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Category:CORRESPONDENCE-LETTERS
MONTHYEARL-99-035, Forwards non-proprietary & Proprietary Versions of Farley Units 1 & 2 LBB Calculation Results Due to SG Replacement & SG Snubber Elimination Programs, Used to Support SG Replacement Project.Proprietary Encl Withheld1999-10-18018 October 1999 Forwards non-proprietary & Proprietary Versions of Farley Units 1 & 2 LBB Calculation Results Due to SG Replacement & SG Snubber Elimination Programs, Used to Support SG Replacement Project.Proprietary Encl Withheld ML20217G0801999-10-0707 October 1999 Informs That on 990930,staff Conducted mid-cycle PPR of Farley & Did Not Identify Any Areas in Which Performance Warranted More than Core Insp Program.Nrc Will Conduct Regional Insps Associated with SG Removal & Installation ML20217P0661999-10-0606 October 1999 Requests Withholding of Proprietary Rept NSD-SAE-ESI-99-389, Farley Units 1 & 2 LBB Calculation Results Due to SG Replacement & SG Snubber Elimination Programs ML20217B1891999-10-0404 October 1999 Submits Clarification Re Development of Basis for Determining Limiting Internal Pressure Loads Re Review of NRC SE for Cycle 16 Extension Request.Util Intends to Use Guidelines When Evaluating SG Tube Structural Integrity ML20212J8391999-09-30030 September 1999 Forwards RAI Re Request for Amends to Ts.Addl Info Needed to Complete Review to Verify That Proposed TS Are Consistent with & Validate Design Basis Analysis.Request Discussed with H Mahan on 990930.Info Needed within 10 Days of This Ltr ML20212J8801999-09-30030 September 1999 Discusses GL 98-01,suppl 1, Y2K Readiness of Computer Sys at Npps. Util 980731,990607 & 03 Ltrs Provided Requested Info in Subj Gl.Nrc Considers Subj GL to Be Closed for Unit 1 L-99-032, Responds to NRC Re Adequacy of Kaowool Fire Retardant Fire Barriers in Use at Jfnp,Units 1 & 21999-09-23023 September 1999 Responds to NRC Re Adequacy of Kaowool Fire Retardant Fire Barriers in Use at Jfnp,Units 1 & 2 L-99-034, Forwards Comments on Draft Current Tech Specs Discussion of Change Tables for Jm Farley Nuclear Plant.Units 1 & 21999-09-23023 September 1999 Forwards Comments on Draft Current Tech Specs Discussion of Change Tables for Jm Farley Nuclear Plant.Units 1 & 2 ML20212F8861999-09-23023 September 1999 Forwards Revised Relief Request Number 32 for NRC Approval. Approval Requested by 991231 to Support Activities to Be Performed During Unit 1 Refueling Outage Scheduled for Spring of 2000 ML20212E7031999-09-23023 September 1999 Responds to GL 98-01, Year 2000 Readiness of Computer Sys at Npps. Util Requested to Submit Plans & Schedules for Resolving Y2K-related Issues ML20212F1111999-09-21021 September 1999 Discusses Closeout of GL 97-06, Degradation of Steam Generator Internals ML20212C2351999-09-16016 September 1999 Submits Corrected Info Concerning Snoc Response to NRC GL 99-02, Lab Testing of Nuclear-Grade Activated Charcoal ML20212D0101999-09-15015 September 1999 Informs That Submittal of clean-typed Copy of ITS & ITS Bases Will Be Delayed.Delay Due to Need for Resolution of Two Issues Raised by NRC staff.Clean-typed Copy of ITS Will Be Submitted within 4 Wks Following Resolution of Issues ML20212C4641999-09-13013 September 1999 Forwards Info Requested in Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Exams L-99-031, Informs NRC That Review of MOV Testing Frequency & Changes Made to Frequency of MOV Testing Has Been Completed1999-09-13013 September 1999 Informs NRC That Review of MOV Testing Frequency & Changes Made to Frequency of MOV Testing Has Been Completed ML20212C8041999-09-10010 September 1999 Responds to to D Rathbun Requesting Review of J Sherman Re Y2K Compliance.Latest NRC Status Rept on Y2K Activities Encl ML20212D4581999-09-10010 September 1999 Responds to to D Rathbun,Requesting Review of J Sherman Expressing Concerns That Plant & Other Nuclear Plants Not Yet Y2K Compliant ML20212A6951999-09-0909 September 1999 Requests That Licensees Affected by Kaowool Fire Barriers Take Issue on Voluntary Initiative & Propose Approach for Resolving Subj Issues.Staff Plans to Meet with Licensees to Discuss Listed Topics ML20212A8341999-09-0909 September 1999 Requests That Licensees Affected by Kaowool Fire Barriers Take Issue on Voluntary Initiative & Propose Approach for Resolving Subj Issues.Staff Plans to Meet with Licensees to Discuss Listed Topics ML20211N8041999-09-0808 September 1999 Informs That on 990930 NRC Issued GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design-Basis Accident Condition, to Holders of Nuclear Plant Operating Licenses ML20211N4301999-09-0808 September 1999 Discusses Proposed Meeting to Discuss Kaowool Fire Barriers. Staff Requesting That Affected Licensees Take Issue on Voluntary Initative & Propose Approach for Resolving Issues ML20212C0071999-09-0202 September 1999 Forwards Insp Repts 50-348/99-05 & 50-364/99-05 on 990627- 0807.No Violations Noted.Licensee Conduct of Activities at Farley Plant Facilities Generally Characterized by safety-conscious Operations & Sound Engineering ML20211Q4801999-09-0101 September 1999 Informs That on 990812-13,Region II Hosted Training Managers Conference on Recent Changes to Operator Licensing Program. List of Attendees,Copy of Slide Presentations & List of Questions Received from Participants Encl ML20211K2131999-08-31031 August 1999 Informs That Snoc Has Conducted Review of Reactor Vessel Integrity Database,Version 2 (RVID2) & Conclude That Latest Data Submitted for Farley Units Has Not Been Incorporated Into RVID2 ML20211K4101999-08-31031 August 1999 Resubmits Relief Requests Q1P16-RR-V-5 & Q2P16-RR-V-5 That Seek to Group V661 Valves from Each Unit Into Sample Disassembly & Insp Group,Per 990525 Telcon with NRC L-99-030, Forwards SNC Review Comments on Draft SE & marked-up Copy of Draft SE Incorporating SNC Comments Re Proposed Conversion to ITS1999-08-30030 August 1999 Forwards SNC Review Comments on Draft SE & marked-up Copy of Draft SE Incorporating SNC