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Category:CORRESPONDENCE-LETTERS
MONTHYEARPLA-5120, Forwards Change J to SSES Security Training & Qualification Plan.Without Encl1999-10-22022 October 1999 Forwards Change J to SSES Security Training & Qualification Plan.Without Encl ML18040B2951999-09-0808 September 1999 Requests Info Re Any NRC or Susquehanna Documented Concerns with MSIV Reliability Prior to Plant Trip & Assurance to Public That NRC Able to Detect Mgt Problems Early PLA-5094, Forwards,For Review,Change 00 to SSES Physical Security Plan.Without Encl1999-08-24024 August 1999 Forwards,For Review,Change 00 to SSES Physical Security Plan.Without Encl ML18040A9741999-07-0808 July 1999 Forwards Rev 30 to SSES Emergency Plan, Adding EAL to Account for Potential Conditions Associated with Dry Cask Storage Sys Being Installed at Plant ML20207G5051999-06-0707 June 1999 Informs That NRC Office of NRR Reorganized Effective 990328.As Part of Reorganization,Divison of Licensing Project Management Created PLA-5072, Forwards Change Nn to SSES Physical Security Plan.Util Determined That Changes Do Not Decrease Safeguards Effectiveness of Plan,Per 10CFR50.54(p).Encl Withheld from Public Disclosure,Per 10CFR73.211999-06-0404 June 1999 Forwards Change Nn to SSES Physical Security Plan.Util Determined That Changes Do Not Decrease Safeguards Effectiveness of Plan,Per 10CFR50.54(p).Encl Withheld from Public Disclosure,Per 10CFR73.21 ML18040A9731999-05-24024 May 1999 Submits Response to RAI Re Exemption from Biennial Exercise Schedule.Changing of Drill Date Will Not Reduce Level of Emergency Preparedness at Plant ML20195B2181999-05-20020 May 1999 Forwards Proprietary Decommissioning Status Rept for 10% Interest in Sses,Units 1 & 2.Proprietary Info Withheld,Per 10CFR2.790 ML18040B2901999-04-30030 April 1999 Forwards Summary Rept of Safety Evaluations Approved During Period from 961024-981029,per 10CFR50.59(b).Format of Rept, Listed PLA-5041, Forwards Proprietary & Redacted Decommissioning Rept of Financial Assurance for Util 90% Interest in Sses,Units 1 & 2,per 10CFR50.75(f)(1).Proprietary Info Withheld,Per 10CFR2.7901999-03-29029 March 1999 Forwards Proprietary & Redacted Decommissioning Rept of Financial Assurance for Util 90% Interest in Sses,Units 1 & 2,per 10CFR50.75(f)(1).Proprietary Info Withheld,Per 10CFR2.790 ML17164A9891999-03-12012 March 1999 Informs That Util 990312 Ltr (PLA-5040) Submitted to NRC, Missing Encl C.Requests to Replace Package in Entirety with Encl ML18040A9691999-03-12012 March 1999 Forwards Revised Proposed Amend 227 to License NPF-14, Proposing Changes to ANFB-10 Critical Power Correlation & MCPR Safety Limits ML18040A9721999-03-11011 March 1999 Requests That Date for full-participation SSES Exercise, Scheduled for Week of 991115,be Changed Due to FEMA Region III Scheduling Conflicts.Fema Requests That Exercise Date Be Changed to Week of 001031 PLA-4852, Forwards non-redacted Version of Pp&L,Inc Corporate Auditing Rept 739459-2-98,dated 980210.Informs That Document Contains Info to Be Withheld IAW 10CFR2.7901999-02-18018 February 1999 Forwards non-redacted Version of Pp&L,Inc Corporate Auditing Rept 739459-2-98,dated 980210.Informs That Document Contains Info to Be Withheld IAW 10CFR2.790 ML20203G5821999-02-17017 February 1999 Second Final Response to FOIA Request for Documents. Documents Listed in App C Being Released in Entirety. Documents Listed in App D Being Withheld in Part (Ref FOIA Exemption 5) ML20202F4761999-01-29029 January 1999 First Partial Response to FOIA Request for Documents.Records in App a Encl & Being Released in Entirety.App B Records Being Withheld in Part (Ref FOIA Exemption 7C) ML18040A9671999-01-29029 January 1999 Notifies That Util Implemented Severe Accident Mgt Strategy in Accordance with Ltr Dtd 950327.Emegency Plan Revs Which Were Required to Implement Strategy Were Submitted by Ltr Dtd 981125 ML18040A9681999-01-29029 January 1999 Requests Exemption from Requirements of 10CFR50 App E,Items IVF.2.b & C,To Allowed to Reschedule Federally Observed Full Participation Emergency Exercise for SSES from Wk of 991115 to Wk of 001031 ML18040A9651999-01-12012 January 1999 Submits Addl Info Re Proposed Amend 184 to License NPF-22 for ANFB-10 Critical Power Correlation & MCPR Safety Limits ML18030A1021998-12-16016 December 1998 Forwards Tables as Requested During 981202 Telcon Re Proposed Amend 184,dtd 980804,re ANFB-10 Critical Power Correlation & MCPR Safety Limits.Tables Provide Roadmap Identifying Applicability of References to TSs ML18030A4331998-11-25025 November 1998 Forwards Rev 29 to SSES Emergecny Plan.Changes Has Been Made Without Commission Approval as It Does Not Decrease Effectiveness of Plan & Plan as Changed Continues to Satisfy Applicable Requirements of App E to 10CFR50 ML20195J9101998-11-18018 November 1998 Forwards Notice of Withdrawal of Application for Amends to Facility Operating Licenses (Notice).Notice Has Been Filed with Ofc of Fr.Amends Would Have Revised TS to Eliminate HPCI Pump auto-transfer on High Suppression Pool Level ML20155F7201998-11-0303 November 1998 Final Response to FOIA Request for Documents.Documents Listed in App B Being Encl & Being Released in Entirety. Documents Listed in App C Being Withheld in Part (Ref Exemption 7C) ML18026A2941998-10-19019 October 1998 Forwards SSES ISI Outage Summary Rept for Unit 1 Tenth Refueling & Insp Outage ML18030A4321998-10-12012 October 1998 Forwards Rev 28 to SSES Emergency Plan, IAW Requirements of 10CFR50.54q.Change Is Summarized PLA-4993, Forwards Change Mm to SSES Physical Security Plan.Encl Withheld,Per 10CFR73.211998-10-12012 October 1998 Forwards Change Mm to SSES Physical Security Plan.Encl Withheld,Per 10CFR73.21 ML18030A1001998-10-12012 October 1998 Forwards Rev 27 to SSES Emergency Plan. Changes Become Effective Upon Implementation of Improved Tech Specs ML18030A4311998-09-29029 September 1998 Forwards Rev 27 & 28 to SSES Emergency Plan ML20151W4951998-09-10010 September 1998 Informs That as Part of NRC Probabilistic Risk Assessment Implementation Plan,Commission Assigned Two Senior Reactor Analysts (Sras) to Each Regional Ofc.T Shedlosky & J Trapp Has Been Assigned SRAs for Region I IR 05000387/19980081998-09-0808 September 1998 Provides Response to Violations Noted in Insp Repts 50-387/98-08 & 50-388/98-08.Corrective Actions:Current Administrative Controls on Fuel Level in EDG Day Tanks Will Remain in Effect Until TS Change is Approved ML18030A0991998-09-0808 September 1998 Provides Response to Violations Noted in Insp Repts 50-387/98-08 & 50-388/98-08.Corrective Actions:Current Administrative Controls on Fuel Level in EDG Day Tanks Will Remain in Effect Until TS Change Is Approved ML18026A4961998-08-31031 August 1998 Responds to NRC 980731 Ltr Re Violations Noted in Insp Repts 50-387/98-03 & 50-388/98-03.Corrective Actions:Procurement & Affected User Group Personnel Visited EDG Vendor Facilities to Appraise Vendor Work Practices & Discuss Expectations IR 05000387/19980031998-08-31031 August 1998 Responds to NRC 980731 Ltr Re Violations Noted in Insp Repts 50-387/98-03 & 50-388/98-03.Corrective Actions:Procurement & Affected User Group Personnel Visited EDG Vendor Facilities to Appraise Vendor Work Practices & Discuss Expectations ML20202F5501998-07-17017 July 1998 Responds to PP&L Corp Auditing Repts 739459-97,739459-1-97 & 739459-2-98 Re SSES Investigations Into Missed Alarm Tests ML20236P9451998-07-15015 July 1998 Forwards Emergency Response Data Sys Implementation Documents Including Data Point Library Updates for Oconee (Number 255),Dresden (Number 257) & Susquehanna (Number 258) ML18017A2181998-07-0808 July 1998 Forwards Final Version of SSES TS Implementing Improved Tech Specs of NUREG 1433.Implementation of Proposed Amend Is Predicated on NRC Issuance of Amends & Is Proposed to Not Exceed 90 Days from Date of Amend Issuance ML18030A4291998-07-0808 July 1998 Forwards Final Version of SSES TS Implementing Improved TS of NUREG-1433.Implementation of Proposed Amend Is Predicted on NRC Issuance of Amends & Proposed to Not Exceed 90 Days from Date of Amend Issue ML18026A2901998-06-0909 June 1998 Forwards Rev 26 to Emergency Plan IAW 10CFR50.54q.Summary of Changes Listed ML18026A2891998-05-22022 May 1998 Submits Withdrawal of Expedited Review/Approval of Tech Specs/Bases 3/4.3.7.11 & 3/4.11.2.6 & Response to Request for Addl Info Re Offgas Sys Mods ML18026A4941998-05-12012 May 1998 Responds to NRC Request to Resubmit Proposal to Change TS for Plant,Units 1 & 2,to Support Implementation of Improved TS & to Implement Provisions of GL 86-10 Re Relocation of Plant'S Fire Protection Program from TS to Another Document ML20202H1331998-04-16016 April 1998 Partially Deleted Ltr Re Concerns Raised to NRC Concerning PP&L Susquehanna Facility ML20216B6811998-04-0101 April 1998 First Partial Response to FOIA Request for Documents. Forwards Documents Listed in App a Being Released in Entirety ML17159A2341998-03-30030 March 1998 Forwards LER 97-007-01,per 10CFR50.73(a)(2)(i)(B).Revised LER Submitted to Modify Previous Position W/Regards to Entry Into TS 3.0.3 for Event PLA-4865, Forwards Listed non-redacted Pp&L,Inc Corporate Auditing Repts.Informs That Document Contains Info to Be Withheld IAW 10CFR2.7901998-03-11011 March 1998 Forwards Listed non-redacted Pp&L,Inc Corporate Auditing Repts.Informs That Document Contains Info to Be Withheld IAW 10CFR2.790 ML17159A1781998-03-0202 March 1998 Forwards Proposed Amends 203 & 161 to License NPF-14 & NPF-22,revising Tech Specs to Be Consistent w/NUREG-1433,rev 1, Std Tech Specs for GE Plants,Bwr 4. PLA-4856, Forwards Proposed Amends to Licenses NPF-14 & NPF-22, Revising TS to Be Consistent w/NUREG-1433,rev 1, Std TS for GE Plants,Bwr 4. Proposed TS Consistent w/NUREG-1433,rev 1, Encl1998-03-0202 March 1998 Forwards Proposed Amends to Licenses NPF-14 & NPF-22, Revising TS to Be Consistent w/NUREG-1433,rev 1, Std TS for GE Plants,Bwr 4. Proposed TS Consistent w/NUREG-1433,rev 1, Encl PLA-4854, Provides Summary of Investigations That PP&L Performed in Response to Concerns Identified by Former Nuclear Plant Operator.Summary Requested by Cj Anderson on 9802131998-02-27027 February 1998 Provides Summary of Investigations That PP&L Performed in Response to Concerns Identified by Former Nuclear Plant Operator.Summary Requested by Cj Anderson on 980213 ML20203M5071998-02-26026 February 1998 Final Response to FOIA Request for Documents.Records in App a Being Placed in PDR & Encl.Records in App B Partially Withheld (Ref FOIA Exemption 6) ML20203B5931998-02-23023 February 1998 Ack Receipt of & Wire in Amount of $55,000 in Payment for Civil Penatly Proposed by NRC Ltr . Corrective Actions Will Be Examined During Future Inspections ML20216B7031998-02-22022 February 1998 Partially Deleted Ltr Requesting Copy of OI Rept on Plant, Unit 2,case 1-96-039 1999-09-08
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARPLA-5120, Forwards Change J to SSES Security Training & Qualification Plan.Without Encl1999-10-22022 October 1999 Forwards Change J to SSES Security Training & Qualification Plan.Without Encl ML18040B2951999-09-0808 September 1999 Requests Info Re Any NRC or Susquehanna Documented Concerns with MSIV Reliability Prior to Plant Trip & Assurance to Public That NRC Able to Detect Mgt Problems Early PLA-5094, Forwards,For Review,Change 00 to SSES Physical Security Plan.Without Encl1999-08-24024 August 1999 Forwards,For Review,Change 00 to SSES Physical Security Plan.Without Encl ML18040A9741999-07-0808 July 1999 Forwards Rev 30 to SSES Emergency Plan, Adding EAL to Account for Potential Conditions Associated with Dry Cask Storage Sys Being Installed at Plant PLA-5072, Forwards Change Nn to SSES Physical Security Plan.Util Determined That Changes Do Not Decrease Safeguards Effectiveness of Plan,Per 10CFR50.54(p).Encl Withheld from Public Disclosure,Per 10CFR73.211999-06-0404 June 1999 Forwards Change Nn to SSES Physical Security Plan.Util Determined That Changes Do Not Decrease Safeguards Effectiveness of Plan,Per 10CFR50.54(p).Encl Withheld from Public Disclosure,Per 10CFR73.21 ML18040A9731999-05-24024 May 1999 Submits Response to RAI Re Exemption from Biennial Exercise Schedule.Changing of Drill Date Will Not Reduce Level of Emergency Preparedness at Plant ML20195B2181999-05-20020 May 1999 Forwards Proprietary Decommissioning Status Rept for 10% Interest in Sses,Units 1 & 2.Proprietary Info Withheld,Per 10CFR2.790 ML18040B2901999-04-30030 April 1999 Forwards Summary Rept of Safety Evaluations Approved During Period from 961024-981029,per 10CFR50.59(b).Format of Rept, Listed PLA-5041, Forwards Proprietary & Redacted Decommissioning Rept of Financial Assurance for Util 90% Interest in Sses,Units 1 & 2,per 10CFR50.75(f)(1).Proprietary Info Withheld,Per 10CFR2.7901999-03-29029 March 1999 Forwards Proprietary & Redacted Decommissioning Rept of Financial Assurance for Util 90% Interest in Sses,Units 1 & 2,per 10CFR50.75(f)(1).Proprietary Info Withheld,Per 10CFR2.790 ML18040A9691999-03-12012 March 1999 Forwards Revised Proposed Amend 227 to License NPF-14, Proposing Changes to ANFB-10 Critical Power Correlation & MCPR Safety Limits ML17164A9891999-03-12012 March 1999 Informs That Util 990312 Ltr (PLA-5040) Submitted to NRC, Missing Encl C.Requests to Replace Package in Entirety with Encl ML18040A9721999-03-11011 March 1999 Requests That Date for full-participation SSES Exercise, Scheduled for Week of 991115,be Changed Due to FEMA Region III Scheduling Conflicts.Fema Requests That Exercise Date Be Changed to Week of 001031 PLA-4852, Forwards non-redacted Version of Pp&L,Inc Corporate Auditing Rept 739459-2-98,dated 980210.Informs That Document Contains Info to Be Withheld IAW 10CFR2.7901999-02-18018 February 1999 Forwards non-redacted Version of Pp&L,Inc Corporate Auditing Rept 739459-2-98,dated 980210.Informs That Document Contains Info to Be Withheld IAW 10CFR2.790 ML18040A9671999-01-29029 January 1999 Notifies That Util Implemented Severe Accident Mgt Strategy in Accordance with Ltr Dtd 950327.Emegency Plan Revs Which Were Required to Implement Strategy Were Submitted by Ltr Dtd 981125 ML18040A9681999-01-29029 January 1999 Requests Exemption