDING. PROPRIETARY-INFORMATION FROM PUBLIC DISCLOSURE- 1.
Subject:
" Structural. Evaluation of the Farley Units 1 and' 2' Pressurizer _ Surge i Lines, Considering the Effects of Thermal Stratification" a (WCAP-12855) !
Dear Dr. Murley:
-1 The proprietary information for which withholding is being.recuested in ithe; -
above-referenced letter;is_ furtheruidet:tified -in Affidavit; CAU91-122 signed.by-the owner of the proprietary information,, Westinghouse ElectricL Corporation, The-affidavit, whicn accompanies-this-. letter,' sets.forth the basis-on-which.the information jaay' be~ withhelt from public_ disclosure; by the ; Commission and addresses with specificity .the considerstions'-listed-in paragraph -(b)(4) of 10-
~
CFR Section 2.790 of~the Commission's regulations.- -
i Accordingly,_ this ~ letter authorizes -the utilization of- the' accompanying- -
l Affidavit by Alabama -Power Company. 1 l Correspondence-with respect to the proprietary aspects.of: the application for t withholding or the: Westinghouse. affidavit should reference this letter,
. CAW 91-122, and should be addressed to the undersigned.-
Veryotruly yours,
. . iPiazza, Manag 'r Enclosures- ing Plant Licensing Support '
cc: C. M. Holzle, Esq.
Office of the : General Counsel, NRC-l- .
1
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[4-
~
Proprietary'Information Notice.
4 1
fransmitted herewith are proprietary and/or non proprietary; versions of j documents furnished to the NRC in connection with requests for generic-and/or-plant-specific review and approval _.- -
In order to conform _ to the requirements of.-10 CFR '2.790 of. the Commission's -I regulations concerning the protection of proprietary information .so submitted !
to the NRC, the information which_is proprietary in the' proprietary versions'is- ;
contained within brackett and where the proprietary information has-been - !
deleted in the non-proprietary versions, only the brackets _ remain 1(theJ information that-was contained.within the brackets intthe proprietary versions having been deleted). The justification for claiming,the information so1 designated as proprietary is indicated-in both versions-'by means of lower case letters (a) through (g) contained within parentheses located as'a superscript-immediately following the brackets enclosing each item of-information- being _
identified as proprietary or in the-margin opposite such-information'.- These-lower case letters refer to the types of information _ Westinghouse customarily holds in confidence identified in Sections (4)(ii)(a).through (4)(ii)(g) of the affidavit accompanying this transmittal pursuant to 10 CFR 2.790(b)(1)l..
J
' Copyright Notice The reports transmitted herewith eachLbear a Westinghouse copyright notice. q The NRC is permitted to make the number of copies of the information contained ;
in these reports which are necessary for its internal use'in connection with generic end plant specific reviews- and approvals as well as: the issuance, denial, amendment, transfer,f renewal, modification, suspension,- revocation, or violation of:a license, permit,_ order, or regulation subject to the I requirements- of 10 CFR 2.790 regarding restrictions on public disclosure to-the extent such information has been identified as proprietary by Westinghouse,' -!
copyright protection not withstanding. WithLrespectito,the non-proprietary- '
versions of these reports, the NRC .isl permitted _to _make the numberiof copies; beyond those necessary for its internal use-whichL are necessaryJin order to .
have one copy available for public viewing inLthe appropriate: docket files in the_ public document _ room in Washington, DC and in ' local public document rooms as may be required _by NRC regulations if the number of copies submitted is.
insufficient for this purpose. The NRC is not authorized to make copies _for the personal use of members of the-public who.make 'use of the NRC public document rooms. Copies made by-the NRC must include the-copyright noticeiin all -instances and the . proprietary notice if theLoriginal was-identified as proprietary.
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l CAW-91-122 i
-AFFIDAVIT ;
-COMMONWEALTH OF PENNSYLVANIA:
Ss COUNTY OF ALLEGHENY:
Before me, the undersigned authority, personally appeared -
Ronald-P DiPiazza, who, being by me duly sworn according to law, deposes and says that he is authorized to execute this Affidavit on behalf of Westinghouse Electric Corporation (" Westinghouse") and that ;
the averments of fact set forth in-this Affidavit are true and correct to the best of his knowledge, information,'and belief: _
4 t'
~Q t Ronak iazza, Manager Operating Plant Licensing Support Sworn to ond subscribed before me this 36'k. day of %"sw ,1991.