Comments Re Proposed Conversion to ITS ML20211G6851999-08-26026 August 1999 Informs That During Insp,Technical Issues Associated with Design,Installation & fire-resistive Performance of Kaowool Raceway fire-barriers Installed at Farley Nuclear Plant Were Identified L-99-029, Forwards Revised Response to Chapter 3.1 RAI Requested in 990726 Conference Call,Rai Response Related to Beyond Scope Issue for Chapter 3.5 Requested by Conference Call on 990805 & RAI Response to Chapter 3.8 Requested on 990615 & 07271999-08-19019 August 1999 Forwards Revised Response to Chapter 3.1 RAI Requested in 990726 Conference Call,Rai Response Related to Beyond Scope Issue for Chapter 3.5 Requested by Conference Call on 990805 & RAI Response to Chapter 3.8 Requested on 990615 & 0727 ML20211B9431999-08-17017 August 1999 Forwards Fitness for Duty Performance Data for six-month Reporting Period 990101-990630,IAW 10CFR26.71(d).Rept Covers Employees at Jm Farley Nuclear Plant & Southern Nuclear Corporate Headquarters ML20211B9211999-08-17017 August 1999 Responds to NRC Re Violations Noted in Insp Rept 50-348/99-09 & 50-364/99-09.Corrective Actions:Security Response Plan Was Revised to Address Vulnerabilities Identified During NRC Insp ML20210R5101999-08-12012 August 1999 Forwards Revised Page 6 to 990430 LAR to Operate Farley Nuclear Plant,Unit 1,for Cycle 16 Only,Based on risk- Informed Approach for Evaluation of SG Tube Structural Integrity,As Result of Staff Comments ML20212C8141999-08-0909 August 1999 Forwards Correspondence Received from Jm Sherman.Requests Review of Info Re Established Policies & Procedures ML20210T2021999-08-0606 August 1999 Forwards Draft SE Accepting Licensee Proposed Conversion of Plant,Units 1 & 2 Current TSs to Its.Its Based on Listed Documents ML20210Q4641999-08-0505 August 1999 Informs That NRC Plans to Administer Gfes of Written Operator Licensing Exam on 991006.Authorized Representative of Facility Must Submit Ltr to La Reyes,As Listed,With List of Individuals to Take exam,30 Days Before Exam Date ML20210J8341999-07-30030 July 1999 Forwards Second Request for Addl Info Re Util 990430 Amend Request to Allow Util to Operate Unit 1,for Cycle 16 Based on risk-informed Probability of SG Tube Rupture & Nominal accident-induced primary-to-second Leakage ML20210G4901999-07-30030 July 1999 Responds to GL 99-02, Laboratory Testing of Nuclear-Grade Activated Charcoal, Issued 990603.Ltr Contains NRC License Commitment to Utilize ASTM D3803-1989 with Efficiency Acceptance Criteria Utilizing Safety Factor of 2 L-99-028, Responds to NRC 990730 RAI Re 990423 OL Change Request to Allow for Risk Informed Approach for Evaluation of SG Tube Structural Integrity as Described by NEI 97-06, SG Program Guidelines1999-07-30030 July 1999 Responds to NRC 990730 RAI Re 990423 OL Change Request to Allow for Risk Informed Approach for Evaluation of SG Tube Structural Integrity as Described by NEI 97-06, SG Program Guidelines L-99-027, Addresses Clarifications to Selected Responses to Chapter 3.8 RAI Requested in NRC Conference Call on 990624, Resolution of Open Issue Related to Containment Purge in Chapter 3.6 & Response Related to Chapter 3.51999-07-27027 July 1999 Addresses Clarifications to Selected Responses to Chapter 3.8 RAI Requested in NRC Conference Call on 990624, Resolution of Open Issue Related to Containment Purge in Chapter 3.6 & Response Related to Chapter 3.5 ML20210G8181999-07-26026 July 1999 Forwards Insp Repts 50-348/99-04 & 50-364/99-04 on 990516- 0626.One Violation Identified & Being Treated as Noncited Violation IR 05000348/19990091999-07-23023 July 1999 Discusses Insp Repts 50-348/99-09 & 50-364/99-09 on 990308- 10 & Forwards Notice of Violation Re Failure to Intercept Adversary During Drills,Contrary to 10CFR73 & Physical Security Plan Requirements ML20210E4071999-07-22022 July 1999 Responds to NRC 990702 RAI Re Change Request to Allow for Risk Informed Approach for Evaluation of SG Tube Structural Integrity as Described in NEI 97-06, SG Program Guidelines L-99-026, Forwards Response to NRC 990702 RAI Re SG Replacement Related TS Change Request Submitted 981201.Ltr Contains No New Commitments1999-07-19019 July 1999 Forwards Response to NRC 990702 RAI Re SG Replacement Related TS Change Request Submitted 981201.Ltr Contains No New Commitments L-99-264, Responds to NRC 990603 Administrative Ltr 99-02, Operating Licensing Action Estimates, for Fy 2000 & 20011999-07-13013 July 1999 Responds to NRC 990603 Administrative Ltr 99-02, Operating Licensing Action Estimates, for Fy 2000 & 2001 ML20209H4721999-07-13013 July 1999 Responds to NRC 990603 Administrative Ltr 99-02, Operating Licensing Action Estimates, for Fy 2000 & 2001 ML20196J6191999-07-0202 July 1999 Forwards Final Dam Audit Rept of 981008 of Category 1 Cooling Water Storage Pond Dam.Requests Response within 120 Days of Date of Ltr 05000364/LER-1999-001, Forwards LER 99-001-00 Re Reactor Trip Due to Loss of Condenser Vacuum Steam Dump Drain Line Failure.Commitments Made by Licensee,Listed1999-07-0202 July 1999 Forwards LER 99-001-00 Re Reactor Trip Due to Loss of Condenser Vacuum Steam Dump Drain Line Failure.Commitments Made by Licensee,Listed ML20196J7471999-07-0202 July 1999 Forwards RAI Re Cycle 16 Extension Request.Response Requested within 30 Days of Date of Ltr ML20196J5781999-07-0202 July 1999 Forwards RAI Re 981201 & s Requesting Amend to TS Associated with Replacing Existing Westinghouse Model 51 SG with Westinghouse Model 54F Generators.Respond within 30 Days of Ltr Date ML20196J6571999-07-0202 July 1999 Discusses Closure to TAC MA0543 & MA0544 Re GL 92-01 Rev 1, Suppl 1,RV Structural Integrity.Nrc Has Revised Rvid & Releasing It as Rvid,Version 2 as Result of Review of Responses ML20196J3591999-06-30030 June 1999 Forwards SE of TR WCAP-14750, RCS Flow Verification Using Elbow Taps at Westinghouse 3-Loop Pwrs 1999-09-09