from Requirements of 10CFR50 App E,Items IVF.2.b & C,To Allowed to Reschedule Federally Observed Full Participation Emergency Exercise for SSES from Wk of 991115 to Wk of 001031 ML18040A9651999-01-12012 January 1999 Submits Addl Info Re Proposed Amend 184 to License NPF-22 for ANFB-10 Critical Power Correlation & MCPR Safety Limits ML18030A1021998-12-16016 December 1998 Forwards Tables as Requested During 981202 Telcon Re Proposed Amend 184,dtd 980804,re ANFB-10 Critical Power Correlation & MCPR Safety Limits.Tables Provide Roadmap Identifying Applicability of References to TSs ML18030A4331998-11-25025 November 1998 Forwards Rev 29 to SSES Emergecny Plan.Changes Has Been Made Without Commission Approval as It Does Not Decrease Effectiveness of Plan & Plan as Changed Continues to Satisfy Applicable Requirements of App E to 10CFR50 ML18026A2941998-10-19019 October 1998 Forwards SSES ISI Outage Summary Rept for Unit 1 Tenth Refueling & Insp Outage PLA-4993, Forwards Change Mm to SSES Physical Security Plan.Encl Withheld,Per 10CFR73.211998-10-12012 October 1998 Forwards Change Mm to SSES Physical Security Plan.Encl Withheld,Per 10CFR73.21 ML18030A4321998-10-12012 October 1998 Forwards Rev 28 to SSES Emergency Plan, IAW Requirements of 10CFR50.54q.Change Is Summarized ML18030A1001998-10-12012 October 1998 Forwards Rev 27 to SSES Emergency Plan. Changes Become Effective Upon Implementation of Improved Tech Specs ML18030A4311998-09-29029 September 1998 Forwards Rev 27 & 28 to SSES Emergency Plan ML18030A0991998-09-0808 September 1998 Provides Response to Violations Noted in Insp Repts 50-387/98-08 & 50-388/98-08.Corrective Actions:Current Administrative Controls on Fuel Level in EDG Day Tanks Will Remain in Effect Until TS Change Is Approved IR 05000387/19980081998-09-0808 September 1998 Provides Response to Violations Noted in Insp Repts 50-387/98-08 & 50-388/98-08.Corrective Actions:Current Administrative Controls on Fuel Level in EDG Day Tanks Will Remain in Effect Until TS Change is Approved ML18026A4961998-08-31031 August 1998 Responds to NRC 980731 Ltr Re Violations Noted in Insp Repts 50-387/98-03 & 50-388/98-03.Corrective Actions:Procurement & Affected User Group Personnel Visited EDG Vendor Facilities to Appraise Vendor Work Practices & Discuss Expectations IR 05000387/19980031998-08-31031 August 1998 Responds to NRC 980731 Ltr Re Violations Noted in Insp Repts 50-387/98-03 & 50-388/98-03.Corrective Actions:Procurement & Affected User Group Personnel Visited EDG Vendor Facilities to Appraise Vendor Work Practices & Discuss Expectations ML18017A2181998-07-0808 July 1998 Forwards Final Version of SSES TS Implementing Improved Tech Specs of NUREG 1433.Implementation of Proposed Amend Is Predicated on NRC Issuance of Amends & Is Proposed to Not Exceed 90 Days from Date of Amend Issuance ML18030A4291998-07-0808 July 1998 Forwards Final Version of SSES TS Implementing Improved TS of NUREG-1433.Implementation of Proposed Amend Is Predicted on NRC Issuance of Amends & Proposed to Not Exceed 90 Days from Date of Amend Issue ML18026A2901998-06-0909 June 1998 Forwards Rev 26 to Emergency Plan IAW 10CFR50.54q.Summary of Changes Listed ML18026A2891998-05-22022 May 1998 Submits Withdrawal of Expedited Review/Approval of Tech Specs/Bases 3/4.3.7.11 & 3/4.11.2.6 & Response to Request for Addl Info Re Offgas Sys Mods ML18026A4941998-05-12012 May 1998 Responds to NRC Request to Resubmit Proposal to Change TS for Plant,Units 1 & 2,to Support Implementation of Improved TS & to Implement Provisions of GL 86-10 Re Relocation of Plant'S Fire Protection Program from TS to Another Document ML17159A2341998-03-30030 March 1998 Forwards LER 97-007-01,per 10CFR50.73(a)(2)(i)(B).Revised LER Submitted to Modify Previous Position W/Regards to Entry Into TS 3.0.3 for Event PLA-4865, Forwards Listed non-redacted Pp&L,Inc Corporate Auditing Repts.Informs That Document Contains Info to Be Withheld IAW 10CFR2.7901998-03-11011 March 1998 Forwards Listed non-redacted Pp&L,Inc Corporate Auditing Repts.Informs That Document Contains Info to Be Withheld IAW 10CFR2.790 ML17159A1781998-03-0202 March 1998 Forwards Proposed Amends 203 & 161 to License NPF-14 & NPF-22,revising Tech Specs to Be Consistent w/NUREG-1433,rev 1, Std Tech Specs for GE Plants,Bwr 4. PLA-4856, Forwards Proposed Amends to Licenses NPF-14 & NPF-22, Revising TS to Be Consistent w/NUREG-1433,rev 1, Std TS for GE Plants,Bwr 4. Proposed TS Consistent w/NUREG-1433,rev 1, Encl1998-03-0202 March 1998 Forwards Proposed Amends to Licenses NPF-14 & NPF-22, Revising TS to Be Consistent w/NUREG-1433,rev 1, Std TS for GE Plants,Bwr 4. Proposed TS Consistent w/NUREG-1433,rev 1, Encl PLA-4854, Provides Summary of Investigations That PP&L Performed in Response to Concerns Identified by Former Nuclear Plant Operator.Summary Requested by Cj Anderson on 9802131998-02-27027 February 1998 Provides Summary of Investigations That PP&L Performed in Response to Concerns Identified by Former Nuclear Plant Operator.Summary Requested by Cj Anderson on 980213 ML20216B7031998-02-22022 February 1998 Partially Deleted Ltr Requesting Copy of OI Rept on Plant, Unit 2,case 1-96-039 PLA-4851, Provides Info That Was Requested by Cj Anderson on 980213 Re Former Util Employee Concern on Radwaste Control Room Offgas Panel Alarm Testing1998-02-18018 February 1998 Provides Info That Was Requested by Cj Anderson on 980213 Re Former Util Employee Concern on Radwaste Control Room Offgas Panel Alarm Testing ML20203M5791998-02-10010 February 1998 Enters Appeal Due to Lack of Response to FOIA Request 97-473 ML18030A0971998-02-0202 February 1998 Forwards Proprietary Response to RAI Re Proposed License Amend 209 to TS Supporting Cycle 11 Reload.Proprietary Info Withheld,Per 10CFR2.790 ML20203G6071998-01-26026 January 1998 Forwards Redacted Version of Pp&L,Inc Corporate Auditings Interim Rept 739459-97,dtd 971015 & Affidavit Pursuant to 10CFR2.790 Justifying That Redacted Portions Be Withheld from Public Disclosure.Without Rept IR 05000387/19970031998-01-0606 January 1998 Provides Updated Response to Violations Noted in Insp Repts 50-387/97-03 & 50-388/97-03.Corrective Actions:Util Currently Scheduling Issuance of All Procedural Revs by End of First Quarter 1998 ML18030A4071998-01-0606 January 1998 Provides Updated Response to Violations Noted in Insp Repts 50-387/97-03 & 50-388/97-03.Corrective Actions:Util Currently Scheduling Issuance of All Procedural Revs by End of First Quarter 1998 ML18017A2931998-01-0606 January 1998 Provides Responses to Improved TS Section 3.8 Per 970324 NRC Rai.Schedule 980628 for Improved TS Implementation. Submittal of Revised Specifications Is Planned for Jan 1998 PLA-4828, Expresses Appreciation for Support Received by Former Project Manager C Poslusny1997-12-29029 December 1997 Expresses Appreciation for Support Received by Former Project Manager C Poslusny ML18026A4901997-12-22022 December 1997 Resolves Commitments Made in Response to NOV Issued as Part of NRC Insp Repts 50-387/97-04 & 50-388/97-04 Dtd 970805. Proposed FSAR QA Program Description Changes,Reason for Changes & Basis Included for Approval IR 05000387/19970041997-12-22022 December 1997 Resolves Commitments Made in Response to NOV Issued As Part of NRC Insp Repts 50-387/97-04 & 50-388/97-04 Dtd 970805. Proposed FSAR QA Program Description Changes,Reason for Changes & Basis Included for Approval ML20203M5741997-12-0505 December 1997 FOIA Request for Copy of Latest OI Rept on Susquehanna Ses Including All Exhibits & for Any Other Communication Between NRC & Susquehanna Ses/Pp&L PLA-4818, Forwards Redacted Version of Pp&L,Inc Corporate Auditings Rept 739459-1-97,dtd 971201 & Affidavit Pursuant to 10CFR2.790 Justifying That Redacted Portions Be Withheld from Public Disclosure.Without Rept1997-12-0404 December 1997 Forwards Redacted Version of Pp&L,Inc Corporate Auditings Rept 739459-1-97,dtd 971201 & Affidavit Pursuant to 10CFR2.790 Justifying That Redacted Portions Be Withheld from Public Disclosure.Without Rept 1999-09-08