V Cf W&'M. t] Eld a Notary Public -
NOTARi/UEAL LoRRAINE M. PlPLICA, NOTARY P'JBLic McNROEVLLEeORo. ALLEGHENYCoVNTY MYCCNM:SS:CN EXPiAES DEO 14.1W Mer.cer Penr4yivam AsM02'antitP.'ets
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= ~ CAW-91 122 T
{
y (1) 1. am Manager, Operating Plant Licensing Support, in the Nuclear and- '
Advanced Technology Division,-of- the Westinghouse: Electric Corporation and as.such, I have been.specifically delegated the-function-of reviewing the proprietary information sought to be withh' eld- from-jeSlic disclosure in -
connection with nuclear power plant licensing and rulemaking proceedings, y and am authorized to apply for its' withholding on~ behalf.'of the Westinghouse Energy' Systems-Business Unit. i (2) I am making this Affidavit in conformance with the provisions of 10CFR' Section 2.790 of the Commission's regulations and in~ conjunction with the ,
Westinghouse application for withholding accompanying this Affidavit.
1 (3) I have personal knowledge' of the criteria and-procedures utilized -by.the-l Westinghouse Energy Systems Business Unit.in-designating information_as a trade secret, privileged or as confidential commercial or financial-information.
l '
(4) Pursuant to the provisions of paragraph (b)(4) of Section'2.790 of the Commission's regulations, the following is. furnished for consideration by the Commission in determining whether-the information sought to-be withheld :
from public disclosure should be withheld. ,
(i) .The information sought to be withheld' from public disclosure is owned
! and has been held in confidence by Westinghouse.
l-I i
.(
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-i CAW 91-!22 1
I (1) I am Manager, Operating Plant Licensing Support, in _the' Nuclear and Advanced Technology Division,'of the Westinghouse Electric Corporation-and as such, I have been specifically delegated the function of reviewing the proprietary information sought to be withheld from public disclosure in connection with nuclear power plant licensing and rulemaking proceedings, and am authorized to apply for its withholding on behalf of the Westinghc'4se Energy Systems Business Unit'.
(2) I am making this Affidavit in conformance with the provisions of 10CFR Section 2.790 of the Commission's: regulations and. in conjunction with the .
Westinghouse application for withholding accompanying this Affidavit, (3) I have personal knowledge of the criteria and proceduresLutilized by the ,
Westinghouse Energy Systems Business Unit in designating information as a-trade secret, privileged or as confidential commercial or financial ~ !
information.
(4) Pursuant to the provisions of- paragraph'(b)(4) of Section 2.790 of the Commission's _ regulations, the following is -furnished for1 consideration by' the Commission in determining whether the information' sought Lto_ be withheld from public disclosure should be withheld, (i) The information sought to be withheld from public disclosure is owned and has been held in confidence by Westinghouse.
R '
3- CAW-91-122.
d (ii) The information Lis of a type _ customarily heldLin . confidence by Westinghouse and not customarily disclosed to:the public.
Westinghouse has a rational basis- for determining the. types of-information customarily held in confidence bylit and, in that--
connection, utilizes a system to: determine .when and whether to hold-certain types of-information;in confidence. .The application of that ,
system and the substance of that; system constitutes Westinghouse-policy and provides the rational basis 1 required.
Under that system, information is hel'd in confidence if it falls in I one or more of-several types, the release-of wh'ich mightL;esultnin the ;
, loss of-an existing or potential competitive advantage, as-follows:-
(a) The information reveals the distinguishing aspects.of~a process (or component, structure, tool, method,xetc.) where prevention of-
-its use by any of Westinghouse's competitors without license from Westinghouse constitutes a competitive economic advantage over I other' companies.
(b) It consists of supporting data, including-Ltest-data, -relative to i a process (or component,. structurei . tool, method, etc.),1the application of which data secures;a_ competitive economic advantage, e.g., by optimization or improved marketability.-
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l CAW 91-122 (c) Its use by a competitor would reduce his expenditure of resources or imprese his competitive position in the design, manufacture, shipment, installation, assurance of quality, or licensing a similar product.