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARL-99-035, Forwards non-proprietary & Proprietary Versions of Farley Units 1 & 2 LBB Calculation Results Due to SG Replacement & SG Snubber Elimination Programs, Used to Support SG Replacement Project.Proprietary Encl Withheld1999-10-18018 October 1999 Forwards non-proprietary & Proprietary Versions of Farley Units 1 & 2 LBB Calculation Results Due to SG Replacement & SG Snubber Elimination Programs, Used to Support SG Replacement Project.Proprietary Encl Withheld ML20217P0661999-10-0606 October 1999 Requests Withholding of Proprietary Rept NSD-SAE-ESI-99-389, Farley Units 1 & 2 LBB Calculation Results Due to SG Replacement & SG Snubber Elimination Programs ML20217B1891999-10-0404 October 1999 Submits Clarification Re Development of Basis for Determining Limiting Internal Pressure Loads Re Review of NRC SE for Cycle 16 Extension Request.Util Intends to Use Guidelines When Evaluating SG Tube Structural Integrity L-99-034, Forwards Comments on Draft Current Tech Specs Discussion of Change Tables for Jm Farley Nuclear Plant.Units 1 & 21999-09-23023 September 1999 Forwards Comments on Draft Current Tech Specs Discussion of Change Tables for Jm Farley Nuclear Plant.Units 1 & 2 L-99-032, Responds to NRC Re Adequacy of Kaowool Fire Retardant Fire Barriers in Use at Jfnp,Units 1 & 21999-09-23023 September 1999 Responds to NRC Re Adequacy of Kaowool Fire Retardant Fire Barriers in Use at Jfnp,Units 1 & 2 ML20212F8861999-09-23023 September 1999 Forwards Revised Relief Request Number 32 for NRC Approval. Approval Requested by 991231 to Support Activities to Be Performed During Unit 1 Refueling Outage Scheduled for Spring of 2000 ML20212C2351999-09-16016 September 1999 Submits Corrected Info Concerning Snoc Response to NRC GL 99-02, Lab Testing of Nuclear-Grade Activated Charcoal ML20212D0101999-09-15015 September 1999 Informs That Submittal of clean-typed Copy of ITS & ITS Bases Will Be Delayed.Delay Due to Need for Resolution of Two Issues Raised by NRC staff.Clean-typed Copy of ITS Will Be Submitted within 4 Wks Following Resolution of Issues L-99-031, Informs NRC That Review of MOV Testing Frequency & Changes Made to Frequency of MOV Testing Has Been Completed1999-09-13013 September 1999 Informs NRC That Review of MOV Testing Frequency & Changes Made to Frequency of MOV Testing Has Been Completed ML20212C4641999-09-13013 September 1999 Forwards Info Requested in Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Exams ML20211K2131999-08-31031 August 1999 Informs That Snoc Has Conducted Review of Reactor Vessel Integrity Database,Version 2 (RVID2) & Conclude That Latest Data Submitted for Farley Units Has Not Been Incorporated Into RVID2 ML20211K4101999-08-31031 August 1999 Resubmits Relief Requests Q1P16-RR-V-5 & Q2P16-RR-V-5 That Seek to Group V661 Valves from Each Unit Into Sample Disassembly & Insp Group,Per 990525 Telcon with NRC L-99-030, Forwards SNC Review Comments on Draft SE & marked-up Copy of Draft SE Incorporating SNC Comments Re Proposed Conversion to ITS1999-08-30030 August 1999 Forwards SNC Review Comments on Draft SE & marked-up Copy of Draft SE Incorporating SNC Comments Re Proposed Conversion to ITS L-99-029, Forwards Revised Response to Chapter 3.1 RAI Requested in 990726 Conference Call,Rai Response Related to Beyond Scope Issue for Chapter 3.5 Requested by Conference Call on 990805 & RAI Response to Chapter 3.8 Requested on 990615 & 07271999-08-19019 August 1999 Forwards Revised Response to Chapter 3.1 RAI Requested in 990726 Conference Call,Rai Response Related to Beyond Scope Issue for Chapter 3.5 Requested by Conference Call on 990805 & RAI Response to Chapter 3.8 Requested on 990615 & 0727 ML20211B9431999-08-17017 August 1999 Forwards Fitness for Duty Performance Data for six-month Reporting Period 990101-990630,IAW 10CFR26.71(d).Rept Covers Employees at Jm Farley Nuclear Plant & Southern Nuclear Corporate Headquarters ML20211B9211999-08-17017 August 1999 Responds to NRC Re Violations Noted in Insp Rept 50-348/99-09 & 50-364/99-09.Corrective Actions:Security Response Plan Was Revised to Address Vulnerabilities Identified During NRC Insp ML20210R5101999-08-12012 August 1999 Forwards Revised Page 6 to 990430 LAR to Operate Farley Nuclear Plant,Unit 1,for Cycle 16 Only,Based on risk- Informed Approach for Evaluation of SG Tube Structural Integrity,As Result of Staff Comments ML20212C8141999-08-0909 August 1999 Forwards Correspondence Received from Jm Sherman.Requests Review of Info Re Established Policies & Procedures ML20210G4901999-07-30030 July 1999 Responds to GL 99-02, Laboratory Testing of Nuclear-Grade Activated Charcoal, Issued 990603.Ltr Contains NRC License Commitment to Utilize ASTM D3803-1989 with Efficiency Acceptance Criteria Utilizing Safety Factor of 2 L-99-028, Responds to NRC 990730 RAI Re 990423 OL Change Request to Allow for Risk Informed Approach for Evaluation of SG Tube Structural Integrity as Described by NEI 97-06, SG Program Guidelines1999-07-30030 July 1999 Responds to NRC 990730 RAI Re 990423 OL Change Request to Allow for Risk Informed Approach for Evaluation of SG Tube Structural Integrity as Described by NEI 97-06, SG Program Guidelines L-99-027, Addresses Clarifications to Selected Responses to Chapter 3.8 RAI Requested in NRC Conference Call on 990624, Resolution of Open Issue Related to Containment Purge in Chapter 3.6 & Response Related to Chapter 3.51999-07-27027 July 1999 Addresses Clarifications to Selected Responses to Chapter 3.8 RAI Requested in NRC Conference Call on 990624, Resolution of Open Issue Related to Containment Purge in Chapter 3.6 & Response Related to Chapter 3.5 ML20210E4071999-07-22022 July 1999 Responds to NRC 990702 RAI Re Change Request to Allow for Risk Informed Approach for Evaluation of SG Tube Structural Integrity as Described in NEI 97-06, SG Program Guidelines L-99-026, Forwards Response to NRC 990702 RAI Re SG Replacement Related TS Change Request Submitted 981201.Ltr Contains No New Commitments1999-07-19019 July 1999 Forwards Response to NRC 990702 RAI Re SG Replacement Related TS