[Table view] Category:UTILITY TO NRC
MONTHYEARML18026A3941990-09-0101 September 1990 Requests Waiver of Compliance from Tech Spec 3.8.1.1 to Evaluate Increase in Action from 72 H to 15 Days Re Ac Sources Based on 900829 Borescopic Insp of Emergency Diesel Generator ML17157A2741990-08-0808 August 1990 Forwards Topical Rept PL-NF-90-001, Application of Reactor Analysis Methods for BWR Design & Analysis. ML18030A0741990-08-0303 August 1990 Responds to Violations Noted in Insp Repts 50-387/90-80 & 50-388/90-80.Corrective Actions:Util Conducted Operator Training on How to Implement EOPs If Suppression Chamber Pressure Not Available ML18026A2351990-07-0202 July 1990 Forwards Application for Proposed Amend 132 to License NPF-14,revising Tech Spec to Support Cycle 6 Reload ML18030A0721990-06-19019 June 1990 Forwards Rev 1 to SEA-EE-183, Evaluation of Unit 1 Computer Class 1E - Non-Class 1E Interfaces & Rev 1 to SEA-EE-184, Evaluation of Unit 1 Annunciator Class 1E - Non-Class 1E Interfaces. ML18026A3931990-06-0707 June 1990 Requests NRC Approval to Install Mod at Plant Determined to Constitute Unreviewed Safety Question When Evaluated.Util Will Implement Administrative Controls to Ensure Larger Min Vol Met for Diesel E Prior to Tech Spec Change ML18030A3671990-05-14014 May 1990 Forwards Proprietary Conclusions of Investigation Re Two False Negative Analytical Results from Two Blind Spike Urine Samples.Investigation Satisfactorily Evaluated Samples. Encl Withheld (Ref 10CFR2.790) ML20043A2461990-05-11011 May 1990 Forwards Draft of Proposed Decommissioning Financial Assurance Plan,Per 10CFR50.33 & 50.75,for Review.Telcon Scheduled for 900515 to Discuss Comments ML18030A0711990-03-19019 March 1990 Responds to Questions Delineated in 900131 Ltr Re Diesel Generator Events That Occurred During Sept & Oct 1989.Draft Procedures for Proposed Intake Air Temp Test Program Transmitted to NRC on 900205.Revised Procedures Encl ML18017A1871990-02-15015 February 1990 Forwards Books 1 & 2 to, Unit 2 Third Refueling & Insp Outage;Outage Summary Rept. IR 05000387/19890331990-02-0505 February 1990 Responds to NRC 900105 Ltr Re Violations Noted in Insp Repts 50-387/89-33 & 50-388/89-31.Corrective Actions:Rhr Svc Water Pump 2P506B Remains in Inoperable Status Until Cause of Deviation Determined & Condition Corrected ML18030A0701990-02-0505 February 1990 Responds to NRC 900105 Ltr Re Violations Noted in Insp Repts 50-387/89-33 & 50-388/89-31.Corrective Actions:Rhr Svc Water Pump 2P506B Remains in Inoperable Status Until Cause of Deviation Determined & Condition Corrected ML18040A9601990-02-0202 February 1990 Forwards Schedules That Provide Details of Tasks Required to Complete Activities Re Diesel Generators & Advises of Plan to Have Spare Parts on Site in Timely Manner to Support Each Diesel Insp PLA-3319, Forwards Preliminary Scope & Schedule for Security Upgrade Project.Encl Withheld (Ref 10CFR73.21)1990-01-25025 January 1990 Forwards Preliminary Scope & Schedule for Security Upgrade Project.Encl Withheld (Ref 10CFR73.21) ML17156B6031990-01-25025 January 1990 Forwards NPDES Discharge Monitoring Rept for Dec 1989 & State of Pa,Dept of Environ Resources Monthly Facility Rept Form (01-112).Noncompliances for Zinc on Cooling Tower Blowdown on 891228 & for Missed Sample Noted ML18040B2671990-01-0505 January 1990 Forwards Rev 0 to SEA-CW-037, Analysis of B & C 1989 Diesels Failure. Rept Details Util Analysis of Overpressurization Incidents Which Occurred in Sept & Oct 1989 of Diesel Generators ML18040B2651989-11-27027 November 1989 Forwards Response to Generic Ltr 89-21.Table of USIs for Which Technical Resolution Has Been Achieved Encl PLA-3292, Responds to Generic Ltr 89-07, Power Reactor Safeguards Contingency Planning for Surface Vehicle Bombs. Util Has Developed & Issued Procedure Which Includes Safeguards Contingency Planning Using Approach Noted in Generic Ltr1989-11-0909 November 1989 Responds to Generic Ltr 89-07, Power Reactor Safeguards Contingency Planning for Surface Vehicle Bombs. Util Has Developed & Issued Procedure Which Includes Safeguards Contingency Planning Using Approach Noted in Generic Ltr PLA-3279, Forwards Application for Amends 126 & 77 to Licenses NPF-14 & NPF-22,respectively,requesting Emergency Temporary Relief from Certain Requirements of Tech Specs 3.2.2 on One Time Basis for Period of 3 Months1989-10-19019 October 1989 Forwards Application for Amends 126 & 77 to Licenses NPF-14 & NPF-22,respectively,requesting Emergency Temporary Relief from Certain Requirements of Tech Specs 3.2.2 on One Time Basis for Period of 3 Months PLA-3277, Forwards Change DD to Physical Security Plan.Change Withheld (Ref 10CFR73.21)1989-10-11011 October 1989 Forwards Change DD to Physical Security Plan.Change Withheld (Ref 10CFR73.21) ML18040B2581989-10-0202 October 1989 Forwards Final Response to Request for Addl Info Re Generic Ltr 88-01, NRC Position on IGSCC in BWR Austenitic Stainless Steel Piping. Listed Items Included in Previous & Current Ref Responses ML18040A9441989-09-12012 September 1989 Responds to Remaining Questions Raised During NRC Insp of Training Programs.Training Procedure Re Technical Exam Bank Instrumentation & Control Training Exams.Health Physics Technicians Trained Re High Radiation Levels PLA-3251, Forwards Response to Regulatory Effectiveness Review Rept. Util Established Team to Evaluate Appropriate Scope for Planned Major Project to Upgrade Security.Scope of Project to Be Finalized & Approved in Nov 1989.Response Withheld1989-08-31031 August 1989 Forwards Response to Regulatory Effectiveness Review Rept. Util Established Team to Evaluate Appropriate Scope for Planned Major Project to Upgrade Security.Scope of Project to Be Finalized & Approved in Nov 1989.Response Withheld ML18040A9421989-08-22022 August 1989 Requests Concurrence W/Scheduling of 1990 Annual NRC Observed Emergency Preparedness Exercise at Plant on 900502. Concurrence Requested by 890930 ML18040B2531989-08-10010 August 1989 Discusses Insp of Operational Status of Emergency Preparedness Program.Susquehanna Review Committee 1987 & 1988 Emergency Plan Audits Encl W/Other Supporting Documentation ML20246A0191989-06-30030 June 1989 