(d) It reveals cost or price iriformation, production capacities, budget levels, or commercial strategies of Westinghouse, its customers or suppliers.
(e) It reveals aspects of past, present, or future Westinghouse or customer funded development plans and programs of potential commercial value to Westinghouse.
(f) It contains patentable ideas, for which patent protection may br.
desirable.
(g) It is not the property of Westinghouse, but must be treated as proprietary by Westinghouse according to agreements with the owner.
There are sound palicy reasons behind the Westinghouse system which include the following:
, (a) The use of such information by Westinghouse gives Westinghouse a competitive advantage over its competitors. It is, therefore, withheld from disclosure to protect the Westinghouse competitive position.
. _ . - - . . . . . _ ~ - -
l CAW-91-122' i
(b) It is information which is marketable in many ways. The extent to which such-information is available'to competitors diminishes -
the Westinghouse-ability to sell products and services' involving the use of the information.
(c) Use by our competitor would pUt Westinghouse at~a competitive-disadvantage by reducing his expenditure of resources'at our' i expense.
(d) Each component of proprietary information pertinent'to a particular competitive advantageis potentially as- valuable as .j
-the total competitive advantage. If_ competitors acqui_re -
components of proprietary information, any one; component may be the key.to the entire puzzle, thereby depriving _ Westinghouse of a competitive advantage.
(e) Unrestricted disclosure would jeopardize th'e position of l - prominence of Westinghouse in.the world market, and thereby give a market advantage.to the competition of those countries.
(f). The Westinghouse capacity to invest corporate assets in-research_
and development depends upon the success in obtaining.and maintaining a competitive advantage.
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CAW-91-122 (iii) .The information-is being transmitted to the Commission in confidence and, under the provisions of 10CFR Section 2.790, it- -
is to be received in confidence by the Commission.
(iv) The information sought to be protected is not available inipublic-sources or available information has not been previously employed in the same original-manner or method to the best of our knowledge and belief. -!
(v) The proprietary information sought to be withheld in this submittal is that inichlis appropriately marked in " Structural Evaluation of the Farley Units 1 and 2 Pressurizer Surge Lines, Censidering the Effects of Thermal Stratification", _WCAPal2855, (Proprietary) foc Joseph M. Farley Units- 1 and_2, being transmitted by-the Alabama Power Company (APCo) -letter and-Application for Withholding Proprietary Information fromL Public Disclosure, Mr. W. G. Hairston 111, APCo, to_ Document _ Control Desk, to the Attention Dr. Thoma's Murley, January,1991. LThe proprietary information as submitted for use:by Alabama Pcwer Company for the -J. M. Farley Units 1- and- 2 is expected to be applicable in other licensee submittals in response 'to certain NRC requirements for pressurizer surge line structural.
evaluation's including thermal . stratification effects.
d 1
-i l
7- CAW 91-122.
t This information is part. of that which will enable Westinghouse-to: j (a) Provide documentation of the-methods for1 structural
- evaluations.'of- pressurizer surgeHline. j (b) Establish applicable ' analytical . technologies. )
(c) Establish the transient-and temperature profiles.
(d) Establish the applicable codes -and standards which are to be: I applied.
(d) Assist the customer'to obtain NRC approval. -t
- Further this information has substantial commercial- value as. i follows:-
(a) Westinghouse plans to sell thetuse' of similar information to: a its: customers for purposes of meeting'NRC:requirementsLfor licensing documentation.
(b) Westinghouse can sell' support'.and defense,of th'e techno1cgyi-to its customers in-the licensing process,
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-l CAW-91 122 i
Public disclosure of this proprietary information is likely to-cause substantial harm to the competitive position of Westinghouse because it would enhance _ the ability _ of competitors to provide similar sleeving services and licensing defense services for commercial power reactors without commensurate ,
expenses. Also, public disclosure of the information would enable others to use the information to meet NRC requirements for licensing documentation without purchasing the right to use the information.
The development of the technology described in' part by the information is the result of applying the results of many years J of experience in an intensive Westinghouse effort and the: i expenditure of a considerable sum of-money, .
In order for competitors of Westinghouse to duplicate this information, similar technical programs would-have .to-be performed and a significant manpower effort,--having the requisite talent and experience, would haa to be expended for developing testing and analytical methods and performing tests.
Further the deponent sayeth not.
_ _--_ _--_- _