Change Request Submitted 981201.Ltr Contains No New Commitments L-99-264, Responds to NRC 990603 Administrative Ltr 99-02, Operating Licensing Action Estimates, for Fy 2000 & 20011999-07-13013 July 1999 Responds to NRC 990603 Administrative Ltr 99-02, Operating Licensing Action Estimates, for Fy 2000 & 2001 ML20209H4721999-07-13013 July 1999 Responds to NRC 990603 Administrative Ltr 99-02, Operating Licensing Action Estimates, for Fy 2000 & 2001 05000364/LER-1999-001, Forwards LER 99-001-00 Re Reactor Trip Due to Loss of Condenser Vacuum Steam Dump Drain Line Failure.Commitments Made by Licensee,Listed1999-07-0202 July 1999 Forwards LER 99-001-00 Re Reactor Trip Due to Loss of Condenser Vacuum Steam Dump Drain Line Failure.Commitments Made by Licensee,Listed L-99-024, Responds to NRC RAI Re Conversion to ITS for Chapters 3.4, 3.5,3.6,3.7,3.9 & 5.0,per 990419-20 Meetings with NRC1999-06-30030 June 1999 Responds to NRC RAI Re Conversion to ITS for Chapters 3.4, 3.5,3.6,3.7,3.9 & 5.0,per 990419-20 Meetings with NRC L-99-025, Forwards Rev 2 to Jfnp Security plan,FNP-0-M-99,IAW 10CFR50.4(b)(4).Attachment 1 Contains Summary of Changes & Amended Security Plan Pages.Encl Withheld from Public Disclosure Per 10CFR73.211999-06-30030 June 1999 Forwards Rev 2 to Jfnp Security plan,FNP-0-M-99,IAW 10CFR50.4(b)(4).Attachment 1 Contains Summary of Changes & Amended Security Plan Pages.Encl Withheld from Public Disclosure Per 10CFR73.21 ML20196J8631999-06-30030 June 1999 Submits Correction to Errors Contained in to NRC Re TS Changes Re Control Room,Penetration Room & Containment Purge Filtration Systems & Radiation Monitoring Instrumentation.Errors Do Not Require Rev of SA L-99-249, Submits Correction to Errors Contained in to NRC Re TS Changes Re Control Room,Penetration Room & Containment Purge Filtration Systems & Radiation Monitoring Instrumentation.Errors Do Not Require Rev of SA1999-06-30030 June 1999 Submits Correction to Errors Contained in to NRC Re TS Changes Re Control Room,Penetration Room & Containment Purge Filtration Systems & Radiation Monitoring Instrumentation.Errors Do Not Require Rev of SA L-99-224, Submits Rev to Unit 2 SG Tube voltage-based Repair Criteria Data Rept.Ltr Contains No Commitments1999-06-0707 June 1999 Submits Rev to Unit 2 SG Tube voltage-based Repair Criteria Data Rept.Ltr Contains No Commitments ML20195F1731999-06-0707 June 1999 Forwards Proprietary & non-proprietary Responses to NRC RAIs Re W TR WCAP-14750, RCS Flow Verification Using Elbow Taps at W 3-Loop Pwrs. W Proprietary Notice,Affidavit & Copyright Notice,Encl.Proprietary Info Withheld L-99-217, Forwards Proprietary & non-proprietary Responses to NRC RAIs Re W TR WCAP-14750, RCS Flow Verification Using Elbow Taps at W 3-Loop Pwrs. W Proprietary Notice,Affidavit & Copyright Notice,Encl.Proprietary Info Withheld1999-06-0707 June 1999 Forwards Proprietary & non-proprietary Responses to NRC RAIs Re W TR WCAP-14750, RCS Flow Verification Using Elbow Taps at W 3-Loop Pwrs. W Proprietary Notice,Affidavit & Copyright Notice,Encl.Proprietary Info Withheld L-99-225, Responds to GL 98-01, Yr 2000 Readiness of Computer Sys at Nuclear Power Plants1999-06-0707 June 1999 Responds to GL 98-01, Yr 2000 Readiness of Computer Sys at Nuclear Power Plants ML20195F0621999-06-0707 June 1999 Submits Rev to Unit 2 SG Tube voltage-based Repair Criteria Data Rept.Ltr Contains No Commitments ML20195E9581999-06-0707 June 1999 Responds to GL 98-01, Yr 2000 Readiness of Computer Sys at Nuclear Power Plants ML20195C6941999-05-28028 May 1999 Forwards Response to NRC RAI Re GL 96-05 for Farley Nuclear Plant.Farley Is Committing to Implement Phase 3 of JOG Program L-99-021, Forwards Response to RAI Re Conversion to ITSs for Chapter 3.3.Attachment II Includes Proposed Revs to Previously Submitted LAR Re Rais,Grouped by RAI number.Clean-typed Copies of Affected ITS Pages Not Included1999-05-28028 May 1999 Forwards Response to RAI Re Conversion to ITSs for Chapter 3.3.Attachment II Includes Proposed Revs to Previously Submitted LAR Re Rais,Grouped by RAI number.Clean-typed Copies of Affected ITS Pages Not Included L-99-203, Forwards Response to NRC RAI Re GL 96-05 for Farley Nuclear Plant.Farley Is Committing to Implement Phase 3 of JOG Program1999-05-28028 May 1999 Forwards Response to NRC RAI Re GL 96-05 for Farley Nuclear Plant.Farley Is Committing to Implement Phase 3 of JOG Program ML20195F2101999-05-24024 May 1999 Requests That Farley Nuclear Plant Proprietary Responses to NRC RAI Re W WCAP-14750, RCS Flow Verification Using Elbow Taps at W 3-Loop Pwrs, Be Withheld from Public Disclosure Per 10CFR2.790 L-99-180, Forwards Responses to NRC RAI Questions for Chapter 3.8 of Ts.Proposed Revs to TS Previously Submitted with LAR Related to RAI1999-04-30030 April 1999 Forwards Responses to NRC RAI Questions for Chapter 3.8 of Ts.Proposed Revs to TS Previously Submitted with LAR Related to RAI ML20206F4321999-04-30030 April 1999 Forwards Responses to NRC RAI Questions for Chapter 3.8 of Ts.Proposed Revs to TS Previously Submitted with LAR Related to RAI L-99-017, Forwards Responses to NRC RAI Questions for Chapters 3.1, 3.2,3.5,3.7 & 3.9 of Ts.Attached Pages Include Proposed Revs Previously Submitted LAR to Rais,Grouped by Chapters & RAI Numbers1999-04-30030 April 1999 Forwards Responses to NRC RAI Questions for Chapters 3.1, 3.2,3.5,3.7 & 3.9 of Ts.Attached Pages Include Proposed Revs Previously Submitted LAR to Rais,Grouped by Chapters & RAI Numbers ML20206C8021999-04-26026 April 1999 Forwards 1998 Annual Rept, for Alabama Power Co.Encls Contain Financial Statements for 1998,unaudited Financial Statements for Quarter Ending 990331 & Cash Flow Projections for 990101-991231 05000348/LER-1998-007, Forwards SG-99-04-001, Farley-1:Final Cycle 16 Freespan ODSCC Operational Assessment, as Committed to in Licensee & LER 98-007-00.Util Is Revising Plant Administrative SG Operating Leakage Requirements as Listed1999-04-23023 April 1999 Forwards SG-99-04-001, Farley-1:Final