Submits Comments on Containment Performance Improvement Program (Cpi).Believes Program Will Be Generic Approach to Improving Containment Performance During Severe Accident PLA-3218, Submits Info Re Settlement Agreements for Discrimination Matters Arising Under Energy Reorganization Act of 1974. No Settlements Made Between Licensee & Any Employees in Section 210 Proceedings1989-06-27027 June 1989 Submits Info Re Settlement Agreements for Discrimination Matters Arising Under Energy Reorganization Act of 1974. No Settlements Made Between Licensee & Any Employees in Section 210 Proceedings ML18040B2501989-06-20020 June 1989 Forwards Summary Rept of Safety Evaluations Approved During 1988.Changes Include Backseating Control Box to Electrically Backset HV-202168 to Reduce Steam Leakage & Rerouting Condensate Supply Line to Main Condenser Keepfill PLA-3194, Forwards Change CC to Physical Security Plan.Change Withheld (Ref 10CFR73.21)1989-05-30030 May 1989 Forwards Change CC to Physical Security Plan.Change Withheld (Ref 10CFR73.21) ML18040A9301989-04-28028 April 1989 Responds to 890322 Request for Addl Info Re Plant Fire Protection Review Rept.Analysis of Circuits Having Potential for Being Impacted by Fire Resulting in Multiple High Impedence Faults Will Be Completed by Last Quarter 1989 ML18040B2441989-04-14014 April 1989 Forwards Application for Amends to Licenses NPF-14 & NPF-22, Resulting from Mods Performed to Essential Svc Water Sys,Per 10CFR50,App R,Consisting of Proposed Amends 23 & 70 PLA-3173, Forwards Change Bb to Physical Security Plan.Encl Withheld (Ref 10CFR73.21)1989-03-22022 March 1989 Forwards Change Bb to Physical Security Plan.Encl Withheld (Ref 10CFR73.21) ML18040A9271989-03-10010 March 1989 Forwards Rev 6 to ISI-T-100.0 for Unit 1 & Rev 3 to ISI-T-200.0 for Unit 2 Pump & Valve Inservice Insp Testing Program. ML18040A9261989-03-0707 March 1989 Discusses Util Position Re Completion & Implementation of NRC Requested Actions Specified in Suppl 1 to NRC Bulletin 88-007, Power Oscillations in Bwrs. ML17156B0131989-02-0202 February 1989 Forwards Proprietary Rept & Affidavit Supporting Proposed Amend 119 to License NPF-14 ML17156A9771988-12-15015 December 1988 Forwards Rev 11 to Susquehanna Units 1 & 2 Emergency Plan ML18040B2331988-11-22022 November 1988 Forwards Listed Addl Info Re Plant Fire Protection Review rept.W/16 Oversize Drawings ML17156A9211988-11-0909 November 1988 Forwards Proprietary GE Rept, Tech Spec Improvement Analysis for Reactor Protection Sys for Susquehanna Steam Electric Station,Units 1 & 2. Rept Withheld (Ref 10CFR2.790) ML18040A9111988-09-15015 September 1988 Informs That Mods Re Fire Barrier Upgrades,Hvac Fan Switches,Ct Secondaries & Raceway Wrapping Completed Except as Listed ML18040A9101988-08-10010 August 1988 Forwards Application for Amend to License NPF-14,extending Operation During Cycle 4 W/One Circulation Loop Out of Svc. Fee Paid ML18040B2221988-08-10010 August 1988 Responds to Generic Ltr 88-01, NRC Position on IGSCC in BWR Austenitic Stainless Steel Piping. Staff Position on Matls, Water Chemistry,Crack Evaluation & Repair Criteria & Insp Schedules Among Topics Addressed.Flaw Evaluations Encl ML18040B2201988-07-27027 July 1988 Forwards Comments to Each Specific SALP Category,Per 880707 Meeting W/Nrc.Presentations from Meeting Also Encl ML18040A9061988-07-21021 July 1988 Forwards GE Rept, Susquehanna Unit 1 CRD Housing Cap Screw Corrosion. Rept Completes Action on Item ML18040A9041988-07-19019 July 1988 Forwards Rev 39 to Updated FSAR for Susquehanna Steam Electric Station Units 1 & 2 Per 10CFR50.71 ML18040A9031988-07-19019 July 1988 Forwards Approved Version of Topical Rept PL-NF-87-001-A, Qualification of Steady State Core Physics Methods for BWR Design & Analysis, Per 880428 Ltr ML18040B2131988-06-24024 June 1988 Forwards 1987 Annual Rept for Allegheny Electric Cooperative,Inc ML18040A9021988-06-15015 June 1988 Provides Revised Response to NRC 871130 Ltr Re Violations Noted in Insp Repts 50-387/87-19 & 50-388/87-19.Corrective Actions:Incumbent Will Be Removed from Emergency Plan Position of Radiation Protection Coordinator PLA-3028, Responds to Suppl 1 to Bulletin 85-003, Motor-Operated Valve Common Mode Failures During Plant Transients Due to Improper Switch Settings. No Revs to Design Review for Original Bulletin Required as Result of Suppl1988-05-31031 May 1988 Responds to Suppl 1 to Bulletin 85-003, Motor-Operated Valve Common Mode Failures During Plant Transients Due to Improper Switch Settings. No Revs to Design Review for Original Bulletin Required as Result of Suppl ML18040A8691988-04-0606 April 1988 Forwards Application for Proposed Amends 110 & 61 to Licenses NPF-14 & NPF-22,respectively,revising Tech Specs Re Radiation Monitoring Instrumentation.Fee Paid ML18040B2001988-02-19019 February 1988 Forwards Inservice Insp Outage Summary Rept for Unit 1 Third Refueling Outage. 1990-09-01
[Table view] |
Text
REGULATD T INFORMATION DISTRIBUTION O STER (RIDS)
ACCESSION NBR:8105190400 DUC ~ DATE: 81/05/14 NOTARIZED; NO DOCKET FAGIL:50"387 Susquehanna Steam Electric Stationr Unit 1> Pennsylva 0 7 50"388 Susquehanna Steam Electric Stationi Unit 2i Pennsylv 050003 8
.-AUTH'AME AUTHOR Al FILIATION CURT ISi u ~ n ~ Pennsylvania Power II, Light Co ~
REC IP ~ NAME RECIPIENI AFFILIATION YOUNGBLOODiB.J ~ Licensing Branch 1
SUBJECT:
Forwards responses to Structural Engineering Branch questions on masonry walls to close SER Outstanding Issue 13 'ustificat>on for use of average response soectra typical wall fix diagrams also CODE: 8001S COI'IES RECEIVED:LTR TITLE: PSALM/FSAR A>IDTS and Related Correspondence encl'ISTRIBUTION KNCL SIZE:
NOTES:Send ILE 3 copies FSAR L all amends.i cy:BWR"LRG P41(L ~ RIts) 05000387 Send IKE 3 copies FSAR II all amends.i cy:BAR LRG PH(CRIB) 05000388 REC IPIENT COPIES RECIPIENT COPIES IO CODE/NAvE LTTR ENCL ID CODE/NAI:E LTTR ENCL ACT ION ~ A/D LICENSNG 1 0 LIC BR 02 BC 1 0 RUSHBROOK<1~. 1 0 STARKrR ~ 04 1 1 INTERNAL: ACC ID EVAI BR2o 1 1 AUX SYS BR 07 1 1 CHEM ENG BR 08 1 1 CONT SYS BR 09 1 1 CO<K PERF 6R 10 1 EFF, TR SYS BR12 1 1 EHERG PREP 22 1 0 EQUIP QUAL oR13 3 3 GEDSCIENCES 14 1 1 HUH FACT ENG UR 1 1 rIYO/GEO BR le ? ' 18C SYS BR 16 1 1 IaE 06 3 3 LIC GUID BR 1 1 LI C QUAL BR 1 l NATL ENG BR 17 1 1 i4IECH ENG BR 16 1 iHP A 1 0 NRC PDR 02 1 1 OELO 1 0 OP LIC BR 1 1 POWER. SYS BR 19 1 1 PROC/TST REV 20 1 1 QA BR 21 1 1 RA S BR22 1 1 RKAC SYS BR 23 1 1 EG F ILE 01 1 1 SIT ANAL BR 24 1 1 TWUC-T NG BR25 1 1 EXTERNAL: ACHS 21 lo 16 LPDR 03 NSLC 05 1 1 ggy 21 1S81 w'1 +I TOTAL NUMBER OF COPIES REQUIRE,D: LTTR 54 ENCL
PPaL TWO NORTH NINTH STREET, ALLENTOWN, PA. 18101 PHONE: (2 IS) 821.5151 NORMAN W. CURTIS Vice President Engineering & Construction 821-5381 May 14, 1981 ~%Ctt>R routnJ01 ISStort Rip, rp /
/ i Mr. B. J. Youngblood, Chief Docket Nos. 50-387 Licensing Branch No. 1 50-388 U.S. Nuclear Regulatory Commission Washington, DC 20555 SUSQUEHANNA STEAM ELECTRIC STATION SER OUTSTANDING ISSUE 13 ER 100450 FILE 841-2 PLA-760
Dear Mr. Youngblood:
Attached are the responses to the Structural Engineering Branch questions on masonry walls.