Cycle 16 Freespan ODSCC Operational Assessment, as Committed to in Licensee & LER 98-007-00.Util Is Revising Plant Administrative SG Operating Leakage Requirements as Listed L-99-015, Forwards Rev 1 to Jfnp Security plan,FNP-O-M-99,resulting from Implementation of Biometrics Sys.Changes Incorporate Changes Previously Submitted to NRC as Rev 28 by Licensee .Encl Withheld,Per 10CFR73.211999-04-21021 April 1999 Forwards Rev 1 to Jfnp Security plan,FNP-O-M-99,resulting from Implementation of Biometrics Sys.Changes Incorporate Changes Previously Submitted to NRC as Rev 28 by Licensee .Encl Withheld,Per 10CFR73.21 ML20206B4391999-04-21021 April 1999 Forwards Corrected ITS Markup Pages to Replace Pages in 981201 License Amend Requests for SG Replacement L-99-172, Forwards FNP Annual Radioactive Effluent Release Rept for 1998, IAW TSs Sections 6.9.1.8 & 6.9.1.9.Changes to ODCM Revs 16,17 & 18 Are Encl,Iaw TS Section 6.14.21999-04-21021 April 1999 Forwards FNP Annual Radioactive Effluent Release Rept for 1998, IAW TSs Sections 6.9.1.8 & 6.9.1.9.Changes to ODCM Revs 16,17 & 18 Are Encl,Iaw TS Section 6.14.2 ML20205S9501999-04-21021 April 1999 Forwards FNP Annual Radioactive Effluent Release Rept for 1998, IAW TSs Sections 6.9.1.8 & 6.9.1.9.Changes to ODCM Revs 16,17 & 18 Are Encl,Iaw TS Section 6.14.2 ML20205R0431999-04-13013 April 1999 Forwards Correction to 960212 GL 95-07 180 Day Response. Level 3 Evaluation for Pressure Locking Utilized Analytical Models.Encl Page Has Been Amended to Correct Error 1999-09-23
[Table view] Category:VENDOR/MANUFACTURER TO NRC
MONTHYEARML20059D4811990-08-14014 August 1990 Requests That Proprietary WCAP-12672, Steam Generator Sleeving Rept Laser Welded Sleeves Jm Farley Units 1 & 2, Be Withheld Per 10CFR2.790(b)(4) ML20043H5891990-06-15015 June 1990 Forwards Proprietary Presentation Matl, Steam Generator Tube Laser Welded Sleeving, Per 900607 Technical Meeting. Westinghouse Expects to Comply W/Requirement for Proprietary & Nonproprietary Versions.Encl Withheld ML20247N0271989-06-23023 June 1989 Requests That Proprietary Rev 1 to WCAP-11786, Jm Farley Unit 2 Engineering Evaluation of Weld Joint Crack in 6-Inch Safety Injection & RHR Piping, Be Withheld (Ref 10CFR2.790) ML20245K7691989-06-21021 June 1989 Responds to Violation Noted in Insp Repts 70-0135/89-02 & 70-0364/89-01 on 890410-13.Notice Should Be Withdrawn Based on Misunderstanding of Requirements & Circumstances of Entry/Exit Procedures for Eddy Current Area ML20058N8141989-01-0909 January 1989 Requests That Proprietary WCAP-11953, Safety Evaluation Supporting More Negative Eol Moderator Temp Coefficient Tech Spec for Joseph M Farley Nuclear Plant Units 1 & 2, Be Withheld Per 10CFR2.790 ML20151U2771988-06-16016 June 1988 Application for Withholding Proprietary Info from Rept, Qualification of ATWS Mitigating Sys Actuation Circuitry in Amco Cabinet & Wall Mounted Hoffman Relay Enclosure (Combined Testing & Analysis) ML20237L0441987-08-18018 August 1987 Requests That Proprietary Replacement Pages for Rev 2 to WCAP-11306 Be Withheld (Ref 10CFR2.790).Affidavit Encl ML20237L0291987-08-18018 August 1987 Requests That Encl Proprietary Replacement Pages for Rev 1 to WCAP 11178 Be Withheld (Ref 10CFR2.790) ML20235J4921987-06-23023 June 1987 Requests That Errata Sheet for Proprietary WCAP 11178,Rev 1 Be Withheld (Ref 10CFR2.790).Affidavit Encl ML20210D2371987-04-27027 April 1987 Requests That Proprietary Rev 1 to WCAP-11178, Steam Generator Sleeving Rept (Mechanical Sleeves), Be Withheld (Ref 10CFR2.790).Affidavit for Withholding Encl ML20210D2771987-04-27027 April 1987 Requests That Proprietary Rev 2 to WCAP 11306, Tubesheet Region Plugging Criterion for Alabama Power Co Farley Nuclear Station Unit 2 Steam Generators, Be Withheld from Public Disclosure,Per 10CFR2.790.Affidavit Encl ML20203H4441986-07-17017 July 1986 Forwards Certificates for Yr Ending 860331 Assuring B&W Ability to Cover Costs of Decommissioning All B&W Nuclear Facilities.Company Working Capital as of 860627 Significantly in Excess of Estimated Decommissioning Costs ML20076K9301983-09-0606 September 1983 Application for Withholding Proprietary Graph Depicting Elevation Dependent Peaking Factor Vs Core Height,In Support of 830825 Radial Peaking Factor Limit Rept.W/Affidavit ML20041G4811982-03-0505 March 1982 Requests Withholding of Proprietary Matl Re Fuel Assemblies Per Util Request (Ref 10CFR2.790).Affidavit Encl ML20062M4661981-11-13013 November 1981 Requests Withholding of Proprietary Info Contained in Response to NRC Inquiry Re Elevation Dependent Peaking Factor.Use of Encl Nonproprietary Affidavit AW-76-10 & Proprietary Affidavit 770302 Authorized ML19337A0621980-07-25025 July 1980 Forwards Setpoint Study for Farley 1 & 2, Proprietary (WCAP-8313) & Nonproprietary (WCAP-9768) Versions. Application & Affidavit for Withholding Encl ML19337B5901979-08-16016 August 1979 Submits Results of Radioactive Liner Test for Free Liquid. Tests Demonstrate Suitability of Urea Formaldehyde as Acceptable Solidification Media ML20151P3341969-12-31031 December 1969 Advises of Organization Changes at Numec 1990-08-14
[Table view] |
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Westinghouse Power Systems pjllu gh Pennsylvania 15230-0355 Electric Corporation i 1
August 18, 1987 l CAW-87-077 j 1
Dr. Thomas Murley, Director )
Office of Nuclear Reactor Regulation i U.S. Nuclear Regulatory Commission Washington, D.C. 20555 APPLICATION FOR WITHHOLDING PROPRIETARY l INFORMATION FROM PUBLIC DISCLOSURE j l
)
Subject:
Transmittal of Errata Sheets for WCAP-11306, Revision 2
Dear Dr. Murley:
I The proprietary material for which withho7 %g is being requested in the enclosed letter by the Alabama Pcwer Company is fu3 eer identified in an affidavit signed by the owner of the proprietary infonnation, westinghouse Electric Corporation. The affidavit, which accompanies this letter, 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 10CFR Section i 2.790 of the Commission's regulations.
The proprietary material for which withholding is being requested is of the same technical type as that proprietary material previously submitted with Application for Withholding CAW-81-079 j Accordingly, this letter authorizes the utilization of the accompanying affidavit by Alabama Power Company.
Correspondence with respect to the proprietary aspects of the application for withholding or the Westinghouse affidavit should reference this letter, CAW-87-077, and should be addressed to the unders'.gned.
Very truly yours,
- ccwcu
/dmr h rt A. Wiesemann, Manager Regulatory & Legislative Affairs Enclosure (s) cc: E. C. Shomaker, Esq.
Office of the General Council, NRC 8708270394 870825
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PDR ADOCK 05000348 .
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PDR
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i PROPRIETARY INFORMATION NOTICE TRANSMITTED HEREWITH ARE PROPRIETARY AND/OR NON-PROPRIETARY VERSIONS OF DOCUMENTS FURNISHED TO THE NRC IN CONNECTION WITH REQUESTS FOR GENERIC AND/OR PLANT SPECIFIC REVIEW AND APPROVAL.
i IN ORDER TO CONFORM TO THE REQUIREMENTS OF 10CFR2.790 0F THE COMMISSION'S REGULATIONS CONCERNING THE PROTECTION OF PROPRIETARY INFORMATION SO SUBMITTED TO THE NRC, THE INFORMATION WHICH IS PROPRIETARY IN THE PROPRIETARY VERSIONS IS CONTAINED WITHIN BRACKETS AND WHERE THE PROPRIETARY INFORMATION HAS BEEN DELETED IN THE NON-PROPRIETARY VERSIONS ONLY THE BRACKETS REMAIN, THE INFORMATION THAT WAS CONTAINED WITHIN THE BRACKETS IN THE PROPRIETARY VEP.SIONS HAVING BEEN 1 DELETED. THE JUSTIFICATION FOR CLAIMING THE INFORMATION S0 DESIGNATED AS PROPRIETARY IS INDICATED IN BOTH VERSIONS BY MEANS OF LOWER CASE LETTERS (a)
THROUGH (g) CONTAINED WITHlN PARENTHESES LOCATED AS A SUPERSCRIPT IMMEDIATELY FOLLOWING THE B. RACKETS 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)(11)(a) THROUGH (4)(ii)(g) 0F THE AFFIDAVIT ACCOMPANYING THIS TRANSMITTAL PURSUANT TO 10CFR2.790(b)(1) . )
p r -
. . CAW-81-79 AFFIDAVIT l COMMONWEALTH OF PENNSYLVANIA: .
ss 1 COUNTY OF ALLEGHENY:
)
l q
l Before me, the undersigned authority, personally. appeared j I
Robert A. Wiesemann, who, being by me duly sworn according to law, l 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:
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I l
Ch 8All/$ l Robert A. Wiesemann, Manager Regulatory and Legislative Affairs. '
i i
Swo'n to and subscribed before me this e day of. D & v. 41 1981.
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?-((/b /* %i J hW
., ,--Notary lPublic./
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-m _. __ _____ . _ _ _ _ _ - _ . _ m._ . . _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ . . _ _ _ _
CAW-81-79 (1) I am Manager, Regulatory and Legislative Affairs, in the Nuclear Technology Division, of Westinghouse Electric Corporation and as such, I have been specifically delegated the function of reviewing ,
the proprietary information sought to be. withheld from public dis-closure in connection with nuclear power plant licensing or rule- j making proceedings, and am authorized.to apply for its withholding on behalf of the Westinghouse Water Reactor Divisions.
(2) I am making this Affidavit in conformance with the provisions of- l l
10CFR Section 2.790 of the Commission's regulations and in con-l junction with the Westinghouse application for withholding-ac- l companying this Affidavit.
(3) I have personal knowledge of the criteria and procedures utilized by Westinghouse Nuclear Energy Systems in' designating information j as a trade secret, privileged or as confidential commercial or financial information.
J (4) Pursuant to the provisions of paragraph (b)(4) of Section 2.790 l of the Dmission's regulations, the following is furnished for l consid N tion by the Commission in determining whether the in-formation 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.
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l CAW-81 -79 (ii) The information is of a type customarily held in confidence by Westinghouse and not customari'y disclosed to the public.
Westinghouse has a rational basis for determining the types of information customarily held in confidence by it and, in j that connection, utilizes a system to determine when and l 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 l rational basis required.
l Under that system, information is held in confidence if it.
l falls in one or more of several types, the release of which
'1 might result in the loss of an existing or potential com- )
f petitive advantage, as follows:
l 1
(a) The information reveals the distinguishing aspects of I a process (or component, structure, tool, method, etc.)
where prevention of its use by any of Westinghouse's j competitors without license from Westinghouse consti-tutes a competitive economic advantage over other companies.
(b) It consists of supporting data, including test data, relative to a process (or component, structure, tool, method, etc.), the application of which data secures a competitive economic advantage, e.g., by optimization or improved marketability.
CAW-81-79 (c) Its use by a competitor would reduce his expenditure of. resources or 3mprove his competitive position in the design, manufn ture, shipment,. installation, assurance of quality, or licensing a similar. product.
1 (d) It reveals cost or price information, production cap-acities, budget levels, or comercial strategies of Westinghouse, its customers or suppliers.
(e) It reveals aspects of past, present, or future Wcst- .q inghouse or customer funded development plans and pro- l grams of potential commercial value to Westinghouse.
(f) It contains patentable ideas, for which patent pro-tection may be desirable.
(g) It is not the property of Westinghouse, but must be treated as proprietary by Westinghouse according to agreements with the owner. l There are sound policy reasons behind the Westinghouse system which include the following:
(a) The use of such informa'cion by Westinghouse gives Westinghouse a competitive advantage over its com-petitors. It is, therefore, withheld from disclosure to protect the Westinghouse competitive position.
CAW-81-79 (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 expense.
(d) Each component of proprietary information pertinent to a particular competitive advantage is potentially as valuable as the total competitive advantage. If competitors acquire components of proprietary infor-mation, any one component may be the key to the entire puzzle, thereby depriving Westinghouse of a competitive advantage.