These responses complete our action to close SER Outstanding Issue 13.
Very truly yours, N. W. Curtis Vice President-Engineering a Construction-Nuclear CTC/mks Attachment pool 810SXS04O <<~
PENNSYLVANIA POWER & LIGHT COMPANY
SUSCU1XAHNA SES UNIT 1 AND 2 DOGQ 7 NUMBERS 50-387 AND 50-388 CATEGORY I MASONRY WALLS PREAMBLE:
'afety related masonry walls are interior partitions whose primary function is to provide shielding and fire protection. Masonry walls are not used as primary shear walls for seismic resistance of the structure. All category I masonry walls are reinforced with all cells fully grouted. The infillmaterial of double wythe walls is either grout or concrete. The minimum specified canpressive strength for grout, concrete, and mortar is 2500 psi. %rtar infillis not used on SSES nasonry wa11s. Metal ties, between the wythes of double wythe walls, are provided at 24" spacing maximum in horizontal and vertical directions. Seismic design is in accordance with SSES FSAR Section 3.7. Allowable stresses are as noted in CESAR Section 3.8, Table 3.8-8 and Table 3.8-9. Safety related rrasonry walls are Q-listed and have been added to the FSAR Design Criteria Surmary (Table 3.2-1), in response to NRC, Quality Assurance Branch, Question No. 260.l-b (34).
QUESTION NO. 1:
In your response to Question 2, you indicated that Sm is the allcmble stress as specified in UBC. For extreme and/or abnormal loading combinations, you increase the alliable stress by a factor of 1.67, which is in conformance with the practice of SRP Sections 3.8.3 and 3.8.4, for reinforced concrete structures. Havever, concrete masonxy walls are quite different frcm reinforced concrete walls, particularly the unreinforced ones, the use of such a practice nay not result in an adequate design. Depending on the types of stress, that is, tensile, shearing or axial carpressive, the factor may vary from 0 to 2.5 (see enclosure 2). Specify the masonry design strength fm used in Susquehanna masonry walls and the allowable values for all types of stresses.
RESPONSE
Code allavable stresses for masonry tension, shear, ccnpression, a+2 bord are increased by a factor of 1.67 for load mnbinaticns involving abnormal and/or extreme environmental conditions which are credible but highly improbable. Since code alliable stresses are generally associated with a factor of safety of 3, the 1.67 increase provides a factor of safety against failure of 1.8 (3 -. 1.67) (see Table 4 for the increase allcwed for each type of stress). 'Ihere are no unreinforced masonry walls on SSES project. Susquehanna SFS masonry walls are designed based on an ultimate cmpressive strength, f'm, of 1500 psi as specified in UBC 1976, for solid grouted hollow masonry. Minima ccmpressive strength at 28 days for mortar, grout, and concrete is 2500 psi. Materials are in accordance with FSAR Appendix 3.8C.
The allowable stresses are as listed in Table l.
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~ q~>> s~ ~ ~y r ee ~ awemr ',',, ~ s ~ 'I ~ ye 8920 TM3LE l.
SSES MZQMABLE STRESSES Materials and Allowable Stress: UBC 1976 (1)
Stress 1~ HBsonry f'm = 1500 (see note 2)
Compression:
Flexural .33f 'm = 500 Axial .20f'm x (1-(h/40t) ) h = clear height, in.
t = wall thickness, in.
Flexural Shear 1.1 ~f'm = 43 Bond (deformed bars) 140 Bearing .25f'm = 375 Bed Joint tension Normal (See note 3)
Parallel Modulus of elasticity, Em 1000f 'm = 1,500,000 Modulus of rigidity, E 400f 'm = 600,000
- 2. Reinforcement:
Tension:
Grade 40 Steel 20,000 (used for ties, only)
Grade 60 Steel 24,000 Ccapression:
Grade 40 Steel 16,000 (used for ties only)
Grade 60 Steel 24, 000 Notes: (1) For stress increase allowed for abnormal, or extreme environmental load ccmbinations See Table 4.
(2) Ultimate compressive strength as specified in UBC 1976 for solid grouted hollow concrete units Grade N.
(3) Zero tension normal to bed joint is used.
WP26/15-2
QUESTION B3. 2 In the note to your response to Question 2, you stated that the allowable shear or tension between masonry block and concrete or grout infill is considered to be equal to three percent of the canpressive strength of the block. 'The allowable shear or tension as specified by you is in the staff's opinion tco hich. To specify the allcwable shear or tension of the vertical joint between wythes in terms of the ccmpression strength of the block is in the first place unconservative and the use of seemingly 1cw percentage of 3% nay actually result in an allowable shearing stress greater than its corresponding strength. 'Iherefore, a revision of the stress criterion is required.
RESPONSE
The specified shear and tension, for the interface of masonry block and concrete or grout, infill, of three percent of ccmpressive strength, f'm, is based on the relationship 1.1 ~f'm given in ACI-531-79. For f'm = 1500 psi, this relationship yields a value of 43 psi ccmpared to 45 psi (.03 x 1500) allowed for evaluation of project masonry walls. The difference of 2 psi is justified by the fact that the ultimate canpressive strength of masonry f'm, is generally higher than 1500 psi.
The values for. shear and tension as specified above have been used only as a guide in evaluatinq double wythe walls, where infill thickness is greater than 8 inches (24" thick walls and larger).
For walls having an infill thickness of less than 8 inches (total of four walls), zero tension/shear is assumed for evaluation purposes; For SSES masonry wa11s, the actual shear stress, as determined by VQ/Zb for uncracked sections, and in the ccapression zone of cracked sections ranges frcm 5-10 psi; except for three walls. For these three walls shearing stress is in the range of 10-15 psi.
QUOI'ION NO. 3 In your response to Question 4: (1) It is indicated that response spectrum method is used for the dynamic analysis of which of the response spectra is used, ~
the concrete masonry walls. However, there is no mention as to response spectrum or the average of the two.
floor or lower floor It is required that an upper bound envelope of the individual flcor is used. (2) Though the use of ACI 318 forrmla the cracking of concrete masonry wall is considered. The use of such a formula is que'stionable in view of the fact that in a concrete masonxy wall the weakest section is the bed joint and the modulus of rupture is equal to that of neither the concrete block nor the mortar. Indicate hew the rxdulus of rupture is established in ycur ccaputation.
WP26/15-3
RESPONSE ITEM (1):
=-892'esponse spectrum for the lcwer floor has been used for evaluation of cracked/uncracked behavior of masonry walls, as applicable, for vertical motion, and for walls cantilevered fran the flcor. For horizontal motion, the lcwer floor response spectrum has been used in the initial evaluation of cracked/uncracked behavior, as applicable, for walls spanning between two flcors and walls having side connection at concrete walls. These walls have also been re-evaluated based on the average acceleration of the upper and laser floors. Where the upper floor acceleration is less than the 1cwer flcor acceleration, the lower floor acceleration is used. For justification of using average acceleration, see Enclosure 1.
RESPGNSE ITEM (2):
Although ACI-318 formula is derived for cracked concrete sections, the use of the formula for masonry walls takes into consideration the difference in material strengths. 'Ihe difference between nasonry behavior and concrete behavior is recognized and allowances are provided in selection of seismic acceleration within a frequency variation of plus or minus fifteen percent of the natural frequency.
The mx2ulus of rupture (fx) for masonry is approximated by increasing the UBC allowable flexural tensile stress by a factor of safety of 3 and then applying a 33% reduction to arrive at a lcwer bourd value. M.s value is used only for stiffness and frequency calculations of the cracked section and not for strength. Allcwance for uncertainties in the nodulus of rupture is accounted for in the frequency variation of
+ 15% of the natural frequency.
QUESTION NO 4:
In response to Question 5, it is stated that when the design stresses of masonry walls exceed the allowable stresses, fixes are designed such that the criteria is satisfied. Indicate the number of walls where such fixes are needed and provide examples.