(e) Unrestricted disclosure would jeopardize the position of prominence of Westinghouse in the world market, and thereby give a market advantage to the competition in 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.
I
CAW-81-79 (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 in public sources or available information has not been pre-viously employed in the same ori.ginal manner or method to the best of our knowledge and belief.
(v) The proprietary information sought to be withheld in this submittal is that which is appropriately marked in " Steam Generator Tube Plugging Margin Analysis" for the Virgil C.
Summer Nuclear Power Plant Unit No.1, WCAP-9912, Revi- i sion 2 (Proprietary) being transmitted by South Carolina Electric and Gas Company letter Application for Withholding Proprietary Information from Public Disclosure, Nichols to Denton, November 1981. The proprietary information as sub-mitted for South Carolina Electric and Gas Company, Virgil C.
Summer Nuclear Station use is expected to be applicable in other licensee and applicant submittals in response to cer-tain NRC requirements for justification of the steam generator tube plugging margin.
This information is part of that which will enable Westing-house to:
I (a) Provide documentation of the analyses, method and test-ing for determining plugging margin.
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CAW-81-79 i
(b) Establish the minimum wall thickness in compliance with !
Regulatory Guide 1.121.
(c) Establish the stress limits "'.rsus thinning of the remaining tube wall.
(d) Establish the maximum allowable leakage in support of the leak-before-break criteria.
(e) Assist the customer to obtain NRC approval.
Further this information has substantial commercial value as follows:
(a) Westinghouse plans to sell similar information to its customers for purposes of meeting NRC requirements for licensing documentation.
(b) Westinghouse can sell support and defense of the tech-nology to its customers in the licensing process.
i Ptslic disclosure of this information is likely to cause substantial harm to the competitive position of Westinghouse because it would enhance the ability of competitors to pro-vide similar analytical documentation 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 require-ments for licensing documentation without purchasing the right to use the information.
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CAW-81-79 1
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The development of the technology described in part by the )
information is the result of. applying the results of many years of experience.in an intensive Westinghouse effort and the 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 ..
I requisite talent and experience, would have to be expended . I 1
for system design software development.
i Further the deponent sayeth not.
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AW-77-58 AFFIDAVIT COMMONWEALTHOFPENNSYLVANI5:
ss COUNTY OF ALLEGHENY:
Before me, the undersigned authority, personally appeared Robert A.- Wiesemann, 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:
.4bfMA
. Robert A. Wiesemann, Manager Licensing Programs Sworn to and subscribed day befo e me this -
of . lwlo1977. l Y'
%a Notary Public oswa_- '
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ut c.. .. ' . :. . . . L u 9
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4 (1) I am Manager, Licensing Programs, in the Pressurized Water Reactor Systems Division, of 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 nuclem power plant licensing or rulemaking l proceedings, and am authrized to apply for its withholding on f behalf of the Westinghc use Water Reactor Divisions.
(2) I am making this affidavit in conformance with the provisions of 10 CFR Section 2.790 of the Commission's regulations and in' con-I junction with the Westinghouse application for withholding accompanying this Affidavit.
_. l (3) I have personal knowledge of the criteria and procedures utilized by Westinghouse Nuclear Energy Systems'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 l
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.-
(ii) The information is of a type customarily held in 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 by it and, in that connection, utilizes a system to determine when and l .
, 3 's ' ,
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 required.
Under that system, information is held in confidence if it-falls in one or more of several types, the release of which might result in the loss of an existing or potential com-petitive advantage, as follows:
l (a) The information reveals the distinguishing aspects of-a process (or component, structure, tool, method', etc.) l where prevention of its use by any of Westinghouse's competitors without license from Westinghouse consti-tutes a competitive economic advantage over other companies.
J (b) It consists of supporting data, including test data, relative to a process (or component, structure, tool, method, etc.), the application of which data secures a competitive economic advantage, e.g., by optimization 3 i
or improved marketability.
l
. (c) Its uie by a competitor would reduce his expenditure of resources or improve his competitive position in the i design, manufacture, shipment, installation, assurance I of quality, or licensing of a similar product.
(d) It reveals cost or price information, production capacities, budget levels, or commercial strategies of Westinghouse, its customers or suppliers.
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(e) It reveals aspects of past, present, or future Westing-house or cus~tomer funded development plans and programs of potential commercial value to Westinghouse.
l (f) It contains patentable ideas, for which patent pro-tection may be desirable.
(g) It is not the property of Westinghouse, but must be treated as proprietary by Westinghouse according to agreements with the owner.
(iii) The information is being transmitted to the Commission in confidence and, under the provisions of 10 CFR Section 2.790 it is to be received il confidence by the Commission.
I 4
(iv) The information is not available in public sources to the best of our knowledge and belief.
I (v) The proprietary information sought to be withheld in this submittal is in the attachment to Westinghouse letter number NS-CE-1596, Eiche1dinger to Stuart, dated November 8,
~
i 1977, concerning Westinghouse Steam Generator Programs.
The letter and attachment are being submitted in response to the request of the Commission and its October 25, 1977 memorandum, Stuart to Eisenhut concerning Westinghouse Steam Generator Programs.
Public disclosure of this information is likely to cause substantial harm to the competitive position of Westinghouse as it would reveal the strategic plans of Westinghouse regarding the nature .and direction of its development programs. .
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Information regarding its development programs is valuable to Westinghouse because:
l (a)
Information resulting from its development programs g'ives
(
Westinghouse a competitive advantage over its competitors.
It is, therefore, withheld from disclosure to protect the Westinghouse competitive position.
-i (b) It is information which is marketable in many ways. The extent to which such information is available to compet-itors 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 com-petitive disadvantage by reducing his expenditure of resources at our expense.
(d) Each component of proprietary infomation pertinent to a particular competitive advantage is potentially as valuable as the total competitive advantage. If. competitors acquire components of proprietary information, any one
~
component may be the key to the entire puzzle, thereby I depriving Westinghouse of a competitive advantage.
(e) The Westinghouse capacity to invest corporate, assets in ,
I research and development depends upon the success in obtaining and maintaining a competitive advantage.
Altogether, a substantial amount of money and effort has been and is being expended by Westinghouse in its development programs which could only be duplicated by a competitor if he were to invest similar sums of j
money and provided he had the appropriate talent available.
Further the deponent sayeth not.
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1 3.0 DESIGN I 4
3.1 SLEEVE DESIGN DOCUMENTATION The J. M. Farley Unit 1 and Unit 2 steam generators were built to the 1968 edition Summer 1970 Addenda and 1971 edition respectively of Section III of the ASME Boller and Pressure Vessel Code, however,'the sleeves have been designed.and analyzed to the 1983 edition of Section III of the Code through the winter 1983 addenda as well as applicable ~ Regulatory Guides. The associated materials and processes also meet the requirements of the Code.
The specific documentation applicable to this program are listed in Table 3.1-1.
3.2 SLEEVE DESIGN DESCRIPTION The reference design of the sleeve, as installed, is illustrated in Figure j 3.2-1. [
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l j a.c.e At the upper end, the sleeve configuration (see Figure 3.2-1) consists of a l section which is [
3a .c.e This I joint configuration is known as a hybrid expansion joint (HEJ). [
j ac.e In the process of sleeve length optimization and allowing for axial tolerance in locating defect by eddy current inspection, the guideline was the icwer most elevation of the hard roll region to be positioned a minimum of 1 inch above the eddy current detected defect area of the tube.
3592M/081087:49 3-1 i k
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TABLE 3.1-1 ASME CODE AND REGULATORY REQUIREMENTS l
Item Applicable Criteria Requirement l
Sleeve Design Section III NB-3200, Analysis NB-3300, Wall Thick-ness Operating Requirements Analysis Conditions l
Reg. Guide 1.83 S/G Tubing Inspec-tibility Reg. Guide 1.121 Plugging Margin Sleeve Material Section II Material Composition Section III NB-2000, Identifica-tion, Tests and Examination Code Case N-20 Mechanical Proper-
. ties Sleeve Joint 10CFR100 Plant Total Primary-Secondary Leak Rate Technical Specifications Plant Leak Rate 3592M/060986: 49 3-2
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ENCLOSURE 2 l l
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Tubesheet Region Plugging Criterion 4 Replacement Pages l 1
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2.1.1 - RAD 7AL PRELOAD TEST CONFIGURATION DESCRIPTION The test program was designed to simulate the interface of a tube-to-tubesheet full depth hardroll for a model 51 steam generator. The test configuration consisted of six cylindrical collars, approximately [ ]"'C inches in length, [ l a.c.e inches in outside diameter, and [ 3a ,c.e inch in I inside diameter. The RE process was designed to provide the same preload independent of hole diameters of up to approximately 0.935 in. The preload was determined by tube thinning which, in turn, was determined by roll expander motor stalling torque. A single nominal stalling torque value was used for all tube-to-tubesheet joints. A mill annealed, Inconel 600 (ASME SB-163), tubing specimen, approximately [ ]"'C inches long with a nominal outside diameter of [ Ja .c.e inch before rolling, was hard rolled into each collar using a process which simulated actual tube installation conditions.
The design of the collars was based on the results of performing finite element analfsis of a section of the steam generator tubesheet to determine radial stiffness and flexibility. The inside diameter of the collar was chosen to tuatch the size of holes drilled in the tubesheet. The outside diameter was selected to provide the same radial stiffness as the tubesheet..
The collars were fabricated from AISI 1018 carbon steel similar in mechanical properties to the actual tubesheet material. The collar assembly was clamped in a vise during the rolling process and for the post roll measurements of the tube ID. Following the taking of all post roll measurements, the collars were saw cut to within a small distance from the tube wall. The collars were then split for removal from the tube and tube ID and OD measurements were repeated.
Two end boundary conditions were imposed on the tube specimen during rolling.
The end was restrained from axial motion in order to perform a tack roll at j the bottom end, and was allowed to expand freely during the final roll..
4 2.1.2 PRELOAD TEST RESULTS DISCUSSION AND ANALYSIS All measurements taken during the test program are tabulated in Table 1. The data recorded was employed to determine the interfacial conditions of the 4306M:49/042487 9 ,
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pressures. The difference between an analysis assuming plane stress and one assuming plane strain is manifested only in a ci.ange in the constant C2 ' , i for materials having a Poisson's ratio of 0.3, the following relation holds:
C2 (Plane Strain) = 0.862
I 1 The effect on the calculated residual pressure is that plane strain results ,
are higher than plane stress results by slightly less than 10 percent.
Comparing this effect with the results reported in reference 2 indicated that ,
better agreement with test values is achieved. It is to be noted that the -
residual radial pressure at the tube to tubesheet interface 15.the compressive f radial stress at the OD of the tube, By substituting the expressions for the constants into equation (1) the deflection at any radial location within the tube wall as a function of the f internal and external pressure (radial stress at the ID and 00) is found. This [I expression was differentiated to obtain flexibility values for the tube '
- 3 deflection at the ID and 00 respectively, e.g., dui/dPo is the ratio of the radial deflection at the ID due to an OD pressure. Thus, dui/dPo was used to find the interface pressure and radial stress between the tube and the ,!
tubesheet as:
S --P = - (ID Radial Springback). / (dU1/dPo) p (3) ro o - ,,.
g The calculated radial residual stress for each specimen at:each i location is tabulated in Table 2. The mean residual tube 00 radial stress Ind the standard deviation was found to be [ 3"'C psi and [ 3a c.e as respectively.
In order to determine a value to be used in the analysis, a rilerance' factor for [ Ja .c.e percent confidence to contain I J a 'C percent of the population was calculated, considering the [ -]"'C useable data points, to be [ l a.c.e Thus, a [
. 3 A 'C
lowr' tolerance limit (LTL) for the /
, ()
radial residual preload at room temperature is [ 3a ,c.e p3g, i
,q i
1 o J\
> t i'
a 4308M:49/042aB7 *
)/
= __ ___= _ __._ _ - Y i
, 7.16*10~0 in/in/*F. Thus, there is a net difference of 0.63*10-6 in/in/*F in the expansion property of the tv) materials. Considering l
a temperature difference of approximate?y 483*F between ambient and '
cold leg op'erating conditions the increase in preload between the tube (t) and the tubesheet (ts) was calculated as- I i
Sri = (0.63E-6)*(483)*RCollar ID) / 2 )/ ((dui/dP1)ts- (duo /dPo)t}
(4)
/
This calculation was also performed and tabulated in Table 2. The results indicaH that the increase in preload radial stress due to l
thermal expansion'is ( )#'E'" psi. It is to be noted that this value applies for both normal operating and fa.ulted conditions. l
- 2. Internal Pressure Tightening - The maximum normal operating j differential pressure from the primary to secondary side of the steam g generator is ( Ja .c.e psi during a loss of Iced transient. The l internal pressure acting on the wall of the tube will result in an
- increase c>f the radia' preload on the crhr of the pressure value. 1 The increase was found as
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q (duo /dPi) /( (dVi/dPi)g - (duo /dPo) ) l SrP -Po = - P3 (5)
[ In actuality, the increase in preload will be more dependent on the internal pressure :f ~the tube since water at secondary side pressure woula not be evpected between the tube and the tubesheet. This differential pressure, along with the associated temperature and tubesheet bowing effects, was the mcst stringent normal condition in ter.Ts of determining the f* itngth. Increased differential pressure not only increases radial preload directly, it also increases tubesheet bending which reduces preload.
4308M:49/04:as? 13 p _ _ _ _ . .
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