RESPONSE
The number of masonry walls requiring fixes for cracked section criteria is 36. Wall location, thickness, and elevation are as shown in Table 2. Typical fixes are shown in details type 1, type 2, type 3, and type 4 (see Enclosure 2).
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TABLE 2
~ SSES MASONRY NMLS WHICH REQUIRED FZKS H)R CRACKED SIXTION CRITERIA WALL BLDG. FZCGR EEZVATION t THICKNESS I NO. OF MALS REF. E4%.
Control 656'-0 8 II C-1301 Control 741'-0 6 II C-1304 Control 741'-0 8" 3 C-1304 Control 753 'W 8ll C-1304 Control 771'-0 8ll 16 C-1304 Control 783'-0 1'W" C-1307 Control 806 '-0 8 II C-1308 Control 806 '-0 1I ~ll C-1308 Reactor 728'-0 8 II C-1202 Reactor 799'-0 8ll C-1205 m26/15-5
38U2H QJESTION M). 5:
Provide justification for any deviation frcm the attached staff 's interim criteria in your desiqn and analysis of the masonry walls.
RESPONSE
Deviations and justification for differences between SSES criteria and SEB interim criteria are as noted in the following paragraphs.
Items which are not specifically addressed are in accordance with the criteria or not applicable to the project.
ITEM NO. 1: General R irments The materials, testing, analysis, design, construction and inspection related to the design and construction of safety-related concrete masonry walls shall conform to the applicable requirements contained in Uniform Building Code 1979, unless specified otherwise, by the provisions in this criteria.
RESPONSE
Uniform Building Cede, 1976 edition, has been used for design and evaluation of Susquehanna masonry walls. A carparison of 1976 and 1979 editions of UBC shows no significant difference in criteria applicable to SSES masonry walls. In addition, ACI-531-79 is used to supplement UBC allowable stresses, and ACI-318 1977 in stiffness ca1culations; ITEM HO. 2: Loads and Load Ccmbinations The loads and load ccmbinations shall include consideration of normal loads, severe environmental load, extrene environmental load, and abnormal loads. Specifically, for operating plants, the load canbinations provided in plant's FSAR shall govern.
For operating license applications, the following load ccmbinations shall apply for definition of load terms, (see SRP Section 3.8.4.11-3).
RESPONSE
For corrparison of SEB interim load combinations and load ccmbinations used for masonry walls evaluation see Table 3. Definition of terms is as shown below.
Notation D = Dead loa4 of- structure plus any other permanent loads contributing stress.
L = Live loads expected to be present when the plant is operating, including aavable eauipnent, piping, cables.
WP26/15-6
P = Design basis accident pressure loads.
R = Steam/water jet forces or reactions resulting fran rupture of process piping.
TQ Therma 1 effects during normal operating conditions including temperature gradient and equipnent and pipe reactions.
Ho = Force on structure due to thermal acpansion of pipes under operating conditions.
Ta Added thermal effects (over and above operating thermal effects) which cccur during a design accident.
Ha Force on structure due to thermal expansion of pipes under accident conditions.
E = Load due to Operating Basis Earthquake.
E' Load due to Design Basis Earthquake.
W = Wind load.
W' Tornado wind load.
Ds = Force on bloc3nall due to story drift under Operating Basis Earthquake Loading.
D's = Force on blockwall due to story drift under Safe Shutdown F~hquake Loading.
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TABLE 3. IOAD COMBINATION COMPARISON IOAD COMBINATION
- l. D+L 1. D+L
- 2. D+L+ E 2. D+L+E+Ds Service 3. D+ L+W 3. Not Applicable INo wind pressure(
load Condition la. D + L + To + Ro la. D + L + To + Ho 2a. D + L + To + Ro + E 2a. D + L + To + H + E 3a. D+L+To+Q+W 3a. Not Applicable )No wind pressure(
Fxtreme 4. D + L + To + Ro + E'.
- 4. D + L + To + H + E' D's envi-'onmental D + L + To + Ro + Wt D + L + To + Ho + W ISee note 2 I
atxmrmal 6e D + L + Ta + Ra + le5 Pa 6e D + L + (To + Ta) + R + ISee note 1 1.25 Pa + Ha abnormal/severe I 7. D + L + Ta + 1.25 Pa + 1.0 7e D + L + (To + Ta) + le25 Pa + R +
environmental (Yr + Yj + Ym) + le25E + Ra 1.25 E + Ds a?normal/ 8e D + L + Ta + Ra + leO P + 8e D + L + (To + Ta) + R + leO P +
extreme leO (Yr + Yj + Ym) + leOE 1.0 E' D',
environmental conditions Notes: (1) Abnormal load canbination in SSES-FSAR Table 3.8-9. Part C will be revised to read D + L + (To + Ta) + R + 1.5 Pa + Ho. All other load ccmbinations will remain unchanged.
(2) W'oes not include W, tornado missile. bhsonry walls are not used for protection of safety related equipnent against tornado missiles.
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ITEM K). 3: Allowable Stresses Allowable stresses p";ovided in chapter 24 of UBC-79, as supplenented by the follcwing rradifications/exceptions shall apply.
(a) When wind or seismic loads (OBE) are considered in the loading ccrnbinations, no increase in the allowable stresses are permitted.
RESPONSE
Design and evaluation of masonry walls is based on a 33% increase in the allowable stress. This increase is permissible per UBC, 1979 and per ACI-531-79. The factor is also ccrrpatible with the 25% increase in stress noted in SSES FSAR for Working Stress Design Method.
ITFÃ NO. 3: (b) Use of allowable stresses corresponding to special inspection category shall be substantiated by derrenstration of ccrnpliance with the inspection requirements of the NRC criteria.
RESPONSE
Stresses corresponding to special inspection have been used in the design and evaluation of SSES masonry walls. Inspection required to assure that masonry construction is in accordance with Appendix "D" and amendments to the PSAR, and to assure that. materials are in accordance with FSAR Appendix 3.8C, is implemented. Documentation of this inspection is in project jobsite files.
arm NO. 3: (c) For load conditions, which represent extreme envirornnental, abrnrmal, abnormal/severe enviroanental, and abnoxmal/
extreme environmental conditions the allowable working stresses may be multiplied by the factors shcwn in the following table: (See table 4).
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TABLE 4.
I,'AY -4 'c I,' 8 (J P [~
STRESS ZNCRFJSE FACIOR COMPARISON
'ACIOR FACTOR JUSTZFZCATZON/COMME%I'xial or flexural conpression 2.5 1.67 See Response Question gl Bearing 2.5 1.67 Reinforcement stress except shear 2.0 l. 67 See note 1 Shear Reinforcement 1.5 1.5 Anchor bolts are not usedl and/or bolts in safety related masonryl walls I
I Masonry tension Parallel to bed joint 1.5 1.5 Shear carried by masonry 1.0 1.67 See note 2 Masonry tension perpendicular to bed joint For reinforced masonry 0 0 For unreinforced masonxy 1.0 N/A No unreinforced I masonry walls I
(1) Shall not exceed .90 fy (2) The actual shear stress carried by masonry is within the allowable shear stress given in UBC Table 24-H with no increase factor applied.
RESPONSE
See table above.
NP26/15-10 QUESTION HO. 5: Design and Analysis Considerations ITEM In new construction, no unreinforced masonry wall is permitted, also all grcut in concrete masonry walls shall be conpacted by vibration.
RES KNSE
- a. 'Ihere are no unreinforced masonry walls in SSES project.
- b. Cell grout and/or infill grout or concrete is ccmpacted by either mechanical vibrators or by redding.
ITEM 4z Special constructions (e.g., multiwythe, carposite) or other items not covered by the cede shall be reviewed on a case by case basis for their acceptance.
RESPCNSE:
Double wythe walls are designed as carposite sections, except as noted in response to Question No. 2. Allowable stresses are per ACI-531-79.
~ETEM 4 Licensees or applicants for staff's review.
shall submit QK/QC information, if available,
RESPONSE
Applicable QA/QC information is available at SSES jobsite and will be submitted upon request.
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ENCLCSURE 1.
JUSI'IFICATHX'T FOR'HE USE OF AVERAGE RESPONSE SPECTRA (13 PAGES)
WP26/23-1
JUSTIFICATION OF USING APPROXIMATION METHOD TO DETERMINE MAXIMUM WALL PANEL RESPONSES TO SEISMIC MOTION The evaluations herein demonstrate that: (l) The use of the average floor acceleration response spectra to calculate the response of the wall panel is appropriate, and (2) The use of uniform inertia load with magnitude equal to the average spectral acceleration for the fundamental mode, in calculating the maximum seismic responses is a good approximation, even considering the higher mode ef feet.
For the purposes of this evaluation, the seismic response of a simply-supported, uniform beam simulating a strip of the wall panel with unit width is considered, as shown in Figure l.
(1) Use of Avera e,S ectra The equation of motion of an undamped, simply-supported beam can be written in terms of the total displacement with respect to some fixed reference axis as:
m 3
St u + EI 34u ax4
=0 Where m and EI are the mass density and flexural rigidity of the beam. Denote the seismic excitations at the ends of the 1
EC-9
the beam as Ua and Ub. Then the total displacement u(x,t) can be expressed in terms of the two seismic motions and the relative displacement to the seismic motions as:
u(xg t) = (x/L) Ub + ( 1 -x/L) Ua + r(xg t) (2)
Where L is the length of the beam. The relation expressed above equation is shown in Figure 2. The relative dis-by'he placement r(x,t) needs to satisfy the following simply-supported conditions:
r(o,t) = r(L,t) = 0 a rl a rI 0 (4) ax Ix=o ax I x=L Substitute Equation 2 into Equation 1, the equation of motion in terms of relative displacement r(x,t) can be expressed as:
~~
2 ma r + EI a r m(x/L) Ub
~~
m(1 x/L) Ua at2 ax4 EC-9
The eigen-function solutions for the homogeneous equation associated with Equation 5 that satisfy the boundary condi-tions specified by Equations 3 and 4 are:
sin L
i n = l, 2, 3, and the corresponding frequencies of vibration are:
n= 1, 2, 3, n mL (6)
So, the solution of Equation 5 can be expressed as:
r(x,t) ='( a(t) sin n=l L Substitute Equation 7 into Equation 5, and multiply the latter by sin nmx, and then integrate L
it with respect to x over the full length of the beam, the equation of motion can be transformed into modal equations of motion as:
EC-9
HN-<'Gl '8 J2[)
~0 2 ~~ ~o n+ nan =r n Ua+U n = 1, 3, 5 2
(Sa) and
~0 2 I ~ 0 ~0 an + Q nan I' Ua Ub) n = 2, 4, 6,
"~ ~
i (Sb) where 1'n = participation factor (9) lf damping in the form of modal damping ratio is included, Equations Sa and Sb becomes:
~0 2 ~~ ~~
an + 2I-n"nan + > 'nan = n Ua + U 2
(10a) and
~y 2 %0 ~0 an + 2<n>n n + > n n = Fn Ua U n = 2,4,6,...
2 (lob)
Where gn is the damping ratio of the nth mode.
EC-9
Equation 10a means that the odd-number modes which are sym-metrical about the mid-span of the beam*will be excited by the average of the two seismic excitations; while equation 10b means that the even-number modes which are antisymmetrical about the mid-span of the beam will be excited by half of the difference between the two seismic excitations.
Expressing the maximum modal displacement response in equa-tions 10a aqd 10b in terms of absolute acceleration response spectra gives:
ap ng n) + b~~ n, n~1 n + n C
4mL4 a(< n,"n) + b(~ n,"n) n5,5EZ n = 1,2,3,...
This illustrates that the use of the average of two floor accelera-tion response spectra to calculate the modal response of a wall panel is appropriate.
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- g -a'al .'802(1 (2) Contribution of Higher Modes From Equation ll, the relative importance of modes can be evaluated by examining the frequency ratios, modal partici-pation ratios, and maximum modal response ratios for constant acceleration which can be shown as
(d,1 lO 2
. hl 3
~
~ ~ ~ ~ 1 i 4 ~ 9 ~ ~ ~ ~ (12) r .r .r
~
2 ~
3
~ ~ 1 : -1/2 : 1/3 : . . . (13) td 1: 2: "3:
2 1 0) 2 2 0) 2
. ~ . = 1 32 1: 243 1:... (14)
For an SRSS method of combining maximum response, the contr'i-bution of higher modes is clearly negligible.
If for example, the fundamental frequency "1 is above 8 Hz, the second frequency is above 32 Hz which is already in the rigid range, i.e., in the range of no amplification. Thus the Sa and Sb values associated with modes other than the fundamental will be the Zero-Period-Acceleration (ZPA) values of the two seismic motions Ua and Ub. Using the absolute sum (ABS) method of combining the modal maximum responses., the con-tribution of higher modes is not more than 4% of the fundamental mode.
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~ ~
~
'he relative importance of modes can also be evaluated by examining the moment and shear responses in the beam for each mode, as shown in the following.
The moment in the beam due to the nt mode can be evaluated by:
M (X) an sin L
('15 )
I
,( 4mL a(<n "n) b (<n,"n) sin nmX n
n = 1,2,3,...
The moment at the mid-span of the beam is contributed only by the symetrical modes and can be expressed as follows-a(<n,"n) + (<n,"n) b (16)
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yg -g 'u(,'892 H For a constant spectral acceleration, the contibution to the mid-span moment of the beam from each mode can be expressed in the following ratio:
H (k) 52~ 27 125 Using the SRSS Method of combining modal responses, the con-tribution of the higher modes to the mid-span moment is less than 1% of that from the fundamental modes. Using the ABS method of combining modal responses, the contribution of higher modes is less than about 5%.
The shear force in the beam due to the n mode can be eval-uated as-'3 0 (X) = EI n >X3 a
n sin nsX L
C 4mL a(<n ~n) + b (~n,"n) cos ( nmX n Tt q L n = 1,2,3,4,...
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The maximum shear occurs at the support of the beam and can be expressed as: I 1
a(<n,"n + (<n,"n)
(4mL b (19) n n2 2 n = 1,2,3,4,...
The contribution of the higher modes to the maximum shear at the beam support relative to that of the fundamental mode can be evaluated by comparing the modal effective masses (MEM) associated with the fundamental mode and the higher modes. The modal effective mass of the fundamental mode is MEM 0.81 mL (20a) 1 .2 The modal effective mass associated with modes higher than the fundamental mode can be calculated as MEM1 = (1 0.81)mL = 0.19 mL (20b)
T The ratio of C
MEM1 TO MEM1 is 0.19/0.81 = 23't. That is the contribution of higher modes to the maximum shear is at most 23% of the contribution due to the fundamental mode. This ratio does not take-inte-account the ratio of the spectral EC-9
~ ~
~
~
n 4 oi gg JP()
acceleration for the fundamental mode to the ZPA value for the higher modes. When the difference in spectral accelera-tions is accounted for, the contribution of higher modes to the maximum shear would be less than 23%. For example,, if the spectral acceleration for the fundamental mode is 1.5 ZPA, then the ratio of higher mode contribution would be 0.19/(0.81 x 1.5) = 16%.
(3) Uniform Inertia Load Approximation Using the modal responses, the maximum moment and shear of the beam can be calculated. This moment and shear can then be compared to the moment and shear based on a uniform inertia load using the average of the two floor spectral accelerations.
at the fundamental mode of the beam.
The maximum moment occured at the mid-span of the beam induced by a uniform load with the following magnitude:
f(X) = m a (<1'~1) + b (<1'~l) (21) can be expressed as:
M*
L mL 2 Sa (~1'"1) + b (~1'1) (22) 2 8
~4
.4 C
From Equation 16, the moment at the mid-span of the beam due to the fundamental mode is:
(Ill+]) + Sb (0] i+1') (23)
The maximum difference between the moments from Equations 22 and 23 is about 3%.
The maximum shear occurred at the support of the beam induced by the uniform load expressed in Equation 21, can be written as:
Q*(0) mL a (<1'"1) + b (<1'"1) (24) 2 From Equation 19, the shear at the support of the beam due to the f undamental mode is:
Sa (<1 "1) + Sb (<1 "1 (25)
Q (O) (4mL 1 2 EC-9 g1
The shear from'qua tion 24 is greater than the shear from Equation 25 by about 25%. This margin can well cover the contribution to the shear due to the higher mode ef feet, as discussed previously.
From the above comparison, it can be concluded that the use of a uniform inertia load with the magnitude of the averaged floor spectral acceleration at the fundamental mode, provides a good approximation for calculating the seismic response in the wall panel .
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